27
KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION USE DOCUMENT INFORMATION 6.2.1.1 Document Type Calculation / Evaluation 6.2.1.2 Document ID C10854 6.2.1.3 Document Title Hi & Hi-Hi Steam Flow and Low Steam Line Pressure ESF Actuation CSA 6.2.1.4 KPS Revision 0 6.2.1.5 Addendum N/A 6.2.1.6 Document Date 10/14/2009 6.2.1.7 Topic Development of the Hi & Hi-Hi Steam Flow and Low Steam Line Pressure ESF Channel Statistical Allowance (CSA) to support Kewaunee's conversion to Improved Technical Specifications (ITS). 6.2.1.8 Document Status Current 6.2.1.9 Superceded By N/A 6.2.1.10 Attachments Y 6.2.1.11 Safety Related Y AUTHOR INFORMATION 6.2.2.1 Author/Submitter JD Desrochers 6.2.2.2 Vendor N/A 6.2.2.3 Vendor Author N/A 6.2.2.4 Discipline Instrument and Control DOCUMENT RELATIONSHIPS 6.2.3.1 System(s) 006- 975 6.2.3.2 DCR(s) N/A 6.2.3.3 Keyword(s) CALC INDEX 6.2.3.4 Inputs 6.2.3.5 Outputs ADMIN/RECORDS USE ONLY 6.2.4.1 Comments 6.2.4.2 Record Type 6.2.4.3 Retention Period 6.2.4.4 Software Application 6.2.4.5 Vault Location 6.2.4.6 Film Reel 6.2.4.7 Reel Odometer

KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

  • Upload
    others

  • View
    3

  • Download
    0

Embed Size (px)

Citation preview

Page 1: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM

Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11INFORMATION USE

DOCUMENT INFORMATION 6.2.1.1 Document Type Calculation / Evaluation 6.2.1.2 Document ID C10854 6.2.1.3 Document Title Hi & Hi-Hi Steam Flow and Low Steam Line Pressure ESF

Actuation CSA 6.2.1.4 KPS Revision 0 6.2.1.5 Addendum N/A 6.2.1.6 Document Date 10/14/2009 6.2.1.7 Topic Development of the Hi & Hi-Hi Steam Flow and Low Steam Line

Pressure ESF Channel Statistical Allowance (CSA) to support Kewaunee's conversion to Improved Technical Specifications (ITS).

6.2.1.8 Document Status Current 6.2.1.9 Superceded By N/A 6.2.1.10 Attachments Y 6.2.1.11 Safety Related Y AUTHOR INFORMATION 6.2.2.1 Author/Submitter JD Desrochers 6.2.2.2 Vendor N/A 6.2.2.3 Vendor Author N/A 6.2.2.4 Discipline Instrument and Control DOCUMENT RELATIONSHIPS 6.2.3.1 System(s) 006- 975 6.2.3.2 DCR(s) N/A 6.2.3.3 Keyword(s) CALC INDEX

6.2.3.4 Inputs

6.2.3.5 Outputs

ADMIN/RECORDS USE ONLY 6.2.4.1 Comments 6.2.4.2 Record Type 6.2.4.3 Retention Period 6.2.4.4 Software Application 6.2.4.5 Vault Location 6.2.4.6 Film Reel 6.2.4.7 Reel Odometer

Page 2: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

~

i', Dominion'"

Calculation Cover SheetPage 1 of 23

( )

Station: Kewaunee - KPS Unit(s): 1 System Code(s):6 - Main Steam

Calculation Number: C10854 Revision: 0 Addendum: N/A

Calculation Quality Class: ~ Safety Related D Non-Safety Related IStatus: Current

Installation Verification Required: ~Yes DNo Discipline: I&C

Keyword(s): Steam Flow, Steam Pressure, ESF, Safety Injection

Supersedes: C10854-2 Rev.2, C10854-3 Rev.1, C10854-5 Rev.O

Subject (Calculation Title): Hi & Hi-Hi Steam Flow and Low Steam Line Pressure ESF Actuation CSA

Initiating Document: Kewaunee Improved Technical Specifications (ITS)

CM-AA-CLC-301, Revision: 1(1) ICM-AA-CLC-301-1001, Revision: 1(1)

AffeCtedi$vstefrl(S,st~ucture(s),/cornponeht s) •.• ···•·•·••.•••·(CQhtihuedohPaQe2):· <. ........... ....... ..)ii .....<Station: Unit: System: Equipment Location (Mark Number): Tag Number (If Applicable):

KPS 1 6 23001 FT-464KPS 1 6 4849401 FQ-464KPS 1 6 4849404 FC-464A/B

Objective: The objective of this calculation is to determine the Channel Statistical Allowance (CSA) forthe Steam Line Isolation and Safety Injection inputs from the Steam Flow and Steam Line Pressureparameters into the logic for the Engineered Safety Features (ESF) actuation system. This calculationsupports the conversion to Improved Technical Specifications (ITS).

Conclusion: The result of the CSA calculation for the Hi Steam Flow bistables is:CSAHi Steam Flow = ± 18.04% Flow Span = ± 0.806 x 106 PPH

The result of the CSA calculation for the Hi-Hi Steam Flow bistables is:CSAHi-Hi Steam Flow = ± 2.051 % Flow Span = ± 0.092 x 106 PPH

The result of the CSA calculation for the Low Steam Line Pressure bistables is:CSALow Steam Line Pressure = ± 2.219% of span = ± 31.066 psig

Originator (Print): Signature: iP &. j Date:J.D. Desrochers ...Lt .I."'-L J A A.._ J,)/ttl /b~Reviewer (Print):

Signatt?l7tdl11l5!it~ Date:D.M. McGrath 10- Jt!-()qOwners Review (Print): ~1~,~re: D~/1ctlet 1U<'61:!./- fc'Jl/ Date:Victor Mvers 1 A v Md-t:vs :b.e,/ +(, _. '.~ n 10-1'1-OrApproval (Print):

~tI v, .

