Text

Selected Licensee Commitments Manual, Revision Dates: 10/24/2011, 02/20/2012, and 03/5/2012
	ML12088A291
Person / Time
Site:	Catawba
Issue date:	03/21/2012
From:	Byers K; Duke Energy Corp
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	DUK120800041
	Download: ML12088A291 (56)
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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 NA NA NA NA NA NA NA NA NA NA 049 013 002 001 006 004 002 003 000 006 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 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 INSTRUCTIONS J R MORRIS VICE PRESIDENT CATAWBA NUCLEAR STATION BY:

K S BYERS CN01RC KSB/RJA

Duke DUKE ENERGY CORPORATION Catawba Nuclear Station Energy 4800 Concord Rd.

York, SC 29745 March 19, 2012 Re:

Catawba Nuclear Station Selected Licensee Commitments Manual Revision Dates: 10/24/2011, 02/20/2012, and 03/5/2012 Attached are revisions to the Catawba Nuclear Station Selected Licensee Commitments Manual. Please remove and replace the following pages:

REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE SECTIONS Pages 1 through 4 Revision 48 Pages 1 through 4 Revision 49 TAB 16.0 - TABLE OF CONTENTS Pages i through v Revision 12 Pages i through v Revision 13 TAB 16.5 SLC 16.5-1 Revision 1 SLC 16.5-9 Revision.0 SLC 16.7-9 Revision 5 SLC 16.7-10 Revision 3 SLC 16.8-2 Revision 1 TAB 16.7 SLC 16.5-1 Revision 2 SLC 16.5-9 Revision 1 SLC 16.7-9 Revision 6 SLC 16.7-10 Revision 4 SLC 16.8-2 Revision 2 TAB 16.8 www. duke-energy. corn

TAB 16.9 SLC 16.9-19 SLC 16.9-19 Revision 2 Revision 3 SLC 16.9-26 Revision 0 TAB 16.11 SLC 16.11-7 SLC 16.11-7 Revision 5 Revision 6 If you have any questions concerning the contents of this package update, contact Kristi Byers at (803)701-3758.

Randy Hart Manager, 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 16.7-3 16.7-4 16.7-5 2

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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 2

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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 3

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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 1

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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 16.5-1-1 Fuel 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 16.5-9-1 Generator (SGý Nozzle Dams Installed or Cold Leg Opening > 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 16.6-5-1 Interlock 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 16.7-13-1 Piping Temperature Monitoring System 16.7-14 Trip of All Main Feedwater Pumps Turbine Trip 16.7-14-1 Instrumentation 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 6.8-1-1 Devices 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 16.9-15-1 Bypass Valves 16.9-16 Fuel Handling Ventilation Exhaust System Filter Cooling 16.9-16-1 Bypass 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 16.9-20-1 Pool 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-Recentlyl6.9-26-1 Irradiated Fuel Assemblies 16.10 COMMITMENTS RELATED TO STEAM AND POWER CONVERSION SYSTEMS 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 16.10-3-1 Accumulators 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 16.11-9-1 Material 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 and Annual Radioactive Effluent Release Report Liquid Holdup Tanks Explosive Gas Mixture Gas Storage Tanks Explosive Gas Monitoring Instrumentation Major Changes to Liquid, Gaseous, and Solid Radwaste Treatment 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 Core 16.5-1 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 instruments are required. These instruments shall have independent transmitters and 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to reactor vessel head removal.

2.

Reconnection of at least two thermocouples shall occur within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reinstalling the reactor vessel head.

3.

The total time without thermocouple indication shall not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Whenever the reactor vessel head is installed, two core exit thermocouples shall be maintained operating with temporary high alarms set at 140OF and monitored.

AND Four power sources shall be available, two offsite sources and two diesel generators.

AND Two independent makeup paths of borated water shall be available, consisting of:

One centrifugal charging pump or one safety injection pump as required per SLC 16.9-7 and 16.9-9.

AND One additional centrifugal charging pump or safety injection pump 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 Core 16.5-1 COMMITMENT (continued)

NOTE -----------.-.-----......-------...

The number of open containment penetrations shall be limited such that the penetrations can be closed prior to the onset of core boiling upon loss of residual heat removal.

Containment closure shall be established. Containment closure is verified by the performance of PT/1/(2)/A/4200/002C&I, Containment Closure Verification, with penetrations not verified acceptable, administratively controlled per OP/O/A/6100/014, Penetration Control For Modes 5 and 6.

AND The reactor has been subcritical for at least 7 days or Engineering has provided a required subcritical time based on plant operating history and actual reduced reactor coolant system level.

AND Operation in a mid-loop condition shall only occur during low decay heat conditions (after refueling).

Whenever irradiated fuel is in the reactor vessel and reactor coolant system 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 Core 16.5-1 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Initiate action to restore Immediately COMMITMENT(S) not compliance with met.

COMMITMENT(S).

AND A.2 Contact station Immediately management for additional guidance.

B.

Primary method of B.1 Monitor and record Once per 15 minutes monitoring core exit thermocouple thermocouples temperatures on the Incore unavailable.

Instrument Panel.

TESTING REQUIREMENTS None BASES Generic Letter 88-17 and NUREG-1410 involve concerns associated with a loss of residual heat removal. Numerous events have occurred in the industry that resulted in a loss of residual heat removal during reduced inventory operation. This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.

This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.

The basis for the requirement for the reactor to be subcritical for 7 days is to ensure 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months until the core is uncovered following a loss of decay heat removal 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 Heat Removal 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 Core 16.5-1 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 Commitment 16.5.3.

