ML081680531
| ML081680531 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/24/2008 |
| From: | Adrian Muniz NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Entergy Nuclear Operations |
| muniz A, ADRO/DORL/415-4044 | |
| References | |
| TAC MD8556 | |
| Download: ML081680531 (5) | |
Text
June 24, 2008 Vice President, Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 10393
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION FOR RELOCATION OF PRESSURE AND TEMPERATURE CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. MD8556)
Dear Sir or Madam:
On April 22, 2008, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment for the James A. FitzPatrick Nuclear Power Plant which would adopt the methodology of SIR-05-044-A, Pressure-Temperature Limits Report [PTLR] Methodology for Boiling Water Reactors, for preparation of the pressure and temperature curves, and incorporate the guidance of Technical Specification Task Force TSTF-419-A, Revise PTLR Definition and References in ISTS [Improved Standard Technical Specifications] 5.5.6, RCS
[Reactor Coolant System] PTLR.
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). During a telephone call on June 23, 2008, the Entergy staff indicated that a response to the RAI would be provided by July 23, 2008.
Please contact me at (301) 415-4093 if you have any questions on this issue.
Sincerely,
/RA/
Adrian Muniz, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
RAI cc w/encl: See next page
ML081680531 OFFICE LPL1-1/PM LPL1-1/LA CVIB/BC LPL1-1/BC NAME AMuniz SLittle MMitchell/BElliot for MKowal DATE 6/23/08 6/23/08 6/23/08 6/24/08
James A. FitzPatrick Nuclear Power Plant 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.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 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 Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Oswego County Administrator Mr. Steven Lyman 46 East Bridge Street Oswego, NY 13126 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING RELOCATION OF PRESSURE AND TEMPERATURE CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT (JAFNPP)
DOCKET NO. 50-333 In a letter dated April 22, 2008, (ADAMS Accession No. ML081200881), Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment to the Technical Specifications (TSs) (or license or licensing basis) for the James A. FitzPatrick Nuclear Power Plant which would adopt the methodology of SIR-05-044-A, Pressure-Temperature Limits Report [PTLR] Methodology for Boiling Water Reactors, for preparation of the pressure and temperature curves, and incorporate the guidance of Technical Specification Task Force TSTF-419-A, Revise PTLR Definition and References in ISTS [Improved Standard Technical Specifications] 5.5.6, RCS [Reactor Coolant System] PTLR. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following questions:
- 1.
Provide an evaluation showing that you have performed analysis for the bottom head region and the non-beltline region in accordance with SIR-05-044-A and identify the portion of the proposed P-T limits (Figure 3 of the proposed PTLR is sufficient) that are limited by materials in these regions.
- 2.
Provide an evaluation for the small diameter, drill-hole type instrument nozzle (e.g., water level nozzle) if it exists in your reactor pressure vessel (RPV) beltline.
- 3.
Identify among the three methodologies (Page 2-13 of SIR-05-044-A) the one that you used to calculate thermal stress intensity factors for shell regions.
- 4.
Provide the temperature instrument uncertainty, the pressure instrument uncertainty, and the pressure head to account for the column of water in the RPV (Page 2-25 of SIR 044-A) so that the NRC staff can assess the difference between the staffs calculated P-T limits and your proposed P-T limits.
- 5.
Provide Reference 6.3, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts, dated February 2008; Reference 6.4, Revised P-T Curves, dated February 2008, and Reference 6.14, BWRVIP-135, Revision 1: BWR Internals Project, Integrated Surveillance Program Data Source Book and Plant Evaluation, dated June 2007, to supplement the above requested specific information and to provide information regarding data and methodology for the adjustment of chemistry factors.
- 6.
The guidelines in SIR-05-044-A provided for analysis of feedwater nozzles. Identify the specific analysis performed for the JAFNPP feedwater nozzles, or explain why the analysis was not necessary.