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NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

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Page 1: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10
Page 2: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10
Page 3: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

NUCLEAR TRAINING LICENSED OPERATOR TRAINING PROGRAM

INTRODUCTION TO EMERGENCY OPERATING PROCEDURES AND

STANDARD POST TRIP ACTIONS EOP-00

INSTRUCTOR HANDBOOK LESSON PLAN: 7-18-10

REVISION: 12 DATE: 10/09/10

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IHB: 07-18-10 Revision: 12

1

REFERENCES

• EOP-00, Standard Post Trip Actions

• CEN-152, CEOG Emergency Procedure Guidelines, Revision 3

• The Critical Safety Functions and Plant Operation, CE System Engineering, Walter M. Guinn

• CE NPSD-259, CEOG Emergency Procedure Training Materials Vol. 1-3

• Post-TMI Reactor Operation Training Materials Vol. 1-7

• SOER 83-8, "Reactor Trip Breaker Failures"

• EOP and AOP User's Guide

• Memo FC-0754-91, Operator Training Regarding Crew Positioning Standard During Normal and Emergency Plant Conditions

• Conduct of Operations, FCS Standing Order, SO-O-1

• Technical Basis Document TBD-EOP-00

• SOER 81-15/PED-SYE-92-0544/EAR-91-50

• INPO SER 21-92, Main Turbine Protection System Problems

• INPO SER 4-93, Reactor Coolant Pressure Transients Caused by Failed Open Pressurizer Spray Valves

• MEMO FC-OPS-0045-93

• OPD-4-11, Policy For When And By What Authority It Is Appropriate To Bypass Engineered Safeguards

• SER 22-93, Inappropriate Disabling of Automatic Actuation Functions for Safety-related Components

• PED-FC-93-3016

• PS 3053 Highlights of the NRC Daily Plant Status Report: 06-APR-94, PS 3055 Highlights of the NRC Daily Plant Status Report: 08-APR-94

• NRC Bulletin 96-01, Control Rod Insertion Problems

• Condition Report No. 200403953

• Technical Specification Amendment 242, Loss of Main Feedwater Event Analysis

• Technical Specification Amendment 263, Steam Generator Blowdown Isolation Requirements

• TDB-VIII

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INSTRUCTIONAL MATERIALS

• Classroom

- Lesson Plan

- Current copy of EOP-00

- Current copy of TBD-EOP-00

- Dry erase marker

- White board

- Overhead projector

• Simulator

- JPM-0008 ASP (Emergency Boration from the Control Room after a Reactor Trip with

> 1 Control Rod Stuck Out)

• Plant

- N/A

Contact Hours

Classroom 3.5

hours

Simulator .5

hours

Plant 0

hours

INSTRUCTIONAL METHODS

Illustrated lecture Discussion

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IHB: 07-18-10 Revision: 12

OUTLINE OF INSTRUCTION COMMENTS

3

I. INTRODUCTION

A. Establish Learning Readiness

1. The EOPs are important documents controlling plant operation during emergency events resulting in a reactor trip.

Relate importance of topic to job. Instructor is encouraged to provide examples from personal experiences to gain student interest.

B. Learning Objectives State objectives.

At the completion of this lesson, the student should be able to:

1.0 DEMONSTRATE general knowledge about the structure, terminology and usage of the Emergency Operation Procedures (EOP's).

Transparency 1.1 & 1.1a SHB pages 2-4

1.1 DEFINE the term Critical Safety Function (CSF).

NOTE

1.2 LIST the four (4) classes of Critical Safety Functions.

: An asterisk (*) indicates a requal objective.

1.3 LIST the five (5) elements of the anti-core melt critical safety function and the three (3) elements of the Containment Integrity Critical Safety Function in priority order.

1.4 EXPLAIN the meaning of the phrase "Success Paths for Safety Functions" as it relates to the EOP's.

1.5 GIVEN a set of plant conditions and a copy of the EOP Resource Assessment Trees, DETERMINE the correct success path for any of the following safety functions:

1.5a Reactivity Control

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OUTLINE OF INSTRUCTION COMMENTS

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I. B. 1.0 1.5

1.5b Maintenance of Vital Auxiliaries (MVA)

1.5c RCS Inventory

1.5d RCS Pressure Control

1.5e RCS and Core Heat Removal

1.5f Containment Isolation

1.5g Containment Temperature and Pressure Control

1.5h Containment Hydrogen Control

1.6 GIVEN a set of plant conditions, DETERMINE if the Standard Post Trip Actions (SPTA's), the Optimal Recovery Guidelines (ORG's) or the Functional Recovery Guideline (FGR) should be used.

1.7 EXPLAIN the organization of the Standard Post Trip Actions, Optimal Recovery Guidelines, Functional Recovery Guideline, Safety Function Status Checks, Resource Assessment Trees and Floating Steps. As a minimum, the explanation will include a discussion of the hierarchy between these items and a discussion of how each procedure is used relative to one another (parallel of series completion sequence).

1.8 GIVEN a copy of the latest revision of the Technical Basis Documents (TBDs), IDENTIFY the basis for specific steps of the Emergency Operating Procedures in use during various accident events.

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OUTLINE OF INSTRUCTION COMMENTS

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I. B. 1.0

1.9 EXPLAIN the format and use of the EOP's. As a minimum, the explanation will include a discussion of the following aspects of the EOP's:

1.9a The types of information found in each column of the two column format.

1.9b Actions to be taken if:

(1) The step in the left hand column is satisfied.

(2) The step in the left hand column cannot be satisfied.

(3) The step in the right hand column is satisfied.

(4) The step in the right hand column cannot be satisfied.

1.9c Actions to be taken if unsure of the proper actions.

1.10 LIST the immediate actions of EOP-00 in the order they are required to be performed.

*1.11 GIVEN a set of plant conditions and a copy of EOP-00, DETERMINE the appropriate response to the plant conditions. Both the corrective actions required and any other EOP's referred to by the procedure must be included.

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I. B. 1.0

*1.12 GIVEN a set of plant conditions and a copy of the diagnostic action flow charts in EOP-00, DETERMINE if an Optimal Recovery Guideline (ORG) should be implemented, and if an ORG is required, which ORG.

*1.13 GIVEN a set of plant conditions and the SPTA checklists, DETERMINE if the safety function meets the acceptance criteria listed.

*1.14 GIVEN a set of plant conditions and a set of EOP floating steps, DETERMINE if the instructions specified in the floating steps can be performed. If an instruction can not be performed, indicate the appropriate contingency action(s).

*1.15 LIST the required operator actions during an Anticipated Transient Without a Scram Condition (ATWS).

Satisfactory performance of knowledge-based objectives will be measured by the achievement of a test score of no less than 80 percent on a written examination containing objective-based questions.

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OUTLINE OF INSTRUCTION COMMENTS

7

II. PRESENTATION

A. Introduction to EOPs

1. Explanation of terms and concepts EO 1.1

a. Critical Safety Functions

(1) Any condition or action needed to prevent core damage or to minimize radiation releases to the general public.

(2) The plant's vital signs

(3) Consists of four major classes

(a) Anti-core melt

Transparency 1.2 SHB page 5 EO 1.2

(b) Containment Integrity

(c) Indirect radioactive release (not covered by EOPs)

(d) Maintenance of vital auxiliaries, i.e, items needed to maintain the other functions.

(4) Anti core melt is made up of:

(a) Reactivity control

Transparency 1.3 SHB page 6 EO 1.3

(b) RCS inventory control

(c) RCS pressure control

(d) Core heat removal

(e) RCS heat removal

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II. A. 1. a.

(5) Containment integrity consists of:

EO 1.3

(a) Containment isolation

(b) Containment temperature and pressure control

(c) Containment H2 control

(6) Maintenance of vital auxiliaries

(a) No supporting functions

(7) Safety function hierarchy

(a) Based on importance and plant response time

Transparency 1.4 SHB page 7

(b) Reactivity control first

• Most important

• The fastest reacting

(c) Containment H2 control last

(d) Maintenance of vital auxiliaries of significant importance - required support for other functions.

(8) Success paths for Safety Function

(a) Definition - actions necessary to satisfy a particular safety function

Transparency 1.5 SHB page 8 EO 1.5

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OUTLINE OF INSTRUCTION COMMENTS

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II. A. 1. a. (8)

(b) Reactivity control (only one necessary)

• CEAs

• Borate CVCS

• Borate HPSI or LPSI

• Drive CEAs in

(c) Maintenance of vital auxiliaries (all necessary)

• Vital 4160 bus available

• 125 VDC bus available

• Instrument Air Available

• RW/CCW or RW available

(d) RCS Inventory (only one necessary)

• CVCS

• SI

(e) RCS Pressure Control (only one necessary)

• Pzr heaters and spray

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II. A. 1. a. (8) (e)

• CVCS charging system

• SI System

• RCP and S/G

• Nat'l Circ and S/G

• PORV

(f) RCS and Core Heat Removal

• RCP no SI

• Nat'l Circ. no SI

• S/G with SI

• Once-through cooling

• Shutdown Cooling System

(g) Containment Isolation

• Remote manual isolation

• Local manual isolation

(h) Containment Temperature and Pressure Control

• Containment Air Coolers

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OUTLINE OF INSTRUCTION COMMENTS

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II. A. 1. a. (8) (h)

• Containment spray

(i) Containment H2 Control

• Containment H2 Purge

b. Emergency Procedure Guidelines (EPG) EO 1.2

(1) The full set of Emergency Procedures is based on maintaining the Safety Functions.

(2) Includes:

(a) Standard Post Trip Actions (SPTAs)

(b) Optimal Recovery Guidelines (ORGs)

(c) Functional Recovery Guidelines (FRGs)

c. SPTAs (EOP-00) EOs 1.6 and 1.7

(1) Entry point into the EOP system

(2) Checks all Safety Functions against acceptance criteria.

NOTE

(3) Provides contingency actions

: Discuss crew positioning during Emergency Operations - refer to Additional Materials Section

(4) Contains ALL the IMMEDIATE ACTIONS STEPS for the EOP system

d. Optimal Recovery Guidelines (ORG)

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II. A. 1. d.

(1) Written for treatment of specific events as contrasted to treatment of a set of symptoms:

EOs 1.6 and 1.7

(a) Reactor Trip Recovery (EOP-01)

(b) LOOP-LOFC (EOP-02)

(c) LOCA (EOP-03)

(d) STGR (EOP-04)

(e) UHE (EOP-05)

(f) LOAFW (EOP-06)

(g) SBO (EOP-07)

(2) Safety Function corrective actions arranged in order most appropriate for the specific event.

e. Functional Recovery Guidelines (FRG) EOs 1.6 and 1.7

(1) Written for multiple, unknown failures or conditions where no specific procedure exists

(2) Functional Recovery Procedure is EOP-20

(3) Safety Function corrective actions in order of predetermined priority.

f. Safety Function Status Checks (SFSC) Transparency 1.7 SHB page 10 EO 1.7

(1) Attachment to each EOP

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II. A. 1. f.

(2) Specific to its associated EOP, i.e. acceptance criteria for expected conditions for event in progress

(3) Provides of ongoing verification of the status of the safety functions

(4) Provides a second check that correct ORG is being used, i.e. acceptance criteria will fail if not in correct ORG

(5) Performed by the Shift Technical Advisor independent of the operator.

g. Resource Assessment Trees

(1) Pictorial representation of system/components available to satisfy Safety Functions

Transparency 1.8 SHB page 11 EO 1.7

(2) Parallels procedure section of FRG

(3) Arranged left to right in order of desirability except MVA

(a) Success path for most degraded condition is to the right

(b) MVA is an exception

• All systems listed are required

Page 17: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

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II. A. 1. g. (3) (b)

• All success paths must be satisfied to go on

2. EOP Structure

a. SPTA Structure

(1) Purpose

NOTE

(2) Entry Conditions

: EOP-00 also contains Primary Operator and Secondary Operator memory aids.

These memory aids are included to help ensure

(3) Placekeeping Index complete instruction and Contingency Action

(4) Precautions completion. Transparency 1.9 SHB page 12 EO 1.7

(5) Instructions/Contingency Actions

(6) Diagnostic Actions Transparencies 1.10a-d SHB page 13-16

(7) Safety Function Status Check

b. ORG Structure

(1) Purpose

(2) Entry conditions

(3) Placekeeping Index Transparency 1.11 SHB page 17 EO 1.7

(4) Precautions

(5) Instructions/Contingency Actions

(6) Exit Conditions

(7) Safety Function Status Checks

(8) Floating Step Monitoring

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OUTLINE OF INSTRUCTION COMMENTS

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II. A. 2.

c. FRG Structure

(1) Purpose

Transparency 1.12 SHB page 18 EO 1.7

(2) Entry conditions

(3) Placekeeping Index

(4) Precautions

(5) Instructions/Contingency Actions

(6) Safety Function Status Checks

(7) Resource Assessment Trees

(8) Reactivity Control

(9) Maintenance of Vital Aux - AC

(10) Maintenance of Vital Aux -DC

(11) Maintenance of Vital Aux - IA

(12) Maintenance of Vital Aux - CC

(13) RCS Inventory Control

(14) RCS Pressure Control

(15) RCS and Core Heat Removal

(16) Containment Integrity

(17) Long-Term Actions

(18) Floating Step Monitoring

B. EOP Bases

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II. B.

1. The EOPs were developed from the CE Owners Group Emergency Procedure Guidelines known as CEN-152.

a. CEN-152 is a generic guideline which describes a function based event mitigation strategy for all Combustion Engineering Plants.

NOTE

b. A copy of CEN-152 is available in the Training Department Resource Center.

: The instructor should bring a copy of CEN-152 to the classroom to show the candidates.

2. NRC Regulations require that documents exist which justify EOP deviations from the Emergency Procedure Guidelines (EPGs). The NUREG also specifies that Plant Specific Technical Guidelines (PSTGs) exist which provide bases for the steps not already stated in the EPGs.

a. At FCS, the "Deviation Documents" and PSTGs coexist as a single set of documents known as Technical Basis Documents (TBDs).

b. Technical Basis Documents are FCS specific and provide a basis for each step in a given EOP. If there is a deviation from CEN-152, the deviation is stated, and a justification is made as to the reason for the deviation.

NOTE

EO 1.8

: The candidate should read the TBD-EOP-INTRODUCTION, and should look at how the various sections of an EOP are handled by the TBD.

C. General Procedure Usage

1. Two column format

Refer to SO-O-1 and Users Guide (OPD-4-09) as necessary to support methodology.

a. Instructions in left column

b. Contingency Actions in right column

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II. C. 1. b.

(1) Verbatim Compliance desired but not required per SO-01, Conduct of Operations

(2) Instructions should

be followed in order if possible

NOTE

(a) When sufficient progress has been made on a given step to ensure completion, to go to the next step

: Refer to OPD-4-11, Policy For When And By What Authority It Is Appropriate To Bypass Engineered Safeguards, in Additional Materials Section of this lesson plan. While this policy specifically addresses bypassing safe-guards, the guidance is applicable to any procedural deviation.

• Example - EOP-03, Step 29, Verify

(b) If step cannot be completed, (or conditions not met) GO TO Contingency Actions.

that the Containment Sump level rises as the SIRWT level lowers

(c) If a contingency actions cannot be completed (or condition not met) guidance is generally provided.

NOTE: Review INPO SER 22-93, Inappropriate Disabling of Automatic Actuation Functions for Safety-related Components, in Operating Experience Section. NOTE

(d) If you are unsure or confused go to EOP-20

: Refer to PED-FC-93-3016, System Response to Loss of Coolant and Loss of Offsite Power IEN 93-17 in Addit. Materials Section. "Matching Flags" is not specifically called for in the EOPs and in some instances could place the emergency diesel loading outside designed basis.

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II. C.

2. Safety Function Status Checks (SFSCs)

a. Completed by STA

(1) Data logged every 10 minutes

b. Six (6) blanks provided

c. Asterisk (*) items require data readings

d. Non-asterisk items are checked () if the Safety Function is satisfied, unsatisfactory is left blank.

e. If criteria not met:

(1) EOP-00 – Notify the CRS/SM.

(2) EOP-01 - Go to Diagnostic Actions in EOP-00 to evaluate need to implement ORG/FRG.

(3) All other ORGs - Evaluate need to implement EOP-20.

3. Floating Steps Transparency 1.13, 1.13a SHB page 19, 20

a. Section 8 of all EOPs except EOP-00 contains the Floating Step Monitoring list.

b. A separate book, EOP/AOP Floating Steps, contains steps that may need to be performed at varying times.

c. Sets of steps are specific for each EOP, greatest number of steps associated with EOP-20

d. STA considers need to perform a Floating Step during CSF status check

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II. C. 3.

e. Entire crew needs to be familiar with content of Floating Steps to assure that they are implemented when needed

4. Attachments

a. Additional material applicable to all EOPs

b. Contained in separate book to aid in implementation

c. Attachments contain directional steps, figures and tables

d. Procedure will direct use of attachment

D. Specific Procedure Usage

1. EOP-00, Standard Post Trip Actions

a. Entry to EOP-00 is IAW Standing Order SO-O-1, Conduct of Operations, Section 12.4

b. EOP-00 is implemented first, in its entirety prior to entering any other EOP

c. EOP-00 is how the Critical Safety Functions are first evaluated after an event occurs

d. Section 15 of the Abnormal Operating Procedure and Emergency Operating Procedure User's Guide directs sequence of performance of Instruction/ Contingency and when performance must be halted

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II. D. 1.

e. Diagnostic Chart used upon completion of instruction/contingency steps to potentially classify event and/or determine the next applicable procedure

2. Use of ORGs, EOP-01 to EOP-07

a. Entry directed from EOP-00

b. EOP use determined by diagnostic chart of EOP-00

3. Use of FRG, EOP-20

a. Entry may be directed from EOP-00 to EOP-07

b. Entry may be required if SFSC acceptance criteria not being met

c. Entry may be required if multiple events in progress

d. Entry may be required if procedures do not cover the plant condition

E. Standard Post Trip Actions, EOP-00

1. Purpose

a. Entry point for entire EOP system

b. Provides consistent evaluation of CSFs and immediate actions which can quickly improve CSFs that are in jeopardy

EOs 1.9, 1.10, 1.14 and 1.15 NOTE

c. Provides diagnostic actions to direct the operator to the correct ORG or the FRG

: Use current revision of EOP-00 and TBD-EOP-00 to review the following sections

d. Structured based on CSFs

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II. E.

2. Entry conditions - Any symptom of a reactor trip

a. "REACTOR TRIP" Alarm (CB-4; A20)

b. Indication that CEAs are inserted

c. Rapid lowering in Reactor Power

d. RPS trip setpoint exceeded

e. CEDM Clutch Power Supply Breakers open

3. Placekeeping Index

a. Provided to allow easy "check off" of completed steps

b. Can be removed from book and used as a tracking device

4. Precautions page NOTE

a. Contains cautions that apply throughout the procedure, or that apply to the first step of the procedure

: Use current revision of EOP-00.

b. Contains notes applicable throughout the procedure

c. Contains procedure expectations applicable throughout the procedure

5. Instruction/Contingency Actions

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II. E. 5.

a. Step 1 - Steps taken to ensure that the reactivity control safety function is satisfied, thus meeting core design criterion that the reactor remain shutdown even with the most reactive rod stuck full out

NOTE

b. Step 2 - Step will stop steam flow to the turbine and prevent decreasing RCS temperature below its no load value.

: Reference PS 3053 and NRC Bulletin 96-01 in the Operating Experience Section.

NOTE

c. Step 3 - Step will prevent motorizing the main generator and overheating the field windings.

: Reference INPO SER 21-92 in Operating Experience Section.

(1) Contingency provided for local tripping of field breaker

d. Steps 4 through 9 - Steps ensure the diesel generators are running if SIAS has occurred, addresses the status of vital auxiliaries: MVA-AC, MVA-DC, MVA-IA and MVA-CC.

(1) Contingency provided for MVA-AC (minimize DC loads)

(2) Contingency provided for MVA-IA

(3) Contingency provided for MVA-CC

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II. E. 5.

e. Step 10 - Steps taken to verify RCS Inventory Control Safety Function

(1) Contingency addresses manual control of CVCS

(2) Contingency addresses stopping and throttling of HPSI flow for cases where PZR level is rising too high because of an SIAS actuation and restoration of HPSI flow when required.

NOTE

Refer to FC-OPS-0045-93, "Use of Safety Injection Stop/Throttle in EOPs", in Operating Experience Section of this lesson plan.

: Refer to Caution prior to Step 10: Development of Natural Circulation May Jeopardize HPSI Stop and Throttle Criteria.

(3) Primary purpose of ensuring RCS inventory is to support heat removal

f. Step 11 - Steps taken to verify RCS Pressure Control Safety Function

TBD-EOP-00: RCS inventory control is designed to maintain an adequate amount of subcooled fluid in the RCS to remove decay heat.

(1) Contingency address closing a block valve for PORV open when < 2300 psia

NOTE

(2) Contingency address tripping 1 RCP in each loop if < 1350 psia

: Refer to SER 4-93, Reactor Coolant Pressure Transients, located in the Operating Experience Section.

(3) Contingency address ensuring proper SIAS conditions if < 1600 pisa

TBD-EOP-00: RCS pressure control relates to the maintenance of subcooled fluid in the RCS in order to adequately remove decay heat.

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24

II. E. 5. f.

(4) Contingency address manual control of heaters and spray

(5) Contingency's purpose is to ensure adequate RCS pressure to support heat removal

g. Steps 12-14 - Steps to verify Heat Removal Safety Function

(1) Contingency address adequate RCP NPSH

TBD-EOP-00: A generic strategy for RCP operations has been developed which results in tripping an RCP in each loop following an SIAS if RCS pressure decreases to < 1350 psia. The remaining RCPs are tripped if NPSH requirements cannot be maintained. NOTE

(2) Contingency list proper indications for development of Natural Circulation

: Discuss TS Amendment 263 for Blowdown automatic isolation following Rx Trip.

(3) Instructions/Contingency to ensure adequate feedwater and S/G level to support heat removal

(4) Instructions/Contingency to ensure adequate steaming path

Blowdown is isolated from both S/G’s automatically on reactor trip. This results in lower decay heat load when AFAS is initiated, enabling it to perform its design function. This strategy gives the operator maximum flexibility in plant control since a normal plant cooldown can be performed while still ensuring a conservative approach to event recovery.

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25

II. E. 5. g.

(5) Contingencies to address excessive heat removal from RCS

(6) Contingency directs stopping one (1) RCP for Tc < 500ºF

NOTE

(7) Steps purpose is to evaluate the condition of heat removal from the core

: Refer to SOER 81-15 and EAR 91-50 (Operating Experience Section) for RCP Trip Scheme Recommendations.

h. Step 15 - Steps to verify Containment Integrity Safety Function

TBD-EOP-00: Core heat removal pertains to the circulation of cooling fluid through the core to remove decay heat. RCS heat removal is split into two steps to accommodate a significant amount of plant-specific detail regarding manual control of feedwater flow restoration and maintenance, and the control of RCS temperature and steam generator pressure via the diverse steaming paths.

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26

II. E. 5. h.

(1) Instructions/Contingency provided to evaluate containment temperature, pressure and radiation conditions

NOTE

(2) Instructions/Contingency provided to evaluate S/G Blowdown and Stack Rad levels and to minimize the spread of contamination

: Reference PS 3055 in Operating Experience Section.

6. Diagnostic Actions

a. Purpose - determine a preliminary diagnosis of the event(s) and determine whether to implement an ORG or the FRG

b. Must be performed upon completion of Instruction/Contingency section

TBD-EOP-00: EOP contingency action 14.3 was added to prevent the possibility of fuel damage due to core barrel lift. As RCS temperature drops below 500ºF, the increased density of the coolant places greater force on the core barrel. TBD-EOP-00: The EPGs address three separate safety functions: containment isolation, containment temperature and pressure control, and containment combustible gas control. The FCS EOPs combine all containment parameters into one safety function called containment integrity. Transparencies 1.10a-d SHB pages 13-16 EO 1.11, 11.12 and 1.13 TBD-EOP-00: The EOP diagnostic actions must be utilized to obtain event diagnosis.

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27

III. SUMMARY

A. Are there any questions on the information covered during this topic?

B. Criterion-referenced Questions

1. List the Fort Calhoun Safety Functions. EO 1.2

2. List the immediate action steps. EO 1.10

3. List the operator steps required to respond to an ATWS.

EO 1.15

4. List the operator steps required to establish Emergency Boration.

EO 1.15

IV. ASSIGNMENT

A. Read and Study

• None

B. Written/Practical

• Perform JPM-0008 ASP with each student as the primary operator. This will be utilized as a teaching tool, not an evaluation. This may be conducted with SSG’s designated in STP 7-68-81.

V. EVALUATION

A. Written

B. Performance

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28

VI. TRANSPARENCY INDEX

Transparency No.

Description

A Title

1.1 Objectives

1.1a Objectives

1.2 Safety Function Classes

1.3 Safety Functions

1.4 Safety Function Hierarchy

1.5 Safety Function Success Paths

1.6 Overview of the Emergency Procedure System

1.7 Safety Function Status Check

1.8 Resource Assessment Tree

1.9 SPTA Structure

1.10a-d Diagnostic Actions

1.11 ORG Structure

1.12 FRG Structure

1.13 Floating Steps 1.13a Floating Steps 1

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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION

LICENSED OPERATOR TRAINING PROGRAM

TITLE: SGTR & UHE

SIMULATOR SCENARIO GUIDE: 82106g REVISION: 2

DATE: 01/12/08 TRAINEES AND INSTRUCTIONAL STAFF: Shift Manager (SM):

Control Room Supervisor (CRS):

At the Controls Operator (ATCO):

Balance of Plant Operator (BOPO):

Shift Technical Advisor (STA):

Additional Operator (RO/SRO/STA):

Simulator Instructor:

Simulator Operator:

Additional Instructor/Observer:

Date of Training: _______________________________

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FCS SSG-82106g Rev 2

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TRAINING OBJECTIVES

OBJECTIVE

1.0 Crew supervisors will direct shift personnel actions.

2.0 Crew members will maintain a rough log that would be sufficient to complete all necessary formal log entries.

3.0 Crew members will respond to equipment and instrument failures and take action to correct/mitigate failures.

4.0 Crew members will respond to alarm conditions and use the ARPs to confirm alarm actions.

5.0 Crew members will use all applicable procedures as required.

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FCS SSG-82106g Rev 2

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NARRATIVE SUMMARY • Condensate Pump Suction Bellows fails. • Turbine Bearing #5 (LP) fails resulting in turbine trip. • Main Steam Safety Valve MS-280 (RC-2B) lifts and won’t reseat on turbine trip • ATWAS occurs with clutch power supplies function. • RC-2B tube leak starts on reactor trip.

INITIAL CONDITIONS

• Power = Mode 1 EQUIPMENT OOS

• None SCENARIO DURATION

• 2.0 hours

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Notes and Comments

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SCENARIO PRESENTATION: Instructor Discuss Simulator Fidelity Issues.

___

Instructor Cover Objectives with students.

___

Operator Fundamentals

Discuss Rotational Focus Area: Monitoring Critical Parameters: From the Industrial Operators Handbook (Chapter 10)

• Critical Parameters are important operating parameters that must be controlled to avoid equipment or system failures.

• Frequency of Monitoring a critical parameter depends upon its importance, its related equipment status and its sensitivity to other equipment changes.

• When monitoring critical parameters operators should watch for designated operating bands and adverse trends that will exceed limits.

• Develop an instrument scan pattern – a habit of glancing at and critically evaluating important operating parameters in a logical sequence.

Instructor

Conduct a brief turnover to the crew

___

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Notes and Comments

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SCENARIO BEGINS:

CREW Walk down the control boards review the shift turnover sheet.

___

CRS Conduct a pre-shift Briefing

___

Scenario Time = After Turnover Briefing EVENT ONE: A Running Condensate Pump Suction Bellows Fails Type Filter Item Value Ramp Delay

MALF CON CON_FW28A (FW-2A) FAIL none none MALF CON CON_FW28B (FW-2B) FAIL none none MALF CON CON_FW28C (FW-2C) FAIL none none BOPO Recognize lowered amp indication on running pump and a

lowering level in the S/Gs. Operator will take action to rotate Condensate pumps and secure the affected pump.

___

CRS Will direct rotating on standby Condensate pump securing affected Condensate pump per appropriate procedure.

___

Scenario Time = Instructor Cue EVENT TWO: Main Turbine Bearing #5 fails (Modify malfunction after ERF alm) Type Filter Item Value Ramp Delay

MALF TUR TUR05E 4 30 s None MALF TUR TUR05E (Modify) 7 15 m None CREW Recognize rising Turbine Bearing Vibration and take action to

monitor and/or trip the plant.

___

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Notes and Comments

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CRS Will enter AOP-26 “Turbine Malfunctions” and direct monitoring turbine vibration and establish a trip point.

___

Simulator Instructor/Operator

FREEZE the SIMULATOR. Discuss Monitoring Critical Parameters.

___

Operator Fundamentals

Monitoring Critical Parameters How did the crew handle monitoring turbine vibration as a Critical Parameter? The CRS should have assigned a crew member to monitor turbine vibration and established an Action Point for manually tripping the reactor. Was an individual assigned? Did changes in vibration get reported appropriately?

Scenario Time = Turbine Trip and Reactor Trip EVENT THREE: ATWAS, Main Steam Safety Valve MS-280 Fails open and Tube Leak starts on RC-2B. Insert Condition (rxtrip eq 1) for initiation on RX Trip

Type Filter Item Value Ramp Delay EVENT NONE ATWAS_PLUS.evt Activate none None MALF SGN SGN_MS280 (rxtrip eq 1) 100 30 s None MALF RCS RCS04B (rxtrip eq 1) 1.0 2 m none ATCO Complete EOP-00 SPTAs for the primary plant. Recognize

ATWAS attempt RX trip at AI-31and commence Emergency Boration.

___

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Notes and Comments

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BOPO Complete EOP-00 SPTAs for the secondary plant. Recognize ATWAS attempt RX trip at DSS and RPS trip breakers. Recognize lowering S/G pressures and close MSIVs.

___

Simulator Instructor/Operator

FREEZE the SIMULATOR. Discuss Monitoring Critical Parameters.

___

Operator Fundamentals

Monitoring Critical Parameters Now, with the current plant conditions the CRS should assign the BOPO to monitor level in the SG with the UHE. The BOPO should sufficiently monitor level to prevent going below 27% prior to establishing steaming in the unaffected SG.

Simulator Operator

If EO dispatched to RM 81, report large amount of steam and noise coming from MS-280.

___

ATCO When RCS pressure reaches 1600 psia, determine proper

safeguards actuation.

___

BOPO Establishes steaming path on unaffected S/G before affected S/G level reaches 27% WR.

___

ATCO Ensure completion of HPSI Stop and Throttle immediately upon meeting required criteria.

___

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Notes and Comments

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CRS Ensure completion of all SPTAs and diagnose transition to EOP-20.

___

STA Confirm diagnosis and transition to EOP-20.

___

SM Enter E-plan and classify the event as an ALERT (EAL 1.5) due to the ATWAS.

___

CRS Transition to EOP-20. Take actions to mitigate UHE and SGTR on same S/G.

___

Simulator Operator

If directed to break condenser vacuum, open VD-200. ___

Type Filter Item Value Ramp Delay REM CND REM:CND_VD200 100.0 1 m none Simulator Operator

Shift Chemist reports on RC-2B rising activity. (This may be the only recognized indicator of SGTR).

___

SM Upgrade Eplan declaration to SAE (EAL 2.7) due to a Primary to Secondary leakage >40 gpm with an ongoing release.

___

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Simulator Instructor

Terminate scenario when RCS pressure and temperature control are established with the faulted S/G isolated, HPSI Stop and Throttle has been completed and all EOP-20 Safety Functions are being met. Ensure E-plan support instructors (if applicable) are satisfied with SM implementation of the EPIPs.

___

Operating Experience

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POST-SCENARIO DISCUSSION

Instructor Review scenario events and procedures used:

___

SM/CRS/Crew Conduct a critique of teamwork, use of procedures, technical performance and human performance fundamentals.

___

SM/CRS/Crew Review Improvement Items.

___

Instructor Discuss any flagged Operator Fundamentals or Operating Experience items that were not discussed during the simulator session.

___

Instructor Discuss issues observed during the simulator session that were not covered during the critique.

Instructor Additional Questions: Question: Answer: Question: Answer:

___

Instructor Review Objectives (Use Objective List)

___

REFERENCES • AOP-26, “Turbine Malfunctions” • EOP-00, “Standard Post Trip Actions” • EOP-20, “Functional Recovery Procedure” • EPIP-OSC-1, “Emergency Plan Implementing Procedure” SIMULATOR MANIPULATIONS

• SIMA – 07a • SIMB – 16, 20, 25

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SIMULATOR OPERATOR INSTRUCTIONS –ATTACHMENT 3 INITIAL SETUP: IC-58 Contains All Commands (Terminate Switch Check with two DSS bypasses in – this is from ATWAS_PLUS.evt) Restore simulator to a Mode 1 IC ___

Activate Event: ATWAS_PLUS.evt

• This allows reactor trip by tripping of the CEDM Clutch Power Supply Breakers ONLY.

___

Activate Event: Ron_EP_WeatherData.evt This ensures that Meterological Data on the ERFCS computer is proper for EAL FC-1188 SM duties.

___

Main Steam Safety Valve MS-280 Fails open and Tube Leak starts on RC-2B on RX trip. Insert Condition (rxtrip eq 1) for initiation on RX Trip

Type Filter Item Value Ramp Delay MALF SGN SGN_MS280 (rxtrip eq 1) 100 30 s None MALF RCS RCS04B (rxtrip eq 1) 1.0 2 m none GO to RUN ___

Ensure Horns are ON ___

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SIMULATOR OPERATOR INSTRUCTIONS – ATTACHMENT 3

Scenario Time = After Turnover Briefing EVENT ONE: A Running Condensate Pump Suction Bellows Fails Type Filter Item Value Ramp Delay

MALF CON CON_FW28A (FW-2A) FAIL none none MALF CON CON_FW28B (FW-2B) FAIL none none MALF CON CON_FW28C (FW-2C) FAIL none none Scenario Time = Instructor Cue EVENT TWO: Main Turbine Bearing #5 fails (Modify malfunction after ERF alm) Type Filter Item Value Ramp Delay

MALF TUR TUR05E 4 30 s None MALF TUR TUR05E (Modify) 7 15 m None Scenario Time = Turbine Trip and Reactor Trip EVENT THREE: ATWAS, Main Steam Safety Valve MS-280 Fails open and Tube Leak starts on RC-2B. Insert Condition (rxtrip eq 1) for initiation on RX Trip

Type Filter Item Value Ramp Delay EVENT NONE ATWAS_PLUS.evt Activate none None MALF SGN SGN_MS280 (rxtrip eq 1) 100 30 s None MALF RCS RCS04B (rxtrip eq 1) 1.0 2 m none Simulator Instructor/Operator

FREEZE the SIMULATOR. Discuss Monitoring Critical Parameters.

___

Simulator Operator

If EO dispatched to RM 81, report large amount of steam and noise coming from MS-280.

___

Simulator Operator

If directed to break condenser vacuum, open VD-200. ___

Type Filter Item Value Ramp Delay REM CND REM:CND_VD200 100.0 1 m none Simulator Instructor

Terminate scenario when RCS pressure and temperature control are established with the faulted S/G isolated, HPSI Stop and Throttle has been completed and all EOP-20 Safety Functions are being met. Ensure E-plan support instructors (if applicable) are satisfied with SM implementation of the EPIPs.

___

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Cutsets Containing Failed M2 Contactor

Probability Initiator7.76E-10 %T3 KC4YTCBAB KRCBM1 KRCBM2 MTC RNOCONLOCA6.75E-10 %S KFFOERMT2S KRCBM1 KRCBM23.26E-10 %T2 KC4YTCBAB KRCBM1 KRCBM2 MTC RNOCONLOCA3.01E-10 %T4 KC4YTCBAB KRCBM1 KRCBM2 MTC RNOCONLOCA2.50E-10 %R KFFOERMT2 KRCBM1 KRCBM2 SGT_RUPTURE2.09E-10 %T3 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV1 RNOCONLOCA2.09E-10 %T3 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV2 RNOCONLOCA1.76E-10 %T3 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK1 RNOCONLOCA1.76E-10 %T3 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK2 RNOCONLOCA1.35E-10 %S KC4YTCBAB KRCBM1 KRCBM21.32E-10 %T22 KC4YTCBAB KRCBM1 KRCBM2 MTC RNOCONLOCA1.27E-10 %T21 KC4YTCBAB KRCBM1 KRCBM2 MTC RNOCONLOCA1.27E-10 %T3 ITR-ATWS KC4YTCBAB KRCBM1 KRCBM29.00E-11 %I3QOUT KFFOERMT2 KRCBM1 KRCBM2 RCPCOOLER8.99E-11 %I3QIN KFFOERMT2 KRCBM1 KRCBM2 NOPER-60 RCPCOOLER8.79E-11 %T2 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV1 RNOCONLOCA8.79E-11 %T2 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV2 RNOCONLOCA8.11E-11 %T4 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV1 RNOCONLOCA8.11E-11 %T4 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV2 RNOCONLOCA7.92E-11 %T24 KC4YTCBAB KRCBM1 KRCBM2 MTC RNOCONLOCA7.42E-11 %T2 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK1 RNOCONLOCA7.42E-11 %T2 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK2 RNOCONLOCA6.84E-11 %T4 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK1 RNOCONLOCA6.84E-11 %T4 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK2 RNOCONLOCA5.34E-11 %T2 ITR-ATWS KC4YTCBAB KRCBM1 KRCBM24.92E-11 %T4 ITR-ATWS KC4YTCBAB KRCBM1 KRCBM24.45E-11 %T3 KC4YTCBAB KRCBM1 KRCBM2 RMMSRVFTO RNOCONLOCA3.57E-11 %T22 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV1 RNOCONLOCA3.57E-11 %T22 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV2 RNOCONLOCA3.47E-11 %T13 KC4YTCBAB KRCBM1 KRCBM2 RNOCONLOCA3.47E-11 %T14B KC4YTCBAB KRCBM1 KRCBM2 RNOCONLOCA3.43E-11 %T21 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV1 RNOCONLOCA3.43E-11 %T21 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV2 RNOCONLOCA3.07E-11 %T3 KC4YTCBAB KRCBM1 KRCBM2 OPER-50 RNOCONLOCA3.01E-11 %T22 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK1 RNOCONLOCA3.01E-11 %T22 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK2 RNOCONLOCA2.89E-11 %T21 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK1 RNOCONLOCA2.89E-11 %T21 KC4YTCBAB KRCBM1 KRCBM2 PORVBLOCK2 RNOCONLOCA2.17E-11 %T22 ITR-ATWS KC4YTCBAB KRCBM1 KRCBM22.13E-11 %T24 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV1 RNOCONLOCA2.13E-11 %T24 KC4YTCBAB KRCBM1 KRCBM2 RMMSRV2 RNOCONLOCA2.08E-11 %T21 ITR-ATWS KC4YTCBAB KRCBM1 KRCBM22.07E-11 %T3 KMMCCFCTCB KRCBM1 KRCBM2 MTC RNOCONLOCA2.00E-11 %R KC4YTCBAB KRCBM1 KRCBM2 SGT_RUPTURE

Basic Events

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KEYBasic Event Description ProbabilityKC4YTCBAB RPS Breaker CB-AB Fails to Open 1.20E-04KC4YTCBCD RPS Breaker CB-CD Fails to Open 1.20E-04KRCBM1 Failure of Trip Contactor M1 to Open 1.20E-04KRCBM2 Failure of Trip Contactor M2 to Open 1.00E+00KRCBM3 Failure of Trip Contactor M3 to Open 1.20E-04KRCBM4 Failure of Trip Contactor M4 to Open 1.20E-04KMMCCFCTC CCF of Trip Contactors 3.59E-02KFFOERMT1 Operator Fails to Trip (Pushbutton #1) see commentKFFOERMT2 Operator Fails to Trip (Pushbutton #2) see commentKFFOERMT1S Operator Fails to Trip (Pushbutton #1) see commentKFFOERMT2S Operator Fails to Trip (Pushbutton #2) see comment

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RNOCONLOCARNOCONLOCARNOCONLOCARNOCONLOCA

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Revision: 0

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE

JPM No.: JPM-0011AF JPM Title: Failure of Automatic Reactor Trip upon demand (ATWAS) System(s): Emergency Operating Procedures Location(s): Control Room Reference(s): (1) EOP-00

(2) NRC K/A 000029,EK3.12 (RO4.4/SRO4.7) (3) NRC K/A 000029,EA2.09 (RO4.4/SRO4.5)

JPM Prepared by: C.E. Ralrick Date: 07/23/09

JPM Approved by: Date:

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE

JPM No.: JPM-0011AF JPM Title: Failure of Automatic Reactor Trip upon demand (ATWAS) Standard: Reactor trip has been verified after opening the CEDM Clutch Power Supply Breakers. Approximate Time: 3 minutes Actual Time:

Operator's Name: Employee ID #: All Critical Steps (*) must be performed or simulated in accordance with the standards contained in this JPM. The operator's performance was evaluated as:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator's Signature: Date:

Operator’s Signature: Date:

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE

JPM No.: JPM-0011AF JPM Title: Failure of Automatic Reactor Trip upon demand (ATWAS) Tools & Equipment: None. Safety Considerations: None. Comments: This is an ALTERNATE SUCCESS PATH JPM.

THIS JPM WILL BE PERFORMED AS A DYNAMIC JPM ON THE SIMULATOR.

Feedback: The evaluator should only provide indication status (ie.: lights, gages and valve position) if

a student performs an evolution and then requests the status of the indication.

SIMULATOR SETUP: Reactor fails to trip upon Low Flow RPS demand.

[EVENT ATWAS_PLUS]

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Revision: 0

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE

JPM No.: JPM-0011AF JPM Title: Failure of Automatic Reactor Trip upon demand (ATWAS)

Initiating Cue: All systems are in a normal lineup. You are the only Reactor Operator in the Control Room and are directed to respond to any alarms received.

EVALUATOR CUE: Initiate Reactor Trip by: [MALF RCP BUS_1A3_5_BKR_TRIP TRUE]

START TIME:___________ *CRITICAL ELEMENT STANDARD STEP * 1. Recognize no Reactor Trip on demand on demand by 2/4 RPS Low Flow trips.

CB-4 No Reactor Trip annunciator and no Control Rod insertion

*_____

2. Trip the Reactor at CB-4. Depress the CB-4 Reactor Trip Pushbutton CB-4

Cue: Reactor did not trip, no Rx Trip alarm.

*____3. Trip the Reactor at the RPS panels.

AI-31 Depress the RPS Reactor Trip Pushbutton Cue: Reactor did not trip, no Rx Trip alarm.

*____4. Trip the Reactor at AI-66A/B

AI-66A/B Place both DSS Manual Trip switches in TRIP Cue: Reactor did not trip, no Rx Trip alarm.

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Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE

JPM No.: JPM-0011AF JPM Title: Failure of Automatic Reactor Trip upon demand (ATWAS) *CRITICAL ELEMENT STANDARD STEP *___ 5. Trip the Reactor at AI-57

AI-57 OPEN both CEDM Clutch Power Supply Breakers Cue: Reactor trip, RX Trip alarm annunciated.

6. Verify Reactivity Control is established by ALL of the following:

*___ Reactor power is lowering *___ Startup Rate is negative *___ No more than one Regulating or Shutdown CEA is NOT inserted.

CB-4 Check the following:

• Power/Wide Range instruments have a lowering trend.

• Startup rate instruments show negative. • SCEAPIS, Primary Synchros and/or Core

Mimic show all trippable rods inserted. Cue: STOP

Termination Criteria: Reactor verified tripped after opening CEDM Clutch Power Supply Breakers.

STOP TI ME:_________

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Fort Calhoun Station Operations Training with respect to M-2 Contactor Issue

Reactivity control is the highest priority of the Emergency Operating Procedure (EOP) safety functions. There is a very high level of confidence that the operators would use every one of the actions prescribed in EOP-00 (Reactor Trip) until the reactor is successfully tripped. This is a recurring area of emphasis in licensed operator training.

The contingency step for EOP-00 has actions listed in order to ensure action is completed by one of the steps listed. This is per (OPD 4-09) EOP/AOP User Guidelines as stated below. 22.0

EVALUATION ORDER

22.1 Steps are to be performed in order of appearance unless otherwise noted. If steps are permitted to be performed out of order, then a note will specify that. Additionally, steps within EOPs are designated as continuously applicable or non-sequential. These steps can be performed in any order as conditions are met, and are not considered deviations. 22.2 Time dependent steps will have the time limit in the step. When a set of steps is time dependent, there will be a note to state that ahead of the first step in the set. 22.3 Equally acceptable steps are a set of steps any of which may accomplish the goal of the overall step. The order of appearance is most-to-least preferred. Operators should attempt to perform step a. If unable to perform step a, attempt b, etc. Therefore, based on the following step contained in EOP-00: 1.1 IF the reactor did NOT trip, THEN establish Reactivity Control by performing step a, b, c or d: a. Manually trip the Reactor (CB-4). b. Manually trip the Reactor (AI-31). c. Place the DSS Manual Trip Switches in "TRIP" (AI-66A/B). d. Manually open the CEDM Clutch Power Supply Breakers (AI-57). The substeps a,b,c or d are considered equally acceptable steps since they all shut down the reactor in the absence of an equipment malfunction.

Operations personnel are trained to ensure the reactor is shut down by performing these specific actions in EOP-00 (Standard Post Trip Actions). The steps listed in EOP-00 include manual trip from CB-4 (Pushbutton), AI-31 (Pushbutton), AI-66 (Two DSS

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switches) or AI-57 (Two CEDM Clutch Power Supply Breakers). Refer to control room layout under Attachment 1 for locations of trip methods.

Operations training uses the steps in EOP-00 to ensure these requirements are met

by training operators to “establish” as defined by OPD 4-09 to mean “To make arrangements for a stated condition” reactivity control by assigning functions to each Reactor Operator. The At The Controls Operator (ATCO) typically would be the first Reactor Operator to manually trip the reactor at CB-4. If this is not successful, the ATCO proceeds to AI-31 Reactor Trip pushbutton. The Balance Of Plant Operator (BOPO) is simultaneously going to AI-66 panels for the DSS switches. In the event neither method (CB-4 or AI-31) is successful, the ATCO returns to CB-4 to establish emergency boration while the BOPO goes to AI-57 to trip CEDM Clutch Power Supply breakers. These actions are typically performed by the two operators in well less than two minutes. In reduced manning training or evaluations, all of these actions are required to be performed by one Reactor Operator, and can still be performed in less than two minutes.

