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Category:Annual Report
MONTHYEARML22320A5592022-11-16016 November 2022
2022 Annual Report - Guarantees of Payment of Deferred Premiums
CNRO-2011-00004, Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2011-04-29029 April 2011
Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G
ENOC-07-00020, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 162007-06-15015 June 2007
Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 16
JAFP-06-0127, CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2006-08-14014 August 2006
CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models
ML0615304192006-05-25025 May 2006
Enclosure 1, 2005 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants
ML0615304262005-12-31031 December 2005
Annual Report Pursuant to Section 13 or 15(d) of the Securities Exchange Act of 1934
ML0701601972005-12-31031 December 2005
JAFNPP - SEIS Web Reference - Eckert 2005, New York Lake Ontario and Upper St. Lawrence River Stocking Program 2005
ML0701602092005-12-31031 December 2005
JAFNPP - SEIS Web Reference - Schaner 2005, Pelagic Planktivores, NYSDEC Lake Ontario Annual Report 2005
BVY 05-057, 2004 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal2005-05-25025 May 2005
2004 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal
JAFP-05-0062, Annual Radioactive Effluent Release Report for January 1, 2004 - December 31, 20042005-04-28028 April 2005
Annual Radioactive Effluent Release Report for January 1, 2004 - December 31, 2004
ML0636202162005-02-28028 February 2005
JAFNPP Er Ref 8-17 Energy Outlook 2005, with Projections to 2025
ML0703805292004-12-31031 December 2004
JAFNPP - Site Audit Requests - 1995-2004 Report of Environmental Radiation in New York State
ML0701603382004-12-31031 December 2004
JAFNPP - SEIS Web Reference - NYSDEC 2004 Status of Lake Ontario
ML0701602082004-12-31031 December 2004
JAFNPP - SEIS Web Reference - Schaner 2004, Pelagic Planktivores, 2004, NYSDEC Lake Ontario Annual Report 2004
JAFP-04-0135, James a FitzPatrick, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2004-08-23023 August 2004
James a FitzPatrick, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models
BVY 04-049, 2003 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants. Form 10-K Through Page E-312004-05-25025 May 2004
2003 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants. Form 10-K Through Page E-31
JPN-04-012, 2003 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants. Financial Results Through Investor Information2004-05-25025 May 2004
2003 Annual Report, and, Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants. Financial Results Through Investor Information
JAFP-04-0054, Annual Radioactive Effluent Release Report for the Period of January 1, 2003 Through December 31, 20032004-04-21021 April 2004
Annual Radioactive Effluent Release Report for the Period of January 1, 2003 Through December 31, 2003
BVY 03-044, 2002 Annual Report, and Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants2003-05-28028 May 2003
2002 Annual Report, and Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants
JAFP-03-0056, Annual Radioactive Effluent Release Report for January 1, 2002 Through December 31, 20022003-04-23023 April 2003
Annual Radioactive Effluent Release Report for January 1, 2002 Through December 31, 2002
JPN-02-023, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2002-08-14014 August 2002
10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models
NL-02-073, Part 2 of 3, Indian Point, Units 1, 2, & 3, James A. FitzPatrick & Pilgrim Nuclear Station - 2001 Annual Report & Security & Exchange Commission Form 10-K, Us Securities & Exchange Commission2002-05-14014 May 2002
Part 2 of 3, Indian Point, Units 1, 2, & 3, James A. FitzPatrick & Pilgrim Nuclear Station - 2001 Annual Report & Security & Exchange Commission Form 10-K, Us Securities & Exchange Commission
JAFP-02-0052, Annual Report, Safety Relief Valve Challenges and Failures, for James A. FitzPatrick Nuclear Power Plant2002-02-28028 February 2002
Annual Report, Safety Relief Valve Challenges and Failures, for James A. FitzPatrick Nuclear Power Plant
ML0636201842000-12-31031 December 2000
JAFNPP Er Ref 8-13 DOE Eia Annual Energy Outlook 2001, with Projections to 2020
ML0703805321994-12-31031 December 1994
JAFNPP - Site Audit Requests - 1994 Annual Report Environmental Radiation in New York State
ML0703805341993-12-31031 December 1993
