ML021980208
| ML021980208 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/25/2002 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano, P , NRR/DLPM, 415-1457 | |
| References | |
| TAC MB4637 | |
| Download: ML021980208 (7) | |
Text
July 25, 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 (RAI) REGARDING RELIEF REQUEST TO USE RISK-INFORMED INSERVICE INSPECTION, INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 (TAC NO. MB4637)
Dear Mr. Kansler:
In a letter dated February 5, 2002, Entergy Nuclear Operations, Inc. (ENO) submitted proposed Relief Request No. RR 3-38 to use the Risk-Informed Inservice Inspection (RI-ISI)
Program as an alternative to the requirements in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Indian Point Nuclear Generating Unit No. 3. The proposed alternative would be applied to Class 1, Category B-F and B-J welds.
The U.S. Nuclear Regulatory Commission staff is reviewing the information provided in the February 5 submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on July 11, 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 25, 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 (RAI) REGARDING RELIEF REQUEST TO USE RISK-INFORMED INSERVICE INSPECTION, INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 (TAC NO. MB4637)
Dear Mr. Kansler:
In a letter dated February 5, 2002, Entergy Nuclear Operations, Inc. (ENO) submitted proposed Relief Request No. RR 3-38 to use the Risk-Informed Inservice Inspection (RI-ISI)
Program as an alternative to the requirements in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Indian Point Nuclear Generating Unit No. 3. The proposed alternative would be applied to Class 1, Category B-F and B-J welds.
The U.S. Nuclear Regulatory Commission staff is reviewing the information provided in the February 5 submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on July 11, 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 T. Chan M. Rubin P. Milano S. Little T. Clark P. Eselgroth, RGN-I A. Keim S. Dinsmore OGC ACRS Accession Number: ML021980208
- Concurred on by e-mail dated 7/24/02 OFFICE PDI-1:PM PDI-1:LA*
EMCB:SC SPSB:SC PDI-1:SC NAME PMilano SLittle TChan SDinsmore for MRubin RLaufer DATE 07/25/02 7/24/02 07/25/02 07/25/02 07/25/02 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 In a letter dated February 5, 2002, Entergy Nuclear Operations, Inc. (the licensee) submitted a proposed Relief Request No. RR 3-38 to use the Risk-Informed Inservice Inspection (RI-ISI)
Program as an alternative to the requirements in Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers(ASME)
Boiler and Pressure Vessel Code for Indian Point Nuclear Generating Unit No. 3. The NRC staff has the following questions regarding the information provided in the proposed alternative:
- 1.
Section 3.4, Risk Characterization, of RI-ISI Program Plan states, in part, that each piping segment was evaluated to determine its potential for failure and impact on containment performance (isolation, bypass and large early release). The Program Plan does not include a large early release frequency (LERF) estimate for your probablisitc risk assessment nor any other LERF information. Describe how the impact of segment failure on containment performance (isolation, bypass and large early release) was evaluated.
- 2.
Provide a discussion of the expected change in LERF due to implementing the RI-ISI program.
- 3.
In Section 4, Implementation and Monitoring, the licensee addresses the procedures to implement and monitor the RI-ISI program. Does the licensee plan, as a minimum, to review and adjust the risk ranking of piping segments on an ASME ISI interval basis?
Will information coming from NRC bulletins or generic letters and from industry and plant-specific feedback be evaluated for significance and factored, as necessary, into more frequent adjustments of the ranking?
- 4.
Section 3.5.1, Additional Examinations, states that "[a]dditional examinations will be performed on these elements up to a number equivalent to the number of elements required to be inspected on the segment or segments initially." Clarify this statement regarding the sample size selection for augmented inspections.
If additional examinations are needed following the identification of an unacceptable flaw, will all high and medium risk welds in the population of welds (with the same degradation mechanisms) be included in the examination population from which the additional sample will be selected? Discuss the time frame for performing these expanded examinations.