ML043230303
| ML043230303 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/18/2004 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Dan Collins NRC/NRR/DLPM/LPD1 |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| BL-04-001, TAC MC3511 | |
| Download: ML043230303 (3) | |
Text
November 18, 2004 MEMORANDUM TO: Daniel S. Collins, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Victor Nerses, Senior Project Manager, Section 2
/RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SEABROOK STATION, UNIT NO. 1, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO.
The attached draft RAI was transmitted by facsimile on November 18, 2004, to Mr. Rajiv Kundalkar of FPL Energy Seabrook, LLC (FPL Energy Seabrook). This draft RAI was transmitted to facilitate the technical review being conducted by Nuclear Regulatory Commission (NRC) staff and to support a conference call with FPL Energy Seabrook in order to clarify certain items. The draft RAI is related to the licensees July 27, 2004, response to NRC issued Bulletin 2004-01 Inspection of Alloy 82/182/600 Materials Used in The Fabrication of Pressurizer Penetrations And Steam Space Piping Connections at Pressurized-water Reactors. Review of the RAI would allow the licensee 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 prior response.
Docket No. 50-443
Enclosure:
Draft RAI
November 18, 2004 MEMORANDUM TO: Daniel S. Collins, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Victor Nerses, Senior Project Manager, Section 2
/RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SEABROOK STATION, UNIT NO. 1, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO.
The attached draft RAI was transmitted by facsimile on November 18, 2004, to Mr. Rajiv Kundalkar of FPL Energy Seabrook, LLC (FPL Energy Seabrook). This draft RAI was transmitted to facilitate the technical review being conducted by Nuclear Regulatory Commission (NRC) staff and to support a conference call with FPL Energy Seabrook in order to clarify certain items. The draft RAI is related to the licensees July 27, 2004, response to NRC issued Bulletin 2004-01 Inspection of Alloy 82/182/600 Materials Used in The Fabrication of Pressurizer Penetrations And Steam Space Piping Connections at Pressurized-water Reactors. Review of the RAI would allow the licensee 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 prior response.
Docket No. 50-443
Enclosure:
Draft RAI DISTRIBUTION PUBLIC PDI-2 Reading SAndruszkiewicz V. Nerses Accession Number: ML043230303 OFFICE PDI-2/PM EMCB-SC NAME VNerses SCoffin DATE 11/18/04 11/17/04 OFFICIAL RECORD COPY
Enclosure DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSEE RESPONSE TO NRC BULLETIN 2004-01 FPL ENERGY SEABROOK, LLC SEABROOK STATION DOCKET NO. 50-443 The NRC staff has completed its review of your response, dated July 27, 2004, to NRC Bulletin 2004-01, Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in The Fabrication of Pressurizer Penetrations And Steam Space Piping Connections at Pressurized-water Reactors. Based on the staffs review, please provide a supplemental response which addresses the following questions.
1.
In item (1)(c) of the licensees response, it appears that the licensee is stating that they may not be examining the Alloy 182 spray, safety and surge nozzle butt welds after the next refueling outage. Please clarify this statement in your Bulletin response since on page 5 of the Bulletin it states, The NRC staff has reviewed the recommendations made by the WOG in its January 30, 2004, letter and finds that, with minor modifications, it would constitute an effective degradation management program for all Alloy 82/182/600 covered under the scope of bulletin 2004-01 based on our current state of knowledge. These examinations should be performed at each refueling outage.
2.
Items 1(b) and1(c) in Bulletin 2004-01 request that the licensee provide the basis for concluding that their plant will satisfy applicable regulatory requirements related to the structural and leakage Integrity of pressurizer penetrations and steam space piping connections. The licensees response to this item does not provide a specific explanation of these items. Please supplement your response to provide this basis.
The section titled, Applicable Regulatory Requirements starting on page 5 in Bulletin 2004-01 lists some of the regulatory requirements that should be addressed in your response.
3.
Item 1(d) in Bulletin 2004-01 states, In light of the information discussed in this bulletin and your understanding of the relevance of recent industry operating experience to your facility, explain why the inspection program identified in your response to item (1)(c) above is adequate for the purpose of maintaining the integrity of your facilitys reactor coolant pressure boundary and for meeting all applicable regulatory requirements which pertain to your facility. The licensees response to this item does not provide a specific explanation of these items. Please provide this explanation.