ML20148G025

Revised Pages to Selected License Commitments Manual, Chapters 16.10.1 & 16.10.2 Re Steam Vent to Atmosphere & Condenser Circulating Water Sys,Respectively

ML20148G025
Person / Time
Site:	Catawba
Issue date:	05/13/1997
From:	Kitlan M DUKE POWER CO.
To:
References
PROC-970513, NUDOCS 9706050137
Download: ML20148G025 (5)

Text

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. Duke Ibwer Company (803)s31 3000 Catawba Nxlear Station 4800 Concord Road  ;

York. SC29745

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' DUKEPOWER May 13,1997 l

RE: Catawba Nuclear Station Selected License Commitment Manual Please update the following Selected License Commitments (SLC) due to an administrative error:

16.10.1 - Steam Vent to Atmosphere 16.10.2 - Condenser Circulating Water System Remove Insert s

SLC 16.10.1 SLC 16.10.1 Page 1 of 2 Page 1 of 2 i Page 2 of 2 Page 2 of 2 l

SLC 16.10.2 SLC 16.10.2 Page 1 of 2 Page 1 of 2 Page 2 of 2 Page 2 of 2 I

If you have any questions conceming contents of this package update, contact Denise Smith at 803-831-3810. 1

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FOR M. . Kitlan, Jr., anager Regulatory Compliance - CNS l

Attachments 6

9706050137 970513 PDR P

ADOCK 05000413 PDR D-  !

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- 16.10 STEAM AND POWER CONVERSION SYSTEM -

i 16.10.1 STEAM VENT TO ATMOSPHERE COMMITMENT:

Four steam generator PORV safety-related gas supply systems shall be OPERABLE with both nitrogen bottles per S/G PORV, pressurized to greater than or equal to 2100 psig.

APPLICABILITY:

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Modes 1, 2, 3,4* )

J REMEDIAL ACTION.  ;

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a. With qDe nitrogen bottle on one or more S/Gs less than 21--psig, )

immediately start corrective action to retum the nitrogen supply to l i OPERABLE. Work to return the nitrogen supply to OPERABLE status should continue without interruption.

b. With two nitrogen bottles on one or more S/Gs less than 2100 psig, q  ;

lQ consider the PORV(s) inoperable and refer to Technical Specification 3.7.1.6 for the required action.

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1 TESTING REQUIREMENTS:

a At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that _gth nitrogen bottles per S/G PORV l

. has a pressure greater than or equal to 2100 psig.

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REFERENCES:

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1) Design Basis Specification for the Catawba Main Steam System, Main l

Steam Vent to Atmosphere and Main Steam Bypass to Condenser l System, Section 20.3.4 3

, 2) PIR 0-C90-0304 4

3) Branch Technical Position RSB5-1

4) CNC-1223.43-01-0011, rev 1

• When Steam Generators are being used for decay heat removal.

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. O Chapter 16.10.1 Page 1 04/30/97

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BASES:

Design Engineering calculation CNC-1223.43-01-0011, rev 1, demonstrates that with gag nitrogen bottle charged to at least 2100 psig, sufficient nitrogen exists to meet the Tech Spec Design basis of the S/G PORVs.

A revision to calculation CNC-1223.43-01-0011 also demonstrates that with two l nitrogen bottles charged to as least 2100 psig, sufficient nitrogen exists to meet j the Branch Technical Position RSBS-1 of supporting a controlled cooldown to the l point where residual heat removal system can be put in service with or without 1 offsite power following an earthquake. j l

The COMMITMENT for having kgth nitrogen bottles pressurized to greater than .

or equal to 2100 psig and the REMEDIAL ACTION, is adequate to ensure the l intent of our FSAR commitment to Branch technical Position RSB5-1 is met. l r

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1 Chapter 16.10.1 Page 2 04/30/97

r 16.10 STEAM AND POWER CONVERSION SYSTEM

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16.10.2 CONDENSER CIRCULATING WATER SYSTEM COMMITMENT:

i With the Condenser Cooling Water System (RC) partially or completely filled, the 4 system boundaries within the Turbine Building and RC pump pit shall be in their

normal alignment.

APPLICABILITY:

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

REMEDIAL ACTION:

Restore the RC System boundaries to the normal commitment alignment in accordance with the Risk Assessment Matrix priorities.

TESTING REQUIREMENTS:

O None

REFERENCES:

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 the Maintenance Rule i

4 b V Chapter 16.10.2 Page 1 01/15/97

t BASES:

! The effective implementation of the Maintenance Rule,10 CFR 50.65, requires the continuous assessment of systems determined Risk Significant in the l 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 (1) It defines the Risk Significant concems of the Condenser Circulating Water, 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. Da.nage 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 concem from this event includes either RC System of Unit 1 or Unit 2 leading to the affect on either Unit / Train transformers.

(2) This SLC also provides a method of tracking this function for intersystem configuration control of the Essential Transformers and their susceptibility to flooding through support of WPM 607 and 10 CFR 50.65.

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V Chapter 16.10.2 Page 2 01/15197