Dat~/ IB. R. Morrison ~AflIO)~ O 1$ oY

This is the revision of CM-AA-CLC-301 and CM-AA-~LC-301-1001 i/ettect at the time the calculation was i~itiate~,'-

1

Page 3: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 2 of 23

Affected System(s), Structure(s), Component(s) (Continued from Page 1.): Station:

KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS KPS

Unit: 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1

System: 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6

Equipment Location (Mark Number): 23005

4849201 4849206

23002 4849801 4849804

23007 4896601 4896604

21094 4849101 4849102 4849103

21095 4849001 4849002 4849004

21097 4849901 4849902 4849903

21098 4849701 4849702 4849703

21096 4848801 4848803 4848802

21099 4872101 4872103 4872102

Tag Number (If Applicable): FT-465 FQ-465

FC-465A/B FT-474 FQ-474

FC-474A/B FT-475 FQ-475

FC-475A/B PT-468 PQ-468

PM-468A PC-468A/B

PT-469 PQ-469

PM-469A PC-469A/B

PT-478 PQ-478

PM-478A PC-478A/B

PT-479 PQ-479

PM-479A PC-479A/B

PT-482 PQ-482

PM-482A PC-482A/B

PT-483 PQ-483

PM-483A PC-483A/B

Page 4: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 3 of 23

TABLE OF CONTENTS

SECTION DESCRIPTION PAGE Calculation Cover Sheet 1 Table of Contents 3 Attachments 3 Record of Revision 3 1.0 Purpose 3 2.0 Method of Analysis 4 3.0 Design Inputs 4 4.0 Assumptions 4 5.0 References 6 6.0 Computer Codes 7 7.0 Functional Block Diagram 8 8.0 Calculations 9 9.0 Conclusion 23 ATTACHMENTS Attachment 1 Section 3.3 of Letter to Donald E. Weinberg from Dr. D. Halmi, Senior

Principal Engineer, Flow Metering and Calcs, BIF Industries, dated 3/23/77. Attachment 2 50.59 Applicability Review Attachment 3 50.59 Pre-Screening RECORD OF REVISION Rev. 0 Original Issue. This calculation replaces Calculations C10854-2 Rev.2, C10854-3

Rev.1, and C10854-5 Rev.0. This calculation is written as a Channel Statistical Allowance (CSA) Calculation versus a Setpoint Calculation.

1.0 PURPOSE The purpose of this calculation is to determine the Channel Statistical Allowance (CSA) values for the Steam Flow and Steam Line Pressure inputs into the Engineered Safety Features (ESF) logic channels. The applicable Steam Flow channels F-464, F-465, F-474, and F-475 provide input into the Steam Line Isolation function. The applicable Steam Line Pressure channels P-468, P-469, P-478, P-479, P-482, and P-483 provide input into the Safety Injection function. Because of the difference in parameters measured, separate CSA's will be determined for the Steam Line Isolation and Safety Injection functions.

Page 5: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 4 of 23

2.0 METHOD OF ANALYSIS This calculation uses the methodology presented in STD-EEN-0304, Revision 6, Calculating Instrumentation Uncertainties by the Square Root of the Sum of the Squares Method (Reference 5.1). The CSA determined in this calculation is a derivation of the following generic equation presented in STD-EEN-0304, Revision 6, Section 6.1:

CSA = SE ± √ [EA² + PMA² + PEA² + (SCA + SMTE)² + SD² + SPE² + STE² + SPSE2 + (M1 + M1MTE)² + (M2 + M2MTE)² + ...+ (Mn + MnMTE)² + RD² + RTE² + RRA²]

(Equation 1)

The error terms in Equation 1 are consistent with standard industry definitions and are described in Section 8.0 and in detail in Reference 5.1. The CSA calculations are based on static conditions. Tolerances associated with the time constants for any dynamic modules are not taken into account in the development of the CSA. The error terms for the Steam Flow channels will be calculated using units in % ΔP Span. The resulting CSA’s will be converted to process units (lbm/hr). The conversion from % ΔP Span to % of Flow Span is found in Reference 5.24 and is given as: % Flow Span = % ΔP Span * 0.5 * (Flow Max / Flow X) (Equation 2) (where X is the flow rate of interest) Transposing Equation 2 yields the following: % ΔP Span = % Flow Span / 0.5 * (Flow Max / Flow X) (Equation 3) 3.0 DESIGN INPUTS The design inputs are manufacturer's published data sheets, active (current) calculations, station controlled drawings and other controlled documents as listed in Section 5.0, References. 4.0 ASSUMPTIONS 4.1 Based on Reference 5.12, all test data is referenced to the rack 10 Ω Test Point Resistor

(TPR), therefore the errors associated with the installed DB Box resistors used to convert the loop current to an applied input voltage to the Foxboro or NUS module under test is included in the overall error of the Foxboro or NUS module as referenced to the rack TPR.

4.2 According to References 5.10, 5.11, and 5.12, a Fluke 45 Digital Multimeter (DMM) is used

to perform the transmitter and rack module calibration. According to Reference 5.13, the DC Voltage accuracies for the ranges of interest are as follows:

Page 6: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 5 of 23

Range Desired Acceptance Range 300 mV 300 mV 299.92 to 300.08 mV

3 V 3 V 2.9992 to 3.0008 V 30 V 30 V 29.992 to 30.008 V

Range Desired Acceptance Range

1000 mV 900 mV 899.76 to 900.24 10 V 9 V 8.9976 to 9.0024

At Kewaunee, there are six possible voltage spans that could be present in the Reactor Protection System; i.e., 40 to 200 mVDC, 100 to 500 mVDC, 1 to 5 VDC, 0.4 to 12.4 VDC, 2 to 10 VDC, and 0 to 10 VDC. The DC voltage accuracies converted to % of span are given below. 100 to 500 mVDC (1000 mV range)

accuracy = (0.24 mVDC / 400 mVDC) * 100% = 0.06% of span

0.4 to 12.4 VDC (30 V range)

accuracy = (0.008 VDC / 12 VDC) * 100% = 0.07% of span 2 to 10 VDC (30 V range)

accuracy = (0.008 VDC / 8 VDC) * 100% = 0.10% of span

0 to 10 VDC (30 V range)

accuracy = (0.008 VDC / 10 VDC) * 100% = 0.08% of span

40 to 200 mVDC (300 mVDC range)

accuracy = (0.08 mVDC / 160 mVDC) * 100% = 0.05% of span

1 to 5 VDC (10 V range)

accuracy = (0.0024 VDC / 4 VDC) * 100% = 0.06% of span

This calculation will be bounded using an accuracy of ± 0.1% of span for the Fluke 45 DMM for all possible conditions for ranges 30 VDC or less. It is acceptable for the calibration procedures to use a DMM with accuracy specifications equal to or better than the Fluke 45 DMM.

4.3 Reference 5.11 specifies that a deadweight tester is used in the calibration of the Steam

Pressure transmitters. Reference 5.10 specifies a pressure measuring device with an accuracy of 2.172 “H2O is used in the calibration of the Steam Flow transmitters. A pressure measuring device with equivalent or better accuracy may be substituted.

Page 7: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 6 of 23

4.4 This calculation is applicable for normal (non-harsh) conditions only. Therefore, the

Environmental Allowance (EA) term is assumed to be zero. This term includes the effects due to degradation of cable insulation (IR) and the effects of high steam pressures and temperatures (SPTE) and radiation (RE) during an accident .

