ML100750328

License Renewal Application - Request for Additional Information for Section 2.4, Scoping and Screening Results: Structures

ML100750328
Person / Time
Site:	Hope Creek
Issue date:	03/31/2010
From:	Ashley D License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
Donnie J. Ashley, 301-415-3191
References
TAC ME1832
Download: ML100750328 (6)

Text

March 31, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION -

REQUEST FOR ADDITIONAL INFORMATION FOR SECTION 2.4, SCOPING AND SCREENING RESULTS: STRUCTURES (TAC NO. ME1832)

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 Regulation Part 54 (10 CFR Part 54) for renewal of Operating License No.

NPF-57 for the Hope Creek Generating Station. 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 requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with John Hufnagel and other members of your staff during a telephone call on March 4, 2010, 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 301-415-3191 or by e-mail at donnie.ashley@nrc.gov.

Sincerely, Donnie J. Ashley, Sr. Project Manager /RA/

Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

As stated cc w/encl: See next page

ML100750328 OFFICE LA:DLR PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1 NAME I. King D. Ashley B. Pham D. Ashley DATE 03/29/10 03/29/10 03/29/10 03/31/10

Letter to T. Joyce from D. Ashley dated March 31, 2010

SUBJECT:

HOPE CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION -

REQUEST FOR ADDITIONAL INFORMATION FOR SECTION 2.4, SCOPING AND SCREENING RESULTS: STRUCTURES (TAC NO. ME1832)

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Hope Creek Generating Station 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. Greg 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

Hope Creek Generating Station 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

ENCLOSURE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION FOR SECTION 2.4, SCOPING AND SCREENING RESULTS: STRUCTURES (TAC NO. ME1832)

RAI 2.4-1 Which components, if any, in the Hope Creek Generating Station (HCGS) license renewal application (LRA) Table 2.4-3 (Auxiliary Building Service/Radwaste Area) include the main steam tunnel structural elements? If these are omitted, please justify their omission.

RAI 2.4-2 Reinforced concrete isolation walls are included in the LRA Table 2.4-2 (Auxiliary Building Control/Diesel Generator Area); however, the isolation function is not listed as an intended function in any concrete component listed in the aforementioned table. Please clarify if this intended function is listed as a different function (shielding, structural support, etc) or justify its exclusion.

RAI 2.4-3 Horizontal seismic restraints are shown in Figures 3.8.1 and 3.8.13 of the HCGS Updated Final Safety Analysis Report (UFSAR) for the Torus of the Primary Containment. These are not included in Table 2.4-7 of the HCGS LRA Section 2.4-7 (Primary Containment). Justify their exclusion.

RAI 2.4-4 Please indicate where the structural elements that transfer the reactor pressure vessel (RPV) loads to the RPV ring girder and subsequently to the RPV pedestal (shown in Figure 3.8.1 in HCGS UFSAR) are evaluated in the HCGS LRA. If they have not been evaluated, please justify their exclusion.

RAI 2.4-5 HCGS LRA Table 2.4-7 (Primary Containment) lists the torus ring girder as one of the components subject to an Aging Management Program (AMP). But this table does not include the RPV ring girder, as shown in UFSAR Figure 3.8.1.

Please justify the omission of the latter.

RAI 2.4-6 Based on a review of the HCGS LRA Sections 2.4.7 (Primary Containment) and 2.4.8 (Reactor Building) and of Tables 2.4-7 and 2.4-8 it is not clear if the following components have been included in the scope of license renewal and subject to an AMR:

a) Refueling seal assembly b) Weld pads on the drywell shell for attachment of pipe supports c) Water seal plates at the base of the drywell head, as shown in UFSAR Figure 3.8.1 d) Spent fuel pool liner plate leak chase system If these components are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of license renewal, please provide the basis for their exclusion.

RAI 2.4-7 UFSAR Figure 3.8-29 (Biological Shield Plan and Elevation) shows details of shear ties. Please identify the component in LRA Table 2.4-7, which includes these structural elements. If these components are covered somewhere else in the LRA, please indicate the location. If they are excluded from the scope of license renewal, please provide the basis for their exclusion.