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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 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 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 2013-016, 2012 ISFSI Annual Radioactive Effluent Release Report2013-02-26026 February 2013 2012 ISFSI Annual Radioactive Effluent Release Report 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 2012-033, Submittal of 2011 Radiological Environmental Operating Report2012-04-24024 April 2012 Submittal of 2011 Radiological Environmental Operating Report PNP 2011-037, & ISFSI, Submittal of 2010 Radiological Environmental Operating Report2011-04-26026 April 2011 & ISFSI, Submittal of 2010 Radiological Environmental Operating Report PNP 2011-025, Report of Changes, Tests and Experiments and Summary of Commitment Changes2011-03-31031 March 2011 Report of Changes, Tests and Experiments and Summary of Commitment Changes ML1011600472009-04-29029 April 2009 2008 Annual Radioactive Effluent Release and Waste Disposal Report (Attached) 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 ML0704605972007-02-0202 February 2007 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for Period from January 1, 2006 Through December 31, 2006 ML0509402212005-03-31031 March 2005 Bi-Annual Report, Changes, Tests, and Experiments Pursuant to 10 CFR 72.48 2022-04-14
[Table view] Category:Letter
MONTHYEARIR 07200043/20234012024-02-0505 February 2024 Public-Big Rock Point (Brp) Independent Spent Fuel Storage Installation (ISFSI) - NRC Security Inspection Report 07200043/2023401 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 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 PNP 2023-015, License Termination Plan, Revision 42023-05-16016 May 2023 License Termination Plan, Revision 4 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 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 2023-013, 2022 Radiological Environmental Operating Report2023-04-12012 April 2023 2022 Radiological Environmental Operating Report ML23101A1172023-04-11011 April 2023 Human Performance Error Resulted in Compensatory Measures Not Properly Employed 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 ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-009, Report of Changes, Tests and Experiments and Summary of Commitment Changes2023-03-28028 March 2023 Report of Changes, Tests and Experiments and Summary of Commitment Changes PNP 2023-003, Independent Spent Fuel Storage Installation Radioactive Effluent Release Report2023-02-15015 February 2023 Independent Spent Fuel Storage Installation Radioactive Effluent Release Report 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 ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22215A1472022-08-0303 August 2022 & Big Rock Point Plant - Update Report for Holtec Decommissioning International (HDI) Fleet Decommissioning Quality Assurance Program (DQAP) Revision 2 ML22213A0092022-07-27027 July 2022 2022 Holtec Palisades, LLC and Holtec Decommissioning International, LLC ANI Certified Copy Endorsements for Palisades Nuclear Plant and Big Rock Point Nuclear Generating Plant ML22182A4982022-07-0101 July 2022 and Big Rock Point Plant, Indemnity Agreements ML22173A1732022-06-28028 June 2022 and Big Rock Point Plant - Issuance of Amendment Nos. 129 and 273 Order Approving Transfer of Licenses and Conforming License Amendments (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) PNP 2022-019, & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals2022-06-24024 June 2022 & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals ML22178A0772022-06-24024 June 2022 (HDI) Satisfactory Documentary Evidence Required Before the Planned Closing Date of the Purchase and Sale Transaction of Palisades Nuclear Plant and Big Rock Point Plant ML22096A3042022-05-0909 May 2022 and Big Rock Point Plant - New Information Regarding Order Approving Transfer of Licenses (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) PNP 2022-003, and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report2022-04-25025 April 2022 and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report ML22104A0782022-04-14014 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 ML22088A2552022-03-29029 March 2022 Change for NRC Distribution Lists Re Entergy'S Vice President, Regulatory Assurance ML22087A5002022-03-28028 March 2022 and Palisades Nuclear Power Plant - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) -- Entergy Nuclear Operations, Inc ML22081A2992022-03-21021 March 2022 Entergy Operations, Inc - Summary of Property Damage Insurance Coverage ML22073A1892022-03-14014 March 2022 River Bend Nuclear Station; and Waterford Steam Electric Station, Unit 3 - Proof of Financial Protection (10 CFR 140.15) PNP 2022-001, 2021 ISFSI Annual Radioactive Effluent Release Report2022-02-24024 February 2022 2021 ISFSI Annual Radioactive Effluent Release Report ML22025A3422022-01-25025 January 2022 and Big Rock Point - Changes to Site Organization ML22021B6702022-01-21021 January 2022 and Big Rock Point - Supplement to Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments ML21354A7452021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination ML21349A3742021-12-15015 December 2021 ISFSI, Decommissioning Funding Plans (10 CFR 72.30) ML21292A1452021-12-13013 December 2021 and Big Rock Point Plant - Order Approving Transfer of Licenses and Draft Conforming Administrative License Amendments (EPID L-2020-LLM-0003) (Letter) ML21302A0642021-10-29029 