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DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TOPRIORITY Rush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS
OTHERWISE IDENTIFIED BELOW
1) 01834 CNS C/R DWGS. SSA CN02OP2) 02049 C M MISEHEIMER EC081
3) 02124 R 0 SHARPE AREVA NP INC.4) 02310 CNS CHEMISTRY HI-RI CN03CH
5) 02467 ELECT. LICENSING LIBRARY EC050
6) 02835 E G WAGNER CN03SE
7) 03200 T G POETZSCH CN03SE
80 S-L NC-RE G-WASHTNG0
9) 03796 SCIENTECH CLEARWTR, FL
10) 03833 CNS COMPL FILE (ORIG)X CN01RC
11) 03945 OPS TRAINING CT01A
12) 04446 M E HENSHAW EC08H
13) 04490 C T KIKER CT01A
14) 04552 L E HAYNES EC07F
15) 05160 PT VU MG01RC
Duke EnergyDOCUMENT TRANSMITTAL FORM
REFERENCE
CATAWBA NUCLEAR STATION
SELECTED LICENSEE COMMITMENTS
Page 2 of 3
Date: 03/21112
Document Transmittal #: DUK120800041
QA CONDITION [: Yes U No
OTHER ACKNOWLEDGEMENT REQUIRED * Yes
IF GA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASEACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:
Duke Energy4800 Concord RoadDocument ManagementCN04DMYork, South Carolina 29745
'4'
Rec'd By
Date
DOCUMENT NO QACOND REV #/DATE DISTR CODE 1 2 3 4 5 6 7 (8/ 9 10 11 12 13 14 15 -ITOTAL
LOES (4 PAGES)TAB 16.0 - TABLE OF CONTENTS
SECTION 16.5-1
SECTION 16.5-9
SECTION 16.7-9
SECTION 16.7-10
SECTION 16.8-2
SECTION 16.9-19
SECTION 16.9-26
SECTION 16.11-7
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CADM-03 V2 vi Vl Vi V1 Vi1 V1 V10 IVl x V26 Vl Vl V1 V1 72
REMARKS: PLEASE REFER TO THE ATTACHED MEMO FOR FILING INSTRUCTIONSJ R MORRIS
VICE PRESIDENT
CATAWBA NUCLEAR STATION
BY:
K S BYERS CN01RC KSB/RJA
Duke DUKE ENERGY CORPORATIONCatawba Nuclear Station
Energy® 4800 Concord Rd.York, SC 29745
March 19, 2012
Re: Catawba Nuclear StationSelected Licensee Commitments ManualRevision Dates: 10/24/2011, 02/20/2012, and 03/5/2012
Attached are revisions to the Catawba Nuclear Station Selected LicenseeCommitments Manual. Please remove and replace the following pages:
REMOVE THESE PAGES INSERT THESE PAGES
LIST OF EFFECTIVE SECTIONS
Pages 1 through 4Revision 48
Pages 1 through 4Revision 49
TAB 16.0 - TABLE OF CONTENTS
Pages i through vRevision 12
Pages i through vRevision 13
TAB 16.5
SLC 16.5-1Revision 1
SLC 16.5-9Revision.0
SLC 16.7-9Revision 5
SLC 16.7-10Revision 3
SLC 16.8-2Revision 1
TAB 16.7
SLC 16.5-1Revision 2
SLC 16.5-9Revision 1
SLC 16.7-9Revision 6
SLC 16.7-10Revision 4
SLC 16.8-2Revision 2
TAB 16.8
www. duke-energy. corn
TAB 16.9SLC 16.9-19 SLC 16.9-19Revision 2 Revision 3
SLC 16.9-26Revision 0
TAB 16.11SLC 16.11-7 SLC 16.11-7Revision 5 Revision 6
If you have any questions concerning the contents of this package update,contact Kristi Byers at (803)701-3758.
Randy HartManager, Regulatory Compliance
Attachment
LIST OF EFFECTIVE SECTIONS
SECTION
TABLE OF CONTENTS
16.1
REVISION NUMBER
12
1
REVISION DATE
06/08/09
08/27/08
16.2
16.3
16.5-1
16.5-2
16.5-3
16.5-4
16.5-5
16.5-6
16.5-7
16.5-8
16.5-9
16.5-10
16.6-1
16.6-2
16.6-3
16.6-4
16.6-5
16.7-1
16.7-2
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08/21/09
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02/20/12
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10/09/02
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02/03/11
02/03/11
08/21/09
08/21/09
Catawba Units 1 and 2 Page 1 Revision 49
LIST OF EFFECTIVE SECTIONS
SECTION
16.7-6
16.7-7
16.7-8
16.7-9
16.7-10
16.7-11
16.7-12
16.7-13
16.7-14
16.7-15
16.7-16
16.8-1
16.8-2
16.8-3
16.8-4
16.8-5
16.9-1
16.9-2
16.9-3
16.9-4
16.9-5
16.9-6
16.9-7
16.9-8
REVISION NUMBER
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01
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5
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REVISION DATE
08/21/09
08/21/09
08/21/09
02/20/12
10/24/11
08/21/09
08/21/09
08/21/09
08/21/09
08/21/09
06/08/09
08/21/09
02/20/12
10/24/06
11/05/07
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10/24/11
10/24/11
02/03/11
08/21/09
06/23/10
08/21/09
08/21/09
08/21/09
Catawba Units 1 and 2 Page 2 Revision 49
LIST OF EFFECTIVE SECTIONS
SECTION
16.9-9
16.9-10
16.9-11
16.9-12
16.9-13
16.9-14
16.9-15
16.9-16
16.9-17
16.9-18
16.9-19
16.9-20
16.9-21
16.9-22
16.9-23
16.9-24
16.9-25
16.9-26
16.10-1
16.10-2
16.10-3
16.11-1
16.11-2
16.11-3
REVISION NUMBER
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REVISION DATE
08/21/09
08/21/09
08/21/09
08/21/09
08/21/09
09/25/06
08/21/09
08/21/09
10/09/02
10/09/02
02/20/12
10/09/02
10/09/02
08/21/09
10/24/11
10/24/06
08/21/09
03/05/12
08/21/09
10/24/06
08/21/09
10/09/02
06/23/10
10/09/02
Catawba Units 1 and 2 Page 3 Revision 49
LIST OF EFFECTIVE SECTIONS
SECTION
16.11-4
16.11-5
16.11-6
16.11-7
16.11-8
16.11-9
16.11-10
16.11-11
16.11-12
16.11-13
16.11-14
16.11-15
16.11-16
16.11-17
16.11-18
16.11-19
16.11-20
16.11-21
16.12-1
16.13-1
16.13-2
16.13-3
16.13-4
REVISION NUMBER
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REVISION DATE
08/21/09
10/09/02
06/08/09
10/24/11
10/09/02
10/09/02
08/21/09
03/20/03
10/09/02
10/09/02
10/09/02
10/09/02
10/24/11
10/09/02
08/21/09
10/09/02
08/21/09
10/09/02
10/09/02
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10/09/02
Catawba Units 1 and 2 PPage 4 Revision 49
TABLE OF CONTENTS
SECTION TITLE PAGE
16.1 INTRODUCTION 16.1-1
16.2 APPLICABILITY 16.2-1
16.3 DEFINITIONS 16.3-1
16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS
16.5 COMMITMENTS RELATED TO REACTOR COOLANT SYSTEM
16.5-1 Reduced Inventory and Mid-Loop Operation with Irradiated 16.5-1-1Fuel in the Core
16.5-2 Deleted
16.5-3 Chemistry 16.5-3-1
16.5-4 Pressurizer 16.5-4-1
16.5-5 Structural Integrity 16.5-5-1
16.5-6 Reactor Coolant System Vents 16.5-6-1
16.5-7 Steam Generator Pressure/Temperature Limitation 16.5-7-1
16.5-8 Reactor Pressure Vessel (RPV) Head Inspection 16.5-8-1
16.5-9 Operation with Irradiated Fuel in the Core with Steam 16.5-9-1Generator (SGý Nozzle Dams Installed or Cold LegOpening > 1 in
16.5-10 Deleted
16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES
16.6-1 Containment Sump 16.6-1-1
16.6-2 Deleted
16.6-3 Inlet Door Position Monitoring System 16.6-3-1
16.6-4 Chlorine Detectors and Associated Circuitry 16.6-4-1
16.6-5 Residual Heat Removal/Containment Spray Sump Pump 16.6-5-1Interlock
Catawba Units 1 and 2 Revision 13
TABLE OF CONTENTS
SECTION TITLE PAGE
16.7 COMMITMENTS RELATED TO INSTRUMENTATION
16.7-1 ATWS Mitigation System Actuation Circuitry (AMSAC) 16.7-1-1
16.7-2 Seismic Instrumentation 16.7-2-1
16.7-3 Meteorological Instrumentation 16.7-3-1
16.7-4 Loose-Part Detection System 16.7-4-1
16.7-5 Turbine Overspeed Protection 16.7-5-1
16.7-6 RN Discharge Instrumentation 16.7-6-1
16.7-7 Movable Incore Detectors 16.7-7-1
16.7-8 Groundwater Level 16.7-8-1
16.7-9 Standby Shutdown System 16.7-9-1
16.7-10 Radiation Monitoring for Plant Operations 16.7-10-1
16.7-11 Position Indication System - Shutdown 16.7-11-1
16.7-12 Position Indication System - Test Exceptions 16.7-12-1
16.7-13 Auxiliary Feedwater (AFW) Pump Turbine Steam Supply 16.7-13-1Piping Temperature Monitoring System