5.0 REFERENCES 5.1 Dominion Standard, STD-EEN-0304, Revision 6, Calculating Instrumentation

Uncertainties by the Square Root of the Sum of the Squares Method. 5.2 Kewaunee Updated Safety Analysis Report (USAR), Chapters 1, 7 and 14. 5.3 Kewaunee Technical Specifications, Sections 3.4, 3.5, 3.6, and Tables TS 3.5-1, TS 3.5-

3 and TS 3.5-4. 5.4 Kewaunee Vendor Technical Manual KW-VTM-000-FOXBO-0031 (100-1762-1) (PT-

001), Revision 15, Nuclear Energy Systems – Instrumentation Reference Manual. 5.5 Kewaunee Vendor Technical Manual KW-VTM-000-FOXBO-0015 (100-1744-1),

Revision 10, Instrumentation Documentation. 5.6 Kewaunee Vendor Technical Manual KW-VTM-000-NUSIN-0017 (240730), Revision 2,

NUS Instruments Series SPS500 Power Supply. 5.7 Kewaunee Vendor Technical Manual KW-VTM-000-NUSIN-0022 (C-N-430-9), Revision

4, SAM504-3 Single & DAM504-3 Dual Alarm Module IOM. 5.8 Kewaunee Vendor Technical Manual KW-VTM-000-ROSEM-0004 (2566-1), Revision 18, Model 1153 Series D Alphaline Nuclear Pressure Transmitter. 5.9 Kewaunee Vendor Technical Manual KW-VTM-000-AMETE-0008 (XK-100-1554, XK-

341-1), Revision 0, Comparator and Deadweight Pressure Determination System- Mansfield & Green Type “T”.

5.10 Kewaunee Instrument Surveillance Procedure MA-KW-ISP-MS-034A, Revision 0, Steam

Generator Steam Flow Transmitters Calibration. 5.11 Kewaunee Surveillance Procedure SP-06-031A-1, Revision 3, Steam Generator Steam

Pressure Loop 468 Transmitter Channel 1 (Red) Calibration. 5.12 Kewaunee Surveillance Procedure SP-06-034B-1, Revision 13, Steam Generator Flow

Mismatch and Steam Pressure Instrument Channel 1 (Red) calibration. 5.13 Kewaunee Instrument and Control Procedure ICP-82B-129, Revision 10, ICE - Fluke 45

Dual Display Multimeters Calibration. 5.14 Kewaunee Instrument and Control Procedure ICP-82B-168, Revision 3, ICE – Heise

PTE-1 Calibrator and HQS-2 Pressure Module Calibration.

Page 8: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 7 of 23

5.15 Kewaunee Instrument and Control Procedure ICP-82B-06, Revision T, ICE - Pressure

Gauge Calibration. 5.16 Kewaunee Instrument and Control Procedure ICP-82B-137, Revision 6, ICE - Precision

Test Resistor Calibration. 5.17 Calculation C10746, Revision 0, Addendum A, Instrument Loop Calibration Resistor Check - Resistor Check Test Equipment Extension and Clarification. 5.18 Interconnection Wiring Diagrams: 5.18.1 XK-100-621, Revision 3N, Rack 1R2 5.18.2 XK-100-627, Revision 2P, Rack W2 5.18.3 XK-100-633, Revision 2P, Rack 1B2 5.18.4 XK-100-638, Revision 2P, Rack Y2 5.18.5 XK-100-623, Revision 2N, Rack R-2 5.18.6 XK-100-635, Revision 2L, Rack B2 5.18.7 XK-100-618, Revision 1, Interconnection Wiring Diagram Notes and Legends 5.19 Instrument Block Diagrams: 5.19.1 XK-100-545, Revision B, Instrument Block Diagram Cover Sheet & Index 5.19.2 XK-100-556, Revision 1U, Comp. Steam Flow / FW (Loop A) 5.19.3 XK-100-557, Revision 2T, Comp. Steam Flow / FW (Loop B) 5.20 Kewaunee Environmental Qualification Plan, Revision 27. 5.21 Kewaunee Drawing M-769, Revision AN, Instrument Locations in Reactor & Auxiliary Building. 5.22 Kewaunee Drawing E-828, Revision AV, W/D - Red, White, Blue and Yellow Protection Channel Instruments 5.23 CN-SSO-00-19, Revision 2, Kewaunee Revised Thermal Design Procedure (RTDP)

Uncertainties for Reload Transition Safety Report (RTSR) and Power Uprate to 1757 MWt-NSSS Power.

5.24 Virginia Power Technical Report EE-0039, Revision 0, Flow Channel Uncertainties,

Dated 3/21/90. 5.25 Calculation C10854-1, Revision 0, SF/FF Mismatch, FW<SF Reactor Trip 6.0 COMPUTER CODES No computer codes were used to perform this calculation. All calculations were performed by hand using the method described in Section 2.0.

Page 9: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 8 of 23

7.0 FUNCTIONAL BLOCK DIAGRAM

FT-464RosemountTransmitter

Model 1153DD60-1438.3 "H2O

PT-468RosemountTransmitter

Model 1153GD90-1400 psig

FQ-464Foxboroor NUS

Power SupplyM1

PQ-468Foxboroor NUS

Power SupplyM1

Safeguard Actuation

High / High-High Steam Line Isolation

Note 1: Instrument Loops F-465, F-474 and F-475 are similar to the F-464 loop depicted above.

Note 2: Instrument Loops P-469, P-478, P-479, P-482 and P-483 are similar to the P-468 loopdepicted above.

Note 3: See Table 7-1 below for additional Tag / Mark Number information.

PC-468A/BFoxboroor NUSBistable

M3

PM-468AFoxboroor NUS

Lead/LagM2

FC-464A/BFoxboroor NUSBistable

M2

Steam Flow Steam Pressure

Page 10: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 9 of 23

Table 7-1

Tag/Mark Number Tag/Mark Number Tag/Mark Number Tag/Mark Number ESF Logic Input FT-464 (23001) FQ-464 (4849401) FC-464A/B (4849404) Hi Steam Line Isolation/

Hi-Hi Steam Line Isolation FT-465 (23005) FQ-465 (4849201) FC-465A/B (4849206) Hi Steam Line Isolation/

Hi-Hi Steam Line Isolation FT-474 (23002) FQ-474 (4849801) FC-474A/B (4849804) Hi Steam Line Isolation/

Hi-Hi Steam Line Isolation FT-475 (23007) FQ-475 (4896601) FC-475A/B (4896604) Hi Steam Line Isolation/

Hi-Hi Steam Line Isolation PT-468 (21094) PQ-468 (4849101) PM-468A (4849102) PC-468A/B (4849103) Lo-Lo Safeguard Actuation PT-469 (21095) PQ-469 (4849001) PM-469A (4849002) PC-469A/B (4849004) Lo-Lo Safeguard Actuation PT-478 (21097) PQ-478 (4849901) PM-478A (4849902) PC-478A/B (4849903) Lo-Lo Safeguard Actuation PT-479 (21098) PQ-479 (4849701) PM-479A (4849702) PC-479A/B (4849703) Lo-Lo Safeguard Actuation PT-482 (21096) PQ-482 (4848801) PM-482A (4848803) PC-482A/B (4848802) Lo-Lo Safeguard Actuation PT-483 (21099) PQ-483 (4872101) PM-483A (4872103) PC-483A/B (4872102) Lo-Lo Safeguard Actuation

