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MONTHYEARML0721302932007-07-27027 July 2007 Technical Specifications, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test Project stage: Approval ML0711002372007-07-27027 July 2007 License Amendment, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test Project stage: Approval 2007-07-27
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Category:Letter
MONTHYEARML23342A1162024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 IR 05000219/20230022023-11-0909 November 2023 EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23249A1212023-09-0606 September 2023 NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076) ML23242A1162023-08-30030 August 2023 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022 ML23214A2472023-08-22022 August 2023 NRC Inspection Report 05000219/2023002 IR 05000219/20230012023-05-31031 May 2023 NRC Inspection Report No. 05000219/2023001 IR 07200015/20234012023-05-16016 May 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401 ML23114A0912023-04-24024 April 2023 Annual Radioactive Effluent Release Report for 2022 ML23114A0872023-04-24024 April 2023 Annual Radioactive Environmental Operating Report for 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 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 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 IR 05000219/20220022023-02-0909 February 2023 NRC Inspection Report No. 05000219/2022002 ML23031A3012023-02-0808 February 2023 Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System ML23033A5052023-02-0202 February 2023 First Use Notification of NRC Approved Cask RT-100 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22347A2732022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 ML22297A1432022-12-15015 December 2022 Part 20 App G Exemption Letter 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 IR 07200015/20224012022-12-0606 December 2022 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1) ML22280A0762022-11-0202 November 2022 Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22286A1402022-10-13013 October 2022 NRC Confirmatory Order EA-21-041 IR 05000219/20220012022-08-11011 August 2022 NRC Inspection Report 05000219/2022001 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22214A1732022-08-0202 August 2022 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML22207B8382022-07-26026 July 2022 NRC Confirmatory Order EA-21-041 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22118A6122022-04-28028 April 2022 Annual Radioactive Environmental Operating Report for 2021 ML22118A5822022-04-28028 April 2022 Annual Radioactive Effluent Release Report for 2021 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22069A3762022-03-10010 March 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML22032A0582022-03-0808 March 2022 EA-21-139; EA-150: Oyster Creek Nuclear Generating Station - NRC Investigation Report Nos.. 1-2021-002 & 1-2021-014 ML22060A2202022-03-0202 March 2022 NRC Office of Investigations Case No. 1-2021-009 ML22049B2452022-02-19019 February 2022 Late Low Level Radwaste Shipment Report Pursuant to 10 CFR 20 Appendix G IR 05000219/20214022022-01-26026 January 2022 EA-21-041: Confirmatory Order Related to Oyster Greek Nuclear Generating Station - NRC Investigation Report I-2020-007; NRC Inspection Report Nos. 05000219/2021402 & 07200015/2021401 ML22025A3422022-01-25025 January 2022 and Big Rock Point - Changes to Site Organization ML22025A2182022-01-25025 January 2022 Late LLRW Shipments Investigation Report Pursuant to 10 CFR 20, Appendix G ML22021B5512022-01-21021 January 2022 Compensatory Measures Not Implemented Per Site'S Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure L-21-134, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2021-12-17017 December 2021 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML21349A5192021-12-15015 December 2021 Commitment Change Summary Report ML21285A1912021-11-30030 November 2021 Nrc'S Analysis of Holtec Decommissioning International'S Decommissioning Funding Status Report for Oyster Creek Nuclear Generating Station and Pilgrim Nuclear Power Station, Docket Nos 50-219 and 50-293 IR 05000219/20210032021-11-16016 November 2021 NRC Inspection Report No. 05000219/2021003 L-21-118, Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades2021-11-0909 November 2021 Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades IR 05000219/20214042021-08-26026 August 2021 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200015/2021402 and Security Decommissioning Inspection Report 05000219/2021404 - (Public) 2024-01-09
