ML021050296

Issuance of Amendment Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip Instrumentation Setpoint (Tac No. MB3153)

ML021050296
Person / Time
Site:	FitzPatrick
Issue date:	05/08/2002
From:	Vissing G NRC/NRR/DLPM/LPD1
To:	Kansler M Entergy Nuclear Operations
Vissing G, NRR/DLPM, 415-1441
Shared Package
ML021330077	List: ML021050296 ML021290213
References
-RFPFR, TAC MB3153
Download: ML021050296 (12)

Text

May 8, 2002 Mr. Michael Kansler Sr. Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - AMENDMENT REGARDING ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)

RECIRCULATION PUMP TRIP INSTRUMENTATION SETPOINT (TAC NO. MB3153)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 273 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 28, 2001.

The amendment revises the ATWS Recirculation Pump Trip Reactor Pressure High setpoint by replacing the current conditional setpoints, which are based upon the number of Safety Relief Valves out of service, with a single setpoint.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.

Sincerely,

/RA/

Guy S. Vissing, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosures:

1. Amendment No. 273 to DPR-59

2. Safety Evaluation cc w/encls: See next page

May 8, 2002 Mr. Michael Kansler Sr. Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - AMENDMENT REGARDING ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)

RECIRCULATION PUMP TRIP INSTRUMENTATION SETPOINT (TAC NO. MB3153)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 273 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 28, 2001.

The amendment revises the ATWS Recirculation Pump Trip Reactor Pressure High setpoint by replacing the current conditional setpoints, which are based upon the number of Safety Relief Valves out of service, with a single setpoint.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.

Sincerely,

/RA/

Guy S. Vissing, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosures:

1. Amendment No. 273 to DPR-59

2. Safety Evaluation cc w/encls: See next page Package: ML021330077 TSs: ML021290213 Accession Number: ML021050296 *Safety Evaluation Provided on 2/20/02 - No major changes OFFICE PDI-1\PM PDI-1\LA EEIB/SC* SRXB/BC* OGC PDI-1\SC NAME GVissing SLittle EMarinos JWeirmiel RHoefling PTam for RLaufer DATE 5/1/02 5/1/02 2/20/02 2/20/02 4/24/02 5/8/02 OFFICIAL RECORD COPY

FitzPatrick Nuclear Power Plant cc:

Mr. Jerry Yelverton Ms. Charlene D. Faison Chief Executive Officer Licensing Entergy Operations Entergy Nuclear Operations, Inc.

1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Theodore H. Sullivan Supervisor Vice President Operations Town of Scriba Entergy Nuclear Operations, Inc. Route 8, Box 382 James A. FitzPatrick Nuclear Power Plant Oswego, NY 13126 P.O. Box 110 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General Mr. Dan Pace New York Department of Law Vice President, Engineering 120 Broadway Entergy Nuclear Operations, Inc. New York, NY 10271 440 Hamilton Avenue White Plains, NY 10601 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. John Kelly 475 Allendale Road Director - Licensing King of Prussia, PA 19406 Entergy Nuclear Operations, Inc.

4400 Hamilton Avenue Oswego County Administrator White Plains, NY 10601 Jack Tierney 46 East Bridge Street Mr. George Tasick Oswego, New York 13126 Licensing Manager Entergy Nuclear Operations, Inc. Mr. William M. Flynn, President James A. FitzPatrick Nuclear Power Plant New York State Energy, Research, P.O. Box 110 and Development Authority Lycoming, NY 13093 Corporate Plaza West 286 Washington Avenue Extension Resident Inspectors Office Albany, NY 12203-6399 U. S. Nuclear Regulatory Commission P.O. Box 136 Mr. Arthur Zaremba, Licensing Manager Lycoming, NY 13093 Director, Safety Assurance Entergy Nuclear Operations, Inc.

Mr. Harry P. Salmon, Jr. James A. FitzPatrick Nuclear Power Plant Director of Oversight P.O. Box 110 Entergy Nuclear Operations, Inc. Lycoming, NY 13093 440 Hamilton Avenue White Plains, NY 10601 Mr. Paul Eddy Electric Division New York State Dept. of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223

FitzPatrick Nuclear Power Plant cc:

Michael J. Colomb General Manager Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Knubel Vice President, Operations Support Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Generation Co.

Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 Mr. J. Spath, Program Director New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Ronald Schwartz SRC Consultant 64 Walnut Drive Spring Lake Heights, NJ 07762 Mr. Ronald J. Toole SRC Consultant Toole Insight 605 West Horner Street Ebensburg, PA 15931 Mr. Charles W. Hehl SRC Consultant Charles Hehl, Inc.

1486 Matthew Lane Pottstown, PA 19465

DATED: May 8, 2002 AMENDMENT NO. 273 TO FACILITY OPERATING LICENSE NO. DPR-59 FITZPATRICK PUBLIC PDI-1 R/F RLaufer OGC GHill (2)

WBeckner ACRS BPlatchek, RI SRichards GVissing SLittle SMazumdar cc: Plant Service list

ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 273 License No. DPR-59

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated September 28, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 273, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by PTam for RLaufer/

Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 8, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 273 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 76a 76a 76c 76c

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 273 TO FACILITY OPERATING LICENSE NO. DPR-59 ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333

1.0 INTRODUCTION

By letter dated September 28, 2001, Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The requested changes would revise the Anticipated Transient Without Scram (ATWS)

Recirculation Pump Trip Reactor Pressure High setpoint by replacing the current conditional setpoints which are based upon the number of Safety Relief Valves (SRVs) out of service, with a single setpoint.

The licensee proposed the following changes to TS Table 3.2-7, ATWS Recirculation Pump Trip Instrumentation Requirements, Reactor Pressure - High, Trip Level Setting, associated with the number of SRVs in service:

a. Change the setting to a single value of < 1155 psig from the current setting of

< 1120 or < 1155 psig (Note 3).

b. Delete Note 3 which states The ATWS Reactor Pressure High Recirculation Pump Trip setpoint shall be < 1155 psig when either zero or one SRVs are out of service. The setpoint shall be < 1120 psig when two or more SRVs are out of service.

2.0 EVALUATION The current TS specifies two trip setpoints for the ATWS Recirculation Pump Trip, Reactor Pressure High, Instrumentation:

< 1120 psig for 1 or fewer SRVs out of service and

< 1155 psig with 2 or more SRVs out of service.

The TS allows a maximum of two SRVs out of service during power operation and based on this criterion the licensee initiated an analysis of the ATWS Reactor Pressure High Recirculation Pump Trip setpoint, the results of which are reported in NEDC-32616P, James A.

FitzPatrick Nuclear Power Plant Anticipated Transient Without Scram (ATWS) Analysis for Recirculation Pump Trip Setpoint Changes, dated July 18, 1996 (Reference 2). The NRC approved this report by letter dated November 17, 1998.

The licensee stated that this analysis was performed using General Electric proprietary ODYN code described in GE Topical Report NEDO-24154. The Nuclear Regulatory Commission (NRC) staff reviewed ODYN and found it acceptable as documented in Safety Evaluation for General Electric Topical Report Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors, NEDO-24154 and NEDO-24154-P Volumes I, II, III, June 1980. The licensee further stated that the GE Analysis of March 2000 (Reference 1) demonstrated that the high reactor pressure vessel (RPV) pressure setpoint should be < 1155 psig with two or fewer SRVs out of service which is well below the worst case RPV pressure of 1401 psig and the allowable RPV pressure of 1500 psig.

By letter dated October 12, 2001, the NRC approved the instrument setpoint methodology used by the licensee in Improved TSs Conversion Beyond Scope issues. Because the proposed changes are based on the NRC-approved calculation methodologies the NRC staff finds the proposed changes acceptable.

The proposed TS changes will remove inconsistencies in the current TSs. The current TSs prohibits plant operation at power with more than two SRVs out of service while Table 3.2-7 specifies ATWS Reactor Pressure High Recirculation Pump Trip setpoints with two or more SRVs out of service. The proposed changes have been established by the NRC-approved calculation methodologies and the NRC staff finds the proposed TS changes acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 64294). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 REFERENCES

(1) ATWS Overpressure Analysis for FitzPatrick, GE-NE-A42-00137-2-01, March 2000.

(2) James A. FitzPatrick Nuclear Power Plant Anticipated Transient Without Scram (ATWS) Analysis for Recirculation Pump Trip Setpoint Changes, NEDC-32616P, July 18, 1996.

(3) FitzPatrick Power Uprate Impact Study, Engineering Report: Section 9.3.1, Anticipated Transient Without Scram Analyses for the James A. FitzPatrick Nuclear Power Plant, GE-NE-187-59-1191, November 1991.

Principal Contributor: Subinoy Mazumdar Date: May 8, 2002