8.0 CALCULATIONS 8.1 Steam Flow Channels F-464, F-465, F-474, and F-475 The High-High Steam Flow or the High Steam Flow coincident with Low-Low TAVG provide input to the Steam Line Isolation logic for Safeguard Actuation. 8.1.1 SE = Systematic Error No Systematic Error has been identified for these loops. SE = 0.000% ΔP Span 8.1.2 EA = Environmental Allowance No Environmental Allowance will be used in this calculation. (Assumption 4.4) EA = 0.000% ΔP Span

Page 11: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 10 of 23

8.1.3 PMA = Process Measurement Accuracy At lower flow rates Steam Enthalpy due to pressure and moisture changes will impact the accuracy of the process measurement. Because of this a PMA term of ± 0.3% of flow span will be applied to the High (but not the High-High) Steam Flow bistables. (Reference 5.23) The PMA value given in terms of flow is converted to % ΔP span as follows: % ΔP Span = PMA (% Flow) / 0.5 * (Flow Max / Flow X) (Equation 3) PMA = ± 0.3% flow span Flow Max = 4.47 x 106 lbm/hr (Reference 5.12) FlowHi Steam = 0.494 x 106 lbm/hr (Reference 5.12) PMA in % ΔP Span = 0.3% / 0.5 * (4.47 x 106 lbm/hr / 0.494 x 106 lbm/hr) = 0.066% ΔP Span PMAHi Steam = ± 0.300% Flow Span = 0.066% ΔP Span 8.1.4 PEA = Primary Element Accuracy Three tolerances for the BIF “Steam Tubes” were identified in Section 3.3.4 of Attachment 1: 1) The Condition of Tube was given a tolerance of 0.2%. For conservatism that tolerance will

be increased to 0.5%. 2) The Basic Tolerance is given as 0.75%. 3) The Installation Effect is given as 0.7%. For conservatism, these tolerances will be added numerically resulting in a tolerance of 1.95%. The PEA value given in terms of flow is converted to % ΔP span with respect to Flow Nom as follows: % ΔP Span = PEA (% Flow) / 0.5 * (Flow Max / Flow X) (Equation 3) PEA = ± 1.95% of flow span Flow Max = 4.47 x 106 lbm/hr (Reference 5.12) Flow Nom = 3.82 x 106 lbm/hr (Reference 5.23) PEA in % ΔP Span = 1.95% / 0.5 * (4.47 x 106 lbm/hr / 3.82 x 106 lbm/hr) = 3.333% ΔP Span PEA = ± 1.950% Flow Span = 3.333% ΔP Span

Page 12: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 11 of 23

8.1.5 SCA = Sensor Calibration Accuracy Reference 5.10 provides a transmitter calibration accuracy of ± 0.25% ΔP span. SCA = ± 0.250% ΔP Span (Reference 5.10) 8.1.6 SMTE = Sensor Measuring and Test Equipment The following Measuring and Test Equipment or its equivalent is used for calibration of the transmitters: 1) SMTE1 = DMM, Fluke Model 45 or equivalent with an accuracy of ± 0.1% of ΔP span SMTE1 = ± 0.100% of ΔP span (Assumption 4.2) 2) SMTE2 = 10 Ω Test Point Resistor (TPR) with an accuracy of ± 0.01% ΔP span SMTE2 = ± 0.010% ΔP span (Reference 5.16) 3) Reference 5.10 states that a pressure measuring device with an accuracy of 2.172 ”H2O or

better is used for the calibration of the Steam Flow transmitters. SMTE3 = (2.172 “H2O / 1438.3 “H2O) * 100% = ± 0.151% ΔP span (Reference 5.10) Therefore the Sensor Measuring and Test Equipment (SMTE) accuracy is equal to: SMTE = [ (SMTE1 + SMTE2)2 + SMTE3

2 ] 1/2 SMTE = [ (0.100 + 0.010)2 + (0.151)2 ] 1/2 SMTE = ± 0.187% ΔP Span 8.1.7 SD = Sensor Drift According to References 5.8 and 5.25 the sensors are Rosemount 1153DD6 transmitters. Based on Reference 5.8, the Rosemount Model 1153DD6 transmitter has a drift value of ± 0.2% of upper range limit (URL) for 30 months. The calibrated span of the instrument per Reference 5.10 is 1438.3 “H2O. The upper range limit of the transmitter is 100 psi (2773.0 “H2O) per Reference 5.8. Therefore the Sensor Drift allowance for a period of up to 30 months is: SD = (± 0.002 * 2773 “H2O / 1438.3 “H2O) * 100% SD = ± 0.386% ΔP span (References 5.8, 5.10 and 5.25)

Page 13: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 12 of 23

8.1.8 SPE = Sensor Pressure Effect Reference 5.8 specifies a Static Pressure Zero Effect and a Static Pressure Span Effect. The Static Pressure Zero Effect is adjusted out by calibration procedures. (Reference 5.10)

The Static Pressure Span Effect equals ± 0.5% of input reading per 1000 PSIG. (Reference 5.8) For conservatism, this calculation will assume the maximum pressure of 1005 PSIG from Reference 5.2 when determining the Static Pressure Span Effect. Therefore, the Static Pressure Span Effect = 100% * (1005 PSIG * 0.005) / 1000 PSI SPE = ± 0.503% ΔP Span 8.1.9 STE = Sensor Temperature Effect The Rosemount Instruction Manual states the temperature effect for Range Code 6 is: ± (0.75% of URL + 0.5% span) per 100°F (Reference 5.8) Upper Range Limit = 2773 “H2O (100 PSI) (Reference 5.8) Transmitter Span = 1438.3 “H2O (Reference 5.10) Temperature Span = 80°F (References 5.3 & 5.20) STE = ± [(0.75% * 2773 “H2O / 1438.3 “H2O) + 0.5%] * (80°F / 100°F) STE = ± 1.557% ΔP Span 8.1.10 SPSE = Sensor Power Supply Effect The Sensor Power Supply Effect for the Steam Flow transmitters is less than 0.005% of output span per volt. The transmitter is qualified to operate in a region ranging from a minimum of 13.5 VDC up to a maximum of 45 VDC depending upon the load resistance. (Reference 5.8) The power supply output voltage is not checked during the performance of the transmitter calibration or the channel calibration procedures, therefore to bound all possible conditions, a power supply output tolerance of + 31.5 VDC (i.e. 45 VDC – 13.5 VDC) will be used to determine the Sensor Power Supply Effect. (References 5.10 & 5.12) SPSE = ± [0.00005 * (31.5 VDC / 1.0 VDC)] * 100% = 0.158% SPSE = + 0.158% ΔP Span

