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Category:Annual Operating Report
MONTHYEARML22104A0782022-04-14014 April 2022 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G PNP 2021-022, 2020 Annual Non-Radiological Environmental Operating Report2021-04-27027 April 2021 2020 Annual Non-Radiological Environmental Operating Report PNP 2021-010, Annual Report of Changes in Emergency Core Cooling System Models2021-03-19019 March 2021 Annual Report of Changes in Emergency Core Cooling System Models PNP 2019-020, Submittal of Annual Report of Changes in Emergency Core Cooling System Models2019-04-0808 April 2019 Submittal of Annual Report of Changes in Emergency Core Cooling System Models ML19094B0782019-04-0303 April 2019 Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G PNP 2018-021, Submittal of 2017 Annual Non-Radiological Environmental Operating Report2018-04-20020 April 2018 Submittal of 2017 Annual Non-Radiological Environmental Operating Report PNP 2018-022, Annual Report of Changes in Emergency Core Cooling System Models2018-04-0909 April 2018 Annual Report of Changes in Emergency Core Cooling System Models ML18347B2982018-04-0303 April 2018 1997 Annual Non-Radiological Environment Operating Report ML18347B2992018-04-0303 April 2018 1996 Annual Non-Radiological Environmental Operating Report PNP 2017-060, Report of Changes, Tests and Experiments and Summary of Commitment Changes2017-10-12012 October 2017 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2017-023, Annual Report of Changes in Emergency Core Cooling System Models2017-05-24024 May 2017 Annual Report of Changes in Emergency Core Cooling System Models PNP 2016-030, Annual Report of Changes in Emergency Core Cooling System Models2016-04-20020 April 2016 Annual Report of Changes in Emergency Core Cooling System Models PNP 2015-082, Report of Changes, Tests and Experiments and Summary of Commitment Changes2015-10-14014 October 2015 Report of Changes, Tests and Experiments and Summary of Commitment Changes CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G PNP 2013-042, Submittal of 2012 Annual Non-Radiological Environmental Operating Report2013-04-23023 April 2013 Submittal of 2012 Annual Non-Radiological Environmental Operating Report PNP 2013-031, Report of Changes in Emergency Core Cooling System Models2013-04-11011 April 2013 Report of Changes in Emergency Core Cooling System Models CNRO-2012-00003, 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 G2012-04-30030 April 2012 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 PNP 2011-036, Submittal of 2010 Annual Non-Radiological Environmental Operating Report2011-04-26026 April 2011 Submittal of 2010 Annual Non-Radiological Environmental Operating Report ML1011900842010-04-28028 April 2010 Submittal of 2009 Annual Non-radiological Environmental Operating Report ML0914002032009-05-20020 May 2009 Submittal of Annual Report of Changes in Emergency Core Cooling System Models and 30-Day Report for Large and Small Break LOCA ML0913406782009-05-14014 May 2009 Submittal of 2008 Radiological Environmental Operating Report ML1011600472009-04-29029 April 2009 2008 Annual Radioactive Effluent Release and Waste Disposal Report (Attached) ML0910602482009-04-15015 April 2009 Annual Non-Radiological Environmental Operating Report CNRO-2009-00006, Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2009-04-13013 April 2009 Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G ML0810805412008-04-17017 April 2008 2007 Nonradiological Environmental Operating Report ML0809804222008-04-0707 April 2008 Generator Tube Inspection Report ML0617301082006-06-21021 June 2006 Annual Report of Changes in Emergency Core Cooling System Models ML0435102052004-12-0808 December 2004 Annual Report of Changes in Emergency Core Cooling System Models ML18347A5031995-09-11011 September 1995 1994 Annual Report of Facility Changes, Tests and Experiments. ML18347B1911986-04-15015 April 1986 1985 Radiological Environmental Monitoring Report 2022-04-14
[Table view] Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
