ML031830611

Request for Additional Information - Hope Creek Generating Station - Amendment Request for Change to Reactor Material Surveillance Program

ML031830611
Person / Time
Site:	Hope Creek
Issue date:	07/16/2003
From:	Richard Ennis NRC/NRR/DLPM/LPD1
To:	Richard Anderson Public Service Enterprise Group
Ennis R, NRR/DLPM, 415-1420
References
TAC MB7151
Download: ML031830611 (6)

Text

July 16, 2003 Mr. Roy A. Anderson President & Chief Nuclear Officer PSEG Nuclear, LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - HOPE CREEK GENERATING STATION - AMENDMENT REQUEST FOR CHANGE TO REACTOR MATERIAL SURVEILLANCE PROGRAM (TAC NO. MB7151)

Dear Mr. Anderson:

By letter dated December 23, 2002, PSEG Nuclear, LLC submitted an application for a license amendment for Hope Creek Generating Station (Hope Creek). The proposed amendment would revise the Hope Creek licensing basis, as described in the Updated Final Safety Analysis Report, to replace the current plant-specific reactor pressure vessel material surveillance program with the Boiling Water Reactor Vessel and Internals Project Integrated Surveillance Program.

The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure. We request that the additional information be provided within 30 days of receipt of this letter. The 30-day response timeframe was discussed with Mr. John Nagle of your staff on July 2, 2003. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.

Sincerely,

/RA/

Richard B. Ennis, Senior Project Manager, Section 2 Project Directorate I Division of Licensing and Project Management Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

Request for Additional Information cc w/encl: See next page

Hope Creek Generating Station cc:

Mr. Timothy J. OConnor Lower Alloways Creek Township Vice President - Operations c/o Mary O. Henderson, Clerk PSEG Nuclear - X15 Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Mr. John T. Carlin Radiation Protection Programs Vice President - Engineering NJ Department of Environmental PSEG Nuclear - N10 Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. David F. Garchow Brian Beam Vice President - Projects and Licensing Board of Public Utilities PSEG Nuclear - N28 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Gabor Salamon U.S. Nuclear Regulatory Commission Manager - Nuclear Safety and Licensing 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Hope Creek Generating Station Jeffrie J. Keenan, Esquire U.S. Nuclear Regulatory Commission PSEG Nuclear - N21 Drawer 0509 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company Nuclear Group Headquarters KSA1-E 200 Exelon Way Kennett Square, PA 19348

July 16, 2003 Mr. Roy A. Anderson President & Chief Nuclear Officer PSEG Nuclear, LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - HOPE CREEK GENERATING STATION - AMENDMENT REQUEST FOR CHANGE TO REACTOR MATERIAL SURVEILLANCE PROGRAM (TAC NO. MB7151)

Dear Mr. Anderson:

By letter dated December 23, 2002, PSEG Nuclear, LLC submitted an application for a license amendment for Hope Creek Generating Station (Hope Creek). The proposed amendment would revise the Hope Creek licensing basis, as described in the Updated Final Safety Analysis Report, to replace the current plant-specific reactor pressure vessel material surveillance program with the Boiling Water Reactor Vessel and Internals Project Integrated Surveillance Program.

The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure. We request that the additional information be provided within 30 days of receipt of this letter. The 30-day response timeframe was discussed with Mr. John Nagle of your staff on July 2, 2003. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.

Sincerely,

/RA/

Richard B. Ennis, Senior Project Manager, Section 2 Project Directorate I Division of Licensing and Project Management Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

Request for Additional Information cc w/encl: See next page DISTRIBUTION:

PUBLIC CRaynor GMiller PDI-2 Reading SCoffin GMeyer, RGN-I JClifford JHoncharik OGC REnnis LLois ACRS ADAMS Accession Number: ML031830611 OFFICE PDI-2/PM PDI-2/PM PDI-2/LA EMCB/SC PDI-2/SC NAME GMiller REnnis CRaynor SCoffin JBoska for JClifford DATE 7/2/03 7/7/03 7/2/03 7/10/03 7/15/03 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated December 23, 2002 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML023650558), PSEG Nuclear, LLC (PSEG) submitted an application for a license amendment for Hope Creek Generating Station (Hope Creek). The proposed amendment would revise the Hope Creek licensing basis, as described in the Updated Final Safety Analysis Report (UFSAR), to replace the current plant-specific reactor pressure vessel (RPV) material surveillance program with the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP). The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that the following additional information is required to complete the review.

1. Attachment 1 of your application dated December 23, 2002, stated that in a letter dated March 29, 2002 (ADAMS Accession No. ML021010214), PSEG committed to update fluence calculations in accordance with Regulatory Guide (RG) 1.190 by May 1, 2005. The commitment in the letter dated March 29, 2002, reads as follows:

Based on approval of this request, new pressure-temperature limit curves will be submitted as part of the Hope Creek extended power uprate utilizing the methodology of Regulatory Guide 1.190. Submittal of the technical specification changes are targeted for May 2003 with implementation of the extended power uprate in the Fall 2004 outage.

In addition, PSEGs letter dated May 29, 2003 (ADAMS Accession No. ML031620164),

stated that the extended power uprate submittal is scheduled for September 2003. Please clarify the date of the commitment to update the fluence calculations in accordance with RG 1.190.

2. The NRC staffs letter dated February 1, 2002 (ADAMS Accession No. ML020380691), and the associated Safety Evaluation, provided the staffs approval of the BWRVIP ISP and specified the conditions for BWR licensees participation in the ISP. The staff concluded that the BWRVIP ISP is acceptable for BWR licensee implementation provided that the licensee use one or more compatible neutron fluence methodologies, acceptable to the NRC staff to determine surveillance capsule and RPV neutron fluences. The NRCs letter dated February 1, 2002, also stated that licensees who elect to participate in the program will need to submit a license amendment request to incorporate the ISP into the facility licensing basis.

Enclosure

Attachment 2 of your application dated December 23, 2002, provided the proposed changes to the Hope Creek UFSAR that would be incorporated as a result of the amendment request. However, the proposed changes do not show the methodology that will be used.

The UFSAR markup should be revised to reflect that the methodology used to perform the fluence calculations will be consistent with RG 1.190.