8.

Work Processes Manual, Sections 602, "Outage Management," and 603, "Unit Trip Forced Outage Management."

9.

Catawba Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989.

10.

Design Study CNDS-0242, "Catawba and McGuire Nuclear Stations, Shutdown by Decay Heat Level Before Mid-Loop Operation."

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 Installed or Cold Leg Opening > 1 in2 16.5-9 16.5 REACTOR COOLANT SYSTEM 16.5-9 Operation with Irradiated Fuel in the Core with Steam Generator (SG) Nozzle Dams Installed or Cold Leg Opening > 1 in2 COMMITMENT APPLICABILITY:

The Reactor Coolant System (RCS) shall be properly vented when SG 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 Immediately met.

compliance with COMMITMENT(S).

TESTING REQUIREMENTS None BASES Generic Letter 88-17 and NUREG-1 410 involve concerns associated with a loss of residual heat removal. Numerous events have occurred in the industry that resulted in a loss of residual heat removal. This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.

The vent path is provided to address Expeditious Action (7) of Generic Letter 88-17. The vent path is provided to assure that the nozzle dams are not dislodged due to pressurization that could result on a loss of decay heat removal event resulting in core boiling. In addition, in the absence of a sufficient vent path, pressurization in combination with cold leg openings could allow water to be ejected from the vessel and lead to core uncovery.

This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical 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 Installed or Cold Leg Opening > 1 in2 16.5-9 BASES (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 Heat Removal 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 Vent Paths During Nozzle Seal Dam Installation and Use."

7.

NUREG-1449, "Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States."

8.

NRC letter to Hal Tucker, "Comments on Expeditious Action and Notice of Audit on Generic Letter 88-17, McGuire and Catawba Nuclear Stations, Units I and 2," dated May 17, 1989.

Catawba Units 1 and 2 16.5-9-2.

Revision 1

SSS 16.7-9 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 days FUNCTIONAL status.

B.

Total accumulative B.1 Declare the standby Immediately LEAKAGE from makeup pump non-unidentified LEAKAGE, functional and enter identified LEAKAGE, Condition A.

and reactor coolant pump seal LEAKAGE >

20 gpm.

C.

More than one cell in a C.1 Enter Condition A.

Immediately 24-Volt battery bank is <

1.36 volts on float charge with no other cells jumpered.

D.

Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

D.2 Be in MODE4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Catawba Units I and 2 16.7-9-1 Revision 6

SSS 16.7-9 TESTING REQUIREMENTS TEST FREQUENCY TR 16.7-9-1 Verify that the electrolyte level of each SSS diesel 7 days starting 24-Volt battery is > the low mark and < the high mark.

TR 16.7-9-2 Verify that the overall SSS diesel starting 24-Volt battery 7 days voltage is > 24 volts on float charge.

TR 16.7-9-3 Verify that the requirements of SLC 16.9-21 are met and 7 days the boron concentration in the storage pool is > the minimum specified in the COLR.

TR 16.7-9-4 Verify the fuel level in the SSS diesel generator fuel 31 days storage tank is > 67 inches.

TR 16.7-9-5 Verify the SSS diesel generator starts from ambient 31 days conditions 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 days battery is above the plates.

TR 16.7-9-7 Verify the total SSS 250/125-Volt battery terminal voltage 31 days is > 258/129 volts on float charge.

TR 16.7-9-8 Perform CHANNEL CHECK of each SSS 31 days instrumentation device.

TR 16.7-9-9 Verify the fuel oil properties of new and stored fuel oil for In accordance with the SSS diesel generator are tested in accordance with, the Diesel Fuel Oil and maintained within the limits of, the Diesel Fuel Oil Testing Program Testing 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

SSS 16.7-9 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.7-9-11 Verify that the Standby Makeup Pump's developed head 92 days at the test flow point is > the required developed head, in accordance with the Inservice Testing Program.

TR 16.7-9-12 Verify that the specific gravity of the SSS 250/125-Volt 92 days battery is appropriate for continued service of the battery.

TR 16.7-9-13 Subject the SSS diesel generator to an inspection in 18 months accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

TR 16.7-9-14 Verify that the SSS diesel starting 24-Volt batteries, cell 18 months plates, and battery racks show no visual indication of physical damage or abnormal deterioration.

TR 16.7-9-15 Verify that the SSS diesel starting 24-Volt battery-to-18 months battery and terminal connections are clean, tight, and free of corrosion.

TR 16.7-9-16 Verify that the SSS 250/125-Volt batteries, cell plates, 18 months and battery racks show no visual indications of physical damage or abnormal deterioration.

TR 16.7-9-17 Verify that the SSS 250/125-Volt battery-to-battery and 18 months terminal 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 months pump and controls from the Standby Shutdown Facility function 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

SSS 16.7-9 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 months capacity of > 70 kW.

BASES The SSS is designed to mitigate the consequences of certain postulated fire, security, and station blackout incidents by providing capability to maintain MODE 3 conditions and by controlling and monitoring vital systems from locations external to the main control room. This capability is consistent with the requirements of 10 CFR Part 50, Appendix R, NUREG-0800, Section 9.5-1, and Appendix A to Branch Technical Position APSCB 9.5-1.

The TESTING REQUIREMENTS ensure that the SSS systems and components are capable of performing their intended functions. The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months uninterrupted operation. It is assumed that, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , either offsite power can be restored or additional fuel can be added to the storage tank.

