ML20135A858

Revised Selected License Commitment Manual

ML20135A858
Person / Time
Site:	Catawba
Issue date:	01/15/1997
From:	DUKE POWER CO.
To:
References
PROC-970115, NUDOCS 9702270458
Download: ML20135A858 (22)

Text

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-, Duke Poun Company (WB)MI 3000 Catau ba Nuclear Station 07far"#" &///3/@/

O DUKEPOWER February 12,1997 RE: Catawba Nuclear Station Selected License Commitment Manual Please add the following new Selected License Commt.ients (SLC):

16.8.2 - 230 KV Switchyard Systems 16.8.3 - 230 KV Switchyard 125 VDC Power System 16.'O.2 - Condenser Circulating Water System Remove Insert LOEP 1 - 10 LOEP 1 - 10 Table of Contents Table of Contents Q

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Page 1 Page 1 of 2 Page 2 of 2 16.8 Table of Contents 16.8 Table of Contents SLC 16.8.2 Page 1 of 2 i Page 2 of 2 j l

1 SLC 16.8.3 Page 1 of 2 Page 2 of 2 16.10 Table of Contents SLC 16.10.2 I Page 1 of 2 I Page 2 of 2

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9702270458 970115 /

PDR ADOCK 05000413 F PDR p)270093 L

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If you have any questions concerning contents of this package update, contact Denise Smith at 803-831-3810.

I A Fon.

M.S. Kitlan, r., Manager Regulatory Compliance - CNS )

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I Apnendix i

Compliance Function Area Manual, Section 3.8

" Selected Licensee Commitments" Page 10 of 10 01/15/97

CATAWBA NUCLEAR STATION O FINAL SAFETY ANALYSIS REPORT l SELECTED LICENSEE COMMITMENTS Table of Contents 4

16.0 Selected Licensee Commitments 16.1 Introduction 16.2 Applicability 16.3 Definitions 16.4 Commitments Related to Reactor Components 16.5 Commitments Related to Reactor Coolant System 16.6 Commitments Related to Engineered Safety Features (Non-ESF Systems) 16.7 Commitments Related to Instrumentation 16.8 Commitments Related to Electrical Power Systems I

16.8.2 230 KV Switchyard Systems 16.8.3 230 KV Switchyard 125 VDC Power System 16.9 Commitments Related to Auxiliary Systems 1

16.9.1 Fire Suppression Water Systems l 16.9.2 Spray and/or Sprinkler Systems 16.9.3 CO2 Systems 16.9.4 Fire Hose Stations 16.9.5 Fire Barrier Penetrations 16.9.6 Fire Detection Instrumentation l 16.10 Commitments Related to Steam and Power Conversion Systems 16.10.2 Condenser Circulating Water System l 16.11 Commitments Related to Radioactive Waste Management 16.12 Commitments Related to Radiation Protection 10.13 Commitments Related to Conduct of Operations O Chapter 16.0 Page 1 of 2 1/15/97

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2 CATAWBA NUCLEAR STATION l FINAL SAFETY ANALYSIS REPORT

SELECTED LICENSEE COMMITMENTS Table of Contents 16.13.1 Fire Brigade l 16.14 Commitmer N Related to Refueling Operations Appendix Compliance Functional Area Manual, Section 3.8 4

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! CHAPTER 16.8

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ELECTRICAL POWER SYSTEMS Table of Contents

! i 16.8.1 Containment Penetration Conductor Overcurrent Protective Devices 4

l l 16.8.2 230 KV Switchyard Systems l 1 1

16.8.3 230 KV Switchyard 125 VDC Power System i

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l-1L6_ 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 Transfortners, 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). .

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c. Buslines 1 A,1B (from Main Stepup Transformers to Switchyard Unit  !

PCBs), including their associated Motor Operated Disconnects, Coupling 1 Capacitor Voltage Transformers, Interconnecting Bus, and Support Structures (EBA system).

d. Buslines 2A,2B (from Main Stepup Transformers to Switchyard Unit i PCBs), including their associated Motor Operated Disconnects, Coupling

• Capacitor Voltage Transformers, Interconnecting Bas, 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). l l

g. 480 VAC Aux Power Load Centers STA for both Units Train A, STB for ,

I both Units Train B (EBI system).

h. 125 VDC Aux Power (EBH system). See SLC 16.8-3.

APPLICABILITY:

At all times in accordance with Technical Specifications (all Modes) and Site Directive 3.1.30 (Mcdes 4,5, & 6).

D l d Chapter 16.8.2 Page 1 01/15/97

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l s-1 l REMEDIAL ACTIONS:

Return Switchyard equipment to the normal commitment alignment in

accordance with Risk Assessment Matrix priorities.

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TESTING REQUIREMENTS: ,

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-None

REFERENCES:

10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants WPM 607, Maintenance Rule Assessment of Equipment out of Service .

CNC-1535.00-00-0008, Severe Accident Analysis Report, CNS PRA Risk Significant SSCs for the Maintenance Rule.