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML21119A0642021-06-25025 June 2021 License Amendment 299 ML21176A1552021-06-25025 June 2021 Issuance of Amendment to Change the Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan to Reflect an ISFSI-Only Configuration (EPID No. L-2020-LLA-0267) Public Version ML19179A2032019-09-18018 September 2019 Amendment No. 298 Issuance of License Amendment for Removal of Cyber Security Plan Requirements ML19164A1562019-07-0101 July 2019 Conforming Amendment No. 297 to License DPR-16 ML19129A3652019-06-12012 June 2019 Offsite Exemption Letter ML19098A2582019-06-11011 June 2019 Issuance of Amendment No. 296, Change to the Effective and Implementation Dates of License Amendment for Emergency Plan and Emergency Action Level Scheme Based on Adiabatic Calculation ML18227A3382018-10-26026 October 2018 Issuance of Amendment No. 295, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML18221A4002018-10-17017 October 2018 Issuance of Amendment No. 294, Revise the Site Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MG0160; L-2017-LLA-0307) ML17356A2132018-03-0707 March 2018 Issuance of Amendment No. 293, Revise the Site Emergency Plan for On-Shift and Emergency Response Organization Staffing for Permanently Defueled Condition (CAC No. MF9352; L-2017-LLA-0177) ML17289A2222017-12-22022 December 2017 Issuance of Amendment No. 292, Request to Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9550; EPID L-2017-LLA-0193) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17067A0422017-06-23023 June 2017 Issuance of Amendment No. 291, Request to Delete Decommissioning Trust Provisions in License Conditions 3.F Through 3.K of the Renewed Facility Operating License ML17090A1582017-04-0707 April 2017 Correction to Renewed Facility Operating License Page for Amendment No. 289 Regarding Changes to the Technical Specifications to Reduce Reactor Steam Dome Pressure ML16235A4132017-03-0707 March 2017 Issuance of Amendment No. 290, Changes to Administrative Controls Section of the Technical Specifications No Longer Applicable to Facility in Permanently Defueled Condition ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15040A7212015-04-0303 April 2015 Issuance of Amendment to Revise Technical Specification for the Snubber Surveillance Requirements ML14329A6252015-03-30030 March 2015 Issuance of Amendment Regarding Reactor Building Vital Area Access Control ML14295A3002015-01-29029 January 2015 Issuance of Amendments Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. ML14226A9402014-12-24024 December 2014 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training (TAC Nos. MF3003, MF3004, MF3005, MF3006, MF3007, MF3008.. ML14008A3502014-05-27027 May 2014 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement... ML13079A3722013-06-20020 June 2013 Issuance of Amendments Staff Qualifications Education and Experience Eligibility Requirments for Licensed Operators (ME9047) ML1118613412011-08-10010 August 2011 Issuance of License Amendments Regarding Exelon Cyber Security Plan ML1113101532011-06-28028 June 2011 Issuance of Amendment Changes to Appendix B, Environmental Technical Specifications ML1111701942011-06-16016 June 2011 Issuance of Amendment Elimination of Daily Testing of an Operable Emergency Diesel Generator ML1024305512010-10-18018 October 2010 Issuance of Amendment Secondary Containment Boundary Definition During Shutdown Conditions ML1019301722010-09-27027 September 2010 Issuance of Amendment Relocation of Surveillance Requirement Frequencies to a Licensee Controlled Document Based on TSTF-425, Revision 3 ML0925305612009-10-22022 October 2009 Issuance of Amendment Control Rod Drive System Rod Notch Testing Frequency ML0912708182009-08-11011 August 2009 Fleet, License Amendment, Application for TS Change Revision of Control Rod Notch Surveillance Test Frequency, Clarification of Source Range Monitor Insert Control Rod Action, & Clarification of a Frequency Example Using the Consolidated. ML0802804402009-04-0808 April 2009 Transmittal Letter - Oyster Creek Renewed License ML19095A4612009-04-0808 April 2009 License Transfer Conforming Amendment ML0835002172009-03-23023 March 2009 Issuance of Amendments Related to Removal of References to NRC Generic Letter 82-12 ML0828908782009-02-24024 February 2009 Issuance of Amendment Deletion of Section 6.5, Review and Audit ML0831903372009-02-23023 February 2009 Fleet, License Amendment, Adopt TS Task Force Change Traveler TSTF-308 ML0827705682009-01-0808 January 2009 Unit 1, Issuance of Conforming Amendments Direct Transfer of Facility Operating License to Exelon Generation Co., LLC ML0827502532008-12-23023 December 2008 Draft Amendment to Facility Operating License ML0826817542008-10-10010 October 2008 Issuance of Amendment Revision to Mechanical Snubber Functional Test Requirements ML0823906852008-09-30030 September 2008 Issuance of Amendment 269 Relocation of Pressure and Temperature Curves to the Pressure and