Further procedural guidance is found in EOP-20 (Functional Recovery Procedure)

for additional methods to shut down the reactor including going to the AI-40 A/B/C/D (120V AC) instrument bus panels to trip AI-57 Power Supply Breakers or AI-3 panel to toggle the individual CEDM Rod drop test toggle switches.

It is important to note that all of the actions identified in EOP-00 and in

EOP-20 are performed without having to leave the control room (see attachment 1 for locations.)

Fort Calhoun Operations Training provides several methods of training and evaluation to Licensed Operators regarding Anticipated Transient Without Scram (ATWS) on both an initial and continuing basis. These methods include classroom lectures, simulator scenarios, written tests and Job Performance Measures (JPM) Classroom training can be found under lesson plan 7-12-25 (Reactor Protective System and Diverse Scram System). These objectives include training on the different trip flow paths available to shut down the reactor (i.e. AI-31 pushbutton, DSS switches to open CEDM (Control Element Drive Mechanism) Clutch Power Supply Breakers, RPS automatic trips and CB-4 pushbutton to open M contactors). This training provides the specific knowledge required to understand the different trip mechanisms and the equipment affected. This lesson plan is used for the Initial Licensed Operator class during Systems training phase and on a two year recurring cycle for Licensed Operator Requalification training. An additional classroom lesson plan is 7-18-10 (EOP-00 Standard Post Trip Actions). This lesson plan is also used for the Initial Licensed Operator class during phase 3 training (Emergency Operations) and on a two year recurring cycle for Licensed Operator Requalification training. Dates of classroom instruction include 2007 Rotation cycle 2, 2009 Rotation cycle 2 and scheduled for 2011 Rotation cycle 2 and 6.

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Additionally Simulator Scenario Guides (SSG) are used to reinforce the classroom training. In these scenarios the crews are required to use multiple methods before the reactor is successfully shut down as described above. Examples from the last two years are included below: Year Used SSGs Success Path 2009 Rotation 09-3 82105g Clutch Power Supply Breakers 2009 Rotation 09-4 82110e Clutch Power Supply Breakers 2010 Rotation 10-2 82106g Clutch Power Supply Breakers 2010 Rotation 10-5 82110e-1 DSS Trip

Job Performance Measure (JPM) evaluation tools are also used to verify correct response. Examples from the last two years are included below: Year Used JPMs Success Path 2009 Annual 0011BF DSS Trip 2009 Annual 0011AF Clutch Power Supply Breakers Initial Licensed Operator Simulator Scenario Guides used include:

8-12-19 Reactor Trip with Emergency Boration 8-13-16 Reactor Trip with Functional Recovery

In summary, based on the content and frequency of training and evaluations on an

ongoing basis, there is a very high level of confidence that the operators would take all of the actions in EOP-00 and if necessary, EOP-20, to trip the reactor if automatic trip failed.

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Attachment 1

AI-31 PB

AI-66

SW

AI-57 BKR (s)

CB-4 PB

AI-3 RDTS

AI-40 A/B BKRS AI-40 C/D BKRS

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1

Fort Calhoun Station and Westinghouse called and discussed question clarification from Jeff Circle (NRR). The following 2 questions were identified:

1) Did Westinghouse use NUREG/CR 5500 methodology for MTC effects (probability of unfavorable MTC)?

NUREG/ CR 5500, Vol. 10, is the reliability study for Combustion Engineering reactor protection systems. It was directed at establishing reliability of the RPS, and MTC is not addressed in that document. The detailed RPS reliability model used in the OPPD assessments was based on CEN-327-A which was reviewed and approved by the NRC. The Fort Calhoun Station (FCS) RPS model was based on CEN-327-A and was updated to include interposing relays and the diverse scram system. Where appropriate, data was adjusted to reflect data contained in NUREG/CR-5500. The treatment of the MTC in the FCS accident sequences is generally consistent with the event tree model presented in NUREG-1780 (Figure A-4 of NUREG-1780, see below). For the evaluation of FCS core damage frequency, the modified CEN-327-A model was integrated into the baseline Rev. 11 PRA. The treatment of ATWS in that PRA revision was based on the generic ATWS analyses and included an unfavorable MTC probability of 0.22.

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2) Provide differences (quantify) between generic ATWS analysis and Westinghouse analysis.

As discussed with Jeff Circle on 6/8/11, the response to this question can be addressed by providing the top 100 cutsets. They are attached in file (FCScutsets Rv1.xlsx). The top 100 cutsets are in the first Tab and the cutsets containing the failed M2 contactor are in the second Tab. None of the failed M2 contactor cutsets were found in the top 100 cutsets. Note: These cutsets reflect the 0.22 unfavorable MTC probability is consistent with the generic ATWS challenges. They do not credit the unfavorable MTC reduction which was observed with revised FCS specific ATWS transient analyses. Those analyses were used in the development of the PRA human error probabilities.

The following questions were received from the M2 Regulatory Conference:

3) Is ASME Service Level C appropriate (<3200 psia) for FCS ATWS analysis? As noted in SECY-83-293, the ASME Service Level C pressure of 3200 psig was assumed to be an unacceptable plant condition during ATWS rule development. This pressure limit criterion was used for the present assessment. Note that there is considerable potential margin in the stipulation that 3200 psig represents a core damage condition. During the period preceding the ATWS rule, structural analyses had been performed for CE PWRs that note that mitigating components of CE PWRs will function to 4300 psia. Thus, the 3200 psig criterion is appropriate.

4) Provide additional guidance to operations to implement EOP-20. Include definition of reactivity control sequence.

The attached lesson plan (file 071810G.doc) is for Operator Standard Post Trip actions and EOP-00. On page 9 at the top of the page is a list of what is necessary to meet reactivity control. The operators must meet one of these to satisfy reactivity control. Also included is a copy of EOP-20 Technical Basis Document, page 36 (file TBD-EOP-20 pg 36.pdf). This document is the resource assessment tree for reactivity control. The operators must complete one of the success paths to consider this safety function not in jeopardy. The safety function for EOP-20 allows the operators to meet the safety function without inserting rods or emergency borating as long as power is below 10-5 % and constant and lowering. The operators must successfully complete one of the Reactivity Control sections before they move on in the procedure. At the end of the EOPs is a safety function status check. The safety function status checks will send the operator to EOP-20, Functional Recovery Procedure.

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3

5) Provide previous failure history and details on CB-AB and CB-CD. The RPS clutch circuit breakers are cycled a minimum of 17 times during, and just prior to, startup after a refueling outage. Attached file, RPS Circuit Breaker Replacement and Maintenance History.docx, provides maintenance history of the RPS trip circuit breakers, CB-AB and CB-AD. Information was obtained via condition reports, work order packages, engineering change packages, surveillance tests, control room logs, and conversations with plant staff members. Attached file, “RPS M Contactor Maintenance and Testing.docx”, provides maintenance history of the RPS clutch power supply M contactors. Information was obtained via condition reports, work order packages, engineering change packages, surveillance tests, control room logs, conversations with plant staff members.

6) Provide actual delta CDF #

The Annual Delta CDF using the values presented at the Regulatory Conference is 1.08E-6/yr. The Delta CDP for the 32.5 day M2 Failure Exposure Time is 9.62E-8.

7) On Slide #18, determine if picture is as found, as staged, or don’t know. Per the System Engineer, who was on location when the picture was taken, the picture is the ‘as found’ condition prior to disassembly.

8) What is the specific peak centerline temperature (PCT) calculated in the ATWS analysis?

The peak centerline temperature is not explicitly calculated by CENTS. Peak temperatures are not expected to significantly exceed that typical of normal operating conditions as no core overpower occurs and the core power is rapidly reduced. The temperature of the surrounding fluid does increase. For the ATWS transient scenarios analyzed, the fuel is continuously covered and heat transfer from the fuel to the water is effective. The small LOCA ATWS event results in core uncover. However, this event was only used to determine the time for operator action prior to core uncovery, so no fuel temperature heat-up calculation was performed.

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Follow-up request from JClark regarding Docketing of Material on June 3, 2011: “In regards to the Westinghouse report FCS provided during the regulatory conference, it is marked as “Westinghouse Proprietary – Class 2.” This and any supplemental information regarding this report is subject to our determination as to whether or not it is releasable to the public. To make this determination, we need from you (and/or Westinghouse) your proprietary justification. This, as a standard, is a letter or affidavit to us.” FCS response: Attached is the scanned affidavit file, CAW Scans 3176 and 3177.pdf

Follow-up request from JClark regarding MTC value differences on June 8, 2011: “In reviewing your analyses for the RPS issue, we noted there were multiple values supplied for your moderator temperature coefficient. These values differed by an order of magnitude (i.e. factor of 10). Please provide the correct value from your reference documents.” FCS response: Pages 5 and 8 of Westinghouse document LTR-RAM-II-11-061 incorrectly indicated that the Fort Calhoun BOC moderator temperature coefficient is -9.4E-04 ∆ρ/°F. The correct value is -0.94E-04 ∆ρ/°F. The document is being revised to correct the error.

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FORT CALHOUN STATION FORM

(J

SURVEILLANCE TEST COVER SHEET

J/5P rf) pA1

FC-1115A C;KCL­R6

Surveillance Test Number: RE-ST-RX-0002 I Work Order Package No: 00316182 01 ./

Title: MODERATOR TEMPERATURE COEFFICIENT MEASUREMENT Due Date: 11/1/2009 I Drop Date: I Frequency: 101 I PMID: 00000612 EEQ:N I Scaffold: N I Trending: N

Special Conditions: 2009 RFO

1. Reason for Test (if other than scheduled):

2. Postponement explanation (if required):

Expected Completion: I Supervisor or System Engineer: Date:

3. Test results acceptable? [X] Yes [ ] No

Tech Specs satisified? (Not required for acceptable test) [ ] Yes [ ] No

Supervisor or System Engineer: / )£)~ Date: IZ "/Y-0) Time:L5~

Additional Code analysis required within 72 hours? [ ] Yes I [ 1 No I [ v]"N/A

STA Initials: 11-)c... Date:IZ/rs/ bf Responsible System Engineer: BARE, MARK M

4. ST Coordinator initial test review Initials: f!t} Date: P·{t '( ((J '7 WO required? [ ] Yes [ J No I

Frequency Increased? [ ] Yes [i/1 No

CR required? [ ] Yes 1/J No Retest required? [ ] Yes 1V1 No System Engineer test review: N Initials: Date:

1ST Coordinator test review: N Initials: Date:

ST Coordinator final test closeout review: Initials: /1/J.- Date: r0crftr ~ v ·;

(SO-G-23)

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Fort Calhoun Station Unit No. 1

RE-ST -RX.-0002

SURVEILLANCE TEST

MODERATOR TEMPERATURE COEFFICIENT MEASUREMENT

Change No. Convert

Reason for Change Converted from WordPerfect to Word.

Requestor N/A

Preparer K. Horn

Issue Date 10-17-07 3:00pm

PAGE 1 OF6

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FORT CALHOUN STATION SURVEILLANCE TEST REFERENCE USE

RE-ST -RX-0002 PAGE 2 OF6

MODERATOR TEMPERATURE COEFFICIENT MEASUREMENT

SAFETY RELATED

1. PURPOSE

To satisfy, after each Refueling prior to reaching 5% of Rated Power, the requirements of Technical Specification 3.1 0(2)1 for Moderator Temperature Coefficient.

This test provides the value of the Moderator Temperature Coefficient at Low power by measuring the Isothermal Temperature Coefficient and is a part of the Low Power Core Physics Testing.

2. REFERENCES/COMMITMENT DOCUMENTS

2.1 Technical Specifications:

• 2.1 0.1: Minimum Conditions for Criticality • 2.10.2: Reactivity Control Systems and Core Physics Parameters Limits • 3.10: Reactor Core Parameters

2.2 SO-G-23, Surveillance Test Program

3. DEFINITIONS

None

4. EQUIPMENT LIST

None

5. PRECAUTIONS AND LIMITATIONS

5.1 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

5.2 No maintenance shall be conducted within this Surveillance Test other than that specifically directed by this procedure.

5.3 Nothing in this procedure shall be construed to override the requirements of the Fort Calhoun Station Unit 1 Operating License. Technical Specification requirements are strictly in effect for the conduct of this test.

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FORT CALHOUN STATION SURVEILLANCE TEST REFERENCE USE

RE-ST -RX-0002 PAGE30F6

5.4 The Reactor Engineer shall be notified within 24 hours of the completion of this test of any marginal, unexpected, or unacceptable results.

5.5 The completed Surveillance Test procedure and all applicable attachments shall be signed and dated by the person(s) who actually performed the test.

6. PREREQUISITES

NOTE: Prerequisites need not be performed in numerical sequence.

6.1 Verify current procedure revision number.

Procedure Rev. No. ----.ff--------6.2 No other test is in progress which could potentially affect this test,

or if this test were performed, could have an effect on that test.

6.3 A prejob briefing has been conducted prior to start of this test. All personnel involved in the performance of this test have read and understand, to the extent of their involvement, the procedure and have completed the Surveillance Test Signature Sheet.

7. PROCEDURE

7.1 Perform lsothennal Temperature Coefficient Measurement attachment of RE-CPT-RX-0001.

7.2 Attach a copy of the Isothermal Temperature Coefficient Measurement from RE-CPT-RX-0001.

8. RESTORATION

8.1 The Shift Manager has been notifi(ld the

9. ATTACHMENTS

9.1 Surveillance Test Signature Sheet

9.2 Comment Sheet

INITIALS/DATE

rJrr/f'i 1 2.oz.z... ate Time

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FORT CALHOUN STATION SURVEILLANCE TEST REFERENCE USE

RE-ST -RX-0002 PAGE4 OF 6

10. ACCEPTANCE CRITERIA

10.1 The value of the Moderator Temperature Coefficient is within the range provided by Nuclear Engineering.

10.2 The value of the Moderator Temperature Coefficient is within the limits of T.S. 2.1 0.2(3).

11. TEST RECORD

11.1 This entire procedure.

11.2 Attachment 3 of RE-CPT-RX-0001.

12. PERFORMANCE AND REVIEW

12.2 Test data shall evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 ho~r/f./Y~: of this test.

Evaluated by tf--rJ~ Datemme'zJslo'f ,zz13 STA

Reviewed by ~rt:61? DatefTime tWr/d) I & 32.0 Shift Manager

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FORT CALHOUN STATION SURVEILLANCE TEST REFERENCE USE

Attachment 9.1 -Surveillance Test Signature Sheet

Name (Print) (\ Signature

-.J. kA I /.P '1{1 ~J§J'fr (/

RE-ST -RX-0002 PAGE 5 OF 6

Initial&

JJ {/

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FORT CALHOUN STATION SURVEILLANCE TEST REFERENCE USE

RE-ST -RX-0002 PAGE 6 OF 6

Attachment 9.2 -Comment Sheet

1) j2t:-, err -J{;<..~OOdl .1J ffA'-~~~"' t ~ ArlAc(W~~ .._-t 7.4 n.., c) "}';_,.. o~M-~vrr- CoeJf:'t-o--!f, AJIJ.du 'St f. rJl~ TJn~-t-- Pl"o/0'\ f?YvJA5 OT tc. ~me--W J

, CJ. (' !A JJl.Jl-A J 7..(,,f(f)9 Tl C/~ I I

z...\ m-rc ft.1 «5tA ~ r.vt ~ o. b \7 ~ 110 ~.., ~ r rf tuAtd M u/; -fl... A.cco--f2u ,. cNTtNd.. of' io.'2.~r5'ft. _c_ +c). f '{I 'JO -Is' hP I (J"r-:: /

, I CJeM JI.IC& ;?/(;J'/IJ1 {/ I I

M~ I fl._. /(' e'"'Cff- flX -?f7501 }e:s r e;, ( J,.., UA,..-

d,j ...c,} A~<:Jr.,. (1~ ,~ J t~ ,~CJ..:h v c JJAJ. ili ,..._f,tLsiJ

(/ I I

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(

FORT CALHOUN STATION CORE PHYSICS TESTING CONTINUOUS USE

RE-CPT -RX-0001 PAGE 42 OF 71

Attachment 3 - Isothermal Temperature Coefficient Measurement

SAFETY RELATED

1. PURPOSE

2.

1.1 To measure the Isothermal Temperature Coefficient.

PREREQUISITES

2.1

2.2

2.3

Tcold is at the nominal value of 532°F (530•F- 534.F).

Reactor is Critical at a Power Level less than 10"1% on a minimum of two (2) Wide Range Logarithmic Channels.

Group 4 CEAs are at 1 00" (85" - 115").

NOTE: Prerequisite 2.4 may be NIAed at the discretion of the LPPT Engineer.

2.4 RCS Loops and Pressurizer Boron Concentrations are within 20 ppm of each other.

2.5 . Pressurizer Level is 44 to 52%.

,v I ll ''" -<>1

,IV' I ll·li'·l>f

_.v I ll·IY•vf

V I ll·tY·I> f

_A/ I IL-tf·Pl

3. PRECAUTIONS

3.1 A sustained maximum Startup and Shutdown Rate of 0.6 DPM shall not be exceeded.

3.2 Unless otherwise instructed, Regulating Group 4 CEAs in Manual Sequential (MIS) shall be used to control and stabilize the Reactor with Group 4 at 1 00" (85" - 115").

3.3 Reactor Power shall not exceed the allowable ranges recorded in Attachment 2, Step 4.13.

4. PROCEDURE

4.1 Ensure Group 4 is at 1 00" (85"- 115") and Reactor Power is stabilized in the Range recorded in Attachment 2, Step 4.13 by movement of Group 4 or BorationiDilution per 01-CH-4.

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(

FORT CALHOUN STATION CORE PHYSICS TESTING CONTINUOUS USE

Attachment 3

RE-CPT-RX-0001 PAGE 43 OF 71

4.2 If desired, obtain and sign a copy of Plant Computer Display LPP. t~/4 / I tJ..it'·")

4.3 Record current time_-'/'-2.....:3_0 __

4.4 If desired, immediately prior to the actual heatup process, obtain and sign a copy of Plant Computer Display LPP.

NOTE: Isolation of blowdown and steam drains will aid in RCS heatup.

NOTE: During the performance of the heatuplcooldown the position of Group 4 should not be changed unless power approaches the upper or lower limit as defined in Step 4.13 of Attachment 2.

4.5 Raise o~dire~chosen by LPPT Engineer) the RCS average~;aturt3Y to 4°F as directed by the Shift Manager.

4.6 With Tcold at the desired temperature, allow 5 minutes for equilibrium.

4.7 If desired, obtain and sign a copy of Plant Computer Display LPP.

NOTE: During the performance of the cooldownlheatup, the position of Group 4 should not be changed unless power approaches the upper or lower limit as defined in Step 4.13 of Attachment 2.

NOTE: If the Pressurizer level approaches the heater cutoff setpoint, the Shift ManageriCRS may take appropriate actions as required. This may include manually controlling charging and letdown, blending to the RCS or terminating the cooldown.

CAUTION Pressurizer level will decrease approximately 1% per degree F .change in RCS temperature.

4.8 Manual control of letdown may be taken during the performance of this Attachment at Shift Manager's discretion to avoid unnecessary charging pump actuation. NIA if not desired.

4.9 Lower or raise (direction chosen by LPPT Engineer) the RCS average temperature 2 to 4°F as directed by the Shift Manager.

4.10 With Tcold at the desired temperature, allow 5 minutes for equilibrium.

_,1/ 1/Z-t'Nf

,p, / I /Z-tr-11{

,4/ I tz.·t f-Of

_J/ I I t.-1~-o~

R45

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(

FORT CALHOUN STATION CORE PHYSICS TESTING CONTINUOUS USE

Attachment 3

4.11 If desired, obtain and sign a copy of Plant Computer Display LPP.

4.12 Ensure that the RMAS software calculates the Isothermal and Moderator Temperature Coefficients. Attach RMAS analysis results pages.

4.13 Verify that the Moderator Temperature Coefficient measurement is within the acceptance criteria.

RE-CPT-RX-0001 PAGE 44 OF 71

4.14 If the Moderator Temperature Coefficient is outside the limits of the acceptance criteria contained in Attachment 7B, perform Steps 4.4 through 4.13 again as necessary to ensure repeatability of the measured value. (NIA if the measured value is within acceptance criteria.) ,;~ V I tZ.·Ik.oJ

4.15 If the Moderator Temperature Coefficient is outside the limits of the acceptance criteria contained in Attachment 7B and is repeatable, repeat Steps 4.4 through 4.13 as necessary with Group 4 inserted as required to generate a Moderator Temperature Coefficient within Technical Specification Limits. (NIA if the measured value is within acceptance criteria.)

4.16 If desired by the Shift ManageriCRS. then return Pressurizer level to Program.

4.17 When desired by the LPPT Engineer, obtain a Group Trend Report for Trend Block (TBA) as follows: {cO,

4.17.1 Open GTR display page.

4.17.2 Set interval to 1 minute.

4.17.3 Set appropriate start date.

4.17.4 Set start time equal to time recorded in Step 4.3.

4.17 .5 Set end time to current or desired end time.

4.17 .6 Select desired output printer.

4.17.7 Click the TBA button to initiate report.

,4/ It z.-1'1- <> 7

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(

FORT CALHOUN STATION CORE PHYSICS TESTING CONTINUOUS USE

RE-CPT-RX-0001 PAGE 59 OF 71

Attachment 7A- Preliminary Results from Comparison of Predicted and Measured Low Power Physics Parameters (Hot Zero Power, 2100 psia, 532°F)

SAFETY RELATED

ALL RODS OUT (ARC) CRITICAL BORON CONCENTRATION (ppm):

PREDICTED* MEASURED DIFFERENCE ACCEPTANCE REVIEW (Pred. - Meas.) CRITERIA CRITERIA

/0 e:J(,D /5'1,0, '3 '2..1'), '2... + 90 of Predicted + 50 of Predicted

ARC ISOTHERMAL TEMPERATURE COEFFICIENT (t. JOF):

PREDICTED*' MEASURED DIFFERENCE ACCEPTANCE REVIEW (Pred. - Meas.) CRITERIA CRITERIA

-f -o,N?w-v +o. o (p'{, X./O- ~ MTC Tech. Spec ± 0.20 X 10'4

-o. o7'1'"-Ja Limit of <+0.50 X 10'4

MOST POSITIVE MODERATOR TEMPERATURE COEFFICIENT (t.p/°F):

o./(pt- xro-5 + o. '"5 '}.ro-) = o ,~p~; vo-5

(Measured MTC (MTC Measurement (Measured MTC at from RMAS Output) Uncertainties)*** HZP with Uncertainties)

From the Startup Physics Parameter Predictions obtained from RPA. Predicted lTC is determined at the boron concentration at which the test is performed. This is calculated by linear interpolation of the predicted HZP upper and lower data from the "Temperature Coefficient Analysis" RMAS printout.

... The uncertainty is calculated as the standard deviation of the state points from the MTC measurements using the following equation. The state point data is from the "Temperature Coefficient Analysis" RMAS printout.

[ " ly, 0'= ~(x;-x)'

n- 1

I certify the predicted and measured values listed in the above Sections are correct, and all Acceptance and Review Criteria listed above has been correctly transposed from Attach~_

~ tf((ft!!' lvZ-/ ~ Dt Time

I certify the predicted and measured values listed in the above Sections have been reviewed and are correct, and all Acceptance and Review Criteria listed above has been reviewed and correctly transposed from ttachment 7B. [AR 09271]

12/lf/ott (6J/ Date Time

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'--

Temperature Coefficient Analysis

FCS Cycle26 Test Date: Friday, December 18,2009 (Printed on 12/18/2009)

PREDICTED DATA: Predicted Value Dependencies: Boron Dependency with Linear Interpolation

Hot Zero Power: Upper Boron Concentration= 1606 PPMB lTC (Upper) = -0.794 PCM/Deg F MTC (Upper) = 0.841 PCM/Deg F DTC (Upper)= -1.635 PCM/Deg F

Lower Boron Concentration= 1479 PPMB lTC (Lower) = -4.276 PCM/Deg F MTC (Lower) = -2.641 PCM/Deg F DTC (Lower) = -1.635 PCM/Deg F

Acceptance Criteria: lTC or MTC Delta (Pred- Meas)= ±2 PCM/Deg F Upper Limit MTC = <5 PCMIDeg F

Prepared by tho 5 ~vI'" Date: l2llf loO!

{j,.__JIL

1 tempco _ official.tco

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\.....

Temperature Coefficient Analysis

FCS Cycle 26 Test Date: Friday, December 18,2009 (Printed on 12/1812009)

MEASURED DATA: Analysis Method: Average of Selected Ramps

lTC (Pred) - lTC (Meas) RCS Boron Concentration = 1606 PPMB Average Temperature= 530.2

State Start End Rho Temp GP4 Point Time Time (PCM) (Deg F) (Steps)

STATE 1 12:26:10 12:27:36 -1.8555 531.38 101.79 STATE2 12:36:54 12:38:22 0.7020 529.06 101.79 STATE3 12:36:51 12:36:22 0.7191 529.06 101.79 STATE4 12:54:14 12:55:43 -3.7518 531.48 101.79

CALCULATIONS:

State Rod Change Change Measured Measured Point Corr. in Rho in Temp Alpha T Alpha M

(PCM) (PCM) (Deg F) (PCMIF) (PCM/F)

STATE 1 T02: 0.0000 2.5575 -2.32 -1.102 0.533 STATE 3T04: 0.0000 -4.4709 2.42 -1.844 -0.209

Average Values -1.473 0.162

Prepared by ao·l <JJ.evl•" Date: f111f /a"' Cl-Jfl-

2 tempco_official.tco

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._ Temperature Coefficient Analysis

FCS Cycle26 Test Date: Friday, December 18, 2009 (Printed on 12/18/2009)

TEST RESULTS: Predicted Alpha T = -0.794 PCM/Deg F Measured Alpha T = -1.473 PCM/Deg F

Predicted Alpha M = 0.841 PCM/Deg F Calculated Alpha M = 0.162 PCM/Deg F

Delta Alpha T (Pred-Meas) = 0.679 PCM/Deg F Acceptance Criteria +/- 2 PCM/Deg F PASS

Upper Limit MTC Acceptance Criteria < 5 PCM/Deg F PASS

Prepared by CJ.n·, "Vtvl•" Date: 1"2 ~~~ lt1"\

CLJIL-

3 temp co_ official.tco

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X • • e

~ f OfOIO 0 0 . . . 0

o <D I ""' 0 ('I) ..--..-- 1.()

0 0 ..--

-

~

u. ~ ~

Cl 2 ~

._ ())

(/) ~

0 0 0. a. a. ~

()) >< ()) -~

(/) 0::

>- ._ ::s ~

:::R - -~ ·:;; ro ""' u ._ a.

._ ())

C) ())

~ ro 0. 0 ()) E a. 0:: ())

r-1 -

t I I ""' 0

9

10 r ()) 0 0

8 ci ail~ 0 0 N 0 . ..-- 1.() ..-- '

Temperature Coefficient Analysis

State 1-2: Rod Correction= 0.0 dRholdt = -t.10 -- --- -·

State 1 1 0~ .79 Steps 53~.38 Deg F -1.86 PCM

-""

...

FCS Cycle 26 State~: Rod Correction = 0. 0 dRholdt = -1.84

- -"' "'

' State 3 1 0~ .79 Steps 52~.06 Deg F 0.72 PCM

~ ""' "'

.A v

- ----""

te~~ Stc: 10 .79 Steps ,.

" " h :as oe9 F, •' 52 0.7 PPCM

12:25:00 12:36:40

12/18/2009

. "

I 12:48:20

-"' ""

. ~

~

State4 10~.79 Steps

" 53~ .48 Deg F -3.75 PCM

13:00:00

tempco _ official.tco

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~PORT,CALHOUN STATION WORK TASK PORM FC1173Z REV. 8 W/0• 00316182 01 PAGE• 1

FACILITY: FC FORT CALHOUN

UNIT ' 1 PROJECT NO. , FCRTBLNKT TASK STATUS: READY ll!la[k Q[d£l[ ~ackage JOB TYPEo ST PRIORITY~ ST TASK DISPLN' RE

PLANNER ' X7129 HARTWELL H L 00316182 01 0

TASK TITLE: MODERATOR TEMPERATURE COEFFICIENT MEASUREMENT

cc, 842 ACTo NUER02 un, ACCTo 530 MASTER

OUTAGEo 2009RFO ORIGINATING W/Oo ECo

W/0 REFERENCE ' PMID/RQo 00000612 01 RPT ' TIPMClN

EARLY DATE: DUE DATEo 11/01/09 LATE DATEo DATE: 02/21/09

TASK NEED DATE: 11/01/09 EQUIPMENT TAGo RERX0002

EQUIP NAMEo MODERATOR TEMPERATURE COEFFICIENT MEASUREMENT 11111111111111111111111111111111111111111111111111111111111111111 WORK ITEM:

:I:echiJjcaJ 2Jannjng Beg:njt:ements WORK TASK REQUIREMENTS

SYSTEMo RC LOCATIONo

FREQ.: 101 DWT: y WI: TS: SR: EP: PLANT MODE REQ: 1

EEQo N CIBo N IST: N SAFETY CLASSo SEISMIC: PEG: 0011 UCRo FCK

CODE/STD1o FID Criticality: PM/ST TREND REQo N

PLANNING REQUIREMENTS

PARTSo N SCAFFOLDING' N FIRE WATCH: N GEI-SS: C/R ACCESS REQo N

FME: N TAGOUTo N G-87, REWORK: INS REMOVAL REQ: N SPEC LIFT REQo

CONFINED SPACE PERMIT: N FP IMPAIRMENT PERMIT: N FLAME PERMIT: RWP: N AWP:

CONT ENTRY PERMIT: N WELDING PERMIT: HEAT STRESSo N FIELD CHEM PERMIT: N FC-9B REQo N

DOCUMENT REFERENCES

RE-ST-RX-0002

WORK SCOPE

COMPLETE RE-ST-RX-0002

POST MAINTENANCE TEST REQOIREME~S

OPERABILITY TEST REQUIREMENTS

PLANNER: HARTWELL SYSTEM ENGINEERo BARE, MARK M EXT: 6757

E:r::e-:rag Release WORK RELEASED BY: RELEASED TOo

DATE: TIMEo PRE-TAG WORK LIMITATIONS'

Sbj ft Manag:ez:: Bel ease CLEARANCE NBR , ESTABLISHED BY:

DATEo TIMEo

SHIFT MGR RELEASEo RELEASE TOo

DATEo TIMEo

LCO(YES/NO)' REQUIRED RETURN TO SERVICE DATE: TIME:

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•• I ·• •'t . ~

FORT CALHOUN STATION FORM

(tJ

SURVEILLANCE TEST COVERSHEET

/

FC-1115A R7

1~111~ 1 ~~~~~~~~~~~~~~~~~~~~111m Surveillance Test Number: RE-ST-RX-0003 Work Order Package No: 00316236 01

Title: Moderator Temperature Coefficient Determination Using Center Cea

Due Date: 1/10/10 Early Date: I Drop Date: I Frequency: 301 EEQ: Scaffold: N I TrendinQ: N RWP: N Tagout: N IPMID: 00000613 Special Conditions:

\

1 .. Reason for Test (if other than scheduled):

2. Postponement explanation (if required):

Expected Completion: I Supervisor or System Engineer: Date:

3. Test results acceptable? ('f.J Yes [ ] No

Tech Specs satisified? (Not required for acceptable test) [ ] Yes [ ] No

Supervisor or System Engineer: ~ t7 /. /l Date: 1/ID/!0 Time: (tfDI Additional Code analysis required within 72 hours? [ ] Yes I [ ] No I [l(] N/A

STA Initials: -¥1-t> Date: 1j10 f,. Responsible System Engineer: BARE, MARK M ' 4. ST Coordinator initial test review Initials: Jit Date: /-1 Z '(/.)

WO required? [ ] Yes ,

()<J No

Frequency Increased? [ ] Yes (XJ No CR required? [ ] Yes [';{No

Retest required? [ ] Yes [/'}-No

System Engineer test review: N Initials: Date:

1ST Coordinator test review: Initials: Date:

ST Coordinator final test closeout review: Initials: "" Date: 1-J'NrJ

(SO-G-23)

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••

Fort Calhoun Station Unit No. 1

RE-ST -RX-0003

SURVEILLANCE TEST

PAGE 1 OF 17

MODERATOR TEMPERATURE COEFFICIENT DETERMINATION USING CENTER CEA

Change No. EC 47997

Reason for Change Added ROD BLOCK as an expected alarm. Prerequisite for running charging pumps changed to allow flushing. Prerequisite to verify TS 2.1 0.4(5)(a) revised to remove reference to Gardel being inoperable. Prerequisite for bypassing CVCS ion exchangers changed to remove the optional bypassing at shift manager's discretion. Changed note prior to Step 7.9 to remove using XC105 to maintain power constant and added further guidance on Delta-T power. Added a note prior to step 7.20 concerning the need to reset VHPT when restoring power. Revised step 7.24 concerning the Load Limit Potentiometer.

Requestor B. Schawe

Preparer L. Hautzinger

Issue Date 12-21-09 3:00pm

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 2 OF 17

MODERATOR TEMPERATURE COEFFICIENT DETERMINATION USING CENTER CEA

SAFETY RELATED

1. PURPOSE

1.1 To satisfy, at any power level within 500 MWD/MTU of initial operation after each refueling, the requirements of Technical Specification 3.1 0(2)2 OR, at any power level within fourteen (± 14) Effective Full Power Days of reaching a Rated Power Equilibrium Boron Concentration of 300 ppm, the requirements of Technical Specification 3.1 0(2)3 for the Moderator Temperature Coefficient.

1.2 This test provides a means of determining the Moderator Temperature Coefficient from the Isothermal Temperature Coefficient.

2. REFERENCES/COMMITMENT DOCUMENTS

2.1 Technical Specifications:

• 2.1 0.2, Reactivity Control Systems and Core Physics Parameters Limits • 2.1 0.4(5), DNBR Margin During Power Operation Above 15% of Rated Power • 3.1 0, Reactor Core Parameters

2.2 Operating Instructions:

• 01-ERFCS-1, Emergency Response Facility Computer System (LAN) • 01-NI-2, In-Core Instrumentation Operability Requirements

2.3 SO-G-23, Surveillance Test Program

2.4 Ongoing Commitments

• AR 14801, LER 93-016

3. DEFINITIONS

None

4. TOOLS AND EQUIPMENT

None

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'. FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 3 OF 17

5. PRECAUTIONS AND LIMITATIONS

5.1 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

5.2 Technical Specification 2.1 0.2(9)a.ii allows for CEA 1 to be misaligned from Group 4 during performance of this test.

5.3 Rod Block Circuitry will prevent Rod Group 4 movement if CEA 1 is misaligned by more than 8 inches, therefore if Group 4 motion is required CEA 1 will have to be aligned with Group 4 to allow movement.

5.4 Pressurizer Level will follow T avg and may result in a back up Charging Pump start on low level.

5.5 Pressurizer level changes will affect VCT pressure, which may adversely affect Reactor Coolant Pump bleed-off pressure and temperature. Close monitoring of bleed-off temperature and/or pressure is advised during the performance of this test.

5.6 Axial Shape Index (AS I) should be monitored to ensure ASI Limits are not exceeded during CEA movement.

5.7 The following guidelines will apply when changing parameters for testing:

• T cold decrease of approximately 1 o•F or Generator Electrical Load decrease of 24 to 26 MWe

• CEA 1 has been inserted 80 inches from its initial position

5.8 Anytime the Mode Selector Switch is in any position other than OFF, all available rod position indications shall be monitored - Syncros, SCEAPIS, ERF (page 302), and Core Mimic. [AR 14801]

5.9 If a CEA position abnormality occurs verify the position of all CEAs. [AR 14801]

5.10 When CEAs are not being moved, the Rod Control Mode Selector Switch shall always be left in the OFF position.

5.11 The Reactor Engineer shall be notified within 24 hours of the completion of this test of any unexpected results.

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST -RX-0003 PAGE 4 OF 17

5.12 The following annunciator windows will be affected by the performance of this procedure:

• CEDM GROUND (CB-4, A7, D-1L)""'/ • ROD DRIVE POWER INTERRUPT (CB-4, A8, A-5U) ./ • ROD POSITION DEVIATION LOW LIMIT (CB-4, A8, B-1U) ~ • ROD POSITION DEVIATION LOW-LOW LIMIT (CB-4, A8, B-1L) ,--• PDIL GR 4 COMPUTER (CB-4, A8, B-3L) ~ • PPDIL GR 4 COMPUTER (CB-4, A8, B-4L) / • REACTOR REGULATING SYSTEM LOOP 1 TREF/TAVG GROSS DEV (CB-4,_..........

A8, D-1U) • REACTOR REGULATING SYSTEM LOOP 1 & 2 TAVG DEV (CB-4, A8, C-1L) ./ • REACTOR REGULATING SYSTEM LOOP 2 TREF/TAVG GROSS DEV (CB-4, /

A8, D-1 L) • NUCLEAR t:..T POWER CHANNEL DEVIATION (CB-4, A20, E-6) / • VOLUME CONTROL TANK LEVEL HI-LO (CB-1/2/3, A2, B-2U) ~ • PRESSURIZER PRESSURE OFF NORMAL HI-LO CHANNEL X (CB-1/2/3, A4.~

A-4) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO A/P1 02X /

(CB-1/2/3, A4, A-7) • PRESSURIZER LEVEL HI-LO CHANNEL X (CB-1/2/3, A4, A-8) / • PRESSURIZER PRESSURE OFF NORMAL HI-LO CHANNEL Y (CB-1/2/3, A4:

B-4) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO B/P102X /

(CB-1/2/3, A4, 8-7) • PRESSURIZER LEVEL HI-LO CHANNEL Y (CB-1/2/3, A4, 8-8) / • PRESSURIZER SURGE LINE TEMP LO (CB-1/2/3, A4, C-1) ,-----• PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO C/P102X /

(CB-1/2/3, A4, C-7) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO D/P102X ,.__./'

(CB-1 /2/3, A4, D-7) • HEATER DRAIN TANK LEVEL HI-LO (CB-10/11, A11, B-3U) ..--• Various EXTRACTION STEAM PRESSURE ALARMS (ERF)

5.13 The following DCS alarms will be affected by the performance of this procedure:

• PPDIL • PDJL • DEV • ROD BLOCK

5.14 Do NOT allow Steam Generator pressure to fall below 770 psia.

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FORT CALHOUN STATION RE-ST-RX-0003 SURVEILLANCE TEST CONTINUOUS USE PAGE 5 OF 17

6. PREREQUISITES INITIALS/DATE

6.1 Procedure Revision Verification:

Revision No. ).I "ttt 1 t/tofo

6.2 No other test is in progress which could potentially affect this test, ~ or if this test were performed, could have an effect on that test. ltLt~hD

' 6.3 Group 4 is inserted to 11 0" ± 5 inches. ~ I !UCJ/;o

6.4 Reactor Power is at least 5% below the power level at which fuel ~ has been preconditioned or as directed by the Reactor Engineer. /IUo~o

6.5 lncore Detectors are operable and monitoring Linear Heat Rate ?& 1 1 /to}v for power levels above 5%.

6.6 The Reactor is at Equilibrium Xenon condition for the current 7l6k I t/,o/tc power level (AS I = ESI ± 0.005 for the last 6 hours).

6.7 All available Charging Pump Packing Cooling Pumps have been 'if/; I I U&/;o running for 30 minutes.

6.8 All available Charging Pumps have been run or flushed to ensure the piping for each pump contains water at the same Boron (#;

1 L1ofo Concentration as the RCS. I

6.9 The Energy Marketer has been notified that fluctuations in Station 'lit 1 fl,of,. Output will occur as a result of this test.

6.10 RCS and Pressurizer Boron Concentration are within 20 ppm or Pressurizer Heater and Spray Operation has been maximized for

lMr at least 24 hours. I J(,o/to

6.11 An additional Licensed Operator is available for manual control of ~ systems during the test. I I {Jo}/o

6.12 A briefing per SO-G-92 has been conducted prior to the start of fL 1 ,[!ofw'o this test. SO-G-92 1

Briefing Manager

6.13 A pre job briefing has been conducted prior to the start of this test. )66 !1/lo/to

6.14 Verify the requirements of Technical Specification 2.1 0.4(5)(a) A&_ "/r~J .. will be met during the performance of this test. RE ra

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

6.15 RCS Zinc Injection is secured.

6.16 Obtain Predicted Fuel Temperature Coefficient (FTC) from Reactor Performance Analysis (RPA):

-/. 3/ X I o - S /J.pfDF

6.17 Obtain Summary of Coefficient and Perturbation Calculations (RPA) illustrating:

• MTe Bias • Predicted MTe (-10'F perturbation) • Predicted MTe (-5'F perturbation)

6.18 Ensure eves lon Exchangers are bypassed during the performance of this test.

6.19 Manual control of Letdown should be taken during the performance of this test at Shift Manager's discretion. N/A if not desired.

6.20 Shift Manager authorizes performance of this test:

RE-ST -RX-0003 PAGE 6 OF 17

/6..b I J/;o//D

Shift Manager--~-----==---=:...._ ____ Date/Time 1-I0-/0 I ~810 7. PROCEDURE

NOTE: Step 7.1 can be performed at anytime and repeated as necessary.

7.1 If this Surveillance Test is turned over, a prejob briefing must be conducted prior to the continuation of this test.

7.2 At the RPSeiP DVM display the following parameters:

• RCS Cold Leg Temperature • ATPower

NOTE: Attachment 9.2 shows the points that are normally in Trend Block 11.

7.3 Note the current time generating the TB 11 Group Trend Report later in this procedure.

Time ()'if 15'

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 7 OF 17

NOTE: Disabling of Insertion Duration Limit Program on ERF Computer requires a Level 4 (Operations) Security Level or greater.

7.4 To ensure unnecessary Insertion Duration Limit program MW Thermal Alarms are not accumulated, change the CEA Program Control "Program Mode" to "TEST" on ERF Page CLU. Jl40

7.5 Ensure following CEA System Switches are placed in required position:

Switch Required

CEA Group Selector GP 4

Individual CEA Selector 1

7.6 Record latest RCS Boron Concentration

-'--'/ o"'--"-z_;_.f __ ppm

7. 7 Record As Found position of Turbine Load Limit Pot.

7.8 Complete Attachment 9.1 (Variable Tavg Test Record).

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 8 OF 17

NOTE: When lowering the RCS Cold Leg Temperature (Tcold) in Step 7.9, Step 7.10 will be used to maintain a constant 11 T Power (± 0.2%) with CEA 1. 11 T Power fluctuates considerably, so target the final value to be nominally within 0.2% of the initial value.

NOTE: Experience has shown that adjusting the Turbine Load Potentiometer at a rate of two notches per 30 seconds provides the best control for this test. Additionally, when approaching each endpoint, the rate should be reduced to 1 notch every 20 seconds.

CAUTION During the test, Makeup to the Volume Control Tank should be maintained at the same Boron Concentration as that prior to testing.

CAUTION Pressurizer Level will follow changes in Tavg even when power remains constant.

CAUTION Axial Shape Index should be monitored during CEA movement to ensure that ASI Operating Limits are not exceeded.

CAUTION Do NOT allow Steam Generator pressure to fall below 770 psia.

7.9 With the Turbine Control Valves, lower the RCS Tcold until:

• Tcold has been reduced by 10oF OR

• CEA 1 has been inserted 80 inches from its initial position OR

• Steam Generator Pressure reduces to 770 psia

7.10 During reduction ofT cola maintain Loop /1T Power constant by inserting CEA 1, in Manual Individual Mode.

7.11 WHEN reduction in Tcola is complete and Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

NOTE: Step 7.12 is not applicable if Tcold is to be returned to the initial temperature immediately.

7.12 Prior to increasing Tcola. complete Attachment 9.1 (Variable Tavg Test '-I, Record). --"-I.:;_ tfbM_

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 9 OF 17

NOTE: Steps 7.13 and 7.14 are performed concurrently.

7.13 With the Turbine Control Valves, raise RCS Tcold to its normal temperature.

7.14 When raising Tcold. maintain L'>. T Power at a constant value by withdrawing CEA 1, in Manual Individual Mode.

7.15 WHEN Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

7.16 If requested by the Reactor Engineer, perform Steps 7.9 through 7.15 for additional data.

NOTE: During the reduction of the Generator Electrical Load in Step 7.17, Step 7.18 will be performed to maintain Tcold constant(± 0.2°F) with CEA 1.

NOTE: Experience has shown that adjusting the Turbine Load Potentiometer at a rate of two notches per 30 seconds provides the best control for this test. Additionally, when approaching each endpoint, the rate should be reduced to 1 notch every 20 seconds.

7.17 With the Turbine Control Valves, reduce Generator Electrical Load until:

• Generator Electrical Load (MWe) has been reduced by 24 to 26 MWe

OR • CEA 1 has been inserted 80 inches from its initial position

7.18 When lowering Generator Load, maintain T cold constant by inserting CEA 1, in Manual Individual Mode.

7.19 WHEN the reduction in Generator Load is complete and Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

NOTE: Steps 7.20 and 7.21 are performed concurrently.

NOTE: While restoring power to the initial load, reset VHPT as required.

CAUTION Do not exceed 100% of Rated Power OR the Administrative Power Limit when this test is being performed at 100% power.

7.20 With Turbine Control Valves, increase Generator Load to the initial '.J." load. I6JI

R27

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 10 OF 17

7.21 WHEN raising Generator Load, THEN maintain Tcold at a constant value 'f6 by withdrawing CEA 1, in Manual Individual Mode. _1 __ _

7.22 WHEN Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

7.23 If requested by the Reactor Engineer, perform Step 7.17 through 7.22 for additional data.

7.24 Ensure Turbine Load Limit Pot is in As Found position recorded in Step 7. 7 or in a position for stabilizing the plant.

7.25 If necessary, align CEA 1 to the Group 4 position, in Manual Individual Mode.

7.26 On ERF Page CLU, change the CEA Program Control "Program Mode" back to OPERATE.

7.27 IF not needed for further testing, THEN on ERF Computer Page GTR, generate a Group Trend Report as follows:

7.27.1 Adjust date and times to encompass the time recorded in Step 7.3 to the current time. Values must be entered in the specified format.

