ML021920079
| ML021920079 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/16/2002 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano P | |
| References | |
| TAC MB2535 | |
| Download: ML021920079 (9) | |
Text
July 16, 2002 Mr. Michael R. Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH SECOND 10-YEAR INSERVICE INSPECTION INTERVAL CLOSEOUT, INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 (TAC NO. MB2535)
Dear Mr. Kansler:
In a letter dated July 16, 2001, Entergy Nuclear Operations, Inc. (ENO) submitted its Second 10-Year Inservice Inspection (ISI) Interval Closeout and associated relief requests for Indian Point Nuclear Generating Unit No. 3 (IP3). ENO requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
Section XI, Inservice Inspection. The Code of record for the ISI Interval was the 1983 Edition, with Summer 1983 Addenda, of ASME Section XI.
The NRC staff and its contractor, Pacific Northwest National Laboratory have reviewed the information submitted by the licensee, and have determined the following information is required to complete the evaluation. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on July 3, 2002, the ENO staff indicated that a response to the RAI would be provided within 60 days.
If you should have any questions, please do not hesitate to call me.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
RAI cc w/encl: See next page
July 16, 2002 Mr. Michael R. Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH SECOND 10-YEAR INSERVICE INSPECTION INTERVAL CLOSEOUT, INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 (TAC NO. MB2535)
Dear Mr. Kansler:
In a letter dated July 16, 2001, Entergy Nuclear Operations, Inc. (ENO) submitted its Second 10-Year Inservice Inspection (ISI) Interval Closeout and associated relief requests for Indian Point Nuclear Generating Unit No. 3 (IP3). ENO requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
Section XI, Inservice Inspection. The Code of record for the ISI Interval was the 1983 Edition, with Summer 1983 Addenda, of ASME Section XI.
The NRC staff and its contractor, Pacific Northwest National Laboratory have reviewed the information submitted by the licensee, and have determined the following information is required to complete the evaluation. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on July 3, 2002, the ENO staff indicated that a response to the RAI would be provided within 60 days.
If you should have any questions, please do not hesitate to call me.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION PUBLIC PDI-1 Reading S. Richards R. Laufer P. Milano S. Coffin S. Little P. Eselgroth, RGN-I T. McLellan B. Platchek, RGN-I OGC ACRS Accession Number: ML021920079 See previous concurrence OFFICE PDI-1:PM PDI-1:LA EMCB:SC*
PDI-1:SC NAME PMilano MOBrien for SLittle SCoffin RLaufer DATE 07/15/02 07/16/02 07/15/02 07/16/02 OFFICIAL RECORD COPY
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. Jerry Yelverton Chief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213 Mr. Robert J. Barrett Vice President - Operations Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P. O. Box 308 Buchanan, NY 10511-0308 Mr. Dan Pace Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Knubel Vice President Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Joseph DeRoy General Manager Operations Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P. O. Box 308 Buchanan, NY 10511-0308 Mr. John Kelly Director - Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene Fiason Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Harry P. Salmon, Jr.
Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Comiotes Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P.O. Box 308 Buchanan, NY 10511-0308 Mr. John Donnelly Licensing Manager Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P.O. Box 308 Buchanan, NY 10511-0308 Mr. John McCann Manager, Licensing and Regulatory Affairs Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 P. O. Box 249 Buchanan, NY 10511-0249 Resident Inspectors Office U.S. Nuclear Regulatory Commission 295 Broadway, Suite 3 P.O. Box 337 Buchanan, NY 10511-0337 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Unit No. 3 cc:
Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. J. Spath, Program Director New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy Electric Division New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Ray Albanese Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592 Mr. Ronald Schwartz SRC Consultant 64 Walnut Drive Spring Lake Heights, NJ 07762 Mr. Ronald J. Toole SRC Consultant Toole Insight 605 West Horner Street Ebensburg, PA 15931 Mr. Charles W. Hehl SRC Consultant Charles Hehl, Inc.
