ML023650403

Request for Additional Information, AC Sources Operating - Beyond Scope Issue No. 7

ML023650403
Person / Time
Site:	Indian Point
Issue date:	12/31/2002
From:	Vissing G NRC/NRR/DLPM/LPD1
To:	Kansler M Entergy Nuclear Operations
Vissing G, NRR/DLPM, 415-1441
References
NUREG-1431, TAC MB5068
Download: ML023650403 (6)

Text

December 31, 2002 Mr. Michael R. Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING SECTION 3.8.1 - AC SOURCES OPERATING - BEYOND SCOPE ISSUE NO. 7 (TAC NO. MB5068)

Dear Mr. Kansler:

The Nuclear Regulatory Commission staff is reviewing your application for a license amendment dated March 27, 2002, to change the format and content of the current Technical Specifications (TSs) for the Indian Point Nuclear Generating Unit No. 2 (IP2) to be generally consistent with NUREG-1431, Standard Technical Specifications Westinghouse Plants Technical Specifications, Revision 2, dated April 2001.

On the basis of our review of the changes proposed for improved TS Section 3.8.1, AC Sources - Operating, we find that additional information identified in the enclosure is needed.

We have discussed this with your staff and it was agreeable to your staff to respond to this RAI and provide comments within 60 days from receipt of this letter.

If you have questions regarding this letter or are unable to meet this response schedule, please contact me by phone on (301) 415-1441 or by electronic mail at gsv@nrc.gov.

Sincerely,

/RA/

Guy S. Vissing, Senior Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247

Enclosure:

As stated cc w/encl: See next page

ML023650403 OFFICE PDI-1/PM PDI-1/LA PDI-1/SC NAME GVissing SLittle RLaufer DATE 12/16/02 12/16/02 12/17/02 Indian Point Nuclear Generating Station Unit 2 Mr. Jerry Yelverton Chief Executive Officer Ms. Charlene Faison Entergy Operations Manager, Licensing 1340 Echelon Parkway Entergy Nuclear Operations, Inc.

Jackson, MS 39213 440 Hamilton Avenue White Plains, NY 10601 Mr. Fred Dacimo Vice President - Operations Mr. John McCann Entergy Nuclear Operations, Inc. Manager, Nuclear Safety and Licensing Indian Point Nuclear Generating Units 1 & 2 Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 295 Broadway, Suite 1 P.O. Box 249 P. O. Box 249 Buchanan, NY 10511-0249 Buchanan, NY 10511-0249 Mr. Robert J. Barrett Mr. Harry P. Salmon, Jr.

Vice President - Operations Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

Indian Point Nuclear Generating Units 3 440 Hamilton Avenue 295 Broadway, Suite 3 White Plains, NY 10601 P.O. Box 308 Buchanan, NY 10511-0308 Mr. John M. Fulton Assistant General Counsel Mr. Dan Pace Entergy Nuclear Operations, Inc.

Vice President Engineering 440 Hamilton Avenue Entergy Nuclear Operations, Inc. White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601 Mr. Thomas Walsh Secretary - NFSC Mr. James Knubel Entergy Nuclear Operations, Inc.

Vice President Operations Support Indian Point Nuclear Generating Unit 2 Entergy Nuclear Operations, Inc. 295 Broadway, Suite 1 440 Hamilton Avenue P. O. Box 249 White Plains, NY 10601 Buchanan, NY 10511-0249 Mr. Christopher J. Schwarz Regional Administrator, Region I General Manager Operations U.S. Nuclear Regulatory Commission Entergy Nuclear Operations, Inc. 475 Allendale Road Indian Point Nuclear Generating Unit 2 King of Prussia, PA 19406 295 Broadway, Suite 1 P.O. Box 249 Senior Resident Inspector, Indian Point 2 Buchanan, NY 10511-0249 U. S. Nuclear Regulatory Commission 295 Broadway, Suite 1 Mr. John Kelly P.O. Box 38 Director of Licensing Buchanan, NY 10511-0038 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

