ML101620190

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

ML101620190
Person / Time
Site:	Salem
Issue date:	06/25/2010
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: ML101620190 (10)

Text

June 25, 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 (TAC NO ME1834 / ME 1836)

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

ML101620190 OFFICE PM:DLR:RPB1 LA:DLR BC:DLR:RPB1 PM:DLR:RPB1 NAME BBrady SFigueroa BPham BBrady DATE 6/22/10 6/15/10 6/23/10 6/25/10

Letter to T. Joyce from B. Brady dated June 25, 2010

SUBJECT:

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

DISTRIBUTION:

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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 (TAC NO ME1834 / ME 1836)

RAI 3.3.2.2.10.6-01

Background:

SRP-LR Section 3.3.2.2.10, item 6 refers to Table 3.3.1, item 28 and GALL Report Item VII.G-9 and recommends further evaluation of a plant-specific program to manage loss of material due to pitting and crevice corrosion for copper alloy piping, piping components, and piping elements exposed to internal condensation. LRA Section 3.3.2.2.10.6 states that copper alloy fire protection system piping, piping components, and piping elements exposed to internal condensation are managed for loss of material due to pitting and crevice corrosion by the Fire Protection and Fire Water System Programs. Specifically, the Fire Protection Program is credited to manage loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted in LRA Table 3.3.2-12, pages 3.3-236, 239, and 243.

Issue:

The description of the Fire Protection Program in LRA Section B.2.1.15 states that the program performs visual inspections of fire barriers and the external surfaces of the Halon and CO2 systems, and includes performance testing of the diesel driven fire pump fuel supply lines. The description of the Fire Protection Program does not include criteria for inspections of the internal surfaces of components which could detect loss of material for the copper alloy spray nozzles, piping and components, and valve bodies exposed to air/gas - wetted listed in LRA Table 3.3.2-

12.

Request:

Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the copper alloy components exposed to air/gas

- wetted in LRA Table 3.3.2-12.

RAI 3.3.2.12-02

Background:

SRP-LR Table 3.3.1, item 54 recommends the Compressed Air Monitoring Program to manage loss of material for stainless steel piping, piping components, and piping elements exposed to internal condensation within the compressed air system. LRA Table 3.3.1, item 3.3.1-54 states that the Fire Protection Program will be substituted to manage loss of material due to pitting and crevice corrosion of the stainless steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for stainless steel spray nozzles, piping and fittings, and valve bodies in LRA Table 3.3.2-12, pages 3.3-238, 239, 240 and 245, where it references Table 3.3.1, item 3.3.1-54.

SRP-LR Table 3.3.1, item 71 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel piping, piping components, and piping elements exposed to moist air or condensation. LRA Table 3.3.1, item 3.3.1-71 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the steel piping, piping components and piping elements exposed to air/gas - wetted in the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for steel piping and fittings in LRA Table 3.3.2-12, page 3.3-235, where it references Table 3.3.1 item 3.3.1-71. Furthermore, in the same table and same page, the LRA also credited the Fire Water System Program for the same material, environment, and aging effect/mechanism combination.

SRP-LR Table 3.3.1, item 72 recommends the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program to manage loss of material for steel HVAC ducting and components internal surfaces exposed to condensation. LRA Table 3.3.1, item 3.3.1-72 states that the Fire Protection Program will be substituted to manage loss of material due to general, pitting and crevice corrosion of the galvanized steel damper housing exposed to air/gas

- wetted for the Fire Protection System. Specifically, the applicant credited the Fire Protection Program for galvanized steel damper housing in LRA Table 3.3.2-12, page 3.3-227, where it references Table 3.3.1, item 3.3.1-72.

Issue:

The Compressed Air Monitoring Program includes control of contaminants in order to limit loss of material due to corrosion, and leakage testing to detect loss of material. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program includes inspections of the internal surfaces of piping and components to detect loss of material. LRA Section B.2.1.15 states, The program also provides for aging management of external surfaces of the Halon and carbon dioxide fire suppression system components through periodic functional tests and visual inspections for any loss of material. The description of the Fire Protection Program in LRA Section B.2.1.15 does not include criteria for inspections of the internal surfaces of components or leakage testing which could detect loss of material. It is not clear to the staff how the Fire Protection Program is adequate to manage loss of material for the steel and stainless steel components for which is it is credited in Table 3.3.2-12 under items 3.3.1-54, 3.3.1-71, and 3.3.1-72.

Request:

Justify how the Fire Protection Program will adequately manage the aging effect of loss of material due to pitting and crevice corrosion for the various steel and stainless steel components exposed to an internal environment of air/gas - wetted discussed above.