ML041890462

RAI, Safety Limits for Minimum Critical Power Ratio

ML041890462
Person / Time
Site:	FitzPatrick
Issue date:	07/06/2004
From:	Milano P NRC/NRR/DLPM/LPD1
To:	Kansler M Entergy Nuclear Operations
Milano P, NRR/DLPM 415-1457
References
TAC MC3391
Download: ML041890462 (5)

Text

July 6, 2004 Mr. Michael Kansler, President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION CONCERNING SAFETY LIMITS FOR MINIMUM CRITICAL POWER RATIO (TAC NO. MC3391)

Dear Mr. Kansler:

In a letter dated June 4, 2004, Entergy Nuclear Operations, Inc. (Entergy) submitted an application requesting a revision to the Technical Specifications (TSs) for the James A.

FitzPatrick Nuclear Power Plant (JAFNNP). Specifically, the proposed TS revisions would change the safety limit values in TS 2.1.1.2 for the minimum critical power ratio (MCPR).

The Nuclear Regulatory Commission (NRC) staff is reviewing the information provided in the application and has determined that additional information is needed to complete its review.

The specific questions are found in the enclosed supplemental RAI. During a telephone call on July 6, 2004, the Entergy staff indicated that a response to the RAI would be provided within 30 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. 50-333

Enclosure:

As stated cc w/encl: See next page

ML041890462 OFFICE PDI-1/PM PDI-1/LA SRXB/SC PDI-1/SC NAME PMilano SLittle by phone FAkstulewicz RLaufer DATE 07/02/04 07/06/04 07/06/04 07/06/04 FitzPatrick Nuclear Power Plant cc:

Mr. Gary J. Taylor Resident Inspector's Office Chief Executive Officer James A. FitzPatrick Nuclear Power Plant Entergy Operations, Inc. U. S. Nuclear Regulatory Commission 1340 Echelon Parkway P.O. Box 136 Jackson, MS 39213 Lycoming, NY 13093 Mr. John T. Herron Ms. Charlene D. Faison Sr. VP and Chief Operating Officer Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Theodore A. Sullivan Mr. Michael J. Colomb Site Vice President Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. William Maquire Mr. Kevin J. Mulligan Director, Nuclear Safety Assurance General Manager, Plant Operations Entergy Nuclear Operations, Inc.

Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant James A. FitzPatrick Nuclear Power Plant P.O. Box 110 P.O. Box 110 Lycoming, NY 13093 Lycoming, NY 13093 Mr. Andrew Halliday Mr. Danny L. Pace Manager, Regulatory Compliance Vice President, Engineering Entergy Nuclear Operations, Inc.

Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. Brian OGrady Supervisor Vice President, Operations Support Town of Scriba Entergy Nuclear Operations, Inc. Route 8, Box 382 440 Hamilton Avenue Oswego, NY 13126 White Plains, NY 10601 Mr. Charles Donaldson, Esquire Mr. John F. McCann Assistant Attorney General Director, Nuclear Safety Assurance New York Department of Law Entergy Nuclear Operations, Inc. 120 Broadway 440 Hamilton Avenue New York, NY 10271 White Plains, NY 10601

FitzPatrick Nuclear Power Plant cc:

Regional Administrator, Region I Ms. Stacey Lousteau U.S. Nuclear Regulatory Commission Treasury Department 475 Allendale Road Entergy Services, Inc.

King of Prussia, PA 19406 639 Loyola Avenue Mail Stop L-ENT-15E Oswego County Administrator New Orleans, LA 70113 Mr. Steven Lyman 46 East Bridge Street Mr. T. A. Sullivan Oswego, NY 13126 Site Vice President Entergy Nuclear Operations, Inc.

Mr. Peter R. Smith, President P. O. Box 110 New York State Energy, Research, Lycoming, NY 13093 and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Mr. Ken L. Graesser BWR SRC Consultant 38832 N. Ashley Drive Lake Villa, IL 60046 Mr. Jim Sniezek Nuclear Management Consultant 5486 Nithsdale Drive Salisbury, MD 21801 Mr. Ron Toole BWR SRC Consultant 1282 Valley of Lakes Box R-10 Hazelton, PA 18202

REQUEST FOR ADDITIONAL INFORMATION (RAI)

REGARDING SAFETY LIMITS FOR MINIMUM CRITICAL POWER RATIO ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 By letter dated June 4, 2004, Entergy Nuclear Operations, Inc. (the licensee) requested a revision to the Technical Specifications (TSs) for the James A. FitzPatrick Nuclear Power Plant (JAFNPP). Specifically, the licensee proposed changes to the safety limit values in TS 2.1.1.2 for the minimum critical power ratio (MCPR). The Nuclear Regulatory Commission (NRC) staff has the following questions regarding the information provided:

1. Provide the values for power and non-power distribution uncertainties listed in Table 1 of Attachment 4 to the June 4 application. Justify that the proposed reduction of the MCPR value is still providing enough margin for Cycle 17 operation with respect to the results shown in Table 4.1 of General Electric Company (GE) Topical Report NEDC-32601P-A, Methodology and Uncertainties for Safety Limit MCPR Evaluations.

Explain why the reduction in the calculated MCPR value due to using the improved/revised methodology is greater for Cycle 17 than the reduction shown in Table 4.1 of NEDO-32601P-A.

2. Provide the relationship (in terms of the product of bundle-by-bundle MCPR distribution and the bundle pin-by-pin power/R-factor distribution) between the calculated MCPR and the power distribution uncertainty methodology and values that were used. Explain how these influenced the calculated MCPR and why a higher product number in Cycle 17 results with a lower calculated MCPR value than that in Cycle 16, as shown in Table 1 of Attachment 4. Also, explain the reason for obtaining a lower bundle-by-bundle MCPR distribution for Cycle 17 under revised Bases with respect to a higher number for Cycle 17 under the GE Thermal Analysis Basis (GETAB).

3. Describe the core monitoring methods to be used in Cycle 17 operation at JAFNPP and its interface with reduced power distribution uncertainties and other related input parameters as given in Table 2a of Attachment 4. Also, describe how the GEXL correlation R-factor uncertainty shown in Table 2b is generated. Discuss whether this uncertainty is a constant or is fuel-dependent, and provide a justification showing that the proposed value is conservative for this calculation.

4. Describe the issue related to outlet-peaked power shapes at any exposure in the cycle and its safety limit MCPR penalty associated with a top-peaked power shape in GE14 bundles for Cycle 17 operation.

Enclosure