ML101680402

Request for Additional Information for Salem Nuclear Generating Station Units 1 and 2, License Renewal Application Regarding Subsection 3.1.2.2.14 (TAC ME1834/ME1836)

ML101680402
Person / Time
Site:	Salem
Issue date:	06/29/2010
From:	Bennett Brady License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
CUADDRADO, SAMUEL NRR/DLR/RPB1 415-2946
References
TAC ME1834, TAC ME1836
Download: ML101680402 (6)

Text

June 29, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REGARDING SUBSECTION 3.1.2.2.14 (TAC NO ME1834 / ME1836)

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 for renewal of Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station Units 1 and 2, respectively. The staff of the U.S.

Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its review, the staff has identified areas where additional information is needed to complete the review. The staffs request for additional information is included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were provided to John Hufnagel and other members of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2981 or by e-mail at bennett.brady@nrc.gov.

Sincerely,

/RA/

Bennett M. Brady, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-272 and 50-311

Enclosure:

As stated cc w/encl: See next page

ML101680402 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa BPham BBrady DATE 6/29/10 6/21/10 06/28/10 06/29/10

Letter to T. Joyce from B. Brady dated June 29, 2010

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REGARDING SUBSECTION 3.1.2.2.14 (TAC NO ME1834 / ME 1836)

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PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource BPham BBrady CEccleston REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI

Salem Nuclear Generating Station, Units 1 and 2 cc:

Mr. Robert Braun Senior Vice President Nuclear PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Plant Manager - Hope Creek PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Vice President - License Renewal Projects Exelon Nuclear LLC 200 Exelon Way Kennett Square, PA 19348 Mr. Jeffrie J. Keenan, Esquire Manager - Licensing PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Gregory Sosson Director Corporate Engineering PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Michael Gaffney Manager - Hope Creek Regulatory Assurance PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Ali Fakhar Manager, License Renewal PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Township Clerk Lower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy, CN 415 Trenton, NJ 08625-0415 Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Paul Davison Vice President, Operations Support PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038

Salem Nuclear Generating Station, Units 1 and 2 cc:

Ms. Christine Neely Director - Regulator Affairs PSEG Nuclear LLC One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079

REQUEST FOR ADDITIONAL INFORMATION FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REGARDING SUBSECTION 3.1.2.2.14 (TAC NO ME1834 / ME 1836)

SNGS RAI 3.1.2.2.14-01 SNGS LRA Table 3.1.1, Item 3.1.1-32 SNGS LRA Subsection 3.1.2.2.14 SNGS LRA Subsection B.2.1.10, Steam Generator Tube Integrity GALL AMP XI.M19, Steam Generator Tube Integrity GALL AMP XI.M17, Flow-Accelerated Corrosion

Background:

SNGS LRA Table 3.1.1, item 3.1.1-32 and subsection 3.1.2.2.14 state that the Steam Generator Tube Integrity Program will be used to manage the aging effect of wall thinning in the steam generator steel feedwater inlet ring and supports. LRA Subsection B.2.1.10 states that the Steam Generator Tube Integrity Program will manage the aging effect of wall thinning, but it does not specify for which components, nor what techniques would be used.

Issue:

GALL AMP XI.M17, which is credited with managing wall thinning due to flow accelerated corrosion for many steel components, includes analysis, inspection, and verification to ensure that flow accelerated corrosion is not occurring at an unacceptable rate and that components are repaired or replaced before wall thinning becomes unacceptable. However, it is not clear to the staff whether the Steam Generator Tube Integrity Program uses both analysis and inspection to verify that unacceptable wall thinning is not occurring.

Request:

1)

Describe the analytical methodology and inspection technique used to manage wall thinning in the steam generator feedwater inlet ring and supports.

2)

Justify that the analytical methodology, together with verification by inspection, are adequate to ensure that loss of component intended function does not occur during the period of extended operation.

3)

Alternatively, if inspection alone is credited to manage the aging effect, justify that the inspection and its associated acceptance criteria are adequate to ensure that need for corrective action is timely identified so that corrective actions are taken before loss of component intended function occurs.

ENCLOSURE