ML20137G895
| ML20137G895 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/27/1997 |
| From: | Horn G NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-06, GL-96-6, NLS970058, NUDOCS 9704010578 | |
| Download: ML20137G895 (3) | |
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GENERAL OFFICE P 0. BOX 499. COL UMBUS. NEBRASKA 68602-0499 Nebraska Public Power District
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a G. R. Horn Senior Vice-President, Energy Supply (402) 563-5518 NLS970058 March 27,1997 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
Subject:
Response to NRC Generic Letter 96-06 Cooper Nuclear Station, NRC Docket 50-298, DPR-46
Reference:
- 1. NRC Generic Letter 96-06 dated September 30,1996," Assurance of Equipment Operability and Containment Integrity during Design-Basis Accident Conditions"
- 2. Letter to USNRC from G.R. Horn (NPPD) dated October 28,1996," Response to NRC Generic Letter 96-06"
- 3. Letter to USNRC from G.R. Horn (NPPD) dated January 28,1997," Response to NRC Generic Letter 96-06" This submittal provides the Nebraska Public Power District's follow up response to NRC Generic Letter (GL) 96-06 (Reference 1) committed to in Reference 3. In Reference 3 the District noted that there were six safety-related containment penetrations which were susceptible to the effects of thermal overpressurization. Reference 3 committed to further evaluation of these six penetrations and to provide the NRC with a follow up letter describing the results of these evaluations and the corrective actions planned to maintain containment integrity. The following is a summary of the results of the evaluations and the corrective actions which will be taken during the next planned outage, scheduled to begin March 28,1997.
Penetration X8:
Size 3", Main Steam Drainline, further investigation showed that this line is normally hot during power operation since the primary isolation valves are maintained in the open position. Thus there is no overpressurization effects on O300 %
this line post accident since the initial temperature in the line is about the same as the drywell temperature post accident, and therefore no modification is necessary.
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_ _ _ _ _ _ _. _ _.. _ _. = _... i NLS970058 March 27,1997 Page 2' b Penetration X12: Size 20", Residual Heat Removal Shutdown Cooling Suction. An analysis is currently being performed to determine acceptability of the current i i configuration. The current configuration will be verified during the scheduled
- L refueling outage. If the current configuration does not meet the requirements, a modification will be implemented during the upcoming outage to alleviate any overpressurization concerns with this line.
l Penetration X14: Size 6", Reactor Water Clean-up Suction, further investigation showed that - this line is normally hot during power operation since the primary isolation j.. valves are maintained in the open position. Thus there is no overpressurization effects on this line post accident since the initial i temperature in the line is about the same as the drywell temperature post accident, and a plant modification is not required. 4 i Penetration XI8: Size 3", Drywell Equipment Sump Discharge, a modification will be i implemented during the outage to install a relief valve that will alleviate any overpressurization concerns with this line. This is a preliminary modification - pending SORC approval. ) Penetration X19: Size 3", Drywell Floor Sump Discharge, a modification will be implemented during the outage to install a relief valve that will alleviate any ) overpressurization concerns with this line. This is a preliminary modification j pending SORC approval. i l Penetration X20: Size 4", Demineralized Water Header Supply, a modification will be j implemented during the outage to install a spectacle flange and procedurally drain the containment piping, alleviating any overpressurization concerns j with this line. This is a preliminary modification pending SORC approval. a Should you have any questions concerning this matter, please contact me. [ Sine rely, i b~~ rn i ior ice President - Energy Supply /nr 1 { cc: Regional Administrator Senior Resident Inspector l USNRC - Region IV USNRC Senior Project Manager NPG Distribution USNRC -NRR Project Directorate IV-1 j 1
l ATTACHMENT 3 LIST OF NRC COMMITMENTS l Correspondence No: NLS970058 The 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 I this document or any associated regulatory commitments. COMMITTED DATE i COMMITMENT OR OUTAGE The current configuration for penetration X12 will be verified during the scheduled refueling outage. If the RFOl6 current configuration does not meet the requirements, a modification will be implemented during the upcoming outage to alleviate any overpressurization concerns. A modification will be implemented for penetration X18 RFOl6 during the outage to install a relief valve that will alleviate any overpressurization concern with this line. A modification will be implemented for penetration X19 RFOl6 during the outage to install a relief valve that will alleviate any overpressurization concerns with this line. A modification will be implemented for penetration X20 during the outage to install a spectacle flange and RFOl6 procedurally drain the containment piping, alleviating any overpressurization concern with this line. i l l l l PROCEDURE NUMBER 0.42 l REVISION NUMBER 4 l PAGE 3 OF 9 l}}