Although the standby makeup pump is not nuclear safety related and was not designed according to ASME Code requirements, it is tested quarterly to ensure its FUNCTIONALITY. The TESTING REQUIREMENT concerning the standby makeup pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Total accumulative. LEAKAGE is calculated in the NC System Leakage Calculation procedure as identified + unidentified + seal leakoff (References 2 and 3). The REMEDIAL ACTION limit of 20 gpm total accumulative LEAKAGE provides additional margin to allow for instrument inaccuracy, and for the predicted increase in seal leakoff rate due to heatup of the reactor coolant pump seal injection water supply temperature following the SSS event (due to spent fuel pool heatup).

Following the increase in seal injection temperature, the standby makeup pump flow of 26 gpm is sufficient to provide in excess of this total accumulative LEAKAGE, thereby assuring that reactor coolant system inventory is maintained at MODE 3 conditions. The supporting evaluation is provided in CNC-1223.04-00-0072 (Ref. 4).

A visual inspection of the diesel starting 24-volt batteries, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. Since Catawba Units 1 and 2 16.7-9-4 Revision 6

SSS 16.7-9 BASES (continued) the battery cell jars are not transparent, a direct visual inspection of the cell plates cannot be performed. Instead, the cell plates are inspected for physical damage and abnormal deterioration by: 1) visually inspecting the 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 diesel starting 24-Volt batteries ensures that each cell is capable of supporting its intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or battery cell) in a fully charged state. The battery cell voltage limit of 1.36 volts is consistent with the nominal design voltage of the battery and is based on the manufacturer's recommended minimum float charge voltage for a fully charged cell with adequate capacity. The battery is designed and sized with a capacity margin sufficient to allow up to one cell per battery bank to be fully degraded with a voltage < 1.36 volts assuming that no cells are jumpered out. The battery sizing calculations account for one degraded cell per battery bank by assuming the degraded cells undergo a worst case polarity reversal during SSS diesel starting.

Verification of proper installation of pressurizer insulation ensures that pressurizer heat losses during an SSS event do not exceed the capacity of the pressurizer heaters powered from the SSS.

Testing of the pressurizer heater capacity ensures the full capacity of the heaters is available to maintain a steam bubble in the pressurizer during an SSS event.

REFERENCES

1.

Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved 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 Seal Leakoff Annunciator Alarm Setpoint for Unit 1 and Unit 2.

5.

CNS-1560.SS-00-0001, Design Basis Specification for the Standby Shutdown Facility.

6.

Catawba Technical Specification Amendments 206/200, July 10, 2003.

7.

Catawba UFSAR, Section 18.2.4.

Catawba Units 1 and 2 16.7-9-5 Revision 6

SSS 16.7-9 REFERENCES (continued)

8.

Catawba License Renewal Commitments, CNS-1274.00 0016, Section 4.5.

Catawba Units 1 and 2 16.7-9-6 Revision 6

Radiation Monitoring for Plant Operations 16.7-10 16.7 INSTRUMENTATION 16.7-10 Radiation Monitoring for Plant Operations COMMITMENT APPLICABILITY:

The radiation monitoring instrumentation channels for plant operations shown 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months monitoring channels within the limit.

Alarm/Trip setpoint for plant operations OR exceeding the value shown in Table 16.7 A.2 Declare the channel non-4 hours

1.

functional.

(continued)

Catawba Units 1 and 2 16.7-10-1 Revision 4

Radiation Monitoring for Plant Operations 16.7-10 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One Containment B.1 NOTE-------

Atmosphere - High In order to utilize Required Gaseous Radioactivity Action B.1, the following (EMF Low Range) conditions must be channel non-functional.

satisfied:

1. The affected unit is in MODES 5 or 6.

2. EMF-36 is FUNCTIONAL and in service for the affected unit.

3. The Reactor Coolant System for the affected unit has been vented.

4. Either the reactor vessel head is in place (bolts are not required),

or if it is not in place, the lifting of heavy loads over the reactor vessel and the movement of irradiated fuel assemblies within containment have been suspended.

Restore the non-functional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channel to FUNCTIONAL status.

(continued)

Catawba Units 1 and 2 16.7-10-2 Revision 4

Radiation Monitoring for Plant Operations 16.7-10 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and C.1 Close the Containment Immediately associated Completion Purge Exhaust System Time of Condition B not (CPES) valves.

met.

OR Required Action B. 1 not utilized.

D.

One Control Room Air D.1 Initiate action to restore Immediately Intake - Radiation Level non-functional channel(s)

- High Gaseous to FUNCTIONAL status.

Radioactivity (EMF-43A

& B - Low Range)

AND channel non-functional in one or both control D.2 Ensure that one Control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months room intakes.

Room Area Ventilation System (CRAVS) train is in operation.

E.

One Fuel Storage Pool E.1 Provide a portable Immediately Area - Criticality -

continuous monitor with Radiation Level (1EMF-the same Alarm Setpoint in 15, 2EMF-4) channel the fuel storage pool area.

non-functional.

AND E.2.1 Restore non-functional 30 days monitor to FUNCTIONAL status.

OR E.2.2 Suspend all operations 30 days involving fuel movement in the fuel building.

(continued)

Catawba Units 1 and 2 16.7-10-3 Revision 4

Radiation Monitoring for Plant Operations 16.7-10 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

One Fuel Storage Pool F.1.1 Initiate action to restore Immediately Area - High Gaseous non-functional channel to Radioactivity (EMF-42)

FUNCTIONAL status.

channel non-functional.

