ML111430704
| ML111430704 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/03/2011 |
| From: | Lynnea Wilkins Plant Licensing Branch IV |
| To: | O'Grady B Nebraska Public Power District (NPPD) |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| References | |
| TAC ME5287 | |
| Download: ML111430704 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 3, 2011 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR REDUCING THE NUMBER OF TECHNICAL SPECIFICATION 3.4.3 REQUIRED SAFETY RELIEF VALVES (TAC NO. ME5287)
Dear Mr. O'Grady:
By letter dated January 5, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110100291), Nebraska Public Power District requested an amendment to Renewed Facility Operating License No. DPR-46 for Cooper Nuclear Station, and Appendix A, Technical Specifications (TSs), of the facility operating license. The proposed amendment would revise TS 3.4.3, "Safety/Relief Valves (SRVs) and Safety Valves (SVs)," to reduce the number of SRVs required to be OPERABLE for over-pressure protection from eight to five.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your submittal and determined that the information specified in the enclosed request for additional information (RAI) is needed for the staff to complete its evaluation. The RAI was discussed with Mr. Edward McCutchen of your staff during a site visit on May 4, 2011. A public teleconference will be scheduled to discuss your responses to the NRC staff's questions.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea.wilkins@nrc.gov.
Sincerely, I)'
/;:
L nea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated January 5, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110100291), Nebraska Public Power District (the licensee) requested an amendment to Renewed Facility Operating License No. DPR-46 for Cooper Nuclear Station, and Appendix A, Technical Specifications (TSs), of the facility operating license. The proposed amendment would revise TS 3.4.3, "Safety/Relief Valves (SRVs) and Safety Valves (SVs)," to reduce the number of SRVs required to be OPERABLE for over-pressure protection from eight to five.
The Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and determined that the following information is needed in order to complete its review.
Please discuss if all cases were analyzed (i.e., all transients addressed).
Please discuss the number of SRVs that are needed for operation as described in the design basis calculations.
Please discuss if these valves have caused a plant shutdown in the past.
Please discuss the timing and increments related to SRV actuation for the full range of transients. Please also discuss which five will be the "required" valves or, if the request is for any five, justify the basis for the TS having only four SRVs available when in the Limiting Condition for Operation.
Please discuss if human factors will affect the mitigation of an accident and, if so, if a human factors analysis has been performed.
Please discuss if the maintenance rule was taken into consideration. What maintenance issues, if any, contributed to the need for this request?
Please discuss how the reduction in required SRVs affects the heat load in the suppression pool.
Please discuss any structural issues that would be impacted.
For all the above, please discuss the basis for concluding the change would not increase the probability/consequences of an accident and not reduce safety margins as described in the Updated Safety Analysis Report.
Enclosure
- OFFICE NRR/LPL4/PM NAME LWilkins DATE 5/26/11 NAME DHarrison DATE 6/1/11 NRRlLPL4/LA E/EICB/BC JBurkhardt NRR/DSS/SRXBlBC AUlses 6/2/11 5/25/11 5/26/11
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