7.27.2 Configure the interval to "one minute" and printer as desired.

7.27.3 Depress button "TB11" and verify report was successful.

8. RESTORATION

8.1 Energy Marketer notified of test completion.

8.2 Calculate MTC value using Attachment 9.3.

8.3

'fbL- 1 r/1 olro

~ I tlj r~/lfl Shift Manager notified th®?leted.

Shift Manager Q) Date/Time 1-!<J-10 1/0S;

R27

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 11 OF 17

8.4 Attach following to test package:

• All Variable Tavg Test Record Sheets [v{ • Calculations performed to determine Moderator · /

Temperature Coefficient 11:}

• Any Graphs used in calculation J, • Rod Group Log printouts [[._.,} • Group Trend TB11 printout ./] • Any Trend Recorder Graphs designated by the Reactor ~~eer 1-"1

Completed by / ~~ Date/Time

9.

10.

ATTACHMENTS

9.1 Variable Tavg Test Record

9.2 Points in Trend Block 11

9.3 MTC Calculation

9.4 Comment Sheet

ACCEPTANCE CRITERIA

10.1 No abnormalities in data or test conditions recorded on the Comment Sheet.

10.2 The value of Moderator Temperature Coefficient is:

- 9. "'"' '/10. ~p/"F (Attachment 9.3, Step 9)

1 0.2.1 Less positive than +0.2x1 o·4 fl.p/"F including uncertainties for power levels at or above 80% of rated power.

1 0.2.2 Less positive than +0.5x1 o·4 fl.p/"F including uncertainties for power levels below 80% of rated power.

1 0.2.3 More positive than the value specified in the COLR including uncertainties at rated power.

R27

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 12 OF 17

11. PERFORMANCE AND REVIEW

11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours of completion of this test.

. . Evaluatedby Q-o/u, 6tAAJ&)

STA Date/Time I ;/o//0 I 1.3'/7

} I

Reviewedby ~~ Shift Manager

Date/Time //10/trll I 'f (J I

11.2 The results of the Moderator Temperature test have been reviewed and are acceptable in accordance with Step 1 0.2.

Reactor Engine~&~~~~~.;t:.====-sn=::...... Date/Time tjtz/'g I d'jZ3

Supervisor-Nuclear Enginee · g _:;{ff)J.22:1:l&('l;;,'Ut.~:b Date/Time 1Az-/o I 11715""

11.3 The Plant Manager or des1gnee has reviewed Temperature Coefficient test.

Plant Manager -pc. \-... ~ QG.(I;\It\\cntr...c.h Date/Time {13{zc1-01 \000

11.4 If the test results do not meet the acceptance criteria, or at the Plant Manager's request, the Plant Review Committee has reviewed the results of the Moderator Temperature Coefficient test.

PRC Chairman N/ft po.r 1\.3 ~ ~\'"n-~~ Date/Time JJt~ I >QOO ~ T-. \,[ '-\~'<v~ • .Gl-.. 'i5Q ~\3f2.0l.O

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Page 91: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.1 -Variable T AVG Test Record

TIME r$17 DATE I /JD/wrt; STEP NO. 7'6 RECORD SHEET

RE-ST -RX-0003 PAGE 13 OF 17

I OF _.2._ --

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

CfftJ, 'IS' % 6TPOWER

Cf? 0 1?-- S' % RPSCIP DVM: rr;., % % AI-31A Al-31 8 Al-31 C Al-310

9/p_. 7-% Cf73% CflS % 9'<6,2. % ~ AI-31A Al-31 8 AI-31C AI-31D

7w.S % cp. g% Cftp, t % '1?. ~ % AI-31A Al-318 Al-31 C Al-310

5'4-1.[ °F TcoLo

~tf2.S OF '?'l(,h OF RPSCIP DVM: f'fO,t; °F AI-31A Al-31 8 Al-31 C Al-31 D

'iLJL 0 °F 5''/o, h °F ~L/ 2· fooF 'i t./1-- (p Of AI-31A Al-318 AI-31C Al-310

'it1/. 3 OF 'i'</0.$ OF 'il/2 .5 OF f</1, 7 OF

AI-31A Al-31 8 Al-31 C AI-31D

5'3S, 7 OF THOT

5~~.'!_ ')"'g, 5 RPSCIP DVM: 7~-7 OF OF OF

AI-31A Al-31 8 AI-31C AI-31D

Nl POWER

RPSCIP DVM: Cf7.'6'% 'f'O. 2 % 97.~ % '17:i) % AI-31A Al-318 AI-31C Al-310

-o. oo?Z. ASI

RPSCIP DVM: -().00(;/:/ -o, OQ'/b -0,0052 AI-31A Al-31 8 Al-31 C Al-310

CEA Group Position Rod Group Log Printout 0<g)... (a Time

Core Axial Shape Index ERF XC093 ~ 0, bO:t,Q2

Core Power ERF XC105 llf !oCf. 'iS MWth

Generator Load ERF Y3273 5zq, 23 rs MWe

RCS Boron Concentration Latest Analysis I Q&5 ppm

Completedby ~~ Date/Time I fro/to! O~Z./ j t

R27

Page 92: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One CUrrent Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 126.9 RR31 126.3 RR15 126.3 RR32 126.9 RR16 126.1 RR33 126.4 RR17 126.6 RR34 127.2 RR35 126.7 RR36 126.6 RR37 126.4

Group Positions: High, Average, Low,

Posn High Avg Low

Dev

Shutdown A

RR37 RR34

RR31

126.4 127.2 126.6 126.3

0.9

Shutdown B

RR17 126.6 RR14 126.9

126.5 RR16 126.1

O.B

Nontrip

RR1B 126.9 RR19 126.5 RR20 126.3 RR21 126.3

and Deviation

Nontrip

RR1B 126.9 RR1B 126.9

126.5 RR21 126.3

0.6

Sunday Jan 10, 20104S?

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR22 126.4 RR02 127.2 RR01 114.9 RROB 126.6 RR23 126.6 RR03 126.4 RR3B 114.2 RR10 126.6 RR24 126.7 RR04 127.1 RR39 114.7 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.9

RR26 126.4 RR41 114.7 RR27 127.0 RR2B 126.7 RR29 126.5

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR27 127.0 RR05 126.4 RR01 114.9 RROB 126.6 RR27 127.0 RR02 127.2 RR40 114.9

126.5 126.6 126.8 114.7 RR06 126.4 RR26 126.4 RR05 126.4 RR3B 114.2

0.3 0.7 0.9 0.7

s -1-er /.8'

Page 93: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable T AVG Test Record

TIME D)<25 DATE 1/l0/10 STEP NO. 7·ll RECORD SHEET ___1.__ OF ___2_

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

<=r7. I L).T POWER

93,0% rs.t_ RPSCIP DVM: % '1.2• (.11 % % AI-31A Al-31 B Al-31 C AI-31D

"J(p ,"/ % 97.S% Cj?, (o% 97J) % AI-31A Al-318 AI-31C AI-31D

9&,'6% Cj'(;,f.# % 1. 7. ~ % Cf<g, 2 % AI-31A Al-31 B AI-31C Al-31 D

RPSCIP DVM: S3'f, I OF TcoLo

533. tf OF 'i35. If OF '53'7 .5 OF

AI-31A Al-31 B AI-31C Al-31 D

r;34, 0 OF 533.5 OF c;J'i.t OF 'i31·5 °F AI-31A AI-31B AI-31C AI-31D

1)?>4' 0 OF S33.t OF '735.5 °F 'iY.() OF

AI-31A Al-318 AI-31C AI-31D

RPSCIP DVM: 5<£1 .CJ OF Ts»T 271../· OF 5'62.3 OF 7'6'"2 {"'OF

AI-31A Al-31 B AI-31C Al-31 D

Nl POWER

RPSCIP DVM: CJ~. D % Cjr;, 3 % Cf':t./1 % 'fLj, 7 % AI-31A Al-31 B AI-31C Al-310

f o.o lc;3 ASI

RPSCIP DVM: + o .o!t?CJ +O, 0/~CJ + o,o; 7/ AI-31A Al-318 AI-31C AI-31D

CEA Group Position Rod Group Log Printout 0'100 Time

Core Axial Shape Index ERF XC093 o, Ol3tp2S/

Core Power ERF XC105 I Lf73, 02 MWth

Generator Load ERF Y3273 52.~,C6~~ MWe

RCS Boron Concentration Latest Analysis 102.-5 ppm

~--;?~ Completed by :..-v ~ Date/Time J(!OLtl 1 o 7oJ

, -- ; ,

R27

Page 94: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One Current Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 126.9 RR31 126.3 RR15 126.3 RR32 126.9 RR16 126.1 RR33 126.4 RR17 126.6 RR34 127.2 RR35 126.7 RR36 126.6 RR37 126.4

Nontrip

RR18 126.9 RR19 126.5 RR20 126.3 RR21 126.3

Group Positions: High, Average, Low, and Deviation

Shutdown A Shutdown B Nontrip ------------ ------------ ------------

Posn RR37 126.4 RR17 126.6 RR18 126.9 High RR34 127.2 RR14 126.9 RR18 126.9 Avg 126.6 126.5 126.5 Low RR31 126.3 RR16 126.1 RR21 126.3

Dev 0.9 0.8 0.6

Sunday Jan 10, 2010~

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR22 126.4 RR02 127.2 RR01 70.2 RR08 126.6 RR23 126.6 RR03 126.4 RR38 114.2 RR10 126.6 RR24 126.7 RR04 127.1 RR39 114.7 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.9

RR26 126.4 RR41 114.7 RR27 127.0 RR28 126.7 RR29 126.5

Group 1 Group 2 Group 3 Group 4 ------------ ------------ ------------ ------------RR06 126.4 RR27 127.0 RR05 126.4 RR01 70.2 RR08 126.6 RR27 127.0 RR02 127.2 RR40 114.9

126.5 126.6 126.8 105.7 RR06 126.4 RR26 126.4 RR05 126.4 RR01 70.2

0.3 0.7 0.9 44.8

) l-ep 7' ll

Page 95: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable T AVG Test Record

TIME 0'13j DATE 1} ID/ 10 STEP NO. ] 112 RECORD SHEET _3._ OF 5" '

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

Cf7, I LHPOWER CJ7, I 9?,7 RPSCIP DVM: % 1]_7' <6 % % %

AI-31A Al-31 B Al-31 C Al-310

'n. 1 % Cf7, 0 % '70. (p % 97,~ % AI-31A Al-318 AI-31C Al-310

r~~~ % ct7. I % <f&, Lf. % '17,5 % AI-31A Al-31 B AI-31C Al-31 D

5'-1 I' 0 "F TcoLo

'i'/2 .7 "F P-!lt (p "F RPSCIP DVM: f}l/O,Cp "F AI-31A Al-31 B Al-31 C Al-31 D

>''-f/ • 2- "F 51.f0.] "F r;y z, I "F 7'1/ f, C{ "F AI-31A Al-318 AI-31C Al-310

r; tf/.{ "F 2'fO.(q "F r;yz, g "F fii.f /, f "F

AI-31A Al-31 B AI-31C Al-31 D

t;'£C6' ~ THaT tJ «<g .3 "F ')t'6/f RPSCIP DVM: "F 5'~2.'3 "F "F

AI-31A Al-31 B AI-31C Al-310

Nl POWER

RPSCIP DVM: 'f?.j_ % c;~./ % CfC6.0 % 97/l% AI-31A Al-318 AI-31C Al-310

ASI +O.Q'J!() RPSCIP DVM: -0, 0Qf6 -0 ,(}(), t - (}d}ll{/j

AI-31A Al-31 B AI-31C Al-31 D

CEA Group Position Rod Group Log Printout Q(tfO Time

Core Axial Shape Index ERF XC093 -O,otJLhsLf?( -

Core Power ERF XC105 /4-{t;{c; .? MWth

Generator Load ERF Y3273 sz 0, 03 0 MWe

RCS Boron Concentration Latest Analysis (OV ppm

Completed by~~ DatefTime I/ 10 (to I 01'i I

R27

Page 96: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One Current Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 126.9 RR31 126.3 RR15 126.3 RR32 126.9 RR16 126.1 RR33 126.4 RR17 126.6 RR34 127.2 RR35 126.7 RR36 126.6 RR37 126.4

Nontrip

RR18 126.9 RR19 126.5 RR20 126.3 RR21 126.3

Group Positions: High, Average, Low, and Deviation

Shutdown A Shutdown B Non trip ------------ ------------ ------------

Posn RR37 126.4 RR17 126.6 RR18 126.9 High RR34 127.2 RR14 126.9 RR18 126.9 Avg 126.6 126.5 126.5 Low RR31 126.3 RR16 126.1 RR21 126.3

Dev 0.9 0.8 0.6

5-lrr ),/.{'

Sunday Jan 10, 20~

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR22 126.4 RR02 127.2 RR01 114.5 RR08 126.6 RR23 126.6 RR03 126.4 RR38 114.2 RR10 126.6 RR24 126.7 RR04 127.1 RR39 114.7 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.9

RR26 126.4 RR41 114.7 RR27 127.0 RR28 126.7 RR29 126.5

Group 1 Group 2 Group 3 Group 4 ------------ ------------ ------------ ------------RR06 126.4 RR27 127.0 RR05 126.4 RR01 114.5 RR08 126.6 RR27 127.0 RR02 127.2 RR40 114.9

126.5 126.6 126.8 114.6 RR06 126.4 RR26 126.4 RR05 126.4 RR38 114.2

0.3 0.7 0.9 0.7

Page 97: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST -RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME /002 DATE II /O/to STEP NO. 7, I { RECORD SHEET ...1_ OF .L_

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

?z...z...% aT POWER

Cfz.7 '73,0 RPSCIP DVM: 13.$'% % % AI-31A Al-318 AI-31C AI-31D

CJz_.S % 9'3./ % 13.5 % '73-'1 % AI-31A Al-318 AI-31C AI-31D

'JZ, 't % '!? .'f % 92.1?% 1'3,~ % AI-31A Al-31 B AI-31C Al-31 D

'i'f t,L TcoLo

)':J.2/j_ OF 5i/rlf RPSCIP DVM: OF 'iWJ,(, OF OF

AI-31A Al-31 B Al-31 C AI-31D

fjlj ;;z_ OF ')'10.7 OF IJ'f2.3 OF Stf!S °F AI-31A Al-318 AI-31C Al-310

7 Lf /. 3, OF l}'fo. I oF '742.. 5 °F J}Lft: k °F AI-31A Al-318 AI-31C AI-31D

lJC(&;,cg THOT 'i'b?. 2._ OF $""~(o,S'oF RPSCIP DVM: OF 5g-?,1 °F

AI-31A Al-31 B AI-31C Al-31 D

Nl POWER

RPSCIP DVM: ''Ttl. 'f % 'ilf,(p % 71.f,2 % flf,l_ % AI-31A Al-31 B Al-31 C Al-310

-T 0.0/7? ASI

f-t!J,02oo RPSCIP DVM: -{-0 ,Qf'd'f -J-.(J, 0?_22 AI-31A Al-318 AI-31C Al-310

CEA Group Position Rod Group Log Printout 10/0 Time

Core Axial Shape Index ERF XC093 o, 0/&?2 '132

Core Power ERF XC105 1-fCfi,'ilf MWth

Generator Load ERF Y3273 C?OL.. $} (Q MWe

RCS Boron Concentration Latest Analysis /02--5 ppm

Completedby ~ Date/Time 1(!0/10 I lOll

R27

Page 98: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One CUrrent Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 126.9 RR31 126.3 RR15 126.3 RR32 126.9 RR16 126.1 RR33 126.4 RR17 126.6 RR34 127.2 RR35 126.7 RR36 126.6 RR37 126.4

Nontrip

RR18 126.9 RR19 126.5 RR20 126.3 RR21 126.3

Group Positions: High, Average, Low, and Deviation

Shutdown A Shutdown B Nontrip

Posn RR37 126.4 RR17 126.6 RR18 126.9 High RR34 127.2 RR14 126.9 RR18 126.9 Avg 126.6 126.5 126.5 Low RR31 126.3 RR16 126.1 RR21 126.3

Dev 0.9 0.8 0.6

Sunday Jan 10, 20106)

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR22 126.4 RR02 127.2 RR01 79.1 RROB 126.6 RR23 126.6 RR03 126.4 RR38 114.2 RR10 126.6 RR24 126.7 RR04 127.1 RR39 114.7 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.9

RR26 126.4 RR41 114.7 RR27 127.0 RR28 126.7 RR29 126.5

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR27 127.0 RR05 126.4 RR01 79.1 RR08 126.6 RR27 127.0 RR02 127.2 RR40 114.9

126.5 126.6 126.8 107.5 RR06 126.4 RR26 126.4 RR05 126.4 RR01 79.1

0.3 0.7 0.9 35.8

51-er /,//

Page 99: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST -RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable T AVG Test Record

TIME /0'2.-'t) DATE i/JO/tO STEP NO. 7, 1--£... RECORD SHEET ___2.._ OF _2_

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

~(o.fo% AT POWER

~'i. f.. 'f'i.[p RPSCIP DVM: ~!a.'J. % % % AI-31A Al-318 AI-31C AI-31D

10.7 % Cf(o,{p % /?,'f % Cftp, (p % AI-31A Al-31 B AI-31C Al-31 D

97, I % '1&. 7 % 7 r;; l.o % i&/1 % AI-31A Al-318 AI-31C Al-310

l)L/0.7 OF TcoLo

)'12/f OF 'S'/1/f OF RPSCIP DVM: rzyo.3 OF

AI-31A Al-318 AI-31C AI-31D

?t/O.J. OF tJ'lfo, Y OF t}LI?--Lf OF tilft i OF AI-31A Al-31 B AI-31C Al-310

r;yo.<b OF tJL/0.3 OF fJ'-12S OF 'i'IP/ OF AI-31A Al-31 B AI-31C AI-31D

t7~~.CJoF !HOT r; ~g-. I ,~,?oF RPSCIP DVM: 'i'f57. z_oF OF

AI-31A Al-318 AI-31C Al-31 D

Nl POWER

RPSCIP DVM: '17./ % 9?.h% 97, I % '17, I % AI-31A Al-31 B Al-31 C Al-310

ASI + O.{J()ZZ.. RPSCIP DVM: -0, ODI) -t-O .f.J{f() 0 1-0. 00/<j AI-31A Al-318 AI-31C AI-31D

CEA Group Position Rod Group Log Printout {033 Time

Core Axial Shape Index ERF XC093 ~ 6 • OO'JO'If§Z)

Core Power ERF XC105 !l/-b2, 2(o MWth

Generator Load ERF Y3273 tJ2'1rfiJ MWe

RCS Boron Concentration Latest Analysis tOZ-) ppm

Completedby ~ Date/Time tfliJ/r(J 1 I 0 3..3

R27

Page 100: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One Current Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 126.9 RR31 126.3 RR15 126.3 RR32 126.9 RR16 126.1 RR33 126.4 RR17 126.6 RR34 127.2 RR35 126.7 RR36 126.6 RR37 126.4

Group Positions: High, Average, Low,

Shutdown A Shutdown B

Posn RR37 126.4 RR17 126.6 High RR34 127.2 RR14 126.9 Avg 126.6 126.5 Low RR31 126.3 RR16 126.1

Dev 0.9 0.8

Nontrip

RR18 126.9 RR19 126.5 RR20 126.3 RR21 126.3

and Deviation

Non trip

RR18 126.9 RR18 126.9

126.5 RR21 126.3

0.6

Sunday Jan 10, 2016

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR22 126.4 RR02 127.2 RR01 114 .s RR08 126.6 RR23 126.6 RR03 126.4 RR38 114.2 RR10 126.6 RR24 126.7 RR04 127.1 RR39 114.7 RR12 126.4 RR25 126.5 RROS 126.4 RR40 114.9

RR26 126.4 RR41 114.7 RR27 127.0 RR28 126.7 RR29 126.5

Group 1 Group 2 Group 3 Group 4

RR06 126.4 RR27 127.0 RROS 126.4 RR01 114 .s RR08 126.6 RR27 127.0 RR02 127.2 RR40 114.9

126.5 126.6 126.8 114.6 RR06 126.4 RR26 126.4 RROS 126.4 RR38 114.2

0.3 0.7 0.9 0.7

sl-er 7, Z.2

Page 101: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.2- Points in Trend Block 11

0 T0111C 0 T0111H 0 T0121C 0 T0121H

0 P0103Y 0 L0101X 0 L0101Y 0 F0114A

0 P0905A • P1046 0 P1048 0 L0903Y

0 P0946A • Y3273 • XC093 0 XC105

0 AR002X 0 AR002Y 0 BR002X 0 BR002Y

0 CR002Y 0 DR002X 0 DR002Y 0 R0003X

0 R0004X • R0004Y

0

0

0

0

0

0

RE-ST -RX-0003 PAGE 14 OF 17

P0103X

P0902A

L0906Y

XC411

CR002X

R0003Y

R27

Page 102: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 15 OF 17

Attachment 9.3- MTC Calculation

1. Calculation of Tcold(initial)

Data from Variable Tavg Test Records.

f'f/.5 Avg. T cold from Step 7.8 + ['{/. {?Avg. Tcold from Step 7.15

Tcold(initial) = --------------;:-------------2

Tcold(initial) = 'J 'f f, 5

2. Determination of Tcold(final)

Tcold(final) = 57'/• 1 Avg. Tcold from Step 7.12 (Variable Tavg Test Record)

3. Calculation of .II. Tcold

.II. T cold = 'fYl' £ T cold(initial) - 'iJ <f. '/ Tcold(final)

.II. T cold = 7t/

4. Calculation of Inserted Rod Worth (initial)

Data from Rod Group Log Printouts.

Jltf,7 CEA4-1 Position (Step 7.8) + II'{.S CEA4-1 Position (Step 7.15)

2

= lft.-f,7 Average Initial CEA 4-1 Position

-'f o!oD,,tl lf.. 'f./0 Inserted Rod Worth (initial) from CEA 4-1 Integral Rod Worth Curve

5. Determination of Inserted Rod Worth (final)

Data from Rod Group Log Printout.

= 70. 2.- Final CEA 4-1 Position (Step 7.12)

- O.D777~ ~t;ferted Rod Worth (final) from CEA 4-1 Integral Rod Worth Curve

R27

Page 103: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.3- MTC Calculation

6. Calculation of t.p

- (), 07'!7'1 Inserted Rod Worth (final)

- '1110-Y Inserted Rod Worth (initial)

%t.p =-o,07'ti'l%t.p wo-"

t.p =- 7• ?7'1 [%t.p 1100% (inserted worth)]

7. Calculation of Measured lTC

-7, 99'/Y.IO -'ft.p

I ], I t.Tcold

lTC = -/dJ 't10-'f

8. Determination of Predicted FTC

RE-ST-RX-0003 PAGE 16 OF 17

- !.31 '/.I0- 5 t.pJOF Predicted Fuel Temperature Coefficient (Prerequisite 6.16)

9. Calculation of MTC

Measured lTC

- (- J,3f'f.lo-f t.pJOFl Predicted FTC

MTC = - (, ~9 'l./0 -S (transfer to Step 1 0.2)

Completed by

Review~< -<

Date/Time 1/t oho I I o '1'/ I I

R27

Page 104: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.4 - Comment Sheet

RE-ST-RX-0003 PAGE 17 OF 17

R27

Page 105: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

REPORT• ** TBll ** was requested on **10-JAN-10 10:39:49.5**

DATE/TIME *TOlllC* *TOlllH* *T0121C* *T0121H* *P0103X* *P0103Y* *LOlOlX* *LOlOlY* *F0114A* *P0902A* *DEG F * *DEG F * *DEG F * *DEG F * *PSIA * *PSIA * * % * * % * * % * *PSIA *

10-JAN-10 08 15 00.0 542.885 591.022 541.653 590.861 2099.559 2099.960 60.026 59.555 105.969 825.020 10-JAN-10 08 16 00.0 542.905 591.172 541.542 589.730 2099.660 2099.960 60.026 59.555 105.343 825.220 10-JAN-10 08 17 00.0 543.045 591.192 541.643 590.561 2099.760 2099.158 60.026 59.455 106.080 824.820 10-JAN-10 08 18 00.0 542.835 590.621 541.542 590.811 2099.960 2099.359 60.126 59.575 106.149 825.220 10-JAN-10 08 19 00.0 542.714 589.710 541.542 590.551 2099.559 2100.160 60.096 59.575 105.969 825.020 10-JAN-10 08 20 00.0 543.095 590.080 541.542 590.982 2100.561 2100.260 60.096 59.575 105.538 824.820 10-JAN-10 08 21 00.0 542.864 590.611 541.643 590.651 2100.260 2100.260 60.096 59.575 104.698 825.220 10-JAN-10 08 22 00.0 542.975 590.200 541.643 590.270 2100.160 2099.259 60.096 59.575 106.052 825.421 10-JAN-10 08 23 00.0 542.975 590.230 541.542 590.741 2100.361 2100.361 60.096 59.575 105.468 824.820 10-JAN-10 08 24 00.0 542.945 589.820 541.542 590.771 2099.259 2099.459 60.096 59.575 105.996 825.120 10-JAN-10 08 25 00.0 542.935 589.649 541.542 591.062 2100.060 2099.459 60.096 59.575 105.538 825.421 10-JAN-10 08 26 00.0 542.945 591.462 541.643 590.341 2100.060 2099.559 60.096 59.575 105.621 825.020 10-JAN-10 08 27 00.0 542.805 590.681 541.542 589.830 2100.461 2100.361 60.096 59.575 104.333 825.321 10-JAN-10 08 28 00.0 543.035 590.821 541.643 591.242 2099.660 2099.259 60.096 59.575 104.769 824.820 10-JAN-10 08 29 00.0 542.945 590.611 541.542 590.220 2099.860 2100.461 60.096 59.575 105.468 825.621 10-JAN-10 08 30 00.0 542.945 590.691 541.542 590.861 2099.860 2099.459 60.096 59.575 105.147 825.120 10-JAN-10 08 31 00.0 542.955 590.951 541.643 590.431 2099.860 2100.060 60.096 59.575 105.343 825.321 10-JAN-10 08 32 00.0 542.824 590.140 541.643 590.601 2099.760 2100.060 60.096 59.575 105.315 825.120 10-JAN-10 08 33 00.0 542.805 591.082 541.542 589.640 2099.760 2100.060 60.096 59.575 105.021 824.920 10-JAN-10 08 34 00.0 542.734 590.661 541.643 590.311 2098.157 2098.858 59.986 59.475 105.913 824.319 10-JAN-10 08 35 00.0 542.504 589.680 541.182 590.711 2097.055 2096.455 59.685 59.275 105.816 821.114 10-JAN-10 08 36 00.0 542.153 590.671 540.842 590.411 2095.953 2095.953 59.135 58.754 105.524 817.508 10-JAN-10 08 37 00.0 541.332 590.320 540. 050 589.369 2096.755 2097.456 58.243 57.802 106.591 811.298 10-JAN-10 08 38 00.0 540.641 588.127 539.339 588.027 2096.755 2096.254 57.362 57.021 105.913 804.788 10-JAN-10 08 39 00.0 539.609 586.614 538.447 587.807 2097.957 2097.356 56.961 56.470 106.467 800.280 10-JAN-10 08 40 00.0 539.179 587.516 538.117 586.835 2098.057 2098.457 56.851 56.370 105.301 797.276 10-JAN-10 08 41 00.0 538.708 585.543 537.546 587.356 2100.961 2101.062 56.971 56.470 105.719 793.269 10-JAN-10 08 42 00.0 538.447 586.374 537.205 585.723 2102.764 2103.065 57.983 57.532 105.983 791.166 10-JAN-10 08 43 00.0 537.987 586.755 536.765 585.863 2101.662 2101.162 58.824 58.423 105.203 788.361 10-JAN-10 08 44 00.0 538.007 585.663 536.414 586.244 2102.764 2102.164 59.726 59.295 106.633 785.857 10-JAN-10 08 45 00.0 537.496 585.263 536.184 585.643 2101.563 2101.162 60.367 59.976 106.080 784.255 10-JAN-10 08 46 00.0 537.396 585.553 536.074 585.362 2101.563 2101.062 61.038 60.627 105.426 781.851 10-JAN-10 08 47 00.0 537.015 584.331 535.753 585.152 2100.060 2099.158 61.468 61.108 106.798 780.248 10-JAN-10 08 48 00.0 537.035 583.780 535.633 584.722 2096.254 2096.855 61.068 60.687 106.439 778.846 10-JAN-10 08 49 00.0 536.574 585.563 535.292 584.832 2096.755 2096.855 60.747 60.367 105.830 777.644 10-JAN-10 08 50 00.0 536.094 584.892 534.962 583.770 2096.655 2097.656 60.226 59.916 105.049 775.441 10-JAN-10 08 51 00.0 536.164 584.171 534.852 584.251 2097.857 2097.656 60.026 59.615 105.147 774.039 10-JAN-10 08 52 00.0 535.953 584.962 534.621 584.501 2099.059 2098.758 59.926 59.415 105.816 773.037 10-JAN-10 08 53 00.0 535.833 584.781 534.722 583.269 2099.158 2099.960 59.926 59.415 106.536 773.638 10-JAN-10 08 54 00.0 535.873 583.650 534.621 583.570 2099.660 2099.960 59.926 59.415 106.674 772.336 10-JAN-10 08 55 00.0 536.024 584.181 534.611 583.580 2099.259 2099.860 59.826 59.415 105.816 772.436 10-JAN-10 08 56 00.0 535.793 585.072 534.501 584.301 2099.259 2099.760 59.936 59.415 106.356 772.336 10-JAN-10 08 57 00.0 535.913 585.322 534.601 584.201 2099.259 2099.459 59.936 59.415 106.038 772.837 10-JAN-10 08 58 00.0 536.094 584.902 534.601 584.171 2099.459 2099.459 59.936 59.415 106.080 772.636 10-JAN-10 08 59 00.0 535.783 584.181 534.491 583.760 2099.559 2099.660 59.936 59.415 106.743 772.837 10-JAN-10 09 00 00.0 535.924 584.722 534.491 582.868 2099.559 2099.660 60.036 59.515 106.232 772.736 10-JAN-10 09 01 00.0 535.903 584.411 534.592 583.910 2099.459 2099.660 60.036 59.515 105.593 772.636 10-JAN-10 09 02 00.0 535.803 584.331 534.592 583.009 2098.958 2098.958 60.036 59.515 106.343 772.837 10-JAN-10 09 03 00.0 535.793 585.202 534.491 584.161 2098.958 2098.958 60.036 59.515 105.538 772.736 10-JAN-10 09 04 00.0 535.884 584.451 534.491 584.401 2099.158 2100.060 60.036 59.615 106.107 772.336 10-JAN-10 09 05 00.0 535.783 583.580 534.501 584.101 2100.461 2100.361 60.146 59.615 106.080 773.137 10-JAN-10 09 06 00.0 536.174 583.620 534.601 583.910 2100.361 2099.960 60.256 59.716 106.107 773.938 10-JAN-10 09 07 00.0 536.074 584.832 534.922 584.091 2100.160 2099.459 60.427 59.956 107.251 776.242 10-JAN-10 09 08 00.0 536.524 585.212 535.022 584.101 2099.359 2099.059 60.547 60.056 106.204 776.943 10-JAN-10 09 09 00.0 536.695 584.571 535.232 584.441 2099.359 2100.160 60.657 60.256 105.580 778.145 10-JAN-10 09 10 00.0 536.925 585.242 535.333 585.102 2100.461 2101.162 61.018 60.567 106.010 780.549 10-JAN-10 09 11 00.0 536.925 585.403 535.543 584.581 2099.459 2098.958 61.018 60.567 106.757 781.651 10-JAN-10 09 12 00.0 537.396 585.373 535.773 584.972 2099.459 2098.758 61.118 60.667 105.524 783.454

Page 106: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

10-JAN-10 09 13 00.0 537.726 585.272 536.104 585.493 2098.357 2098.658 61.118 60.667 105.913 784.956 10-JAN-10 09 14 00.0 537.636 585.803 536.314 585.152 2098.357 2098.658 61.248 60.777 106.121 786.559 10-JAN-10 09 15 00.0 537.987 584.872 536.424 586.054 2099.359 2098.658 61.248 60.777 105.133 788.161 10-JAN-10 09 16 00.0 538.197 586.695 536.645 585.763 2099.059 2099.559 61.448 60.988 106.564 790.665 10-JAN-10 09 17 00.0 538.428 586.515 537.205 586.064 2100.160 2099.559 61.649 61.188 105.566 793.770 10-JAN-10 09 18 00.0 538.768 586.564 537.416 586.134 2099.660 2099.559 61.859 61.288 104.614 796.775 10-JAN-10 09 19 00.0 538.978 586.424 537.656 586.054 2099.860 2099.559 61.859 61.388 105.774 799.279 10-JAN-10 09 20 00.0 539.910 587.145 538.237 587.065 2100.160 2100.861 62.200 61.699 105.133 803.285 10-JAN-10 09 21 00.0 540.431 587.496 538.798 587.937 2102.164 2102.764 62.640 62.129 106.522 808.093 10-JAN-10 09 22 00.0 541.022 588.598 539.640 587.887 2099.459 2099.459 63.031 62.600 106.052 813.702 10-JAN-10 09 23 00.0 541.562 589.249 540.210 589.509 2100.361 2100.661 63.442 63.001 104.993 818.710 10-JAN-10 09 24 00.0 542.564 590.210 541.002 589.640 2101.863 2101.662 64.012 63.522 105.398 824.519 10-JAN-10 09 25 00.0 543.155 591.002 541.703 589.739 2098.457 2098.558 63.902 63.522 104.502 828.025 10-JAN-10 09 26 00.0 543.175 590.521 541.913 591.142 2096.455 2096.354 63.562 63 .121 105.301 828.626 10-JAN-10 09 27 00.0 543.205 590.761 541.813 590.831 2097.857 2097.456 62.891 62.360 106.218 827.524 10-JAN-10 09 28 00.0 543.215 590.351 541.703 590.451 2097.055 2097.256 62.470 61.929 104.600 827.324 10-JAN-10 09 29 00.0 543.315 590.882 541.703 590.631 2097.957 2098.157 62.159 61.629 105.468 827.624 10-JAN-10 09 30 00.0 543.175 590.230 541.923 590.571 2099.259 2099.760 62.059 61.428 105.746 828.025 10-JAN-10 09 31 00.0 543.345 591.462 541.923 590.721 2096.455 2097.256 61.639 61.088 104.825 827.524 10-JAN-10 09 32 00.0 543.205 591.152 541.703 589.930 2097.256 2097.356 61.338 60.757 104.895 826.523 10-JAN-10 09 33 00.0 542.945 591.122 541.703 590.861 2097.256 2097.356 60.998 60.527 104.993 825.721 10-JAN-10 09 34 00.0 542.814 590.882 541.603 590.631 2098.157 2097.456 60.897 60.327 106.770 824.920 10-JAN-10 09 35 00.0 542.935 590.621 541.603 590.341 2098.457 2098.758 60.797 60.226 104.853 825.521 10-JAN-10 09 36 00.0 542.945 590.571 541.603 590.220 2098.858 2099.559 60.697 60.016 105.063 825.621 10-JAN-10 09 37 00.0 543.075 589.459 541.703 590.511 2098.658 2098.858 60.477 60.016 105.760 825.621 10-JAN-10 09 38 00.0 542.965 591.192 541.502 591.042 2099.259 2099.860 60.377 59.916 105.566 825.120 10-JAN-10 09 39 00.0 543.075 589.900 541.603 590.882 2099.259 2098.457 60.377 59.916 104.783 825.521 10-JAN-10 09 40 00.0 542.955 590.471 541.703 590.561 2098.057 2098.658 60.266 59.816 105.663 825.220 10-JAN-10 09 41 00.0 543.165 590.991 541.703 590.170 2100.060 2099.660 60.266 59.716 104.502 825.721 10-JAN-10 09 42 00.0 542.945 590.982 541.603 590.020 2099.059 2099.559 60.266 59.716 105.259 825.220 10-JAN-10 09 43 00.0 542.935 591.132 541.703 590.842 2100.361 2100.661 60.266 59.716 106.107 825.821 10-JAN-10 09 44 00.0 542.925 590.861 541.703 589.960 2098.858 2099.660 60.166 59.716 105.329 825.821 10-JAN-10 09 45 00.0 543.065 590.110 541.703 590.871 2099.860 2100.260 60.276 59.716 105.119 825.521 10-JAN-10 09 46 00.0 542.824 591.092 541.603 590.801 2099.660 2099.059 60.166 59.615 105.524 825.922 10-JAN-10 09 47 00.0 542.935 590.932 541.713 590.000 2099.359 2100.160 60.166 59.615 106.177 825.721 10-JAN-10 09 48 00.0 542.935 591.312 541.943 590.771 2100.561 2101.362 60.487 59.826 105.007 828.726 10-JAN-10 09 49 00.0 543.185 591.282 542.063 591.362 2098.057 2098.257 60.286 59.716 105.343 830.028 10-JAN-10 09 50 00.0 543.085 590.821 542.063 589.640 2096.855 2096.855 59.856 59.385 105.203 830.429 10-JAN-10 09 51 00.0 543.165 590.030 541.542 588.748 2098.157 2097.857 59.405 58.764 105.440 828.826 10-JAN-10 09 52 00.0 542.945 588.828 541.643 589.028 2101.162 2101.262 59.635 58.964 105.913 830.930 10-JAN-10 09 53 00.0 543.205 589.299 541.863 588.698 2100.060 2100.060 59.856 59.375 105.259 834.235 10-JAN-10 09 54 00.0 543.666 589.449 542.094 588.838 2098.958 2098.958 59.956 59.375 105.844 834.535 10-JAN-10 09 55 00.0 543.295 589.299 542.094 588.388 2097.756 2097.857 59.625 59.075 104.670 832.933 10-JAN-10 09 56 00.0 543.085 588.388 541.663 588.818 2099.059 2098.758 59.415 58.874 104.375 830.729 10-JAN-10 09 57 00.0 542.875 587.847 541.663 588.217 2098.958 2099.760 59.315 58.774 105.482 829.828 10-JAN-10 09 58 00.0 542.554 588.207 541.462 588.788 2099.960 2099.860 59.315 58.774 105.301 829.828 10-JAN-10 09 59 00.0 542.985 588.758 541.252 588.808 2100.961 2100.861 59.415 58.774 105.552 829.527 10-JAN-10 10 00 00.0 542.644 588.397 541.362 587.987 2099.960 2099.960 59.415 58.894 105.788 829.327 10-JAN-10 10 01 00.0 542.774 588.187 541.362 588.197 2099.960 2100.060 59.525 58.994 106.274 828.526 10-JAN-10 10 02 00.0 542.674 588.958 541.362 588.007 2100.661 2101.362 59.766 59.095 105.635 829.327 10-JAN-10 10 03 00.0 542.885 588.297 541.362 587.877 2100.661 2100.260 59.966 59.405 105.245 830.429 10-JAN-10 10 04 00.0 543.105 589.329 541.472 588.638 2099.860 2100.060 60.086 59.525 105.941 831.030 10-JAN-10 10 OS 00.0 542.755 589.529 541.472 588.367 2098.758 2099.059 60.086 59.525 105.607 830.729 10-JAN-10 10 06 00.0 542.845 588.167 541.472 588.227 2098.958 2099.059 60.086 59.525 104.811 830.329 10-JAN-10 10 07 00.0 543.065 589.689 541.583 588.237 2099.158 2099.059 60.086 59.525 105.691 830.429 10-JAN-10 10 08 00.0 542.704 588.518 541.482 588.558 2099.158 2099.059 59.986 59.525 105.077 830.529 10-JAN-10 10 09 00.0 543.035 588.478 541.482 588.097 2099.459 2099.059 59.886 59.415 105.552 830.028 10-JAN-10 10 10 00.0 542.814 588.067 541.482 588.077 2099.259 2099.660 59.996 59.415 106.204 830.429 10-JAN-10 10 11 00.0 542.704 588.658 541.382 588.447 2098.457 2098.558 59.996 59.415 104.755 830.128 10-JAN-10 10 12 00.0 542.704 588.988 541.382 587.516 2099.459 2100.060 59.996 59.415 105.468 830.329 10-JAN-10 10 13 00.0 542.704 589.179 541.382 588.267 2099.459 2099.059 59.996 59.415 105.607 830.429 10-JAN-10 10 14 00.0 542.824 587.396 541.482 588.337 2099.359 2099.059 59.996 59.415 105.858 830.028

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10-JAN-10 10 15 00.0 542.795 588.478 541.272 588.137 2098.157 2098.958 59.886 59.305 105.566 828.025 10-JAN-10 10 16 00.0 542.564 589.018 541.172 588.588 2101.362 2101.362 60.317 59.615 106.232 827.424 10-JAN-10 10 17 00.0 542.604 589.920 541.282 588.518 2101.362 2101.262 60.537 60.026 105.356 827.624 10-JAN-10 10 18 00.0 543.125 590.601 541.623 589.659 2099.559 2098.758 60.767 60.256 104.979 826.823 10-JAN-10 10 19 00.0 542.634 589.760 541.422 589.189 2098.457 2097.756 60.467 59.936 105.468 823.918 10-JAN-10 10 20 00.0 542.384 589.680 541.172 590.220 2098.658 2098.457 60.347 59.816 104.530 822.015 10-JAN-10 10 21 00.0 542.504 590.481 541.162 589.640 2100.260 2099.359 60.397 59.816 104.993 822.216 10-JAN-10 10 22 00.0 542.283 590.200 541.072 589.710 2100.260 2100.260 60.296 59.716 107.114 821.915 10-JAN-10 10 23 00.0 542.524 590.571 541.172 590.190 2099.259 2100.260 60.196 59.716 105.426 822.316 10-JAN-10 10 24 00.0 542.414 589.589 541.172 589.680 2099.259 2099.459 60.196 59.615 105.329 822.216 10-JAN-10 10 25 00.0 542.193 590.090 541.072 590.581 2099.559 2099.960 60.196 59.716 105.705 821.915 10-JAN-10 10 26 00.0 542.304 590.511 541.172 589.750 2100.561 2101.262 60.407 59.826 105.398 823.317 10-JAN-10 10 27 00.0 542.845 590.871 541.262 590.320 2099.559 2100.260 60.407 59.826 105.440 823.418 10-JAN-10 10 28 00.0 542.604 590.341 541.472 589.750 2099.158 2099.559 60.286 59.826 105.802 823.918 10-JAN-10 10 29 00.0 542.514 590.911 541.262 590.210 2099.359 2099.059 60.306 59.826 105.217 823.718 10-JAN-10 10 30 00.0 542.614 590.611 541.382 589.529 2099.359 2099.860 60.306 59.726 104.558 823.618 10-JAN-10 10 31 00.0 542.624 589.259 541.382 590.030 2099.359 2098.558 60.206 59.726 104.951 823.117 10-JAN-10 10 32 00.0 542.634 590.461 541.262 590.120 2099.158 2099.158 60.206 59.625 104.839 823.918 10-JAN-10 10 33 00.0 542.524 590.821 541.372 589.509 2099.158 2099.158 60.206 59.625 105.872 823.518 10-JAN-10 10 34 00.0 542.774 589.780 541.252 589.549 2099.158 2099.158 60.206 59.625 105.524 823.818 10-JAN-10 10 35 00.0 542.444 591.102 541.252 589.860 2098.958 2099.459 60.116 59.625 105.398 823.718 10-JAN-10 10 36 00.0 542.805 589.940 541.362 588.998 2099.960 2099.259 60.116 59.625 104.741 824.018 10-JAN-10 10 37 00.0 542.584 590.531 541.252 589.670 2099.960 2099.860 60.126 59.625 105.802 823.418 10-JAN-10 10 38 00.0 542.574 590.421 541.252 590.200 2099.860 2099.860 60.126 59.625 105.007 823.718 10-JAN-10 10 39 00.0 542.574 589.619 541.352 589.790 2099.359 2099.059 60.126 59.525 105.426 823.317 10-JAN-10 10 40 00.0 542.464 591.663 541.372 590.611 2100.060 2099.860 60.026 59.525 104.431 823.918 10-JAN-10 10 41 00.0 542.464 591.663 541.372 590.611 2100.060 2099.860 60.026 59.525 104.431 823.918 10-JAN-10 10 42 00.0 542.464 591.663 541.372 590.611 2100.060 2099.860 60.026 59.525 104.431 823.918 10-JAN-10 10 43 00.0 542.464 591.663 541.372 590.611 2100.060 2099.860 60.026 59.525 104.431 823.918 10-JAN-10 10 44 00.0 542.464 591.663 541.372 590.611 2100.060 2099.860 60.026 59.525 104.431 823.918 10-JAN-10 10 45 00.0 542.464 591.663 541.372 590.611 2100.060 2099.860 60.026 59.525 104.431 823.918

DATE/TIME *P0905A* *P1046* *P1048* *L0903Y* *L0906Y* *P0946A* *Y3273* *XC093* *XC105* *XC411* *PSIA • *PSIG * *PSIG * • % • • % * *PSIG • * MW • *ASIU * * MW • *% PWR*