AND F.1.2 ---------

NOTE ------

Only applicable during fuel handling operations in the fuel building.

Ensure one Fuel Handling Immediately Ventilation Exhaust System (FHVES) train is in operation and all operating FHVES trains are in the filtered mode.

OR F.2 Suspend all operations Immediately involving fuel movement in the fuel building.

G.

One Auxiliary Building G.1 Ensure one Auxiliary Immediately Ventilation - High Building Filtered Ventilation Gaseous Radioactivity Exhaust System (ABFVES)

(EMF-41) channel non-train is OPERABLE and in functional.

operation and all operating ABFVES trains are in the filtered mode.

(continued)

Catawba Units 1 and 2 16.7-10-4

. Revision 4

Radiation Monitoring for Plant Operations 16.7-10 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

One Component H.1 Collect and analyze grab Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Cooling Water System samples for principal (EMF-46A & B) channel gamma emitters (listed in non-functional.

Table 16.11-1-1, NOTE 3) at a lower limit of detection of no more than 5x10 7 p.Ci/ml.

AND H.2 Restore non-functional 30 days channel to FUNCTIONAL status.

One or more N-16 1.1 Ensure that the Condenser Immediately Leakage Monitor (EMF-Evacuation System Noble 71, 72, 73, & 74)

Gas Activity Monitor (EMF-channels non-functional.

33) is FUNCTIONAL and in operation.

OR 1.2 Ensure that Required Immediately Actions are met per SLC 16.11-7 if the Condenser Evacuation System Noble Gas Activity Monitor (EMF-

33) is non-functional or not in operation.

Catawba Units 1 and 2 16.7-10-5 Revision 4

Radiation Monitoring for Plant Operations 16.7-10 TESTING REQUIREMENTS Refer to Table 16.7-10-1 to determine which TRs apply for each Radiation Monitoring for Plant Operations channel.

TEST FREQUENCY TR 16.7-10-1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 Operations 16.7-10 Table 16.7-10-1 Radiation Monitoring Instrumentation for Plant Operations MONITOR APPLICABLE REQUIRED ALARM/TRIP TESTING MODES CHANNELS SETPOINT REQUIREMENTS

1. Containment Atmosphere -

1,2, 3,4, 5,6 1

Note (a)

TR 16.7-10-1 High Gaseous TR 16.7-10-2 Radioactivity TR 16.7-10-3 (EMF Low Range)

2. Fuel Storage Pool Areas -

With irradiated 1

1.7 x 10i' pCi/mi TR 16.7-10-1 High Gaseous fuel in the fuel TR 16.7-10-2 Radioactivity storage pool TR 16.7-10-3 (EMF-42) areas

3. Fuel Storage Pool Areas -

With fuel in the

< 15 mR/h TR 16.7-10-1 Criticality - Radiation Level fuel storage pool TR 16.7-10-2 (Fuel Bridge - 1 EMF-1 5, areas TR 16.7-10-3 2EMF-4)

4. Control Room Air Intake -

At all times 2 (1/intake)

< 1.7 x 10.4 ýLCi/ml TR 16.7-10-1 Radiation Level - High TR 16.7-10-2 Gaseous Radioactivity TR 16.7-10-3 (EMF-43A & B - Low Range)

5. Auxiliary Building 1, 2, 3, 4 1

1.7 x 10-4 pLCi/ml TR 16.7-10-1 Ventilation - High Gaseous TR 16.7-10-2 Radioactivity 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 Operations 16.7-10 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 of SLC 16.11-6 in accordance with the methodology and parameters in the ODCM. When not venting or purging in Modes 5 or 6, the alarm setpoint concentration (MCi/ml) shall be such that the actual submersion dose rate would not exceed 5 mR/hr without alarm. When not venting or purging in Modes 1 through 4, the alarm setpoint shall be no more than 3 times 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 be FUNCTIONAL. This requirement is based on the existence of an interlock which blocks the EMF loss of flow alarm from being 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 Operations 16.7-10 BASES The FUNCTIONALITY of the radiation monitoring instrumentation for plant operations ensures that: (1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, and (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance. The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded. The radiation monitors send actuation signals to initiate alarms or automatic isolation action and actuation of emergency exhaust or ventilation systems. Some of the final actuations are dependent on plant condition in addition to the actuation signals from the radiation monitors.

Operation of the Component Cooling Water (CCW) System Train A with the Train A Radiation Monitoring System (EMF) monitor non-functional and relying on the Train B EMF monitor for detection of radioactivity is not permissible. Likewise, operation of the CCW System Train B with the Train B EMF monitor non-functional and relying on the Train A EMF monitor for detection of radioactivity is not permissible. This is due to the interlock between the EMF monitor low-flow alarm and the operation of the CCW System pump motors on the same train. The EMF monitor in the operating CCW System pump train must be FUNCTIONAL, or the compensatory measures taken as specified.

Initiation of the Containment Purge Exhaust System (CPES) with EMF-39 non-functional is not permissible. The basis for Required Action B.1 is to allow the continued operation of the CPES with EMF-39 initially FUNCTIONAL. Continued operation of the CPES is contingent upon the ability of the affected unit to meet the requirements as noted in Required Action B.1.

REFERENCES

1.

Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.

Catawba Units 1 and 2 16.7-10-9 Revision 4

230 kV Switchyard Systems 16.8-2 16.8 ELECTRICAL POWER SYSTEMS 16.8-2 230 kV Switchyard Systems COMMITMENT The following switchyard equipment shall be in its normal alignment:

a.