JAFNPP - Site Audit Requests - 1993 Annual Report Environmental Radiation in New York State
2022-11-16
[Table view]
Category:Letter type:JPN
MONTHYEARJPN-05-009, Entergy Response to NRC Request for Information on Entergy Actions to Ensure Employees at FitzPatrick Remain Willing to Raise Safety Concerns (Letter Dated June 15, 2005)2005-06-15015 June 2005
Entergy Response to NRC Request for Information on Entergy Actions to Ensure Employees at FitzPatrick Remain Willing to Raise Safety Concerns (Letter Dated June 15, 2005)
JPN-05-005, Status of Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc., for Year Ending December 31,2004 - 10 CFR 50.75(f)(1)2005-03-28028 March 2005
Status of Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc., for Year Ending December 31,2004 - 10 CFR 50.75(f)(1)
JPN-04-017, Request for Extension to Answer the November 5, 2004, Order Imposing Requirements for the Protection of Certain Safeguards Information (EA-04-190)2004-11-23023 November 2004
Request for Extension to Answer the November 5, 2004, Order Imposing Requirements for the Protection of Certain Safeguards Information (EA-04-190)
JPN-04-011, Comments on Preliminary Accident Sequence Precursor Analysis of August 14, 2003 Operational Event2004-05-17017 May 2004
Comments on Preliminary Accident Sequence Precursor Analysis of August 14, 2003 Operational Event
JPN-04-010, Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs2004-04-14014 April 2004
Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs
JPN-04-002, Alternative to Appendix Viii, Supplement 4 Requirements for Reactor Vessel Pressure Retaining Weld Inspection2004-02-11011 February 2004
Alternative to Appendix Viii, Supplement 4 Requirements for Reactor Vessel Pressure Retaining Weld Inspection
JPN-03-025, Proof of Financial Protection (10CFR140.15)2003-09-30030 September 2003
Proof of Financial Protection (10CFR140.15)
JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-6002003-08-11011 August 2003
Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600
JPN-03-011, Entergy Nuclear Operations, Inc. Service List Updates2003-05-20020 May 2003
Entergy Nuclear Operations, Inc. Service List Updates
JPN-03-007, Status of Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc. for Year Ending December 31, 2002 - 10 CFR 50.75(f)(1)2003-03-31031 March 2003
Status of Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc. for Year Ending December 31, 2002 - 10 CFR 50.75(f)(1)
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-03-002, 20-Day Response to NRC January 7, 2003 Order for Compensatory Measures Related to Access Authorization2003-01-27027 January 2003
20-Day Response to NRC January 7, 2003 Order for Compensatory Measures Related to Access Authorization
JPN-02-026, Relief Request RR-28, Revision 3 for Third 10-Year Inservice Inspection Interval Program Plan2002-09-12012 September 2002
Relief Request RR-28, Revision 3 for Third 10-Year Inservice Inspection Interval Program Plan
JPN-02-025, Final Response to Issuance of Orders for Interim Safeguards and Security Compensatory Measures2002-09-0303 September 2002
Final Response to Issuance of Orders for Interim Safeguards and Security Compensatory Measures
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
JPN-02-023, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2002-08-14014 August 2002
10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models
JPN-02-022, License DPR-59, Relief Request RR-28, Revision 2 for the Third 10-Year Inservice Inspection Interval Program Plan2002-07-10010 July 2002
License DPR-59, Relief Request RR-28, Revision 2 for the Third 10-Year Inservice Inspection Interval Program Plan
JPN-02-019, & James A. FitzPatrick Nuclear Power Plant Entergy Quality Assurance Program Manual2002-06-13013 June 2002
& James A. FitzPatrick Nuclear Power Plant Entergy Quality Assurance Program Manual
JPN-02-018, Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures from James A. FitzPatrick Power Plant2002-06-12012 June 2002
Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures from James A. FitzPatrick Power Plant
JPN-02-016, Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling Dose Consequences2002-06-0707 June 2002
Proposed License Amendment for a Limited Scope Application of the Alternate Source Term Guidelines in NUREG-1465 Related to the Re-Evaluation of the Fuel Handling Dose Consequences
JPN-02-015, Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures from James A. FitzPatrick Nuclear Power Plant2002-06-0707 June 2002
Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures from James A. FitzPatrick Nuclear Power Plant
JPN-02-013, Letter from Michael R. Kansler Re James A. FitzPatrick Nuclear Power Plant License DPR-59 Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures2002-05-15015 May 2002
Letter from Michael R. Kansler Re James A. FitzPatrick Nuclear Power Plant License DPR-59 Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures
JPN-02-011, Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan2002-05-0808 May 2002
Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan
JPN-02-010, Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan2002-05-0808 May 2002
Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan
JPN-02-008, Proof of Financial Protection (10 CFR 140.15) and Guarantee Payment of Deferred Premiums (10 CFR.21)2002-04-10010 April 2002
Proof of Financial Protection (10 CFR 140.15) and Guarantee Payment of Deferred Premiums (10 CFR.21)
JPN-02-007, Sources and Levels of Insurance Required by 10 CFR 50.54(w)2002-03-28028 March 2002
Sources and Levels of Insurance Required by 10 CFR 50.54(w)
JPN-02-006, Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures for James A. FitzPatrick Power Plant2002-03-28028 March 2002
Supplemental Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures for James A. FitzPatrick Power Plant
JPN-02-005, Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures2002-03-18018 March 2002
Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures
JPN-02-004, Request for an Extension of Time to Submit an Answer and Request for Hearing2002-03-18018 March 2002
Request for an Extension of Time to Submit an Answer and Request for Hearing
JPN-02-002, Entergy Nuclear Northeast'S Submittal of Fitness-for-Duty Program Performance Report for the Period July - December 20012002-02-25025 February 2002
Entergy Nuclear Northeast'S Submittal of Fitness-for-Duty Program Performance Report for the Period July - December 2001
JPN-02-001, Submittal of James A. FitzPatrick Owner'S Activity Report, JAF-RPT-MULTI-04331, Rev. 0 Which Contains Inservice Inspection Results & Repair/Replacement Activities Performed During 1st Period of Third 10-Year ISI Interval2002-01-28028 January 2002
Submittal of James A. FitzPatrick Owner'S Activity Report, JAF-RPT-MULTI-04331, Rev. 0 Which Contains Inservice Inspection Results & Repair/Replacement Activities Performed During 1st Period of Third 10-Year ISI Interval
2005-06-15
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Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc 440 Hamilton Avenue Entergy White Plains, NY 10601 Tel 9142723200 Fax 914 272 3205 Michael R. Kansler Senior Vice President &
Chief Operating Officer August 14, 2002 JPN-02-023 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555-0001
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models
References:
- 1. Entergy letter, M. Kansler to USNRC dated August 15, 2001 (JPN-01-014) regarding the same subject.
Dear Sir:
The attached report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period from July 1, 2001 to June 30, 2002 for Entergy's James A. FitzPatrick Nuclear Power Plant.
A total of two changes or errors to the Fit2Patrick model have been identified since the last annual report (Reference 1). Thirty-day reports were not submitted for these errors because they do not qualify as a significant change (a peak cladding temperature change of greater than 50 0 F) according to 10 CFR 50.46(a)(3)(i).
Corrected for these errors, estimated peak cladding temperatures (PCTs) remain below the 2200'F requirement of 10 CFR 50.46(b)(1).
/:VoDCI
No new commitments are contained in this letter. If you have any questions, please contact Ms.
Charlene Faison at 914-272-3378.
Very truly yours, ich~aeI R. Kansle
/ Senior Vice Pr dent and Chief Operati g Officer cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Guy Vissing, Project Manager Project Directorate I Office of Nuclear Reactor Regulation Mail Stop: OWFN 8C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P. 0. Box 136 Lycoming, NY 13093
Attachment:
Annual 10 CFR 50.46(a)(3)(ii) Report on Changes or Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from July 1, 2001 to June 30, 2002 2
Attachment to JPN-02-023 Annual 10 CFR 50.46(a)(3)(ii) Report on Changes or Errors ini Emergency Core Cooling System (ECCS) Evaluation Models for the period from July 1, 2001 to June 30, 2002 Entergy Nuclear Operations Inc.
