ML052420519
| ML052420519 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/18/2005 |
| From: | Benyak D Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-NO5-0424, S1-RR-04-V01, S1-RR-04-V02 | |
| Download: ML052420519 (2) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 AUG 1 8 2005 LR-N05-0424 o PSEG NuclearLLC U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING RELIEF REQUESTS S1-RR-04-V01 AND V02 SALEM NUCLEAR GENERATING STATION, UNIT NO. I FACILITY OPERATING LICENSES NO. DPR-70 DOCKET NO. 50-272
References:
LR-N04-0299, Inservice Inspection Program Relief Requests S1-RR-04-VOI and V02 Salem Generating Station Unit 1, dated July 9, 2004 LR-N04-0591 Response to Request for Additional Information Regarding Relief Requests Sl-RR-04-VOI and V02 Salem Nuclear Generating Station, Unit No. 1 Facility Operating Licenses No. DPR-70 Docket No. 50-272, dated January 6, 2005 On July 9, 2004, and January 6, 2005, PSEG Nuclear LLC (PSEG) submitted the referenced letters relative to the subject relief request. This would allow use of an alternate testing methodology to that specified in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants OMa-1 988, Part 10-4.3.2.1 for Accumulator Outlet Check Valves 11 SJ55, 12SJ55, 13SJ55, 14SJ55, 11SJ56, 12SJ56, 13SJ56, and 14SJ56.
On March 24, 2005, a conference call between members of PSEG and the Nuclear Regulatory Commission (NRC) resulted in a verbal request for information and clarification relative to PSEG's response to the October 6, 2004 RAI Question 5.
Specifically, PSEG had only modeled one of the lines, and proposed to use the results for the remaining three lines. However, differences in line resistance and Accumulator motor operated valve (MOV) SJ54 stroke characteristics could make this approach non-conservative. During this conference call, PSEG agreed to revise the calculation to perform an analysis of each line and submit the results to the NRC, along with appropriate revisions to the relief request.
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95-2168 REV. 7199
Document Control Desk LR-N05-0424 to this letter is calculation S-1-SJ-MDC-1 539, Rev 2, "Accumulator Pressure Decay Time During Discharge Test", which is used to determine the acceptance criteria associated with the Alternate Testing. This calculation has been revised to account for individual line resistances and MOV stroke time characteristics.
Additionally, the MOV SJ54 stroke times and accumulator pressure decay times are measured from when the valve disc begins to move. PSEG is requesting that the methodology presented in the calculation be accepted for the accumulator check valve testing relief request. Valves that fail to meet the times specified in the calculation will be opened and inspected. to this letter provides the appropriately revised relief requests SI-RR V01 and V02. Attachment 3 to this letter provides a revised General Approach Proposed For Full Open Testing of Accumulator Check Valves.
If you have any questions or require additional information, please contact Mr. Enrique Villar at (856) 339-5456.
Sincerely, Darin Benyak Director - Regulatory Assurance Attachments C:
S. Collins, Regional Administrator - NRC Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Bailey, Project Manager-Salem U.S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 2