Switchyard Unit 1 PCBs 14, 15, 17, and 18 including their associated manual disconnects, current transformers, interconnecting bus, and support structures (EBA system),

b.

Switchyard Unit 2 PCBs 20, 21, 23, and 24 including their associated manual disconnects, current transformers, interconnecting bus, and support structures (EBA system),

c.

Buslines 1A, 1B (from main stepup transformers to switchyard unit PCBs), including their associated motor operated disconnects, coupling capacitor voltage transformers, interconnecting bus, and support structures (EBA system),

d.

Buslines 2A, 2B (from main stepup transformers to switchyard unit PCBs), including their associated motor operated disconnects, coupling capacitor voltage transformers, interconnecting bus, and support structures (EBA system),

e.

Controls associated with the equipment above (EBE, ERE systems),

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 (all MODES) 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 Systems 16.8-2 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Switchyard equi 5ment A.1 Return switchyard In accordance with not in normal equipment to normal the Electronic Risk COMMITMENT COMMITMENT alignment.

Assessment Tool alignment.

TESTING REQUIREMENTS None BASES Effective implementation of the Maintenance Rule, 10 CFR 50.65, requires the continuous assessment of systems determined to be risk significant in the protection against core damage or radiation release. It has been determined through probabilistic risk assessment (PRA) numerical methods that switchyard systems are risk significant from the standpoint of causing or being able to recover from Loss of Offsite Power events. This SLC serves two purposes. It defines the risk significant portions of the switchyard.

It also provides a method of tracking the switchyard systems for the 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 Maintenance Rule.

5.

CNS-010.01-EB-0001, Switchyard Design Basis Specification.

6.

Technical Specification sections 3.8.1 and 3.8.2, LCOs for AC Power Sources during Operating and Shutdown MODES.

7.

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 16.8-2-2 Revision 2

Refueling Operations - Manipulator Crane 16.9-19 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 be FUNCTIONAL with:

a.

The manipulator crane used for movement of fuel assemblies having:

1 )

A minimum capacity of 3250 pounds, and

2)

An overload cutoff limit < 2900 pounds.

b.

Auxiliary hoists used for latching, unlatching, and drag load testing of control rods having:

1)

A minimum capacity of 1000 pounds, and

2)

A load indicator which shall be used to prevent applying a lifting force > 600 pounds on the core internals.

During movement of fuel assemblies and control rods within the reactor vessel.

APPLICABILITY:

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Manipulator crane or A.1 Suspend use of any non-Immediately auxiliary hoist non-functional manipulator functional.

crane or auxiliary hoist from operations involving the movement of fuel assemblies and control rods within the reactor vessel.

Catawba Units 1 and 2 16.9-19.-l Revision 3

Refueling Operations - Manipulator Crane 16.9-19 TESTING REQUIREMENTS TEST FREQUENCY TR 16.9-19-1 Perform a load test of > 3250 pounds for each Within 30 days manipulator crane used for movement of fuel assemblies prior to movement within the reactor vessel and demonstrate an automatic of fuel assemblies load 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 days hoist and associated load indicator used for movement of prior to movement control rods or control rod drag load testing within the of control rods or reactor vessel.

control rod drag load testing within the reactor vessel BASES The FUNCTIONALITY requirements for the manipulator cranes ensure that:

(1) manipulator cranes will be used for movement of control rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

REFERENCES

1.

Letter from NRC to Gary R. Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.

2.

10 CFR 50.59 Screen, "Changing the Testing Requirement Frequency of SLC 16.9-19", Action Request 366602, Eric Pace, September 8, 2011.

Catawba Units 1 and 2 16.9-19-2 Revision 3

Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies 16.9-26 16.9 AUXILIARY SYSTEMS 16.9-26 Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies COMMITMENT The following requirements governing containment closure and fuel building closure shall be maintained to ensure defense-in-depth:

NOTE If containment closure or fuel building closure, as applicable, is hampered by an outage activity or by a loss of power, suitable contingency actions providing an equivalent level of protection shall be developed.

a. The equipment necessary to implement containment closure shall be appropriately staged prior to maintaining any containment penetration open, including containment air lock doors. For the purposes of this SLC, the containment equipment hatch is not considered a penetration that may be maintained open; therefore, it shall be maintained closed.

b. Hoses and cables running through an open containment penetration or containment air lock shall be configured to facilitate rapid removal in the event that containment closure is required.

c. The containment air lock may be open provided the following conditions 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 to protect the air lock seals/doors or devices used to keep the air lock door open/supported do not violate this provision.

4. Personnel shall be available with the responsibility for immediate closure of at least one air lock door or for closure of an appropriate temporary door following containment evacuation.

d. Other containment penetrations may be open provided the following conditions exist:

(continued)

Catawba Units 1 and 2 16.9-26-1 Revision 0

Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies 16.9-26 COMMITMENT (continued)

1. One valve in each open penetration shall be capable of being closed, 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 necessary installation tools.

2. Personnel shall be available with the responsibility for immediate closure of the penetration opening(s) following a fuel handling accident inside containment.

e. The fuel building doors shall be maintained closed, except for normal entry and exit, OR the Fuel Handling Ventilation Exhaust System (FHVES), with associated radiation release monitoring for the release path, shall be available.

APPLICABILITY:

During movement of non-recently irradiated fuel assemblies in containment or in the fuel building, as applicable.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

COMMITMENT not met.