16.7-14 Trip of All Main Feedwater Pumps Turbine Trip 16.7-14-1Instrumentation
16.7-15 Hydrogen Monitors 16.7-15-1
16.7-16 Reactor Trip Breaker and Solid State Protection System 16.7-16-1(SSPS) Logic Train Out of Service Commitments
16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS
16.8-1 Containment Penetration Conductor Overcurrent Protectivel 6.8-1-1Devices
16.8-2 230 kV Switchyard Systems 16.8-2-1
16.8-3 230 kV Switchyard 125 VDC Power System 16.8-3-1
16.8-4 6900 V Standby Transformers 16.8-4-1
Catawba Units 1 and 2 ii Revision 13
TABLE OF CONTENTS
SECTION TITLE PAGE
16.8-5 Diesel Generator Supplemental Testing Requirements 16.8-5-1
16.9 COMMITMENTS RELATED TO AUXILIARY SYSTEMS
16.9-1 Fire Suppression Water Systems 16.9-1-1
16.9-2 Spray and/or Sprinkler Systems 16.9-2-1
16.9-3 CO2 Systems 16.9-3-1
16.9-4 Fire Hose Stations 16.9-4-1
16.9-5 Fire Rated Assemblies 16.9-5-1
16.9-6 Fire Detection Instrumentation 16.9-6-1
16.9-7 Boration Systems Flow Path - Shutdown 16.9-7-1
16.9-8 Boration Systems Flow Paths - Operating 16.9-8-1
16.9-9 Boration Systems Pumps - Shutdown 16.9-9-1
16.9-10 Boration Systems Charging Pumps - Operating 16.9-10-1
16.9-11 Boration Systems Borated Water Source - Shutdown 16.9-11-1
16.9-12 Boration Systems Borated Water Sources - Operating 16.9-12-1
16.9-13 Snubbers 16.9-13-1
16.9-14 Lake Wylie Water Temperature 16.9-14-1
16.9-15 Auxiliary Building Filtered Exhaust System Filter Cooling 16.9-15-1Bypass Valves
16.9-16 Fuel Handling Ventilation Exhaust System Filter Cooling 16.9-16-1Bypass Valves
16.9-17 Refueling Operations - Decay Time 16.9-17-1
16.9-18 Refueling Operations - Communications 16.9-18-1
16.9-19 Refueling Operations - Manipulator Crane 16.9-19-1
16.9-20 Refueling Operations - Crane Travel - Spent Fuel Storage 16.9-20-1Pool Building
16.9-21 Refueling Operations - Storage Pool Water Level 16.9-21-1
Catawba Units 1 and 2 iii Revision 13
TABLE OF CONTENTS
SECTION TITLE PAGE
16.9-22 Control Room Area Ventilation System - Intake Alarms 16.9-22-1
16.9-23 Fire Hydrants 16.9-23-1
16.9-24 Alternate Cooling for Charging Pumps 16.9-24-1
16.9-25 Tornado Isolation Dampers 16.9-25-1
16.9-26 Commitments Associated With Movement of Non-Recentlyl6.9-26-1Irradiated Fuel Assemblies
16.10 COMMITMENTS RELATED TO STEAM AND POWER CONVERSIONSYSTEMS
16.10-1 Steam Vent to Atmosphere 16.10-1-1
16.10-2 Condenser Circulating Water System 16.10-2-1
16.10-3 Auxiliary Feedwater (AFW) Flow Control Valve Air 16.10-3-1Accumulators
16.11 COMMITMENTS RELATED TO RADIOACTIVE WASTE MANAGEMENT
16.11-1 Liquid Effluents 16.11-1-1
16.11-2 Radioactive Liquid Effluent Monitoring Instrumentation 16.11-2-1
16.11-3 Dose 16.11-3-1
16.11-4 Liquid Radwaste Treatment System 16.11-4-1
16.11-5 Chemical Treatment Ponds 16.11-5-1
16.11-6 Gaseous Effluents 16.11-6-1
16.11-7 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7-1
16.11-8 Dose - Noble Gases 16.11-8-1
16.11-9 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive 16.11-9-1Material in Particulate Form
16.11-10 Gaseous Radwaste Treatment System 16.11-10-1
16.11-11 Solid Radioactive Wastes 16.11-11-1
16.11-12 Total Dose 16.11-12-1
Catawba Units 1 and 2 iv Revision 13
TABLE OF CONTENTS
SECTION
16.11-13
16.11-14
16.11-15
16.11-16
16.11-17
16.11-18
16.11-19
16.11-20
16.11-21
16.12
16.12-1
16.13
16.13-1
16.13-2
16.13-3
16.13-4
TITLE
Monitoring Program
Land Use Census
Interlaboratory Comparison Program
Annual Radiological Environmental Operating Report andAnnual Radioactive Effluent Release Report
Liquid Holdup Tanks
Explosive Gas Mixture
Gas Storage Tanks
Explosive Gas Monitoring Instrumentation
Major Changes to Liquid, Gaseous, and Solid RadwasteTreatment Systems
COMMITMENTS RELATED TO RADIATION PROTECTION
Sealed Source Contamination
COMMITMENTS RELATED TO CONDUCT OF OPERATIONS
Fire Brigade
Deleted
Deleted
Minimum Station Staffing Requirements
PAGE
16.11-13-1
16.11-14-1
16.11-15-1
16.11-16-1
16.11-17-1
16.11-18-1
16.11-19-1
16.11-20-1
16.11-21-1
16.12-1-1
16.13-1-1
16.13-4-1
Catawba Units 1 and 2 V Revision 13
Reduced Inventory and Mid-Loop Operation with Irradiated Fuel in the Core16.5-1
16.5 REACTOR COOLANT SYSTEM
16.5-1 Reduced Inventory and Mid-Loop Operation with Irradiated Fuel in the Core
COMMITMENT Two independent trains of reactor coolant system level instrumentsare required. These instruments shall have independent transmittersand shall not include the reactor coolant system sightglass (NCLG-6450) or tygon tubing.
AND
N I~C~-------------------------- I. l--•'b.----------------------------------------1. Final disconnection of the last two core exit
thermocouples shall occur no sooner than 2 hours priorto reactor vessel head removal.
2. Reconnection of at least two thermocouples shall occurwithin 2 hours after reinstalling the reactor vessel head.
3. The total time without thermocouple indication shall notexceed 12 hours.
Whenever the reactor vessel head is installed, two core exitthermocouples shall be maintained operating with temporary highalarms set at 140OF and monitored.
AND
Four power sources shall be available, two offsite sources and twodiesel generators.
AND
Two independent makeup paths of borated water shall be available,consisting of:
One centrifugal charging pump or one safety injection pumpas required per SLC 16.9-7 and 16.9-9.
AND
One additional centrifugal charging pump or safety injectionpump on the opposite train of the first required makeup path.
AND
(continued)
Catawba Units 1 and 2 16.5-1-1 Revision 2
Reduced Inventory and Mid-Loop Operation with Irradiated Fuel in the Core16.5-1
COMMITMENT (continued)
------------------------- NOTE -----------.-.-----......-------...The number of open containment penetrations shall be limited suchthat the penetrations can be closed prior to the onset of core boilingupon loss of residual heat removal.
Containment closure shall be established. Containment closure isverified by the performance of PT/1/(2)/A/4200/002C&I, ContainmentClosure Verification, with penetrations not verified acceptable,administratively controlled per OP/O/A/6100/014, Penetration ControlFor Modes 5 and 6.
AND
The reactor has been subcritical for at least 7 days or Engineeringhas provided a required subcritical time based on plant operatinghistory and actual reduced reactor coolant system level.
AND
Operation in a mid-loop condition shall only occur during low decayheat conditions (after refueling).
Whenever irradiated fuel is in the reactor vessel and reactor coolantsystem wide range level is < 16%.
APPLICABILITY:
Catawba Units 1 and 2 16.5-1-2 Revision 2
Reduced Inventory and Mid-Loop Operation with Irradiated Fuel in the Core16.5-1
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. One or more A.1 Initiate action to restore ImmediatelyCOMMITMENT(S) not compliance withmet. COMMITMENT(S).
AND
A.2 Contact station Immediatelymanagement for additionalguidance.
B. Primary method of B.1 Monitor and record Once per 15 minutesmonitoring core exit thermocouplethermocouples temperatures on the Incoreunavailable. Instrument Panel.
