ML101450179
| ML101450179 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/03/2010 |
| From: | Bennett Brady License Renewal Projects Branch 1 |
| To: | Joyce T Public Service Enterprise Group |
| Brady B NRR/DLR/RPB1, 415-2981 | |
| References | |
| TAC ME1832 | |
| Download: ML101450179 (9) | |
Text
June 3, 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 THE REVIEW 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 Licenses 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. 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 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
ML101450179 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME B. Brady B. Pham B. Brady DATE 05/27/10 05/26/10 05/28/10 06/03/10
ENCLOSURE Letter to T. Joyce from B. Brady dated June 3, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION (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 ACunanan SCuadrado CEccleston REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI
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 FOR THE REVIEW OF THE HOPE CREEK GENERATING STATION (HCGS) LICENSE RENEWAL APPLICATION (LRA)
RAI 3.3.2.2.13-01
Background:
HCGS LRA Table 3.3.1, Item 3.3.1-34 HCGS LRA Subsection 3.3.2.2.13 10 CFR 54.21(a)(1)(ii)
HCGS LRA Table 3.3.1 states that item 3.3.1-34 is not applicable. HCGS LRA Subsection 3.3.2.2.13 states that item number 3.3.1-34 is not applicable for Hope Creek because elastomer components that experience wear are periodically replaced and therefore are not subject to aging management review.
10 CFR 54.21(a)(ii) states that, Structures and components subject to an aging management review shall encompass those structures and components -- that are not subject to replacement based on a qualified life or specified time period.
Issue:
Although the HCGS LRA states that elastomer components that experience wear are periodically replaced, it is not clear to the staff whether the replacement frequency is based on a qualified life or on a specified time period.
Request:
a)
Identify what systems contain in-scope elastomer components that experience wear and are subject to periodic replacement.
b)
Clarify whether the replacement frequency for elastomer components that experience wear is based on a qualified life or on a specified time period.
c)
Provide the technical basis for the components qualified life or replacement time period, and justify that the replacement frequency is adequate to provide reasonable assurance that failure due to age-related wear does not occur between successive replacements.
RAI B.2.2.2-01
Background:
The plant-specific B.2.2.2 Periodic Inspection Programs detection of aging effects program element does not describe when, where, and how program data are collected. However, Section A1.2.3 of NUREG-1800, Appendix A, states that the program element should describe when, where, and how program data are collected (i.e., all aspects of activities to collect data as part of the program).
Issue:
LRA Section B.2.2.2 Periodic Inspection in the detection of aging effects program element description states that the parameters monitored and inspected include direct visual inspection of component surfaces and ultrasonic wall thickness measurements. It is not clear to the staff what parameter would be monitored during direct visual inspections to identify effects of aging on aluminum components, (e.g., pitting and crevice corrosion) (LRA Table 3.3.2-7).
Request:
State what parameters would be monitored to identify effects of aging on aluminum components, (e.g., pitting and crevice corrosion) (LRA Table 3.3.2-7).
RAI B.2.2.2-02
Background:
The plant-specific B.2.2.2 Periodic Inspection Programs detection of aging effects program element does not describe when, where, and how program data are collected. However, Section A1.2.3 of NUREG-1800, Appendix A states that the program element should describe when, where, and how program data are collected (i.e., all aspects of activities to collect data as part of the program).
Issue:
LRA Section B.2.2.2 Periodic Inspection in the detection of aging effects program element description states that visual inspections of elastomer components will detect the presence and extent of hardening and loss of strength; and visual inspection may include physical manipulation to assist in detecting hardening and degradation of elastomer components. Given that visual inspection would not always include physical manipulations, the staff is not clear on:
(a) the process in determining a need for physical manipulation to assist visual inspections of elastomer components; (b) the characteristics assessed by physical manipulations; and (c) how collected information quantified or otherwise will be used to assess component longevity.
Request:
Clarify the process in determining a need for physical manipulation to assist visual inspections of elastomer components. Clarify characteristics assessed by physical manipulations and how collected information quantified or otherwise will be used to assess component longevity.
RAI B.2.2.2-03
Background:
Section A1.2.3 of NUREG-1800, Appendix A, states that the acceptance criteria of the program and its basis should be described.
Issue:
In Element 6 of the LRA Periodic Inspection AMP, it states that acceptance criteria for loss of material are based on the original equipment design wall thickness and any corrosion allowance requirements. It is not clear to the staff what the acceptance criteria are for determining effects of aging, specifically, on aluminum components.
Request:
Clarify the acceptance criteria for determining effects of aging on aluminum components.
RAI 3.2.2-01
Background:
The GALL Report does not include the outdoor-air exposure for aluminum components in the service water system. The HCGS LRA indicates that loss of material can occur for aluminum pump casings in the service water system (LRA Table 3.3.2-27) when exposed to outdoor air.
The LRA also states that the Open-Cycle Cooling Water System Program will be used to manage this aging issue. The LRA further states in the Open-Cycle Cooling Water System Program description, that this program is for managing internal corrosion of piping.
Issue:
It is not clear to the staff that the Open-Cycle Cooling Water Program is an acceptable program to manage the external surface of the aluminum pump casing exposed to outdoor air.
Request:
Provide additional information on the technical background of the Open-Cycle Cooling Water System Program that will ensure that loss of material for the external surface of the aluminum pump casing is appropriately managed.
RAI 3.2.2-02
Background:
The GALL Report, under item VII.C1-6, indicates that copper alloy heat exchanger tubes exposed to raw water can result in reduction of heat transfer, and the aging effect can be managed by the Closed-Cycle Cooling Water System Program. In addition, the GALL Report,Section IX.D defines raw water to be untreated, fresh, salt, or ground water.
Issue:
The HCGS LRA Table 3.3.2-2 indicates that the Periodic Inspection Program is credited to manage reduction of heat transfer for copper alloy heat exchanger components (thermo-siphon) in the closed-cycle cooling water system exposed to raw water. The LRA uses Note G, along with a plant-specific note that states, The environment for this component is glycol based coolant used in the compressor cooling system. This coolant is considered raw water for purposes of determining aging effects because it is not monitored by a chemistry program. It is not clear how the applicants Periodic Inspection Program will be used to manage the effects of a reduction of heat transfer.
Request:
Provide justification for the effectiveness of the Periodic Inspection Program in managing the aging effect of reduction of heat transfer for copper alloy heat exchanger components exposed to raw water.