ML101020511: Difference between revisions

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| issue date = 04/27/2010
| issue date = 04/27/2010
| title = License Renewal Application - Request for Additional Information for Section 2.1, Scoping and Screening Methodology
| title = License Renewal Application - Request for Additional Information for Section 2.1, Scoping and Screening Methodology
| author name = Ashley D J
| author name = Ashley D
| author affiliation = NRC/NRR/DLR/RPOB
| author affiliation = NRC/NRR/DLR/RPOB
| addressee name = Joyce T
| addressee name = Joyce T

Revision as of 11:40, 11 July 2019

License Renewal Application - Request for Additional Information for Section 2.1, Scoping and Screening Methodology
ML101020511
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 04/27/2010
From: Ashley D
NRC/NRR/DLR/RPOB
To: Joyce T
Public Service Enterprise Group
References
Download: ML101020511 (7)


Text

April 27, 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 2.1, SCOPING AND SCREENING METHODOLOGY (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 staff's 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, 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, /RA/ Donnie J. Ashley, Sr. 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

ML101020511 OFFICE PM:DLR:RPB1LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME D. Ashley Y. Edmonds B. Pham (B. Brady for) D. Ashley DATE 4/16/10 4/16/10 4/26/10 4/27/10 Letter to T. Joyce from D. Ashley dated April 27, 2010

SUBJECT:

HOPE CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION - REQUEST FOR ADDITIONAL INFORMATION FOR SECTION 2.1, SCOPING AND SCREENING METHODOLOGY (TAC NO. ME1832)

DISTRIBUTION

HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource -------------

BPham BBrady CEccleston REnnis ABurritt, RI MModes, RI DTifft, RI NMcNamara, RI RConte, RI BHarris, OGC 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 08038Mr. 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 2.1, SCOPING AND SCREENING METHODOLOGY (TAC NO. ME1832)

RAI 2.1-1

Background

Pursuant to 10 CFR 54.4(a)(1), the applicant must consider the following plant systems, structures, and components within the scope of license renewal:

Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions -

(i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1), 10 CFR 50.67(b)(2), or 10 CFR 100.11, as applicable.

License Renewal Application (LRA) Section 2.1.3.2, "Identification of Safety-Related Systems and Structures," states:

Safety-related systems and structures are included in the scope of license renewal in accordance with 10 CFR 54.4(a)(1) scoping criterion. Hope Creek systems and structures that have been classified as safety-related are identified as "Q" in the controlled quality classification data field in the Systems, Applications and Products in Data Processing (SAP) database. Hope Creek quality classification procedures were reviewed against the license renewal "safety-related" scoping criterion in 10 CFR 54.4(a)(1), to confirm that Hope Creek safety-related classifications are consistent with license renewal requirements. This review is included in a technical basis document. The basis document also provides a summary list of the systems and structures that are safety-related at Hope Creek. These systems and structures were included in the scope of license renewal under the 10 CFR 54.4(a)(1) scoping criteria.

Issues: 1. During review of the LRA and performance of the scoping and screening methodology audit, performed on-site on January 11-21, 2010, the staff determined that the scoping implementing documents discuss the use of the classification "SR," listed in the component classification field in the SAP, as an initial identifier of safety-related systems. In addition, the classification "Q," listed in the component classification field in the SAP, was also used to determine whether systems identified as safety-related in the SAP would be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(1). The staff determined that a detailed description of the process would be required for the staff to complete its review.

Request: The staff requests that the applicant provide a detailed description of the use of all component classifications in the SAP, including "SR" and "Q", that were used to identify safety-related systems to be included within the scope of license renewal or used to exclude systems from within the scope of license renewal.

2. During review of the LRA and performance of the scoping and screening methodology audit, performed on-site January 11-21, 2010, the staff determined that the 10 CFR 54.4(a)(1) implementing document discusses incorrect or conservative SAP component data module (CDM) classifications. The implementing procedure provided the process and results of the applicant's determination that certain systems do not perform safety-related functions as defined in 10 CFR 54.4(a)(1), and were, therefore, not included within the scope of license renewal. The staff determined that a detailed description of the process would be required for the staff to complete its review.

Request: The staff requests that the applicant provide a detailed description of the process used to evaluate systems or components, identified as safety-related in SAP, and to conclude that the SAP component data module (CDM) classifications were conservative or incorrect and that the systems or components do not perform safety-related functions as defined in 10 CFR 54.4(a)(1).

The staff requests that the applicant perform a review of these issues and indicate if the review concludes that use of the scoping methodology precluded the identification of structures, systems and components (SSCs) which should have included within the scope of license renewal in accordance with 10 CFR 54.4(a). Describe any additional scoping evaluations to be performed to address the 10 CFR 54.4(a) criteria. As part of your response, list any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted or any additional information related to material and environment combinations. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.