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 INTRODUCTION This report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period from July 1, 2001 to June 30, 2002 for Entergy's James A. FitzPatrick Nuclear Power Plant.
A total of 2 (two) changes or errors to the FitzPatrick model have been identified since the last annual report (Reference 1). Thirty-day reports were not submitted for these errors because they do not qualify as a significant change (a peak cladding temperature [PCi] change of greater than 50 0F) according to 10 CFR 50.46(a)(3)(i).
Table 1 summarizes the errors or changes to the current Fit2Patrick ECCS evaluation models.
The last two entries represent ECCS evaluation changes or errors identified during the period July 1, 2001 to June 30, 2002.
Additional information on the changes or errors identifed during the reporting period is proVided below.
DISCUSSION OF CHANGES OR ERRORS IDENTIFIED DURING REPORTING PERIOD SAFER Core Spray Iniection Elevation Error In 10 CFR 50.46 Notification Letter 2002-01 (Reference 16), General Electric reported an error in the automation code that prepares the input basedecks br the SAFER analysis. This error resulted in too low a value being calculated for the core spray injection elevation for the lower core spray sparger. As a result of this error, the licensing basis PCTfor all fuel types at FitzPatrick increased by 5 degrees F.
This error changed PCT by less than 50'F. Consequently it did not qualify as a significant change according to 10 CFR 50.46(a)(3)(i) and no 30-dayreport was submitted.
Impact of SAFER Bulk Water Level Error on the Peak Clad Temperature In 10 CFR 50.46 Notification Letter 2002-02 (Reference 17), General Electric reported an error in the initial water level used in some SAFE/REFLOOD and SAFER LOCA analyses. Initial water levels did not properly account for the effect of steam dryer pressure drop. When corrected for dryer pressure drop, the initial bulk water temperature in the vessel is lower than that used in the original SAFE or SAFER analyses. As a result of this error, licensing basis PCT for all fuel types increased by 10 degrees F.
This error changed PCT by less than 50 0F. Consequently it did not qualify as a significant change according to 10 CFR 50.46(a)(3)(i) and no 30-dayreport was submitted.
1
Attachment to JPN-02-023
SUMMARY
Since the last annual 10 CFR 50.46 report (Reference 1), estimated FitzPatrick PCT increased by 15 degrees F. Estimated PCTs, corrected for these errors, remain well below the 2200'F requirement of 10 CFR 50.46(b)(1).
2
Attachment to JPN-02-023 TABLE I -ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK For the period from July 1, 2001 to June 30, 2002 Estimated Updated Report ECCS PCT Change PCT Period Evaluation GE11 GE12 GE11 GE12 Fuel Fuel Fuel 1993 Fitzpatrick LOCA Baseline N/A 1570°F N/A Analysis (Ref. 7)
Fitzpatrick Reload 12 Baseline Supplemental Report (Ref. 8) N/A Baseline N/A 1370°F Evals.
Fitzpatrick Reload 13 Supplemental Report (Ref. 9). Baseline 1570°F 1370°F 10 CFR 50.46 Notification Regarding Sensitivity To +50°F 1620OF 1420°F Small Input Parameter Changes (Ref. 10)
Prior to 10 CFR 50.46 Notification July 1, Regarding Minor Code +50 F 1625 0 F 1425 0 F 2000 Corrections (Ref. 10) 10 CFR 50.46 Notification Regarding Bottom Head Drain +100 F 1635°F 1435 0 F (Ref. 11) 10 CFR 50.46 Notification Regarding Time Step Size -50 F 1630OF 1430°F (Ref. 3)
Estimated Effect Of July 1, Condensation Error On PCT +90°F 1720OF 1520OF 2000 - (Ref. 12)
June 30, Estimated Effect Of Pressure 2001 Rate Inconsistency Error On +100 F 1730°F 1530°F PCT (Ref. 13)
Estimated Effect Of Accounting Error On PCT N/A -50 F 1730°F 1525 0 F (Ref. 14)
SAFER Core Spray Injection July 1, Elevation Error (Ref. 16.) +50 F 1735 0 F 1530°F 2001 June 30, Impact of SAFER Bulk Water 2002 Level Error on the Peak Clad +100 F 1745 0 F 1540OF Temperature (Ref. 17.).
