ML101830347
| ML101830347 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/02/2010 |
| From: | Richard Ennis Plant Licensing Branch 1 |
| To: | Chernoff H Plant Licensing Branch 1 |
| Ennis R, NRR/DORL, 415-1420 | |
| References | |
| TAC ME3545 | |
| Download: ML101830347 (3) | |
Text
July 2, 2010 MEMORANDUM TO:
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Richard B. Ennis, Senior Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME3545)
The attached draft request for additional information (RAI) was transmitted on July 2, 2010, to Mr. Jeff Keenan of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Hope Creek Generating Station dated March 19, 2010. The proposed amendment would modify the Technical Specifications by relocating specific surveillance frequencies to a licensee-controlled document. The proposed amendment is based on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Traveler TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative 5b.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.
Docket No. 50-354
Attachment:
Draft RAI
July 2, 2010 MEMORANDUM TO:
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Richard B. Ennis, Senior Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME3545)
The attached draft request for additional information (RAI) was transmitted on July 2, 2010, to Mr. Jeff Keenan of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Hope Creek Generating Station dated March 19, 2010. The proposed amendment would modify the Technical Specifications by relocating specific surveillance frequencies to a licensee-controlled document. The proposed amendment is based on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Traveler TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative 5b.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket No. 50-354
Attachment:
Draft RAI DISTRIBUTION PUBLIC AHowe, NRR/DRA/APLA LPL1-2 R/F GWaig, NRR/DIRS/ITSB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMREnnis Resource ACCESSION NO.: ML101830347 OFFICE LPL1-2/PM NAME REnnis DATE 7/2/10 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RISK-INFORMED RELOCATION OF SURVEILLANCE FREQUENCY REQUIREMENTS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By application dated March 19, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100900224), PSEG Nuclear LLC (the licensee) submitted a license amendment request for the Hope Creek Generating Station (HCGS). The proposed amendment would modify the Technical Specifications by relocating specific surveillance frequencies to a licensee-controlled document. The proposed amendment is based on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Traveler TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative 5b.
The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
- 1.
Table 2.2-1 of Attachment 2 of the application dated March 19, 2010, identifies supporting requirements from the Probabilistic Risk Assessment (PRA) standard for internal events which are not at capability category II as required to support this application. Only four supporting requirements are identified. Does Table 2.2-1 identify all supporting requirements not met at capability category II for the HCGS internal events PRA model, or do the four items represent those judged by the licensee to be relevant to this application? The licensee should clarify the scope of the items in Table 2.2-1 and identify and disposition any other supporting requirements not at capability category II, if applicable.
- 2.
With regards to supporting requirement DA-D1, the Table 2.2-1 entry identifies that not all component failure data is based on plant-specific experience, but the importance of this item to the application is not discussed. Instead, it is stated that a majority of important systems use plant-specific data, and then the requirement of Nuclear Energy Institute 04-10 to perform sensitivity studies is identified. The licensee needs to more specifically identify the scope of this deficiency in plant data and characterize why it is not significant for the calculation of risk associated with surveillance frequency extensions for those systems to which the deficiency applies.
Attachment