A.1 Suspend movement of Immediately non-recently irradiated fuel assemblies in containment or in the fuel building, as applicable.

AND A.2 Restore compliance with Prior to resuming COMMITMENT.

movement of non-recently irradiated fuel assemblies in containment or in the fuel building, as applicable TESTING REQUIREMENTS None Catawba Units 1 and 2 16.9-26-2 Revision-0

Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies 16.9-26 BASES This SLC formally documents and implements a portion of the regulatory commitments made in Reference 1, approved by the NRC via Reference 2, and subsequently modified via Reference 3 and Reference 4. These commitments were made as a means of providing additional defense-in-depth during movement of non-recently irradiated fuel assemblies in containment or in the fuel building. The commitments concerning non-recently irradiated fuel movement with an open containment equipment hatch have not been implemented in this SLC. Until such time that a methodology is developed for complying with the commitments concerning non-recently irradiated fuel movement with an open containment equipment hatch, the hatch shall be maintained closed.

In the revised analysis utilizing the Alternative Source Term for a fuel handling accident in containment, no credit is taken for containment integrity with respect to containment equipment hatch closure, containment air lock closure, containment penetration closure, or filtration by the CPES prior to release. For a postulated fuel handling accident within the fuel building', both the fuel handling accident and the weir gate drop accident analyses were revised. In the revised analyses, no credit is taken for filtration of the release by the FHVES.

The revised analyses confirmed that sufficient radioactive decay has occurred after 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months that certain existing controls are no longer necessary to ensure that the consequences of a postulated fuel handling accident remain within regulatory limits. The analysis demonstrated that a decay period of 19.5 days was sufficient to ensure that the consequences of a weir gate drop accident remain within regulatory limits.

Although not required by the accident analysis, these administrative controls were committed to be put in place during the movement of non-recently irradiated fuel. If movement of irradiated fuel assemblies were to occur prior to the 72-hour decay period, the currently existing Technical Specification controls would apply.

Administrative controls exist such that the weir gate will not be moved over spent fuel assemblies decayed less than 19.5 days.

For the purpose of this SLC, the definition of availability for the FHVES is being capable of performing its design basis functions as defined by the Technical Specification 3.7.13, "Fuel Handling Ventilation Exhaust System (FHVES)" surveillance tests.

For the purpose of this SLC, the definition of an open containment penetration is a penetration that provides direct access from the containment atmosphere to the outside environment.

Catawba Units 1 and 2 16.9-26-3 Revision 0

Commitments Associated With Movement of Non-Recently Irradiated Fuel Assemblies 16.9-26 REFERENCES

1.

Letters from G.R. Peterson, Duke, to NRC, "Proposed Amendment for Partial Scope Implementation of the Alternate Source Term and Proposed Amendment to Technical Specifications (TS) 3.7.10, Control Room Area Ventilation System, TS 3.7.11, Control Room Area Chilled Water System, TS 3.7.13, Fuel Handling Ventilation Exhaust System, and TS 3.9.3, Containment Penetrations", dated December 20, 2001, February 14, 2002, and March 26, 2002.

2.

Letter from NRC to G.R. Peterson, Duke, License Amendments 198 and 191 for Units 1 and 2, respectively, dated April 23, 2002.

3.

Letter from J.R. Morris, Duke, to NRC, "Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System", dated September 3, 2009.

4.

Letter from NRC to J.R. Morris, Duke, License Amendments 260 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 Instrumentation 16.11-7 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-7 Radioactive Gaseous Effluent Monitoring Instrumentation COMMITMENT The Radioactive Gaseous Effluent Monitoring Instrumentation channels shown in Table 16.11-7-1 shall be FUNCTIONAL with their Alarm/Trip Setpoints 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 and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

As shown in Table 16.11-7-1.

REMEDIAL ACTIONS

NOTE Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Suspend the release of Immediately Radioactive Gaseous radioactive gaseous Effluent Monitoring effluents monitored by the Instrumentation affected channel(s).

channel(s) Alarm/Trip Setpoint less OR conservative than required.

A.2 Declare the channel(s)

Immediately non-functional.

B.

One or more B.1 Enter the applicable Immediately Radioactive Gaseous Conditions and Required Effluent Monitoring Actions specified in Table Instrumentation 16.11-7-1 for the channel(s) non-channel(s).

functional.

(continued)

Catawba Units 1 and 2 116.11-7-1 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One channel non-functional.

C.,1 Verify that EMF-36 (Low Range) is FUNCTIONAL.

OR C.2.1 Analyze two independent samples of the tank's contents.

AND C.2.2 Perform independent verification of the discharge line valving.

AND 0.2.3.1 Perform independent verification of manual portion of the computer input for release rate calculations performed by computer.

OR C.2.3.2Perform independent verification of entire calculations for release rate calculations performed manually.

AND C.2.4 Restore channel to FUNCTIONAL status.

OR C.3 Suspend release of radioactive effluents via this pathway.

Prior to initiating a release Prior to initiating a release Prior to initiating a release Prior to initiating a release Prior to initiating a release 14 days Immediately (continued)

Catawba Units 1 and 2 16.11-7-2 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

One or more flow rate D.1 Estimate the flow rate of Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months measurement device the release.

during releases channel(s) non-functional.

AND D.2 Restore channel to 30 days FUNCTIONAL status.

E.

One or more Noble Gas E.1 Obtain grab samples from Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Activity Monitor effluent pathway.

during releases channel(s) non-functional.

AND E.2 Perform an analysis of Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of grab samples for obtaining the sample radioactivity.

