ML043580369
| ML043580369 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/23/2004 |
| From: | Darrell Roberts NRC/NRR/DLPM/LPD1 |
| To: | Bakken A Public Service Enterprise Group |
| Miller G, NRR/DLPM, 415-2481 | |
| References | |
| TAC MC4987 | |
| Download: ML043580369 (4) | |
Text
December 23, 2004 Mr. A. Christopher Bakken, III President & Chief Nuclear Officer PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK NUCLEAR GENERATING STATION - EVALUATION OF REQUEST TO UTILIZE 1998 EDITION WITH 2000 ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE FOR THE SECOND 10-YEAR INTERVAL (TAC NO. MC4987)
Dear Mr. Bakken:
By letter dated October 29, 2004, as supplemented by letter dated November 29, 2004, PSEG Nuclear, LLC (PSEG) requested Nuclear Regulatory Commission (NRC) approval to use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI 1998 Edition up to and including the 2000 Addenda for the Hope Creek Generating Station (Hope Creek). PSEGs request was made pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g)(4)(iv). PSEG requested to use the later edition of the ASME Code for the remainder of the second 10-year inservice inspection (ISI) interval, which is scheduled to be completed by December 12, 2007, for all ASME Code,Section XI (Class 1, 2, and 3), Subsections IWB, IWC, IWD, and IWF, systems, structures, and components contained in IWX-2500-1.
PSEG stated that use of the later edition of the ASME Code will ensure a greater degree of implementation consistency between all stations (referring to Hope Creek and Salem Generating Station, Unit Nos. 1 and 2), decrease costs associated with surveillance procedure revisions, reduce opportunities for inadvertent human errors due to differences between code requirements and lessen administrative burdens and complexities associated with maintaining multiple ISI program long-term plans.
In its October 29, 2004, submittal, PSEG stated that they will comply with the following imposed additional requirements, as discussed in Federal Register Notice 69 FR 58804, dated October 1, 2004:
Exam Category B-D, items B3.40, B3.60, B3.120, and B3.140 for the use of ASME [Code] 1998 Edition for the inspection of Nozzle Inner Radii.
Exam Category B-G-2, item B7.80 for the use of ASME [Code] 1995 Edition to perform VT-1 of CRD [control rod drive] housing bolts, studs and nuts when disassembled.
Exam Category B-K, item B10.10 for the use of ASME [Code] 1995 Edition to examine welded attachments on at least one vessel in each group.
A. Christopher Bakken, III Additionally, in response to NRC staff questions, PSEG confirmed in its November 29, 2004, letter that it will comply with the additional requirements that the NRC has imposed for the use of the 1998 Edition, with 2000 Addenda of the ASME Code as discussed in 69 FR 58804:
PSEG will not use the provisions of paragraph IWA-4340 of the 2000 addenda with regard to mitigating defects by modification. When using the 1998 Edition through 2000 Addenda of Section XI of the ASME Code, PSEG will comply with the provisions in IWA-4540(c), 1998 Edition of Section XI, for pressure testing Class 1, 2, and 3 mechanical joints.
PSEG further stated that ASME Code Section XI Subsections IWE and IWL will continue to be performed in accordance with PSEGs previously submitted and NRC-approved relief requests for IWE and IWL for Hope Creek. The NRCs safety evaluation report of that relief request is available in the Agencywide Documents Access and Management System under accession number ML003720636.
The limitations identified above are consistent with the limitations imposed on the implementation of the ASME Code up to the 2003 Addenda, as incorporated by reference in 10 CFR 50.55a. Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), the NRC approves the licensees request to use the 1998 Edition through the 2000 Addenda of the ASME Code,Section XI, with the limitations discussed above, for the remainder of the second 10-year ISI interval for Hope Creek.
If you have any questions, please contact G. Edward Miller, at 301-415-2481.
Sincerely,
/RA/
Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354 cc: See next page
- Input by Memo ML043500052 OFFICE PDI-2/PE PDI-2/PM PDI-2/LA EMCB/SC OGC PDI-2/SC NAME GMiller DCollins CRaynor TChan*
MYoung DRoberts DATE 12/23/04 12/23/04 12/22/04 12/6/2004 12/23/04 12/23/04
Hope Creek Generating Station cc:
Mr. John T. Carlin Vice President - Nuclear Assessment PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Patrick S. Walsh Vice President - Eng/Tech Support PSEG Nuclear - N28 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Michael Brothers Vice President - Site Operations PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James A. Hutton Plant Manager PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038 Ms. Christina L. Perino Director - Licensing & Nuclear Safety 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 Exelon Generation Company, LLC 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