ML100630282

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Request for Additional Information Regarding Scoping of Fire Protection and Metal Fatigue for the Hope Creek Generating Station
ML100630282
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/22/2010
From: Ashley D
License Renewal Projects Branch 1
To: Joyce T
Public Service Enterprise Group
Ashley Donnie, NRC/NRR/DLR/RPB1
References
Download: ML100630282 (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 AND METAL FATIGUE FOR THE HOPE CREEK GENERATING STATION

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 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 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 No. 50-354

Enclosure:

As stated cc w/encl: See next page

ML100630282 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 AND METAL FATIGUE FOR THE HOPE CREEK GENERATING STATION DISTRIBUTION:

HARD COPY:

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Hope Creek Generating Station cc:

Mr. Robert Braun Mr. Michael Gaffney Senior Vice President Nuclear Manager - Hope Creek Regulatory PSEG Nuclear LLC Assurance One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Brian Booth Director Nuclear Oversight Mr. Ali Fakhar PSEG Nuclear Manager, License Renewal P.O. Box 236 PSEG Nuclear LLC Hancocks Bridge, NJ 08038 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. John Perry Station Vice President - Hope Creek Township Clerk PSEG Nuclear Lower Alloways Creek Township P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Larry Wagner Mr. Paul Bauldauf, P.E., Asst. Director Plant Manager - Hope Creek Radiation Protection Programs PSEG Nuclear LLC NJ Department of Environmental One Alloway Creek Neck Road Protection and Energy, CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. Michael Gallagher Mr. Brian Beam Vice President - License Renewal Projects Board of Public Utilities Exelon Nuclear LLC 2 Gateway Center, Tenth Floor 200 Exelon Way Newark, NJ 07102 Kennett Square, PA 19348 Regional Administrator, Region I Mr. Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission Manager - Licensing 475 Allendale Road PSEG Nuclear LLC King of Prussia, PA 19406 One Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Mr. Paul Davison Vice President, Operations Support Mr. Greg Sosson PSEG Nuclear LLC Director Corporate Engineering One Alloway Creek Neck Road PSEG Nuclear LLC Hancocks Bridge, NJ 08038 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

REQUEST FOR ADDITIONAL INFORMATION REGARDING SCOPING OF FIRE PROTECTION FOR THE HOPE CREEK GENERATING STATION LICENSE RENEWAL APPLICATION The staff reviewed the Hope Creek Generating Station (Hope Creek) license renewal application (LRA); LRA drawings; Section 9.5.1, Fire Protection Program, of the updated final safety analysis report; and the following fire protection current licensing basis documents listed in Hope Creek Operating License Condition 2.C(7):

  • NUREG-1048, Safety Evaluation Report related to the operation of Hope Creek Generating Station, dated October 1984
  • NUREG-1048, Supplement No. 6, dated July 1986 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 2.3.3.10-1 The following LRA drawings shows fire protection system components as out of scope (i.e., not colored in green):

  • LR - M 0, SH. 1, Fire Protection - Fire Water Permanent & Temporary Fire Pumphouse: The Deep Well Water Pumps and associated components to Fire Water Storage Tanks OAT508 and OBT508 The staff requests that the applicant verify whether the fire protection systems and 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 these systems and components 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 2.3.3.10-2 Tables 2.3.3-10 and 3.3.2-10 of the LRA do not include the following fire protection components:

  • hose racks
  • passive components in diesel engines for fire water pumps
  • fire retardant coating for structural steel ENCLOSURE
  • sight glasses (foam storage tank)
  • spray nozzles (iodine removal filter)

The staff requests that the applicant determine whether Tables 2.3.3-10 and 3.3.2-10 should include each component listed above and, if not, justify the exclusion.

RAI 2.3.3.10-3 Safety Evaluation Report, NUREG-1048, dated October, 1984, NUREG-1048, Supplement No. 5, dated April 1986, and Updated Final Safety Analysis Report, Table 9.5-2, list various types of fire suppression systems for fire suppression activities. The listed fire suppression systems include:

  • Halon 1301 total flooding fire suppression system in the quality assurance vault in the administration building and underneath the raised floor of room 1 in the guardhouse The staff requests that the applicant verify whether the fire suppression system listed above is 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 it is 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 2.3.3.10-4 Section 9.5.1.4, General Plant Guidelines, of NUREG-1048, Supplement No. 5, dated April 1986, states on page 9-9:

the staff also questioned the fire rating of certain bullet-resistant panels used in the control rooms. The applicant provided the staff with . a letter from the manufacturer certifying that these panels were fabricated from the same type of materials and in a configuration used in 3-hour-rated fire doors The staff requests that the applicant verify whether bullet-resistant panels 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 2.3.3.10-5 Section 9.5.1.4, General Plant Guidelines, of NUREG-1048, Supplement No. 5, dated April 1986, states on page 9-11:

In the SER the staff identified 12 locations were the applicant committed to install automatic sprinkler systems to protect areas containing high concentrations of cables and cable trays The staff requests that the applicant verify whether these automatic sprinkler systems 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.