Indian Point Nuclear Generating Station Unit 2 Mr. William M. Flynn, President Paul Leventhal New York State Energy, Research, and The Nuclear Control Institute Development Authority 1000 Connecticut Avenue NW 17 Columbia Circle Suite 410 Albany, NY 12203-6399 Washington, DC, 20036 Mr. J. Spath, Program Director Karl Copeland New York State Energy, Research, and Pace Environmental Litigation Clinic Development Authority 78 No. Broadway 17 Columbia Circle White Plains, NY 10603 Albany, NY 12203-6399 Jim Riccio Mr. Paul Eddy Greenpeace Electric Division 702 H Street, NW New York State Department Suite 300 of Public Service Washington, DC 20001 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 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.

639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113 Alex Matthiessen Executive Director Riverkeeper, Inc.

25 Wing & Wing Garrison, NY 10524

REQUEST FOR ADDITIONAL INFORMATION REVIEW OF IMPROVED TECHNICAL SPECIFICATION (ITS) BEYOND SCOPE ITEM NO. 7 ITS SECTION 3.8.1 - AC SOURCES - OPERATING INDIAN POINT UNIT 2

1. Note that Surveillance Requirement (SR) 3.8.1.12 allows all three emergency diesel generators (EDGs) to be tested concurrently, however during shutdown at least one EDG is required to be operable. Please justify testing all three EDGs simultaneously.

2. Provide justification for performing SR 3.8.1.10 for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rather than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by NUREG-1432, Rev. 2.

3. Limiting Condition for Operation (LCO) 3.8.1A3 of NUREG-1432 establishes a limit on the maximum time of 6 days allowed for any combination of required AC power sources to be inoperable during any single contiguous occurrence of failing to meet the LCO.

Please provide justification for not providing this 6-day limit as required by NUREG-1432 in the proposed SRs 3.8.1.A and B.

4. The proposed SRs 3.8.1.7 and 8 verify manual transfer of AC power sources from the normal offsite circuit to the alternate offsite circuit and automatic transfer of AC power for 6.9 kV buses 2 and 3 from the unit auxiliary transformer to 6.9 kV buses 5 and 6 respectively. NUREG-1432 requires that these surveillances not be performed during Modes 1 and 2. Please provide justification for not having any Mode restrictions for these SRs.

5. Required Action 3.8.1.A2 replaces the requirement of current technical specification 3.7.B.4 that 6.9 kV bus tie breaker control switches -- in the CCR [central control room]

shall be placed in the pull-out position and tagged with the requirement to disable the automatic transfer within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and re-verify every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. It is not clear to the staff as to how the operator will know that the switches are in the pull-out position if these switches are not tagged. Please justify for removing the current requirement of tagging the switches.

6. The proposed LCO 3.8.1.A3 requires the declaration of the required feature(s) with no offsite power automatically available inoperable when its redundant required feature(s) is inoperable. Provide justification for not declaring required feature(s) inoperable when its redundant required feature(s) is inoperable when manually connected offsite power source is available.

7. It is stated that on a trip of the main generator, one or two reactor coolant pumps are supplied by the 13.8 kV offsite source and that the 13.8 kV source retains sufficient capacity to support engineered safety feature loads required in Modes 3 and 4. It is not clear to the staff if this source has enough capacity to supply these loads in Modes 1 and 2. Please clarify.

Enclosure

8. Please explain as to why the proposed change to verify that auto transfer is disabled within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rather than the current requirement to disable the automatic transfer performed prior to switching to the 13.8 kV offsite source is a more restrictive change.

In addition, please explain if the 13.8/6.9 kV source is capable of powering the safety loads for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event of a unplanned transfer.

9. NUREG-1432, SR 3.8.1.18 requires verification that the interval between each sequenced load block is within +/-10 % of design interval for each emergency load sequencer. The proposed change verifies that load sequence timer relay functions are within the required design interval. It is not clear to the staff why there is not any compensation provided for the load sequencer timer relay drift.