ML073380120
| ML073380120 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/23/2008 |
| From: | Boska J NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Balduzzi M Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MD6137 | |
| Download: ML073380120 (12) | |
Text
January 23, 2008 Mr. Michael A. Balduzzi Sr. Vice President & COO Regional Operations, NE Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENT RE: ADD ACTION STATEMENT FOR TWO INOPERABLE CONTROL ROOM AIR CONDITIONING SUBSYSTEMS, CONSISTENT WITH TECHNICAL SPECIFICATION TASK FORCE-477 (TAC NO. MD6137)
Dear Mr. Balduzzi:
The Commission has issued the enclosed Amendment No. 290 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Facility Operating License (FOL) and the Technical Specifications (TSs), in response to your application dated July 25, 2007, (Agencywide Document and Management System (ADAMS) accession no. ML072130164) as supplemented on November 1, 2007 (ADAMS accession no. ML073130038).
The amendment revises the FOL, and adds an Action statement to the Limiting Conditions for Operation (LCOs) for TS 3.7.4, Control Room Air Conditioning (AC) System. Specifically, the new Action statement allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore one control room air conditioning subsystem to operable status and requires verification that the control room temperature remains below 90 °F every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the period of inoperability. This amendment adopts Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF)-477, Revision 3, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. This operating license improvement and TS revision was made available by the NRC on March 26, 2007 (72 FR 14143) as part of the consolidated line item improvement process (CLIIP).
M. Balduzzi A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
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. 50-333
Enclosures:
- 1. Amendment No. 290 to DPR-59
- 2. Safety Evaluation cc w/enclosures: See next page
M. Balduzzi A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
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. 50-333
Enclosures:
- 1. Amendment No. 290 to DPR-59
- 2. Safety Evaluation cc w/enclosures: See next page Package No.: ML073380170 Amendment No.: ML073380120 Tech Spec No.: ML073380185
- See memo dated November 14, 2007 OFFICE LPL1-1\\PM LPL1-1\\LA ITSB/BC OGC LPL1-1\\BC NAME JPBoska SLittle TKobetz*
EWilliamson MKowal DATE 1/14/08 1/14/08 11/14/07 1/18/08 1/23/08 Official Record Copy
DATED: January 23, 2008 AMENDMENT NO. 290 TO FACILITY OPERATING LICENSE NO. DPR-59 FITZPATRICK PUBLIC LPL1-1 R/F RidNrrDorl RidsNrrDorlLpl1-1 RidsOGCMailCenter GHill (2) (paper copies)
RidsNrrDirsItsb AJLising, DIRS RidsAcrsAcnw&mMailCenter RidsNrrPMJBoska RidsNrrLASLittle (paper copy)
ECobey, RI RidsRgn1MailCenter RidsNrrDorlDpr TKobetz, DIRS cc: Plant Mailing list
FitzPatrick Nuclear Power Plant 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. Peter T. Dietrich Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Kevin J. Mulligan General Manager, Plant Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 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. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Costedio Manager, Licensing Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
FitzPatrick Nuclear Power Plant cc:
Mr. William C. Dennis Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 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 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306 Mr. John Doering BWR SRC Consultant P.O. Box 189 Parker Ford, PA 19457
ENTERGY NUCLEAR FITZPATRICK, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 290 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 July 25, 2007, as supplemented on November 1, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 Commission's 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 Commission's 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 Appendix A, as revised through Amendment No. 290, 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 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: January 23, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 290 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 3
3 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 3.7.4-1 3.7.4-1 3.7.4-2 3.7.4-2 3.7.4-3 3.7.4-3
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 290 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 application July 25, 2007 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML072130164), Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Facility Operating License (FOL) and the Technical Specifications (TSs) for James A. FitzPatrick Nuclear Power Plant (JAF). The supplement, dated November 1, 2007 (ADAMS Accession No. ML073130038), provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as originally published in the Federal Register (FR) on September 11, 2007 (72 FR 51855).