AND E.3 Restore channel to 30 days FUNCTIONAL status.

(continued)

Catawba Units 1 and 2 16.11-7-3 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Noble Gas Activity F. 1

NOTE---------

Monitor (EMF Low In order to utilize Required Range) providing Action F.1, the following automatic termination of conditions must be release via the satisfied:

Containment Purge

1. The affected unit is in Exhaust System (CPES)

MODES 5 or 6.

non-functional.

2. EMF-36 is FUNCTIONAL and in service for the affected unit.

3. The Reactor Coolant System for the affected unit has been vented.

4. Either the reactor vessel head is in place (bolts are not required),

or if it is not in place, the lifting of heavy loads over the reactor vessel and the movement of irradiated fuel assemblies within containment have been suspended.

Restore the non-functional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channel to FUNCTIONAL status.

G.

Required Action and G.1 Suspend PURGING of Immediately associated Completion radioactive effluents via Time of Condition F not this pathway.

met.

OR Required Action F.1 not utilized.

(continued)

I Catawba Units 1 and 2 16.11-7-4 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

One or more sampler H.1 Perform sampling with Continuously channel(s) non-auxiliary sampling functional.

equipment as required by Table 16.11-6-1.

AND H.2 Restore channel to 30 days FUNCTIONAL status.

I.

One Condenser

.1-----------

NOTE -------------

Evacuation System Applicable to effluent Noble Gas Activity releases via the Condenser Monitor (EMF-33)

Steam Air Ejector (ZJ) channel non-functional.

System.

Obtain grab samples from Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months effluent pathway.

during releases AND 1.2 NOTE-------

Applicable to effluent releases via the Condenser Steam Air Ejector (ZJ)

System.

Perform an analysis of Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of grab samples for obtaining the sample radioactivity.

AND (continued)

Catawba Units 1 and 2 16.11-7-5 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

1.

(continued) 1.3 NOTE -------------

Applicable to effluent releases via the Steam Generator Blowdown (BB)

System atmospheric vent valve (BB-27) in the off-normal mode.

Perform an analysis of grab samples for radioactivity at a lower limit of detection of 10-7 microCurie/ml.

AND 1.4 Restore channel to FUNCTIONAL status.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during releases when secondary specific activity is >

0.01 microCurie/gm DOSE EQUIVALENT 1-131 AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during releases when secondary specific activity is <

0.01 microCurie/gm DOSE EQUIVALENT 1-131 30 days J.

Noble Gas Activity Monitor (EMF Low Range) providing automatic termination of release via the Containment Air Release and Addition System non-functional.

J.1 Verify that EMF-36 is FUNCTIONAL.

OR J.2.1 Analyze two independent samples of the containment atmosphere.

AND Prior to initiating a release Prior to initiating a release (continued)

Catawba Units 1 and 2 16.11-7-6 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME J.

(continued)

J.2.2 Perform independent verification of the discharge line valving.

AND J.2.3.1 Perform independent verification of manual portion of the computer input for release rate calculations performed by computer.

OR J.2.3.2 Perform independent verification of entire calculations for release rate calculations performed manually.

AND J.2.4 ---------

NOTE-------

If channel remains or is anticipated to remain non-functional for > 90 days, re-evaluate the configuration of the affected unit in accordance with the applicable portions of 10 CFR 50.59 and 10 CFR 50.65(a)(4) prior to expiration of the 90-day period.

Prior to initiating a release Prior to initiating a release Prior to initiating a release 30 days

.Restore channel to FUNCTIONAL status.

(continued)

Catawba Units 1 and 2 16.11-7-7 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K.

Required Action and K.1 Explain why the non-In the next associated Completion functionality was not scheduled Time of Condition C, D, corrected within the Radioactive Effluent E, F, H, I, or J not met.

specified Completion Time.

Release Report pursuant to Technical Specification 5.6.3 TESTING REQUIREMENTS NOTE --------------------------------------------------------

Refer to Table 16.11-7-1to determine which TRs apply for each Radioactive Gaseous Effluent Monitoring Instrumentation channel.

TEST FREQUENCY TR 16.11-7-1 Perform CHANNEL CHECK.

Prior to each release TR 16.11-7-2 -----.......--------------

NOTE ---------------------------------

For Instruments la, 4, and 5, a SOURCE CHECK for these channels shall be the qualitative assessment of channel response when the channel sensor is exposed to a light-emitting diode.

Perform SOURCE CHECK.

Prior to each release TR 16.11-7-3 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TR 16.11-7-4 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Instrumentation 16.11-7 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.11-7-6

NOTE For Instruments 2 and 3a, a SOURCE CHECK for these channels shall be the qualitative assessment of channel response 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 shall also demonstrate, as applicable, that automatic isolation of this pathway and control room alarm annunciation (for EMF-58, alarm annunciation is in the Monitor Tank Building control room and on the Monitor Tank Building control panel remote annunciator panel) occur if any of the following conditions exist:

a.

Instrument indicates measured levels above the Alarm/Trip Setpoint, or

b.

Circuit failure/instrument downscale failure (alarm only)

Perform COT.

9 months TR 16.11-7-8

NOTE For Instrument 4, the COT shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exist:

a.

Instrument indicates measured levels above the Alarm/Trip Setpoint, or

b.

Circuit failure/instrument downscale failure (alarm only)

Perform COT.