TESTING REQUIREMENTS None
BASES Generic Letter 88-17 and NUREG-1410 involve concerns associated with aloss of residual heat removal. Numerous events have occurred in theindustry that resulted in a loss of residual heat removal during reducedinventory operation. This is of great concern due to the potential forsubstantial core damage occurring in a relatively short time period.
This Selected Licensee Commitment depicts those commitments which areextremely important to nuclear safety, however, are not presently covered byTechnical Specifications.
The basis for the requirement for the reactor to be subcritical for 7 days is toensure 2.5 hours until the core is uncovered following a loss of decay heatremoval when at mid-loop operation (Refs. 10, 11).
REFERENCES 1. Generic Letter 88-17, "Loss of Decay Heat Removal."
2. NUREG-1410, "Loss of Vital AC Power and Residual HeatRemoval during Mid-Loop Operation at Vogtle."
3. Nuclear System Directive 403, "Shutdown Risk Management(Modes 4, 5, 6, and No-Mode) per 10 CFR 50.65 (a)(4)."
Catawba Units 1 and 2 16.5-1-3 Revision 2
Reduced Inventory and Mid-Loop Operation with Irradiated Fuel in the Core16.5-1
REFERENCES (continued)
4. OP/1 (2)/A/6150/06, "Draining the Reactor Coolant System."
5. Catawba Nuclear Station Technical Specifications.
6. Catawba Design Basis Specification for the Reactor Coolant(NC) System.
7. Oconee Nuclear Station Selected Licensee Commitment16.5.3.
8. Work Processes Manual, Sections 602, "OutageManagement," and 603, "Unit Trip Forced OutageManagement."
9. Catawba Nuclear Station responses to Generic Letter 88-17dated January 3, 1989.
10. Design Study CNDS-0242, "Catawba and McGuire NuclearStations, Shutdown by Decay Heat Level Before Mid-LoopOperation."
11. DPC-1552-08-00-0023, "Loss of Decay Heat Removal (G.L.88-17)."
Catawba Units 1 and 2 16.5-1-4 Revision 2
Operation with Irradiated Fuel in the Core with SG Nozzle Dams Installedor Cold Leg Opening > 1 in2
16.5-916.5 REACTOR COOLANT SYSTEM
16.5-9 Operation with Irradiated Fuel in the Core with Steam Generator (SG) Nozzle DamsInstalled or Cold Leg Opening > 1 in2
COMMITMENT
APPLICABILITY:
The Reactor Coolant System (RCS) shall be properly vented whenSG nozzle dams are in use or the, RCS cold leg is open > 1 in2.
Whenever irradiated fuel is in the reactor vessel.
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. COMMITMENT(S) not A.1 Initiate action to restore Immediatelymet. compliance with
COMMITMENT(S).
TESTING REQUIREMENTS None
BASES Generic Letter 88-17 and NUREG-1 410 involve concerns associated with aloss of residual heat removal. Numerous events have occurred in theindustry that resulted in a loss of residual heat removal. This is of greatconcern due to the potential for substantial core damage occurring in arelatively short time period.
The vent path is provided to address Expeditious Action (7) of Generic Letter88-17. The vent path is provided to assure that the nozzle dams are notdislodged due to pressurization that could result on a loss of decay heatremoval event resulting in core boiling. In addition, in the absence of asufficient vent path, pressurization in combination with cold leg openingscould allow water to be ejected from the vessel and lead to core uncovery.
This Selected Licensee Commitment depicts those commitments which areextremely important to nuclear safety, however, are not presently covered byTechnical Specifications.
The vent path may be satisfied by:
Catawba Units 1 and 2 16.5-9-1 Revision 1
Operation with Irradiated Fuel in the Core with SG Nozzle Dams Installedor Cold Leg Opening > 1 in2
16.5-9BASES (continued)
1 . On the vented loop, no hot leg nozzle dam installed
AND
Removal of either of the following:
a. A hot leg diaphragm and manway
OR
b. A cold leg diaphragm and manway
OR
2. Reactor vessel head is removed.
REFERENCES 1. Generic Letter 88-17, "Loss of Decay Heat Removal."
2. NUREG-1410, "Loss of Vital AC Power and Residual HeatRemoval during Mid-Loop Operation at Vogtle."
3. Nuclear System Directive 403, "Shutdown Risk Management(Modes 4, 5, 6, and No-Mode) per 10 CFR 50.65 (a)(4)."
4. Catawba Design Basis Specification for the Reactor Coolant(NC) System.
5. Catawba Nuclear Station responses to Generic Letter 88-17,dated January 3, 1989 and February 2, 1989.
6. DPC-1552.08-00-0017, "Analysis of Potential NC System VentPaths During Nozzle Seal Dam Installation and Use."
7. NUREG-1449, "Shutdown and Low-Power Operation atCommercial Nuclear Power Plants in the United States."
8. NRC letter to Hal Tucker, "Comments on Expeditious Actionand Notice of Audit on Generic Letter 88-17, McGuire andCatawba Nuclear Stations, Units I and 2," dated May 17,1989.
Catawba Units 1 and 2 16.5-9-2. Revision 1
SSS16.7-9
16.7 INSTRUMENTATION
16.7-9 Standby Shutdown System (SSS)
COMMITMENT
APPLICABILITY:
The SSS shall be FUNCTIONAL.
MODES 1, 2, and 3.
REMEDIAL ACTIONS
-NOTE-SLC 16.2.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME
A. SSS non-functional. A.1 Restore SSS to 7 daysFUNCTIONAL status.
B. Total accumulative B.1 Declare the standby ImmediatelyLEAKAGE from makeup pump non-unidentified LEAKAGE, functional and enteridentified LEAKAGE, Condition A.and reactor coolantpump seal LEAKAGE >20 gpm.
C. More than one cell in a C.1 Enter Condition A. Immediately24-Volt battery bank is <1.36 volts on floatcharge with no othercells jumpered.
D. Required Action and D.1 Be in MODE 3. 6 hoursassociated CompletionTime of Condition A not ANDmet.
D.2 Be in MODE4. 12 hours
Catawba Units I and 2 16.7-9-1 Revision 6
SSS16.7-9
TESTING REQUIREMENTS
TEST FREQUENCY
TR 16.7-9-1 Verify that the electrolyte level of each SSS diesel 7 daysstarting 24-Volt battery is > the low mark and < the highmark.
TR 16.7-9-2 Verify that the overall SSS diesel starting 24-Volt battery 7 daysvoltage is > 24 volts on float charge.
TR 16.7-9-3 Verify that the requirements of SLC 16.9-21 are met and 7 daysthe boron concentration in the storage pool is > theminimum specified in the COLR.
TR 16.7-9-4 Verify the fuel level in the SSS diesel generator fuel 31 daysstorage tank is > 67 inches.
TR 16.7-9-5 Verify the SSS diesel generator starts from ambient 31 daysconditions and operates for > 30 minutes at > 700 kW.
TR 16.7-9-6 Verify that the electrolyte level of each SSS 250/125-Volt 31 daysbattery is above the plates.
TR 16.7-9-7 Verify the total SSS 250/125-Volt battery terminal voltage 31 daysis > 258/129 volts on float charge.
TR 16.7-9-8 Perform CHANNEL CHECK of each SSS 31 daysinstrumentation device.
TR 16.7-9-9 Verify the fuel oil properties of new and stored fuel oil for In accordance withthe SSS diesel generator are tested in accordance with, the Diesel Fuel Oiland maintained within the limits of, the Diesel Fuel Oil Testing ProgramTesting Program.
TR 16.7-9-10 Verify that the SSS diesel starting 24-Volt battery 92 days
individual cell voltage is > 1.36 volts on float charge.
(continued)
Catawba Units 1 and 2 16.7-9-2 Revision 6
SSS16.7-9
TESTING REQUIREMENTS (continued)
TEST FREQUENCY
TR 16.7-9-11 Verify that the Standby Makeup Pump's developed head 92 daysat the test flow point is > the required developed head, inaccordance with the Inservice Testing Program.
TR 16.7-9-12 Verify that the specific gravity of the SSS 250/125-Volt 92 daysbattery is appropriate for continued service of the battery.
TR 16.7-9-13 Subject the SSS diesel generator to an inspection in 18 monthsaccordance with procedures prepared in conjunction withits manufacturer's recommendations for the class ofservice.
TR 16.7-9-14 Verify that the SSS diesel starting 24-Volt batteries, cell 18 monthsplates, and battery racks show no visual indication ofphysical damage or abnormal deterioration.
TR 16.7-9-15 Verify that the SSS diesel starting 24-Volt battery-to- 18 monthsbattery and terminal connections are clean, tight, andfree of corrosion.
TR 16.7-9-16 Verify that the SSS 250/125-Volt batteries, cell plates, 18 monthsand battery racks show no visual indications of physicaldamage or abnormal deterioration.
TR 16.7-9-17 Verify that the SSS 250/125-Volt battery-to-battery and 18 monthsterminal connections are clean, tight, free of corrosion,and coated with anti-corrosion material.