10-JAN-10 08 15 00.0 821.114 790.964 785.921 62.945 62.396 529.067 528.127 -0.009 1468.658 102.042 10-JAN-10 08 16 00.0 821.314 790.964 785.921 62.771 62.705 528.996 527.254 -0.009 1468.732 102.435 10-JAN-10 08 17 00.0 820.914 790.964 785.921 62.973 63.035 528.856 527.683 -0.009 1469.113 102.234 10-JAN-10 08 18 00.0 821.314 790.964 785.921 62.771 62.668 528.996 527.762 -0.009 1469.215 101.781 10-JAN-10 08 19 00.0 821.014 790.964 785.921 62.961 62.795 528.786 528.143 -0.008 1469.084 101.378 10-JAN-10 08 20 00.0 821.314 790.964 785.921 62.953 62.850 529.067 526.763 -0.009 1469.131 101.861 10-JAN-10 08 21 00.0 821.014 790.964 785.921 62.865 62.842 528.926 526.905 -0.010 1469.164 101.328 10-JAN-10 08 22 00.0 821.314 790.964 785.921 62.916 62.672 528.856 528.777 -0.009 1469.198 100.451 10-JAN-10 08 23 00.0 821.414 790.964 785.921 62.846 62.787 529.137 527.683 -0.010 1469.327 101.499 10-JAN-10 08 24 00.0 821.214 790.964 785.921 62.684 62.701 528.926 527.905 -0.009 1469.317 101.590 10-JAN-10 08 25 00.0 821.515 790.964 785.921 62.672 62.645 529.067 527.778 -0.009 1469.292 102.183 10-JAN-10 08 26 00.0 821.114 790.964 785.921 62.877 62.834 528.926 527.381 -0.009 1469.455 102.878 10-JAN-10 08 27 00.0 821.214 790.964 785.921 62.783 62.756 529.137 527.667 -0.009 1469.470 101.548 10-JAN-10 08 28 00.0 821.214 790.964 785.921 62.865 62.938 528.646 527.381 -0.009 1469.432 102.345 10-JAN-10 08 29 00.0 821.314 790.964 785.921 62.684 62.807 529.067 527.286 -0.010 1469.451 101.267 10-JAN-10 08 30 00.0 821.615 790.964 785.921 62.877 62.676 528.786 526.778 -0.010 1469.281 101.771 10-JAN-10 08 31 00.0 821.314 790.964 785.921 62.873 62.783 528.786 527.857 -0.010 1469.107 102.687 10-JAN-10 08 32 00.0 821.615 790.964 785.921 63.055 62.969 528.926 526.794 -0.009 1469.369 101.267 10-JAN-10 08 33 00.0 820.813 790.964 785.921 63.066 62.869 528.786 527.651 -0.009 1469.612 102.355 10-JAN-10 08 34 00.0 820.914 789.703 785.921 62.830 62.869 530.609 528.682 -0.008 1469.527 101.478 10-JAN-10 08 35 00.0 817.107 787.376 781.641 63.098 62.885 532.151 529.888 -0.008 1469.599 102.274 10-JAN-10 08 36 00.0 813.502 782.910 778.272 62.861 62.857 533.063 531.173 -0.004 1469.744 102.888 10-JAN-10 08 37 00.0 807.392 776.307 772.332 63.248 63.410 532.362 532.395 -0.001 1470.123 103.805 10-JAN-10 08 38 00.0 801.482 771.540 765.436 63.342 63.316 530.819 529.888 0.002 1470.938 100.804 10-JAN-10 08 39 00.0 797.175 765.529 761.511 64.324 63.480 530.118 528.841 0.004 14 71.949 102.093 10-JAN-10 08 40 00.0 793.670 762.299 757.201 64.293 63.328 530.258 529.047 0.006 1472.743 102.274 10-JAN-10 08 41 00.0 789.764 759.099 752.814 64.426 63.506 529.627 529.063 0.008 1472.758 102.999 10-JAN-10 08 42 00.0 787.360 755.740 750.741 64.012 63.275 530.118 529.063 0.008 1472.329 101.630

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10-JAN-10 08 43 00.0 784.956 753.529 748.668 63.457 63.654 530.399 530.539 0.008 14 71.538 103.301 10-JAN-10 08 44 00.0 782.652 751.489 746.584 62.965 62.914 529.768 529.190 0.009 1470.756 102.606 10-JAN-10 08 45 00.0 780.749 749.421 744.479 62.811 62.830 530.469 529.888 0.010 1469.937 102.143 10-JAN-10 08 46 00.0 778.245 747.233 742.099 62.656 62.941 530.188 528.365 0.011 1469.511 102.173 : 10-JAN-10 08 47 00.0 777.444 744.993 740.055 62.621 63.150 530.819 529.238 0.011 1469.234 102.072 10-JAN-10 08 48 00.0 776.242 743.981 738.887 62.904 63.143 531.030 530.301 0.011 1468.880 101.307 10-JAN-10 08 49 00.0 773.838 741.675 736.791 62.795 62.992 531.030 529.126 0.012 1468.405 103.805 10-JAN-10 08 50 00.0 772.135 740.473 735.608 62.768 63.000 530.749 529.317 0.012 1468.205 102.546 10-JAN-10 08 51 00.0 771.134 738.403 733.264 62.877 63.035 530.749 530.523 0.012 1468.807 102.022 10-JAN-10 08 52 00.0 769.932 737.223 732.241 63.129 63.020 530.819 530.063 0.014 1469.619 103.896 10-JAN-10 08 53 00.0 769.732 737.223 732.241 63.197 62.787 531.100 529.698 0.015 1470.640 103.553 10-JAN-10 08 54 00.0 769.732 737.223 732.241 62.885 62.930 530.399 530.221 0.013 1471.904 101.337 10-JAN-10 08 55 00.0 769.631 737.223 732.241 62.822 62.834 530.539 529.698 0.015 1473.092 102.264 10-JAN-10 08 56 00.0 769.431 737.223 732.241 62.668 62.729 530.258 529.476 0.013 1473.708 104.399 10-JAN-10 08 57 00.0 769.131 737.223 732.241 62.791 62.842 530.469 529.333 0.014 1473.851 104.681 10-JAN-10 08 58 00.0 769.030 737.223 732.241 62.744 62.613 530.399 528.539 0.013 1473.786 103.653 10-JAN-10 08 59 00.0 769.231 737.223 732.241 62.764 62.996 530.329 529.888 0.014 1473.780 102.626 10-JAN-10 09 00 00.0 769.431 737.223 732.241 62.795 63.043 530.539 529.602 0.015 1473.731 103.573 10-JAN-10 09 01 00.0 769.030 737.223 732.241 63.020 62.941 530.118 528.793 0.014 1473.617 102.868 10-JAN-10 09 02 00.0 769.331 737.223 732.241 62.973 62.771 530.469 529.602 0.013 1473.495 102.807 10-JAN-10 09 03 00.0 769.331 737.223 732.241 62.877 63.221 530.469 530.396 0.013 1473.486 104.671 10-JAN-10 09 04 00.0 769.431 737.223 732.241 62.748 63.023 530.258 529.428 0.014 1473.562 103.069 10-JAN-10 09 05 00.0 769.932 737.223 732.241 62.760 62.949 529.627 529.793 0.014 1473.643 102.455 10-JAN-10 09 06 00.0 770.533 738.331 733.254 62.771 62.783 529.277 528.841 0.016 1473.650 101.579 10-JAN-10 09 07 00.0 772.135 739.462 734.307 62.904 62.732 529.277 527.635 0.015 1473.595 103.211 10-JAN-10 09 08 00.0 773.538 741.610 736.718 62.660 63.271 528.506 527.603 0.015 1473.548 103.422 10-JAN-10 09 09 00.0 775.140 742.800 737.862 62.904 62.869 528.295 527.619 0.015 1473.365 101.750 10-JAN-10 09 10 00.0 777.143 744.905 740.103 62.822 63.100 528.365 527.350 0.014 1473.044 102.767 10-JAN-10 09 11 00.0 778.446 747.030 741.170 62.648 62.471 527.875 527.461 0.015 1472.617 102.878 10-JAN-10 09 12 00.0 779.648 748.246 743.224 62.949 62.748 527.734 526.382 0.014 1472.227 102.113 10-JAN-10 09 13 00.0 781.150 749.325 744.295 62.854 62.729 526.122 525.795 0.015 14 71.820 101.690 10-JAN-10 09 14 00.0 782.953 751.412 746.363 62.965 62.764 526 .122 525.969 0.015 1471.251 102.194 10-JAN-10 09 15 00.0 784.655 753.720 748.509 62.877 62.918 524.790 524.065 0.014 1470.521 102.234 10-JAN-10 09 16 00.0 787.660 755.829 750.655 62.684 62.877 524.439 523.669 0.014 1469.667 103.089 10-JAN-10 09 17 00.0 789.864 759.000 753.764 62.850 62.834 524.439 523.431 0.014 1468.698 101.932 10-JAN-10 09 18 00.0 792.568 761.196 756.979 62.748 62.713 523.528 522.368 0.012 1467.537 101.478 10-JAN-10 09 19 00.0 795.273 764.444 759.282 62.803 62.803 522.266 521.210 0.012 1466.301 101.508 10-JAN-10 09 20 00.0 799.279 768.943 764.158 62.787 62.775 522.055 519.480 0.011 1465.128 100.672 10-JAN-10 09 21 00.0 803.986 773.345 768.516 62.660 62.705 521.565 520.623 0.007 1463.940 101.176 10-JAN-10 09 22 00.0 809.796 778.882 773.826 62.512 62.373 521.494 520.988 0.008 1462.224 101.065 10-JAN-10 09 23 00.0 814.904 784.714 780.624 62.082 62.396 520.443 519.877 0.005 1460.602 101.780 10-JAN-10 09 24 00.0 821.014 790.805 786.147 62.137 62.520 521.214 519.322 0.003 1459.206 101.387 10-JAN-10 09 25 00.0 823.518 793.970 789.428 62.061 62.369 522.266 520.432 0.000 1457.789 101.680 10-JAN-10 09 26 00.0 824.519 795.203 790.530 62.137 62.609 524.159 521.400 -0.001 1456.922 101.730 10-JAN-10 09 27 00.0 823.117 794.180 789.407 62.346 62.697 524.369 523.018 -0.001 1456.637 101.176 10-JAN-10 09 28 00.0 823.017 792.977 788.349 62.625 62.748 524.229 523.526 -0.001 1456.871 100.512 10-JAN-10 09 29 00.0 823.718 794.123 789.366 62.467 62.877 524.509 523.240 -0.003 1457.301 101.277 10-JAN-10 09 30 00.0 824.519 794.123 789.366 63 .148 63.131 525.210 524.986 -0.002 1457.780 100.572 10-JAN-10 09 31 00.0 823.317 794.123 789.366 63.078 62.697 528.436 526.604 -0.003 1458.103 102.193 10-JAN-10 09 32 00.0 822.216 793.037 788.295 63.221 62.779 527.805 525.414 -0.003 1459.031 101.931 10-JAN-10 09 33 00.0 821.615 792.029 787.197 62.818 62.645 528.506 527.429 -0.003 1460.043 102.133 10-JAN-10 09 34 00.0 821.615 790.923 786.194 62.711 63.096 528.155 526.715 -0.003 1461.212 101.882 10-JAN-10 09 35 00.0 821.615 790.923 786.194 62.594 62.795 528.295 526.477 -0.004 1462.766 101.237 10-JAN-10 09 36 00.0 821.314 790.923 786.194 63.004 62.748 528.225 527.365 -0.004 1463.952 101.630 10-JAN-10 09 37 00.0 821.414 792.060 786.194 62.688 62.814 528.365 527.540 -0.003 1464.721 100.773 10-JAN-10 09 38 00.0 821.114 792.060 786.194 62.965 62.869 528.225 526.001 -0.003 1465.225 102.456 10-JAN-10 09 39 00.0 821.815 791.022 786.194 62.729 62.814 528.225 526.033 -0.004 1465.675 101.620 10-JAN-10 09 40 00.0 821.314 791.022 786.194 63.004 63.162 528.015 527.746 -0.002 1466.065 100.813 10-JAN-10 09 41 00.0 821.314 791.022 786.194 62.787 62.668 528.225 526.636 -0.005 1466.899 101.649 10-JAN-10 09 42 00.0 821.414 791.022 786.194 63.299 63 .115 528.155 527.445 -0.003 1467.594 101.952 10-JAN-10 09 43 00.0 821.314 791.022 786.194 63.055 62.652 528.436 526.525 -0.005 1468.052 102.163 10-JAN-10 09 44 00.0 821.414 791.022 786.194 63.186 62.902 528.295 527.810 -0.004 1468.273 101.629

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10-JAN-10 09 45 00.0 821.815 791.022 786.194 62.617 62.969 528.225 526.810 -0.005 1468.110 101.508 10-JAN-10 09 46 00.0 821.214 791.022 786.194 62.984 63.096 528.295 527.048 -0.003 1467.945 102.616 • 10-JAN-10 09 47 00.0 821.615 791.022 787.218 62.613 62.648 528.436 527.000 -0.004 1467.775 102.737 10-JAN-10 09 48 00.0 824.419 794.601 789.477 62.609 62.656 525.070 523.653 -0.002 1467.418 102.284 10-JAN-10 09 49 00.0 825.821 796.745 791.901 62.857 62.684 521.354 520.861 0.002 1467.196 102.012 10-JAN-10 09 SO 00.0 825.922 796.745 791.901 63.264 62.717 516.376 515.784 0.007 1466.870 100.280 10-JAN-10 09 51 00.0 825.220 796.745 791.901 63.918 63.387 510.487 510.247 0.011 1465.646 99.877 10-JAN-10 09 52 00.0 827.224 797.746 794.156 64.623 63.445 507.752 507.454 0.011 1463.578 97.984 10-JAN-10 09 53 00.0 829.828 800.958 797.422 64.871 63.375 505.930 506.518 0.013 1460.287 98.044 10-JAN-10 09 54 00.0 830.329 803.096 798.437 64.348 63.363 505.088 505.344 0.015 1455.410 97.651 10-JAN-10 09 55 00.0 828.826 800.920 797.271 63.906 63.256 504.387 506.169 0.015 1449.370 97.722 10-JAN-10 09 56 00.0 827.224 799.775 795.036 63.236 63.115 503.335 503.710 0.016 1442.826 97.400 10-JAN-10 09 57 00.0 826.322 798.721 793.988 62.752 62.895 502.634 503.345 0.017 1436.045 96.402 10-JAN-10 o9 sa oo.o 825.721 797.697 793.988 62.703 62.688 502.284 501.759 0.017 1429.342 98.075 10-JAN-10 09 59 00.0 825.421 797.697 792.976 62.795 62.656 502.003 501.663 0.017 1422.976 97.893 10-JAN-10 10 00 00.0 825.821 797.697 792.976 62.783 62.791 502.143 502.298 0.016 1416.915 97.299 10-JAN-10 10 01 00.0 825.120 797.697 792.976 62.764 63.162 SOl. 512 501.108 0.017 1411.581 97.450 10-JAN-10 10 02 00.0 825.821 797.697 792.976 62.691 63.043 SOl. 933 501.997 0.017 1407.165 98.396 10-JAN-10 10 03 00.0 826.723 797.697 794.020 62.996 63.092 502.494 503.012 0.016 1404.065 96.855 10-JAN-10 10 04 00.0 826.623 798.861 794.020 62.645 62.680 502.704 502.885 0.018 1402.358 98.598 10-JAN-10 10 OS 00.0 826.523 798.861 795.029 62.547 62.764 502.564 502.742 0.017 1401.866 99.353 10-JAN-10 10 06 00.0 826.823 798.861 795.029 62.482 62.992 502.564 SOl. 806 0.015 1402.220 96.644 10-JAN-10 10 07 00.0 826.222 798.861 793.988 62.873 62.861 502.284 501.663 0.017 1402.943 99.252 10-JAN-10 10 08 00.0 826.623 798.861 793.988 62.807 62.641 502.424 501.949 0.017 1403.397 96.876 10-JAN-10 10 09 00.0 826.122 798.861 793.988 63.066 62.934 502.143 502.996 0.016 1404.279 96.946 10-JAN-10 10 10 00.0 826.523 798.861 793.988 63.027 62.977 502.424 500.854 0.016 1404.507 96.362 10-JAN-10 10 11 00.0 826.322 798.861 793.988 63.000 63.135 502.214 502.536 0.017 1404.549 97.782 10-JAN-10 10 12 00.0 826.523 797.854 793.988 62.945 62.732 502.424 502.044 0.016 1404.551 98.407 10-JAN-10 10 13 00.0 825.922 797.854 793.988 63.113 62.857 502.214 502.377 0.015 1404.472 98.790 10-JAN-10 10 14 00.0 826.422 797.854 793.988 62.920 62.729 502.424 501.870 0.017 1404.698 96.875 10-JAN-10 10 15 00.0 824.219 796.711 791.899 63.086 62.910 505.369 506.042 0.014 1404.953 97.399 10-JAN-10 10 16 00.0 823.418 795.474 790.745 63.008 63.012 509.435 509.041 0.011 1405.028 98.820 10-JAN-10 10 17 00.0 823.418 794.316 790.745 62.342 62.709 514.203 514.308 0.004 1405.236 100.481 10-JAN-10 10 18 00.0 822.716 794.284 789.676 61.959 62.400 519.111 517.910 0.002 1406.038 100.984 10-JAN-10 10 19 00.0 820.212 791.008 786.382 61.281 62.262 521.985 521.511 0.002 1407.820 99.988 10-JAN-10 10 20 00.0 817.809 788.535 783.001 61.762 62.350 524.790 522.828 -0.001 1411.119 101.418 10-JAN-10 10 21 00.0 818.309 787.475 783.001 61.443 62.191 525.491 524.288 -0.003 1415.953 101.830 10-JAN-10 10 22 00.0 817.608 787.475 783.001 62.094 62.543 525.280 523.954 -0.002 1421.806 101.579 10-JAN-10 10 23 00.0 818.109 788.482 783.001 62.295 62.539 525.351 524.859 -0.002 1428.293 101.982 10-JAN-10 10 24 00.0 818.109 788.482 783.001 62.949 62.717 525.771 523.923 -0.002 1434.756 100.300 10-JAN-10 10 25 00.0 818.309 788.482 783.001 63.137 62.969 525.280 524.557 -0.001 1441.260 102.435 10-JAN-10 10 26 00.0 819.311 789.510 784.048 63.256 62.814 525.000 523 .129 -0.002 1447.436 102.083 10-JAN-10 10 27 00.0 819.511 789.510 784.048 63.307 62.988 525.210 524.208 -0.003 1453.067 102.173 10-JAN-10 10 28 00.0 819.912 789.510 785.172 63.236 62.768 525.351 524.034 -0.002 1457.746 101.136 10-JAN-10 10 29 00.0 819.611 789.510 785.172 63.252 62.869 525.351 524.605 -0.003 1461.112 102.586 10-JAN-10 10 30 00.0 819.912 789.510 785.172 62.932 62.697 525.561 524.050 -0.002 1462.917 101.761 10-JAN-10 10 31 00.0 819.812 789.510 785.172 62.691 62.934 525.140 525.414 -0.002 1463.403 100.582 10-JAN-10 10 32 00.0 819.411 789.510 785.172 62.725 62.574 525.491 523.812 -0.003 1463.028 101.559 10-JAN-10 10 33 00.0 819.411 789.510 785.172 62.691 62.857 525.070 525.176 -0.003 1462.258 102.284 10-JAN-10 10 34 00.0 819.912 789.510 785.172 62.680 62.961 525.421 523.938 -0.003 1461.428 100.058 10-JAN-10 10 35 00.0 819.611 789.510 785.172 62.904 63.074 525.210 524.906 -0.002 1460.729 103.049 10-JAN-10 10 36 00.0 819.912 789.510 785.172 62.869 62.574 525.421 524.446 -0.004 1460.258 100.239 10-JAN-10 10 37 00.0 819.411 789.510 785.172 63.193 62.926 525.140 525.144 -0.002 1460.086 101.761 10-JAN-10 10 38 00.0 819.611 789.510 785.172 63.008 62.756 525.561 524.065 -0.003 1460.141 101.549 10-JAN-10 10 39 00.0 819.912 789.510 785.172 63.078 62.906 525.561 524.399 -0.001 1460.268 100.179 10-JAN-10 10 40 00.0 819.611 789.510 785.172 63.066 62.865 525.351 523.907 -0.001 1460.405 103.533 10-JAN-10 10 41 00.0 819.611 789.510 785.172 63.066 62.865 525.351 523.907 -0.001 1460.405 103.533 10-JAN-10 10 42 00.0 819.611 789.510 785.172 63.066 62.865 525.351 523.907 -0.001 1460.405 103.533 10-JAN-10 10 43 00.0 819.611 789.510 785.172 63.066 62.865 525.351 523.907 -0.001 1460.405 103.533 10-JAN-10 10 44 00.0 819.611 789.510 785.172 63.066 62.865 525.351 523.907 -0.001 1460.405 103.533 10-JAN-10 10 45 00.0 819.611 789.510 785.172 63.066 62.865 525.351 523.907 -0.001 1460.405 103.533

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---- --

' DATE/TIME *AR002X* *AR002Y* *BR002X* *BR002Y* *CR002X* *CR002Y* *DR002X* *DR002Y* *R0003X* *R0003Y*

* % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* ' 10-JAN-10 08 15 00.0 49.226 49.034 49.250 48.809 49.095 48.857 49.285 48.883 44.780 43.232

10-JAN-10 08 16 00.0 49.351 48.970 49.168 48.804 49.277 49.013 49.341 48.990 44.806 43.168 : 10-JAN-10 08 17 00.0 49.250 49.014 49.212 48.809 49.252 48.928 49.282 48.970 44.849 43.296 10-JAN-10 08 18 00.0 49.346 48.982 49.263 48.814 49.178 48.918 49.316 49.006 44.833 43.186 10-JAN-10 08 19 00.0 49.359 49.056 49.189 48.792 49.282 49.018 49.237 48.968 44.811 43.171 10-JAN-10 08 20 00.0 49.322 49.019 49.107 48.769 49.240 48.889 49.256 48.952 44.865 43.168 10-JAN-10 08 21 00.0 49.332 48.944 49.213 48.729 49.261 48.925 49.266 48.971 44.829 43.200 10-JAN-10 08 22 00.0 49.245 48.981 49.221 48.761 49.224 49.011 49.300 48.998 44.801 43.226 10-JAN-10 08 23 00.0 49.329 49.026 49.210 48.764 49.303 48.957 49.434 49.096 44.886 43.228 10-JAN-10 08 24 00.0 49.391 49.071 49.272 48.821 49.239 49.011 49.304 48.965 44.851 43.261 10-JAN-10 08 25 00.0 49.269 48.958 49.24D 48~ 792 49~208 48 ~915 49.3l6 48.992 44.845 43.197 10-JAN-10 08 26 00.0 49.248 48.955 49.296 48.776 49.168 48.989 49.317 48.992 44.925 43.287 10-JAN-10 08 27 00.0 49.248 49.010 49.143 48.758 49.248 48.962 49.266 48.889 44.756 43.133 10-JAN-10 08 28 00.0 49.337 49.079 49.154 48.716 49.260 49.003 49.282 48.994 44.946 43.316 10-JAN-10 08 29 00.0 49.353 48.954 49.232 48.784 49.218 48.965 49.298 48.938 44.833 43.311 10-JAN-10 08 30 00.0 49.337 49.032 49.248 48.752 49.250 48.982 49.282 48.962 44.926 43.208 10-JAN-10 08 31 00.0 49.337 49.087 49.154 48.772 49.218 48.976 49.354 48.998 44.803 43.208 10-JAN-10 08 32 00.0 49.237 49.050 49.157 48.748 49.266 48.934 49.271 48.957 44.897 43.290 10-JAN-10 08 33 00.0 49.322 48.918 49.162 48.776 49.228 49.006 49.330 49.030 44.800 43.167 10-JAN-10 08 34 00.0 49.330 49.032 49.210 48.822 49.271 49.042 49.247 49.018 44.849 43.253 10-JAN-10 08 35 00.0 49.284 49.032 49.155 48.811 49.138 48.926 49.335 49.024 44.849 43.268 10-JAN-10 08 36 00.0 49.071 48.832 48.915 48.705 48.913 48.870 49.050 48.905 44.683 43.163 10-JAN-10 08 37 00.0 48.740 48.700 48.622 48.526 48.731 48.647 48.678 48.712 44.353 42.970 10-JAN-10 08 38 00.0 48.365 48.519 48.321 48.341 48.192 48.367 48.460 48.455 44.074 42.843 10-JAN-10 08 39 00.0 48.216 48.386 48.255 48.295 48.080 48.325 48.253 48.365 43.872 42.712 10-JAN-10 08 40 00.0 48.088 48.343 48.131 48.212 48.005 48.330 48.130 48.348 43.777 42.655 10-JAN-10 08 41 00.0 48.072 48.372 47.954 48.115 4 7. 740 48.106 47.928 48.218 43.627 42.587 10-JAN-10 08 42 00.0 48.005 48.319 48.045 48.194 47.857 48.288 47.933 48.208 43.595 42.617 10-JAN-10 08 43 00.0 47.838 48.183 47.843 48.026 47.692 48.082 47.873 48.119 43.474 42.460 10-JAN-10 08 44 00.0 47.851 48.192 47.830 47.971 47.593 48.016 47.715 48.066 43.481 42.460 10-JAN-10 08 45 00.0 47.641 48.053 47.700 47.955 47.559 48.008 47.716 47.994 43.372 42.391 10-JAN-10 08 46 00.0 47.631 48.040 47.529 47.801 4 7.490 47.947 47.474 47.877 43.321 42.404 10-JAN-10 08 47 00.0 47.614 48.131 47.599 47.875 47.529 47.905 47.625 48.010 43.338 42.386 10-JAN-10 08 48 00.0 47.614 48.053 47.625 47.905 47.510 47.933 47.502 47.896 43.271 42.321 10-JAN-10 08 49 00.0 47.436 47.912 47.460 47.824 47.433 47.901 47.518 47.971 43.096 42.192 10-JAN-10 08 50 00.0 47.502 47.865 47.585 47.881 47.357 47.881 47.412 47.867 43.202 42.215 10-JAN-10 08 51 00.0 47.444 47.886 47.365 47.704 47.386 47.833 47.468 47.912 43.119 42.231 10-JAN-10 08 52 00.0 47.391 47.872 47.373 47.724 47.194 47.745 47.293 47.817 42.998 42.135 10-JAN-10 08 53 00.0 47.429 47.880 47.373 47.792 47.296 47.929 47.293 47.853 43.064 42.280 10-JAN-10 08 54 00.0 47.313 47.816 47.391 47.740 47.293 47.811 47.359 47.833 43.091 42.173 10-JAN-10 08 55 00.0 47.346 47.949 47.383 47.734 47.179 4 7. 840 47.285 47.838 43.027 42.176 10-JAN-10 08 56 00.0 47.410 47.910 47.413 47.777 47.290 47.851 47.444 47.837 43.066 42.223 10-JAN-10 08 57 00.0 47.415 47.913 47.434 47.798 47.189 47.841 47.321 47.804 43.154 42.218 10-JAN-10 08 58 00.0 47.449 47.878 47.442 47.756 47.329 47.901 47.431 47.912 43.167 42.309 10-JAN-10 08 59 00.0 47.335 47.861 47.378 47.764 47.277 47.840 47.332 47.814 43.103 42.269 10-JAN-10 09 00 00.0 47.380 47.901 4 7.442 47.830 47.308 47.889 47.306 47.897 43.117 42.311 10-JAN-10 09 01 00.0 47.383 47.902 47.463 47.785 47.316 47.905 47.378 47.870 43.106 42.272 10-JAN-10 09 02 00.0 4 7.454 47.902 47.442 47.845 47.319 47.851 47.373 47.846 43.051 42.218 10-JAN-10 09 03 00.0 47.450 47.888 47.498 47.845 47.277 47.843 47.441 47.938 43.096 42.237 10-JAN-10 09 04 00.0 47.442 47.970 47.386 47.814 47.396 47.929 47.369 47.872 43.096 42.321 10-JAN-10 09 05 00.0 47.375 47.938 47.319 47.740 4 7. 223 47.833 4 7. 402 47.925 43.095 42.184 10-JAN-10 09 06 00.0 47.306 47.870 47.449 47.843 47.226 47.907 47.317 47.889 43.125 42.287 10-JAN-10 09 07 00.0 47.421 47.976 47.535 47.941 47.322 47.931 47.396 47.920 43.144 42.300 10-JAN-10 09 08 00.0 47.484 47.954 47.454 47.889 47.351 47.963 47.341 47.872 43.144 42.311 10-JAN-10 09 09 00.0 47.454 48.005 47.564 47.891 47.389 48.067 47.478 47.987 43.260 42.438 10-JAN-10 09 10 00.0 47.607 48.104 47.649 48.038 47.481 48.045 47.554 48.101 43.274 42.452 10-JAN-10 09 11 00.0 47.530 48.082 47.678 48.079 47.498 48.103 47.575 48.079 43.271 42.442 10-JAN-10 09 12 00.0 47.662 48.200 47.747 48.136 47.530 48.130 47.622 48.127 43.354 42.543 10-JAN-10 09 13 00.0 47.575 48.088 47.569 48.024 4 7.458 48.087 47.442 47.978 43.389 42.479 10-JAN-10 09 14 00.0 47.580 48 .192 47.659 48.045 47.575 48.080 47.521 48.088 43.353 42.479

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10-JAN-10 09 15 00.0 47.630 48.162 47.527 47.938 47.510 48.096 47.543 48.037 43.248 42.526 10-JAN-10 09 16 00.0 47.784 48.311 47.804 48.170 47.646 48.280 47.721 48.242 43.373 42.530

~ 10-JAN-10 09 17 00.0 47.752 48.210 47.822 48.189 47.657 48.261 47.676 48.173 43.357 42.563 10-JAN-10 09 18 00.0 47.784 48.367 47.878 48.165 47.651 48.171 47.833 48.207 43.465 42.623 : 10-JAN-10 09 19 00.0 47.768 48.261 47.910 48.239 47.777 48.247 47.830 48.287 43.540 42.606 10-JAN-10 09 20 00.0 48.141 48.567 48.189 48.423 48.093 48.575 48.131 48.526 43.846 42.883 10-JAN-10 09 21 00.0 48.313 48.556 48.324 48.500 48.319 48.686 48.343 48.554 43.891 42.883 10-JAN-10 09 22 00.0 48.292 48.601 48.271 48.418 48.308 48.723 48.303 48.580 43.990 42.864 10-JAN-10 09 23 00.0 48.548 48.843 48.583 48.643 48.510 48.760 48.620 48.720 44.199 43.008 10-JAN-10 09 24 00.0 48.795 48.872 48.671 48.668 48.700 48.905 48.763 48.926 44.377 43.165 10-JAN-10 09 25 00.0 48.851 48.933 48.872 48.683 48.907 49.003 48.947 48.970 44.506 43.234 10-JAN-10 09 26 00.0 49.064 49.067 48.926 48.800 48.994 49.010 49.018 49.013 44.630 43.264 10-JAN-10 09 27 00.0 48.902 48.905 48.938 48.772 48.973 49.026 49.048 49.022 44.532 43.176 10-JAN-10 09 28 00.0 49.071 49.056 49.038 48.867 48.949 49.005 49.061 49.029 44.449 43.109 10-JAN-10 09 29 00.0 49.125 49.080 49.053 48.867 49.143 49.088 49.213 49.080 44.718 43.369 10-JAN-10 09 30 00.0 49.130 49.080 49.075 48.853 49.133 49.101 49.107 49.080 44.715 43.303 10-JAN-10 09 31 00.0 49.354 49.245 49.175 48.986 49.248 49.191 49.348 49.228 44.925 43.370 10-JAN-10 09 32 00.0 49.356 49.122 49.204 48.941 49.213 49.147 49.276 49.146 44.873 43.370 10-JAN-10 09 33 00.0 49.208 49.104 49.074 48.934 49.162 49.101 49.194 49.083 44.756 43.306 10-JAN-10 09 34 00.0 49.138 49.051 49.151 48.909 49.155 49.103 49.139 49.029 44.774 43.295 10-JAN-10 09 35 00.0 49.309 49.215 49.194 48.909 49.119 49.048 49.276 49.159 44.859 43.397 10-JAN-10 09 36 00.0 49.304 49.202 49.146 48.909 49.212 49.149 49.237 49.125 44.784 43.327 10-JAN-10 09 37 00.0 49.293 49.175 49.183 48.981 49.210 49.123 49.242 49.163 44.848 43.333 10-JAN-10 09 38 00.0 49.133 49.042 48.995 48.776 49.053 49.000 49.067 49.000 44.716 43.333 10-JAN-10 09 39 00.0 49.303 49.192 49.173 49.005 49.247 49.117 49.311 49.179 44.856 43.391 10-JAN-10 09 40 00.0 49.133 49.059 49.061 48.849 49.088 49.133 49.091 49.095 44.804 43.356 10-JAN-10 09 41 00.0 49.288 49.179 49.122 48.872 49.223 49.079 49.252 49.088 44.750 43.248 10-JAN-10 09 42 00.0 49.231 49.173 49.151 48.978 49.210 49.054 49.240 49.179 44.784 43.353 10-JAN-10 09 43 00.0 49.216 49.101 49.175 48.835 49.240 49.141 49.179 49.059 44.763 43.381 10-JAN-10 09 44 00.0 49.284 49.087 49.24 7 48.990 49.050 48.998 49.197 49.087 44.785 43.324 10-JAN-10 09 45 00.0 49.276 49.131 49.250 48.893 49.213 49.143 49.252 49.138 44.814 43.349 10-JAN-10 09 46 00.0 49.165 49.141 49.175 48.885 49.096 49.037 49.157 49.043 44.747 43.292 10-JAN-10 09 47 00.0 49.191 49.091 49.104 48.856 49.114 49.059 49.213 49.085 44.777 43.321 10-JAN-10 09 48 00.0 49.123 49.066 49.006 48.793 49.008 48.979 49.091 49.040 44.681 43.226 10-JAN-10 09 49 00.0 48.689 48.777 48.707 48.731 48.607 48.755 48.707 48.782 44.300 43.030 10-JAN-10 09 50 00.0 48.308 48.582 48.237 48.402 48.272 48.596 48.258 48.535 43.997 42.845 10-JAN-10 09 51 00.0 47.813 48.261 47.723 48.006 47.737 48.232 47.782 48.176 43.494 42.540 10-JAN-10 09 52 00.0 47.744 48.135 47.734 48.027 47.659 48.163 47.737 48.125 43.476 42.506 10-JAN-10 09 53 00.0 47.583 48.091 47.474 47.825 47.513 48.040 47.551 48.005 43.181 42.324 10-JAN-10 09 54 00.0 47.377 47.915 47.378 47.758 4 7. 303 48.002 47.415 47.885 43.106 42.266 10-JAN-10 09 55 00.0 47.276 47.853 47.362 47.683 47.141 47.779 47.196 47.766 43.024 42.133 10-JAN-10 09 56 00.0 47.103 47.729 47.232 47.599 47.130 47.788 47.054 47.713 42.973 42.189 10-JAN-10 09 57 00.0 47.042 47.676 47.109 47.591 46.982 47.641 47.029 47.635 42.849 42.034 10-JAN-10 09 58 00.0 47.072 47.638 47.037 47.476 46.912 47.606 46.957 47.591 42.845 42.069 10-JAN-10 09 59 00.0 47.035 47.652 47.147 47.598 46.965 47.724 47.083 4 7. 702 42.827 42.079 10-JAN-10 10 00 00.0 47.069 47.598 47.093 47.538 46.931 47.598 46.997 47.609 42.716 41.986 10-JAN-10 10 01 00.0 46.941 47.537 46.899 47.502 46.792 47.484 46.913 47.441 42.679 41.982 10-JAN-10 10 02 00.0 46.997 47.635 47.072 47.619 47.008 4 7. 643 47.085 4 7. 704 42.811 42.063 10-JAN-10 10 03 00.0 47.213 47.780 47.144 47.585 47.013 47.659 47.152 4 7. 679 42.843 42.077 10-JAN-10 10 04 00.0 47.127 47.740 47.223 47.651 46.950 47.700 47.072 47.758 42.933 42.147 10-JAN-10 10 05 00.0 47.157 47.756 47.216 47.663 46.994 47.670 47.075 47.699 42.886 42.111 10-JAN-10 10 06 00.0 47.112 47.718 47.162 47.508 47.037 47.678 47.071 47.635 42.878 42.107 10-JAN-10 10 07 00.0 47.085 47.742 47.160 47.596 46.981 47.631 46.974 47.566 42.827 42.069 10-JAN-10 10 08 00.0 47.136 47.707 47.115 47.617 47.013 47.670 47.008 47.649 42.780 42.069 10-JAN-10 10 09 00.0 47.045 47.663 47.074 47.527 46.973 47.623 46.982 4 7. 542 42.755 42.069 10-JAN-10 10 10 00.0 47.074 47.647 47.119 47.612 47.006 47.633 47.066 47.651 42.849 42.075 10-JAN-10 10 11 00.0 47.026 47.638 47.175 47.622 46.944 47.654 47.054 47.649 42.869 42.091 10-JAN-10 10 12 00.0 47.103 4 7. 614 4 7.112 47.559 46.974 47.631 46.966 47.564 42.880 42.099 10-JAN-10 10 13 00.0 47.022 47.550 47.080 47.452 47.071 47.721 46.974 47.572 42.824 42.038 10-JAN-10 10 14 00.0 47.058 47.675 47.061 4 7.482 46.957 47.617 46.934 4 7. 636 42.795 42.038 10-JAN-10 10 15 00.0 47.345 47.886 47.321 47.683 47.322 47.905 47.303 47.849 43.125 42.205 10-JAN-10 10 16 00.0 47.643 48.082 47.620 47.873 47.585 48.016 47.583 47.995 43.447 42.405

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• '

10-JAN-10 10 17 00.0 48.189 48.381 48.365 48.377 48.200 48.425 48.330 48.495 43.971 42.737 f' ' 10-JAN-10 10 18 00.0 48.396 48.490 48.372 48.269 48.357 48.551 48.394 48.527 44.077 42.869 • 10-JAN-10 10 19 00.0 48.478 48.595 48.500 48.455 48.365 48.495 48.489 48.575 44.130 42.878

10-JAN-10 10 20 00.0 48.841 48.816 48.671 48.543 48.691 48.676 48.753 48.713 44.402 43.030 10-JAN-10 10 21 00.0 48.816 48.764 48.758 48.513 48.755 48.737 48.804 48.739 44.410 43.010 10-JAN-10 10 22 00.0 48.761 48.792 48.752 48.619 48.683 48.615 48.742 48.681 44.423 43.010 10-JAN-10 10 23 00.0 48.782 48.732 48.764 48.579 48.710 48.710 48.699 48.673 44.343 43.013 10-JAN-10 10 24 00.0 48.841 48.780 48.760 48.566 48.726 48.760 48.774 48.736 44.421 43.013 10-JAN-10 10 25 00.0 48.832 48.840 48.772 48.580 48.630 48.635 48.774 48.795 44.423 43.026 10-JAN-10 10 26 00.0 48.699 48.655 48.630 48.460 48.704 48.627 48.628 48.585 44.361 42.910 10-JAN-10 10 27 00.0 48.902 48.808 48.902 48.684 48.752 48.739 48.889 48.814 44.492 43.051 10-JAN-10 10 28 00.0 48.846 48.792 48.689 48.505 48.705 48.718 48.774 48.723 44.389 43.061 10-JAN-10 10 29 00.0 48.865 48.800 48.686 48.502 48.787 48.753 48.787 48.705 44.462 42.954 10-JAN-10 10 30 00.0 48.785 48.832 48.724 48.518 48.614 48.609 48.593 48.535 44.420 43.077 10-JAN-10 10 31 00.0 48.889 48.821 48.764 48.631 48.798 48.740 48.740 48.771 44.474 43.046 10-JAN-10 10 32 00.0 48.954 48.792 48.813 48.604 48.712 48.686 48.784 48.697 44.474 43.045 10-JAN-10 10 33 00.0 48.827 48.840 48.809 48.596 48.795 48.768 48.809 48.718 44.373 42.965 10-JAN-10 10 34 00.0 48.897 48.747 48.771 48.619 48.702 48.670 48.885 48.806 44.417 43.029 10-JAN-10 10 35 00.0 48.888 48.825 48.760 48.612 48.716 48.692 48.833 48.811 44.380 43.029 10-JAN-10 10 36 00.0 48.941 48.829 48.856 48.556 48.744 48.660 48.736 48.655 44.495 43.029 10-JAN-10 10 37 00.0 48.843 48.768 48.718 48.529 48.710 48.683 48.758 48.787 44.402 43.011 10-JAN-10 10 38 00.0 48.918 48.862 48.696 48.514 48.808 48.739 48.886 48.803 44.524 43.053 10-JAN-10 10 39 00.0 48.752 48.779 48.788 48.681 48.612 48.593 48.761 48.691 44.333 42.992 10-JAN-10 10 40 00.0 48.787 48.710 48.788 48.607 48.788 48.755 48.819 48.724 44.380 43.051 10-JAN-10 10 41 00.0 48.787 48.710 48.788 48.607 48.788 48.755 48.819 48.724 44.380 43.051 10-JAN-10 10 42 00.0 48.787 48.710 48.788 48.607 48.788 48.755 48.819 48.724 44.380 43.051 10-JAN-10 10 43 00.0 48.787 48.710 48.788 48.607 48.788 48.755 48.819 48.724 44.380 43.051 10-JAN-10 10 44 00.0 48.787 48.710 48.788 48.607 48.788 48.755 48.819 48.724 44.380 43.051 10-JAN-10 10 45 00.0 48.787 48.710 48.788 48.607 48.788 48.755 48.819 48.724 44.380 43.051

DATE/TIME *R0004X* *R0004Y* *CECORASI**CECORFRT**CECORFXY* * % PWR* * % PWR* ** ASIU **********************

10-JAN-10 08 15 00.0 45.228 47.377 0.000 0.000 1. 660 10-JAN-10 08 16 00.0 45.385 47.071 0.000 0.000 1. 660 10-JAN-10 08 17 00.0 45.293 46.974 0.000 0.000 1. 660 10-JAN-10 08 18 00.0 45.322 47.373 0.000 0.000 1. 660 10-JAN-10 08 19 00.0 45.333 47.583 0.000 0.000 1. 660 10-JAN-10 08 20 00.0 45.333 48.732 0.000 0.000 1. 660 10-JAN-10 08 21 00.0 45.264 46.220 0.000 0.000 1. 660 10-JAN-10 08 22 00.0 45.327 46.838 0.000 0.000 1. 660 10-JAN-10 08 23 00.0 45.420 47.601 0.000 0.000 1. 660 10-JAN-10 08 24 00.0 45.287 47.564 0.000 0.000 1. 660 10-JAN-10 08 25 00.0 45.380 46.583 0.000 0.000 1. 660 10-JAN-10 08 26 00.0 45.304 47.332 0.000 0.000 1. 660 10-JAN-10 08 27 00.0 45.351 47.139 0.000 0.000 1. 660 10-JAN-10 08 28 00.0 45.280 45.388 0.000 0.000 1. 660 10-JAN-10 08 29 00.0 45.290 47.460 0.000 0.000 1. 660 10-JAN-10 08 30 00.0 45.338 47.250 0.000 0.000 1. 660 10-JAN-10 08 31 00.0 45.394 47.212 0.000 0.000 1. 660 10-JAN-10 08 32 00.0 45.301 49.367 0.000 0.000 1. 660 10-JAN-10 08 33 00.0 45.306 49.069 o.ooo 0.000 1. 660 10-JAN-10 08 34 00.0 45.340 48.106 0.000 0.000 1. 660 10-JAN-10 08 35 00.0 45.284 48.120 0.000 0.000 1. 660 10-JAN-10 08 36 00.0 45.189 47.936 0.000 0.000 1. 660 10-JAN-10 08 37 00.0 44.708 4 7. 766 0.000 0.000 1. 660 10-JAN-10 08 38 00.0 44.463 45.901 0.000 0.000 1.660 10-JAN-10 08 39 00.0 44.370 48.096 0.000 0.000 1. 660 10-JAN-10 08 40 00.0 44.272 47.519 0.000 0.000 1. 660 10-JAN-10 08 41 00.0 44.088 48.178 0.000 0.000 1. 660 10-JAN-10 08 42 00.0 44.056 48.186 0.000 0.000 1. 660 10-JAN-10 08 43 00.0 43.952 47.131 0.000 0.000 1.660 10-JAN-10 08 44 00.0 43.921 47.649 0.000 0.000 1.660

Page 113: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

10-JAN-10 08 45 00.0 43.896 47.500 0.000 0.000 1.660 10-JAN-10 08 46 00.0 43.662 45.449 0.000 0.000 1. 660 10-JAN-10 08 47 00.0 43.806 47.104 0.000 0.000 1. 660 : 10-JAN-10 08 48 00.0 43.756 46.269 0.000 0.000 1. 660 10-JAN-10 08 49 00.0 43.716 50.061 0.000 0.000 1. 660 10-JAN-10 08 50 00.0 43.633 48.210 0.000 0.000 1. 660 10-JAN-10 08 51 00.0 43.590 46.704 0.000 0.000 1. 660 10-JAN-10 08 52 00.0 43.506 45.851 0.000 0.000 1. 660 10-JAN-10 08 53 00.0 43.478 46.708 0.000 0.000 1. 660 10-JAN-10 08 54 00.0 43.521 45.447 0.000 0.000 1. 660 10-JAN-10 08 55 00.0 43.479 45.317 0.000 0.000 1. 660 10-JAN-10 08 56 00.0 43.508 46.497 0.000 0.000 l. 660 10-JAN-10 08 57 00.0 43.522 47.173 0.000 0.000 1. 660 10-JAN-10 08 58 00.0 43.534 46.982 0.000 0.000 l. 660 10-JAN-10 08 59 00.0 43.518 46.282 0.000 0.000 l. 660 10-JAN-10 09 00 00.0 43.494 46.696 0.000 0.000 1. 660 10-JAN-10 09 01 00.0 43.603 46.128 0.000 0.000 1. 660 10-JAN-10 09 02 00.0 43.519 44.684 0.000 0.000 1. 660 10-JAN-10 09 03 00.0 43.550 47.032 0.000 0.000 l. 660 10-JAN-10 09 04 00.0 43.638 45.244 0.000 0.000 1.660 10-JAN-10 09 OS 00.0 43.577 47.612 0.000 0.000 1.660 10-JAN-10 09 06 00.0 43.577 46.821 0.000 0.000 1.660 10-JAN-10 09 07 00.0 43.593 47.721 0.000 0.000 1.660 10-JAN-10 09 08 00.0 43.582 48.269 0.000 0.000 1.660 10-JAN-10 09 09 00.0 43.691 47.529 0.000 0.000 1.660 10-JAN-10 09 10 00.0 43.704 46.889 0.000 0.000 1.660 10-JAN-10 09 11 00.0 43.760 48.723 0.000 0.000 1.660 10-JAN-10 09 12 00.0 43.744 47.188 0.000 0.000 1.660 10-JAN-10 09 13 00.0 43.704 47.304 0.000 0.000 1. 660 10-JAN-10 09 14 00.0 43.696 47.572 0.000 0.000 l. 660 10-JAN-10 09 15 00.0 43.660 47.295 0.000 0.000 l. 660 10-JAN-10 09 16 00.0 43.938 45.889 0.000 0.000 1. 660 10-JAN-10 09 17 00.0 43.829 47.322 0.000 0.000 1. 660 10-JAN-10 09 18 00.0 43.917 47.788 0.000 0.000 l. 660 10-JAN-10 09 19 00.0 43.986 4 7. 429 0.000 0.000 l. 660 10-JAN-10 09 20 00.0 44.269 47.974 0.000 0.000 1. 660 10-JAN-10 09 21 00.0 44.462 47.643 0.000 0.000 1. 660 10-JAN-10 09 22 00.0 44.397 47.931 0.000 0.000 l. 660 10-JAN-10 09 23 00.0 44.681 46.902 0.000 0.000 l. 660 10-JAN-10 09 24 00.0 44.861 47.433 0.000 0.000 1. 660 10-JAN-10 09 25 00.0 44.963 48.359 0.000 0.000 1. 660 10-JAN-10 09 26 00.0 44.963 47.696 0.000 0.000 l. 660 10-JAN-10 09 27 00.0 44.986 48.426 0.000 0.000 1. 660 10-JAN-10 09 28 00.0 44.902 50.014 0.000 0.000 1.660 10-JAN-10 09 29 00.0 45.117 49.486 0.000 0.000 1. 660 10-JAN-10 09 30 00.0 45.119 49.228 0.000 0.000 1. 660 10-JAN-10 09 31 00.0 45.313 49.101 0.000 0.000 1. 660 10-JAN-10 09 32 00.0 45.231 46.543 0.000 0.000 1. 660 10-JAN-10 09 33 00.0 45.112 47.678 0.000 0.000 l. 660 10-JAN-10 09 34 00.0 45.165 48.300 0.000 0.000 l. 660 10-JAN-10 09 35 00.0 45.255 48.240 0.000 0.000 1.660 10-JAN-10 09 36 00.0 45.321 49.992 0.000 0.000 1.660 10-JAN-10 09 37 00.0 45.194 48.966 0.000 0.000 1.660 10-JAN-10 09 38 00.0 45.064 46.309 0.000 0.000 1.660 10-JAN-10 09 39 00.0 45.260 48.439 0.000 0.000 1.660 10-JAN-10 09 40 00.0 45.210 48.830 0.000 0.000 1.660 10-JAN-10 09 41 00.0 45.311 50.253 0.000 0.000 1.660 10-JAN-10 09 42 00.0 45.269 47.845 0.000 0.000 1. 660 10-JAN-10 09 43 00.0 45.184 48.657 0.000 0.000 1. 660 10-JAN-10 09 44 00.0 45.263 49.196 0.000 0.000 1.660 10-JAN-10 09 45 00.0 45.263 47.407 0.000 0.000 1. 660 10-JAN-10 09 46 00.0 45.168 48.407 0.000 0.000 1. 660

