ML031710391

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Request for Additional Information, Relief Request HC-RR-B12
ML031710391
Person / Time
Site: Hope Creek 
Issue date: 06/26/2003
From: Richard Ennis
NRC/NRR/DLPM/LPD1
To: Richard Anderson
Public Service Enterprise Group
Ennis R, NRR/DLPM, 415-1420
References
TAC MB8407
Download: ML031710391 (4)


Text

June 26, 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 - RELIEF REQUEST HC-RR-B12 (TAC NO. MB8407)

Dear Mr. Anderson:

By letter dated April 14, 2003, PSEG Nuclear, LLC, requested relief from the required volumetric examination required by the American Society of Mechanical Engineers Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item B3.100. The relief was requested pursuant to Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(ii). The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that the information contained in the enclosed request for additional information will be needed for the staff to complete its review.

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 Vice President - Operations PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John T. Carlin Vice President - Engineering PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David F. Garchow Vice President - Projects and Licensing PSEG Nuclear - N28 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Gabor Salamon Manager - Nuclear Safety and Licensing PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 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 Lower Alloways Creek Township c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 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 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038

June 26, 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 - RELIEF REQUEST HC-RR-B12 (TAC NO. MB8407)

Dear Mr. Anderson:

By letter dated April 14, 2003, PSEG Nuclear, LLC, requested relief from the required volumetric examination required by the American Society of Mechanical Engineers Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item B3.100. The relief was requested pursuant to Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(ii). The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that the information contained in the enclosed request for additional information will be needed for the staff to complete its review.

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 PDI-2 R/F JClifford REnnis GMiller CRaynor OGC WHeld TChan GMeyer, RGN 1 ADAMS Accession Number: ML031710391 OFFICE PDI-2/PM PDI-2/PM PDI-2/LA PDI-2/SC NAME GMiller REnnis CRaynor REnnis for JClifford DATE 6/24/2003 6/24/03 06/25/03 6/25/03 Official Record Copy

Enclosure REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RELIEF REQUEST HC-RR-B12 HOPE CREEK GENERATING STATION DOCKET NUMBER 50-354 By letter dated April 14, 2003, PSEG Nuclear, LLC (the licensee), requested relief from the required volumetric examination required by the American Society of Mechanical Engineers Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item B3.100. The relief was requested pursuant to Title 10 of the Code of Federal Regulations Section 50.55a(a)(3)(ii). The NRC staff is reviewing your submittal and has determined that the following information will be needed for the staff to complete its review.

1. Table 1 in the submittal includes the summary number and component identification for each nozzle to be examined. The type of nozzle to be examined is also important because nozzles subjected to large thermal gradients have a past history of thermal cracking.

Describe the type (i.e., feedwater, recirculation inlets, jet pump instrumentation, etc.),

nominal inside diameter and material (i.e., carbon, nickel, etc.) of the nozzles included in the relief request.

2. The licensee states the estimated coverage of each of the nozzles in Table 1 of its submittal. This list fails to state specific information about which area of the nozzle will be inaccessible to examination (e.g., top, side, bottom). The severity of thermal fatigue is dependant upon the circumferential location, thermal gradient and thermal sleeve leakage.

Describe the portion of each nozzle that will be inaccessible to examination, providing a sketch if necessary.

3. In the alternative, the licensee states that the resolution sensitivity will be established using a 1-mil diameter wire standard that is similar to that used for other reactor pressure vessel internal examinations intended to detect cracking, without stating which standards are being referenced. Explain the qualification process that will be used to demonstrate the 1-mil width sensitivity and the equipment used for the examination.