TR 16.7-9-18 Verify that the steam turbine driven auxiliary feedwater 18 monthspump and controls from the Standby Shutdown Facilityfunction as designed from the SSS.
TR 16.7-9-19 Perform CHANNEL CALIBRATION of each SSS 18 months
instrumentation device.
(continued)
Catawba Units 1 and 2 16.7-9-3 Revision 6
SSS16.7-9
TESTING REQUIREMENTS (continued)
TEST FREQUENCY
TR 16.7-9-20 Verify proper installation of pressurizer insulation. 18 months
TR 16.7-9-21 Verify pressurizer heaters powered from the SSS have a 18 monthscapacity of > 70 kW.
BASES The SSS is designed to mitigate the consequences of certain postulatedfire, security, and station blackout incidents by providing capability tomaintain MODE 3 conditions and by controlling and monitoring vitalsystems from locations external to the main control room. This capabilityis consistent with the requirements of 10 CFR Part 50, Appendix R,NUREG-0800, Section 9.5-1, and Appendix A to Branch TechnicalPosition APSCB 9.5-1.
The TESTING REQUIREMENTS ensure that the SSS systems andcomponents are capable of performing their intended functions. Therequired level in the SSS diesel generator fuel storage tank ensuressufficient fuel for 72 hours uninterrupted operation. It is assumed that,within 72 hours, either offsite power can be restored or additional fuel canbe added to the storage tank.
Although the standby makeup pump is not nuclear safety related and wasnot designed according to ASME Code requirements, it is tested quarterlyto ensure its FUNCTIONALITY. The TESTING REQUIREMENTconcerning the standby makeup pump water supply ensures that anadequate water volume is available to supply the pump continuously for72 hours.
Total accumulative. LEAKAGE is calculated in the NC System LeakageCalculation procedure as identified + unidentified + seal leakoff(References 2 and 3). The REMEDIAL ACTION limit of 20 gpm totalaccumulative LEAKAGE provides additional margin to allow forinstrument inaccuracy, and for the predicted increase in seal leakoff ratedue to heatup of the reactor coolant pump seal injection water supplytemperature following the SSS event (due to spent fuel pool heatup).Following the increase in seal injection temperature, the standby makeuppump flow of 26 gpm is sufficient to provide in excess of this totalaccumulative LEAKAGE, thereby assuring that reactor coolant systeminventory is maintained at MODE 3 conditions. The supporting evaluationis provided in CNC-1223.04-00-0072 (Ref. 4).
A visual inspection of the diesel starting 24-volt batteries, cell plates, andbattery racks provides an indication of physical damage or abnormaldeterioration that could potentially degrade battery performance. Since
Catawba Units 1 and 2 16.7-9-4 Revision 6
SSS16.7-9
BASES (continued)
the battery cell jars are not transparent, a direct visual inspection of thecell plates cannot be performed. Instead, the cell plates are inspected forphysical damage and abnormal deterioration by: 1) visually inspectingthe jar sides of each cell for excessive bowing and/or deformation, and 2)visually inspecting the electrolyte of each cell for abnormal appearance.
Verifying individual cell voltage while on float charge for the SSS dieselstarting 24-Volt batteries ensures that each cell is capable of supportingits intended function. Float charge is the condition in which the charger issupplying the continuous charge required to overcome the internal lossesof a battery (or battery cell) and maintain the battery (or battery cell) in afully charged state. The battery cell voltage limit of 1.36 volts isconsistent with the nominal design voltage of the battery and is based onthe manufacturer's recommended minimum float charge voltage for afully charged cell with adequate capacity. The battery is designed andsized with a capacity margin sufficient to allow up to one cell per batterybank to be fully degraded with a voltage < 1.36 volts assuming that nocells are jumpered out. The battery sizing calculations account for onedegraded cell per battery bank by assuming the degraded cells undergoa worst case polarity reversal during SSS diesel starting.
Verification of proper installation of pressurizer insulation ensures thatpressurizer heat losses during an SSS event do not exceed the capacityof the pressurizer heaters powered from the SSS.
Testing of the pressurizer heater capacity ensures the full capacity of theheaters is available to maintain a steam bubble in the pressurizer duringan SSS event.
REFERENCES 1. Letter from NRC to Gary R. Peterson, Duke, Issuance ofImproved Technical Specifications Amendments for Catawba,September 30, 1998.
2. PT/1(2)/A/4150/001 D, NC System Leakage Calculation.
3. PT/1 (2)/N4150/001 1, Manual NC Leakage Calculation.
4. CNC-1223.04-00-0072, Reactor Coolant Pumps No. 1 SealLeakoff Annunciator Alarm Setpoint for Unit 1 and Unit 2.
5. CNS-1560.SS-00-0001, Design Basis Specification for theStandby Shutdown Facility.
6. Catawba Technical Specification Amendments 206/200, July10, 2003.
7. Catawba UFSAR, Section 18.2.4.
Catawba Units 1 and 2 16.7-9-5 Revision 6
SSS16.7-9
REFERENCES (continued)
8. Catawba License Renewal Commitments, CNS-1274.00-00-0016, Section 4.5.
Catawba Units 1 and 2 16.7-9-6 Revision 6
Radiation Monitoring for Plant Operations16.7-10
16.7 INSTRUMENTATION
16.7-10 Radiation Monitoring for Plant Operations
COMMITMENT
APPLICABILITY:
The radiation monitoring instrumentation channels for plant operationsshown in Table 16.7-10-1 shall be FUNCTIONAL.
As shown in Table 16.7-10-1.
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. One or more radiation A.1 Adjust the setpoint to 4 hoursmonitoring channels within the limit.Alarm/Trip setpoint forplant operations ORexceeding the valueshown in Table 16.7-10- A.2 Declare the channel non- 4 hours1. functional.
(continued)
Catawba Units 1 and 2 16.7-10-1 Revision 4
Radiation Monitoring for Plant Operations16.7-10
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
B. One Containment B.1 --------- NOTE-------Atmosphere - High In order to utilize RequiredGaseous Radioactivity Action B.1, the following(EMF-39 - Low Range) conditions must bechannel non-functional. satisfied:
1. The affected unit is inMODES 5 or 6.
2. EMF-36 isFUNCTIONAL and inservice for the affectedunit.
3. The Reactor CoolantSystem for the affectedunit has been vented.
4. Either the reactorvessel head is in place(bolts are not required),or if it is not in place,the lifting of heavyloads over the reactorvessel and themovement of irradiatedfuel assemblies withincontainment have beensuspended.
Restore the non-functional 12 hourschannel to FUNCTIONALstatus.
(continued)
Catawba Units 1 and 2 16.7-10-2 Revision 4
Radiation Monitoring for Plant Operations16.7-10
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
C. Required Action and C.1 Close the Containment Immediatelyassociated Completion Purge Exhaust SystemTime of Condition B not (CPES) valves.met.
OR
Required Action B. 1 notutilized.
D. One Control Room Air D.1 Initiate action to restore ImmediatelyIntake - Radiation Level non-functional channel(s)- High Gaseous to FUNCTIONAL status.Radioactivity (EMF-43A& B - Low Range) ANDchannel non-functionalin one or both control D.2 Ensure that one Control 1 hourroom intakes. Room Area Ventilation
System (CRAVS) train is inoperation.
E. One Fuel Storage Pool E.1 Provide a portable ImmediatelyArea - Criticality - continuous monitor withRadiation Level (1EMF- the same Alarm Setpoint in15, 2EMF-4) channel the fuel storage pool area.non-functional.
AND
E.2.1 Restore non-functional 30 daysmonitor to FUNCTIONALstatus.
OR
E.2.2 Suspend all operations 30 daysinvolving fuel movement inthe fuel building.
(continued)
Catawba Units 1 and 2 16.7-10-3 Revision 4
Radiation Monitoring for Plant Operations16.7-10
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
F. One Fuel Storage Pool F.1.1 Initiate action to restore ImmediatelyArea - High Gaseous non-functional channel toRadioactivity (EMF-42) FUNCTIONAL status.channel non-functional.
AND
F.1.2 --------- NOTE ------Only applicable during fuelhandling operations in thefuel building.
Ensure one Fuel Handling ImmediatelyVentilation Exhaust System(FHVES) train is inoperation and all operatingFHVES trains are in thefiltered mode.
OR
F.2 Suspend all operations Immediatelyinvolving fuel movement inthe fuel building.
G. One Auxiliary Building G.1 Ensure one Auxiliary ImmediatelyVentilation - High Building Filtered VentilationGaseous Radioactivity Exhaust System (ABFVES)(EMF-41) channel non- train is OPERABLE and infunctional. operation and all operating
ABFVES trains are in thefiltered mode.
(continued)
Catawba Units 1 and 2 16.7-10-4 . Revision 4
Radiation Monitoring for Plant Operations16.7-10
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
H. One Component H.1 Collect and analyze grab Once per 12 hoursCooling Water System samples for principal(EMF-46A & B) channel gamma emitters (listed innon-functional. Table 16.11-1-1, NOTE 3)
at a lower limit of detectionof no more than 5x10 7
p.Ci/ml.