Page 114: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

10-JAN-10 09 47 00.0 45.189 47.750 0.000 0.000 1.660 10-JAN-10 09 48 00.0 45.099 45.941 0.000 0.000 1.660 10-JAN-10 09 49 00.0 44.758 45.990 0.000 0.000 1.660 10-JAN-10 09 50 00.0 44.292 47.726 0.000 0.000 1.660 i'

' 10-JAN-10 09 51 00.0 43.880 48.136 0.000 0.000 1.660 10-JAN-10 09 52 00.0 43.843 47.989 0.000 0.000 1. 660 10-JAN-10 09 53 00.0 43.660 48.776 0.000 0.000 1. 660 10-JAN-10 09 54 00.0 43.497 45.405 0.000 0.000 1. 660 10-JAN-10 09 55 00.0 43.357 47.571 0.000 0.000 1. 660 10-JAN-10 09 56 00.0 43.353 47.902 0.000 0.000 1. 660 10-JAN-10 09 57 00.0 43.260 46.920 0.000 0.000 1. 660 10-JAN-10 09 58 00.0 43.125 48.652 0.000 0.000 1. 660 10-JAN-10 09 59 00.0 43.313 46.054 0.000 0.000 1. 660 10-JAN-10 10 00 00.0 43.167 47.514 0.000 0.000 1. 660 10-JAN-10 10 01 00.0 43.114 46.492 0.000 0.000 1. 660 10-JAN-10 10 02 00.0 43.236 48.654 0.000 0.000 1.660 10-JAN-10 10 03 00.0 43.356 47.484 0.000 0.000 1. 660 10-JAN-10 10 04 00.0 43.258 48.207 0.000 0.000 1. 660 10-JAN-10 10 OS 00.0 43.208 47.766 0.000 0.000 1. 660 10-JAN-10 10 06 00.0 43.282 46.750 0.000 0.000 1. 660 10-JAN-10 10 07 00.0 43.290 46.942 0.000 0.000 1. 660 10-JAN-10 10 08 00.0 43.231 48.117 0.000 0.000 1.660 10-JAN-10 10 09 00.0 43.247 47.325 0.000 0.000 1.660 10-JAN-10 10 10 00.0 43.154 47.436 0.000 0.000 1.660 10-JAN-10 10 11 00.0 43.175 46.675 0.000 0.000 1.660 10-JAN-10 10 12 00.0 43.155 47.421 0.000 0.000 1.660 10-JAN-10 10 13 00.0 43.236 46.354 0.000 0.000 1.660 10-JAN-10 10 14 00.0 43.093 46.035 0.000 0.000 1.660 10-JAN-10 10 15 00.0 43.574 49.051 0.000 0.000 1. 660 10-JAN-10 10 16 00.0 43.737 45.949 0.000 0.000 1. 660 10-JAN-10 10 17 00.0 44.450 45.534 0.000 0.000 1. 660 10-JAN-10 10 18 00.0 44.441 47.970 0.000 0.000 1. 660 10-JAN-10 10 19 00.0 44.636 48.880 0.000 0.000 1. 660 10-JAN-10 10 20 00.0 44.838 48.897 0.000 0.000 1. 660 10-JAN-10 10 21 00.0 44.861 48.444 0.000 0.000 1. 660 10-JAN-10 10 22 00.0 44.796 50.386 0.000 0.000 1. 660 10-JAN-10 10 23 00.0 44.780 48.415 0.000 0.000 1. 660 10-JAN-10 10 24 00.0 44.878 47.665 0.000 0.000 1. 660 10-JAN-10 10 25 00.0 44.878 47.269 0.000 0.000 1. 660 10-JAN-10 10 26 00.0 44.721 45.595 0.000 0.000 1. 660 10-JAN-10 10 27 00.0 44.909 46.787 0.000 0.000 1. 660 10-JAN-10 10 28 00.0 44.819 49.260 0.000 0.000 1. 660 10-JAN-10 10 29 00.0 44.803 46.530 0.000 0.000 1. 660 10-JAN-10 10 30 00.0 44.883 44.470 0.000 0.000 1. 660 10-JAN-10 10 31 00.0 44.856 45.481 0.000 0.000 1. 660 10-JAN-10 10 32 00.0 44.901 46.971 0.000 0.000 1.660 10-JAN-10 10 33 00.0 44.821 46.609 0.000 0.000 1. 660 10-JAN-10 10 34 00.0 44.915 47.691 0.000 0.000 1.660 10-JAN-10 10 35 00.0 44.893 46.013 0.000 0.000 1. 660 10-JAN-10 10 36 00.0 44.893 47.160 0.000 0.000 1.660 10-JAN-10 10 37 00.0 44.832 46.913 0.000 0.000 1.660 10-JAN-10 10 38 00.0 45.016 48.606 0.000 0.000 1.660 10-JAN-10 10 39 00.0 44.840 49.478 0.000 0.000 1.660 10-JAN-10 10 40 00.0 44.926 47.832 0.000 0.000 1.660 10-JAN-10 10 41 00.0 44.926 47.832 0.000 0.000 1.660 10-JAN-10 10 42 00.0 44.926 47.832 0.000 0.000 1. 660 10-JAN-10 10 43 00.0 44.926 47.832 0.000 0.000 1. 660 10-JAN-10 10 44 00.0 44.926 47.832 0.000 0.000 1. 660 10-JAN-10 10 45 00.0 44.926 47.832 0.000 0.000 1. 660

Page 115: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Memorandum

DATE: January 6, 2010

FROM: T.A. Heng

TO: P. Cronin B.P. Schawe

NED-10-0002 RPA

SUBJECT: Cycle 26 Predictions for Beginning of Cycle MTC Test

Data has been generated in support of the Cycle 26 Beginning of Cycle (BOC) Moderator Temperature Coefficient (MTC) test. The data is provided in the attachment to this memo and includes predictions for lTC, MTC, and FTC perturbations of -1 0°F and -5°F from the nominal core inlet temperature of 543°F, power coefficients (PC) at perturbations of -5% and -7% power from the nominal core power of 98%, and CEA 4-1 worth versus position. The data was calculated at a predicted burnup of 495 MWD/MTU.

If you have any questions or comments regarding this information, please feel free to contact me at extensi n 7212 or Don Williamson at extension 7214.

Acting Supervisor-Reactor Performance Analysis

TAWdrw/bap

Attachment

cc: J. E. Willett NED Correspondence File

~r? ==-----Uflfill OnWJa Public Power District 4167

Page 116: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

··-------------------~-

Attachment NED-10-0002 RPA Cycle 26 Predictions for BOC MTC Test

ATTACHMENT

The attached data was prepared and reviewed by the foUowing personnel.

Prepared by:

Nuclear Engineer I -Reactor Perfonnance

Reviewed by:

Richard Roenigk Senior Nuclear Design Engineer- Reactor Perfonnance

Page I of3

'Dke

//(,/'24/D Date

Page 117: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

.-- ------------~------------------------------

Attachment NED-I 0-0002 RP A Cycle 26 Predictions for BOC MTC Test

Unbiased Predicted lTC, MTC, FTC, and PC Biased Predicted lTC and MTC

Parameter

lTC

lTC

MTC

MTC

FTC

FTC

PC

PC

20

0

-20

-140

-160

-180

Perturbation Unbiased Value Pelt1lrbatlon Unbiased Parameter ('F) Value

(pcmrF)

-10'F -9.86 pcmi"F lTC -10 -9.86

-5'F -10.17 pcm/'F lTC -5 -10.17

-10'F -8.55 pcmi"F MTC -10 -8.55

-5'F -8.86 pcm/'F MTC -5 -8.86

-10'F -1.31 pcmi"F

-5'F -1.31 pcmi"F Associated Parameters

-5% Power -13.59 pcmi%Power CBC@ Test Cond. (ppm) 1049

-7%Power -13.59 pcm/%Power MTC/JTC Bias (pcm/"F) -0.588

BOC Cycle 26 CEA 4-1 Worth vs. Position (Group 4 at 114.5 Inches Withdrawn)

0

-20

-60

-80

-100

-120

Ril -140

-160

-180

CEA 4-1 position (Inches withdrawn)

Page2 of3

Biased Value

(pcmrF)

-10.448

-10.758

-9.138

-9.448

Page 118: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Attachment NED-I 0-0002 RP A Cycle 26 Predictions for BOC MTC Test

Predicted CEA 4-1 Worth

CEA Position k-effectlve worth worth {%dp) (pcm)

126.0 1.00156 0.0090 9.0

120.0 1.00153 0.0060 6.0

115.0 1.00148 0.0010 1.0 114.5 1.00147 0.0000 0.0 110.0 1.00140 -0.0070 -7.0

105.0 1.00132 -0.0150 -15.0

100.0 1.00122 -0.0250 -25.0

95.0 1.00113 -0.0340 -34.0 90.0 1.00103 -0.0439 -43.9

85.0 1.00094 -0.0529 -52.9

80.0 1.00085 -0.0619 -61.9

75.0 1.00076 -0.0709 -70.9

70.0 1.00067 -0.0799 -79.9

65.0 1.00059 -0.0879 -87.9

.60.0 1.00051 -0.0959 -95.9

55.0 1.00043 -0.1039 -103.9

50.0 1.00035 -0.1119 -111.9

45.0 1.00028 -0.1189 -118.9

40.0 1.00020 -0.1269 -126.9

35.0 1.00013 -0.1339 -133.9

30.0 1.00006 -0.1409 -140.9

25.0 0.99999 -0.1479 -147.9

20.0 0.99993 -0.1539 -153.9 15.0 0.99986 -0.1609 -160.9

10.0 0.99980 -0.1669 -166.9

5.0 0.99975 -0.1719 -171.9

0.0 0.99972 -0.1749 -174.9

Page3 of3

Page 119: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

. '

FORT CALHOUN STATION FORM

SURVEILLANCE TEST COVERSHEET

11~1 ~IIIII ~11111111 ~1111~1 ~~ li ru1100 mIll Surveillance Test Number: RE-ST-RX-0003 Work Order Package No: 00381908 01

Title: Moderator Temperature Coefficient Determination Using Center Cea

Due Date: 12/13/10 Early Date: 8/9/10 I Drop Date: 4/18/11 Frequency: W72 EEQ:N Scaffold: N I Trendin~r N RWP: N Tagout: N IPMID: 00000613 Special Conditions:

1. Reason for Test (if other than scheduled):

2. Postponement explanation (if required):

Expected Completion: I Supervisor or System Engineer: Date:

3. Test results acceptable? [)(J Yes [ J No Tech Specs satisified? (Not require9'for ~ept~ble wst) [ ] Yes [ 1 No Supervisor or System Engineer: 'I I 1\.4 f./ f.( .... Date: (/ q ('Yo!! Time: l'hi7 Additional Code analysis required wit~ n 72 hours? [ ] Yes I [ 1 No I (')(J N/A

STA Initials: ,J.> Date:\ 1"'11\ Responsible System Engineer: SCHAFFER, CHARLES H

4. ST Coordinator initial test review Initials: I JI.!J Oat~: {-tD 1 WO required? [ ] Yes v ( I{No

Frequency Increased? [ ] Yes [ 'No CR required? [ ] Yes [1- No Retest required? [ 1 Yes [ i(No System Engineer test review: K Initials: Date: 1ST Coordinator test review: ~ Initials: Date: ST Coordinator final test closeout review: Initials: Ki25 Date: 3~25= 1 J

(SO-G-23)

Page 120: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

' .

Fort Calhoun Station Unit No.1

RE-ST -RX-0003

SURVEILLANCE TEST

PAGE 1 OF 17

MODERATOR TEMPERATURE COEFFICIENT DETERMINATION USING CENTER CEA

Change No. EC 47997

Reason for Change Added ROD BLOCK as an expected alarm. Prerequisite for running charging pumps changed to allow flushing. Prerequisite to verify TS 2.1 0.4(5)(a) revised to remove reference to Gardel being inoperable. Prerequisite for bypassing CVCS ion exchangers changed to remove the optional bypassing at shift manager's discretion. Changed note prior to Step 7.9 to remove using XC105 to maintain power constant and added further guidance on Delta-T power. Added a note prior to step 7.20 concerning the need to reset VHPT when restoring power. Revised step 7.24 concerning the Load Limit Potentiometer.

Requestor B. Schawe

Pre parer L. Hautzinger

Issue Date 12-21-09 3:00pm

R27

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 2 OF 17

MODERATOR TEMPERATURE COEFFICIENT DETERMINATION USING CENTER CEA

SAFETY RELATED

1. PURPOSE

1.1 To satisfy, at any power level within 500 MWD/MTU of initial operation after each refueling, the requirements of Technical Specification 3.1 0(2)2 OR, at any power level within fourteen(± 14) Effective Full Power Days of reaching a Rated Power Equilibrium Boron Concentration of 300 ppm, the requirements of Technical Specification 3.1 0(2)3 for the Moderator Temperature Coefficient.

1.2 This test provides a means of determining the Moderator Temperature Coefficient from the Isothermal Temperature Coefficient.

2. REFERENCES/COMMITMENT DOCUMENTS

2.1 Technical Specifications:

• 2.10.2, Reactivity Control Systems and Core Physics Parameters Limits • 2.10.4(5), DNBR Margin During Power Operation Above 15% of Rated Power • 3.1 0, Reactor Core Parameters

2.2 Operating Instructions:

• 01-ERFCS-1, Emergency Response Facility Computer System (LAN) • 01-NI-2, In-Core Instrumentation Operability Requirements

2.3 SO-G-23, Surveillance Test Program

2.4 Ongoing Commitments

• AR 14801, LER 93-016

3. DEFINITIONS

None

4. TOOLS AND EQUIPMENT

None

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..

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST -RX-0003 PAGE 3 OF 17

5. PRECAUTIONS AND LIMITATIONS

5.1 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted on the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

5.2 Technical Specification 2.1 0.2(9)a.ii allows for CEA 1 to be misaligned from Group 4 during performance of this test.

5.3 Rod Block Circuitry will prevent Rod Group 4 movement if CEA 1 is misaligned by more than 8 inches, therefore if Group 4 motion is required CEA 1 will have to be aligned with Group 4 to allow movement.

5.4 Pressurizer Level will follow T avg and may result in a back up Charging Pump start on low level.

5.5 Pressurizer level changes will affect VCT pressure, which may adversely affect Reactor Coolant Pump bleed-off pressure and temperature. Close monitoring of bleed-off temperature and/or pressure is advised during the performance of this test.

5.6 Axial Shape Index (AS I) should be monitored to ensure ASI Limits are not exceeded during CEA movement.

5.7 The following guidelines will apply when changing parameters for testing:

• Tcold decrease of approximately 10oF or Generator Electrical Load decrease of 24 to 26 MWe

• CEA 1 has been inserted 80 inches from its initial position

5.8 Anytime the Mode Selector Switch is in any position other than OFF, all available rod position indications shall be monitored - Syncros, SCEAPIS, ERF (page 302), and Core Mimic. [AR 14801]

5.9 If a CEA position abnormality occurs verify the position of all CEAs. [AR 14801]

5.10 When CEAs are not being moved, the Rod Control Mode Selector Switch shall always be left in the OFF position.

5.11 The Reactor Engineer shall be notified within 24 hours of the completion of this test of any unexpected results.

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..

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE4 OF 17

5.12 The following annunciator windows will be affected by the performance of this procedure:

• CEDM GROUND (CB-4, A?, D-1L) • ROD DRIVE POWER INTERRUPT (CB-4, A8, A-5U) • ROD POSITION DEVIATION LOW LIMIT (CB-4, A8, B-1 U) • ROD POSITION DEVIATION LOW-LOW LIMIT (CB-4, A8, B-1 L) • POll GR 4 COMPUTER (CB-4, A8, B-3L) • PPDIL GR 4 COMPUTER (CB-4, A8, B-4L) • REACTOR REGULATING SYSTEM LOOP 1 TREF/TAVG GROSS DEV (CB-4,

A8, D-1 U) • REACTOR REGULATING SYSTEM LOOP 1 & 2 TAVG DEV (CB-4, A8, C-1L) • REACTOR REGULATING SYSTEM LOOP 2 TREF/TAVG GROSS DEV (CB-4,

A8, D-1 L) • NUCLEAR ~T POWER CHANNEL DEVIATION (CB-4, A20, E-6) • VOLUME CONTROL TANK LEVEL HI-LO (CB-1/2/3, A2, B-2U) • PRESSURIZER PRESSURE OFF NORMAL HI-LO CHANNEL X (CB-1/2/3, A4,

A-4) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO A/P102X

(CB-1/2/3, A4, A-7) • PRESSURIZER LEVEL HI-LO CHANNEL X (CB-1/2/3, A4, A-8) • PRESSURIZER PRESSURE OFF NORMAL HI-LO CHANNEL Y (CB-1/2/3, A4,

B-4) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO B/P102X

(CB-1/2/3, A4, B-7) • PRESSURIZER LEVEL HI-LO CHANNEL Y (CB-1/2/3, A4, B-8) • PRESSURIZER SURGE LINE TEMP LO (CB-1/2/3, A4, C-1) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO C/P102X

(CB-1/2/3, A4, C-7) • PRESSURIZER LO PRESSURE SETPOINT OFF NORMAL HI-LO D/P102X

(CB-1/2/3, A4, D-7) • HEATER DRAIN TANK LEVEL HI-LO (CB-10/11, A11, B-3U) • Various EXTRACTION STEAM PRESSURE ALARMS (ERF)

5.1:3 The following DCS alarms will be affected by the performance of this procedure:

• PPDIL • PDIL • DEV • ROD BLOCK

5.14 Do NOT allow Steam Generator pressure to fall below 770 psia.

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 5 OF 17

6. PREREQUISITES IN ITIALSIDA TE

6.1 Procedure Revision Verification:

Revision No. 'Z] ~~l·'i-11

6.2 No other test is in progress which could potentially affect this test, or if this test were performed, could have an effect on that test. l4i.- I 1·1·11

6.3 Group 4 is inserted to 11 0" ± 5 inches. :>i-t- I l · f ·1 1

6.4 Reactor Power is at least 5% below the power level at which fuel has been preconditioned or as directed by the Reactor Engineer. 7'!£. I ;. r. I (

6.5 lncore Detectors are operable and monitoring Linear Heat Rate for power levels above 5%. 541.--1 / r ;I

6.6 The Reactor is at Equilibrium Xenon condition for the current power level (AS I = ESI ± 0.005 for the last 6 hours). 141 I 1· 1' If

6.7 All available Charging Pump Packing Cooling Pumps have been running for 30 minutes. ?'!1.--1 I· f · I 1

6.8 All available Charging Pumps have been run or flushed to ensure the piping for each pump contains water at the same Boron ""VtAI I· a.;t Concentration as the RCS. /"H..- t

6.9 The Energy Marketer has been notified that fluctuations in Station Output will occur as a result of this test. "")4i..- I I ·1' 1/

6.10 RCS and Pressurizer Boron Concentration are within 20 ppm or Pressurizer Heater and Spray Operation has been maximized for ..riA 1 at least 24 hours. H;t...- 1 /. CJ • I

6.11 An additional Licensed Operator is available for manual control of """' ~ systems during the test. '"r''-1 l· f. fl

6.12 A briefing per SO-G-92 has been conducted prior to the start of this test.

6.13 A prejob briefing has been conducted prior to the start of this test.

6.14 Verify the requirements of Technical Specification 2.1 0.4(5)(a) will be met during the performance of this test.

SO-G-92 Briefing Manager

Al{l 1thltt RE ~~

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 6 OF 1] I w...-

7.

6.15 RCS Zinc Injection is secured.

6.16 Obtain Predicted Fuel Temperature Coefficient (FTC) from Reactor Performance Analysis (RPA):

-1,,57 ,{ Jo -S llp/"F

6.17 Obtain Summary of Coefficient and Perturbation Calculations (RPA) illustrating:

• MTC Bias • Predicted MTC (-1 o•F perturbation) • Predicted MTC (-s·F perturbation)

6.18 Ensure CVCS len Exchangers are bypassed during the performance of this test.

6.19 Manual control of Letdown should be taken during the performance of this test at Shift Manager's discretion. N/A if not desired.

6.20 Shift Manager authorizes perfo;mance of this test:

1-'i-1 .J( 14-L-I~ ,.T,

~ 1·1'·11

~,,.q.,,

Shift Mgr

Shift M'"''" ~/I LPtt~ uKJ t Date/Time I-'J·II, t>'OJ(.e

PROCEDURE

NOTE: Step 7.1 can be perf-~ at anytime and repeated as necessary. 7'"cu

7.1 If this Surveillance Test is turned over, a prejob briefing must be conducted prior to the continuation of this test.

7.2 At the RPSCIP DVM display the following parameters:

• RCS Cold Leg Temperature ~-• /lTPower ~

NOTE: Attachment 9.2 shows t~ints that are normally in Trend Block 11.

7.3 Note the current time generating the TB11 Group Trend Report later in this procedure.

Time 0~1]

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST -RX-0003 PAGE 7 OF 17

NOTE: Disabling of Insertion D~on Limit Program on ERF Computer requires a Level 4 )9f'erations) Security Level or greater.

7.4 To ensure unnecessary Insertion Duration Limit program MW Thermal Alarms are not accumulated, change the CEA Program Control "Program Mode" to "TEST" on ERF Page CLU.

7.5 Ensure following CEA System Switches are placed in required position:

Switch Required

CEA Group Selector GP 4

Individual CEA Selector 1

7.6 Record latest RCS Boron Concentration

_7-=c--..:7_'?,__ __ ppm

7.7 Record As Found position ofTurbine Load Limit Pot.

7.8 Complete Attachment 9.1 (Variable Tavg Test Record).

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 8 OF 17

NOTE: When lowering the RCS Cold Leg mperature (Tcold) in Step 7 .9, Step 7.10 will be used to main 1n a constant b. T Power (± 0.2%) with CEA 1. b. T Power flue tes considerably, so target the final value to be nominally within 0. Yo of the · itial value.

NOTE: Experience has shown that adju mg the Turbine Load Potentiometer at a rate of two notche per 30 seconds provides the best control for this test. Additiona , when approaching each endpoint, the rate should be red ed to 1 notch every 20 seconds.

CAUTION During the test, Makeup to the Volum ontrol Tank should be maintained at the same Boron Con ntration as that prior to testing.

Pressurizer Level will follow cha es in Tavg even when power remains CAU~ION

constant.

Axial Shape Index should be mo ored during CEA movement to CAU~ION

ensure that ASI Operating Li · s are not exceeded.

CAUTIO Do NOT allow Steam Generat pressure to fall below 770 psia.

7.9 With the Turbine Control Valves, lower the RCS Tcold until:

• Tcold has been reduced by 1 ooF OR

• CEA 1 has been inserted 80 inches from its initial position OR

• Steam Generator Pressure reduces to 770 psia

7.10 During reduction ofT cold maintain Loop b.T Power constant by inserting CEA 1, in Manual Individual Mode.

7.11 WHEN reduction in Tcold is complete and Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

NOTE: Step 7.12 is not apf1 · le ~s to be returned to the initial temperature immediate! .

7.12 Prior to increasing T cold. complete Attachment 9.1 (Variable Tavg Test Record).

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FORT CALHOUN STATION SURVEILLANCE TEST

RE-ST-RX-0003 PAGE 9 OF 17

NOTE: Steps 7.13 and 7.14 e pe~d concurrently.

7.13 With the Turbine Control Valves, raise RCS Tcord to its normal temperature.

7.14 When raising T cord. maintain .t:.. T Power at a constant value by withdrawing CEA 1, in Manual Individual Mode.

7.15 WHEN Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

7.16 If requested by the Reactor Engineer, perform Steps 7.9 through 7.15 for additional data.

NOTE: During the reduction of the nerator Electrical Load in Step 7.17, Step 7.18 will be perfo ed to maintain Tcord constant(± 0.2°F) with CEA 1.

/

NOTE: Experience has shown that adj ing the Turbine Load Potentiometer at a rate of two notche per 30 seconds provides the best control for this test. Addition , when approaching each endpoint, the rate should be red ed to 1 notch every 20 seconds.

7.17 With the Turbine Control Valves, reduce Generator Electrical Load until:

• Generator Electrical Load (MWe) has been reduced by 24 to 26 MWe

OR • CEA 1 has been inserted 80 inches from its initial position

7.18 When lowering Generator Load, maintain Tcord constant by inserting CEA 1, in Manual Individual Mode.

7.19 WHEN the reduction in Generator Load is complete and Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record). /

NOTE: Steps 7.20 and 7.21 are prormed concurrently.

NOTE: While restoring power to J:initialload, reset VHPT as required. 7"~

CAUTION~ Do not exceed 100% of Rated Powe R the Administrative Power Limit when this test is being perfor ed at 100% power.

7.20 With Turbine Control Valves, increase Generator Load to the initial load. ~

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST -RX-0003 PAGE 10 OF 17

7.21 WHEN raising Generator Load, THEN maintain Tcold at a constant value by withdrawing CEA 1, in Manual Individual Mode.

7.22 WHEN Reactor conditions have stabilized, THEN complete Attachment 9.1 (Variable Tavg Test Record).

7.23 If requested by the Reactor Engineer, perform Step 7.17 through 7.22 for additional data.

7.24 Ensure Turbine Load Limit Pot is in As Found position recorded in Step 7. 7 or in a position for stabilizing the plant.

7.25 If necessary, align CEA 1 to the Group 4 position, in Manual Individual Mode.

7.26 On ERF Page CLU, change the CEA Program Control "Program Mode" back to OPERATE.

7.27 IF not needed for further testing, THEN on ERF Computer Page GTR, generate a Group Trend Report as follows:

~

-18L-

;1/ ~ ;'o/57

:141- !·~·~/

)I/A-1ti;

"'ll-L-

7.27.1 Adjust date and times to encompass the time recorded in Step 7.3 to -v~_, the current time. Values must be entered in the specified format. p=t"l---

7.27.2 Configure the interval to "one minute" and printer as desired. ~

7.27.3 Depress button "TB11" and verify report was successful. ~

8. RESTORATION

8.1 Energy Marketer notified of test completion.

8.2 Calculate MTC value using Attachment 9.3.

8.3 Shift Manager notified this test is completed.

Sh;ft MoM!"" ~-'t>~~ )__~uq f

~ 1-CJ·/1

~ 1·1-11

Date/Time !.f-It 1 ItS' (

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

8.4 Attach following to test package:

• All Variable Tavg Test Record Sheets [ .;]' • Calculations performed to determine Moderator ~

Temperature Coefficient [ • Any Graphs used in calculation [ • Rod Group Log printouts [ v( • Group Trend TB11 printout ( :..( • Any Trend Recorder Graphs designated by the Reactor /

Engineer [ v(

Compl•t.d by0a-11 ~vio f D•t•mm, 9. ATTACHMENTS

9.1 Variable Tavg Test Record

9.2 Points in Trend Block 11

9.3 MTC Calculation

9.4 Comment Sheet

10. ACCEPTANCE CRITERIA

RE-ST-RX-0003 PAGE110F17

1'f1:,;.rt·lf l·f/fJ t13f

10.1 No abnormalities in data or test conditions recorded on the Comment Sheet.

10.2 The value of Moderator Temperature Coefficient is:

-Z./08 )( IO -"1 llp/"F (Attachment 9.3, Step 9)

10.2.1 Less positive than +0.2x10-4llp/"F including uncertainties for power levels at or above 80% of rated power.

1 0.2.2 Less positive than +0.5x1 0-4 llp/"F including uncertainties for power levels below 80% of rated power.

1 0.2.3 More positive than the value specified in the COLR including uncertainties at rated power.

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 12 OF 17

11. PERFORMANCE AND REVIEW

11.1 Test data shall be evaluated by the STA and reviewed by the Shift Manager for acceptability within 24 hours of completion of this test.

Evaluated by...J%J;~::::.....:1-=--:=--------Date!Time\}O\..}\\ I lUI'\ STA

11.2 The results of the rator Temperature test have been reviewed and are acceptable in accordance with,Ste~ ~

Reactor Engineer ~W;~ Date/Time3tbA I o0,/7 Tl

Supervisor-Nuclear Engineering l1vt tA)~ ..L Date/Time '3/v-tj,, 1 12. '18 11.3 The Plant Manager or designee has reviewed the results of the Moderator

Temperature Coeffic~

Plant Manager~~ ~: •• :v--~ .... ~k-\.._ Date/Time $/Mill 113,2.\

11.4 If the test results do not meet the acceptance criteria, or at the Plant Manager's request, the Plant Review Committee has reviewed the results of the Moderator Temperature Coefficient test.

PRC Chairman ~ ~~uw\J Date/Time ~<4~01~ Y3~3 ~-~~\)~ie~

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FORT, CALHOUN STATION SURVEILLANCE TEST !

CONTINUOUS USE RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME O<od.' DATE \fti.l z..~· STEP NO. I .S f'r RECORD SHEET _l_oFl_

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

%.'\ % 6TPOWER

RPSCIP DVM: C(l.$ % 9_1. \ % '11·1 % AI-31A Al-318 AI-31C Al-310

C0.2 % 'f/.1 % co.s % "lu·l % AI-31A Al-31 8 AI-31C Al-310

f1i.u % ql.(p % q[./% ql..c~ % AI-31A Al-31 8 AI-31C Al-310

s'io.cr OF TcoLo

)'{(.-,oF S'~ '-" OF RPSCIP DVM: !)YoS OF AI-31A Al-31 8 AI-31C Al-31 D

.5'-\o:<?J OF c;tfo. ~OF ')'11·'-( OF ~'1 f .':J. OF

AI-31A Al-31 8 AI-31C Al-310

~'-\:~.5 OF 51.-/0 .lt OF 5'12.2-oF ~/.)oF AI-31A Al-31 8 AI-31C Al-31 D

RPSCIP DVM: s10e. ( OF T~oT S'D21. -OF ~.UoF JlAS.S OF

AI-31A Al-31 8 AI-31C Al-310

Nl POWER

RPSCIP DVM: cn..1:> % en.'-/% Cf.7,<; % Cjl.O %

AI-31A Al-31 8 AI-31C Al-31 D

ASI RPSCIP DVM: .O\Cf.>3 .ono .. o ll"Z- .o1S\

AI-31A Al-318 AI-31C Al-310

CEA Group Position Rod Group Log Printout ~w Time

Core Axial Shape Index ERF XC093 C.D~'Z.'\

Core Power ERF XC105 I L\(a l ,<-\0 MWth

Generator Load ERF Y3273 5~./4) MWe z. 7;J

RCS Boron Concen\):a,tion Latest Analysis 9: '7'f5' 111 ~t•141•tppm

Completed by/(// fl1£{ 1'!/._ ~; DatefTime /.fl. II I C/l1l.PJ

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OPPD Fort Calhoun Station Unit One CUrrent Rod Positions

Individual Rod Positions by Group

Shutdown A

RR30 RR31 RR32 RR33 RR34 RR35 RR36 RR37

126.5 126.3 126.9 126.2 127 .o 126.7 126.6 126.4

Shutdown B

RR14 RR15 RR16 RR17

125.7 126.2 126.0 126.4

Non trip

RR18 RR19 RR20 RR21

127.0 126.4 126.2 126.3

Group Positions: High, Average, Low, and Deviation

Posn High Avg Low

Dev

Shutdown A

RR37 RR34

RR33

126.4 127.0 126.6 126.2

0.8

Shutdown B

RR14 RR17

RR14

125.7 126.4 126.1 125.7

0.7

Nontrip

RR20 RR18

RR20

126.2 127.0 126.4 126.2

0.8

Group 1 ------------RR06 126.3 RR08 126.6 RR10 126.5 RR12 126.4

Group 1

RR06 RR08

RR06

126.3 126.6 126.5 126.3

0.3

Group 2 ------------RR22 126.4 RR23 126.4 RR24 126.7 RR25 126.5 RR26 126.4 RR27 127.0 RR28 126.7 RR29 126.4

Group 2

RR22 RR27

RR29

126.4 127.0 126.5 126.4

0.6

Sunday Jan 09, 2011 08:26 AM

Group 3 ------------RR02 127.1 RR03 126.4 RR04 127.2 RR05 126.4

Group 3

RR05 RR04

RR03

126.4 127.2 126.8 126.4

0.8

Group 4 ------------RR01 114.4 RR38 114.5 RR39 114.3 RR40 114.4 RR41 114.5

Group 4

RR01 RR38

RR39

114.4 114.5 114.4 114.3

0.2

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FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME ()(§:J_ DATE 1/Cdll STEP NO."'] • H A RECORD SHEET~ OF__]__

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

~TPOWER RPSCIP DVM: <\/.::)% q/.3% ~1."7 % q_& o %

AI-31A Al-31 B AI-31C Al-31 D

9 7.') % ~% 91-'1 % <J..u·2% A1-31A 1 AI-31C Al-310

5],~ % q /.'5"'% ql, \ % ~l(o.(o % AI-31A Al-31 B AI-31C Al-31 D

RPSCIP DVM: ~ '!)j .CD ° F Tc3LD

53'"f. 'F 5 3(.,.1 'F 535'·}'F AI-31A Al-31 B AI-31C Al-31 D

5~'-\."1 'F 5 -,4,1 'F s~v.4'F 53'>-t 'F AI-31A Al-31 B AI-31C AI-31D

5 3'1.1f> 'F 5)4-J'F 5 ~i.P-2 'F 5 3<;.::f 'F AI-31A Al-31 B AI-31C Al-310

RPSCIP DVM: ':)~.'1 'F ~1.crfrfq 1/l/tr g()J, 5Cfi~·i 'F 5fl3. 3'F

AI-31A Al-31 B AI-31C Al-310

Nl POWER

RPSCIP DVM: q(, ·( % q(,.) % ~5.~ % qs:_,.,- % AI-31A Al-31 B AI-31C Al-310

ASI RPSCIP DVM: . O'?Jllt ,03Ca'Z- 'O~[i-{ .()?[.~

AI-31A Al-31 B AI-31C Al-31 D

CEA Group Position Rod Group Log Printout 01;fU Time

Core Axial Shape Index ERF XC093 0 .0~<-\

Core Power ERF XC105 IYlZ. 'i'l-- MWth

Generator Load ERF Y3273 :B~ ,C(fbZ.. MWe ~7~

RCS Boron Concentration J,.atest Analysis J:lB ' 1 ~ 1 " ppm

~ JfYl!F _tJ _/? ~ -Completed by /(f /!. ~

Date/Time I {tfq I 09';,S7

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OPPD Fort Calhoun Station Unit One CUrrent Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 125.7 RR31 126.3 RR15 126.2 RR32 126.9 RR16 126.0 RR33 126.2 RR17 126.4 RR34 127.0 RR35 126.7 RR36 126.6 RR37 126.4

Group Positions: High, Average, Low,

Shutdown A Shutdown B ------------ ----~-------

Posn RR37 126.4 RR14 125.7 High RR34 127.0 RR17 126.4 Avg 126.6 126.1 Low RR33 126.2 RR14 125.7

Dev 0.8 0.7

Non trip

RR18 127.0 RR19 126.4 RR20 126.2 RR21 126.3

and Deviation

Nontrip ------------RR20 126.2 RR18 127.0

126.4 RR20 126.2

0.8

Sunday Jan 09, 2011 08:56 AM

Group 1 Group 2 Group 3 Group 4

RR06 126.3 RR22 126.4 RR02 127.1 RR01 36.4 RR08 126.6 RR23 126.4 RR03 126.4 RR38 114.5 RR10 126.5 RR24 126.7 RR04 127.2 RR39 114.3 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.4

RR26 126.4 RR41 114.5 RR27 127.0 RR28 126.7 RR29 126.4

Group 1 Group 2 Group 3 Group 4 ------------ ------------ ------------ ------------RR06 126.3 RR22 126.4 RR05 126.4 RR01 36.4 RR08 126.6 RR27 127.0 RR04 127.2 RR38 114.5

126.5 126.5 126.8 98.8 RR06 126.3 RR29 126.4 RR03 126.4 RR01 36.4

0.3 0.6 0.8 78.1

Page 136: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME O'i\'1 DATE 1/'l/11 STEP NO. ].15~ RECORD SHEET _L OF 2_ <va P.>

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

RPSCIP DVM: ~l.l% toT POWER Cfu.'l % 'f/.IJ % q":z_%

AI-31A Al-31 B AI-31C Al-31 D

q.,-; ... llJo''' 9Lt-~ % q,_ I % 5lD :z. % AI-31A Al-31 B AI-31C Al-31 D

9J.< % 41-1-% 'i1 ·'-~ II. 11'1" Q~l'~ .. % ~1(2.0 %

AI-31A Al-31 B AI-31C Al-310

TcoLo RPSCIP DVM: 5~().\ OF S'10 ~OF s~fZ.) oF 2.il~oF

AI-31A Al-31 AI-31C Al-310

s~u t OF s c.f().3 OF s'j z.. 1 oF 5 '11.1. OF AI-31A Al-318 AI-31C Al-31 D

-st.-J Cl ro OF s-u0·3 OF S"'·i1.1 OF 5~:{/.'3 OF AI-31A A -318 AI-31C Al-310

5Yl.ll0.) OF THor

9B~.9 OF RPSCIP DVM: I!IQ~.u oF 8~9... (, OF AI-31A Al-31 B AI-31C Al-310

Nl POWER

RPSCIP DVM: 9_1."' % ~7.1 % en ,s- % ~7-1 % AI-31A Al-31 B AI-31C AI-31D

.oz.~ ASI

RPSCIP DVM: .r:J.tz.u ,oz.~ .e:.z.n AI-31A Al-31 B AI-31C Al-310

CEA Group Position Rod Group Log Printout lll.I..'Z-3 Time

Core Axial Shape Index ERF XC093 ,0\lP'\

Core Power ERF XC105 I L\{£fd£.... MWth

Generator Load ERF Y3273 ~.5£11 MWe ""ct'KI '\

RCS Boron Concentration Latest Analysis ~z-n ppm

Completed by / !1/1111J1!/J £t- Daternme 1/'1111 /61Z, ')

R27

Page 137: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One CUrrent Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 125.7 RR31 126.3 RR15 126.2 RR32 126.9 RR16 126.0 RR33 126.2 RR17 126.4 RR34 127.0 RR35 126.7 RR36 126.6 RR37 126.4

Nontrip

RR18 127.0 RR19 126.4 RR20 126.2 RR21 126.3

Group Positions: High, Average, Low, and Deviation

Shutdown A Shutdown B Nontrip ------------ ------------ ------------

Posn RR37 126.4 RR14 125.7 RR20 126.2 High RR34 127.0 RR17 126.4 RR18 127.0 Avg 126.6 126.1 126.4 Low RR33 126.2 RR14 125.7 RR20 126.2

Dev 0.8 0.7 0.8

/.15A Sunday Jan 09, 2011 09:23 AM

1·'013

Group 1 Group 2 Group 3 Group 4

RR06 126.3 RR22 126.4 RR02 127.1 RR01 114.0 RR08 126.6 RR23 126.4 RR03 126.4 RR38 114.5 RR10 126.5 RR24 126.7 RR04 127.2 RR39 114.3 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.4

RR26 126.4 RR41 114.5 RR27 127.0 RR28 126.7 RR29 126.4

Group 1 Group 2 Group 3 Group 4 ------------ ------------ ------------ ------------RR06 126.3 RR22 126.4 RR05 126.4 RR01 114 .o RR08 126.6 RR27 127.0 RR04 127.2 RR38 114.5

126.5 126.5 126.8 114.3 RR06 126.3 RR29 126.4 RR03 126.4 RR01 114 .o

0.3 0.6 0.8 0.6

'\

Page 138: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME D'NlJ DATE \lqhl STEP NO. J.ll 5 RECORD SHEET _s_ OF ....:J_

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

t..T POWER RPSCIP DVM: cn.3 % 96-D% ~e.-z.. % ~(.,.~ %

AI-31A Al-31 B AI-31C Al-310

jlS % S~l % '\~.0 % '1~.4 % AI-31A Al-31 B AI-31C Al-310 . ~/.£, % ~l-~ % 'il.t. % '1 (g.q % AI-31A Al-31 B AI-31C Al-31 D

5'!>~ .] OF TcoLo

RPSCIP DVM: ?Jl/.1.. OF ~l~·} OF 5"2). L OF AI-31A Al-31 B AI-31C Al-310

S}'-1.~ OF 53'-1. I OF ~( •. 'Z. OF S"3(). 2.. OF AI-31A Al-31 B AI-31C Al-310

53'-f .9JoF 5:JtJ.1-oF Sl(,:Z. OF s-:;).Z, OF AI-31A Al-31 B AI-31C Al-310

THor RPSCIP DVM: St1.<l' OF s-w.s OF ~1.'-1 OF <:)f)Z.l.. OF

AI-31A Al-31 B AI-31C Al .. 310

Nl POWER

RPSCIP DVM: q(t.~ % CJl.t.Z. % <ii.0 % '15_. 2, % AI-31A Al-31 B AI-31C Al-310

ASI RPSCIP DVM: .0<-10'-l: .0~\b . 0~\') -641[_

AI-31A Al-31 B AI-31C Al-310

CEA Group Position Rod Group Log Printout OtJ"> I Time

Core Axial Shape Index ERF XC093 D-o~

Core Power ERF XC105 l"tl'Vt& MWth

Generator Load ERF Y3273 '53'1./ll!) MWe -z_"lj

RCS Boron Concentration Latest Analysis &lq, .... ~ '"'''' ppm

Completed by /ffl~" DatefTime 1/lf/" I 6'1S'Z.

R27

Av~.

S3S,O'l

Page 139: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One Current Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B

RR30 126.5 RR14 125.7 RR31 126.3 RR15 126.2 RR32 126.9 RR16 126.0 RR33 126.2 RR17 126.4 RR34 127.0 RR35 126.7 RR36 126.6 RR37 126.4

(.\l 15

Nontrip Group 1

RR18 127.0 RR06 126.3 RR19 126.4 RR08 126.6 RR20 126.2 RR10 126.5 RR21 126.3 RR12 126.4

Group Positions: High, Average, Low, and Deviation

Shutdown A Shutdown B Nontrip Group 1 ------------ ------------ ------------ ------------

Posn RR37 126.4 RR14 125.7 RR20 126.2 RR06 126.3 High RR34 127.0 RR17 126.4 RR18 127.0 RR08 126.6 Avg 126.6 126.1 126.4 126.5 Low RR33 126.2 RR14 125.7 RR20 126.2 RR06 126.3

Dev 0.8 0.7 0.8 0.3

Sunday Jan 09, 2011 09:51 AM

Group 2 Group 3 Group 4

RR22 126.4 RR02 127.1 RR01 36.2 RR23 126.4 RR03 126.4 RR38 114.5 RR24 126.7 RR04 127.2 RR39 114.3 RR25 126.5 RR05 126.4 RR40 114.4 RR26 126.4 RR41 114.5 RR27 127.0 RR28 126.7 RR29 126.4

Group 2 Group 3 Group 4 ------------ ------------ ------------RR22 126.4 RR05 126.4 RR01 36.2 RR27 127.0 RR04 127.2 RR38 114.5

126.5 126.8 98.8 RR29 126.4 RR03 126.4 RR01 36.2

0.6 0.8 78.3

Page 140: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.1 -Variable TAvG Test Record

TIME lOl) DATE l/'1111 STEP NO. /.15"& RECORD SHEET

RE-ST-RX-0003 PAGE 13 OF 17

5 OF _:]____

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

AT POWER RPSCIP DVM: '1/.'l, % 18.L. % '1 '"). ~ % :1~-~ %

AI-31A Al-31 B AI-31C Al-310

~s.o % ~8-~ % 't/.1 % gc..~ % AI-31A Al-31 B AI-31C Al-31 D

1~.0 % s~.~ % '11?..1 % 9/.1 % AI-31A Al-31 B AI-31C Al-31 D

TcoLo 5'1 t. "1.,.~ ll~t ,, RPSCIP DVM: 5'-\6 .fb OF ~0-t OF 7'14>{ OF ~\.1 OF

AI-31A Al-31 B AI-31C Al-31 D

'5"(Cl.f! OF S"'iO.(,, OF <;'i 1-.3 "F ~l.'i OF

AI-31A Al-31 B AI-31C Al-31 D

'5"'-tO .I OF 5'1 0 .5" oF ~1..? OF S'/I.Y "F AI-31A Al-31 B AI-31C Al-310

5'09Jj OF THor

RPSCIP DVM: ~.o oF 'f.Rit. L.. oF ~.~ OF

AI-31A Al-31 B AI-31C Al-31 D

Nl POWER

RPSCIP DVM: en.:; % til.'( % '17. -z. % q 7. I % AI-31A Al-31 B AI-31C Al-310

ASI RPSCIP DVM: • o?.1l9 • Q?).,Z.. . 6 t.c.<~ .6?-71

AI-31A Al-31 B AI-31C Al-31 D

CEA Group Position Rod Group Log Printout loll\ Time

Core Axial Shape Index ERF XC093 a.auz..