October 2021 and Big Rock Point - Supplement to Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments IR 07200043/20214012021-07-29029 July 2021 Independent Spent Fuel Storage Installation Security Inspection Report 07200043/2021401 PNP 2021-023, Biennial Update License Termination Plan2021-05-19019 May 2021 Biennial Update License Termination Plan PNP 2021-015, and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report2021-04-21021 April 2021 and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report ML21054A1322021-04-14014 April 2021 U.S. NRC Analysis of Entergy Nuclear Operations, Inc'S Initial and Updated Decommissioning Funding Plans for the Big Rock Point, Indian Point, Pilgrim, Palisades, Fitzpatrick, and Vermont Yankee Independent Spent Fuel Storage Installations ML21091A1472021-04-0101 April 2021 Annual Report for Entergy Quality Assurance Program Manual and Indian Point Energy Center Quality Assurance Program 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 ML21089A3222021-03-30030 March 2021 Entergy Operations, Inc and Entergy Nuclear Operations, Inc. - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML21084A7892021-03-25025 March 2021 Entergy Nuclear Operations, Inc. Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2020 - 10 CFR 50.82(a)(8)(vii) ML21084A8112021-03-25025 March 2021 Indian Point Nuclear Generating, Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) PNP 2021-009, 2020 ISFSI Annual Radioactive Effluent Release Report2021-02-25025 February 2021 2020 ISFSI Annual Radioactive Effluent Release Report ML21022A2212021-02-0505 February 2021 Letter to Senator Charles Schumer from Margaret Doane Response for NRC to Reconsider Its Decision to Not Allow for a Public Hearing in the Transfer of Indian Point'S License ML21012A0312021-02-0101 February 2021 and Big Rock Point Plant - Notice of Consideration of Approval of Transfer of Control of Licenses and Conforming Amendments and Opportunity for a Hearing ML21011A0672021-02-0101 February 2021 Proposed Post-Shutdown Decommissioning Activities Report with Site-Specific Decommissioning Cost Estimate PNP 2020-042, and Big Rock Point Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2020-12-23023 December 2020 and Big Rock Point Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments PNP 2020-041, Independent Spent Fuel Storage Installation Radioactive Effluent Release Report2020-12-0909 December 2020 Independent Spent Fuel Storage Installation Radioactive Effluent Release Report 2024-02-05
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consumersney A CMS Energy Company Big Rock Point Nuclear Plant Kurt M. Hass 10269 US-31 North General Manager Charlevoix. Al 49720 March 31, 2005 10 CFR 72.48(d)(2)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 DOCKETS 50-155 AND 72-043 - LICENSE DPR BIG ROCK POINT PLANT -
BI-ANNUAL REPORT, CHANGES, TESTS, AND EXPERIMENTS PURSUANT TO 10 CFR 72.48 In accordance with 10 CFR 72.48(d)(2), as a general licensee under the provisions of Certificate of Compliance (CoC) 72-1026, this report serves to describe and summarize evaluation of changes, tests, and experiments affecting the FuelSolutionsTM Storage System Safety Analysis Reports for the period of April 1, 2003 to April 1, 2005.
Attachment 1 contains a short description and summary of the Big Rock Point 10 CFR 72.48 evaluation affecting the WSNF-220 FuelSolutionsTm Storage System Final Safety Analysis Report (FSAR), as updated, for the W150 Storage Cask and W100 Transfer Cask.
No Big Rock Point 10 CFR 72.48 evaluations affecting the WSNF-223 FuelSolutionsTM Storage System FSAR, as updated, for the Wesflex W74 canister were performed in the period.
In all cases, no prior NRC approval for the changes, test, or experiment was required. As a general licensee, Big Rock Point did not request the 72-1026 Certificate holder to obtain a license amendment, nor did the Certificate holder obtain any license amendments. The changes, tests, or experiments did not:
- 1. Result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the FSARs (as updated),
- 2. Result in more than a minimal increase in the likelihood of occurrence of a malfunction of a system, structure, or component (SSC) important to safety previously evaluated in the FSARs (as updated),
- 3. Result in more than a minimal increase in the consequences of an accident previously evaluated in the FSARs (as updated),
- 4. Result in more than a minimal increase in the consequences of a malfunction of an SSC important to safety previously evaluated in the FSARs (as updated),
- 5. Create a possibility for an accident of a different type than previously evaluated in the FSARs (as updated),
- 6. Create a possibility for a malfunction of an SSC important to safety with a different result than any previously evaluated in the FSARs (as updated),
- 7. Result in a design basis limit for a fission product barrier as described in the SARs (as updated) being exceeded or altered, or Page 1 of 2
- 8. Result in a departure from a method of evaluation described in the FSARs (as updated) used in establishing the design bases or in the safety analyses.
Copies of the 10 CFR 72.48 evaluation are contained in our site Administrative Volume 30, Dry Fuel Storage Exceptions Document. The evaluations contained in Volume 30 are used in subsequent 10 CFR 72.48 evaluations and from our site-specific exceptions to the BNFL FSARs.
If you have any questions, please contact Licensing Supervisor, Linda Castiglione, at 231-547-8365.