AND
H.2 Restore non-functional 30 dayschannel to FUNCTIONALstatus.
One or more N-16 1.1 Ensure that the Condenser ImmediatelyLeakage Monitor (EMF- Evacuation System Noble71, 72, 73, & 74) Gas Activity Monitor (EMF-channels non-functional. 33) is FUNCTIONAL and in
operation.
OR
1.2 Ensure that Required ImmediatelyActions are met per SLC16.11-7 if the CondenserEvacuation System NobleGas Activity Monitor (EMF-33) is non-functional or notin operation.
Catawba Units 1 and 2 16.7-10-5 Revision 4
Radiation Monitoring for Plant Operations16.7-10
TESTING REQUIREMENTS
Refer to Table 16.7-10-1 to determine which TRs apply for each Radiation Monitoring for PlantOperations channel.
TEST FREQUENCY
TR 16.7-10-1 Perform CHANNEL CHECK. 12 hours
TR 16.7-10-2 Perform CHANNEL OPERATIONAL TEST. 9 months
TR 16.7-10-3 Perform CHANNEL CALIBRATION. 18 months
Catawba Units 1 and 2 16.7-10-6 Revision 4
Radiation Monitoring for Plant Operations16.7-10
Table 16.7-10-1
Radiation Monitoring Instrumentation for Plant Operations
MONITOR APPLICABLE REQUIRED ALARM/TRIP TESTINGMODES CHANNELS SETPOINT REQUIREMENTS
1. Containment Atmosphere - 1,2, 3,4, 5,6 1 Note (a) TR 16.7-10-1High Gaseous TR 16.7-10-2Radioactivity TR 16.7-10-3(EMF-39 - Low Range)
2. Fuel Storage Pool Areas - With irradiated 1 1.7 x 10i' pCi/mi TR 16.7-10-1High Gaseous fuel in the fuel TR 16.7-10-2Radioactivity storage pool TR 16.7-10-3(EMF-42) areas
3. Fuel Storage Pool Areas - With fuel in the < 15 mR/h TR 16.7-10-1Criticality - Radiation Level fuel storage pool TR 16.7-10-2(Fuel Bridge - 1 EMF-1 5, areas TR 16.7-10-32EMF-4)
4. Control Room Air Intake - At all times 2 (1/intake) < 1.7 x 10.4 ýLCi/ml TR 16.7-10-1Radiation Level - High TR 16.7-10-2Gaseous Radioactivity TR 16.7-10-3(EMF-43A & B - LowRange)
5. Auxiliary Building 1, 2, 3, 4 1 1.7 x 10-4 pLCi/ml TR 16.7-10-1Ventilation - High Gaseous TR 16.7-10-2Radioactivity TR 16.7-10-3(EMF-41)
6. Component Cooling Water At all times 1(b) < 1 x 10-3 jiCi/ml TR 16.7-10-1
System TR 16.7-10-2(EMF-46A & B) TR 16.7-10-3
7. N-16 Leakage Monitor 1(40-100% 4 (1/steamline) Note (c) TR 16.7-10-1(EMF-71, 72, 73, & 74) reactor power) TR 16.7-10-2
TR 16.7-10-3
Catawba Units 1 and 2 16.7-10-7 Revision 4
Radiation Monitoring for Plant Operations16.7-10
Table 16.7-10-1 Notes
(a) When venting or purging from containment to the atmosphere, the trip setpoint shall not exceed the equivalent limits ofSLC 16.11-6 in accordance with the methodology and parameters in the ODCM. When not venting or purging in Modes 5or 6, the alarm setpoint concentration (MCi/ml) shall be such that the actual submersion dose rate would not exceed 5mR/hr without alarm. When not venting or purging in Modes 1 through 4, the alarm setpoint shall be no more than 3times the containment atmosphere activity as indicated by the radiation monitor.
(b) For EMF-46A & B: The EMF monitor associated with the operating Component Cooling Water System train shall beFUNCTIONAL. This requirement is based on the existence of an interlock which blocks the EMF loss of flow alarm frombeing received in the control room when the associated train pump motor(s) are not running.
(c) The setpoint is as required by the primary to secondary leak rate monitoring program.
Catawba Units 1 and 2 16.7-10-8 Revision 4
Radiation Monitoring for Plant Operations16.7-10
BASES The FUNCTIONALITY of the radiation monitoring instrumentation forplant operations ensures that: (1) the associated action will be initiatedwhen the radiation level monitored by each channel or combinationthereof reaches its setpoint, (2) the specified coincidence logic ismaintained, and (3) sufficient redundancy is maintained to permit achannel to be out of service for testing or maintenance. The radiationmonitors for plant operations senses radiation levels in selected plantsystems and locations and determines whether or not predeterminedlimits are being exceeded. The radiation monitors send actuation signalsto initiate alarms or automatic isolation action and actuation of emergencyexhaust or ventilation systems. Some of the final actuations aredependent on plant condition in addition to the actuation signals from theradiation monitors.
Operation of the Component Cooling Water (CCW) System Train A withthe Train A Radiation Monitoring System (EMF) monitor non-functionaland relying on the Train B EMF monitor for detection of radioactivity is notpermissible. Likewise, operation of the CCW System Train B with theTrain B EMF monitor non-functional and relying on the Train A EMFmonitor for detection of radioactivity is not permissible. This is due to theinterlock between the EMF monitor low-flow alarm and the operation ofthe CCW System pump motors on the same train. The EMF monitor inthe operating CCW System pump train must be FUNCTIONAL, or thecompensatory measures taken as specified.
Initiation of the Containment Purge Exhaust System (CPES) with EMF-39non-functional is not permissible. The basis for Required Action B.1 is toallow the continued operation of the CPES with EMF-39 initiallyFUNCTIONAL. Continued operation of the CPES is contingent upon theability of the affected unit to meet the requirements as noted in RequiredAction B.1.
REFERENCES 1. Letter from NRC to Gary R. Peterson, Duke, Issuance ofImproved Technical Specifications Amendments for Catawba,September 30, 1998.
. . Catawba Units 1 and 2 16.7-10-9 Revision 4
230 kV Switchyard Systems16.8-2
16.8 ELECTRICAL POWER SYSTEMS
16.8-2 230 kV Switchyard Systems
COMMITMENT The following switchyard equipment shall be in its normalalignment:
a. Switchyard Unit 1 PCBs 14, 15, 17, and 18 including theirassociated manual disconnects, current transformers,interconnecting bus, and support structures (EBA system),
b. Switchyard Unit 2 PCBs 20, 21, 23, and 24 including theirassociated manual disconnects, current transformers,interconnecting bus, and support structures (EBA system),
c. Buslines 1A, 1B (from main stepup transformers toswitchyard unit PCBs), including their associated motoroperated disconnects, coupling capacitor voltagetransformers, interconnecting bus, and support structures(EBA system),
d. Buslines 2A, 2B (from main stepup transformers toswitchyard unit PCBs), including their associated motoroperated disconnects, coupling capacitor voltagetransformers, interconnecting bus, and support structures(EBA system),
e. Controls associated with the equipment above (EBE, EREsystems),
f. Protective relaying associated with the equipment above(EBD, ERD systems),
g. 480 VAC auxiliary power load centers STA for both units'Train A, STB for both units' Train B (EBI system), and
h. 125 VDC auxiliary power (EBH system) per SLC 16.8-3.
APPLICABILITY: At all times in accordance with Technical Specifications (allMODES) and Nuclear System Directive 403 (MODES 4, 5,6, and No-MODE).
Catawba Units 1 and 2 16.8-2-1 Revision 2
230 kV Switchyard Systems16.8-2
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. Switchyard equi 5ment A.1 Return switchyard In accordance withnot in normal equipment to normal the Electronic RiskCOMMITMENT COMMITMENT alignment. Assessment Toolalignment.
TESTING REQUIREMENTS None
BASES Effective implementation of the Maintenance Rule, 10 CFR 50.65,requires the continuous assessment of systems determined to berisk significant in the protection against core damage or radiationrelease. It has been determined through probabilistic riskassessment (PRA) numerical methods that switchyard systemsare risk significant from the standpoint of causing or being able torecover from Loss of Offsite Power events. This SLC serves twopurposes. It defines the risk significant portions of the switchyard.It also provides a method of tracking the switchyard systems forthe purposes of supporting 10 CFR 50.65.
REFERENCES 1. 10 CFR 50.65, Requirements for Monitoring the
Effectiveness of Maintenance at Nuclear Power Plants.
