ML033570293
| ML033570293 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-070) |
| Issue date: | 12/12/2003 |
| From: | Mannon S Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LRN-03-0499, S1-13-RR-A13 | |
| Download: ML033570293 (4) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 DEC 1 2 2003 O PSEG LRN-03-0499 ANuclearLLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SALEM GENERATING STATION - UNIT I THIRD TEN-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST S1-13-RR-A13 FACILITY OPERATING LICENSE DPR-70 DOCKET NOS. 50-272
Reference:
Letter LRN-01-031 0, Salem Generating Station -Unit I Third Ten -Year Inservice Inspection Program Submittal, dated September 25, 2001.
The referenced letter states that the specified Code of record referenced by 10CFR50.55a(b) for Salem Generating Station - Unit 1 is Section Xl of the ASME Boiler and Pressure Vessel Code, Division 1, 1995 Edition, 1996 Addenda, except for Subsection IWE and IWL that will comply with the 1998 Edition through 1998 Addenda.
Pursuant to I OCFR50.55a(g)(4)(iv), PSEG Nuclear requests NRC approval of the following request for the third ten-year Inservice Inspection Interval for Salem Generating Station - Unit 1. PSEG proposes to upgrade the Code of record to the ASME Boiler and Pressure Vessel Code, Division 1,Section XI 1998 Edition up through and including 2000 Addenda for the remainder of the third 10-year Inservice Inspection Interval. PSEG has adopted this edition of the Code for the second 10-year Inservice Inspection Interval for Salem Generating Station - Unit 2, which began on November 26, 2003. The details of this request are enclosed in Attachment 1 to this submittal.
PSEG requests approval of this relief request by March 2004, to support the Spring 2004 Refueling Outage (1R16).
Should you have any questions regarding this request, please contact Mr. Michael Mosier at 856-339-5434.
Sincerely, Steven Mannon Manager-Nuclear Safety and Licensing Attachment 95-2168 REV. 7/99
Document Control Desk 2
LRN-03-0499 DEC 1 2 2003 C
Mr. H. Miller Regional Administrator-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Fretz, Project Manager-Salem U.S. Nuclear Regulatory Commission Mail Stop 08B2 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
Document Control Desk Attachment I LRN-03-0499 10 CFR 50.55a Relief Request SI-13-RR-A13 Proposed Use of Subsequent Edition and Addenda In Accordance with 10 CFR 50.55a(g)(4)(iv) for Inservice Inspection Items ASME Code Components Affected All affected ASME Xl Subsections IWB, IWC, IWD and IWF (Class 1,2 and 3) systems, structures and components contained within Tables IWX-2500-1.
Applicable Code Edition and Addenda
PSEG Nuclear specified the ASME Boiler and Pressure Vessel Code Section Xl 1995 Edition up through and including 1996 as the "Code of Record" by reference 12 months prior to the start of the Third 10 Year Inspection Interval (May 19, 2001) in accordance with 10CFR50.55a(g)(4)(ii). The version of 10 CFR 50 in effect on May 19, 2001 indicated ASME Boiler and Pressure Vessel Code Section Xl 1995 Edition up through and including 1996 Addenda was applicable.
Proposed Subsequent Code Edition and Addenda PSEG Nuclear proposes to use the ASME Code Edition and Addenda in accordance with 10CFR50.55a(g)(4 (iv) to perform IS1 on all affected ASME Xl (Class 1,2 and 3)
Subsections IWB, IWC, IWD and IWF systems, structures and components contained within Tables IWX-2500-1. The Federal Register (Notice 66 FR 40626) amended 1 OCFR50.55a(g) and revised the requirements for inservice inspection (ISI) of nuclear power plant components by permitting the use of ASME Boiler and Pressure Vessel Code, Section Xl 1998 Edition up through and including 2000 Addenda.
ASME Xl Exam Categories B-F, B-J, C-F-1 and C-F-2 will be performed in accordance with the Salem Units 1 and 2 Risk Informed Inservice Inspection (RI-ISI) of class 1 and 2 piping systems as approved by an NRC Safety Evaluation Report (SER) issued on October 27, 2003.
Related Requirements 10CFR50.55a(g)(4)(iv) indicates 'Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the limitations and modifications listed in 1 OCFR50.55a (b)(2), and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.
PSEG will comply with 1998 Edition up through and including 2000 Addenda unless relief is requested in accordance with 1 OCFR50.55a (a)(3). PSEG will comply with the following 10CFR50.55a imposed additional requirements for:
1
N Document Control Desk LRN-03-0499 Attachment I 10 CFR 50.55a Relief Request SI-13-RR-A13 Proposed Use of Subsequent Edition and Addenda In Accordance with 10 CFR 50.55a(a)(4)(iv) for Inservice Inspection Items 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, items B7.80 item B7.80 for the use of ASME 1995 Edition to perform VT-I of CRD housing bolts, studs and nuts when disassembled.
o Exam Category B-K, items B10.10 for the use of ASME 1995 Edition to examine welded attachments on at least one vessel in each group.
Duration of Proposed Request This Request is applicable to:
Salem, Unit I - Third Ten-Year Interval Inservice Inspection Program 2