JAFP-09-0056, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.48
ML091420364 | |
Person / Time | |
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Site: | FitzPatrick ![]() |
Issue date: | 05/11/2009 |
From: | Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
JAFP-09-0056 | |
Download: ML091420364 (5) | |
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Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask JAFP-13-0096, James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2013-08-0101 August 2013 James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models JAFP-12-0135, Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML13162A6272012-02-20020 February 2012 Summary of R1 Containment Vents ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1125101872011-09-0808 September 2011 NRC Investigation Report Nos. 1-2009-041, 1-2010-019, and 1-2010-031 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants JAFP-09-0091, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models2009-07-31031 July 2009 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-09-0056, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.482009-05-11011 May 2009 Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.48 ML0831006632008-11-19019 November 2008 Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-CRV-01 JAFP-08-0103, Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility2008-10-0202 October 2008 Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility ML0810102772008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions ML0805905802008-02-15015 February 2008 List of Requesters Fitzpatrick ML0805905792008-02-14014 February 2008 Foia/Pa Cases Received from 02/12/07 to 02/12/08 ML0711601862007-05-21021 May 2007 Biological Assessment for Species Under the Jurisdiction of the U.S. Fish and Wildlife Service - James A. FitzPatrick Nuclear Power Plant License Renewal Review ML0710004922007-03-26026 March 2007 Usfws Threatened and Endangered Species System (Tess) - New York ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 JAFP-07-0013, License Renewal Application, Amendment 4, Response to Request for Additional Information2007-01-29029 January 2007 License Renewal Application, Amendment 4, Response to Request for Additional Information ML0704704712007-01-0101 January 2007 Great Lakes St. Lawrence Seaway - Ballast Water ML0704704322007-01-0101 January 2007 Oswego Industrial Directory JAFP-06-0179, JAFNPP - Site Audit Requests - (24) November and December 2006 Monthly Discharge Monitoring Reports2006-12-21021 December 2006 JAFNPP - Site Audit Requests - (24) November and December 2006 Monthly Discharge Monitoring Reports ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006 Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006 CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee BVY 06-016, Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 20052006-02-27027 February 2006 Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 2005 ML0704704112006-01-0101 January 2006 Fws Hydroelectric Licensing BVY 05-089, Entergy Nuclear Northeast - Proof of Financial Protection2005-09-28028 September 2005 Entergy Nuclear Northeast - Proof of Financial Protection ML0636201702005-09-27027 September 2005 JAFNPP Er Ref 8-5 FHA User Guidelines BVY 05-078, Fitness-for-Duty Program Performance Report for the Period January - June 20052005-08-29029 August 2005 Fitness-for-Duty Program Performance Report for the Period January - June 2005 JAFP-05-0126, Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2005-08-17017 August 2005 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models BVY 05-018, Fitness-for-Duty Program Performance Report for the Period July - December 20042005-02-28028 February 2005 Fitness-for-Duty Program Performance Report for the Period July - December 2004 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement JAFP-04-0159, Entergy Nuclear Operations, Inc., NRC Generic Letter 2003-01, Control Room Habitability, Initial Summary Actions Report2004-09-27027 September 2004 Entergy Nuclear Operations, Inc., NRC Generic Letter 2003-01, Control Room Habitability, Initial Summary Actions Report ML0703905852004-09-0101 September 2004 International Joint Commission, 12th Biennial Report Great Lakes Water Quality ML0636201442004-01-31031 January 2004 JAFNPP Er Ref 8-16, DOE Eia Annual Energy Outlook 2004 BVY 03-069, Fitness-for-Duty Program Performance Report for Period January - June 20032003-08-18018 August 2003 Fitness-for-Duty Program Performance Report for Period January - June 2003 ML0701602032003-05-30030 May 2003 JAFNPP - SEIS Web Reference - Mills Et Al 2003 JPN-03-004, Fitness-for-Duty Program Performance Report for the Period July - December 20022003-02-26026 February 2003 Fitness-for-Duty Program Performance Report for the Period July - December 2002 JPN-02-024, Fitness-for-Duty Program Performance Report for the Period January - June 20022002-08-15015 August 2002 Fitness-for-Duty Program Performance Report for the Period January - June 2002 ML0702303602002-08-13013 August 2002 JAFNPP Condition Reports Bird Deaths 2020-10-23 |
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2-i Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP P.O. Box 110 SEntergy Lycoming, NY 13093 Tel 315-342-3840 Pete Dietrich Site Vice President May 11, 2009 JAFP-09-0056 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.48
Dear Sir or Madam:
This letter transmits the summary of changes, tests and experiments implemented at the James A. FitzPatrick Nuclear Power Plant (JAF) for the years 2007 and 2008 as required by 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2).
During this period there were no changes to the Independent Spent fuel Storage Installation requiring a 10 CFR 72.48 Evaluation. The plant changes requiring evaluation under 10 CFR 50.59 are summarized in Attachment 1.
There are no new commitments made in this letter.
Should you have any questions concerning this report, please direct them to Mr. Joseph Pechacek, Licensing Manager*,&ti 5) 349-6766.
PD:JP:mh
Attachment:
- 1. Summary of 10 CFR 50.59 Reports for 2007 and 2008 cc: next page J7Z~2 /7
JAFP-09-0056 Page 2 of 2 cc: Mr. Samuel Collins
'Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555
ATTACHMENT 1 JAFP-09-0056 Summary of 10 CFR 50.59 Reports for 2007 and 2008 James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Entergy Nuclear Operations, Inc
2007 Summary JAF-SE-07-001, Rev. 0: Use of Ultra Low Sulfur Diesel (ULSD) Fuel (< 15 ppm Sulfur) In JAF Diesel Generators ACTIVITY TYPE: Design Change Engineering Change EC-0551 evaluated the impact of reduced sulfur content on the available heat content in fuel oil. The 50.59 evaluation addressed use of a time dependent loading in the calculation method as well as the change in sulfur content. The evaluation concluded that use of ultra low sulfur diesel fuel was acceptable.
I This 50.59 Evaluation is withdrawn. Based on issues raised during the 2007 Component Design Bases Inspection it was necessary to revise the calculation method and add additional conservatisms into the calculation. Based on using an NRC approved methodology it was determined that a 50.59 Evaluation was not required.
JAF-SE-07-002, Rev. 0: Implementation of the Maximum Extended Operating Domain (MEOD)
ACTIVITY TYPE: Evaluation EC 5000018317 documents the bases for use of an expanded operating map (the set of allowable reactor power / core flow conditions for plant operation) known as the
.Maximum Extended Operating Domain (MEOD). This 50.59 evaluation reviewed the analyses and evaluations in the engineering change to determine if MEOD could be implemented without prior NRC concurrence. The conclusion was that MEOD could be implemented contingent upon NRC approval of the Average Power Range Monitor, Rod Block Monitor Technical Specification (ARTS) Improvement Amendment. NRC approved ARTS in JAF Amendment 287 and MEOD was implemented based on the conclusions of this 50.59.
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2008 Summary JAF-SE-08-001, Rev. 0: Cycle 19 Core Reload ACTIVITY TYPE: Evaluation This 50.59 evaluation evaluated the use of GNF-2 fuel in the cycle 19 core reload. The evaluation focused on an exposure limitation imposed on the GNF-2 Fuel. NRC had identified a potential non-conservatism in the licensed fuel thermal-mechanical analysis code (GESTR-M). The evaluation concluded that the imposition of a fuel burn-up limit, that prevented the fuel from reaching the point where the potential non-conservatism could affect the analysis of the fuel was acceptable for Cycle 19.
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