1
Attachment to JPN-02-023 REFERENCES
- 1. NYPA letter, M.J. Colomb to USNRC (JAFP-00-0164), dated July21, 2000, regarding reporting of changes and errors in ECCS evaluation models.
- 2. Entergy Nuclear Operations, Inc. letter, M Kansler to USNRC, (JPN-01-010) dated June 4, 2001, regarding 10 CFR 50.46(a)(3)(ii) 30-dayreport, two errors in ECCS evaluation models.
- 3. Global Nuclear Fuel letter, A. Alzaben (GNF) to C. Franklin (NYPA), (AFA-00-N061 dated November 20, 2000) regarding 10 CFR 50.46 error report - impact ofSAFER time step size on the peak clad temperature (PCT) for jet pump plant analyses. Includes General Electric/Global Nuclear Fuel 10 CFR 50.46 Notilication Letter 2000-04 dated November 8, 2000 regarding "Impact of SAFER Time Step Size on the Peak Clad Temperature (PCT) for Jet Pump Plant Analyses." (Proprietary)
- 4. NEDC-23785-1-PA Rev. 1, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-Of-Coolant Accident Volume II, SAFER - Long Term Inventory Model for BWR Loss Of-Coolant Analysis," October 1984.
- 5. NEDC-23785-1-PA Rev. 1, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-Of-Coolant Accident Volume III, SAFER/GESTR Application Methodology," October 1984.
- 6. General Electric Nuclear Energy Report, J 11-03757SRL, August 2000, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 14, Cycle 15."
- 7. General Electric Nuclear Energy, "James A. FitzPatrick Nuclear Power Plant SAFER/GESTER-LOCA, Loss-of-Coolant Analysis," Licensing Topical Report NEDC 31317P, Class III (proprietary), Revision 2, April 1993.
- 8. General Electric Nuclear Energy Report, J11-02914SRL, Revision 0, August 1996, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 12, Cycle 13."
- 9. General Electric Nuclear Energy Report, J11-03359SRL, Revision 1, Class I, October 1998, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 13, Cycle 14."
- 10. General Electric Nuclear Energy, MFN-090-93, June 30, 1993, "Reporting of Changes and Errors in ECCS Evaluation Models."
- 11. General Electric Nuclear Energy, MFN-020-96, February 20, 1996, "Reporting of Changes and Errors in ECCS Evaluation Models."
- 12. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notiication Letter 2001-01 dated May 8, 2001 (via E-mail) regarding "Impact of SAFER Condensation Error on the Peak Clad Temperature (PCT)." (Proprietary) 1
Attachment to JPN-02-023
- 13. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notifcation Letter 2001-02 dated May 10, 2001 (via E-mail) regarding "Impact of SAFER Pressure Rate Inconsistency Error on the Peak Clad Temperature (PCT)." (Proprietary)
- 14. Global Nuclear Fuel letter, A. Alzben (GNF) to J. Head (EntergyNuclear Operations, Inc.),
(AFA-01-E004, June 29, 2001) regarding GE12 Upper Bound PCTfor FitzPatrick, (Proprietary).
- 15. Entergy letter, M. Kansler to USNRC, dated August 15, 2001 (JPN-01-0014) regarding "10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models."
- 16. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notiication Letter 2002-01 regarding "SAFER Core Spray Injection Elevation Error." (Proprietary)
- 17. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notifcation Letter 2002-02 regarding "Impact of SAFER Bulk Water Level Error on the Peak Clad Temperature (PCT)."
(Proprietary) 2