Page 14: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 13 of 23

8.1.11 M1 = Loop Power Supply This calculation assumes that either a Foxboro or NUS Loop Power Supply is installed. The Loop Power Supply for the process racks is used to power the transmitter current loop and is not used as a signal converter. Therefore, the calibration accuracy is equal to 0.0 % of span. (References 5.10 & 5.12) M1 = 0.000% ΔP Span 8.1.12 M1MTE = Loop Power Supply Measuring and Test Equipment The Loop Power Supply for the process racks is used to power the transmitter current loop. The Loop Power Supply is not used as a signal converter and thus no calibration is required. Therefore, M1MTE is equal to 0.0% of span. (References 5.10 & 5.12) M1MTE = 0.000% ΔP Span 8.1.13 M2 = Bistable Based on Reference 5.19, either a Foxboro Model M/63U-BC or NUS Instruments Model DAM504-3 may be installed as a Steam Flow bistable. The calibrated accuracy is ± 0.500% of span. (Reference 5.12) M2 = ± 0.500% ΔP Span 8.1.14 M2MTE = Bistable Module Measuring and Test Equipment One DMM and Test Point Resistor (TPR) are used to calibrate the bistables. (Reference 5.12) M2MTE = ± (Fluke + TPR)

Fluke Accuracy = ± 0.100% of span (Assumption 4.2) Installed Rack Test Point Resistor Accuracy = ± 0.100% of span (Reference 5.17) M2MTE = ± (0.100 + 0.100) = ± 0.200% of span M2MTE = ± 0.200% ΔP Span

Page 15: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 14 of 23

8.1.15 RD = Rack Drift The superseded calculations specified a drift value derived from previous testing. However, that data is not current and Kewaunee is replacing Foxboro rack modules with NUS Instruments equivalents where sufficient drift trends have not been established. Therefore, the standard and conservative value of ± 1.0% of span as referenced in STD-EEN-0304, Revision 6 will be used in this calculation. RD = ± 1.000% ΔP Span (Reference 5.1) 8.1.16 RTE = Rack Temperature Effect For Kewaunee calculations the Rack Temperature Effect term was either assumed to be embedded in the Rack Drift term or set to zero percent of span. However, the effects of rack temperature changes have not been monitored or documented . Therefore, the standard and conservative value of ± 0.5% of span as referenced in STD-EEN-0304, Revision 6 will be used in this calculation. RTE = ± 0.500% ΔP Span (Reference 5.1) 8.1.17 RRA = Rack Readability Allowance Rack Readability Allowance (RRA) is applicable for the indication portion of the loops. This calculation is only applicable to bistables and does not address indicators. RRA = ± 0.0% ΔP Span

Page 16: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 15 of 23

8.1.18 Hi Steam Flow Bistable Uncertainty The Channel Uncertainty for the Hi Steam Flow Bistable is derived using the following equation:

CSA = SE ± [EA2 + PMA2 + PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M2 + M2MTE)2 + RD2 + RTE2 + RRA2]½ Where: SE = 0.000% ΔP Span EA = 0.000% ΔP Span PMA = 0.066% ΔP Span PEA = 3.333% ΔP Span SCA = 0.250% ΔP Span SMTE = 0.187% ΔP Span SD = 0.386% ΔP Span SPE = 0.503% ΔP Span STE = 1.557% ΔP Span SPSE = 0.158% ΔP Span M1 = 0.000% ΔP Span M1MTE = 0.000% ΔP Span M2 = 0.500% ΔP Span M2MTE = 0.200% ΔP Span RD = 1.000% ΔP Span RTE = 0.500% ΔP Span RRA = 0.000% ΔP Span CSA = 0.0 ± [0.02 + 0.0662 + 3.3332 + (0.250 + 0.187)2 + 0.3862 + 0.5032 + 1.5572 + 0.1582 + (0.0 + 0.0)2 + (0.500 + 0.200)2 + 1.0002 + 0.5002 + 0.02]½ CSAHi Steam Flow = ± 3.987% ΔP Span % Flow Span = % ΔP Span * 0.5 * (Flow Max / Flow X) (Equation 2) % Flow Span = 3.987% ΔP Span * 0.5 * (4.47 x 106 PPH / 0.494 x 106 PPH) = 18.04% Flow Span CSAHi Steam Flow = 18.04% Flow Span = 0.806 x 106 PPH

Page 17: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 16 of 23

8.1.19 Hi-Hi Steam Flow Bistable Uncertainty The Channel Uncertainty for the Hi-Hi Steam Flow Bistable is derived using the following equation:

CSA = SE ± [EA2 + PMA2 + PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M2 + M2MTE)2 + RD2 + RTE2 + RRA2]½

Where: SE = 0.000% ΔP Span EA = 0.000% ΔP Span PMA = 0.000% ΔP Span PEA = 3.333% ΔP Span SCA = 0.250% ΔP Span SMTE = 0.187% ΔP Span SD = 0.386% ΔP Span SPE = 0.503% ΔP Span STE = 1.557% ΔP Span SPSE = 0.158% ΔP Span M1 = 0.000% ΔP Span M1MTE = 0.000% ΔP Span M2 = 0.500% ΔP Span M2MTE = 0.200% ΔP Span RD = 1.000% ΔP Span RTE = 0.500% ΔP Span RRA = 0.000% ΔP Span CSA = 0.0 ± [0.02 + 0.02 + 3.3332 + (0.250 + 0.187)2 + 0.3862 + 0.5032 + 1.5572 + 0.1582 + (0.0 + 0.0)2 + (0.500 + 0.200)2 + 1.0002 + 0.5002 + 0.02]½ CSAHi-Hi Steam Flow = ± 3.986% ΔP Span % Flow Span = % ΔP Span * 0.5 * (Flow Max / Flow X) (Equation 2) % Flow Span = 3.986% ΔP Span * 0.5 * (4.47 x 106 PPH / 4.3439 x 106 PPH) = 2.051% Flow Span CSAHi-Hi Steam Flow = 2.051% Flow Span = 0.092 x 106 PPH

Page 18: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 17 of 23

8.2 Steam Pressure Channels P-468, P-469, P-478, P-479, P-482 and P-483 The Steam Pressure Channels provide inputs to the logic for Safeguard Actuation. 8.2.1 SE = Systematic Error No Systematic Error has been identified for these loops. SE = 0.000% of span 8.2.2 EA = Environmental Allowance No Environmental Allowance will be used in this calculation. (Assumption 4.4) EA = 0.000% of span 8.2.3 PMA = Process Measurement Accuracy PMA is not applicable for this loop configuration. PMA = ± 0.000% of span 8.2.4 PEA = Primary Element Accuracy PEA is not applicable for this loop configuration. PEA = ± 0.000% of span 8.2.5 SCA = Sensor Calibration Accuracy Reference 5.11 provides a transmitter calibration accuracy of ± 0.25% of span. SCA = ± 0.250% of span (Reference 5.11)

Page 19: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 18 of 23

8.2.6 SMTE = Sensor Measuring and Test Equipment The following Measuring and Test Equipment or its equivalent is used for calibration of the transmitters: 1) SMTE1 = DMM, Fluke Model 45 or equivalent with an accuracy of ± 0.1% of ΔP span SMTE1 = ± 0.100% of span (Assumption 4.2) 2) SMTE2 = 10 Ω Test Point Resistor (TPR) with an accuracy of ± 0.01% ΔP span SMTE2 = ± 0.010% of span (Reference 5.11) The surveillance procedures for the calibration of the Steam Generator Steam Pressure transmitters (Reference 5.11) specify the use of a Deadweight Tester for the measurement of the pressure input during calibration. To allow for future changes in the calibration methods, this calculation will assume that a pressure gauge (temperature compensated) with an accuracy of ± 2.0 psig or better is used in the calibration of the transmitter. This accuracy will bound that of the Deadweight Tester and also a Heise Handheld with Pressure Module.