Core Power ERF XC105 1 '-'I.Dco:z/;- MW,h

Generator Load ERF Y3273 ") 3:.> ,l'·\'Z.. MWe -z.-13

RCS Boron Concentration Latest Analysis ..::;;:t'/) m«-11~1 '' ppm

' (Ill' 1-L'?/) 0 _p . Completed by '/L/.1.1~... rL Date/Time 1/'l(ll I I Ol'l

R27

Page 141: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One Current Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown B ---------#-- ------------RR30 126.5 RR14 125.7 RR31 126.3 RR15 126.2 RR32 126.9 RR16 126.0 RR33 126.2 RR17 126.4 RR34 127.0 RR35 126.7 RR36 126.6 RR37 126.4

(.l')[?

Nontrip Group 1 ------------ ------------RR18 127.0 RR06 126.3 RR19 126.4 RR08 126.6 RR20 126.2 RRlO 126.5 RR21 126.3 RR12 126.4

Group Positions: High, Average, Low, and Deviation

Shutdown A Shutdown B Non trip Group 1 ------------ ------------ ------------ ------------

Posn RR37 126.4 RR14 125.7 RR20 126.2 RR06 126.3 High RR34 127.0 RR17 126.4 RR18 127.0 RR08 126.6 Avg 126.6 126.1 126.4 126.5 Low RR33 126.2 RR14 125.7 RR20 ~26.2 RR06 ~26.3

Dev 0.8 0.7 0.8 0.3

Sunday Jan 09, 2011 10:19 AM

Group 2 Group 3 Group 4 ------------ ------------ ------------RR22 126.4 RR02 127.1 RR01 114 .o RR23 126.4 RR03 126.4 RR38 114.5 RR24 126.7 RR04 127.2 RR39 114.3 RR25 126.5 RR05 126.4 RR40 114.4 RR26 126.4 RR41 114.5 RR27 127.0 RR28 126.7 RR29 126.4

Group 2 Group 3 Group 4 ------------ ------------ ------------. RR22 126.4 RR05 126.4 RR01 114.0 RR27 127.0 RR04 127.2 RR38 114.5

126.5 126.8 114.3 RR29 126.4 RR03 126.4 RROl 1.1.4.0

0.6 0.8 0.5

Page 142: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME 103~ DATE 11_ '\l 1\ STEP NO. :J.\'1 RECORD SHEET .!:L OF ::1._

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

t.T POWER RPSCIP DVM: 11.') % q '},t;' % "i"' :l % 'fZ,.~ %

AI-31A Al-31 B AI-31C Al-31 D

~'·' % ---- tj?:'J % q-;,u % 'll·l % AI-31A Al-318 AI-31C Al-31 D

1;.) % 'i1. \ % 1') ."' % '11.1 % AI-31A Al-318 AI-31C Al-31 D

TcoLo <:;'lt. 'V

RPSCIP DVM: 5 '-f().l, OF 540.'1. OF 5"'fi~~~l'ifli 5"fi:Z. OF AI-31A Al-31 B AI-31C Al-310

5'-10.7 OF 54D.I OF S~:fZ.:i OF S L-/ I. "Z. o F AI-31A Al-31 B AI-31C Al-310

s '-/() ."') °F 5 c..{(}, ( OF S "I'Z . '2-- o F ~"'I.) OF AI-31A Al-31 B AI-31C Al-31 D

RPSCIP DVM: %."1 OF T1oT 5'3(c ·" OF ~~.J OF ~'-·"1 OF

AI-31A Al-318 AI-31C Al-310 Nl POWER

RPSCIP DVM: Cf'{,() % j-4.] % '13.1 % "i'p % AI-31A Al-318 AI-31C Al-310

ASI RPSCIP DVM: ,o '-1"5'1.. . oc..jlDZ.. .o~s::~ • c.'{(,.c,

AI-31A Al-31 B AI-31'C Al-31 D CEA Group Position Rod Group Log Printout lD7P Time

Core Axial Shape Index ERF XC093 0 .ot{O'L

Core Power ERF XC105 l '1~.'11.{ MWth

Generator Load ERF Y3273 .;PS.3'i'Z MWe Z,?:!>

RCS Boron Concentration Latest Analysis z;::t'b- IV\IL I /4/ 'I ppm

Completed b(/f / ttttJJr'f tJ 12 ~ DaterTime t/'1 /II I IO 38

R27

~(.O"'l

Page 143: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One Current Rod Positions

Individual Rod Positions by Group

Shutdown A

RR30 RR31 RR32 RR33 RR34 RR35 RR36 RR37

126.5 126.3 126.9 126.2 127.0 126.7 126.6 126.4

Shutdown B

RR14 RR15 RR16 RR17

125.7 126.2 126.0 126.4

Group Positions: High, Average, Low,

Shutdown A Shutdown B ------------ ------------

Posn RR37 126.4 RR14 125.7 High RR34 127.0 RR17 126.4 Avg 126.6 126.1 Low RR33 126.2 RR14 125.7

Dev 0.8 0.7

{.\~

Nontrip Group 1 ------------ ------------RR18 127.0 RR06 126.3 RR19 126.4 RR08 126.6 RR20 126.2 RR10 126.5 RR21 126.3 RR12 126.4

and Deviation

Nontrip Group 1 ------------ ------------RR20 126.2 RR06 126.3 RR18 127.0 RR08 126.6

126.4 126.5 RR20 126.2 RR06 126.3

0.8 0.3

Sunday Jan 09, 2011 10:36 AM

Group 2 Group 3 Group 4 ------------ ------------ ------------RR22 126.4 RR02 127.1 RR01 65.6 RR23 126.4 RR03 126.4 RR38 114 .s RR24 126.7 RR04 127.2 RR39 114.3 RR25 126.5 RR05 126.4 RR40 114.4 RR26 126.4 RR41 114.5 RR27 127.0 RR28 126.7 RR29 126.4

Group 2 Group 3 Group 4 ------------ ------------ ------------RR22 126.4 RR05 126.4 RR01 65.6 RR27 127.0 RR04 127.2 RR38 114.5

126.5 126.8 104.7 RR29 126.4 RR03 126.4 RR01 65.6

0.6 0.8 48.9

Page 144: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 13 OF 17

Attachment 9.1 -Variable TAvG Test Record

TIME lOt.{~ DATE lLqJu STEP NO. I.L'Z. RECORD SHEET_:]____ OF .::J_

NOTE: A new Record Sheet is used for each Data Collection step, therefore copies of this page must be made to complete testing.

RPSCIP DVM: ~1.~ % lHPOWER

'IY.t-1 % 'i1.v % '1&·1 % AI-31A Al-31 B AI-31C Al-310

n; % 'i~.u % 9).~ % ql...~ot % AI-31A Al-31 B AI-31C Al-310

1g.c % ~~·~ % 'fl,li % g_ (.,.(. % AI-31A Al-31 B AI-31C Al-31 D

TeeLe RPSCIP DVM: <;"'~0.(.., OF -=;-IJ.O.i OF ("-fl.! OF <::;"41./ OF

AI-31A Al-31 B AI-31C Al-31 D

<40lD OF ~0·1 OF .:;-y-z ·I OF D-//.f OF AI-31A Al-31 B AI-31C Al-310

<:4o.C:: OF -;yo.D OF ~L.f£.( OF s::::ILI OF AI-31A Al-31 B AI-31C Al-310

S}'Jl.) THor

RPSCIP DVM: OF ')~l.~ OF '\9Jg.(, OF ~.I OF AI-31A Al-31 B AI-31C Al-310

Nl POWER

RPSCIP DVM: cntt % C,~.C, % %j % qlL,e; % AI-31A Al-31 B AI-31C Al-310

,OZ,/1.{ ASI

RPSCIP DVM: .o1..UD .uz..ro •C>L.~ AI-31A Al-31 B AI-31C Al-310

CEA Group Position Rod Group Log Printout lo52- Time

Core Axial Shape Index ERF XC093 D OZ. I 'f

Core Power ERF XC105 I Ljl\'(. 2-U> MWth

Generator Load ERF Y3273 '5Vb.l'i) MWe 7-'T)

RCS Boron Concentration Latest Analysis ~ ,P. I /'II " ppm

Completed by~atl';// f tJo ')- Date!Time I /1111 I 105~

R27

Page 145: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OPPD Fort Calhoun Station Unit One CUrrent Rod Positions

Individual Rod Positions by Group

Shutdown A Shutdown 8

RR30 126.5 RR14 125.7 RR31 126.3 RR15 126.2 RR32 126.9 RR16 126.0 RR33 126.2 RR17 126.4 RR34 127.0 RR35 126.7 RR36 126.6 RR37 126.4

Group Positions: High, Average, Low,

Shutdown A Shutdown 8 ------------ ------------

Posn RR37 126.4 RR14 125.7 High RR34 127.0 RR17 126.4 Avg 126.6 126.1 Low RR33 126.2 RR14 125.7

Dev 0.8 0.7

Nontrip

RR18 127.0 RR19 126.4 RR20 126.2 RR21 126.3

and Deviation

Nontrip ------------RR20 126.2 RR18 127.0

126.4 RR20 126.2

0.8

/.2<. Sunday Jan 09, 2011 10:52 AM

Group 1 Group 2 Group 3 Group 4

RR06 126.3 RR22 126.4 RR02 127.1 RR01 114 .o RR08 126.6 RR23 126.4 RR03 126.4 RR38 114.5 RR10 126.5 RR24 126.7 RR04 127.2 RR39 114.3 RR12 126.4 RR25 126.5 RR05 126.4 RR40 114.4

RR26 126.4 RR41 114.5 RR27 127.0 RR28 126.7 RR29 126.4

Group 1 Group 2 Group 3 Group 4 ------------ ------------ ------------ ------------RR06 126.3 RR22 126.4 RR05 126.4 RR01 114.0 RR08 126.6 RR27 127.0 RR04 127.2 RR38 114.5

126.5 126.5 126.8 114.3 RR06 126.3 RR29 126.4 RR03 126.4 RR01 114.0

0.3 0.6 0.8 0.5

Page 146: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.2- Points in Trend Block 11

• T0111C • T0111H • T0121C • T0121 H

• P0103Y • L0101X • L0101Y • F0114A

• P0905A • P1046 • P1048 • L0903Y

• P0946A • Y3273 • XC093 • XC105

• AR002X • AR002Y • BR002X • BR002Y

• CR002Y • DR002X • DR002Y • R0003X

• R0004X • R0004Y

• • • • • •

RE-ST-RX-0003 PAGE 14 OF 17

P0103X

P0902A

L0906Y

XC411

CR002X

R0003Y

R27

Page 147: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

RE-ST-RX-0003 PAGE 15 OF 17

Attachment 9.3 - MTC Calculation

1. Calculation ofT cold(initial)

Data from Variable Tavg Test Records.

')'-{\.'~'"{ Avg. Tcold from Step 7.8 + S"'\I.Z'Z-Avg. Tcold from Step 7.15

T cold(initial) = ---------------::-------------2

T cold(initial) = S'{(. Z3 ° p

2. Determination ofT cold(final)

T cold(final) = S3<5 14 Avg. T cold from Step 7.12 (Variable Tavg Test Record)

3. Calculation of 1::. T cold

l:.Tcold = <)(j(o"Z.1 Tcold(initial) - 53<;".l'( Tcold(final)

4. Calculation of Inserted Rod Worth (initial)

Data from Rod Group Log Printouts.

W·\."2. CEA4-1 Position(Step7.8)+ \1(!.0 CEA4-1 Position(Step7.15)

2 ,,-..~.\ ~II. 11~111

= ~Average Initial CEA4-1 Position

-a [JjO "1 '1·M~erted Rod Worth (initial) from CEA 4-1 Integral Rod Worth Curve

5. Determination of Inserted Rod Worth (final)

Data from Rod Group Log Printout.

= 7-f,.,.?J Final CEA4-1 Position (Step 7.12)

-0.\~1~ tns~ed Rod Worth (final) from CEA 4-1 Integral Rod Worth Curve

R27

Page 148: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.3 - MTC Calculation

6. Calculation of l1p

-0 ·'~1~5·lT~serted Rod Worth (final)

_ -o.oo01 ~~erted Rod Worth (initial)

%!1p = -().13(1l %!1p

!1p = -o.oo1-y, (l;ol1p 1100% (inserted worth)]

7. Calculation of Measured lTC

-o.f»1 ;u 1P I ~ .O'i f1 Tcold

lTC = -1.. 2-&..\ c;' ,qo-<f 6 p

8. Determination of Predicted FTC

RE-ST-RX-0003 PAGE 16 OF 17

'D·I~l"'10-1,p/"F Predicted Fuel Temperature Coefficient (Prerequisite 6.16)

9. Calculation of MTC

-z..z'-{ )l((o-".:l!?~fasured lTC

- ( -0·!31 ~10-'i l1p/"Fl Predicted FTC

MTC = -?...\D'6 KlO--tL\?f(fransfer to Step 1 0.2)

Completed by'}f!~ · Reviewed b~2.-----C

Date/Time 1 ( <i (" I 110'{

Date/Time I/: /11 I II Z<r I I

R27

Page 149: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

I,.·"

FORT CALHOUN STATION SURVEILLANCE TEST CONTINUOUS USE

Attachment 9.4 - Comment Sheet

RE-ST -RX-0003 PAGE 17 OF 17

R27

Page 150: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Memorandum

Date:

From:

To:

Subject:

January 7, 2011

C. L. Waszak

M. R. Smith B. P. Schawe

Cycle 26 MTC Predictions for End of Cycle MTC Test

NED-11-0004 RP A

Data has been generated in support of the Cycle 26 End of Cycle (EOC) Moderator Temperature Coefficient (MTC) test. The data is provided in the attachment to this memo and includes predictions for lTC, MTC, and FTC for perturbations of -I 0°F and -5°F from the nominal core inlet temperature of 543°F, power coefficients (PC) at perturbations of -5% and -7% power from the nominal core power of 98%, and CEA 4-1 worth versus position with a constant xenon distribution. The data was calculated at a predicted burn up of 10,920 MWD/MTU.

If you have any questions or comments regarding this information, please feel free to contact me at extension 6482.

Carol L. Waszak Supervisor- Reactor Performance Analysis

CLW/MCR

Page 151: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Attachment NED-11-0004 RPA Cycle 26 MTC Predictions for EOC MTC Test

ATTACHMENT

The attached data was prepared and reviewed by the following personnel.

Prepared By:

1tl~-Matthew Rybenski Date

Senior Nuclear Design Engineer- Reactor Performance

Reviewed By:

/ / 7 /2o/} Richard Roenigk Date

Senior Nuclear Design Engineer- Reactor Performance

Page 1 of 3

Page 152: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Attachment NED-11-0004 RPA Cycle 26 MTC Predictions for EOC MTC Test

Unbiased Predicted lTC, MTC, FTC, and PC Biased Predicted lTC and MTC

Parameter Perturbation

lTC -10'F

lTC -S'F

MTC -10'F

MTC -5'F

FTC -10'F

FTC -S'F

PC -5% Power

PC -7% Power

50

0

"E CJ E. .s: t: 0 -50 ;: ~ .:!: -CJ ... ..

-100 0:: -.., <( w u

Unbiased Value Perturbation Unbiased Biased Parameter

('F) Value Value (pcm/'F) (pcm/'F)

-22.30 pcm/'F lTC -10 -22.30 -22.66

-22.80 pcm/'F lTC -5 -22.80 -23.16

-20.93 pcm/'F MTC -10 -20.93 -21.29

-21.43 pcm/'F MTC -5 -21.43 -21.79

-1.37 pcm/'F

-1.37 pcm/'F Associated Parameters

-18.49 pcm/% Power Predicted Boron at Test Conditions (ppm) 289

-18.48 pcm/% Power MTCIITC Bias (pcm/'F) -0.36

End of Cycle 26 CEA 4-1 Worth vs. Position (CEA Group 4 at114.51nches Withdrawn)

.../" ~

v v

v / v v

v v v

/ v -150

l.---

-200 0 10 20 30 40 50 60 70 80 90 100 110 120 130

CEA4-1 Position (inches withdrawn)

Page 2 of 3

Page 153: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Attachment NED-11-0004 RPA

CEA Position

126

120

115

114.5

110

105

100

95

90

85

80

75

70

65

60

55

50

45

40

35

30

25

20

15

10

5

0

Cycle 26 MTC Predictions for EOC MTC Test

Predicted CEA 4-1 Worth

k-Reactivity Reactivity

effective Worth Worth

(%t.p) (pcm)

0.99990 0.012 12

0.99986 0.008 8

0.99979 0.001 1

0.99978 0.000 0

0.99970 -0.008 -8

0.99960 -0.018 -18

0.99949 -0.029 -29

0.99939 -0.039 -39

0.99928 -0.050 -50

0.99918 -0.060 -60

0.99909 -0.069 -69

0.99899 -0.079 -79

0.99890 -0.088 -88

0.99882 -0.096 -96

0.99874 -0.104 -104

0.99866 -0.112 -112

0.99859 -0.119 -119

0.99852 -0.126 -126

0.99845 -0.133 -133

0.99839 -0.139 -139

0.99832 -0.146 -146

0.99826 -0.152 -152

0.99820 -0.158 -158

0.99814 -0.164 -164

0.99809 -0.169 -169

0.99805 -0.173 -173

0.99802 -0.176 -176

Page 3 of 3

Page 154: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

REPORT: "** TB11 ** was requested on **09-JAN-11 10:58:12.7**

DATE/TIME *T0111C* *T0111H* *T0121C* *T0121H* *P0103X* *P0103Y* *L0101X* *L0101Y"* "*F0114A* *P0902A* "*DEG F * *DEG F * *DEG F * "*DEG F * *PSIA • *PSIA • • % • • % • • % • *PSIA •

09-JAN-11 08 15 00.0 542.714 590.250 541.482 590.060 2102 .164 2102.764 64.253 63.452 105.913 823.217 09-JAN-11 08 16 00.0 542.864 591.042 541.372 590.050 2102.164 2101.362 64.343 63.452 104.951 823.818 09-JAN-11 08 17 00.0 542.544 590.541 541.362 590.381 2102 .164 2101.262 64.343 63.452 105.063 823.317 09-JAN-11 08 18 00.0 542.795 591.042 541.262 589.269 2101.463 2101.362 64.223 63.452 105.021 823.117 09-JAN-11 08 19 00.0 542.784 590.060 541.262 589.750 2101.563 2101.463 64.223 63.452 104.684 823.317 09-JAN-11 08 20 00.0 542.885 589.940 541.262 589.750 2101.863 2101.763 64.223 63.452 105.412 824.018 09-JAN-11 08 21 00.0 542.774 591.122 541.262 590.411 2101.963 2101.763 64.373 63.452 105.524 823.418 09-JAN-11 08 22 00.0 542.795 590.671 541.372 590.741 2101.963 2101.763 64.273 63.452 105.343 824.018 09-JAN-11 08 23 00.0 542.664 590.651 541.262 590.431 2101.963 2101.763 64.273 63.452 104.727 823.117 09-JAN-11 08 24 00.0 542.664 590.501 541.362 590.801 2102.464 2102.063 64.273 63.452 105.538 823.117 OS-JAN-ll OB 2S 00.0 S42. 664 59n.o3o '54'1.362 590.77'1 2l0l..463 2).0).. 863 64.273 63.452 105.287 822.917 09-JAN-11 08 26 00.0 542.544 591.031 541.382 589.900 2102.364 2101.863 64.273 63.452 105.189 823.418 09-JAN-11 08 27 00.0 542.644 590.080 541.272 590.601 2101.963 2100.761 64.273 63.452 104.670 823.117 09-JAN-11 08 28 00.0 542.674 590.851 541.382 590.911 2101.963 2101.262 64.163 63.452 104.951 823.418 09-JAN-11 08 29 00.0 542.925 589.980 541.402 590.821 2101.963 2101.262 64.163 63.452 105.077 823.317 09-JAN-11 08 30 00.0 542.824 589.970 541.302 589.830 2100.961 2100.961 64.173 63.452 105.621 823.618 09-JAN-11 08 31 00.0 542.714 590.370 541.302 590.220 2101.863 2101.662 64.173 63.351 105.049 823.317 09-JAN-11 08 32 00.0 542.604 589.790 541.402 590.391 2101.863 2101.662 64.173 63.351 105.468 823.718 09-JAN-11 08 33 00.0 542.845 590.170 541.172 590.130 2099.660 2099.860 63.922 63.141 104.811 821.414 09-JAN-11 08 34 00.0 542.274 589.169 540.741 589.640 2099.960 2099.359 63.472 62.710 105.343 817.308 09-JAN-11 08 35 00.0 541.843 589.670 540.210 589.840 2100.160 2099.860 63.081 62.300 104.530 813.902 09-JAN-11 08 36 00.0 541.162 588.988 539.990 588.718 2098.858 2099.459 62.650 61.869 105.983 810.297 09-JAN-11 08 37 00.0 540.721 588.768 539.459 588.518 2099.559 2099.559 62.330 61.548 105.552 806.991 09-JAN-11 08 38 oo.o 540.391 587.837 538.798 587.927 2100.661 2100.160 62.109 61.348 106.757 803.586 09-JAN-11 08 39 00.0 539.810 587.115 538.568 587.276 2099.259 2098.658 61.659 60.907 105.203 799.579 09-JAN-11 08 40 00.0 539.579 586.745 538.047 587.376 2101.463 2101.763 61.769 60.907 106.426 796.675 09-JAN-11 08 41 00.0 539.329 587.717 537.717 586.845 2100.361 2100.961 61.769 60.907 105.816 795.473 09-JAN-11 08 42 00.0 538.688 586.104 537.506 586.344 2101.362 2100.661 61.639 60.807 105.175 791.867 09-JAN-11 08 43 00.0 538.598 586.324 537.045 585.723 2101.162 2100.561 61.488 60.607 104.867 788.862 09-JAN-11 08 44 00.0 537.947 585.974 536.564 585.333 2101.062 2100.361 61.368 60.507 105.510 785.958 09-JAN-11 08 45 00.0 537.626 585.884 536.344 585.373 2101.563 2101.662 61.498 60.607 105.454 783.854 09-JAN-11 08 46 00.0 537.195 585.623 535.803 584.632 2102.564 2101.662 61.599 60.717 106.536 781.550 09-JAN-11 08 47 00.0 537.195 584.752 535.803 585.353 2102.364 2102.564 61.839 60.927 105.580 780.649 09-JAN-11 08 48 00.0 537.186 585.663 535.483 584.261 2102.264 2102.664 61.839 61.028 105.858 778.946 09-JAJ:.J-11 08 49 00.0 536.845 584.672 535.373 584.632 2103.265 2102.764 62.149 61.238 106.246 778.245 09-JAN-11 08 50 00.0 536.695 584.601 535.272 584.601 2103.566 2102.764 62 .490 61.589 105.329 778.145 09-JAN-11 08 51 00.0 536.585 584.892 535.272 584.331 2102.664 2102.063 62.710 61.789 105.969 777.845 09-JAN-11 08 52 oo.o 536.835 585.022 535.172 584.271 2102.564 2102.063 62.921 61.989 105.885 777.745 09-JAN-11 08 53 00.0 536.855 584.741 535.373 584.131 2102.564 2101.763 63.121 62.190 105.370 778.045 09-JAN-11 08 54 00.0 536.735 585.112 535.252 584.321 2102.464 2102.264 63.221 62.400 106.163 778.145 09-JAN-11 08 55 00.0 536.614 584.301 535.252 584.301 2102.464 2102.264 63.431 62.500 106.426 778.446 09-JAN-11 08 56 00.0 536.595 584.882 535.252 584.621 2101.563 2102.063 63.431 62.500 106.577 778.145 09-JAN-11 08 57 oo.o 536.835 585.383 535.353 584.571 2102.364 2102.164 63.532 62.610 105.231 778.245 09-JAN-11 08 58 00.0 536.755 584.551 535.252 585.172 2101.563 2100.961 63.532 62.710 105.830 778.446 09-JAN-11 08 59 00.0 536.655 585.032 535.252 584.772 2101.563 2101.963 63.632 62.710 105.231 777.544 09-JAN-11 09 00 00.0 536.895 583.580 535.252 584.281 2102.564 2101.662 63.642 62.810 105.356 778.345 09-JAN-11 09 01 00.0 537.095 584.802 535.353 584.120 2102.564 2102.063 64.063 63.071 104.586 780.749 09-JAN-11 09 02 00.0 537.516 586.905 535.793 585.623 2102.364 2102.865 64.223 63.371 105.733 783.353 09-JAN-11 09 03 00.0 537.837 585.873 536.224 585.773 2103.065 2101.863 64.443 63.572 105.663 785.958 09-JAN-11 09 04 00.0 538.077 586.505 536.555 585.673 2101.763 2102.063 64.573 63.702 106.038 789.063 09-JAN-11 09 OS 00.0 538.658 586.755 537.125 586.254 2101.763 2102.063 64.683 63.802 105.189 791.967 09-JAN-11 09 06 00.0 538.688 586.975 537.326 587.396 2101.662 2100.761 64.483 63.702 105.245 794.371 09-JAN-11 09 07 00.0 539.289 587.786 537.766 586.765 2100.661 2100.461 64.353 63.602 106.038 797.175 09-JAN-11 09 08 00.0 539.640 587.937 537.987 587.245 2101.662 2101.563 64.353 63.502 104.755 799.079 09-JAN-11 09 09 00.0 540.110 588.027 538.538 587.366 2101.463 2101.162 64.463 63.602 105.245 802.284 09-JAN-11 09 10 00.0 540.431 588.708 538.969 588.538 2101.262 2100.561 64.263 63.482 105.719 805.589 09-JAN-11 09 11 00.0 540.451 588.608 539.299 587.906 2101.262 2100.861 64.153 63.361 105.231 807.793 09-JAN-11 09 12 00.0 541.052 589.439 539.399 589.199 2102.564 2102.264 64.263 63.462 105.370 811.899

Page 155: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

09-JAN-11 09 13 00.0 541.833 589.609 540.070 589.249 2102.564 2101.563 64.493 63.662 104.417 816.506 09-JAN-11 09 14 00.0 541.943 589.269 540.651 590.311 2102.063 2101.362 64.613 63.762 105.468 820.313 09-JAN-11 09 15 00.0 542.404 590.551 541.192 589.880 2100.861 2100.060 64.303 63.552 106.066 822.216 09-JAN-11 09 16 00.0 542.504 590.932 541.302 589.990 2100.461 2100.160 64.002 63.241 105.398 823.017 09-JAN-11 09 17 00.0 542.604 591.112 541.192 589.980 2099.960 2098.758 63.702 62.921 104.403 823.418 09-JAN-11 09 18 00.0 542.724 590.621 541.192 590.220 2099.860 2099.860 63.401 62.610 105.440 823.718 09-JAN-11 09 19 00.0 542.664 590.471 541.402 590.261 2099.760 2099.860 62.991 62.200 104.305 823.718 09-JAN-11 09 20 00.0 542.664 590.070 541.302 590.641 2100.661 2099.860 62.760 61.979 104.093 823.217 09-JAN-11 09 21 00.0 542.875 590.280 541.302 590.621 2100.661 2100.661 62.650 61.759 105.635 823.518 09-JAN-11 09 22 00.0 542.664 590.370 541.402 590.761 2101.162 2100.661 62.550 61.649 104.544 823.518 09-JAN-11 09 23 00.0 542.935 590.691 541.402 590.030 2101.262 2100.661 62.350 61.548 104.741 823.618 09-JAN-11 09 24 00.0 542.784 591.012 541.302 589.870 2101.262 2101.662 62.250 61.448 105.105 823.618 09-JAN-11 09 25 00.0 542.674 590.771 541.302 590.150 2102.464 2102.664 62.450 61.448 105.315 823.418 09-JAN-11 09 26 00.0 542.784 590.401 541.302 590.261 2103.666 2103.065 62.680 61.759 105.315 823.418 09-JAN-11 09 27 00.0 542.664 590.521 541.292 590.481 2102.664 2103.166 62.921 61.979 105.203 823.217 09-JAN-11 09 28 00.0 542.424 590.060 540.962 589.750 2101.563 2100.761 62.700 61.869 105.259 819.912 09-JAN-11 09 29 00.0 542.304 589.920 540.651 589.369 2100.461 2100.561 62.500 61.669 105.719 816.907 09-JAN-11 09 30 00.0 541.603 589.179 540.220 589.149 2100.060 2099.459 62.169 61.338 105.384 812.500 09-JAN-11 09 31 00.0 541.031 589.649 539.659 589.199 2099.158 2099.559 61.839 61.008 104.881 808.694 09-JAN-11 09 32 00.0 540.431 588.347 539.118 588.487 2100.561 2099.559 61.619 60.797 105.035 804.688 09-JAN-11 09 33 00.0 540.290 588.227 538.768 588.087 2101.262 2100.961 61.378 60.467 106.646 801.082 09-JAN-11 09 34 00.0 539.579 586.855 538.217 587.847 2100.361 2100.060 61.138 60.367 105.788 797.075 09-JAN-11 09 35 00.0 538.918 587.136 537.546 586.905 2101.463 2101.062 61.038 60.166 106.135 794.071 09-JAN-11 09 36 00.0 538.437 585.753 537.205 586.044 2101.362 2102.063 61.038 60.166 105.245 790.966 09-JAN-11 09 37 00.0 538.337 586.054 536.965 585.573 2102.664 2102.164 61.158 60.266 104.951 788.762 09-JAN-11 09 38 00.0 537.967 585.292 536.534 585.242 2102.063 2101.863 61.158 60.266 105.538 786.158 09-JAN-11 09 39 00.0 537.636 584.781 536.154 585.593 2102.264 2102.063 61.368 60.367 105.440 784.155 09-JAN-11 09 40 00.0 537.646 585.102 535.953 585.132 2102.364 2102.264 61.589 60.687 106.536 782.652 09-JAN-11 09 41 00.0 537.396 584.882 535.733 584.882 2102.063 2102.264 61.719 60.887 105.677 781.350 09-JAN-11 09 42 00.0 537.115 585.252 535.733 585.212 2103.065 2102.564 62.129 61.188 105.217 780.449 09-JAN-11 09 43 00.0 536.895 584.592 535.633 584.952 2101.763 2102.564 62.109 61.188 105.329 778.946 09-JAN-11 09 44 00.0 536.745 585.232 535.403 584.251 2101.563 2101.362 62.210 61.288 105.663 778.245 09-JAN-11 09 45 00.0 536.875 584.972 535.403 584.191 2101.563 2101.362 62.099 61.288 106.315 777.945 09-JAN-11 09 46 00.0 536.875 585.403 535.292 585.102 2100.361 2100.160 61.979 61.178 105.329 778.245 09-JAN-11 09 47 00.0 536.655 584.221 535.292 583.840 2101.162 2100.060 61.849 61.078 105.663 777.745 09-JAN-11 09 48 00.0 536.635 583.980 535.182 584.431 2101.262 2100.361 61.939 61.078 106.439 777.644 09-JAN-11 09 49 00.0 536.534 584.521 535.292 584.501 2101.262 2100.361 61.839 60.978 105.231 777.344 09-JAN-11 09 50 00.0 536.534 584.110 535.292 584.311 2101.062 2100.561 61.739 60.877 106.177 777.544 09-JAN-11 09 51 00.0 536.755 585.062 535.292 584.080 2101.463 2100.561 61.538 60.777 106.329 777.745 09-JAN-11 09 52 00.0 536.875 584.051 535.182 585.212 2101.563 2100.461 61.538 60.677 106.121 777.845 09-JAN-11 09 53 00.0 536.655 584.000 535.182 584.481 2100.561 2100.861 61.438 60.577 106.715 777.745 09-JAN-11 09 54 00.0 536.665 585.122 535.182 584.992 2100.561 2100.861 61.328 60.577 105.049 777.845 09-JAN-11 09 55 00.0 536.564 584.531 535.182 584.691 2101.662 2101.863 61.358 60.477 104.839 778.245 09-JAN-11 09 56 00.0 537.245 585.623 535.613 584.882 2102.063 2101.963 61.669 60.777 105.259 781.150 09-JAN-11 09 57 00.0 537.216 585.192 535.853 584.641 2101.863 2101.662 61.889 60.907 105.858 782.853 09-JAN-11 09 58 00.0 537.786 586.074 536.274 585.643 2101.763 2101.563 62.109 61.238 105.259 785.457 09-JAN-11 09 59 00.0 537.897 586.945 536.484 585.833 2101.863 2101.463 62.210 61.238 106.287 787.760 09-JAN-11 10 00 00.0 538.347 586.144 536.705 586.344 2101.863 2101.262 62.310 61.438 105.983 790.164 09-JAN-11 10 01 00.0 538.718 586.254 537.136 586.224 2101.963 2102.264 62.410 61.548 105.719 792.468 09-JAN-11 10 02 00.0 538.948 587.216 537.446 586.614 2102.063 2100.961 62.540 61.649 105.788 794.872 09-JAN-11 10 03 00.0 539.149 587.226 537.656 587.556 2100.661 2101.262 62.540 61.749 105.885 797.776 09-JAN-11 10 04 00.0 539.499 587.235 537.997 587.035 2102.264 2101.563 62.660 61.649 106.260 799.579 09-JAN-11 10 OS 00.0 539.940 587.797 538.458 587.286 2103.666 2103.065 62.981 62.059 105.941 803.986 09-JAN-11 10 06 00.0 540.611 588.808 539.118 588.728 2103.666 2102.965 63.401 62.500 105.175 808.494 09-JAN-11 10 07 00.0 541.312 589.449 539.739 588.658 2101.362 2101.162 63.482 62.610 105.691 813.301 09-JAN-11 10 08 00.0 541.663 589.900 540.270 589.730 2102.364 2102.164 63.612 62.710 105.649 816.506 09-JAN-11 10 09 00.0 542.264 589.840 540.611 589.860 2101.863 2101.463 63.612 62.710 105.844 819.311 09-JAN-11 10 10 00.0 542.584 589.860 541.052 589.910 2101.563 2100.461 63.401 62.600 105.035 821.515 09-JAN-11 10 11 00.0 542.474 590.751 541.062 590.421 2099.559 2099.960 63.081 62.300 105.161 822.416 09-JAN-11 10 12 00.0 542.805 590.601 541.162 589.469 2099.860 2099.960 62.750 61.989 105.203 822.917 09-JAN-11 10 13 00.0 542.805 591.272 541.282 589.810 2099.059 2099.059 62.550 61.689 105.119 823.217 09-JAN-11 10 14 00.0 542.704 590.311 541.282 589.950 2100.060 2099.059 62.119 61.358 104.783 823.117

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09-JAN-11 10 15 00.0 542.915 589.649 541.282 590.541 2100.060 2100.260 61.909 61.048 105.161 822.917 09-JAN-11 10 16 00.0 542.594 589.459 541.282 590.160 2099.559 2100.260 61.689 60.847 105.816 822.917 09-JAN-11 10 17 00.0 542.714 589.850 541.282 590.000 2100.461 2100.461 61.488 60.637 105.035 823.017 09-JAN-11 10 18 00.0 542.845 590.421 541.182 590.270 2100.561 2100.361 61.488 60.527 105.774 823.117 09-JAN-11 10 19 00.0 542.724 590.351 541.282 590.100 2100.561 2099.860 61.288 60.417 105.370 823.117 09-JAN-11 10 20 00.0 542.864 590.611 541.282 590.651 2101.463 2100.861 61.178 60.317 105.287 823.017 09-JAN-11 10 21 00.0 542.845 590.431 541.282 590.030 2100.961 2100.861 61.038 60.116 104.923 822.917 09-JAN-11 10 22 00.0 542.604 590.751 541.402 590.130 2101.963 2100.861 61.038 60.116 104.445 823.317 09-JAN-11 10 23 00.0 542.624 590.100 541.402 589.850 2100.861 2100.961 60.938 60.016 104.825 823.518 09-JAN-11 10 24 00.0 542.965 589.870 541.522 590.280 2102.264 2102.364 61.148 60.216 104.937 826.222 09-JAN-11 ra zs aa.a 543.115 589.780 541.643 589.399 2098.658 2097.957 60.517 59.776 105.301 826.823 09-JAN-11 10 26 00.0 542 .484 588.928 541.092 589.139 2097.756 2097.556 59.976 59.115 104.600 825.120 09-JAN-11 10 27 00.0 542.604 589.259 541.202 588.808 2102.264 2101.262 60.196 59.215 104.895 827.724 09-JAN-11 10 28 00.0 543.185 589.249 541.522 589.229 2102.564 2101.763 60.517 59.625 104.502 830.329 09-JAN-11 10 29 00.0 543.165 588.277 541.522 588.558 2100.060 2100.461 59.996 59.195 105.217 830.028 09-JAN-11 10 30 00.0 542.604 588.117 541.212 588.147 2101.362 2100.361 59.796 58.964 105.384 828.425 09-JAN-11 10 31 00.0 542.624 587.757 541.222 588.327 2101.362 2101.662 59.796 58.964 104.993 828.025 09-JAN-11 10 32 00.0 542.845 587.997 541.112 588.297 2101.662 2101.662 59.916 58.964 104.600 828.125 09-JAN-11 10 33 00.0 542.534 587.536 541.112 588.468 2102.664 2101.662 60.016 59.065 104.431 827.825 09-JAN-11 10 34 00.0 542.444 587.866 541.112 587.997 2101.863 2101.662 60.126 59.165 105.384 827.524 09-JAN-11 10 35 00.0 542.774 588.578 541.212 587.316 2101.863 2101.662 60.126 59.265 104.656 827.524 09-JAN-11 10 36 00.0 542.534 588.127 540.991 587.045 2102.764 2102.664 60.226 59.265 105.398 827.724 09-JAN-11 10 37 00.0 542.424 587.636 541.092 587.516 2101.763 2101.563 60.126 59.265 105.858 827.424 09-JAN-11 10 38 00.0 542 .414 587.736 541.092 587.917 2102.164 2101.763 60.156 59.265 106.356 827.324 09-JAN-11 10 39 00.0 542.474 588.007 541.092 587.466 2102.063 2101.863 60.266 59.365 105.203 827.224 09-JAN-11 10 40 00.0 542 .444 588.538 540.991 587.736 2102.063 2101.863 60.367 59.365 105.315 826.923 09-JAN-11 10 41 00.0 542.444 588.377 540.991 587.656 2102.063 2101.863 60.367 59.465 105.077 826.523 09-JAN-11 10 42 00.0 542.354 588.478 540.991 588.317 2103.265 2102.965 60.607 59.685 105.426 825.321 09-JAN-11 10 43 00.0 542.354 588.44 7 541.092 588.508 2102.464 2102.865 60.938 60.026 105.063 824.219 09-JAN-11 10 44 00.0 542 .464 589.179 541.092 588.478 2101.463 2100.661 60.837 59.926 105.719 822.015 09-JAN-11 10 45 00.0 542.243 589.229 540.882 589.499 2101.662 2102.164 60.958 60.026 105.315 821.414 09-JAN-11 10 46 00.0 542.224 589.630 540.891 589.710 2103.065 2103.365 61.168 60.236 105.552 821.515 09-JAN-11 10 47 00.0 542.243 589.770 541.012 588.858 2101.963 2101.162 61.168 60.236 104.965 821.414 09-JAN-11 10 48 00.0 542.594 590.070 541.122 590.110 2100.861 2101.262 61.168 60.236 104.755 821.114 09-JAN-11 10 49 00.0 542.584 589.689 540.911 589.920 2101.162 2101.563 60.958 60.126 105.607 821.014 09-JAN-11 10 50 00.0 542.354 590.170 540.911 590.080 2101.162 2100.661 60.958 60.026 105.384 821.615 09-JAN-11 10 51 00.0 542.564 589.239 541.012 589.990 2101.162 2101.763 60.857 59.926 105.273 820.613 09-JAN-11 10 52 00.0 542.464 590.000 541.012 589.940 2100.861 2100.661 60.887 59.926 106.439 821.414 09-JAN-11 10 53 00.0 542.354 590.180 540.901 590.381 2101.863 2101.662 60.767 59.826 105.760 821.815 09-JAN-11 10 54 00.0 542.584 591.002 540.911 589.309 2101.863 2101.662 60.667 59.826 105.315 821.114 09-JAN-11 10 55 00.0 542.584 590.160 540.911 589.409 2100.961 2101.662 60.667 59.726 105.440 821.114 09-JAN-11 10 56 00.0 542.644 591.072 541.122 589.539 2102.063 2101.662 60.667 59.726 105.426 821.715 09-JAN-11 10 57 00.0 542.424 589.870 541.012 589.750 2101.262 2101.662 60.667 59.826 105.885 821.014 09-JAN-11 10 58 00.0 542.314 590.010 541.012 589.619 2100.761 2100.661 60.767 59.826 105.161 821.515 09-JAN-11 10 59 00.0 542.314 590.882 541.012 590.391 2101.963 2101.662 60.657 59.826 105.468 821.615 09-JAN-11 11 00 00.0 542.314 590.882 541.012 590.391 2101.963 2101.662 60.657 59.826 105.468 821.615

DATE/TIME *P0905A* *P1046* *P1048* *L0903Y* *L0906Y* *P0946A* *Y3273* *XC093* *XC105* *XC411* *PSIA • *PSIG * *PSIG * * % • • % * *PSIG * *MW * *ASIU * * MW * *% PWR*

09-JAN-11 08 15 00.0 818.410 788.787 784.101 62.893 62.957 528.436 529.333 0.012 1466.935 100.834 09-JAN-11 08 16 00.0 818.710 788.787 784.101 62.992 62.803 528.646 529.666 0.012 1467.072 102.385 09-JAN-11 08 17 00.0 818.610 788.787 784.101 63.043 62.732 528.365 529.460 0.013 1467.269 101.710 09-JAN-11 08 18 00.0 818.610 788.787 784.101 62.846 62.846 528.506 530.332 0.012 1467.472 102.566 09-JAN-11 08 19 00.0 818.309 788.787 784.101 62.850 63.174 528.295 530.110 0.012 1467.573 100.603 09-JAN-11 08 20 00.0 818.410 788.787 784.101 63.059 63.340 528.646 530.427 0.012 1467.549 100.259 09-JAN-11 08 21 00.0 818.410 788.787 784.101 62.988 62.969 528.506 530.158 0.012 1467.537 102.748 09-JAN-11 08 22 00.0 818.109 788.787 784.101 63.125 62.709 528.295 529.253 0.012 1467.562 101.851 09-JAN-11 08 23 00.0 818.209 788.787 784.101 62.957 63.139 528.295 529.825 0.012 1467.608 101.468 09-JAN-11 08 24 00.0 818.410 788.787 784.101 62.660 62.732 528.295 530.761 0.012 1467.598 102.113 09-JAN-11 08 25 00.0 818.710 788.787 784.101 62.838 63.051 528.365 530.332 0.012 1467.507 102.053 09-JAN-11 08 26 00.0 819.010 788.787 784.101 62.924 62.760 528.365 530.142 0.013 1467.419 102.677 09-JAN-11 08 27 00.0 818.810 788.787 784.101 63.078 62.854 528.436 529.333 0.012 1467.412 101.820

