ML062070460

Request for Additional Information Related to Amendment Request to Relocate Overcurrent Protective Devices

ML062070460
Person / Time
Site:	Hope Creek
Issue date:	08/24/2006
From:	Stewart Bailey NRC/NRR/ADRO/DORL/LPLB
To:	Levis W Public Service Enterprise Group
Bailey S N,NRR/DLPM,415-1321
References
TAC MC8602
Download: ML062070460 (4)

Text

August 24, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC-N09 Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO AMENDMENT REQUEST TO RELOCATE OVERCURRENT PROTECTIVE DEVICES (TAC NO. MC8602)

Dear Mr. Levis:

By letter dated October 11, 2005, PSEG Nuclear LLC requested an amendment to the Facility Operating License for the Hope Creek Generating Station (Hope Creek). The amendment would relocate the Technical Specification requirements for the overcurrent protective devices to the Hope Creek Updated Final Safety Analysis Report.

The Nuclear Regulatory Commission staff has determined that responses to the enclosed questions are necessary in order for the staff to complete its review. These questions, in draft form, were sent by e-mail to Mr. James Mallon of your staff on June 14, 2006. Your staff has not requested a conference call to discuss the questions.

In order to complete our timely review of your amendment request, we require your response within 30 days from the date of this letter. If you cannot respond within 30 days, please inform us in writing why you cannot respond and provide an alternate response date. This alternate response date must be no later than 45 days from the date of this letter.

Please note that if you do not respond to this letter within 30 days or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-1321.

Sincerely,

/RA/

Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc w/encl: See next page

August 24, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC-N09 Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO AMENDMENT REQUEST TO RELOCATE OVERCURRENT PROTECTIVE DEVICES (TAC NO. MC8602)

Dear Mr. Levis:

By letter dated October 11, 2005, PSEG Nuclear LLC requested an amendment to the Facility Operating License for the Hope Creek Generating Station (Hope Creek). The amendment would relocate the Technical Specification requirements for the overcurrent protective devices to the Hope Creek Updated Final Safety Analysis Report.

The Nuclear Regulatory Commission staff has determined that responses to the enclosed questions are necessary in order for the staff to complete its review. These questions, in draft form, were sent by e-mail to Mr. James Mallon of your staff on June 14, 2006. Your staff has not requested a conference call to discuss the questions.

In order to complete our timely review of your amendment request, we require your response within 30 days from the date of this letter. If you cannot respond within 30 days, please inform us in writing why you cannot respond and provide an alternate response date. This alternate response date must be no later than 45 days from the date of this letter.

Please note that if you do not respond to this letter within 30 days or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-1321.

Sincerely,

/RA/

Stewart N. Bailey, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc w/encl: See next page DISTRIBUTION:

PUBLIC LPL1-2 R/F RidsNrrDorlLpl1-2 RidsNrrLACRaynor RidsNrrDlpmDpr RidsNrrPMSBailey RidsOgcRp RidsAcrsAcnwMailCenter RidsRgnIMailCenter RidsNrrDeEeeb APal ADAMS Accession Number: ML062070460 OFFICE LPL1-2/PM LPL1-2/LA EEEB/BC LPL1-2/BC (A)

NAME SBailey:rsa CRaynor GWilson BPoole DATE 8/24/06 8/24/06 8/16/2006 8/24/06 OFFICIAL RECORD COPY

Hope Creek Generating Station cc:

Mr. Dennis Winchester Township Clerk Vice President - Nuclear Assessments Lower Alloways Creek Township PSEG Nuclear Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Mr. George P. Barnes Radiation Protection Programs Site Vice President - Hope Creek NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. George H. Gellrich Mr. Brian Beam Plant Support Manager Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Michael J. Massaro U.S. Nuclear Regulatory Commission Plant Manager - Hope Creek 475 Allendale Road PSEG Nuclear King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station Mr. Darin Benyak U.S. Nuclear Regulatory Commission Director - Regulatory Assurance Drawer 0509 PSEG Nuclear - N21 Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing 200 Exelon Way - KSA 3-E Kennett Square, PA 19348 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Michael Jesse Manager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038

REQUEST FOR ADDITIONAL INFORMATION AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS RELOCATION OF OVERCURRENT PROTECTIVE DEVICES HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated October 11, 2005, PSEG Nuclear LLC (PSEG) requested an amendment to the Hope Creek Generating Station (Hope Creek) Technical Specifications (TSs). The amendment would relocate the TS requirements for the overcurrent protective devices to the Hope Creek Updated Final Safety Analysis Report (UFSAR). PSEG requested this change on the basis that the overcurrent protective devices do not meet the criteria in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, for inclusion in the TSs.

The Nuclear Regulatory Commission staff has determined that additional information, as requested below, is necessary in order for the staff to complete its review.

1. The primary containment penetration conductors are used for both safety-related and non-safety-related power, control and instrumentation circuits. Some of these circuits may be susceptible to fault during a design-basis accident (DBA). Of particular concern would be 4160-volt and 480-volt non-safety-related power circuits with equipment that is not qualified for the post-accident containment environment. It is recognized that some of the non-safety-related circuits are de-energized during a DBA, while other circuits may be de-energized after some time delay. However, for those circuits that are energized, actuation of the protective devices may be necessary to protect the electrical penetrations from fault current levels that could damage them and compromise the integrity of the containment fission product barrier. Based on the above, provide a discussion why the TS requirements for the primary containment penetration conductor overcurrent protective devices defined in TS 3/4.8.4.1 do not meet Criterion 3 of 10 CFR 50.36(c)(2)(ii) and, therefore, can be relocated to the UFSAR.

2. Class 1E isolation breaker overcurrent protective devices are used whenever non-safety-related (NSR) circuits are fed from the safety-related (SR) distribution system.

Some of these circuits may be susceptible to faults during a DBA (such as a high-energy-line break). Actuation of the Class 1E isolation breaker overcurrent protective devices may be necessary in order to prevent degradation of the SR distribution system from electrical faults of NSR circuits. The electrical design basis is to prevent common-mode failures that originate from the failure of NSR circuits. These failures have a potential to affect redundant trains, which in turn has the potential to compromise emergency core cooling systems. Based on the above, provide a discussion why the TS requirements for the Class 1E isolation breaker overcurrent protective devices defined in TS 3/4.8.4.5 do not meet Criterion 3 of 10 CFR 50.36(c)(2)(ii) and, therefore, can be relocated to the UFSAR.

Enclosure