3) SMTE3 = Ashcroft Pressure Gauge or equivalent (temperature compensated), 0 to 2000 psig with an accuracy of + 2.0 psig or better (Reference 5.15)

SMTE3 = ± (2.0 psig / 1400 psig) * 100% (References 5.11 & 5.15) SMTE3 = ± 0.143% of span Therefore the Sensor Measuring and Test Equipment (SMTE) accuracy is equal to: SMTE = [ (SMTE1 + SMTE2)2 + SMTE3

2 ] 1/2 SMTE = [ (0.100 + 0.010)2 + (0.143)2 ] 1/2 SMTE = ± 0.180% of span 8.2.7 SD = Sensor Drift According to Reference 5.8 the sensors are Rosemount Model 1153 Series D Alphaline Nuclear Pressure Transmitters (Model 1153GD9RB) with a drift equal to ± 0.2% of upper range limit (URL) for 30 months SD = ± 0.2% * (3000 psi / 1400 psi) SD = ± 0.429% of span (Reference 5.8)

Page 20: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 19 of 23

8.2.8 SPE = Sensor Pressure Effect SPE is not applicable to this instrument configuration. SPE = ± 0.000% of span 8.2.9 STE = Sensor Temperature Effect The Rosemount Instruction Manual states the temperature effect for Range Code 9 is: ± (0.75% of URL + 0.5% span) per 100°F (Reference 5.8) Upper Range Limit = 3000 psi (Reference 5.8) Transmitter Span = 1400 psi (Reference 5.11) Temperature Span = 70°F (Reference 5.20) Note: The Environmental Qualification Plan specifies a Design Input Temperature of 120°F. It also states that the Average Temperature found at Thermocouple L1 in the Shield Building/Annulus is 78.3°F. For conservatism, this calculation will assume a minimum temperature of 50°F to account for a transmitter calibration performed when the building is at its coolest. This results in a Temperature Span of 70°F. STE = ± [(0.75% * 3000 psi / 1400 psi) + 0.5%] * (70°F / 100°F) STE = ± 1.475% of span 8.2.10 SPSE = Sensor Power Supply Effect The Sensor Power Supply Effect for the Steam Pressure transmitters is less than 0.005% of output span per volt. The transmitter is qualified to operate in a region ranging from a minimum of 13.5 VDC up to a maximum of 45 VDC depending upon the load resistance. (Reference 5.8) The power supply output voltage is not checked during the performance of the transmitter calibration or the channel calibration procedures, therefore to bound all possible conditions, a power supply output tolerance of + 31.5 VDC (i.e. 45 VDC – 13.5 VDC) will be used to determine the Sensor Power Supply Effect. (References 5.11 & 5.12) SPSE = ± [0.00005 * (31.5 VDC / 1.0 VDC)] * 100% = 0.158% SPSE = + 0.158% of span

Page 21: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 20 of 23

8.2.11 M1 = Loop Power Supply This calculation assumes that either a Foxboro or NUS Loop Power Supply is installed. The Loop Power Supply for the process racks is used to power the transmitter current loop and is not used as a signal converter. Therefore, the calibration accuracy is equal to 0.0 % of span. (Reference 5.12) M1 = 0.000% of span 8.2.12 M1MTE = Loop Power Supply Measuring and Test Equipment The Loop Power Supply for the process racks is used to power the transmitter current loop. The Loop Power Supply is not used as a signal converter and thus no calibration is required. Therefore, M1MTE is equal to 0.0 % of span. (References 5.12) M1MTE = 0.000% of span 8.2.13 M2 = Lead/Lag Module A Foxboro Model M/66RC-OL (or NUS equivalent module) is installed as the Lead/Lag Module. The static calibration accuracy is ± 0.500 % of span. (References 5.12 & 5.18) M2 = ± 0.500% of span 8.2.14 M2MTE = Lead/Lag Module Measuring and Test Equipment Two DMM’s and two Test Point Resistors (TPR) are required to calibrate this module. M2MTE = ± [ (Fluke1 + TPR1)2 + (Fluke2 + TPR2)2 ]½ M2MTE = ± [ (0.100 + 0.100)2 + (0.100 + 0.100)2 ]½ (Assumption 4.2 & Reference 5.17) M2MTE = ± 0.283% of span (Reference 5.12) 8.2.15 M3 = Bistable Based on Reference 5.18, either a Foxboro Model M/63U-BC or NUS Instruments Model DAM504-3 may be installed as a Steam Pressure bistable. The calibrated accuracy is ± 0.500 % of span. M3 = ± 0.500% of span (Reference 5.12)

Page 22: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 21 of 23

8.2.16 M3MTE = Bistable Module Measuring and Test Equipment One DMM and one Test Point Resistor (TPR) are required to calibrate this module. M3MTE = ± (Fluke + TPR)

M3MTE = ± (0.100 + 0.100) (Assumption 4.2 & Reference 5.17) M3MTE = ± 0.200% of span (Reference 5.12) 8.2.17 RD = Rack Drift The superseded calculations specified a drift value derived from previous testing. However, that data is not current and Kewaunee is replacing Foxboro rack modules with NUS Instruments equivalents where sufficient drift trends have not been established. Therefore, the standard and conservative value of ± 1.0% of span as referenced in STD-EEN-0304, Revision 6 will be used in this calculation. RD = ± 1.000% of span (Reference 5.1) 8.2.18 RTE = Rack Temperature Effect For Kewaunee calculations the Rack Temperature Effect term was either assumed to be embedded in the Rack Drift term or set to zero percent of span. However, the effects of rack temperature changes have not been monitored or documented . Therefore, the standard and conservative value of ± 0.5% of span as referenced in STD-EEN-0304, Revision 6 will be used in this calculation. RTE = ± 0.500% of span (Reference 5.1) 8.2.19 RRA = Rack Readability Allowance Rack Readability Allowance (RRA) is applicable for the indication portion of the loops. This calculation is only applicable to bistables and does not address indicators. RRA = ± 0.0% of span

