ML081640092
| ML081640092 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/11/2008 |
| From: | Geoffrey Miller NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Chernoff H NRC/NRR/ADRO/DORL/LPLI-2 |
| Miller G, NRR/DORL, 415-2481 | |
| References | |
| TAC MD8566 | |
| Download: ML081640092 (3) | |
Text
June 11, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
G. Edward Miller, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD8566)
The attached draft request for information (RAI) was transmitted on June 11, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated October 18, 2007.
The proposed amendment would revise the Oyster Creek Technical Specifications by replacing the snubber breakaway test with a drag force test.
The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.
Docket No. 50-219
Enclosure:
Draft RAI
June 11, 2008 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
G. Edward Miller, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MD8566)
The attached draft request for information (RAI) was transmitted on June 11, 2008, to Mr. Tom Loomis of AmerGen Energy Company, LLC (AmerGen). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek), dated October 18, 2007.
The proposed amendment would revise the Oyster Creek Technical Specifications by replacing the snubber breakaway test with a drag force test.
The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.
Docket No. 50-219
Attachment:
Draft RAI DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2 LPL I-2 Reading RidsNrrPMGMiller RidsNrrDorlDpr GBedi ACCESSION NO.: ML081640092 OFFICE LPLI-2/PM NAME G. E. Miller DATE 6/11/08 OFFICIAL RECORD COPY
ENCLOSURE DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT REPLACEMENT OF SNUBBER BREAKAWAY TEST WITH DRAG FORCE TEST OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 By letter dated October 18, 2007, AmerGen Energy Company, LLC (Amergen) submitted an amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would revise the Oyster Creek Technical Specifications (TSs) by replacing the snubber breakaway test with a drag force test.
The Nuclear Regulatory Commission staff has reviewed the information provided in support of the proposed amendment and finds that the following information is required to complete its review:
- 1) By letter dated October 2, 2002, the NRC authorized an alternative to the American Society of Mechanical Engineers (ASME) Boiler and pressure Vessel code (ASME Code),Section XI, Rules for inservice Inspection of Nuclear Power Plant Components, Article IWF-5000, with regard to visual examination and functional testing of snubbers. The proposed TS change is based on Subsection ISTD of the ASME Code for Operations and Maintenance of Nuclear Power Plants (OM Code). Please clarify this apparent discrepancy or discuss your intent to revise the previously authorized alternative to be consistent with the proposed TS revision.
- 2) The proposed TS change would use the ASME OM Code for inservice inspection of mechanical snubbers. Oyster Creek TS 4.3.B references ASME Section XI for inservice inspection of ASME Code Class 1, 2, and 3 systems and components. Please clarify this apparent discrepancy or include a proposed revision to TS 4.3.B to include the ASME OM Code for snubbers.
- 3) The proposed amendment would change an inservice testing requirement of mechanical snubbers from the ASME Code,Section XI, to the ASME OM Code requirements. All other TS Snubber examination and testing requirements remain unchanged, and are based on the ASME Code,Section XI, IWF-5000. Please explain how the proposed change meets the requirements of Title 10 of the Code of Federal Regulations, Section 50.55a(g)(4)(iv) which states, in part,...portions of or addenda may be used provided that all related requirements of the respective editions or addenda are met.