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09-JAN-11 08 28 00.0 818.410 788.787 784.101 63.016 62.869 528.295 530.713 0.012 1467.402 102.304 09-JAN-11 08 29 00.0 818.510 788.787 784.101 62.877 62.684 528.295 530.237 0.012 1467.396 101.851 09-JAN-11 08 30 00.0 819.010 788.787 784.101 62.924 62.861 528.436 529.840 0.011 1467.445 100.562 09-JAN-11 08 31 00.0 819.010 788.787 784.101 62.924 62.814 528.506 530.665 0.012 1467.421 101.257 09-JAN-11 08 32 00.0 818.610 788.787 784.101 62.857 62.885 528.365 529.888 0.012 1467.341 101.629 09-JAN-11 08 33 00.0 815.905 786.491 781.773 62.861 62.834 531.100 531.506 0.013 1467.235 100.854 09-JAN-11 08 34 00.0 812.500 783.154 778.456 63.178 63.166 531.801 532.918 0.017 1467.217 100.794 09-JAN-11 08 35 00.0 809.095 779.836 774.249 63.051 63.201 532.642 533.918 0.018 1467.588 102 .163 09-JAN-11 08 36 00.0 805.890 775.476 770.466 63.154 63.104 533.413 534.283 0.023 1468.143 101.357 09-JAN-11 08 37 00.0 802.284 772.171 767.217 63.260 63.473 533.694 535.600 0.025 1468.684 101.891 09-JAN-11 08 38 00.0 799.179 768.875 763.971 63.383 63.275 533.554 534.822 0.028 1469.363 101.196 09-JAN-11 08 39 00.0 795.473 764.558 759.544 63.070 63.248 532.572 534.076 0.032 1470.263 100.703 09-JAN-11 08 40 00.0 792.869 761.487 757.454 63.441 63.355 533.484 534.505 0.033 1471.270 101.660 09-JAN-11 08 41 00.0 790.966 759.287 755.134 63.213 63.352 534.185 535.536 0.035 1472.099 102.929 09-JAN-11 08 42 00.0 787.560 757.213 751.678 63.039 63.078 533.904 535.219 0.036 1472.800 101.025 09-JAN-11 08 43 00.0 784.655 754.013 748.436 62.807 63.367 533.413 534.203 0.036 1473.633 101.539 09-JAN-11 08 44 00.0 781.651 750.661 745.248 63.082 63.297 532.642 534.314 0.036 1474.522 101.972 09-JAN-11 08 45 00.0 779.648 748.370 744.020 63.170 63.189 532.222 533.347 0.035 1475.149 102.335 09-JAN-11 08 46 00.0 777.444 746.275 741.787 62.896 63.271 531.380 533.347 0.034 1475.529 102.788 09-JAN-11 08 47 00.0 776.242 745.135 739.655 62.941 63.221 531.591 533.458 0.033 1475.629 102.244 09-JAN-11 08 48 00.0 774.239 742.798 738.555 62.873 62.902 531.380 533.410 0.030 1475.343 103.201 09-JAN-11 08 49 00.0 773.738 742.798 737.482 63.070 63.004 530.819 533.109 0.030 1474.735 101.660 09-JAN-11 08 50 00.0 774.039 742.798 737.482 62.703 62.799 530.960 533.347 0.029 1474.088 101.771 09-JAN-11 08 51 00.0 773.638 742.798 737.482 62.916 62.744 530.329 532.093 0.030 1473.785 102.465 09-JAN-11 08 52 00.0 773.738 742.798 737.482 63.074 62.988 530.469 531.903 0.030 1473.810 102.577 09-JAN-11 08 53 00.0 773.337 742.798 737.482 63.020 62.854 530.609 532.268 0.031 1473.836 101.448 09-JAN-11 08 54 00.0 773.638 742.798 737.482 63.027 62.857 530.609 532.284 0.030 1473.554 102.778 09-JAN-11 08 55 00.0 773.838 741.729 737.482 62.896 62.961 530.749 532.918 0.030 1473.148 101.267 09-JAN-11 08 56 00.0 773.738 741.729 737.482 62.877 62.775 530.749 531.982 0.031 1472.819 102.455 09-JAN-11 08 57 00.0 773.638 741.729 737.482 62.949 62.869 530.749 533.093 0.031 1472.605 103.120 09-JAN-11 08 58 00.0 773.438 741.729 737.482 62.980 62.740 530.819 533.331 0.031 1472.594 102.878 09-JAN-11 08 59 00.0 773.638 741.729 737.482 62.711 62.934 530.609 532.950 0.031 1472.780 102.697 09-JAN-11 09 00 00.0 774.439 741.729 737.482 63.000 63.127 529.978 532.506 0.031 1473.020 100.945 09-JAN-11 09 01 00.0 776.643 744.964 739.503 62.740 62.891 529.978 531.713 0.035 1473.163 101.690 09-JAN-11 09 02 00.0 778.646 747.120 742.617 62.881 62.547 530.188 532.125 0.038 1473.072 105.054 09-JAN-11 09 03 00.0 781.250 749.396 744.753 62.984 62.559 530.749 532.125 0.039 1472.882 102.223 09-JAN-11 09 04 00.0 783.754 752.721 747.929 62.625 62.492 530.960 533.061 0.040 1472.938 102.919 09-JAN-11 09 OS 00.0 787.059 755.810 750.124 62.672 62.439 530.960 532.442 0.040 1473.274 102.264 09-JAN-11 09 06 00.0 789.664 758.074 753 .144 62.648 62.729 530.889 532.379 0. 038 1473.815 103.321 09-JAN-11 09 07 00.0 791.967 761.223 756.349 62.633 62.543 530.539 533.029 o. 037 1474.507 103.059 09-JAN-11 09 08 00.0 794.171 763.338 758.547 62.814 62.645 529.838 531.919 0.035 1475.136 102.788 09-JAN-11 09 09 00.0 797.776 766.580 762.092 62.732 62.660 529.838 531.586 0.034 1475.547 101.941 09-JAN-11 09 10 00.0 800.481 769.803 765.115 62.814 62.885 529.417 531.030 0.032 1475.750 102.556 09-JAN-11 09 11 00.0 802.684 772.062 767.533 62.744 62.551 527.244 528.175 0.032 1475.846 102.002 09-JAN-11 09 12 00.0 807.091 776.492 771.759 62.688 62.854 527.664 528.920 0.028 1475.814 102.969 09-JAN-11 09 13 00.0 811.198 781.016 776.256 62.668 62.842 526.893 528.587 0.025 1475.498 101.851 09-JAN-11 09 14 00.0 815.204 785.329 780.766 62.771 62.582 527.033 528.000 0.021 1474.912 102.566 09-JAN-11 09 15 00.0 817.208 787.365 782.872 62.744 62.471 527.103 527.651 0.019 1474.020 102.042 09-JAN-11 09 16 00.0 818.209 788.518 782.872 62.857 62.439 527.594 529.476 0.017 14 72. 984 103.180 09-JAN-11 09 17 00.0 818.309 788.518 784.109 62.807 62.617 527.945 530.063 0.016 1472.030 102.968 09-JAN-11 09 18 00.0 818.610 788.518 784.109 63.004 62.984 528.155 529.111 0.017 1471.197 101.861 09-JAN-11 09 19 00.0 818.810 788.518 784.109 62.893 63.166 527.945 529.587 0.016 1470.462 101.408 09-JAN-11 09 20 00.0 818.910 788.518 784.109 63.121 62.945 528.365 529.777 0.016 1469.769 101.851 09-JAN-11 09 21 00.0 818.510 788.518 784.109 62.916 62.803 528.015 530.158 0.017 1469.030 101.599 09-JAN-11 09 22 00.0 818.510 788.518 784.109 62.938 62.803 528.085 529.967 0.016 1468.452 101.388 09-JAN-11 09 23 00.0 818.510 788.518 784.109 62.969 62.918 528.155 529.364 0.017 1468.122 101.579 09-JAN-11 09 24 00.0 818.410 788.518 784.109 62.969 62.771 528.085 529.587 0.017 1467.864 102.214 09-JAN-11 09 25 00.0 818.309 788.518 784.109 63.217 62.764 528.155 530.380 0.017 1467.795 102.647 09-JAN-11 09 26 00.0 818.109 788.518 784.109 63.027 62.877 528.085 529.650 0.017 1467.717 101.891 09-JAN-11 09 27 00.0 818.209 788.518 784.109 62.969 63.078 529.137 529.507 0.016 1467.431 101.619 09-JAN-11 09 28 00.0 814.904 785.338 780.894 63.121 63.012 531.731 533.759 0.018 1467.077 101.267 09-JAN-11 09 29 00.0 812.200 781.999 777.476 63.117 63.082 533.273 534.156 0.021 1466.910 101.418

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09-JAN-11 09 30 00.0 808.494 777.715 773.028 62.961 62.857 533.694 534.965 0. 025 1467.182 101.065 09-JAN-11 09 31 00.0 803.786 773.344 769.456 63.086 63.170 533.554 534.616 0.029 1467.899 103.150 09-JAN-11 09 32 00.0 800.581 770.046 765.101 63.000 63.490 533.624 534.584 0.032 1468.846 101.962 09-JAN-11 09 33 00.0 796.174 766.529 761.814 63.178 63.104 533.343 534.854 0.035 1469.826 101.932 09-JAN-11 09 34 00.0 792.768 762.226 757.265 63.357 63.127 532.853 533.505 0. 039 1470.846 102.435 09-JAN-11 09 35 00.0 789.263 758.686 753.807 63.334 63.383 532.502 533.839 0.040 1471.685 102.345 09-JAN-11 09 36 00.0 786.759 756.401 750.580 63.330 63.395 532.292 534.679 0.041 1472.292 100.975 09-JAN-11 09 37 00.0 783.954 753.087 748.491 63.326 63.051 532.011 532.601 0.040 1472.740 101.338 09-JAN-11 09 38 00.0 781.450 750.797 746.230 63.154 63.328 531.661 533.378 0.039 1473.135 100.612 09-JAN-11 09 39 00.0 779.147 748.690 744 .158 63.074 62.953 531.450 532.918 0.039 1473.461 101.931 09-JAN-11 09 40 00.0 777.945 747.556 741.960 63.102 62.736 531.520 533.283 0.038 1473.503 101.196 09-JAN-11 09 41 00.0 777.043 746.366 740.816 62.928 63.170 531.450 533.585 0.037 1473.242 101.166 09-JAN-11 09 42 00.0 775.841 744.190 739.727 63.008 63.158 531.661 533.759 0.038 1472.918 102.193 09-JAN-11 09 43 00.0 774.239 743.111 738.719 62.938 62.705 531.380 533.156 0.036 1472.578 101.912 09-JAN-11 09 44 00.0 773.337 742.102 737.644 62.900 63.111 531.030 533.109 0.035 1472.321 102.858 09-JAN-11 09 45 00.0 773.438 742.102 736.638 63.020 62.826 531.170 532.902 0.035 1472.272 102.203 09-JAN-11 09 46 00.0 773.237 742 .102 736.638 62.779 62.977 530.960 533.156 0.034 1472.371 103.180 09-JAN-11 09 47 00.0 773.237 742.102 736 .63S 62.916 62.877 530.749 532.062 0.035 1472.551 101.025 09-JAN-11 09 48 00.0 773.337 742 .102 736.638 62.908 63.016 530.819 531.665 0.036 1472.867 101.578 09-JAN-11 09 49 00.0 773.037 742 .102 736.638 62.916 63.092 530.679 532.062 0.035 1473.295 101.751 09-JAN-11 09 SO 00.0 773.438 742.102 736.638 62.969 63.055 531.170 533.029 0.035 1473.646 101.327 09-JAN-11 09 51 00.0 772.837 742.102 736.638 63.039 62.783 530.749 532.744 0.036 1473.889 102.617 09-JAN-11 09 52 00.0 773.137 742.102 736.638 63.023 63.248 530.889 531.443 0.036 1473.965 102.908 09-JAN-11 09 53 00.0 773.438 742.102 736.638 62.838 62.996 530.749 533.045 0.036 1473.941 101.660 09-JAN-11 09 54 00.0 773.137 742.102 736.638 62.838 62.898 530.749 532.188 0.036 1473.879 102.938 09-JAN-11 09 55 00.0 774.039 742.102 737.784 62.953 62.574 529.978 532.188 0.037 1473.777 102.173 09-JAN-11 09 56 00.0 776.242 744.395 740.163 62.941 62.854 530.329 531.776 0.041 1473.700 102.929 09-JAN-11 09 57 00.0 778.345 746.672 742.214 62.707 62.861 530.258 532.934 0.042 1473.724 101.851 09-JAN-11 09 58 00.0 780.950 748.893 744.732 62.719 62.775 530.469 532.188 0.043 1473.723 102.626 09-JAN-11 09 59 00.0 782.652 750.954 746.794 62.740 62.455 530.399 531.998 0.044 1473.704 104.057 09-JAN-11 10 00 00.0 785.156 754.354 748.881 62.744 62.563 530.469 531.665 0.044 1473.766 102.173 09-JAN-11 10 01 00.0 787.660 756.612 751.940 62.672 62.566 530.258 531.935 0.044 1473.928 101.186 09-JAN-11 10 02 00.0 790.365 758.700 754.138 62.691 62.701 529.838 530.872 0.043 1474.213 102.576 09-JAN-11 10 03 00.0 792.568 761.798 757.351 62.850 62.471 529.207 531.665 0.043 1474.632 102.848 09-JAN-11 10 04 00.0 795.172 763.983 759.817 62.904 62.672 528.506 530.015 0.041 1474.975 101. SOB 09-JAN-11 10 OS 00.0 798.878 768.298 763.101 62.771 62.740 528.155 530.205 0.037 1475.035 101.730 09-JAN-11 10 06 00.0 803.986 773.226 767.820 62.834 62.705 528.576 531.966 0.033 1474.977 102.425 09-JAN-11 10 07 00.0 808.193 777.596 773.746 62.684 62.543 528.225 530.412 0.031 1474.849 102.385 09-JAN-11 10 08 00.0 810.998 781.080 775.980 62.656 62.408 528.646 530.919 0.027 1474.523 102.404 09-JAN-11 10 09 00.0 814.303 784.158 779.296 62.516 62.451 528.085 529.412 0.025 1474.012 101.377 09-JAN-11 10 10 00.0 817.007 786.396 782.411 62.531 62.668 527.805 529.507 0.022 1473.534 100.713 09-JAN-11 10 11 00.0 817.308 787.399 782.411 62.748 62.760 528.225 529.285 0.021 1473.083 102.506 09-JAN-11 10 12 00.0 817.909 788.461 783.427 62.896 62.717 527.945 530.348 0.021 1472.490 101.770 09-JAN-11 10 13 00.0 817.909 788.461 783.427 63.217 62.563 528.015 529.936 0. 021 1471.731 102.999 09-JAN-11 10 14 00.0 818.209 788.461 783.427 63.039 63.096 528.155 529.650 0.021 1470.924 101.166 09-JAN-11 10 15 00.0 818.009 788.461 783.427 63.047 63.162 527.945 529.840 0.022 1470.251 101.418 09-JAN-11 10 16 00.0 818.209 788.461 783.427 62.779 62.881 528.155 529.666 0. 021 1469.633 100.975 09-JAN-11 10 17 00.0 818.009 788.461 783.427 62.889 62.656 528.085 530.539 0. 021 1468.968 100.532 09-JAN-11 10 18 00.0 818.109 788.461 783.427 63.217 62.818 528.155 529.714 0. 021 1468.443 101.348 09-JAN-11 10 19 00.0 818.309 788.461 783.427 62.893 62.732 528.085 530.142 0. 021 1468.067 101.428 09-JAN-11 10 20 00.0 818.109 788.461 783.427 62.941 63.201 527.945 530.205 0.021 1467.693 101.690 09-JAN-11 10 21 00.0 817.909 788.461 783.427 62.838 62.988 528.085 529.872 0.020 1467.389 101.267 09-JAN-11 10 22 00.0 817.909 788.461 783.427 63.102 62.945 528.365 528.762 0.020 1467.128 102.032 09-JAN-11 10 23 00.0 818.109 788.461 783.427 63.008 62.768 527.945 529.809 0.021 1466.828 100.703 09-JAN-11 10 24 00.0 821.515 791.957 787.586 62.838 63.135 523.458 525.097 0.022 1466.565 100.602 09-JAN-11 10 25 00.0 822.015 792.976 788.594 62.602 63.043 518.690 520.956 0.030 1466.197 99.323 09-JAN-11 10 26 00.0 820.212 791.939 787.585 63.551 63.383 514.623 516.529 0.035 1465.534 99.222 09-JAN-11 10 27 00.0 822.817 794.042 789.700 63.445 63.650 511.188 513.023 0.035 1464.211 99.232 09-JAN-11 10 28 00.0 825.922 797.620 792.932 63.547 63.600 508.454 511.611 0.036 1461.372 98.306 09-JAN-11 10 29 00.0 825.220 798.654 794.077 63.295 63.189 504.597 508.184 0.039 1456.819 96.936 09-JAN-11 10 30 00.0 823.718 796.615 791.785 63.477 63.430 502.845 506.502 0.039 1451.287 96.987 09-JAN-11 10 31 00.0 823.918 796.615 791.785 63.141 63.264 502.845 506.487 0.039 1445.024 97.319

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09-JAN-11 10 32 00.0 823.217 796.615 791.785 62.861 63.074 502.845 505.106 0.039 1438.265 97.148 09-JAN-11 10 33 00.0 823.017 796.615 791.785 62.873 62.977 502.494 505.614 0.039 1431.585 97.803 09-JAN-11 10 34 00.0 823.117 795.579 791.785 62.826 62.744 502.564 504.995 0.040 1425.045 96.644 • 09-JAN-11 10 35 00.0 822.817 795.579 791.785 62.764 63.016 502.354 504.345 0.040 1418.854 97.682 09-JAN-11 10 36 00.0 822.616 795.579 791.785 62.928 62.732 502.424 505.693 0.040 1413.214 97.238 09-JAN-11 10 37 00.0 822.516 795.579 791.785 62.969 62.992 502.284 504.361 0.040 1408.443 96.261 09-JAN-11 10 38 00.0 822.516 795.579 790.644 63.035 62.949 501.863 503.615 0.040 1405.252 96.836 09-JAN-11 10 39 00.0 822.316 795.579 790.644 63.174 62.807 502.214 505.424 0.040 1403.610 96.956 09-JAN-11 10 40 00.0 822.115 795.579 790.644 63.031 62.795 502.073 505.630 0.040 1403.114 98.155 09-JAN-11 10 41 00.0 821.715 794.572 790.644 63.105 63.059 505.369 507.470 0.040 1402.285 97.832 09-JAN-11 10 42 00.0 820.413 792.565 788.205 63.020 62.865 509.575 511.516 0.039 1402.489 98 .125 09-JAN-11 10 43 00.0 819.712 791.452 787.111 62.744 62.744 513.922 515.451 0.035 1403.265 98.085 09-JAN-11 10 44 00.0 817.608 789.414 784.955 62.605 62.455 517.708 520.892 0.032 1404.884 99.323 09-JAN-11 10 45 00.0 816.707 788.391 783.763 62.535 62.980 520.373 523.209 0.028 1407.465 100.401 09-JAN-11 10 46 00.0 816.506 787.258 782.627 62.629 62.211 523.878 526.112 0.024 1410.953 100.834 09-JAN-11 10 47 00.0 816.607 787.258 782.627 62.381 62.145 526.122 527.857 0.021 1415.330 100.451 09-JAN-11 10 48 00.0 816.006 786.241 781.620 62.494 62.381 526.613 527.540 0.021 1420.622 101.035 09-JAN-11 10 49 00.0 815.705 786.241 781.620 62.574 62.451 526.613 528.603 0.022 1426.665 100.874 09-JAN-11 10 50 00.0 816.006 786.241 781.620 62.941 62.811 526.823 528.730 0.021 1433.156 101.609 09-JAN-11 10 51 00.0 816.106 786.241 781.620 62.760 62.965 526.683 528.587 0.022 1439.801 100.935 09-JAN-11 10 52 00.0 815.905 786.241 781.620 62.924 63.111 526.823 530.237 0.022 1446.249 100.411 09-JAN-11 10 53 00.0 816.506 786.241 781.620 62.961 63.170 527.033 527.318 0.022 1452.043 102.043 09-JAN-11 10 54 00.0 816.406 786.241 782.628 62.799 62.807 526.963 528.809 0.022 1456.789 102.344 09-JAN-11 10 55 00.0 816.406 786.241 782.628 62.652 62.672 527.033 527.112 0.022 1460.331 101.358 09-JAN-11 10 56 00.0 816.106 786.241 782.628 63.166 62.760 526.893 528.571 0.021 1462.870 102.918 09-JAN-11 10 57 00.0 816.707 786.241 782.628 62.873 62.803 526.963 528.270 0.021 1464.542 100.834 09-JAN-11 10 58 00.0 816.707 786.241 782.628 63.193 63.131 527.384 529.428 0.021 1465.264 101.226 09-JAN-11 10 59 00.0 816.406 786.241 782.628 62.912 62.996 527.314 527.714 0.021 1465.264 102.334 09-JAN-11 11 00 00.0 816.406 786.241 782.628 62.912 62.996 527.314 527.714 0.021 1465.264 102.334

DATE/TIME *AR002X* *AR002Y* *BR002X* *BR002Y* *CR002X* *CR002Y* *DR002X* *DR002Y* *R0003X* *R0003Y* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR* * % PWR*

09-JAN-11 08 15 00.0 48.508 49.029 47.630 47.779 48.534 49.035 48.069 48.630 51.804 52.248 09-JAN-11 08 16 00.0 48.479 49.019 47.829 47.929 48.526 49.050 48.306 48.838 51.894 52.452 09-JAN-11 08 17 00.0 48.340 48.899 47.679 47.832 48.418 48.962 48.191 48.740 51.663 52.215 09-JAN-11 08 18 00.0 48.574 49.109 47.768 47.889 48.526 49.032 48.245 48.769 51.856 52.463 09-JAN-11 08 19 00.0 48.433 48.986 47.779 47.888 48.561 49.075 48.348 48.846 51.825 52.378 09-JAN-11 08 20 00.0 48.441 48.998 47.764 47.902 48.561 49.103 48.343 48.865 51.803 52.333 09-JAN-11 08 21 00.0 48.330 48.872 47.755 47.893 48.349 48.875 48.130 48.663 51.606 52.202 09-JAN-11 08 22 00.0 48.538 49.066 47.885 47.997 48.535 49.042 48.258 48.782 51.713 52.293 09-JAN-11 08 23 00.0 48.433 48.968 47.790 47.917 48.457 48.966 48.215 48.736 51.798 52.335 09-JAN-11 08 24 00.0 48.506 49.037 47.846 47.963 48.572 49.091 48.311 48.854 51.814 52.380 09-JAN-11 08 25 00.0 48.500 49.061 47.973 48.082 48.436 48.978 48.269 48.808 51.752 52.354 09-JAN-11 08 26 00.0 48.391 48.949 47.804 47.933 48.300 48.859 48.027 48.583 51.620 52.213 09-JAN-11 08 27 00.0 48.431 48.970 47.644 4 7. 774 48.510 49.011 48.240 48.755 51.846 52.397 09-JAN-11 08 28 00.0 48.553 49.096 47.952 48.093 48.500 49.032 48.454 48.966 51.837 52.314 09-JAN-11 08 29 00.0 48.446 48.997 47.800 47.933 48.439 48.978 48.141 48.670 51.731 52.295 09-JAN-11 08 30 00.0 48.519 49.027 47.744 47.864 48.489 48.984 48.173 48.692 51.808 52.356 09-JAN-11 08 31 00.0 48.434 48.955 47.676 47.801 48.447 48.971 48.200 48.742 51.713 52.338 09-JAN-11 08 32 00.0 48.285 48.840 47.723 47.843 48.279 48.821 48.138 48.694 51.542 52.114 09-JAN-11 08 33 00.0 48.466 49.059 47.885 48.056 48.476 49.077 48.407 48.981 51.764 52.402 09-JAN-11 08 34 00.0 48.388 49.088 47.803 48.080 48.473 49.168 48.303 49.013 51.723 52.460 09-JAN-11 08 35 00.0 48.234 49.002 47.829 48.159 48.296 49.069 48.268 49.019 51.441 52.269 09-JAN-11 08 36 00.0 48.000 48.942 47.425 47.910 48.130 49.051 47.880 48.808 51.399 52.370 09-JAN-11 08 37 00.0 47.986 49.002 4 7.458 48.058 48.165 49.186 47.901 48.912 51.316 52.402 09-JAN-11 08 38 00.0 48.090 49.202 47.599 48.260 48.178 49.293 47.974 49.082 51.369 52.487 09-JAN-11 08 39 00.0 47.745 49.018 47.317 48.138 47.854 49.136 47.580 48.846 50.965 52.337 09-JAN-11 08 40 00.0 47.691 48.987 47.303 48.157 47.772 49.085 47.643 48.926 50.963 52.351 09-JAN-11 08 41 00.0 47.567 48.917 47.154 48.064 47.780 49.154 47.663 48.966 50.901 52.452 09-JAN-11 08 42 00.0 47.607 48.990 46.994 47.958 47.784 49.176 47.551 48.918 50.862 52.345 09-JAN-11 08 43 00.0 47.550 48.958 47.087 48.066 47.643 49.066 47.471 48.851 50.798 52.311 09-JAN-11 08 44 00.0 47.386 48.737 46.893 47.873 47.473 48.878 47.218 48.577 50.785 52.276

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09-JAN-11 08 45 00.0 47.518 48.843 47.024 47.950 47.556 48.912 47.296 48.644 50.567 52.021 09-JAN-11 08 46 00.0 47.396 48.678 46.803 47.712 47.513 48.813 47.357 48.635 50.530 51.925 09-JAN-11 08 47 00.0 47.420 48.665 46.926 47.790 47.577 48.873 47.474 48.699 50.636 51.992 • 09-JAN-11 08 48 00.0 47.434 48.572 46.843 47.614 47.482 48.644 47.245 48.380 50.635 51.856 09-JAN-11 08 49 00.0 47.393 48.551 46.758 47.558 47.454 48.643 47.220 48.369 50.609 51.933 09-JAN-11 08 50 00.0 47.582 48.723 47.042 47.793 47.607 48.768 47.373 48.510 50.803 52.021 09-JAN-11 08 51 00.0 47.370 48.530 46.978 4 7. 744 47.367 48.551 47.522 48.639 50.527 51.776 09-JAN-11 08 52 00.0 47.372 48.534 46.894 47.681 47.505 48.699 47.321 48.482 50.652 51.904 09-JAN-11 08 53 00.0 47.542 48.699 46.891 47.700 47.556 48.745 47.351 48.527 50.734 51.976 09-JAN-11 08 54 00.0 47.484 48.644 46.885 47.684 47.471 48.652 47.212 48.375 50.623 51.877 09-JAN-11 08 55 00.0 47.514 48.694 46.994 47.796 47.556 48.755 47.380 48.522 50.753 51.992 09-JAN-11 08 56 00.0 47.412 48.598 46.856 47.694 47.447 48.663 47.237 48.413 50.681 51.854 09-JAN-11 08 57 00.0 47.471 48.651 46.949 47.772 47.530 48.742 47.380 48.545 50.580 51.849 09-JAN-11 08 58 00.0 47.425 48.622 46.889 47.720 47.338 48.545 47.191 48.372 50.513 51.801 09-JAN-11 08 59 00.0 47.529 48.718 47.064 47.891 47.524 48.748 47.349 48.529 50.588 51.894 09-JAN-11 09 00 00.0 47.425 48.625 46.885 47.724 47.546 48.752 47.415 48.577 50.551 51.840 09-JAN-11 09 01 00.0 47.466 48.785 46.990 47.921 47.500 48.856 47.287 48.587 50.707 52.138 09-JAN-11 09 02 00.0 47.567 49.000 46.952 47.997 47.471 48.955 47.372 48.788 50.792 52.351 09-JAN-11 09 03 00.0 47.537 49.016 47.027 48.119 47.566 49.080 47.377 48.861 50.732 52.332 09-JAN-11 09 04 00.0 47.527 49.045 47.038 48.135 47.482 49.038 47.308 48.804 50.696 52.343 09-JAN-11 09 OS 00.0 47.535 49.051 47.127 48.213 47.609 49.165 4 7. 494 48.992 50.822 52.399 09-JAN-11 09 06 00.0 47.792 49.244 47.271 48.295 47.830 49.322 47.571 49.019 50.921 52.502 09-JAN-11 09 07 00.0 47.776 49.213 47.356 48.361 47.747 49.216 47.646 49.054 51.050 52.583 09-JAN-11 09 08 00.0 47.960 49.327 47.455 48.373 48.022 49.425 47.910 49.266 51.178 52.614 09-JAN-11 09 09 00.0 48.006 49.337 47.519 48.396 47.954 49.308 47.740 49.067 51.122 52.567 09-JAN-11 09 10 00.0 47.784 49.050 47.239 48.083 47.862 49.175 47.681 48.971 51.152 52.514 09-JAN-11 09 11 00.0 48.075 49.319 47.365 48.184 48.058 49.311 47.708 48.958 51.319 52.639 09-JAN-11 09 12 00.0 48.098 49.216 47.587 48.274 48.117 49.269 47.970 49.095 51.200 52.420 09-JAN-11 09 13 00.0 48.125 49.114 47.513 48.082 48.127 49.136 47.986 48.982 51.431 52.497 09-JAN-11 09 14 00.0 48.271 49.133 4 7. 641 48.075 48.335 49.199 48.071 48.926 51.546 52.489 09-JAN-11 09 15 00.0 48.149 48.963 47.615 48.000 48.290 49.093 47.987 48.784 51.465 52.325 09-JAN-11 09 16 00.0 48.272 49.022 47.667 48.000 48.269 49.018 48.125 48.872 51.503 52.304 09-JAN-11 09 17 00.0 48.508 49.200 47.840 48.125 48.564 49.250 48.269 48.944 51.841 52.577 09-JAN-11 09 18 00.0 48.359 49.074 47.740 48.030 48.522 49.224 48.218 48.934 51.760 52.510 09-JAN-11 09 19 00.0 48.492 49.186 47.830 48.109 48.550 49.245 48.213 48.904 51.856 52.591 09-JAN-11 09 20 00.0 48.583 49.261 47.966 48.229 48.652 49.340 48.396 49.063 51.912 52.646 09-JAN-11 09 21 00.0 48.288 49.013 47.728 48.042 48.330 49.053 48.111 48.827 51.558 52.316 09-JAN-11 09 22 00.0 48.393 49.103 47.841 48.135 48.508 49.236 48.364 49.077 51.729 52.479 09-JAN-11 09 23 00.0 48.361 49.082 47.825 48.125 48.619 49.327 48.261 48.976 51.646 52.502 09-JAN-11 09 24 00.0 48.365 49.061 47.816 48.101 48.446 49.160 48.280 48.984 51.670 52.417 09-JAN-11 09 25 00.0 48.519 49.202 47.788 48.069 48.543 49.242 48.175 48.893 51.806 52.550 09-JAN-11 09 26 00.0 48.367 49.077 47.732 48.037 48.450 49.163 48.146 48.848 51.784 52.542 09-JAN-11 09 27 00.0 48.438 49.141 47.864 48.143 48.554 49.252 48.269 48.968 51.885 52.636 09-JAN-11 09 28 00.0 48.534 49.282 47.808 48.14 7 48.537 49.300 48.282 49.038 51.854 52.577 09-JAN-11 09 29 00.0 48.159 49.013 47.546 48.003 48.404 49.261 48.130 48.976 51.538 52 .446 09-JAN-11 09 30 00.0 48.112 49.096 47.590 48.154 48.268 49.258 47.936 48.926 51.391 52.444 09-JAN-11 09 31 00.0 47.950 49.077 47.370 48.079 48.136 49.301 47.918 49.050 51.296 52.521 09-JAN-11 09 32 00.0 47.897 49.149 47.399 48.234 47.955 49.252 47.803 49.067 51.197 52.545 09-JAN-11 09 33 00.0 47.824 49.192 47.388 48.309 47.894 49.277 47.692 49.059 51.151 52.617 09-JAN-11 09 34 00.0 4 7. 630 49.112 47.144 48.192 47.768 49.264 4 7.458 48.934 51.008 52.606 09-JAN-11 09 35 00.0 4 7. 540 49.043 47.199 48.272 47.652 49.208 47.409 48.934 50.851 52.474 09-JAN-11 09 36 00.0 47.446 48.986 47.037 48.167 47.667 49.245 47.439 48.974 50.681 52.357 09-JAN-11 09 37 00.0 47.625 49.173 47.131 48.264 47.745 49.329 47.556 49.074 50.830 52.497 09-JAN-11 09 38 00.0 47.151 48.628 46.712 47.785 47.361 48.880 47.218 48.676 50.444 52.069 09-JAN-11 09 39 00.0 47.322 48.806 46.872 47.966 47.516 49.029 47.301 48.752 50.582 52.173 09-JAN-11 09 40 00.0 47.348 48.798 46.873 47.946 47.425 48.917 47.228 48.673 50.558 52.117 09-JAN-11 09 41 00.0 47.389 48.780 46.857 47.883 47.450 48.889 47.197 48.590 50.571 52.090 09-JAN-11 09 42 00.0 47.606 49.019 46.944 48.005 47.490 48.968 47.277 48.688 50.673 52.226 09-JAN-11 09 43 00.0 4 7.441 48.787 46.877 47.870 47.510 48.883 47.224 48.569 50.659 52.095 09-JAN-11 09 44 00.0 47.439 48.748 46.897 47.840 47.397 48.723 47.223 48.548 50.545 51.965 09-JAN-11 09 45 00.0 47.587 48.894 47.066 47.994 47.500 48.875 47.343 48.654 50.707 52.101 09-JAN-11 09 46 00.0 47.550 48.861 47.008 47.958 47.679 49.030 47.486 48.788 50.809 52.218

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09-JAN-11 09 47 00.0 47.280 48.612 46.864 47.827 47.537 48.889 47.372 48.675 50.644 52.064 09-JAN-11 09 48 00.0 47.280 48.633 46.857 47.829 47.378 48.771 47.223 48.566 50.470 51.938 09-JAN-11 09 49 00.0 47.410 48.726 46.886 47.829 47.615 48.960 47.417 48.729 50.742 52.152 • 09-JAN-11 09 50 00.0 47.429 48.771 46.992 4 7. 954 47.513 48.894 47.378 48.707 50.631 52.061 09-JAN-11 09 51 00.0 47.296 48.659 46.835 47.817 4 7. 394 48.772 47.229 48.588 50.487 52.035 09-JAN-11 09 52 00.0 47.272 48.630 46.681 47.688 47.303 48.713 47.260 48.598 50.420 51.894 09-JAN-11 09 53 00.0 47.306 48.683 46.720 47.742 47.290 48.708 47.155 48.506 50.468 51.954 09-JAN-11 09 54 00.0 4 7.487 48.832 46.926 47.909 4 7.481 48.861 47.304 48.654 50.655 52.114 09-JAN-11 09 55 00.0 47.428 48.833 46.982 48.037 47.593 49.035 47.296 48.683 50.710 52.252 09-JAN-11 09 56 00.0 47.348 48.886 46.992 48.149 47.486 49.059 47.338 48.851 50.516 52.285 09-JAN-11 09 57 00.0 47.402 48.984 46.821 48.019 47.436 49.048 47.112 48.670 50.599 52.271 o9-JAN-11 09 sa oo.o 47.548 49.146 47.093 48.316 47.787 49.431 47.418 49.021 50.692 52.455 09-JAN-11 09 59 00.0 47.417 49.045 46.960 48.210 47.429 49.127 47.196 48.832 50.665 52.421 09-JAN-11 10 00 00.0 47.401 49.079 46.952 48.213 47.585 49.298 47.399 49.061 50.623 52.413 09-JAN-11 10 01 00.0 47.548 49.210 47.109 48.341 47.583 49.282 47.373 48.997 50.740 52.551 09-JAN-11 10 02 00.0 47.579 49.194 47.027 48.236 4 7. 614 49.296 47.268 48.904 50.859 52.540 09-JAN-11 10 03 00.0 47.511 49.112 47.048 48.240 4 7. 494 49.162 47.292 48.904 50.684 52.423 09-JAN-11 10 04 00.0 47.713 49.272 47.269 48.409 47.819 49.431 47.527 49.074 50.966 52.651 09-JAN-11 10 OS 00.0 47.787 49.215 47.284 48.290 48.005 49.462 47.593 49.035 51.133 52.675 09-~AN-~~ ~U U6 UU.U 4%.064 49-.310 41.532. 4'0.41.3 ~'0.1.'01. ~9-.~9-S ~'3 .'i)~3 ~9.31.1. 51..f:t1./ 52.'3~9 09-JAN-11 10 07 00.0 48.072 49.282 47.454 48.237 48.220 49.442 47.875 49.080 51.506 52.769 09-JAN-11 10 08 00.0 48.260 49.319 47.644 48.288 48.196 49.282 48.071 49.147 51.470 52.603 09-JAN-11 10 09 00.0 48.410 49.380 47.744 48.303 48.335 49.329 48.042 49.051 51.649 52.686 09-JAN-11 10 10 00.0 48.436 49.337 47.808 48.285 48.433 49.341 48.333 49.208 51.766 52.726 09-JAN-11 10 11 00.0 48.438 49.317 47.845 48.295 48.429 49.319 48.191 49.059 51.782 52.686 09-JAN-11 10 12 00.0 48.460 49.330 47.857 48.314 48.460 49.349 48.207 49.082 51.686 52.604 09-JAN-11 10 13 00.0 48.343 49.196 47.838 48.269 48.494 49.357 48.178 49.061 51.579 52.591 09-JAN-11 10 14 00.0 48.361 49.204 47.785 48.216 48.514 49.380 48.309 49.159 51.732 52.679 09-JAN-11 10 15 00.0 48.385 49.231 47.768 48.213 48.535 49.401 48.247 49.109 51.721 52.635 09-JAN-11 10 16 00.0 48.345 49.202 47.654 48.104 48.529 49.386 48.189 49.042 51.663 52.572 09-JAN-11 10 17 00.0 48.293 49.139 47.633 48.083 48.529 49.394 48.229 49.087 51.655 52.546 09-JAN-11 10 18 00.0 48.362 49.220 47.821 48.269 48.405 49.271 48.090 48.966 51.651 52.590 09-JAN-11 10 19 00.0 48.123 48.992 47.572 48.029 48.226 49.122 48.128 48.995 51.457 52.389 09-JAN-11 10 20 00.0 48.369 49.224 47.813 48.263 48.413 49.284 48.188 49.058 51.679 52.688 09-JAN-11 10 21 00.0 48.295 49.144 47.978 48.380 48.396 49.253 48.252 49.080 51.628 52.530 09-JAN-11 10 22 00.0 48.407 49.245 47.817 48.232 48.530 49.354 48.359 49.199 51.678 52.688 09-JAN-11 10 23 00.0 48.258 49.122 47.750 48.197 48.346 49.228 48.058 48.923 51.579 52.490 09-JAN-11 10 24 00.0 48.285 49.162 47.611 48.074 48.407 49.279 48.059 48.950 51.612 52.538 09-JAN-11 10 25 00.0 47.556 48.726 47.016 47.755 47.647 48.825 47.321 48.478 so. 811 52.075 09-JAN-11 10 26 00.0 47.173 48.527 46.806 47.705 47.364 48.739 47.207 48.546 50.409 51.838 09-JAN-11 10 27 00.0 47.074 48.423 46.494 47.409 47.168 48.540 46.803 48.149 50.054 51.510 09-JAN-11 10 28 00.0 46.845 48.229 46.319 47.271 46.963 48.375 46.723 48.079 50.189 51.657 09-JAN-11 10 29 00.0 46.465 47.925 45.878 46.934 46.614 48.093 46.393 47.851 49.566 51.122 09-JAN-11 10 30 00.0 46.333 47.801 45.849 46.918 46.389 47.894 46.287 47.734 49.540 51.048 09-JAN-11 10 31 00.0 46.447 47.904 45.982 47.018 46.442 47.963 46.321 47.788 49.622 51.095 09-JAN-11 10 32 00.0 46.421 47.878 45.904 46.965 46.598 48.099 46.478 47.926 49.558 51.197 09-JAN-11 10 33 00.0 46.470 47.926 45.973 47.010 46.438 47.933 46.189 47.660 49.537 51.125 09-JAN-11 10 34 00.0 46.332 47.798 45.843 46.925 46.369 47.893 46.226 4 7. 704 49.728 51.288 09-JAN-11 10 35 00.0 46.296 47.787 45.936 47.005 46.569 48.069 46.207 47.683 49.303 50.893 09-JAN-11 10 36 00.0 46.263 47.758 45.822 46.886 46.306 47.840 46.117 47.612 49.439 51.022 09-JAN-11 10 37 00.0 46.213 47.704 45.758 46.827 46.349 47.875 46.083 47.575 49.407 50.998 09-JAN-11 10 38 00.0 46.240 47.736 45.745 46.835 46.276 47.798 46.069 47.563 49.636 51.208 09-JAN-11 10 39 00.0 46.425 47.921 45.990 4 7. 046 46.404 47.928 46.226 47.699 49.593 51.184 09-JAN-11 10 40 00.0 46.325 47.809 45.784 46.848 46.293 47.814 46.200 47.675 49.429 51.000 09-JAN-11 10 41 00.0 46.399 47.867 45.901 46.971 46.574 48.079 46.377 47.856 49.665 51.245 09-JAN-11 10 42 00.0 46.530 47.995 46.127 47.144 46.678 48.163 46.537 48.003 49.768 51.317 09-JAN-11 10 43 00.0 47.008 48.337 46.481 47.375 47.117 48.463 46.796 48.146 50.271 51.688 09-JAN-11 10 44 00.0 47.263 48.503 46.958 47.756 47.502 48.758 47.258 48.500 so. 545 51.801 09-JAN-11 10 45 00.0 47.724 48.813 47.095 47.774 47.611 48.734 4 7.468 48.577 50.838 52.071 09-JAN-11 10 46 00.0 48.042 48.995 4 7. 412 47.973 48.051 49.045 47.732 48.716 51.378 52.391 09-JAN-11 10 47 00.0 48.200 49.054 47.554 48.014 48.183 49.048 47.853 48.721 51.454 52.407 09-JAN-11 10 48 00.0 48.175 49.038 47.603 48.050 48.170 49.050 48.088 48.968 51.364 52.282

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' 09-JAN-11 10 49 00.0 48.064 48.923 47.466 47.913 48.136 49.022 4.7~89~ 48.7BS S1.AB s2. :ns 09-JAN-11 10 SO 00.0 48.144 49.008 47.521 47.984 48.167 49.045 47.963 48.827 51.373 52.319 • 09-JAN-11 10 51 00.0 48.157 49.032 47.521 47.994 48.093 48.998 47.944 48.837 51.426 52.385 09-JAN-11 10 52 00.0 47.942 48.827 47.325 47.806 48.067 48.949 47.865 48.731 51.309 52.244 09-JAN-11 10 53 00.0 48.139 49.008 47.500 47.966 48.237 49.136 47.995 48.875 51.460 52.418 09-JAN-11 10 54 00.0 48.135 49.013 4 7.441 47.920 48.125 49.021 47.963 48.851 51.466 52.407 09-JAN-11 10 55 00.0 48.144 49.024 47.506 47.978 48.133 49.037 47.888 48. 7T7 51.393 52.351 09-JAN-11 10 56 00.0 48.122 48.989 47.627 48.069 48.181 49.054 47.905 48.758 51.365 52.298 09-JAN-11 10 57 00.0 48.175 49.024 47.540 48.003 48.131 49.024 47.989 48.854 51.457 52.364 09-JAN-11 10 58 00.0 48.128 48.998 47.595 48.051 48.204 49.080 48.107 48.979 51.433 52.357 09-JAN-11 10 59 00.0 48.192 49.045 47.559 48.003 48.090 48.971 47.904 48.760 51.364 52.293 09-JAN-11 11 00 00.0 48.192 49.045 47.559 48.003 48.090 48.971 47.904 48.760 51.364 52.293

DATE/TIME *R0004X* *R0004Y* * % PWR* * % PWR*

09-JAN-11 08 15 00.0 50.806 46.772 09-JAN-11 08 16 00.0 51.095 46.976 09-JAN-11 08 17 00.0 51.000 46.853 09-JAN-11 08 18 00.0 50.944 46.869 09-JAN-11 08 19 00.0 51.085 46.984 09-JAN-11 08 20 00.0 51.056 46.963 09-JAN-11 08 21 00.0 50.974 46.997 09-JAN-11 08 22 00.0 51.103 47.006 09-JAN-11 08 23 00.0 51.030 46.950 09-JAN-11 08 24 00.0 so. 926 46.873 09-JAN-11 08 25 00.0 51.136 46.936 09-JAN-11 08 26 00.0 50.838 46.790 09-JAN-11 08 27 00.0 51.079 46.986 09-JAN-11 08 28 00.0 51.141 47.037 09-JAN-11 08 29 00.0 50.965 46.888 09-JAN-11 08 3D oo.o so. 973 46.875 09-JAN-11 08 31 00.0 50.960 46.968 09-JAN-11 08 32 00.0 50.950 46.973 09-JAN-11 08 33 00.0 51.181 4 7.120 09-JAN-11 08 34 00.0 51.071 47.131 09-JAN-11 08 35 00.0 51.082 47.210 09-JAN-11 08 36 00.0 so. 636 46.952 09-JAN-11 08 37 00.0 50.537 46.976 09-JAN-11 08 38 00.0 50.803 47.274 09-JAN-11 08 39 00.0 50.343 47.024 09-JAN-11 08 40 00.0 50.452 47.119 09-JAN-11 08 41 00.0 50.370 47.083 09-JAN-11 08 42 00.0 50.204 46.987 09-JAN-11 08 43 00.0 50.077 47.003 09-JAN-11 08 44 00.0 so. 043 46.955 09-JAN-11 08 45 00.0 50.006 46.707 09-JAN-11 08 46 00.0 49.821 46.686 09-JAN-11 08 47 00.0 50.101 46.795 09-JAN-11 08 48 00.0 49.883 46.516 09-JAN-11 08 49 00.0 49.867 46.561 09-JAN-11 08 50 00.0 50.075 46.675 09-JAN-11 08 51 00.0 50.204 46.774 09-JAN-11 08 52 00.0 49.990 46.615 09-JAN-11 08 53 00.0 49.987 46.630 09-JAN-11 08 54 00.0 49.878 46.524 09-JAN-11 08 55 00.0 so .122 46.726 09-JAN-11 08 56 00.0 49.934 46.659 09-JAN-11 08 57 00.0 50.163 46.806 09-JAN-11 08 58 00.0 49.957 46.625 09-JAN-11 08 59 00.0 50.090 46.734 09-JAN-11 09 00 00.0 50.088 46.?29 09-JAN-11 09 01 00.0 so. 045 46.800

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' 09-JAN-11 09 02 00.0 50.063 46.946 09-JAN-11 09 03 00.0 50.061 47.005 09-JAN-11 09 04 00.0 50.133 47.077 • 09-JAN-11 09 OS 00.0 50.207 47.210 09-JAN-11 09 06 00.0 50.346 47.232 09-JAN-11 09 07 00.0 50.397 47.232 09-JAN-11 09 08 00.0 50.540 47.256 09-JAN-11 09 09 00.0 50.569 47.285 09-JAN-11 09 10 00.0 50.282 46.986 09-JAN-11 09 11 00.0 50.405 47.160 09-JAN-11 09 12 00.0 50.571 47.095 09-JAN-11 09 13 00.0 50.662 47.048 09-JAN-11 09 14 00.0 50.813 47.046 09-JAN-11 09 15 00.0 50.718 46.905 09-JAN-11 09 16 00.0 50.840 4 7. 054 09-JAN-11 09 17 00.0 51.030 47.091 09-JAN-11 09 18 00.0 50.893 4 7. 002 09-JAN-11 09 19 00.0 50.904 47.035 09-JAN-11 09 20 00.0 51.130 47.075 09-JAN-11 09 21 00.0 50.934 47.032 09-JAN-11 09 22 00.0 51.111 47.160 09-JAN-11 09 23 00.0 50.979 47.063 09-JAN-11 09 24 00.0 50.986 4 7. 043 09-JAN-11 09 25 00.0 50.925 47.096 09-JAN-11 09 26 00.0 50.920 46.994 09-JAN-11 09 27 00.0 51.080 4 7.125 09-JAN-11 09 28 00.0 50.949 47.176 09-JAN-11 09 29 00.0 50.795 47.032 09-JAN-11 09 30 00.0 50.772 4 7. 216 09-JAN-11 09 31 00.0 50.678 47.191 09-JAN-11 09 32 00.0 50.604 47.229 09-JAN-11 09 33 00.0 50.348 47.208 09-JAN-11 09 34 00.0 50.152 47.043 09-JAN-11 09 35 00.0 50.103 47.051 09-JAN-11 09 36 00.0 50.074 47.037 09-JAN-11 09 37 00.0 50.199 47.171 09-JAN-11 09 38 00.0 49.833 46.753 09-JAN-11 09 39 00.0 49.954 46.880 09-JAN-11 09 40 00.0 49.909 46.806 09-JAN-11 09 41 00.0 49.885 46.750 09-JAN-11 09 42 00.0 49.938 46.829 09-JAN-11 09 43 00.0 49.920 46.750 09-JAN-11 09 44 00.0 49.893 46.686 09-JAN-11 09 45 00.0 50.117 46.875 09-JAN-11 09 46 00.0 50.127 46.896 09-JAN-11 09 47 00.0 50.038 46.756 09-JAN-11 09 48 00.0 49.913 46.704 09-JAN-11 09 49 00.0 49.994 46.766 09-JAN-11 09 50 00.0 50.095 46.798 09-JAN-11 09 51 00.0 49.957 46.745 09-JAN-11 09 52 00.0 49.837 46.667 09-JAN-11 09 53 00.0 49.728 46.585 09-JAN-11 09 54 00.0 50.013 46.814 09-JAN-11 09 55 00.0 49.962 46.761 09-JAN-11 09 56 00.0 49.992 46.976 09-JAN-11 09 57 00.0 49.795 46.838 09-JAN-11 09 58 00.0 50.021 47.071 09-JAN-11 09 59 00.0 49.899 47.003 09-JAN-11 10 00 00.0 50.035 47.149 09-JAN-11 10 01 00.0 50.114 47.106 09-JAN-11 10 02 00.0 49.933 47.013 09-JAN-11 10 03 ao.o 50.112 47.152

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09-JAN-11 10 04 00.0 S0.280 47.280 09-JAN-11 10 OS 00.0 S0.324 47.168 09-JAN-11 10 06 00.0 so. 691 47.361 09-JAN-11 10 07 00.0 SO.S43 47.151 09-JAN-11 10 08 00.0 50.729 47.162 09-JAN-11 10 09 00.0 50.848 47.205 09-JAN-11 10 10 00.0 Sl.162 47.397 09-JAN-11 10 11 00.0 51.027 47.264 09-JAN-11 10 12 00.0 51.074 47.295 09-JAN-11 10 13 00.0 51.013 47.1S9 09-JAN-11 10 14 00.0 51.071 47.300 09-JAN-11 10 15 00.0 S0.990 47.176 09-JAN-11 10 16 00.0 S0.827 47.08S 09-JAN-11 10 17 00.0 50.877 47.109 09-JAN-11 10 18 00.0 51.016 47.244 09-JAN-11 10 19 00.0 50.864 47.101 09-JAN-11 10 20 00.0 S0.986 47.199 09-JAN-11 10 21 00.0 51.123 47.301 09-JAN-11 10 22 00.0 51.046 47.266 09-JAN-11 10 23 00.0 50.944 47.165 09-JAN-11 10 24 00.0 50.771 47.045 09-JAN-11 10 25 00.0 50.109 46.729 09-JAN-11 10 26 00.0 49.899 46.689 09-JAN-11 10 27 00.0 49.49S 46.32S 09-JAN-11 10 28 00.0 49.405 46.192 09-JAN-11 10 29 00.0 48.933 45.933 09-JAN-11 10 30 00.0 48.851 45.966 09-JAN-11 10 31 00.0 48.984 45.995 09-JAN-11 10 32 00.0 49.024 46.03S 09-JAN-11 10 33 00.0 48.875 45.905 09-JAN-11 10 34 00.0 48.928 .45.928 09-JAN-11 10 35 00.0 48.688 45.744 09-JAN-11 10 36 00.0 48.811 45.861 09-JAN-11 10 37 00.0 48.635 45.699 09-JAN-11 10 38 00.0 48.881 4S.936 09-JAN-11 10 39 00.0 48.899 45.891 09-JAN-11 10 40 00.0 48.745 45.745 09-JAN-11 10 41 00.0 48.931 45.981 09-JAN-11 10 42 00.0 49.115 46 .17S 09-JAN-11 10 43 00.0 49.476 46.285 09-JAN-11 10 44 00.0 49.921 46.S99 09-JAN-11 10 45 00.0 50.199 46.790 09-JAN-11 10 46 00.0 50.462 46.950 09-JAN-11 10 47 00.0 50.655 46.960 09-JAN-11 10 48 00.0 50.862 47.026 09-JAN-11 10 49 00.0 50.654 46.920 09-JAN-11 10 50 00.0 S0.683 46.869 09-JAN-11 10 51 00.0 50.699 46.971 09-JAN-11 10 52 00.0 50.500 46.801 09-JAN-11 10 53 00.0 SO.S9S 46.929 09-JAN-11 10 54 00.0 50.671 46.9S8 09-JAN-11 10 55 00.0 50.700 46.987 09-JAN-11 10 56 00.0 50.731 46.936 09-JAN-11 10 57 00.0 50.787 47.042 09-JAN-11 10 58 00.0 50.745 47.006 09-JAN-11 10 59 00.0 50.787 46.968 09-JAN-11 11 00 00.0 50.787 46.968

Page 165: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

RPS Circuit Breaker Replacement History

CB-AB

CB-CD

DATE BREAKER STYLE

DATE BREAKER STYLE

Initial 1972 Westinghouse Type JA Circuit Breaker Initial 1972

Westinghouse Type JA Circuit Breaker

11/1999

Westinghouse Type JA Circuit Breaker -- Replaced in-kind because reset handle was broken.

