LR-N04-0421, Update ASME XI Code of Record
| ML043140290 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/29/2004 |
| From: | Perino C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N04-0421 | |
| Download: ML043140290 (6) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 OCT 2 9 2004
@ PSEG LR-N04-0421 NuclearLLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 SALEM GENERATING STATION UNIT I UPDATE ASME XI CODE OF RECORD FACILITY OPERATING LICENSE DPR-70 DOCKET NO. 50-272
Reference:
LR-N04-0130, Salem Generating Station - Unit I Third Ten-Year Inservice Inspection Interval Update ASME XI Code of Record, dated March 24, 2004 The referenced letter informed the NRC that the Code of record for Salem Generating Station - Unit 1 for the remainder of the third 10-year interval, which is scheduled to be completed by May 20, 2011, has been upgraded to the latest approved ASME Section XI (ASME Boiler and Pressure Vessel Code, Section Xl 1998 Edition up through and including 2000 Addenda) incorporated into 1 OCFR50.55a for ISI on all affected ASME XI (Class 1, 2 and 3) Subsections IWB, IWC, IWD and IWF systems, structures and components contained within Table IWX-2500-1. Subsequently, on July 28, 2004, the NRC issued Regulatory Issue Summary (RIS) 2004-12. RIS 2004-12 indicates that licensees must request approval in writing in accordance with 1 OCFR50.55a(f)(4)(iv) or 1 OCFR50.55a(g)(4)(iv).
The current ISI Program for Salem Generating Station - Unit 1 is based on ASME Section Xl 1995 Edition up through and including 1996 Addenda. This letter requests approval, in accordance with IOCFR50.55a(g)(4)(iv), to use the code referenced above. This will ensure a greater degree of implementation consistency, 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. PSEG requests approval by February 2005.
ADQ4 95-2168 REV. 7/99
LR-N04-0421 2
OCT 2 9 2004 Document Control Desk PSEG will comply with 1998 Edition up through and including 2000 Addenda unless relief is requested in accordance with 10CFR50.55a (a)(3). PSEG will comply with the following imposed additional requirements for:
o Exam Category B-D, items B3.40, B3.60, B3.120 and B3.140 for the use of ASME 1998 Edition for the inspection of Nozzle Inner Radii.
o Exam Category B-G-2, item B7.80 for the use of ASME 1995 Edition to perform VT-1 of CRD housing bolts, studs and nuts when disassembled.
o Exam Category B-K, item B10.10 for the use of ASME 1995 Edition to examine welded attachments on at least one vessel in each group.
ASME Xl Subsections IWE and IWL will continue to be performed in accordance with PSEG Nuclear's previously submitted and approved relief requests for IWE and IWL and the NRC's Safety Evaluation Reports (SER) (TAC MA6865, MA6866, and MA6867) for Salem Units I and 2 containment inspections.
ASME Xl Appendix Vil requirements will continue to be performed in accordance with ASME Xl 1998 Edition up to and including the 2000 Addenda, as modified by 1 OCFR.50.55a final rulemaking.
There are no new commitments contained in this letter. If you have any questions, please contact Michael Mosier at (856) 339-5434.
Siner y,
Christina L. Perino Director - Licensing and Nuclear Safety
LR-N04-0421 3
OCT 2 9 2004 Document Control Desk C:
Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager-Hope Creek/Salem U.S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625
.1
'r v-PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 OCT 2 9 2004 0 PSEG LR-N04-0420 Nuclear LLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 HOPE CREEK GENERATING STATION UPDATE ASME Xl CODE OF RECORD FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354
Reference:
LR-N04-0161, Hope Creek Generating Station Second Ten-Year Inservice Inspection Interval Update ASME Xl Code of Record, dated, May 7, 2004 The referenced letter informed the NRC that the Code of record for Hope Creek Generating Station for the remainder of the second ten-year interval, which is scheduled to be completed by December 12, 2007, has been upgraded to the latest approved ASME Section Xl incorporated into 10CFR50.55a for ISI on all affected ASME XI (Class 1, 2 and 3) Subsections IWB, IWC, IWD and IWF systems, structures and components contained within Table IWX-2500-1. The latest approved Code is the ASME Boiler and Pressure Vessel Code, Section Xl 1998 Edition up through and including 2000 Addenda. Subsequently, on July 28, 2004, the NRC issued Regulatory Issue Summary (RIS) 2004-12. RIS 2004-12 indicates that licensees must request approval in writing in accordance with 1 OCFR50.55a(g)(4)(iv) or 1 OCFR50.55a(g)(4)(iv).
The current ISI Program for Hope Creek Generating Station is based on ASME Section Xl, 1989 Edition no Addenda. This letter requests approval, in accordance with10CFR50.55a(g)(4)(iv), to use the code referenced above. This will ensure a greater degree of implementation consistency between all stations, 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.
95-2168 REV. 7/99
LR-N04-0420 2
OCT 2 9 2004 Document Control Desk PSEG will comply with 1998 Edition up through and including 2000 Addenda unless relief is requested in accordance with 10CFR50.55a (a)(3). PSEG will comply with the following imposed additional requirements for:
o Exam Category B-D, items B3.40, B3.60, B3.120 and B3.140 for the use of ASME 1998 Edition for the inspection of Nozzle Inner Radii.
o Exam Category B-G-2, item B7.80 for the use of ASME 1995 Edition to perform VT-1 of CRD housing bolts, studs and nuts when disassembled.
o Exam Category B-K, item B10.10 for the use of ASME 1995 Edition to examine welded attachments on at least one vessel in each group.
ASME Xl Subsections IWE and IWL will continue to be performed in accordance with PSEG Nuclear's previously submitted and approved relief requests for IWE and IWL and the NRC's Safety Evaluation Reports (SER) (TAC MA6865, MA6866, and MA6867) for Hope Creek Generating Station containment inspection.
ASME Xl Appendix Vill requirements will continue to be performed in accordance with ASME Xl 1998 Edition up to and including the 2000 Addenda, as modified by IOCFR.50.55a final rulemaking.
There are no new commitments contained in this letter. If you have any questions, please contact Michael Mosier at (856) 339-5434.
Sincerely, Christina L. Perino Director - Licensing and Nuclear Safety
LR-N04-0420 3
OCT 2 9 2004 Document Control Desk C
Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager-Hope Creek/Salem U.S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. K. Tosch Manager IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625