ML20211M918
| ML20211M918 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/09/1997 |
| From: | Graham P NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-298-97-07, 50-298-97-7, NLS970178, NUDOCS 9710150177 | |
| Download: ML20211M918 (5) | |
Text
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i COOPER NUCLEAR STATON P.O. 90X 98. BROW'NLLE. NEBRASKA 68321 Nebraska Public Power District
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NLS970178 October 9,1997
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l U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
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Subject:
Reply to a Notice of Violation NRC Inspection Report No. 50-298/97-07 Cooper Nuclear Station, NRC Docket 50-298, DPR-46
Reference:
1.
Letter to G. R. Horn (NPPD) from T. P. Gwynn (USNRC) dated September 4,1997, "NRC Inspection Report 50-298/97-07, Notice of Violation" By letter dated September 4,1997 (Reference 1), the NRC cited Nebraska Public Power District (District) as being in violation of NRC requirements. This letter, including Attachment 1, constitutes the District's reply to the referenced Notice of Violation in accordance with 10 CFR 2.201. The District admits to the violation and has completed all of the corrective actions necessary to return Coopei Nuclear Station (CNS) to full compliance with respect to the cited violation.
This NOV response was due on October 6,1997, however, as explained in the October 7,1997 telephone call betwcen CNS licensing and NRC personnel, extra time was required to provide a full and accurate description of the cause of the events leading to the NOV and the appropriate corrective actions required to prevent re-occurrence.
Should you have any questions concerning this matter, please contact me.
Sincerely, fU &
P. D. Graham Jj Vice President of Nuclear Energy 1
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NLS970178 LOctober 8,1997 Page 2 cc:
Regional Administrator USNRC - Region IV Senior Project Maruger USNRC - NRR Project Directorate IV-1 Senior Resident Inspector USNRC
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to NLS970178 Page1of2 j
I REPLY TO SEPTEMBER 4,1997, NOTICE OF VIOLATION COOPER NUCLEAR STATION NRC DOCKET NO. 50-298, LICENSE DPR-46 During NRC inspection activities conducted May 18 through June 28,1997, a violation of NRC requirements was identified. The paniculu violation and the District's reply are set forth below:
Violation TechnicalSpecification 6.3.3.A requites, inpart, that routine testprocedures be provided to satisfy operating license requirements, such as routine testing of equipment required by the TechnicalSpecifications.
Contrary to the above:
- 1. On July 31, the inspector identified that Procedure 6.PC.308, "DrywellPressure Suppression Chamber Vacuum Breaker Cahoration andFunctional Test, " a routine test procedure, did not satisfy operating license requirements in that plant conditions caused a differentialpressure across the torus-to-drywell vacuum breakers during hftforce testing which was not addressedin the acceptance criteria or evaluation offorces on the mlve.
- 2. On May 4,1997, Valve RHR-MOV-MO34B was tested witi, a routine test procedure which was not appropriate in that a modification of the whv was not reflectedin the test stroke time limit.
1his is a Severity LevelIV violation. (Supplement 1) (298/97007-05)
Adminion or Denial to Violation The District admits the violation.
Reason for Violation The apparent cause for this violation is a weakness in the post-maintenance and post-modification testing processes which allowed specification of testing without verification that such testing is appropriate for the plant conditions.
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e to NLS970178 Page 2 of 2 Corrective Steos Taken and tne Results Achieved The following immediate actions have been taken:
- 1) Procedure 6.PC.308 was revised on August 1,1997, to require that the drywell and to ventilation are secured and drywell to torus vacuum breakers me opened to equalize t pressure between the drywell and the torus prior to the performance of the test.
- 2) The torus-to-drywell surveillance test was performed following the above revision of procedure 6.PC.308 with satisfactory results.
- 3) Procedure 6.2RHR.201 was revised to include,in the IST Retest and Operability L effects of the modification on the RHR-MOV-MO34B valve.
Corrective Steos That Will Be Taken to Avoid Further Violations An assessment of the post-maintenance / post-modification testing processes will be determine the effectiveness of these processes to specify the appropriate ini'.ial test co Date When Full Comnliance Will Be Achieved The District is in full compliance with respect to the cited violation.
-l ATTACHMqNT 4 LIST OF NRC COMMETMEMTS l
Correspondence No: NLS970178 The following table identifies those actions conndtted 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 t7e Licensing Manager at Cooper Nuclear Station of sny questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE,_
Revise procedure 6.PC.308 to require that the drywell and torus ventilation are secured and drywell to torus vacuur breakers are opened to equalize the pressure between the Complate drywell and the torus prior to the performance of the test Revise procedure 6.2RHR.201 to include in the IST Retest I
and Operability Limits the effects of the modification on Complete the RHR-MOV-MO34B valve An assessment of the post-maintenance / post-modification testing processes will be performed to dete;mine the January 20,1998 effectiveness of these procesces to specify the appropriate initial test conditions I
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PROCEDURE NUMBER 0.42 l
REVISION NUMBER 5 l
PAGE 8 OF 9 l
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