The requested changes are the adoption of Technical Specification Task Force (TSTF)-477, Revision 3, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems which was proposed by the TSTF industry group in a letter dated September 8, 2006 (ADAMS Accession No. ML062510321). The changes proposed in TSTF-477 would revise Standard Technical Specification 3.7.4 Control Room Air Conditioning (AC) System by adding the following TS Action Requirements:
CONDITION REQUIRED ACTION COMPLETION TIME B. Two [control room AC]
subsystems inoperable B.1 Verify control room area Temperature, < 90F.
AND B.2 Restore one [control room AC]
subsystem to OPERABLE status Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 72 hours The TSTF change traveler TSTF-477, Revision 3, was announced for availability in the FR on March 26, 2007 (72 FR 14143) as part of the consolidated line item improvement process (CLIIP).
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (the Act) requires applicants for nuclear power plant operating licenses to include TS as part of the license. The TS ensure the operational capability of structures, systems and components that are required to protect the health and safety of the public. The Commissions regulatory requirements related to the content of the TS are contained in 10 CFR Section 50.36. That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(d)(1)); (2) limiting conditions for operation (50.36(d)(2)); (3) surveillance requirements (50.36(d)(3)); (4) design features (50.36(d)(4)); and (5) administrative controls (50.36(d)(5)).
In general, there are two classes of changes to TS: (1) changes needed to reflect modifications to the design basis (TS are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TS over time. This amendment addresses the second class of changes. In determining the acceptability of revising Control Room Air Conditioning AC Subsystem TS, the staff used the accumulation of generically approved guidance in NUREG-1433, Standard Technical Specifications, Revision 3 General Electric Plants, BWR/4 dated June, 2004, referred to as Boiling-Water Reactor Model 4, Standard Technical Specifications (BWR/4 STS)).
Licensees may revise the TS to adopt current improved Standard Technical Specifications (ISTS) format and content provided that a plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The required content of the BWR/4 STS for the Control Room Air Conditioning AC System do not contain an Actions requirement for two inoperable subsystems. During the TS Conversion of the BWR/6 Plants, the BWR/6 Plants adopted Action Statements for the Ventilation and AC systems that contained Action Statements for 2 inoperable subsystems similar to the proposed Action Statements in TSTF-477. The STS for numerous safety-related systems also contain Action Statements for 2 inoperable subsystems. The TSTF proposes to add an Action Condition for 2 inoperable Control Room AC subsystems to the BWR STS in order to be consistent with the BWR/6 current STS. Furthermore, the consistency of the BWR STS will be enhanced since most safety-related systems presently have Action Statements in the STS to address two inoperable subsystems.
3.1 Action Requirements For 2 Inoperable Control Room Air Conditioning Subsystems The proposed BWR Condition, Required Action, and Completion Time allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore 1 Control Room Air Conditioning (CRAC) subsystem to the operable status for the TS condition of 2 inoperable subsystems. During the 72-hour completion time, the Control Room Temperature is verified < 90 degrees every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If 1 CRAC cannot be restored to operable status or the Control Room Temperature cannot be maintained < 90 degrees then the unit must be placed in at least Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Maintaining the Control Room Temperature < 90 degrees assures that the safety-related equipment in the Control Room will remain within the original licensed design operating temperature, because the maximum allowable Control Room Temperature is unchanged by TSTF-477. The NRC staff finds that the proposed changes in TSTF-477 are acceptable for FitzPatrick Nuclear Power Plant because the changes in TSTF-477 provide TS requirements that the Control Room Temperature will be maintained within the original licensed design operating temperature of the Control Room equipment or the plant will be placed in the Cold Shutdown Mode (Mode 4).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. 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 the finding issued on September 11, 2007 (72 FR 51855). 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.
6.0 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.
Principal Contributor: A. Jason Lising Date: January 23, 2008