18 months (continued)

Catawba Units 1 and 2 16.11-7-9 Revision' 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.11-7-9 NOTE For Instruments la, 2, 3a, 3c, 4, 5, and 6a, the initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have 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 Instrumentation 16.11-7 Table 16.11-7-1 Radioactive Gaseous Effluent Monitoring Instrumentation (page 1 of 2)

INSTRUMENT REQUIRED CONDITIONS APPLICABLE TESTING CHANNELS 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 16.11-7-1 Alarm and Automatic Termination of when the isolation TR 16.11-7-2 Release valve is closed and TR 16.11-7-7 (EMF 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 16.11-7-1 Device when the isolation TR 16.11-7-9 valve is closed and locked

2.

Condenser Evacuation System Noble 1

A, I, K When air ejectors TR 16.11-7-3 Gas Activity Monitor are in operation TR 16.11-7-6 (EMF-33) (BB-27 is only isolation (Apply Required TR 16.11-7-7 function required) (Note 1)

Action 1.3 when air TR 16.11-7-9 ejectors are not in operation)

3.

Vent System 3.a Noble Gas Activity Monitor 1

A, E, K At all times TR 16.11-7-4 (EMF Low Range)

TR 16.11-7-6 TR 16.11-7-7 TR 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 16.11-7-7 TR 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 16.11-7-2 Activity Monitor - Providing Alarm and TR 16.11-7-3 Automatic Termination of Release TR 16.11-7-8 (EMF Low Range)

TR 16.11-7-9 (continued)

Catawba Units 1 and 2 16.11-7-11 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 Table 16.11-7-1 Radioactive Gaseous Effluent Monitoring Instrumentation (page 2 of 2)

INSTRUMENT REQUIRED CONDITIONS APPLICABLE TESTING CHANNELS MODES REQUIREMENTS

5.

Containment Air Release and Addition A, J, K 1, 2, 3, 4, 5, 6 TR 16.11-7-2 System Noble Gas Activity Monitor -

TR 16.11-7-3 Providing Alarm and Automatic TR 16.11-7-7 Termination of Release TR 16.11-7-9 (EMF Low Range)

6.

Monitor Tank Building HVAC 6.a Noble Gas Activity Monitor - Providing 1 per station A, E, K At all times TR 16.11-7-4 Alarm (Note 2)

TR 16.11-7-6 (EMF 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 Instrumentation 16.11-7 BASES The Radioactive Gaseous Effluent Monitoring Instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the.gaseous effluent release requirements of SLC 16.11-8 shall be 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 the continued operation of the CPES with EMF-39 initially FUNCTIONAL. Continued operation of the CPES is contingent upon the ability of the affected unit to meet the requirements as noted in Required Action F.1.

TR 16.11-7-7 requires the performance of a COT on the applicable Radioactive Gaseous Effluent Radiation Monitors. The test ensures that a signal from the control room module can generate the appropriate alarm and actuations. The required actuations/isolations for a High Radiation condition (i.e., radiation level above its Trip 2 setpoint) are listed below for each monitor.

OEMF Waste Gas Discharge Monitor 1WG160 closes when EMF-50 detects radiation level above its setpoint.

1/2EMF Condensate Steam Air Ejector Exhaust Monitor The following actuations occur when EMF-33 detects radiation level above its setpoint:

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 the negative effects on the Blowdown System with the unit at power.

b.

Testing during innages will be by verification of relay contacts opening in the valve circuit.

2.

Closure of BB24, BB65, BB69, and BB73 is required to minimize the amount of potentially contaminated material being delivered to the Blowdown Tank.

3.

Closure of NM269, NM270, NM271, and NM272 is required to minimize the amount of potentially contaminated material being delivered to the Conventional Sampling System.

4.

Closure of NM267 is required to minimize the amount of potentially contaminated material being delivered to the Condensate Storage Tank by isolating flow through EMF-34.

5.

Closure of BB48 is required to minimize the amount of potentially contaminated material being delivered from the Blowdown System discharge to the Turbine Building sump.

Catawba Units 1 and 2 16.11-7-13 Revision 6

Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 BASES (continued) 1/2EMF Unit Vent Noble Gas Monitor The following actuations occur when EMF-36 detects radiation level above its setpoint:

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 Unit Vent Particulate Monitor (Sampler)

The following actuations occur when EMF-35 detects radiation level above its setpoint:

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 Containment Noble Gas Monitor The following actuations occur when EMF-39 detects radiation level above its setpoint:

1.

Signals are provided to both trains of the Solid State Protection System (SSPS) to initiate a CPES isolation. This is verified by observing that Relays K615 in the SSPS A output cabinet and the SSPS B output cabinet are latched.

2.

EMF-39 isolates the CPES without going through the SSPS by stopping CPES supply fans A and B, CPES exhaust fans A and B, and by closing the appropriate valves and dampers.

3.

Containment Evacuation Alarm, unless the source range trip is blocked.

OEMF-58 This monitor provides no control function.

TR 16.11-7-8 requires the performance of a COT on the Containment Noble Gas Monitor, 1/2EMF-39. The test ensures that a signal from the control room module can generate the appropriate alarm and actuations. The required actuations/isolations for a High Radiation condition (i.e., radiation level above its Trip 2 setpoint) are listed below.

1/2EMF Containment Noble Gas Monitor The following actuations occur when EMF-39 detects radiation level above its setpoint:

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 Instrumentation 16.11-7

1.

Catawba Offsite Dose Calculation Manual.

2.

10 CFR Part 20.

REFERENCES Catawba Units 1 and 2 16.11-7-15 Revision 6

ML12088A291

Text

16.1 INTRODUCTION

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