05/28/2002 Westinghouse Type JA Circuit Breaker replaced in-kind due to buzzing noise from the UV coil. (CR 200201777) It was noted that the new breaker was also making some noise.

09/2003 Westinghouse Type JA Circuit Breaker replaced with Cutler Hammer Type KDB Circuit Breaker because: 1. OPS said the breaker was noisy. 2. Unavailability of like-for- like spare breakers or parts.

05/03/2011 New Cutler Hammer Type KDB Circuit Breaker Installed. The removed C-H KDB breaker was sent to an offsite lab for testing.

05/04/2011 New Cutler Hammer Type KDB Circuit Breaker Installed. The removed Westinghouse JA breaker sent to an offsite lab for testing.

Page 166: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

6.0 RPS Circuit Breaker Testing & Maintenance History

(From the 1999 Refueling Outage to the Present)

DATE ACTIVITY CIRCUIT BREAKER WORK DOCUMENT RESULTS CB-AB CB-CD 10/11/99 Refueling test of

CB-AB & CB-CD X X WO 18428

EM-RR-RPS-0200 Breakers tested SAT per EM procedure, but CB-CD handle was broken during performance of OP-ST-RPS-0008.

11/08/99 Replace CB-CD due

to broken operating handle.

X

WO 43493 EM-RR-RPS-0200

CB-CD replaced, Westinghouse for Westinghouse, per EM-RR-RPS-0200. PMT per OP-ST-RPS-0008 on 11/10/99.

03/27/01 Refueling test of CB-AB & CB-CD X X WO 59032

EM-RR-RPS-0200 Breakers tested SAT per EM procedure and PMT per OP-ST-RPS-0008.

05/10/02 Refueling test of CB-AB & CB-CD X X WO 100158

EM-RR-RPS-0200 Breakers tested SAT per EM procedure and PMT per OP-ST-RPS-0008.

05/28/02 Westinghouse Type JA Circuit Breaker replaced in-kind due to buzzing noise from the UV coil.

X

WO 117427 CR 200201777

When the trip coil was de-energized to open the breaker, the buzzing stopped.(1)

CB-AB replaced in-kind per EM-RR-RPS-0200 and tested SAT per PMT OP-ST-RPS-0008.

09/20/03 Westinghouse Type JA Circuit Breaker Replaced. X

WO 119963 EC 30208

CB-AB replaced. Westinghouse Type JA breaker replaced with Cutler Hammer Type KDB breaker per EM-RR-RPS-0200. Tested SAT on 10/26/03.

09/20/03 Refueling test of CB-CD.

X WO 125339

CB-CD tested SAT per EM-RR-RPS-0200. CB-AB & CB-CD tested SAT per PMT OP-ST-RPS-0008 on 10/26/03.

03/10/05 Refueling test of X X WO 158157 Breakers tested SAT per EM procedure and PMT

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CB-AB & CB-CD per OP-ST-RPS-0008 (05/27/05). 10/16/06 Refueling test of

CB-AB & CB-CD X X WO 202323 Breakers tested SAT per EM procedure and PMT per OP-ST-RPS-0008.

DATE ACTIVITY CIRCUIT BREAKER CB-AB CB-CD WORK DOCUMENT RESULTS

10/17/06 Lug fell off the closing coil.

X WR 99968 WO 251422

Re-lug closing coil wire for CB-CD per EWP-8.

05/21/08 Refueling test of CB-AB & CB-CD X X WO 262124 Breakers tested SAT per EM procedure and PMT

per OP-ST-RPS-0008 (06/15/08). 11/08/09 Refueling test of

CB-AB & CB-CD

X X WO 304754

Tested CB-AB & CB-CD per EM-RR-RPS-0200. • CB-AB tripped low at 1450 amps. Wrote

WR 143122 and CR 2009-5489. • CB-CD tripped low at 1482 amps. Wrote

WR 143128 and CR 2009-5495.

11/22/09 Reinstalled CB-AB per EM-RR-RPS-0200.

X WO 358354

CR 2009-5489

CB-AB accepted as-is per EC 47932. Breaker PMT’d SAT per OP-ST-RPS-0008 on 12/15/09.

11/22/09 Reinstalled CB-CD per EM-RR-RPS-0200.

X

WO 358756 CR 2009-5495

CB-CD accepted as-is per EC 47932. Breaker PMT’d SAT per OP-ST-RPS-0008 on 12/15/09.

04/23/11 Refueling test of CB-AB & CB-CD

X X WO 360697

Per EM-RR-RPS-0200, • Removed and bench tested the installed CB-AB

Cutler Hammer Type KDB breaker prior to being sent off for lab testing.

• Removed and bench tested the installed CB-CD Westinghouse Type JA breaker prior to being sent off for lab testing.

Both breakers tested SAT. 05/03/11 Installed new Cutler X WO 411857 New breaker installed per EM-RR-RPS-0200.

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Hammer Type KDB breaker

Awaiting PMT per OP-ST-RPS-0008.

05/04/11 Installed new Cutler Hammer Type KDB

breaker

X WO 411859

New breaker installed per EM-RR-RPS-0200. Awaiting PMT per OP-ST-RPS-0008.

05/25/11 Offsite lab testing X X ESI Project 34702M Failure Analysis Report issued 05/26/11.

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RPS M Contactor Testing & Maintenance History

Timeline includes Surveillance Tests and Maintenance affecting M Contactors (Timeline prior to 2008 is not all inclusive)

Date Event M

Contactor Condition

Report Work Document

Supporting Documentation

Resolution

12/07/87 While performing ST-RPS-11, M-3 contactor was found buzzing.

M-3 Related IR 890370

Maintenance Work Order 875595

*ST-RPS-11 *MP-RPS-M- Contactor per PM 8809465

Shading coil was adjusted. Paperwork does not give details on how.

03/23/96 Observation at the Reactor Vessel Head: One or more of the CEDM drive packages was making an intermittent “clicking” noise.

199600356 During the time this observation occurred, I&C was performing IC-ST-RPS-0042. It was not believed that this test was related to the clicking. Prior to criticality, OP-ST-CEA-0005 was performed; there was no evidence of a clutch coil or motor brake anomaly. Following the plant trip on 03/29/96, test IC-ST-RPS-0042 was performed again; no anomalies were noted.

05/05/06 Forced Outage Surveillance Test

M-1, M-2 M-3, M-4 WO 233584-01 OP-ST-RPS-0008 ST completed SAT.

02/28/08 Quarterly Surveillance M-1, M-2 WO 288669-01 IC-ST-RPS-0042 ST completed SAT.

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Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

Test. M-3, M-4 03/21/08 Post Trip – Pre Startup

Surveillance Test M-1, M-2 M-3, M-4

CR 2008-1848 WO 298811-01 OP-ST-RPS-0008 Test failed – unrelated to M Contactors. Refer to CR

03/21/08 Pre Startup Surveillance Test

M-1, M-2 M-3, M-4 WO-297315-01 OP-ST-RPS-0008 ST performed SAT.

05/22/08 Refueling M Contactor Maint.

M-1, M-2 M-3, M-4 WO 261848-01 EM-RR-RPS-0201 Procedure completed SAT.

06/12/08 Quarterly Surveillance Test M-1, M-2

M-3, M-4

WO 306666-01 IC-ST-RPS-0042 ST Completed SAT. Also served as PMT for WO 261848-01 and EM-RR-RPS-0201.

06/15/08 Refueling Surveillance Test.

M-1, M-2 M-3, M-4 WO 266582-01

OP-ST-RPS-0008

ST completed SAT.

06/15/08 Refueling Surveillance Test

M-1, M-2 M-3, M-4 OP-ST-CEA-0005 ST completed SAT.

08/13/08 Quarterly Surveillance Test.

M-1, M-2 M-3, M-4 WO 304528-01 IC-ST-RPS-0042 ST completed SAT.

11/03/08 While performing IC-ST-RPS-0042, M2 contactor began chattering

M-2 2008-6624 WR 00128955 WO 321729-01

IC-ST-RPS-0042 WO 321729-01 EM-RR-RPS-0201 WO 321729-02 EC 44745 See photos

Found that the shading coil had become loose and was laying across the coil so the coil could not make up all the way. Both shading coils loose & out of place. Signs of wear indicated on coil. Excessive dust found in bottom of contactor housing.

Page 171: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

2008-6624-01 thru 2008-6624-07

PRC Degraded Nonconforming Condition Subcommittee determined the event is not a degraded or nonconforming condition. Re-installed shading coils ensuring tight fit per WO 321729-01. Coil was replaced with new like for like part. PMT per IC-ST-RPS-0042 completed SAT 11/6/08. System Engineer recommended all 4 contactors be replaced due to age. EC 44745 initiated. WO 321729-02 initiated to replace Contactor M-2.

11/06/08 PMT -- WO 321729-01 & Quarterly ST

M-1, M-2 M-3, M-4

WO 313130-01 IC-ST-RPS-0042 ST completed SAT.

01/27/09 Quarterly Surveillance Test.

M-1, M-2 M-3, M-4 WO 321948-01 IC-ST-RPS-0042 ST completed SAT.

04/21/09 Quarterly Surveillance Test.

M-1, M-2 M-3, M-4 WO 329865-01 IC-ST-RPS-0042 ST completed SAT.

07/14/09 Quarterly Surveillance Test.

M-1, M-2 M-3, M-4 WO 333060-01 IC-ST-RPS-0042 ST completed SAT.

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Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

10/05/09 Quarterly Surveillance Test.

M-1, M-2 M-3, M-4 WO 337448-01 IC-ST-RPS-0042 ST completed SAT.

12/15/09 Quarterly/Refueling Surveillance Test

M-1, M-2 M-3, M-4 WO 315712-01

WO 344728-01 IC-ST-RPS-0042 ST completed SAT.

12/15/09 Refueling Surveillance Test.

M-1, M-2 M-3, M-4 WO 298814-01

WO 305260-01 OP-ST-RPS-0008 EM-RR-RPS-0201

ST completed SAT.

12/17/09 Refueling Surveillance Test.

M-1, M-2 M-3, M-4 WO 298549-01 OP-ST-CEA-0005 ST completed SAT.

02/28/10 Quarterly Surveillance Test. M-1, M-2

M-3, M-4 WO 369702-01 IC-ST-RPS-0042 ST completed SAT.

Also served as the PMT for WO 369243-01.

03/20/10 Buzzing/chattering heard from panel AI-3, noise changed in pitch and volume.

M-2 2010-1378 WR 00148645

CR 2008-6624 Condition Level D and close. Condition will be tracked by WR 00148645. CR closed 03/24/10.

03/25/10 During quarterly IC-ST-RPS-0042, the noise coming from AI-3 became louder. Noise increased when M-2 was energized. The ST was stopped. Also found the cover for M-1 contactor had fallen off.

M-2 2010-1460 WO 353272-01 (quarterly ST)

IC-ST-RPS-0042 Apparent Cause Analysis Summary Report dated 5/6/10: Abnormal Noise in AI-3 Panel.

M-2 Contactor started making a very loud vibration. Stopped ST and backed out of procedure. This is the 2nd time this shading coil has come loose. See previous CR 2008-6624. CR states past OE shows that coils & contacts can operate for extended periods making noise. M-2 coil would trip and provide

Page 173: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

protection as designed. 03/31/10 M-2 coil/contactor

repaired per EM-RR-RPS-0201. PMT per IC-ST-RPS-0042.

M-2

WO 372893-01 WO 373453-01 (quarterly ST) WO 372893-02 (cancelled)

See photos 2010-1460-01 thru 2010-1460-06

M contactor as found was very loud. Found shading coils dislodged and creating closure interference. Per WO and EM-RR-RPS-0201, cleaned contactor and snapped shading coils back into position. Cycled contactor 6 times on 3/31/10 per IC-ST-RPS-0042. After the ST, the offensive noise from M-2 was not as pronounced. Vibration reduced but not eliminated.

04/01/10 No spare parts for CQE equipment, i.e., M-1, M-2, M-3, M-4 contactors

M-1 M-2 M-3 M-4

2010-1586

SRI EC 44745

EC being designed on an emergent basis to identify replacement components. Tentatively scheduled for 2011 refueling.

04/02/10 Post Maintenance Test M-2 WO 372893-01 PMT completed per IC-ST-RPS-0042

04/08/10 Forced Outage to replace MCC-3A1 degraded cable.

Reference CR 2010-3724.

M Contactors were not inspected due to a lack of resources.

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Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

04/10/10 During plant startup, while performing OP-ST-RPS-0008, M-2 contactor started making noise again in panel AI-3.

M-2 2010-1738 WO 301892 WR 149645 -> WO 374724 -> (cancelled to WO 321729-02) WR 149661 (cancelled)

OP-ST-RPS-0008 Deduced that the shading coil was loose again. This is the 3rd time a shading coil has come loose on M2. Operability basis again assumed that M-2 would trip and function as designed. Shading coil was scheduled to be re-installed on 08/09/10.

04/11/10 Plant Startup Surveillance Test

M-1, M-2 M-3, M-4

OP-ST-CEA-0005 ST completed SAT.

NOTE 64 days ---- April 10 to June 14 M-2

Contactor M-2 apparently in a degraded state and making noise.

06/14/10 M-2 Contactor failed to open during quarterly IC-ST-RPS-0042.

M-2

2010-2923

WO 362334-01

IC-ST-RPS-0042 See photos 2010-2923-01 and 2010-2923-02

Part of one of the shading coils wedged in the mechanism preventing the contactor from dropping out. Apparent Cause Analysis performed & issued 7/29/10.

06/15/10 Disassembled and M-2 WO 381020-01 EM-RR-RPS-0201 Due to the as-found

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Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

inspected M-2 Contactor. Shading coils found broken & dislodged. Contactor is not repairable.

condition of contactor, backed out of this work package. Repairs will be performed per WO 381209-01.

06/17/10 Repaired contactor. M-2 WO 381209-01 Specified sections - EM-RR-RPS-0201

Contactor was repaired 6/17/10 using parts from Palisades. Replaced yoke & armature assembly, coil, spare aux contact, and coil cover.

06/17/10 Attempted to run IC-ST-RPS-0042 to satisfy quarterly test and PMT following repair of M-2 Contactor.

M-1, M-2, M-3,

M-4

CR 2010-2991 WO 381209-01 IC-ST-RPS-0042 IC-ST-RPS-0042 performed UNSAT on 06/17/10 due to out of spec output current from the RPS Clutch Power Supplies.

06/23/10 Retest performed – IC-ST-RPS-0042.

M-1, M-2, M-3,

M-4

IC-ST-RPS-0042 Procedure Change EC-49634.

ST performed SAT on 06/23/10.

09/07/10 Quarterly Surveillance Test

M-1, M-2, M-3,

M-4

WO 369965-01 IC-ST-RPS-0042 ST completed SAT.

11/29/10 Quarterly Surveillance Test

M-1, M-2,

WO 379203-01 IC-ST-RPS-0042 ST completed SAT.

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Date Event M Contactor

Condition Report

Work Document

Supporting Documentation

Resolution

M-3, M-4

12/25/10 Forced Outage Surveillance Test

M-1, M-2, M-3,

M-4

WO 375835 OP-ST-RPS-0008 ST completed SAT.

12/25/10 Forced Outage Surveillance Test

M-1, M-2, M-3,

M-4

WO 375827 OP-ST-CEA-0005 ST completed SAT.

02/04/11 Quarterly Surveillance Test

M-1, M-2, M-3,

M-4

WO 388315-01 IC-ST-RPS-0042 ST completed SAT.

02/05/11 All 4 M Contactors replaced during weekend mini-outage.

M-1, M-2, M-3,

M-4

WO 324289-01 WO 321729-02 WO 324290-01 WO 324291-01

EC 44745 EM-RR-RPS-0201

All 4 M Contactors replaced during weekend mini-outage.

02/05/11 Quarterly Surveillance Test

M-1, M-2, M-3,

M-4

IC-ST-RPS-0042 ST completed SAT. M Contactors dropped out and picked up with no abnormal sounds.

02/05/11 Prior to Startup Surveillance Test

M-1,M-2, M-3, M-4

OP-ST-RPS-0008 ST completed SAT.

Page 177: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

Date Event M

Contactor Condition

Report Work Document

Supporting Documentation

Resolution

04/09/11 Refueling PM on M Contactors per

EM-RR-RPS-0201

M-1,M-2, M-3, M-4

WO 361210-01 FC-1066 Track # 3676

Performance of procedure during the 2011 refueling outage deferred to the 2012 refueling outage because all 4 M contactors were replaced during mini-outage on 2/5/11.

05/20/11 The M Contactor capacitors have been installed beyond their

EPRI recommended life

CR 2011-4746

Replacement recommended during the 2011 refueling outage.

Page 178: NUCLEAR TRAINING INTRODUCTION TO EMERGENCY …INTRODUCTION TO EMERGENCY OPERATING PROCEDURES . AND . STANDARD POST TRIP ACTIONS . EOP-00 . INSTRUCTOR HANDBOOK . LESSON PLAN: 7-18-10

OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION

LICENSED OPERATOR TRAINING PROGRAM

TITLE: REACTOR TRIP WITH EMERGENCY BORATION

SIMULATOR SCENARIO GUIDE: 08-12-19 REVISION: 8

DATE: 11/06/10 TRAINEES AND INSTRUCTIONAL STAFF: Shift Manager (SM):

Control Room Supervisor (CRS):

At the Controls Operator (ATCO):

Balance of Plant Operator (BOPO):

Shift Technical Advisor (STA):

Additional Operator (RO/SRO/STA):

Simulator Instructor:

Simulator Operator:

Additional Instructor/Observer:

Date of Training: _______________________________

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FCS SSG-08-12-19 Rev 8

Page 2 of 14

TRAINING OBJECTIVES

# OBJECTIVE

K/A MTL

1.0 The CRS will provide appropriate and timely directions to Control Room personnel.

000000 2.1.09

0064

2.0 The CRS/ATCO/BOPO will complete required shift logs and records.

000000 2.1.18

0050

3.0 The CRS/ATCO/BOPO will provide appropriate and timely directions to personnel outside of the Control Room.

000000 2.1.08

0077

4.0 The CRS/ATCO will respond to a letdown flow instrument failure.

004000 A2.21

4.1 The ATCO will restore letdown flow.

004000 A2.21

0119

5.0 The CRS/ATCO/BOPO will respond to an ATWS.

000021 EK3.12

0011

5.1 The ATCO/BOPO will manually trip the reactor.

000021 EK3.11

0011

5.2 The CRS will enter EOP-00 following a Reactor Trip.

000000 2.4.04

0006

5.3 The ATCO will ensure Reactivity Control following a reactor trip.

000007 EA1.06

0006

5.4 The ATCO will perform an Emergency Boration

0008

5.5 The BOPO will ensure turbine and generator trip following a reactor trip.

000007 EA1.07

0006

5.6 The BOPO will verify electrical system status following a reactor trip.

000007 EK3.01

0006

5.7 The BOPO will verify Instrument Air status following a reactor trip.

000007 EK3.01

0006

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FCS SSG-08-12-19 Rev 8

Page 3 of 14

5.8 The ATCO will verify CCW and RW status following a reactor trip.

000007 EK3.01

0006

5.9 The ATCO will verify RCS Inventory Control status following a reactor trip.

000007 EK3.01

0006

5.10 The ATCO will verify RCS Pressure Control status following a reactor trip.

000007 EA1.03

0006

5.11 The ATCO/BOPO will ensure Heat Removal Status following a Reactor Trip.

000007 EA1.02 EA1.04

0006

5.12 The ATCO will verify Containment Status following a Reactor Trip.

000007 EK3.01

0006

5.13 The CRS will perform EOP-00 diagnostic actions and transition to the correct procedure.

000000 2.4.04

0006

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FCS SSG-08-12-19 Rev 8

Page 4 of 14

NARRATIVE SUMMARY

1. Letdown Flow Transmitter Fails high. Letdown isolates.

2. Main Feedwater Regulating Valve, FCV-1102, fails closed. The level in Steam Generator RC-2B lowers to the trip setpoint but the automatic trip does not occur.

3. The operators manually trip the reactor. Several CEAs fail to insert. Emergency

Boration is required. PRE-SIMULATOR CLASSROOM SESSION It is recommended that lesson plan 07-17-03 be scheduled for the classroom session prior to teaching this SSG. (Even though the emergency boration will be conducted using EOP-00) INITIAL CONDITIONS The plant is operating at 100% power. Preset malfunctions should be setup for ATWS. (See Attachment 1) SCENARIO DURATION This scenario is expected to take approximately 1 hour.

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FCS SSG-08-12-19 Rev 8

Notes and Comments

Page 5 of 14

SCENARIO PRESENTATION: Instructor Cover Objectives with students.

___

Instructor Discuss Simulator Fidelity Issues.

___

Instructor Conduct a brief turnover to the crew

___

Scenario Begins:

CRS/ATCO/BOPO Walk down the control boards review the shift turnover

sheet.

___

CRS Conduct a pre-shift Briefing

___

EVENT ONE: Letdown Flow Transmitter Fails High.

Type Filter Item Value Ramp Delay transmitters cvc CVC_FT212 Full scale 20 sec N/A

CRS/ATCO Responds to “Letdown High Flow” and “Intermediate Letdown Press HI-LO” alarms Acknowledges alarms

___

ATCO/BOPO Reviews ARP-CB-1,2,3/A2 B1L and A1L for appropriate actions

___

ATCO Ensures HCV-204 has automatically closed. Close TCV-202

___

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FCS SSG-08-12-19 Rev 8

Notes and Comments

Page 6 of 14

ATCO Determines that Flow instrument FI-212 has failed high

___

ATCO If XC-105 10 minute average power computer alarm comes in, verify NI and delta-T power.

___

CRS Directs ATCO to override flow interlock and restore letdown flow

___

ATCO Place HC-204-1 “High Flow interlock Override switch” in DEFEAT

___

ATCO Place HC-101-3, Limiter Bypass switch, in BYPASS

___

ATCO Place HIC-101-1/101-2 in MANUAL

___

ATCO Close LCV-101-1 and/or LCV-101-2

___

ATCO Place PIC-210 in Manual and throttle to 10% open

___

ATCO Open HCV-204 and TCV-202

___

ATCO Initiate letdown flow using HIC-101-1/101-2 while adjusting PCV-210 to maintain letdown pressure approximately 300 psig. Balance charging and letdown flows.

___

ATCO Place HC-101-3 in NORMAL

___

ATCO Place HIC-101-1/101-2 and PIC-210 in AUTO

___

CRS Notify Work Week Manager of failure with FI-212

___

ATCO Monitor charging and letdown for proper operation

___

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FCS SSG-08-12-19 Rev 8

Notes and Comments

Page 7 of 14

EVENT TWO: FCV-1102 Fails Closed, ATWS Type Filter Item Value Ramp Delay valves fwc fwc_fcv1102 0 30 sec N/A BOPO Identifies lowering S/G level, flow and FCV-1102 position.

___

CRS>BOPO Attempts to take manual control of FCV-1102

___

CRS/BOPO Determines that S/G low level trip setpoint is reached with no trip.

___

CRS Direct Operators to manually trip the reactor, enter EOP-00 and perform standard post-trip actions

___

ATCO Manually attempts to trip the reactor. Determines it did not trip.

___

ATCO/BOPO Manually attempts to trip reactor at RPS panels.

___

ATCO/BOPO Trips reactor using DSS switches.

___

ATCO Verify Reactivity Control: • Power lowering • SUR negative • Determines that several CEA’s have not inserted • Monitor for cooldown.

___ ___ ___ ___

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FCS SSG-08-12-19 Rev 8

Notes and Comments

Page 8 of 14

BOPO Performs Emergency Boration: • Ensures FCV-269X/Y are both closed • Opens HCV-268 • Opens HCV-265 • Opens HCV-258 • Starts both boric acid Pumps, CH-4A/B • Starts all charging pumps, CH-1A/B/C • Closes LCV-218-2 • Ensures LCV-218-3 is closed • Ensures HCV-257 is closed • Ensures HCV-264 is closed.

___ ___ ___ ___ ___ ___ ___ ___ ___ ___

BOPO Ensure turbine tripped: • Stop and Intercept valves closed.

___

BOPO Ensure Generator Breakers Tripped: • Breaker 3451-4 • Breaker 3451-5 • Generator Field Breaker

___ ___ ___

BOPO Ensure Electrical Power: • Vital busses 1A3 and 1A4 energized. • Non-vital busses 1A1 and 1A2 energized. • Both 125 volt DC busses energized.

___ ___ ___

BOPO Verify Instrument Air Status: • Instrument Air Pressure > 90 psig • At least one air compressor running.

___ ___

ATCO Verify CCW status:

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• At least one CCW pump running. • CCW pump discharge pressure > 60 psig. • At least one RW pump running. • HCV-438A/B/C/D open if CCW discharge pressure > 40

psig.

___ ___ ___ ___

ATCO Verify RCS Inventory Control: • PZR Level 30-70% trending toward 45-60% • Subcooling > 20°F

___ ___

ATCO Verify RCS Pressure Control: • RCS Pressure 1800-2300 psia trending toward 2050-

2150 psia. • PORVs closed.

___ ___

ATCO Verify Core Heat Removal: • RCP NPSH adequate per attachment 2. • At least one RCP running. • Core ΔT < 10°F.

___ ___ ___

BOPO Ensure Main Feedwater is restoring level in at least one steam generator:

• Both feed reg valves ramped closed. • Both feed reg bypass valves ramped to 40-45%. • No more than 1 main FW Pump running. • No more than 1 Condensate Pump running. • No heater drain pumps running. • 43/FW switch in “OFF” • Blowdown isolated.

___ ___ ___ ___ ___ ___ ___

BOPO Verify Steam Dump and bypass valves are controlling:

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• T-cold 525-535°F. • S/G pressure 850-925 psia.

___ ___

ATCO Verify containment conditions: • No unexpected rise in sump level. • No containment are radiation monitor alarms. • No alarms on RM-051, RM-052 or RM-062. • No alarms on RM-054A, RM-054B or RM-057. • No upward trends on RM-054A, RM-054B or RM-057. • Containment pressure < 3psig • Containment temperature < 120°F

___ ___ ___ ___ ___ ___ ___

CRS Perform EOP-00 “Diagnostic Actions” and go to EOP-01.

___

Scenario Ends after transition to EOP-01 with emergency boration still in progress.

Deliberate Bypass of the RPS when draining S/G’s This scenario uses a failure of all four interposing relays to give us the ATWS condition. The plant is often deliberately placed in this condition when we drain steam generators in mode 4 or 5 to allow the CEDM clutch coils to remain energized with an RPS signal present. (OI-RPS-1, Attachment 2).

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Operator Fundamentals

It is important to ensure that the RPS is restored to normal before plant startup. This bypass is tracked as a temporary modification.

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POST-SCENARIO DISCUSSION (Can be conducted after the simulator session or during the next day’s classroom session)

Instructor Review scenario events and procedures used:

• Letdown Flow Transmitter Fails high. Letdown isolates.

• Main Feedwater Regulating Valve, FCV-1102, fails closed. The level in Steam Generator RC-2B lowers to the trip setpoint but the automatic trip does not occur.

• The operators manually trip the reactor. Several CEAs

fail to insert. Emergency Boration is required.

___

SM/CRS/Crew Conduct a critique of teamwork, use of procedures, technical performance and human performance fundamentals.

___

SM/CRS/Crew Review Improvement Items.

___

Instructor Discuss any flagged Operator Fundamentals or Operating Experience items that were not discussed during the simulator session.

___

Instructor Discuss issues observed during the simulator session that were not covered during the critique.

Instructor Additional Questions: Question: How would a loss of Bus 1A3 affect the ability to perform emergency boration from the control room? Answer: With no power to bus 1A3, emergency boration could not be performed from the control room. HCV-268 could not be opened preventing flow from the boric acid pumps. LCV-218-2 could not be closed, so VCT pressure would prevent gravity feed. (Note: LCV-218-3 would not have any power either) Question: How would this ATWS event be classified per the E-Plan? Answer: This ATWS event would be classified as an ALERT (SA2).

___

Instructor Review Objectives (Use Objective List)

___

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REFERENCES

EOP-00, “Standard Post Trip Actions”

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ATTACHMENT ONE – SIMULATOR OPERATOR INSTRUCTIONS INITIAL SETUP: Use a 100% power IC. ___

Setup ATWS Run Event File ATWAS_DSS_WORKS.evt Type Filter Item Value Ramp Delay malf crd rod_pwr_401_2 true none none malf crd rod_pwr_303_2 true none none malf crd rod_pwr_441_2 true none none Go to Run

___

Ensure Horns are Turned ON

___

EVENT ONE: Letdown Flow Transmitter Fails High.

Type Filter Item Value Ramp Delay transmitters cvc CVC_FT212 Full scale 20 sec N/A EVENT TWO: FCV-1102 Fails Closed, ATWS Type Filter Item Value Ramp Delay valves fwc fwc_fcv1102 0 30 sec N/A Scenario Ends after transition to EOP-01 with emergency boration still in progress.

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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION

LICENSED OPERATOR TRAINING PROGRAM

TITLE: REACTOR TRIP WITH FUNCTIONAL RECOVERY

SIMULATOR SCENARIO GUIDE: 08-13-16 REVISION: 10

DATE: 10/26/10 TRAINEES AND INSTRUCTIONAL STAFF: Shift Manager (SM):

Control Room Supervisor (CRS):

At the Controls Operator (ATCO):

Balance of Plant Operator (BOPO):

Shift Technical Advisor (STA):

Additional Operator (RO/SRO/STA):

Simulator Instructor:

Simulator Operator:

Additional Instructor/Observer:

Date of Training: _______________________________

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TRAINING OBJECTIVES

# OBJECTIVE

K/A MTL

1.0 The CRS will provide appropriate and timely directions to Control Room personnel.

000000 2.1.09

0064

2.0 The CRS/ATCO/BOPO will complete required shift logs and records.

000000 2.1.18

0050

3.0 The CRS/ATCO/BOPO will provide appropriate and timely directions to personnel outside of the Control Room.

000000 2.1.08

0077

4.0 The CRS/ATCO/BOPO will respond to a reactor trip.

000007 EK3.01

0006

4.1 The CRS will enter EOP-00

000000 2.4.04

0006

4.2 The ATCO will perform primary standard post trip actions.

000007 EK3.01

0006

4.3 The BOPO will perform secondary standard post trip actions.

000007 EK3.01

0006

4.4 The CRS will perform diagnostic actions and transition to the correct procedure.

000000 2.4.04

0006

5.0 The CRS/ATCO/BOPO will respond to a loss of the Reactivity Control Safety Function.

000029 EK3.12

0797

5.1 The CRS will enter EOP-20

000029 EK3.12

0797

5.2 The CRS/ATCO/BOPO will attempt to insert CEAs using EOP-20, RC-1

000029 EK3.10

1007

5.2 The CRS/ATCO/BOPO will attempt to initiate emergency boration using EOP-20, RC-2

000029 EK3.11

1007

5.3 The CRS/ATCO/BOPO will perform 480 Volt hot bus transfers

062000 A2.05

1087

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5.4 The CRS/ATCO/BOPO will initiate SI flow for reactivity control using EOP-20, RC-3

000029 EK3.11

1007

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NARRATIVE SUMMARY

1. The plant is operating at 100% power MOL. Equilibrium Xenon. Charging pump "A" out of service. FW-54 is 00S for maintenance.

2. A Loss of Offsite Power occurs. A Reactor Trip signal is generated on loss of flow, but numerous CEAs fail to insert.

3. DG-2 fails to start resulting in the loss of power to bus 1A4. Emergency Boration can not be performed because there is no power to any charging pumps..

4. Standard Post Trip Actions are completed and diagnosis indicates that the reactivity control safety function is not satisfied., transition to EOP-20.

5. Evaluation of Safety Functions leads to performance of RC-1 and RC-2. 6. Breaker BT-1B3B will not close preventing powering CH-1C. 7. Can power CH-1B by powering bus 1B4C from bus 1B3C via bus 1B3C-4C 8. Shortly after being started, CH-1B trips. 9. Crew then uses RC-3 by depressurizing RCS to allow HPSI injection 10. Scenario ends with reactivity control safety function being satisfied due to Safety

Injection or wide range power less than 1E-5%. PRE-SIMULATOR CLASSROOM SESSION It is recommended that lesson plan 07-18-18 be scheduled for the classroom session prior to teaching this SSG. INITIAL CONDITIONS The plant is operating at 100% power MOL. Equilibrium Xenon. Charging pump, CH-1A is out of service. FW-54 is 00S for maintenance. SCENARIO DURATION This scenario is expected to last approximately 2 hours.

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SCENARIO PRESENTATION: Instructor Cover Objectives with students.

___

Instructor Discuss Simulator Fidelity Issues.

___

Instructor Conduct a brief turnover to the crew: The plant is operating at 100% power MOL. Equilibrium Xenon. Charging pump, CH-1A is out of service. FW-54 is 00S for maintenance.

___

Scenario Begins:

CRS/ATCO/BOPO Walk down the control boards review the shift turnover

sheet.

___

CRS Conduct a pre-shift Briefing

___

Time = 5 minutes after pre-shift briefing EVENT ONE: Loss of Offsite Power ATWS Type Filter Item Value Ramp Delay malf swd swd02 true none none malf swd swd01 true none none

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CRS/ATCO/BOPO Recognize and report Reactor Trip

___

CRS Direct Operators to enter EOP-00 and perform standard post-trip actions

___

ATCO Verify Reactivity Control: • Power lowering • SUR negative • Multiple CEAs not inserted • Manual trip not successful • DSS trip not successful • CEDM clutch power supply breakers open • Can not emergency borate – no charging pumps • Monitor for cooldown.

___

BOPO Ensure turbine tripped: • Stop and Intercept valves closed.

___

BOPO Ensure Generator Breakers Tripped: • Breaker 3451-4 • Breaker 3451-5 • Generator Field Breaker

___

BOPO Ensure Electrical Power: • Only DG-1 started • Vital busses 1A3 energized and 1A4 de-energized. • Non-vital busses 1A1 and 1A2 de-energized. • Both 125 volt DC busses energized. • Direct EONT to minimize DC loads

___

BOPO Verify Instrument Air Status: • Instrument Air Pressure > 90 psig

___

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• At least one air compressor running.

ATCO Verify CCW status: • At least one CCW pump running. • CCW pump discharge pressure > 60 psig. • At least one RW pump running. • HCV-438A/B/C/D open if CCW discharge pressure

> 40 psig.

___

ATCO Verify RCS Inventory Control: • PZR Level 30-70% lowering trend. • Subcooling > 20°F

___

ATCO Verify RCS Pressure Control: • RCS Pressure 1800-2300 psia trending toward 2050-

2150 psia. • PORVs closed.

___

ATCO Verify Core Heat Removal: • No RCPs running • Monitor for development of natural circulation.

___

BOPO Initiate FW flow to S/G’s • All main FW pumps tripped. • All condensate pumps tripped. • No Heater Drain Pumps running. • 43/FW switch in “OFF” • Isolate blowdown • Establish AFW flow using FW-6 or FW-10

___

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BOPO Steam dump and bypass valves not available • Control S/G pressure 850-925 psia. Using HCV-1040

or MS-291 and MS-292

___

ATCO Verify containment conditions: • No unexpected rise in sump level. • No containment are radiation monitor alarms. • No alarms on RM-051, RM-052 or RM-062. • No alarms on RM-054A, RM-054B or RM-057. • No upward trends on RM-054A, RM-054B or RM-

057. • Containment pressure < 3psig • Containment temperature < 120°F

___

CRS Perform EOP-00 “Diagnostic Actions” determine reactivity control not met and go to EOP-20.

___

CRS Implement path RC-1

___

CRS>BOPO Maintain S/G pressures using HCV-1040 or MS-291 and MS-292.

___

CRS>ATCO Trip AI-57 Power supply breakers

___

CRS>ATCO Open individual rod drop test switches

___

CRS Implement path RC-2

___

CRS>ATCO or BOPO

Power bus 1B3B-4B from bus 1B3B (OI-EE-2B, attachment 9)

___

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ATCO or BOPO Report that breaker BT-1B3B will not close

___

Note to instructor: Ensure students know that breaker BT-1B3B did not close due to a scenario malfunction, not because of an improper hot bus transfer. CRS>ATCO or BOPO

Power CH-1B by powering bus 1B4C from bus 1B3C via bus 1B3C-4C (OI-EE-2B, attachment 17)

___

ATCO or BOPO

Energize bus 1B4C from bus 1B3C via bus 1B3C-4C ___

CRS>ATCO Start CH-1B and begin emergency boration.

___

Time = 45 seconds after CH-1B is started EVENT TWO: CH-1B trips Type Filter Item Value Ramp Delay malf cvc bus_1B4C_6_bkr_trip true None None ATCO Report trip of CH-1B

___

CRS Implement Path RC-3

___

CRS>ATCO Attempt to insert CEAs using Manual Sequential or Manual Group then Manual Individual with rod block bypass in bypass.

___

CRS>ATCO or BOPO

Initiate HPSI flow ___

CRS>ATCO or BOPO

Depressurize the RCS by opening the available PORV ___

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CRS>ATCO or BOPO

Maximize heat removal via the S/Gs until HPSI flow begins ___

Instructor note: If the reactivity control safety function is met due to power being below 1E-5% power and constant or lowering. Have the students continue lowering RCS pressure until adequate HPSI flow is developed. The scenario ends when the reactivity control safety function is met and hpsi injection is taking place.

Operator Fundamentals

Having a solid understanding of plant design and theory Following a reactor trip, a negative startup rate is expected but does not mean that reactivity is becoming more negative. It only means that the delayed neutron precursors are decaying away. It is completely possible for reactivity to be increasing while the startup rate remains negative. Be aware of any changes in parameters that could cause positive reactivity addition such as dilution or cooldown. If these parameters are changing such that a positive reactivity addition could be made assume that a positive reactivity addition is being made, even though the SUR is still negative.

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POST-SCENARIO DISCUSSION (Can be conducted after the simulator session or during the next day’s classroom session)

Instructor Review scenario events and procedures used:

• The plant is operating at 100% power MOL. Equilibrium Xenon. Charging pump "A" out of service. FW-54 is 00S for maintenance.

• A Loss of Offsite Power occurs. A Reactor Trip signal is generated on loss of flow, but numerous CEAs fail to insert.

• DG-2 fails to start resulting in the loss of power to bus 1A4. Emergency Boration can not be performed because there is no power to any charging pumps..

• Standard Post Trip Actions are completed and diagnosis indicates that the reactivity control safety function is not satisfied., transition to EOP-20.

• Evaluation of Safety Functions leads to performance of RC-1 and RC-2.

• Breaker BT-1B3B will not close preventing powering CH-1C.

• Can power CH-1B by powering bus 1B4C from bus 1B3C via bus 1B3C-4C

• Shortly after being started, CH-1B trips. • Crew then uses RC-3 by depressurizing RCS to allow

HPSI injection • Scenario ends with reactivity control safety function

being satisfied due to Safety Injection or wide range power less than 1E-5%.

___

SM/CRS/Crew Conduct a critique of teamwork, use of procedures, technical performance and human performance fundamentals.

___

SM/CRS/Crew Review Improvement Items.

___

Instructor Discuss any flagged Operator Fundamentals or Operating Experience items that were not discussed during the simulator session.

___

Instructor Discuss issues observed during the simulator session that were not covered during the critique.

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Instructor Additional Questions: Question: How would this event be classified per the E-Plan? Answer: After 15 minutes the event would be classified as an ALERT (SA5) due to AC power capability to vital 4160 volt busses reduced to a single power source.

___

Instructor Review Objectives (Use Objective List)

___

REFERENCES

• EOP-00, “Standard Post Trip Actions”

• EOP-20, “Functional Recovery”

• OI-EE-2B, “480 Volt Hot Bus Transfer”

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ATTACHMENT ONE – SIMULATOR OPERATOR INSTRUCTIONS INITIAL SETUP: Restore the simulator to a 100% power IC. ___

CH-1A OOS Hang tags and place CS in pull to lock Type Filter Item Value Ramp Delay rem cvc rem:bus_1b3a_4_bkr out none none FW-54 OOS Hang tags Type Filter Item Value Ramp Delay rem afw rem:afw_fwc04 stop none none rem afw rem:afw_fwc02 local none none Setup malfunctions to have numerous CEAs stick out on trip. Type Filter Item Value Ramp Delay malf crd rod_pwr_401_2 stuck none none malf crd rod_pwr_303_2 stuck none none malf crd rod_pwr_441_2 stuck none none malf crd rod_pwr_B15_2 stuck none none malf crd rod_pwr_B16_2 stuck none none Setup D/G -2 fails to start Type Filter Item Value Ramp Delay malf dge dge02 true none none Setup breaker BT-1B3B will not close Type Filter Item Value Ramp Delay malf eda bt_1b3b_bkr_trip true none none Ensure horns are ON

___

Go to RUN

___

Time = 5 minutes after pre-shift briefing EVENT ONE: Loss of Offsite Power ATWS Type Filter Item Value Ramp Delay malf swd swd02 true none none malf swd swd01 true none none

Note to instructor: Ensure students know that breaker BT-1B3B did not close due to a scenario malfunction, not because of an improper hot bus transfer.

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Time = 45 seconds after CH-1B is started EVENT TWO: CH-1B trips Type Filter Item Value Ramp Delay malf cvc bus_1B4C_6_bkr_trip true None None

Instructor note: If the reactivity control safety function is met due to power being below 1E-5% power and constant or lowering. Have the students continue lowering RCS pressure until adequate HPSI flow is developed.

The scenario ends when the reactivity control safety function is met and hpsi injection is taking place.

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Figure II.C.3 - Cycle 26 Moderator Temperature Coefficient vs. Burnup (ARO, HFP & HZP, Equilibrium Xenon)