ML20148G025
| 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 g.
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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 SLC 16.10.2 SLC 16.10.2 Page 1 of 2 Page 1 of 2 Page 2 of 2 Page 2 of 2 If you have any questions conceming contents of this package update, contact Denise Smith at 803-831-3810.
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FOR M.. Kitlan, Jr.,
anager Regulatory Compliance - CNS l
Attachments 6
9706050137 970513 PDR ADOCK 05000413 D-P PDR MM lillillillilglylilly!Il
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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*
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J REMEDIAL ACTION.
a.
With qDe nitrogen bottle on one or more S/Gs less than 21--psig,
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i immediately start corrective action to retum the nitrogen supply to 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
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3.7.1.6 for the required action.
1 TESTING REQUIREMENTS:
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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 has a pressure greater than or equal to 2100 psig.
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REFERENCES:
j 1)
Design Basis Specification for the Catawba Main Steam System, Main 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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Chapter 16.10.1 Page 1 04/30/97
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- O BASES:
J 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 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.
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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.
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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 system boundaries within the Turbine Building and RC pump pit shall be in their 4
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
bV Chapter 16.10.2 Page 1 01/15/97 4
t BASES:
The effective implementation of the Maintenance Rule,10 CFR 50.65, requires l
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 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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