ML080350278

Request for Additional Information Regarding Amendment Application to Modify Technical Specifications for the Diesel Generator Endurance Test

ML080350278
Person / Time
Site:	Indian Point
Issue date:	02/07/2008
From:	Boska J NRC/NRR/ADRO/DORL/LPLI-1
To:	Balduzzi M Entergy Nuclear Operations
Boska J, NRR, 301-415-2901
References
TAC MD4923
Download: ML080350278 (8)

Text

February 7, 2008 Mr. Michael A. Balduzzi Sr. Vice President & COO Regional Operations, NE Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION TO MODIFY TECHNICAL SPECIFICATIONS FOR THE DIESEL GENERATOR ENDURANCE TEST (TAC NO. MD4923)

Dear Mr. Balduzzi:

On March 22, 2007, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment for Indian Point Nuclear Generating Unit No. 2 which would revise the test acceptance criteria for the endurance test for the emergency diesel generators, Technical Specification Surveillance Requirement 3.8.1.10.

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). In an email dated January 29, 2008, the Entergy staff indicated that a response to the RAI would be provided by March 31, 2008.

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

ML080350278 OFFICE LPL1-1/PM LPL1-1/LA EEEB/BC LPL1-1/BC NAME JBoska SLittle GWilson MKowal DATE 2/04/08 2/06/08 2/06/08 2/07/08

Indian Point Nuclear Generating Unit No. 2 cc:

Mr. Michael R. Kansler President & CEO / CNO Entergy Nuclear Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Sr. Vice President Entergy Nuclear Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Sr. Vice President Engineering & Technical Services Entergy Nuclear Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Mr. Fred R. Dacimo Site Vice President Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Anthony Vitale - Acting General Manager, Plant Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511-0249 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Mr. Joseph P. DeRoy Vice President, Operations Support Entergy Nuclear Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Mr. John A. Ventosa GM, Engineering Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Mr. Ernest J. Harkness Director, Oversight Entergy Nuclear Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Mr. Patric W. Conroy Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Robert Walpole Manager, Licensing Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P. O. Box 249 Buchanan, NY 10511-0249 Mr. William C. Dennis Assistant General Counsel Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

Indian Point Nuclear Generating Unit No. 2 cc:

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 3 Empire State Plaza Albany, NY 12223-1350 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 Senior Resident Inspector=s Office Indian Point 3 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. William DiProfio PWR SRC Consultant 48 Bear Hill Road Newton, NH 03858 Mr. Garry Randolph PWR SRC Consultant 1750 Ben Franklin Drive, 7E Sarasota, FL 34236 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 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

Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION TO MODIFY TECHNICAL SPECIFICATIONS FOR THE DIESEL GENERATOR ENDURANCE TEST ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 By letter to the Nuclear Regulatory Commission (NRC) dated March 22, 2007, (Agencywide Documents Access Management System (ADAMS) Accession No. ML070890307), Entergy Nuclear Operations, Inc. (Entergy or the licensee) requested an amendment to the Indian Point Nuclear Generating Unit No. 2 (IP2) Technical Specifications (TS) Surveillance Requirement (SR) related to test acceptance criteria for emergency diesel generator (EDG) testing. By letter dated July 23, 2007 (ADAMS Accession No. ML072000254) the NRC requested additional information from the licensee. By letter dated November 13, 2007 (ADAMS Accession No. ML073250358), the licensee supplied the additional information. The NRC staff is reviewing the submittal and has the following questions:

1.

The IP2 response to Question 2a on the EDGs in the Entergy letter dated November 13, 2007, stated, The sequential limitation applied to the overload rating results from test and evaluation of the EDG output breaker (Westinghouse DB-75 switchgear) which has a continuous rating of 3000 A at 40° C. With the EDG upgrade to 2100 kW and 2300 kW, the equivalent amperes are 3000 A and 3300 A, respectively. Since 3300 A is above the continuous rating of the switchgear, evaluation and testing of the short-term ratings was performed. Testing was performed by Satin American Corp on a Westinghouse breaker of similar vintage and considered bus duct and switchgear sections. The limiting component was identified as the phenolic insulators on the breakers.

a.

Provide documentation from the breaker and switchgear vendors/manufacturers that operation above the breakers and switchgears continuous rating of 3000 A is acceptable (provide time constraints for currents above 3000 A if such operation is allowed). Provide justification that the breaker is operable during worst-case accident scenarios when current exceeds 3000 A. Also provide documentation from the breaker manufacturer that there is sufficient margin in the published ratings to handle the design-basis accident (DBA) loading (for loss of offsite power (LOOP) with a large-break loss-of-coolant accident (LBLOCA) and LOOP with a small-break loss-of-coolant accident (SBLOCA)).

b.

Provide the testing documentation (which includes set-up, procedure, sample size, and results) from Satin American Corp. Verify that the testing was performed under a 10 CFR Part 50 Appendix B program.

c.

Tables 5.3-2b, 5.5-2a, 6.1-2a, and 6.1-2c of the EDG loading calc show conditions where the loading exceeds the 2-hour short-term rating after a half-hour of operation into an event. Provide justification that the EDG output breaker and switchgear will remain operable under these accident scenarios given the sequential limitation for operating at the ratings as discussed in the TS Bases.

d.

Provide documentation which supports that the 480 V switchgear (including the EDG output breakers) is properly sized following the EDG upgrade modification.

2.

Demonstrate that the worst case load profiles (and the proposed TS SR acceptance criteria) take into account the 90 kW instrument uncertainty stated on page 2-1 of the loading calculation. If not, explain how this uncertainty would be incorporated into the proposed testing given that in some instances, the added uncertainty would exceed the 2300 kW rating threshold. Consider the effects of operating the EDGs at the upper range of the allowable frequency, minimum acceptable voltage and the average power factor of the total load. These factors affect the EDG loading and current flow through the output breaker.

3.

Provide the vendor/manufacturers supporting documentation for the EDG short term and extended operation ratings (after the upgrade modification).

4.

How were the short-time ratings determined, and what are the consequences for operating the EDGs beyond these ratings (the license amendment request is proposing to test the EDGs for a half-hour beyond the 2-hour short-time rating)?

5.

What is the design basis temperature of the EDG room, and what is the peak temperature that the room will reach during a DBA? Provide the EDG vendors derating curves for temperatures. Also, provide confirmation that the generator set is adequately rated for the peak temperatures.

6.

Provide the loading profile for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of a LOOP/SBLOCA assuming the failure of one EDG. Also provide the loading profile for the LOOP/LBLOCA and LOOP/SBLOCA for long-term operation (at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />).

7.

The SBLOCA loading profiles show peak loads of 2300 kW (Table 6.1-2a) and 2266 kW (Table 6.1-2c). Provide documentation to support that the proposed power factor values bound these scenarios.

8.

IP2 is proposing EDG load curtailment after 70 minutes into an event. Verify that the safety analyses evaluation for the worst-case scenario envelopes the core decay heat load with electrical loads curtailed or reduced.