CNS-010.01-EB-0001, Switchyard Design Basis Specification TECH SPEC sections 3.8.1.1. and 3.8.1.2, LCOs for AC Power Sources during Operating and Shutdown modes SITE DIRECTIVE 3.1.30, Unit Shutdown Configuration Control 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 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 defiries the Risk Significant l portions of the Switchyard. It also provides a method of tracking the Switchyard Systems for the purposes of supporting 10 CFR 50.65 and WPM 607.

O Chapter 16.8.2 Page 2 01/15/97

16J ELECTRICAL POWER SYSTEMS 16.8.3 230 KV SWITCHYARD 125 VDC POWER SYSTEM COMMITMENT:

With the Switchyard in service, providing a power exchange between the site and the transmission grid, the 230 KV Switchyard 125 VDC Power System (EBH) shall be AVAILABLE, with a minimum of one battery (SYB-1 or SYB-2) and one charger (SYBC-1, SYBC-S, or SYBC-2) aligned to each distribution bus.

This will provide an adequate, uninterruptable power source for relaying, control, and associated equipment requirements for normal switchyard operations.

APPLICABILITY:

At all times. l REMEDIAL ACTION:

Restore to the normal commitment alignment in accordance with the Risk i

Assessment Matrix priorities.

r b TESTING REQUIREMENTS:

Periodic Tests performed in accordance with the IEEE Std 450-1980, "lEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations".

REFERENCES:

4 IEEE Std 450-1980, "lEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations".

WPM 607, Maintenance Rule Assessment of Equipment out of Service 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.

SAAG File: 160 Severe Accident Analysis Report, CNS Probability Risk Assessment (PRA) Risk Significant SSCs for the Maintenance Rule.

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BASES:

The effective implementation of the Maintenance Rule,10 CFR 50.65, requires the continuous assessment of systenis determined to be Risk Significant in the ,

protection against Core Damage or Radiation Release. it has been determined l through PRA numerical methods that portions of the Switchyard Systems are '

Risk Significant from the standpoint of being able to recover from the Loss of Offsite Power Events. This SLC serves two purposes. It defines the Risk  :

Significant portion of the Relaying and Power Control System of the Switchyard  !

through acceptable EBH system configuration alignments. It also provides a  :

method of tracking the Relaying and Power Control System for the purposes of  ;

supporting 10 CFR 50.65 and WPM 607.  !

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CATAWBA NUCLEAR STATION

f FINAL SAFETY ANALYSIS REPORT l SELECTED LICENSEE COMMITMENTS l CHAPTER 16.10 l

l STEAM AND POWER CONVERSION SYSTEM 4

Table of Contents 1

1 16.10.1 Steam Vent to Atmosphere

! 16.10.2 Condenser Circulating Water System s

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16.10 STEAM AND POWER CONVERSION SYSTEM A

, 'Q 16.10.2 CONDENSER CIRCULATING WATER SYSTEM COMMITMENT:

With the Condenser Cooling Water System (RC) partially or completely filled, the i system boundaries within the Turbine Building and RC pump pit shall be in their

normal alignment.

f APPLICABILITY:

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All Plant conditions which require the availability of the 6900/4160V Essential j Transformers: (SATA, SATB,1 ATC,1 ATD, 2ATC, 2ATD) for EITHER Train and '

for EITHER Unit.

1 REMEDIAL ACTION:

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Restore the RC Svstem boundarios to the normal commitment alignment in '

accordance with ene Risk Assessment Matrix priorities.

TESTING REQUIREMENTS:  !

l None

REFERENCES:

, i l CNS FSAR, Section 10.4.5.3

WPM 607, Maintenance Rule Assessment of Equipment out of Service 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.

SAAG File: 160 Severe Accident Analysis Report, CNS Probability Risk Assessment (PRA) Risk Significant SSCs for tne Maintenance Rule Chapter 16.10.2 Page 1 01/15/97

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v BASES; l

The effective implementation of the Maintenance Rule,10 CFR 50.65, requires the continuous assessment of systems determined Risk Significant in the protection against Core Damage or Radiation Release. It has been determined through PRA numerical methods that this system function provides a significant contribution to the defense in the prevention of a Loss of Offsite Power Event.

This SLC serves two purposes.

(1) It defines the Risk Significant concerns of the Condenser Circulating W-ter, i RC System integrity with respect to flooding EITHER Units 6900/4160V Essential Transformers. A failure to control the RC system inventory while partially or completely full has the potential consequence of degrading the power function of the 6900/4160 V Essential Transformers for either or both units. Damage to these transformers may result in either the Loss of Offsite Power (LOOP) or a significant decrease in the defense of Accident Mitigating Equipment. The i concern from this event includes either RC System of Unit 1 or Unit 2 leading to the affect on either Unit / Train transformers. j i

(2) This SLC also provides a method of tracking this function for intersystem  !

configuration control of the Essential Transformers and their susceptibility to l O flooding through support of WPM 607 and 10 CFR 50.65.  !

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i rh Chapter 16.10.2 Page 2 01/15/97