2. Deleted.
3. Deleted.
4. CNC-1535.00-00-0008, Severe Accident Analysis Report,CNS PRA Risk Significant SSCs for the MaintenanceRule.
5. CNS-010.01-EB-0001, Switchyard Design BasisSpecification.
6. Technical Specification sections 3.8.1 and 3.8.2, LCOs forAC Power Sources during Operating and ShutdownMODES.
7. Nuclear System Directive 403, "Shutdown RiskManagement (Modes 4, 5, 6, and No-Mode) per 10 CFR50.65 (a)(4)."
Catawba Units 1 and 2 16.8-2-2 Revision 2
Refueling Operations - Manipulator Crane16.9-19
16.9 AUXILIARY SYSTEMS
16.9-19 Refueling Operations - Manipulator Crane
COMMITMENT The reactor building manipulator crane and an auxiliary hoist shall be.used for movement of fuel assemblies or control rods and shall beFUNCTIONAL with:
a. The manipulator crane used for movement of fuel assemblieshaving:
1 ) A minimum capacity of 3250 pounds, and
2) An overload cutoff limit < 2900 pounds.
b. Auxiliary hoists used for latching, unlatching, and drag loadtesting of control rods having:
1) A minimum capacity of 1000 pounds, and
2) A load indicator which shall be used to preventapplying a lifting force > 600 pounds on the coreinternals.
During movement of fuel assemblies and control rods within thereactor vessel.
APPLICABILITY:
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. Manipulator crane or A.1 Suspend use of any non- Immediatelyauxiliary hoist non- functional manipulatorfunctional. crane or auxiliary hoist
from operations involvingthe movement of fuelassemblies and controlrods within the reactorvessel.
Catawba Units 1 and 2 16.9-19.-l Revision 3
Refueling Operations - Manipulator Crane16.9-19
TESTING REQUIREMENTS
TEST FREQUENCY
TR 16.9-19-1 Perform a load test of > 3250 pounds for each Within 30 daysmanipulator crane used for movement of fuel assemblies prior to movementwithin the reactor vessel and demonstrate an automatic of fuel assembliesload cutoff when crane load is > 2850 pounds. within the reactor
vessel
TR 16.9-19-2 Perform a load test of > 1000 pounds for each auxiliary Within 30 dayshoist and associated load indicator used for movement of prior to movementcontrol rods or control rod drag load testing within the of control rods orreactor vessel. control rod drag
load testing withinthe reactor vessel
BASES The FUNCTIONALITY requirements for the manipulator cranes ensure that:(1) manipulator cranes will be used for movement of control rods and fuelassemblies, (2) each crane has sufficient load capacity to lift a control rod orfuel assembly, and (3) the core internals and reactor vessel are protectedfrom excessive lifting force in the event they are inadvertently engagedduring lifting operations.
REFERENCES 1. Letter from NRC to Gary R. Peterson, Duke, Issuance ofImproved Technical Specifications Amendments for Catawba,September 30, 1998.
2. 10 CFR 50.59 Screen, "Changing the Testing RequirementFrequency of SLC 16.9-19", Action Request 366602, EricPace, September 8, 2011.
Catawba Units 1 and 2 16.9-19-2 Revision 3
Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies16.9-26
16.9 AUXILIARY SYSTEMS
16.9-26 Commitments Associated With Movement of Non-Recently Irradiated FuelAssemblies
COMMITMENT The following requirements governing containment closure and fuelbuilding closure shall be maintained to ensure defense-in-depth:
-------------------- NOTE ---------------------If containment closure or fuel building closure, as applicable, ishampered by an outage activity or by a loss of power, suitablecontingency actions providing an equivalent level of protection shallbe developed.
a. The equipment necessary to implement containment closure shallbe appropriately staged prior to maintaining any containmentpenetration open, including containment air lock doors. For thepurposes of this SLC, the containment equipment hatch is notconsidered a penetration that may be maintained open; therefore,it shall be maintained closed.
b. Hoses and cables running through an open containmentpenetration or containment air lock shall be configured to facilitaterapid removal in the event that containment closure is required.
c. The containment air lock may be open provided the followingconditions exist:
1. One door in each air lock shall be capable of being closed.2. Hoses and cables running through the air lock shall employ a
means to allow safe, quick disconnection or severance.3. The air lock door shall not be blocked in such a way that it
cannot be immediately closed. Protective covers used toprotect the air lock seals/doors or devices used to keep the airlock door open/supported do not violate this provision.
4. Personnel shall be available with the responsibility forimmediate closure of at least one air lock door or for closure ofan appropriate temporary door following containmentevacuation.
d. Other containment penetrations may be open provided thefollowing conditions exist:
(continued)
Catawba Units 1 and 2 16.9-26-1 Revision 0
Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies16.9-26
COMMITMENT (continued)
1. One valve in each open penetration shall be capable of beingclosed, or other methods to close the penetration(s) (i.e.,restrict air flow out of containment), such as a closure cover,shall be fabricated and available, along with the necessaryinstallation tools.
2. Personnel shall be available with the responsibility forimmediate closure of the penetration opening(s) following afuel handling accident inside containment.
e. The fuel building doors shall be maintained closed, except fornormal entry and exit, OR the Fuel Handling Ventilation ExhaustSystem (FHVES), with associated radiation release monitoring forthe release path, shall be available.
APPLICABILITY: During movement of non-recently irradiated fuel assemblies incontainment or in the fuel building, as applicable.
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. COMMITMENT not met. A.1 Suspend movement of Immediatelynon-recently irradiated fuelassemblies in containmentor in the fuel building, asapplicable.
AND
A.2 Restore compliance with Prior to resumingCOMMITMENT. movement of non-
recently irradiatedfuel assemblies incontainment or in thefuel building, asapplicable
TESTING REQUIREMENTS None
Catawba Units 1 and 2 16.9-26-2 Revision-0
Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies16.9-26
BASES This SLC formally documents and implements a portion of the regulatorycommitments made in Reference 1, approved by the NRC via Reference 2,and subsequently modified via Reference 3 and Reference 4. Thesecommitments were made as a means of providing additional defense-in-depth during movement of non-recently irradiated fuel assemblies incontainment or in the fuel building. The commitments concerning non-recently irradiated fuel movement with an open containment equipment hatchhave not been implemented in this SLC. Until such time that a methodologyis developed for complying with the commitments concerning non-recentlyirradiated fuel movement with an open containment equipment hatch, thehatch shall be maintained closed.
In the revised analysis utilizing the Alternative Source Term for a fuelhandling accident in containment, no credit is taken for containment integritywith respect to containment equipment hatch closure, containment air lockclosure, containment penetration closure, or filtration by the CPES prior torelease. For a postulated fuel handling accident within the fuel building', boththe fuel handling accident and the weir gate drop accident analyses wererevised. In the revised analyses, no credit is taken for filtration of the releaseby the FHVES.
The revised analyses confirmed that sufficient radioactive decay hasoccurred after 72 hours that certain existing controls are no longer necessaryto ensure that the consequences of a postulated fuel handling accidentremain within regulatory limits. The analysis demonstrated that a decayperiod of 19.5 days was sufficient to ensure that the consequences of a weirgate drop accident remain within regulatory limits.
Although not required by the accident analysis, these administrative controlswere committed to be put in place during the movement of non-recentlyirradiated fuel. If movement of irradiated fuel assemblies were to occur priorto the 72-hour decay period, the currently existing Technical Specificationcontrols would apply.
Administrative controls exist such that the weir gate will not be moved overspent fuel assemblies decayed less than 19.5 days.
For the purpose of this SLC, the definition of availability for the FHVES isbeing capable of performing its design basis functions as defined by theTechnical Specification 3.7.13, "Fuel Handling Ventilation Exhaust System(FHVES)" surveillance tests.
For the purpose of this SLC, the definition of an open containmentpenetration is a penetration that provides direct access from the containmentatmosphere to the outside environment.
Catawba Units 1 and 2 16.9-26-3 Revision 0
Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies16.9-26
REFERENCES 1. Letters from G.R. Peterson, Duke, to NRC, "ProposedAmendment for Partial Scope Implementation of the AlternateSource Term and Proposed Amendment to TechnicalSpecifications (TS) 3.7.10, Control Room Area VentilationSystem, TS 3.7.11, Control Room Area Chilled Water System,TS 3.7.13, Fuel Handling Ventilation Exhaust System, and TS3.9.3, Containment Penetrations", dated December 20, 2001,February 14, 2002, and March 26, 2002.
2. Letter from NRC to G.R. Peterson, Duke, LicenseAmendments 198 and 191 for Units 1 and 2, respectively,dated April 23, 2002.
3. Letter from J.R. Morris, Duke, to NRC, "Request to AmendTechnical Specification (TS) 3.7.10: Control Room AreaVentilation System", dated September 3, 2009.
4. Letter from NRC to J.R. Morris, Duke, License Amendments260 and 255 for Units 1 and 2, respectively, dated August 9,2010.
Catawba Units 1 and 2 16.9-26-4 Revision 0
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
16.11 RADIOLOGICAL EFFLUENTS CONTROLS
16.11-7 Radioactive Gaseous Effluent Monitoring Instrumentation
COMMITMENT The Radioactive Gaseous Effluent Monitoring Instrumentation channelsshown in Table 16.11-7-1 shall be FUNCTIONAL with their Alarm/TripSetpoints set to ensure that the limits of SLC 16.11-6 are not exceeded.