1486 Matthew Lane Pottstown, PA 19465 Mr. Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Mr. Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Mr. Karl Copeland Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001
Enclosure Request for Additional Information Regarding Relief Request RR 3-28 to Use Risk-informed Inservice Inspection Indian Point Nuclear Generating Unit No. 3 (IP3)
Docket No. 50-286 On July 16, 2001, Entergy Nuclear Operations, Inc. (the licensee) submitted requests for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, for Indian Point Nuclear Generating Unit No. 3 (IP3).
The requests for relief are for the closeout of the second 10-year inservice inspection (ISI) interval. The Code of record for the ISI Interval was the 1983 Edition, with Summer 1983 Addenda, of ASME Section XI. The NRC staff and its contractor, Pacific Northwest National Laboratory (PNNL), have reviewed the information submitted by the licensee, and based on this review, determined the following information is required to complete the evaluation.
- 1.
Request for Relief RR 2-Closeout-1, Rev. 0, Examination Category B-A, Pressure Retaining Welds in Reactor Vessel In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee requested relief from 100% volumetric examination of reactor pressure vessel (RPV) longitudinal shell weld no. 5. Upon review of the licensees submittal, clarifications to the request were required. During a conference call with representative from the licensee on July 03, 2002, it was determined that the subject request was intended to satisfy the augmented examination of reactor pressure vessel (RPV) welds as specified in 10 CFR 50.55a(g)(6)(ii)(A), not the Code-required examination of one longitudinal core region weld. Longitudinal weld no. 5, is in fact, outside of the core region, but nonetheless a longitudinal shell weld where volumetric examination coverage is impacted by the geometry of an outlet nozzle.
The Code of Federal Regulations (CFR), specifically Title 10 Section 50.55a(g)(6)(ii)(A),
requires licensees of operating commercial nuclear power reactors to implement a one-time augmented examination of all RPV shell welds. This regulation, which became effective on September 8, 1992, requires that licensees perform volumetric examinations of "essentially 100%" of RPV shell welds in accordance with the 1989 Edition of the ASME Section XI.
Essentially 100% is defined as more than 90% of the examination volume of each weld, where the reduction is due to component geometry or interference with another component. In addition, 10 CFR 50.55a(g)(6)(ii)(A)(5) states that, when licensees determine they are unable to meet the augmented examination requirements, they shall submit information to the NRC staff to support this determination and propose an alternative that would provide an acceptable level of quality and safety.
Therefore, the licensee should revise this request to propose an alternative in accordance with 10 CFR 50.55a(g)(6)(ii)(A)(5). Describe the limitations to the examination, results of the limited examination, and a basis to conclude that your proposed alternative provides an acceptable level of quality and safety.
- 2.
Request for Relief RR 2-Closeout-5, Rev. 0, Examination Category B-K-1, Integral Attachments for Piping, Pumps, and Valves In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee requested relief from performing the Code-required 100% surface or volumetric examination of three integrally welded supports on reactor coolant pump (RCP) no. 32. Due to their design, only limited examinations can be performed on the attachment welds of these supports. The licensee invoked ASME Code Case N-509, which allows a 10% sampling in lieu of the 1983 Code requirement to examine all Class 1 integrally welded attachments. Code Case N-509 also requires that 100% of the sampled items be examined. The NRC staff has determined that N-509 provides an acceptable alternative when adopted in its entirety. However, the staff has concluded that granting relief from a Code Case, which of itself, is an alternative to Code requirements, is not appropriate.
This was discussed with the licensee during the July 3, 2002, conference call.
The licensee should revise this request to propose an alternative in accordance with 10 CFR 50.55a(a)(3)(i) for all Class 1 RCP integrally welded attachments. The alternative should technically support any reduction in population sampling of components in lieu of the 1983 Code requirement to examine all Class 1 integrally welded attachments, as well as, describe the licensees approach to limited examinations for these items. The licensee should include current industry inspection practices, state-of-the-art nondestructive examination methods, or any other factors that would influence a determination that reasonable assurance of the continued structural integrity of the welded attachments has been provided.