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Nuc c Communfed to Nu!erxel Palisades Nuclear Plant Operated by Nuclear Management Company, LLC December 8, 2004 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Annual Report of Changes in Emeraencv Core Cooling System Models Nuclear Management Company, LLC, is submitting the annual report of changes in the emergency core cooling system (ECCS) models for the Palisades Nuclear Plant. The report is submitted in accordance with 10 CFR 50.46(a)(3)(ii). The report contains both the small break loss-of-coolant accident ECCS evaluation summary and the large break loss-of-coolant accident evaluation summary. This report covers the period from December 12, 2003, through December 8, 2004.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
0r vv Oc Daniel J. Malone Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure (1)
CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC (D 27780 Blue Star Memorial Highway . Covert, Michigan 49043-9530 Telephone: 269.764.2000
ENCLOSURE I ANNUAL REPORT OF CHANGES IN EMERGENCY CORE COOLING MODELS 1.0 CHANGES AND ERRORS IN SMALL BREAK LOSS-OF-COOLANT ACCIDENT (SBLOCA) EMERGENCY CORE COOLING (ECCS) EVALUATION MODEL Framatome Advanced Nuclear Power, Inc. (FANP) performed the SBLOCA analysis for fuel cycles 17 and 18 for the Palisades Nuclear Plant. The peak cladding temperature (PCT) of 14650 F for cycle 17 was reported to the NRC in Reference 1. The peak cladding temperature (PCT) of 14650 F for cycle 18 was reported to Palisades in Reference 2.
FANP has reported the following error since the Reference 1 report.
Choked Flow Error with Non-Condensables Present (FANP Condition Report 10594)
An error was discovered in Subroutine JCHOKE in S-RELAP5, Realistic Large Break Loss of Coolant Accident (RLBLOCA) version UMARO2 and SBLOCA version USEPO2. In these and previous versions of S-RELAP5, the choked flow model incorrectly allowed the flow to not choke, but only under specific conditions. The error occurred after the accumulators had completely discharged their liquid, and nitrogen was injected into the primary system. The affected calculations are the smaller breaks in the RLBLOCA methodology and the larger breaks in the SBLOCA methodology. The analysis documented for Palisades used the same or earlier version of the code identified as affected by this error.
Review of the analysis indicates that the safety injection tanks (i.e.,
accumulators) did not completely empty by the time of PCT so the error did not have an effect. The estimated 10 CFR 50.46 impact due to correcting the subject error is 00 F for Palisades SBLOCA analyses.
The resulting PCT, as applicable for the current fuel cycle 18, is 14650F.
2.0 CHANGES AND ERRORS IN LARGE BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA) ECCS EVALUATION MODEL FANP evaluates the LBLOCA for the Palisades Nuclear Plant with the SEM/PWR-98 methodology. The PCT of 1961'F for fuel cycle 17 was reported in Reference 1. FANP has reported the following error since the Reference 1 report.
Inconsistent Loss Coefficients (FANP Condition Report 9317)
Review of the Palisades LBLOCA analysis input revealed that there is one loss coefficient mismatch between RELAP4 and RFPAC/REFLEX of the type specified in CR 9317. The mismatch is that not all of the downcomer, lower plenum and lower head loss coefficients in RELAP4 were included in the downcomer node loss coefficient in the RFPAC/REFLEX input. For this Page 1 of 2
evaluation, the limiting break spectrum case (single-ended cold leg split break with a 1.0 discharge coefficient, end-of-cycle axial power shape, middle-of-cycle stored energy, and the loss of one diesel generator) was used as the base for evaluating the change in PCT. This evaluation also used 6% Gadolinia rod analysis input for Cycle 17. Comparing the results of the new calculation with the results from the base case value shows that reportable PCT is unchanged at 19450 F. Therefore, the results of the calculation shows that the 10 CFR 50.46 impact of CR 9317 is 00 F for Palisades.
The resulting PCT, as applicable for the current fuel cycle 18, is 1961'F.
3.0 REFERENCES
- 1. Letter, Douglas E. Cooper (Nuclear Management Company) to Document Control Desk (NRC), uAnnual Report of Changes in ECCS Models per 10 CFR 50.46," dated December 11, 2003.
- 2. EMF-3097, Revision 0, Palisades Cycle 18 Safety Analysis Report, June 2004.
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