AND
The Alarm/Trip Setpoints of these channels shall be determined andadjusted in accordance with the methodology and parameters in theOFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: As shown in Table 16.11-7-1.
REMEDIAL ACTIONS
--------------------- NOTESeparate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME
A. One or more A.1 Suspend the release of ImmediatelyRadioactive Gaseous radioactive gaseousEffluent Monitoring effluents monitored by theInstrumentation affected channel(s).channel(s) Alarm/TripSetpoint less ORconservative thanrequired. A.2 Declare the channel(s) Immediately
non-functional.
B. One or more B.1 Enter the applicable ImmediatelyRadioactive Gaseous Conditions and RequiredEffluent Monitoring Actions specified in TableInstrumentation 16.11-7-1 for thechannel(s) non- channel(s).functional.
(continued)
Catawba Units 1 and 2 116.11-7-1 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
C. One channel non-functional.
C.,1 Verify that EMF-36 (LowRange) is FUNCTIONAL.
OR
C.2.1 Analyze two independentsamples of the tank'scontents.
AND
C.2.2 Perform independentverification of thedischarge line valving.
AND
0.2.3.1 Perform independentverification of manualportion of the computerinput for release ratecalculations performed bycomputer.
OR
C.2.3.2Perform independentverification of entirecalculations for releaserate calculations performedmanually.
AND
C.2.4 Restore channel toFUNCTIONAL status.
OR
C.3 Suspend release ofradioactive effluents viathis pathway.
Prior to initiating arelease
Prior to initiating arelease
Prior to initiating arelease
Prior to initiating arelease
Prior to initiating arelease
14 days
Immediately
(continued)
Catawba Units 1 and 2 16.11-7-2 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
D. One or more flow rate D.1 Estimate the flow rate of Once per 4 hoursmeasurement device the release. during releaseschannel(s) non-functional. AND
D.2 Restore channel to 30 daysFUNCTIONAL status.
E. One or more Noble Gas E.1 Obtain grab samples from Once per 12 hoursActivity Monitor effluent pathway. during releaseschannel(s) non-functional. AND
E.2 Perform an analysis of Within 24 hours ofgrab samples for obtaining the sampleradioactivity.
AND
E.3 Restore channel to 30 daysFUNCTIONAL status.
(continued)
Catawba Units 1 and 2 16.11-7-3 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
F. Noble Gas Activity F. 1 ----- NOTE---------Monitor (EMF-39 - Low In order to utilize RequiredRange) providing Action F.1, the followingautomatic termination of conditions must berelease via the satisfied:Containment Purge 1. The affected unit is inExhaust System (CPES) MODES 5 or 6.non-functional. 2. EMF-36 is
FUNCTIONAL and inservice for the affectedunit.
3. The Reactor CoolantSystem for the affectedunit has been vented.
4. Either the reactorvessel head is in place(bolts are not required),or if it is not in place,the lifting of heavyloads over the reactorvessel and themovement of irradiatedfuel assemblies withincontainment have beensuspended.
Restore the non-functional 12 hourschannel to FUNCTIONALstatus.
G. Required Action and G.1 Suspend PURGING of Immediatelyassociated Completion radioactive effluents viaTime of Condition F not this pathway.met.
OR
Required Action F.1 notutilized.
(continued)
I
Catawba Units 1 and 2 16.11-7-4 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
H. One or more sampler H.1 Perform sampling with Continuouslychannel(s) non- auxiliary samplingfunctional. equipment as required by
Table 16.11-6-1.
AND
H.2 Restore channel to 30 daysFUNCTIONAL status.
I. One Condenser .1----------- NOTE -------------Evacuation System Applicable to effluentNoble Gas Activity releases via the CondenserMonitor (EMF-33) Steam Air Ejector (ZJ)channel non-functional. System.
Obtain grab samples from Once per 12 hours
effluent pathway. during releases
AND
1.2 -- NOTE-------Applicable to effluentreleases via the CondenserSteam Air Ejector (ZJ)System.
Perform an analysis of Within 24 hours ofgrab samples for obtaining the sampleradioactivity.
AND
(continued)
Catawba Units 1 and 2 16.11-7-5 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
1. (continued) 1.3 ---------- NOTE -------------Applicable to effluentreleases via the SteamGenerator Blowdown (BB)System atmospheric ventvalve (BB-27) in the off-normal mode.
Perform an analysis ofgrab samples forradioactivity at a lower limitof detection of 10-7
microCurie/ml.
AND
1.4 Restore channel toFUNCTIONAL status.
Once per 12 hoursduring releaseswhen secondaryspecific activity is >0.01 microCurie/gmDOSE EQUIVALENT1-131
AND
Once per 24 hoursduring releaseswhen secondaryspecific activity is <0.01 microCurie/gmDOSE EQUIVALENT1-131
30 days
J. Noble Gas ActivityMonitor (EMF-39 - LowRange) providingautomatic termination ofrelease via theContainment AirRelease and AdditionSystem non-functional.
J.1 Verify that EMF-36 isFUNCTIONAL.
OR
J.2.1 Analyze two independentsamples of thecontainment atmosphere.
AND
Prior to initiating arelease
Prior to initiating arelease
(continued)
Catawba Units 1 and 2 16.11-7-6 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
J. (continued) J.2.2 Perform independentverification of thedischarge line valving.
AND
J.2.3.1 Perform independentverification of manualportion of the computerinput for release ratecalculations performed bycomputer.
OR
J.2.3.2 Perform independentverification of entirecalculations for releaserate calculations performedmanually.
AND
J.2.4 --------- NOTE-------If channel remains or isanticipated to remain non-functional for > 90 days,re-evaluate theconfiguration of theaffected unit in accordancewith the applicable portionsof 10 CFR 50.59 and 10CFR 50.65(a)(4) prior toexpiration of the 90-dayperiod.
Prior to initiating arelease
Prior to initiating arelease
Prior to initiating arelease
30 days.Restore channel toFUNCTIONAL status.
(continued)
Catawba Units 1 and 2 16.11-7-7 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
REMEDIAL ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
K. Required Action and K.1 Explain why the non- In the nextassociated Completion functionality was not scheduledTime of Condition C, D, corrected within the Radioactive EffluentE, F, H, I, or J not met. specified Completion Time. Release Report
pursuant toTechnical
Specification 5.6.3
TESTING REQUIREMENTS
--------------------- NOTE --------------------------------------------------------Refer to Table 16.11-7-1to determine which TRs apply for each Radioactive Gaseous EffluentMonitoring Instrumentation channel.
TEST FREQUENCY
TR 16.11-7-1 Perform CHANNEL CHECK. Prior to eachrelease
TR 16.11-7-2 -----.......-------------- NOTE ---------------------------------For Instruments la, 4, and 5, a SOURCE CHECK forthese channels shall be the qualitative assessment ofchannel response when the channel sensor is exposedto a light-emitting diode.
Perform SOURCE CHECK. Prior to eachrelease
TR 16.11-7-3 Perform CHANNEL CHECK. 12 hours
TR 16.11-7-4 Perform CHANNEL CHECK. 24 hours
TR 16.11-7-5 Perform CHANNEL CHECK. 7 days
(continued)
Catawba Units 1 and 2 16.11-7-8 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
TESTING REQUIREMENTS (continued)
TEST FREQUENCY
TR 16.11-7-6 ------------------- NOTE -----------------For Instruments 2 and 3a, a SOURCE CHECK for thesechannels shall be the qualitative assessment of channelresponse when the channel sensor is exposed to a light-emitting diode.
Perform SOURCE CHECK. 31 days
TR 16.11-7-7 ------------------- NOTE -----------------For Instruments la, 2, 3a, 3c, 5, and 6a, the COT shallalso demonstrate, as applicable, that automatic isolationof this pathway and control room alarm annunciation (forEMF-58, alarm annunciation is in the Monitor TankBuilding control room and on the Monitor Tank Buildingcontrol panel remote annunciator panel) occur if any ofthe following conditions exist:
a. Instrument indicates measured levels above theAlarm/Trip Setpoint, or
*b. Circuit failure/instrument downscale failure (alarmonly)
Perform COT. 9 months
TR 16.11-7-8 ------------------- NOTE ----------------For Instrument 4, the COT shall also demonstrate thatautomatic isolation of this pathway and control roomalarm annunciation occur if any of the followingconditions exist:
a. Instrument indicates measured levels above theAlarm/Trip Setpoint, or
b. Circuit failure/instrument downscale failure (alarmonly)
Perform COT. 18 months
(continued)
Catawba Units 1 and 2 16.11-7-9 Revision' 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
TESTING REQUIREMENTS (continued)
TEST FREQUENCY
TR 16.11-7-9 ------------- - --NOTE -----------------For Instruments la, 2, 3a, 3c, 4, 5, and 6a, the initialCHANNEL CALIBRATION shall be performed using oneor more of the reference standards certified by theNational Bureau of Standards (NBS) or using standardsthat have been obtained from suppliers that participate inmeasurement assurance activities with NBS. Thesestandards shall permit calibrating the system over itsintended range of energy and measurement range. Forsubsequent CHANNEL CALIBRATION, sources thathave been related to the initial calibration shall be used.
