ML101380620

Request for Additional Information Regarding Sections 4.6 and 4.7 of the Hope Creek Generating Station License Renewal Application

ML101380620
Person / Time
Site:	Hope Creek
Issue date:	06/01/2010
From:	Bennett Brady License Renewal Projects Branch 1
To:	Joyce T Public Service Enterprise Group
CuadradoDeJesus S, NRR/DLR, 415-2946
References
TAC ME1832
Download: ML101380620 (5)

Text

June 1, 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 REGARDING SECTIONS 4.6 AND 4.7 OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (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 Regulations 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 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. 50-354

Enclosure:

As stated cc w/encl: See next page

ML101380620 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady Ikeda King B. Pham B. Brady DATE 5/24/10 5/20/10 5/28/10 6/01/10

Letter to T. Joyce from B. Brady dated June 1, 2010

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SECTIONS 4.6 AND 4.7 OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO ME1832)

DISTRIBUTION:

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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. 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

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 REQUEST FOR ADDITIONAL INFORMATION REGARDING SECTIONS 4.6 AND 4.7 OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (TAC NO. ME1832)

RAI 4.6-01

Background:

Standard Review Plan License Renewal (NUREG 1800), Section 4.6.1.1 states that containment liner plates, metal containment, and penetration sleeves may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations that can be used for the time-limited aging analyses (TLAAs).

Issue:

The Hope Creek Generating Station (HCGS) license renewal application (LRA) Section 4.6.2 Primary Containment Process Penetrations and Bellows Fatigue Analysis, states that the maximum 40-year cumulative usage factor (CUF) ratio (CUF/allowable) identified for feedwater penetrations P-2A and P-2B P heads will be included in the Metal Fatigue of Reactor Coolant Pressure Boundary Program (B.3.1.1) as a program enhancement. All relevant plant transient events will be tracked to ensure that the CUF remains less than 0.1 for these two triple flued heads.

Request:

Explain how the tracking of all relevant plant transient events for feedwater penetrations P-2A and P-2B will ensure that the CUF remains less than 0.1. The staff needs the above information to ensure that the effects of aging on the intended function will be adequately managed for the period of extended operation as required by 10 CFR 54.21(c)(1)(iii).

RAI 4.7-01

Background:

In LRA Section 2.3.3.8, Scoping and Screening, the applicant listed a total of 18 cranes and hoists as in scope for license renewal. Table 3.3.2-8 of the LRA requires a TLAA of Crane/Hoist Bridge/Trolley girders for aging management due to Cumulative Fatigue Damage/Fatigue in accordance with the GALL Report recommendations.

Issue:

LRA Section 4.7.1, Crane Load Cycle Limit, identifies TLAAs for only two cranes, the Reactor Building Polar Crane and the Service Water Intake Structure Gantry Crane. TLAAs for other cranes with support girders and in the scope of license renewal are not included in LRA Section

4.7.1. Request

Provide an explanation or clarification of why the Reactor Building Polar Crane and the Service Water Intake Gantry Crane are the only two cranes with a TLAA when the overall number of cranes within scope is at 18. The staff needs the above information to confirm that an evaluation of the fatigue of the in scope crane girders has been performed that will remain valid for the period of extended operation as required by 10 CFR 54.21(c)(1).