ML20083A134
| ML20083A134 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/02/1995 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20083A131 | List: |
| References | |
| NUDOCS 9505100051 | |
| Download: ML20083A134 (4) | |
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Appendix to'.-
NLS950075 May-2,1995 APPENDIX MARKED-UP AND REVISED AFFECTED TECHNICAL SPECIFICATION PAGE 162 9505100051' 950502
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. LIMITING CONDITIONS FOR OPERATION-SURVEIIIANCE REOUTREMENTS 3.7.A (Cont'd) 4.7.A.2.e (cont'd) repeated provided locally measured leakage. reductions, achieved by repairs, reduce the containment's overall measured leakage.rato sufficiently to meet the acceptance criteria.
f.
Local Imak Rate Tests 1.
With the exceptions specified below, local leak rate tests (LlAT's) shall be performed on the primary containment testable penetrations and isolation valves at'a pressure D of 58 psig during each reactor 7 shutdown for refueling, or other convenient intervals, but in no casef at intervals greater than tv ar The test duration of all valves an g
penetrations shall be of sufficient length to determine repeatable results.
The total acceptable leakage for. all valves and penetrations other than the MSIV's is 0.60 La.
2.
Bolted double-gasket seals shall be tested after each opening and during l
each reactor shutdown for refueling, or other convenient intervals but in j
no case at intervals-greater than two years.
3.
The main steam isolation valves-(MSIV's) shall be_ tested at a pressure - of 29 psig.
If a total leakage rate of 11.5 sef/hr for any one MSIV is exceeded, repairs and retest shall be performed to correct the condition. 'Ihis is an exemption to Appendix ~J of 10CFR50.
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t,rwrTT51a enNDITTONM FOR OPERATTON sURVETLIJLNcE REOUTREMFMTS 3 '.7. A ' (Cont ' d) ~
4.7.A.2.e (cont'd) repnated provided locally' measured leakage reductions, achieved by:
repairs, reduce the containment's-overall measured leakage rate sufficiently to meet the acceptance criteria, f,
Lot-a l T.amlr Rate Tests
'1.
With the execptions specified.
l below, local leak rate testa (LLRT's) shall be performed on the primary containment testable l
penetrations and isolation valves at a pressure of 58 psig during each reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years *.
l The test duration of all valves and penetrations shall be of sufficient length to determine repeatable results. The total acceptable leakage for all valves and penetrations other than the MSIV's is 0.60 La.
2.
Bolted double-gasket seals shall be tested after each opening and-during each reactor shutdown for refueling, or other convenient intervals but in no case at intervals greater than two years.
3.
The main steam isolation valves (MSIV's) shall'be tested at a pressure of 29 psig. If a total leakage rate of 11.5 scf/hr for any one MSIV is exceeded, repairs and retest shall be performed to-correct the condition. This is an exemption to Appendix J of 10CFR50.
The two year interval requirement for Penetrations DWH and X-4 (Drywell Head and Manport) may be extended until completion of Refueling Outage No. 16 (RE-16).
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LIST OF NRC COMMITMENTS l ATTACHMENT 3 l
Correspondence No: NLS950075 ne following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE Contingent upon NRC approval, perform Type B LLRTs on the Drywell Head RE-16 and Manport (Penetrations DWil and X-4 respectively) prior to the conclusion of Refueling Outage No.16 (RE-16).
PROCEDURE NUMBER 0.42 l
REVISION NUMBER 0 l
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