Perform CHANNEL CALIBRATION. 18 months
Catawba Units 1 and 2 16.11-7-10 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
Table 16.11-7-1
Radioactive Gaseous Effluent Monitoring Instrumentation (page 1 of 2)
INSTRUMENT REQUIRED CONDITIONS APPLICABLE TESTINGCHANNELS MODES REQUIREMENTS
1. Waste Gas Holdup System
1.a Noble Gas Activity Monitor - Providing 1 per station A, C, K At all times except TR 16.11-7-1Alarm and Automatic Termination of when the isolation TR 16.11-7-2Release valve is closed and TR 16.11-7-7(EMF-50 - Low Range) locked TR 16.11-7-9
1 .b Effluent System Flow Rate Measuring 1 per station D, K At all times except TR 16.11-7-1Device when the isolation TR 16.11-7-9
valve is closed andlocked
2. Condenser Evacuation System Noble 1 A, I, K When air ejectors TR 16.11-7-3Gas Activity Monitor are in operation TR 16.11-7-6(EMF-33) (BB-27 is only isolation (Apply Required TR 16.11-7-7function required) (Note 1) Action 1.3 when air TR 16.11-7-9
ejectors are not inoperation)
3. Vent System
3.a Noble Gas Activity Monitor 1 A, E, K At all times TR 16.11-7-4(EMF-36 - Low Range) TR 16.11-7-6
TR 16.11-7-7TR 16.11-7-9
3.b Deleted.
3.c Particulate Sampler 1 A, H, K At all times TR 16.11-7-4(EMF-35) (Note 2) TR 16.11-7-6
TR 16.11-7-7TR 16.11-7-9
3.d Unit Vent Stack Flow Rate Meter 1 D, K At all times TR 16.11-7-4(no alarm/trip function) (Note 2) TR 16.11-7-9
3.e Unit Vent Radiation Monitor Flow Meter 1 E, K At all times TR 16.11-7-4(Note 2) TR 16.11-7-9
4. Containment Purge System Noble Gas 1 A, F, G, K 5, 6 TR 16.11-7-2Activity Monitor - Providing Alarm and TR 16.11-7-3Automatic Termination of Release TR 16.11-7-8(EMF-39 - Low Range) TR 16.11-7-9
(continued)
Catawba Units 1 and 2 16.11-7-11 ' Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
Table 16.11-7-1
Radioactive Gaseous Effluent Monitoring Instrumentation (page 2 of 2)
INSTRUMENT REQUIRED CONDITIONS APPLICABLE TESTINGCHANNELS MODES REQUIREMENTS
5. Containment Air Release and Addition A, J, K 1, 2, 3, 4, 5, 6 TR 16.11-7-2System Noble Gas Activity Monitor - TR 16.11-7-3Providing Alarm and Automatic TR 16.11-7-7Termination of Release TR 16.11-7-9(EMF-39 - Low Range)
6. Monitor Tank Building HVAC
6.a Noble Gas Activity Monitor - Providing 1 per station A, E, K At all times TR 16.11-7-4Alarm (Note 2) TR 16.11-7-6(EMF-58 - Low Range) TR 16.11-7-7
TR 16.11-7-9
6.b Effluent Flow Rate Measuring Device 1 per station D, K At all times TR 16.11-7-4(Note 2) TR 16.11-7-9
Note 1: The setpoint is as required by the primary to secondary leak rate monitoring program.
Note 2: Except when the effluent pathway is isolated and a release to the environment is not possible.
Catawba Units 1 and 2 16.11-7-12 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
BASES The Radioactive Gaseous Effluent Monitoring Instrumentation is provided tomonitor and control, as applicable, the releases of radioactive materials ingaseous effluents during actual or potential releases of gaseous effluents. TheAlarm/Trip Setpoints for these instruments shall be calculated and adjusted inaccordance with the methodology and parameters in the ODCM to ensure thatthe Alarm/Trip will occur prior to exceeding the limits of 10 CFR Part 20. TheFUNCTIONALITY and use of this instrumentation is consistent with therequirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFRPart 50. The sensitivity of any noble gas activity monitor used to showcompliance with the.gaseous effluent release requirements of SLC 16.11-8 shallbe such that concentrations as low as 1 x 10-6 pCi/cc are measurable.
Initiation of the Containment Purge Exhaust System (CPES) with EMF-39 non-functional is not permissible. The basis for Required Action F.1 is to allow thecontinued operation of the CPES with EMF-39 initially FUNCTIONAL. Continuedoperation of the CPES is contingent upon the ability of the affected unit to meetthe requirements as noted in Required Action F.1.
TR 16.11-7-7 requires the performance of a COT on the applicable RadioactiveGaseous Effluent Radiation Monitors. The test ensures that a signal from thecontrol room module can generate the appropriate alarm and actuations. Therequired actuations/isolations for a High Radiation condition (i.e., radiation levelabove its Trip 2 setpoint) are listed below for each monitor.
OEMF-50 - Waste Gas Discharge Monitor1WG160 closes when EMF-50 detects radiation level above its setpoint.
1/2EMF-33 - Condensate Steam Air Ejector Exhaust MonitorThe following actuations occur when EMF-33 detects radiation level above itssetpoint:1. Closure of BB27 is required in order to isolate the Blowdown Tank from
the environment. Because of plant limitations/restrictions:a. Opening the valve (in order to verify it goes closed on a High
Radiation signal) is only possible during outages due to thenegative effects on the Blowdown System with the unit at power.
b. Testing during innages will be by verification of relay contactsopening in the valve circuit.
2. Closure of BB24, BB65, BB69, and BB73 is required to minimize theamount of potentially contaminated material being delivered to theBlowdown Tank.
3. Closure of NM269, NM270, NM271, and NM272 is required to minimizethe amount of potentially contaminated material being delivered to theConventional Sampling System.
4. Closure of NM267 is required to minimize the amount of potentiallycontaminated material being delivered to the Condensate Storage Tankby isolating flow through EMF-34.
5. Closure of BB48 is required to minimize the amount of potentiallycontaminated material being delivered from the Blowdown Systemdischarge to the Turbine Building sump.
Catawba Units 1 and 2 16.11-7-13 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
BASES (continued)
1/2EMF-36 - Unit Vent Noble Gas MonitorThe following actuations occur when EMF-36 detects radiation level above itssetpoint:1. Containment Air Release and Addition System fans discharge to unit vent
valve VQ10 closes.2. Auxiliary Building unfiltered ventilation exhaust fans A and B stop.3. Fuel Handling Ventilation Exhaust System (FHVES) exhaust trains align
to the filter units.4. (For 1EMF-36 only) 1WG160 closes.
1/2EMF-35 - Unit Vent Particulate Monitor (Sampler)The following actuations occur when EMF-35 detects radiation level above itssetpoint:1. Containment Air Release and Addition System fans discharge to unit vent
valve VQ10 closes.2. Auxiliary Building unfiltered ventilation exhaust fans A and B stop.3. Fuel Handling Ventilation Exhaust System (FHVES) exhaust trains align
to the filter units.4. ((For 1EMF-35 only) 1WG160 closes.
1/2EMF-39 - Containment Noble Gas MonitorThe following actuations occur when EMF-39 detects radiation level above itssetpoint:1. Signals are provided to both trains of the Solid State Protection System
(SSPS) to initiate a CPES isolation. This is verified by observing thatRelays K615 in the SSPS A output cabinet and the SSPS B outputcabinet are latched.
2. EMF-39 isolates the CPES without going through the SSPS by stoppingCPES supply fans A and B, CPES exhaust fans A and B, and by closingthe appropriate valves and dampers.
3. Containment Evacuation Alarm, unless the source range trip is blocked.
OEMF-58This monitor provides no control function.
TR 16.11-7-8 requires the performance of a COT on the Containment Noble GasMonitor, 1/2EMF-39. The test ensures that a signal from the control roommodule can generate the appropriate alarm and actuations. The requiredactuations/isolations for a High Radiation condition (i.e., radiation level above itsTrip 2 setpoint) are listed below.
1/2EMF-39 - Containment Noble Gas MonitorThe following actuations occur when EMF-39 detects radiation level above itssetpoint:1. Containment Air Release and Addition System fans discharge to unit vent
valve VQ10 closes.2. Containment Evacuation Alarm, unless the source range trip is blocked.
Catawba Units 1 and 2 16.11-7-14 Revision 6
Radioactive Gaseous Effluent Monitoring Instrumentation16.11-7
1. Catawba Offsite Dose Calculation Manual.
2. 10 CFR Part 20.
REFERENCES
Catawba Units 1 and 2 16.11-7-15 Revision 6
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