Page 23: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 22 of 23

8.2.20 Lo Steam Line Pressure Bistable Uncertainty The Channel Uncertainty for the Lo Steam Line Pressure Bistable is derived using the following equation:

CSA = SE ± [EA2 + PMA2 + PEA2 + (SCA + SMTE)2 + SD2 + SPE2 + STE2 + SPSE2 + (M1 + M1MTE)2 + (M2 + M2MTE)2 + (M3 + M3MTE)2 + RD2 + RTE2 + RRA2] ½

Where: SE = 0.000% of span EA = 0.000% of span PMA = 0.000% of span PEA = 0.000% of span SCA = 0.250% of span SMTE = 0.180% of span SD = 0.429% of span SPE = 0.000% of span STE = 1.475% of span SPSE = 0.158% of span M1 = 0.000% of span M1MTE = 0.000% of span M2 = 0.500% of span M2MTE = 0.283% of span M3 = 0.500% of span M3MTE = 0.200% of span RD = 1.000% of span RTE = 0.500% of span RRA = 0.000% of span CSA = 0.0 ± [0.02 + 0.02 + 0.02 + (0.250 + 0.180)2 + 0.4292 + 0.02 + 1.4752 + 0.1582 + (0.0 + 0.0)2 + (0.500 + 0.283)2 + (0.500 + 0.200)2 + 1.0002 + 0.5002 + 0.02] ½

CSA = ± 2.219% of span The Steam Pressure transmitters have a calibrated span of 0 - 1400 psig. Therefore, the CSA in process units is: CSA = 1400 psig * (± 2.219% of span / 100% of span) = ± 31.066 psig CSA = ± 31.066 psig

Page 24: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Engineering Work Sheet

Calculation Number: C10854

Revision: 0

Addendum: N/A

Page 23 of 23

9.0 CONCLUSION The results of the CSA calculations are as follows: Hi Steam Flow: CSA = ± 18.04% Flow Span = ± 0.806 x 106 PPH Hi-Hi Steam Flow: CSA = ± 2.051% Flow Span = ± 0.092 x 106 PPH Lo Steam Line Pressure: CSA = ± 2.219% of span = ± 31.066 psig

Page 25: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

c. 0 €>54 fZe.. V. 0 Att "- c ~ M t<.. \1\ t 1

p~~ I o-f' )

I

'rhe nominal inlet I,D. of subject tubes is 27.9S1~; the nominal throatdia. is 16.000~; thus the ~omina: Beta ratio is 0,5724.

3.3.1 V.alue of ITCH and Its Basic Toleranc.e

.--. The value of lie" is 0.987'3 on which the basi~ toleranc'e is±O. 75% •-3.3.2 Effect of Installation on "C'f

Since subject tubes are direct coupled to a sudden increaser andlong radius elbow that precedes them~ an additional ±O.7% tolerancemust be considered on their "C'S",

3. 3.3 Behavior of uCH

The fact that these tubes are used at high Rn's shoud not add toabove stated "e" tolerances.

3.3.4 Jotal tolerance

The Total Maximum Tolerance:

• Due to Condition of Tube(See par. 1. in letter)

• Basic Tolerance(See par. 3.3.1)

• Effect of Installation(See par. 3.3.2)

Summ:

The probable accuracy of lie" should be 'Hithin:

± %

0.2

0.75

0.7

1.65

= ± l.l%" /"

D. HalmiSenior Principal EngineerFlow Metering & CalesB I F'3/23/77

Page 26: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

Calculation C10854, Rev. 0Attachment 2Page 1 of 1

50.59 APPLICABILITY REVIEW(Is the activity excluded from 50.59 review?)

Document/Activity number: _C_l_08_5_4~,R_ev_is_i_on_O _

Briefdescription ofproposed activity (what is being changed and why):

This calculation supercedes calculation CI0854-2, Revision 2, Cl0854-3, Revision 1 and CI0854-5, Revision O. Calculation CI0854, Revision 0develops the Channel Statistical Allowance (CSA) values associated with Kewaunee's Unit 1 Hi & Hi-Hi Steam Flo,v and Low Steam Line PressureESF actuation functions. This calculation supports Kewaunee's conversion to Improved Technical Specifications (ITS).Does the proposed activity involve or change any of the following documents or processes? Check YES or NO for EACH applicability review iteln.Explain in comments ifnecessary. [Ref. USA 50.59 Resource Manual] .

1.

2.

3.

NOTE: Ifyou are unsure ifa document or process may be affected, contact the process owner.

Yes No Document or Applicable ContactJAction./ -/ Process Regulation

a 0 I8J Technical Specifications or Operating License lOCFR50.92Process change per LI-AA-IOI.Contact Licensing.

Activity/change previously approved by NRC in Identify NRC letter in comments below. Processb 0 181 IOCFR50,90 change.

license amendment or NRC SER Contact Licensing for assistance.

c 0 181 Activity/change covered by all existing approvedIOCFR50 Appendix B

Identify screening or evaluation in comments below.lOCFRSO.59 review, screening, or evaluation. Process change,

d 0 181 Dominion Quality Assurance Program Description10CFRSO.54(a)

ContactQA.(DOM-QA-l) Refer to NO-AA-IOI.

0 181 Etnergency Plan 1OCFR50.54(q)ContactEP.

e Refer to FP-R-EP-02.

f D 181 Security Plan 1OCFR50.54(p)Contact Security.Refer to FP-S-SPE-Ol.

g D I8l 1ST Plan 1OCFRSO.55a(f)Contact 1ST process owner.Refer to ER-AA-IST-IO.

h D 181 lSI Plan 1OCFRSO.55a(g)Contact lSI process owner. Refer toER-AA-NDE-122, NAD-Ol.05, andNAD-05.11.

i 0 ~ BeeS Acceptance Criteria lOCFR50.46 Contact Licensing.

USAR or any document incorporated by reference - Process USARchangeperNEP-05.02.j 0 181 Check YES only ifchange is editorial (see lOCFR50.71 Contact USAR process owner for assistance.

Attachment A).Commitment - Commitment changes associated Contact Licensing.

k D ~ with a response to Generic Letters and Bulletins, or 10CFRSO Appendix Bif described in the USAR require apre~screening.

Refer to LI-AA-I10.

Maintenance activity or new/revised maintenance Evaluate under Maintenance Rule.I 0 ~

procedure - CheckYES only if clearly maintenancelOCFR50.65 Refer to ER-AA-MRL-IO, ER-AA-MRL-IOO, andand equipment will be restored to its as-designed

NAD-08.21.condition within 90 days (see Attachment C).New/revised administrative or managerialdirective/procedure (e.g., NAD, GNP, Fleet

m 0 ~Procedure) or a change to any procedure or other

10CFRSO Appendix B Process procedure/document revision.controlled document (e.g., plant drawing) which isclearly editorial/administrative. See Attachments AandB.

n D 181 Fire Plan lOCFR50.48Fire Protection Program Document Change Control,GNP-05.30.01.

