ML081650521
| ML081650521 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/19/2008 |
| From: | Boska J NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MD7501 | |
| Download: ML081650521 (4) | |
Text
June 19, 2008 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION FOR EMERGENCY CORE COOLING SYSTEM VALVE SURVEILLANCE REQUIREMENTS (TAC NO. MD7501)
Dear Sir or Madam:
On December 13, 2007, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment for Indian Point Nuclear Generating Unit No. 2 which would change the surveillance requirements for a portion of the emergency core cooling system valves.
The Nuclear Regulatory Commission staff is reviewing the 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). On June 3, 2008, the Entergy staff indicated that a response to the RAI would be provided within 30 days of the date of this letter.
Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely,
/RA/
John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
RAI cc w/encl: See next page
- Per memo dated May 27, 2008.
OFFICE LPL1-1/PM LPL1-1/LA SRXB/BC LPL1-1/BC NAME JBoska SLittle GCranston*
MKowal DATE 6/19/08 6/19/08 5/27/08 6/19/08
Indian Point Nuclear Generating Unit No. 2 cc:
Senior Vice President Entergy Nuclear Operations Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Vice President Oversight Entergy Nuclear Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Senior Vice President and COO Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Paul Tonko President and CEO New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. John P. Spath New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Department of Public Service Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector=s Office Indian Point 2 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Phillip Musegaas Riverkeeper, Inc.
828 South Broadway Tarrytown, NY 10591 Mr. Mark Jacobs IPSEC 46 Highland Drive Garrison, NY 10524 Mr. Sherwood Martinelli FUSE USA via email 3 Empire State Plaza Albany, NY 12223-1350
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING EMERGENCY CORE COOLING SYSTEM VALVE SURVEILLANCE REQUIREMENTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 In a letter dated December 13, 2007 (ADAMS Accession No. ML073540519), Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment to the Technical Specifications (TSs) and license for Indian Point Nuclear Generating Unit No. 2 which would change the surveillance requirements for a portion of the emergency core cooling system (ECCS) valves. The Nuclear Regulatory Commission staff is reviewing the submittal and has the following questions:
- 1.
Please provide flow diagrams for the systems in which the subject seven valves are located. Identify the valves in the diagrams.
- 2.
If the high-head branch line stop valves are set to the open position, with power removed, and not regularly surveilled, then how can the inadvertent closure of one of these valves be assumed as the single failure in a loss-of-coolant accident (LOCA) analysis? Would this not be an undetected operator error; unrelated to the LOCA?
- 3.
If one of these valves can be inadvertently closed, then why not more than one? Why not all?
- 4.
If a high-head branch line stop valve is closed, then its branch line becomes inoperable, since it is incapable of performing its design function. How would this inoperable status be detected?
- 5.
If a high-head branch line stop valve is found closed, is there a controlled procedure to re-open it within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />? If yes, then what is it?
- 6.
The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of allowed outage is based upon the results of an SAI study of the Surry plant, Reference 5 in the application. The report noted (1) the Surry plant ECCS is rather atypical of most PWRs [pressurized-water reactors], and (2) recent changes to the Surry plant, particularly power lockout of some valves, are not reflected. Justify the applicability of Reference 5 to Indian Point Unit 2, with the four high-head branch line stop valves locked open.