Kurt M. Haas Site General Manager cc: Regional Administrator, U.S. NRC, Region IlIl Project Manager, U.S. NRC, NMSS Steve Sisley, BNFL FuelSolutionsTm Licensing/Regulatory Compliance Manager Attachment Page 2 of 2
Attachment 1 Consumers Energy Company Big Rock Point Dockets 50-155 and 72-043 10 CFR 72.48 Evaluations WSNF-220 FuelSolutions'Storage System Final Safety Analysis Report W150 Storage Cask and W100 Transfer Cask 2 Pages March 31, 2005 Consumers Energy Company Big Rock Point 10 CFR 72.48 Evaluations WSNF-223 FuelSolutionsm Storage System Final Safety Analysis Report Wesflex W74 Canister Big Rock Point Quality Review Form Log Number: 284-04 Informational BNFL Fuel Solutionsm Condition Report and IOCFR72.48 Evaluation on WIOO Transfer Cask Coating (reference letter from BNFL to Kurt Haas dated September 9, 2004)
DESCRIPTION:
Revised Volume 30, Dry Fuel Storage Exceptions Document (DFSED) to include notification from Certificate Holder, concerning adverse conditions affecting Structures, Systems, or Components (SSC's) purchased by Big Rock Point for Dry Fuel Storage.
The addition of vendor-supplied evaluations (and site-specific evaluations) of dry fuel storage SSC's "exceptions" or other informational issues is appropriate as a location for future reference and retrievability of information.
The revision included a reference to the BNFL FuelSolutionsTM letter to Kurt Haas dated September 9, 2004. This letter informed Big Rock Point of a minor discrepancy in the type of coating used on the W100 Transfer Cask neutron shield as a result of a BNFL FuelSolutionsm Condition Report (#04-022Q). The revised coating type did not alter the purpose of this coating. However, some changes resulted to the SAR section on the thermal analysis due to a revision in the thermal limitations of the coating type (SAR reported maximum allowable service temperature of 3500 F as opposed to a Vendor specification of 250 0F.)
SUMMARY
Reference FuelSolutionsTM Storage System FSAR (WSNF-220), Revision 1, April 2003.
Section 4.1.2, Design Basis Ambient Conditions lists a temperature range of -400 F to 125 0F. The rating of the revised coating of 250'F bounds those values. Coating absorptivity values were not reported as revised by BNFL in their September 9, 2004 letter. This value was assumed to have remained the same, as it was an empirical number, chosen from an outside reference.
During fire events, the coating is not expected to survive and conservative emissivity value was assumed in the analysis.
Editorial revision to the DFSED and inclusion of this reference does not degrade the analysis in the FSAR. (WSNF-220). The condition report evaluated the revised coating type. Although the SAR is in error, the revision to update the temperature to the Manufacture's Specification for in-service heat loads does not increase the frequency of occurrence of thermal accidents.
The WIOO Transfer cask is affected by this activity. The indirect affect is to slightly alter statements in the BNFL FuelSolutionsT mFSAR in the description of thermal analyses.
The change in likelihood of failure due to analyzed thermal events is negligible, as the FSAR revisions are editorial (coating temperature specification has no affect on thermal analysis.)
I Consumers Energy Company Big Rock Point 10 CFR 72.48 Evaluations WSNF-223 FuelSolutionsm Storage System Final Safety Analysis Report Wesflex W74 Canister The consequences from dose resulting from the thermal accidents evaluated in the SARs are minimally affected. Thermal accidents evaluated in the FSAR, Chapter 4, for the WI 00 Transfer Cask. Although the maximum n-shield jacket temperature reported in the FSAR (WSNF-200) is 260'F (Table 4.5 Transfer Cask Maximum Material Temperatures for Off-Normal Conditions) this increase of 100 F, above the Vendor Specified value of 2500 F is considered a minimal increase (<4%.) Since little or no credit is taken for n-shield coating in the thermal analysis (non for the fire-accident), and conservative assumptions were taken for emissivity values, the thermal analysis remains valid.
The intent of the revision to correct erroneous maximum allowable coating temperatures results on no increase in the consequences of analyzed thermal accidents due to this proposed change.
Existing SAR-evaluated accidents bound the type of thermal accidents as a result of revision of coating temperature specifications.
Malfunctions of W100 Transfer Cask coating have been evaluated and are bounded by current thermal analyses in the SAR. Type of malfunction remains the same, since only the temperature specification is revised. The initiators (fire and extreme off-normal temperatures) are explicitly described in the SAR and are not revised by this specification change. A new failure mechanism is not introduced by this revision.
Type of failure (breach due to temperature affect) and results of failure modes (loss of containment and radiological release) due to this temperature revision is bounded by or minimally affects accidents previously evaluated in the SAR.
The fission barrier design basis limits (failure due to temperature affects) have not been exceeded or altered. Editorial changes to the SAR and revised temperature specification for WI 00 Transfer Cask coating results in a predicted response to thermal accidents that has not changed. The design basis thermal accident with revised coating temperature specifications is essentially the same as current SAR thermal analyses.
Changes to input for coating limiting temperature in the thermal analysis methods for the WI00 Transfer Cask that yield results that are essentially the same over entire range of use. Changes do not affect the BNL WSNF-200 SAR method and is not a departure from that approved method.
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