ML100630226

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Request for Additional Information Regarding Scoping of Fire Protection for the Salem Nuclear Generating Station Units 1 and 2
ML100630226
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/22/2010
From: Ashley D
License Renewal Projects Branch 1
To: Joyce T
Public Service Enterprise Group
ashely donnie, NRR/DLR/RPB1 415-3191
References
Download: ML100630226 (7)


Text

March 22, 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 SCOPING OF FIRE PROTECTION FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2

Dear Mr. Joyce:

By letter dated August 18, 2009, as supplemented by letter dated January 23, 2009, Public Service Enterprise Group Nuclear, LLC (PSEG), submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License Nos.

DPR-70 and DPR-75 for Salem Nuclear Generating Station (SNGS) 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 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 February 25, 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,

/RA/

Donnie J. Ashley, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosure:

As stated cc w/encl: See next page

ML100630226 OFFICE LA:DLR PM:DLR:RPB1 BC:DLR:RPB1 PM:DLR:RPB1 NAME Y. Edmonds D. Ashley B. Pham D. Ashley DATE 03/16/10 03/16/10 03/22/10 03/22/10 Letter to T. Joyce from D. Ashley, dated March 22, 2010

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING OF FIRE PROTECTION FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

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Salem Nuclear Generating Station, Units 1 and 2 cc:

Mr. Robert Braun Mr. Ali Fakhar Senior Vice President Nuclear Manager, License Renewal PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Mr. William Mattingly Senior Vice President - Salem Manager - Salem Regulatory Assurance PSEG Nuclear LLC PSEG Nuclear LLC One Alloway Creek Neck Road One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Township Clerk Vice President - License Renewal Projects Lower Alloways Creek Township Exelon Nuclear LLC Municipal Building, P.O. Box 157 200 Exelon Way Hancocks Bridge, NJ 08038 Kennett Square, PA 19348 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Ed Eilola Radiation Protection Programs Plant Manager - Salem NJ Department of Environmental PSEG Nuclear LLC Protection and Energy, CN 415 One Alloway Creek Neck Road Trenton, NJ 08625-0415 Hancocks Bridge, NJ 08038 Mr. Brian Beam Mr. Brian Booth Board of Public Utilities Director Nuclear Oversight 2 Gateway Center, Tenth Floor PSEG Nuclear Newark, NJ 07102 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Jeffrie J. Keenan, Esquire 475 Allendale Road Manager - Licensing King of Prussia, PA 19406 PSEG Nuclear LLC One Alloway Creek Neck Road Mr. Greg Sosson Hancocks Bridge, NJ 08038 Director Corporate Engineering PSEG Nuclear LLC Senior Resident Inspector One Alloway Creek Neck Road Salem Nuclear Generating Station Hancocks Bridge, NJ 08038 U.S. Nuclear Regulatory Commission Drawer 0509 Mr. Paul Davison Hancocks Bridge, NJ 08038 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 Mr. Earl R. Gage Salem County Administrator Administration Building 94 Market Street Salem, NJ 08079

REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING OF FIRE PROTECTION FOR THE SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION The staff reviewed the Salem Nuclear Generating Station, Units 1 and 2 license renewal application (LRA); LRA drawings; Section 9.5.1.1, Fire Protection Program, of the Updated Final Safety Analysis Report for Salem 1 and 2; and the following fire protection current licensing basis documents listed in Salem, Unit 1, Operating License Condition 2.C(5) and in Salem, Unit 2, Operating License Condition 2.C(10):

  • Amendment No. 21 to Facility Operating License No. DPR-70, dated November 20, 1979
  • Safety evaluation report dated September 16, 1982
  • Safety evaluation report dated November 5, 1982
  • Safety evaluation report dated June 17, 1983
  • Safety evaluation report dated July 20, 1989
  • Safety evaluation report dated June 17, 1994
  • Safety evaluation report dated January 7, 2004 The staff found that the applicant excluded the fire protection systems and components, discussed in the following sections, from the scope of license renewal and aging management review (AMR). These systems and components were not included in the license renewal boundaries, and they apparently have fire-protection-intended functions required for compliance with Title 10 of the Code of Federal Regulations (10 CFR) 50.48, Fire Protection, as stated in 10 CFR 54.4, Scope. Therefore, the staff requires responses to the requests for additional information (RAIs) described below to complete its review.

RAI 2.3.3.12-1 The following LRA drawing shows fire protection system components as out of scope (i.e., not highlighted in green):

  • LR-205221 SH.1, No.1 & 2 Units, Fresh Water : Nos. 1,2,3, 5, and 6 Productions Wells at locations H4, D1, H2, H6, and A2 respectively in the Fresh Water Well Pump House; Fire Pump House at locations C7 and D5; tank 1FWE4 at location G2 and associated components to the Fire Pump House and to the Fire Protection Storage Tank 1FWE16 The staff requests that the applicant verify whether the fire protection system components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.12-2 Tables 2.3.3.12 and 3.3.2-12 of the LRA do not include the following fire protection components:

  • hose racks
  • filter housing
  • flame arrestor
  • passive components in diesel engines for fire water pumps
  • fire retardant coating for structural steel
  • fire retardant coating on duct work The staff requests that the applicant verify whether the fire protection system components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.12-3 Section 4.0 and 5.0 of the Safety Evaluation Report dated June 17, 1983, states that fire protection is provided in Fire Zone P1E, Elevation 84 Auxiliary Building Electrical Penetration Area, in part, by a manually operated total flooding carbon dioxide extinguishing system and in Fire Area P1B 4 kV line. Switchgear Room by a manual total flooding carbon dioxide fire suppression system.

The staff requests that the applicant verify whether the fire suppression systems in Fire Zone P1E Elevation 84, Auxiliary Building Electrical Penetration Area and in Fire Area P1B - 4 kV line. Switchgear Room are in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.12-4 The Safety Evaluation Report dated July 20, 1989, states on page 4 of Section 1.3:

Where non-rated steel hatches exist, either the area below is protected by an automatic fire suppression system or potential fire spread up through the hatch will not affect redundant shutdown systems.

and on page 16 of Section 6.2:

the licensee proposed to implement the following modifications:

-Expand the existing wet-pipe sprinkler system in the charging pump area to provide full coverage around the pump;

-Enhance the sprinkler systems which protect the auxiliary feedwater pumps The staff requests that the applicant verify whether the fire suppression systems associated with non-rated steel hatches, the wet-pipe sprinkler system in the charging pump area, and the sprinkler systems which protect the auxiliary feedwater pumps are in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.