0 D ~ Independent Spent Fuel Storage Installation (ISFSI) lOCFR72.48 Implement DNAP-3004, starting with Applicability.

/0 Ill/If) 91 ,

I o-/!£- CJ'l

Date:,...;..----"lIl~~~~---

Date:D.M. McGrath

4.

5.

Reviewed by:(print/sign)

Conclusion. Check one of the following:~ All documents/processes listed above are checked NO. lOCFR50.S9 applies to the proposed activity. A 50.59 pre-screening shall be

perfonned.

o One or more of the doculnents/processes listed above are checked YES, AND controls all aspects of the proposed activity. lOCFRSO.59 doesNOT apply. Process the change under the applicable program/process/procedure.

o One or more of the documents/processes listed above are checked YES, however, some portion of the proposed activity is not controlled byany of the above processes. lOCFRSO.59 applies to that portion. A 50.59 pre-screening shall be perfoIUled.

Comments:ET-CEE-09-0009, Rev.O will transmit the 50.59/72.48 Evaluation and program/document updates.

6. Print name followed by signature. Attach completed fonn to docum t/activity/change p kage.

Prepared by: ID. Desrochers(print/sign)

Form GNP-04_04.01-1 Rev_ 12 Date; APR 08 2008 Page 15 of 16

INFORMATION USE

Page 27: KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE … · KEWAUNEE NUCLEAR POWER PLANT DESIGN BASIS DATABASE LOAD FORM Form GNP-05.27.07-1 Rev. 9 Date: MAR 20 2008 Page 11 of 11 INFORMATION

50.59 PRE-SCREENING Calculation C10854, Rev. 0(Is a 50.59 screening required?) Attachment 3

1. Do'cumentlActivity number: CI0854, Revision 0 Page 1 of 12. Briefdescliption ofproposed activity (what is being changed and why):

This calculation snpercedes calculation CI0854-2, Revision 2, CI0854-3, Revision 1 and CI0854-5, Revision O. Calculation C10854, Revision 0develops the Channel Statistical Allowance (CSA) values associated with Kewaunee's Unit 1Hi & Hi-Hi Steam Flow and Low Steam Line Pressure ESFactuation functions. This calculation supports Kewaunee's conversion to Improved Technical Specifications (ITS).

3. Does the proposed activity involve or change any of the following documents or processes? Explain in Comments if necessary.

Check YES or NO for EACH pre-screening item. [Ref. USA 50.59 Resource Manual]NOTE: Ifyou are unsure if a document or process may be affected, contact the process owner.NOTE: An asterisk (*) indicates that the document is incorporated by reference in the USAR or is implicitly considered part of the USAR.NOTE: Check NO if activity/change is considered editorial) administrative, or maintenance as defmed in Attachments A, B, and C. Explain in Comments

if necessary.

Yes"" No,/ DocumentIProcessDirective!Procedure

a D r8l Updated Safety Analysis Report (USAR) NEP-05.02

b D ~ * Technical Specifications Bases or Technical Requirements Manual (TRM)LI-AA-IOI,

U-AA-IOI-lOOl

c D ~ * Commitments made in response to NRC Generic Letters and Bulletins, and those described in the USAR LI-AA-ll0

d D ~ * Environmental Qualification (EQ) Plan NAn-Ol.08

e D ~ * Regulatory Guide 1.97 (RG 1.97) Accident Monitoring Instrumentation Plan NAD-05.22

f D ~ * Fire Plan NAD-Ol.02

g D ~ * Appendix R Design Description NAD-Ol.02

h D ~ * Fire Protection Program Analysis (FPPA) NAD-Ol.02

i D ~ * Offsite Dose Calculation Manual (ODCM) NAD-05.l3

j D ~ * Radiological Environmental Monitoring Manual (REMM) NAD-05.13

k D ~ * Station Blackout Design Description

1 D ~ * Control Room Habitability Study

D ~Plant Drawing ChangeslDiscrepancies-Check YES only if: 1) the change adds information to, deletes information

m from, or alters the configuration of a drawing that is incorporated in the USAR, or 2) configures an SSC NAn-OS.O!differently than described or credited in USAR text.

n D ~CalculationslEvaIuations/Analyses/Computer Software - Check YES only if: 1) It affects a method of evaluation Variousdescribed in the USAR, or 2) It independently (i.e., not part of a modification) affects the licensing or design basis.

0 D ~ Pennanent Plant Physical Changes - All require a screening. NAD-04.03

p D ~Temporary Plant Physical Changes (TCRs) - Check No only if installed for maintenance AND in effect for less

NAD-04.03than 90 days at power conditions.

q D [gI QA Typing Determinations - Check YES only if reduction in classification, or affects design function as describedNAn-01.0t

inUSAR.

r D ~ Setpoint or Acceptance Criteria - Check YES only if change affects plant monitoring, pelforrnance, or operation. Various

s D ~Plant ProcedureslRevisions - Check YES only if the change directly or indirectly involves operating, controlling NAD-03.01or configuring an SSC differently than described or credited in U8AR.

t D ~ Engineering Specifications - Check YES only if a design function ,or design requirement may be affected. NAD-05.03

u D ~Operations Night Orders or Operator Work Arounds - Check YES only if SSCs are operated or configured

GNP-03.30.01differently than described in D8AR.NAD-08.l4,

D ~Temporary plant alterations (e.g., jumpers, scaffolding, shielding, barriers) - Check YES only if installed (or in GMP-127,

v effect) for maintenance for longer than 90 days at power conditions. GNP~01.23.04,

FPP-08-09

w D ~ Temporary plant alterations ~ Check YES only if not associated with maintenance.

x D ~Corrective/Compensatory Actions - Check YES only if degraded/non-confonning plant condition accepted "as-is"

OP-AA-I02or compensatory action taken.

4 Conclusion. Check one of the following:

~ All of the documents or processes listed above are checked NO. A 50.59 screening is NOT required. Process change in accordance with theapplicable program/process/procedure.

D One or more of the documents or processes listed above are checked YES. A 50.59 screening shall be perfonned.

5 Corrunents:ET-CEE-09-0009, Rev.O will transmit the 50.59/72.48 Evaluation and program/document updates.

6 ~::~~ followed by signature. Either the preparer or reviewerfShfjanbe~50'59 screening qualified. Attach completed fann to document/activity/change

Pr~pare,d by: J.D. Desrochers I Date: J(J IIA/la,(pont/SIgn) r -~ I (J J ,0Reviewed by: D,M. McGrath ". ~ Date: La ~ /y'-IJ~(print/sign)

Form GNP-04.04.01-2 Rev. 12 Date: APR 08 2008INFORMATION USE

Page 16 of 16