Temperature Limits Report ML0806003302008-08-28028 August 2008 License Amendment, TSTF Change Traveler TSTF-479 & TSTF-497 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0808606702008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Issuance of Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators. (Tacs MD6364 ML0812303282008-05-30030 May 2008 Issuance of Amendment Primary Containment Oxygen Concentration ML0810505322008-04-30030 April 2008 License Amendment No. 265 the Incorporation of TSTF-448, Revision 3, Control Room Habitability. (Tac MD5281) ML0721406062007-08-0909 August 2007 Revised Pages of Facility Operating License DPR-16 ML0716504372007-08-0808 August 2007 Issuance of Amendment Request to Revise Annual Radioactive Effluent Release Report Sutmittal Date ML0711002372007-07-27027 July 2007 License Amendment, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test ML0710800192007-04-26026 April 2007 License Amendment Application of Alternate Source Term Methodology ML0622600272006-09-13013 September 2006 Issuance of Amendment Request to Increase Safety Valve As-Found Setpoint Tolerance from 1 Percent to 3 Percent ML0622001142006-09-0101 September 2006 Issuance of License Amendment 260 Regarding Revision to Electromatic Relief Valve Surveillance Requirement ML0620901592006-08-25025 August 2006 Issuance of Amendment Deletion of Reporting Requirement in Facility Operating License 2021-06-25
[Table view] Category:Safety Evaluation
MONTHYEARML21119A0632021-06-25025 June 2021 Safety Evaluation Report ISFSI Only Tech Specs ML21119A0622021-06-25025 June 2021 Letter to A. Sterdis Re Oyster Creek Issuance of Amendment to Revise Permanently Defueled Tech Specs ML19179A2052019-09-18018 September 2019 Safety Evaluation Report Oyster Creek Amendment No. 298 Issuance of License Amendment for Removal of Cyber Security Plan Requirements ML19095A4572019-06-20020 June 2019 License Transfer SER ML19095A8732019-06-11011 June 2019 Letter, Exemption from the Effective Date of Exemptions from Certain Emergency Planning Requirements, Change of Adiabatic Heat-up Calculation ML19098A2582019-06-11011 June 2019 Issuance of Amendment No. 296, Change to the Effective and Implementation Dates of License Amendment for Emergency Plan and Emergency Action Level Scheme Based on Adiabatic Calculation ML18227A3382018-10-26026 October 2018 Issuance of Amendment No. 295, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML18221A4002018-10-17017 October 2018 Issuance of Amendment No. 294, Revise the Site Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MG0160; L-2017-LLA-0307) ML18220A9802018-10-16016 October 2018 Letter and Safety Evaluation, Exemption from Portions of 10 CFR 50.47 and Appendix E to 10 CFR 50 to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition (CAC MG0153; EPID L-2017-LLE-0020) ML18226A3302018-09-28028 September 2018 Review of Update to Spent Fuel Management Plan ML18165A1362018-06-27027 June 2018 Independent Spent Fuel Storage Installation - Review and Acceptance of Changes Decommissioning Quality Assurance Program ML17356A2132018-03-0707 March 2018 Issuance of Amendment No. 293, Revise the Site Emergency Plan for On-Shift and Emergency Response Organization Staffing for Permanently Defueled Condition (CAC No. MF9352; L-2017-LLA-0177) ML17289A2222017-12-22022 December 2017 Issuance of Amendment No. 292, Request to Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9550; EPID L-2017-LLA-0193) ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17067A0422017-06-23023 June 2017 Issuance of Amendment No. 291, Request to Delete Decommissioning Trust Provisions in License Conditions 3.F Through 3.K of the Renewed Facility Operating License ML17150A0912017-06-0505 June 2017 Fleet - Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques (CAC Nos. MF8763-MF8782 and MF9395) ML16235A4132017-03-0707 March 2017 Issuance of Amendment No. 290, Changes to Administrative Controls Section of the Technical Specifications No Longer Applicable to Facility in Permanently Defueled Condition ML16222A7872016-09-0606 September 2016 Unit 1; and Quad Cities Nuclear Power Station, Units 1 and 2 - Review of Certified Fuel Handler Training and Retraining Program ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML16131A7502016-07-0606 July 2016 Staff Assessment Preliminary Decommissioning Cost Estimate and Spent Fuel Management Program (Cac. No. MF5577) ML15245A3462015-09-15015 September 2015 Review of Physical Security Plan, Revision 13 ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15097A1532015-05-0101 May 2015 Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief and R-45 (TAC Nos. MF3406 and MF3407) ML15040A7212015-04-0303 April 2015 Issuance of Amendment to Revise Technical Specification for the Snubber Surveillance Requirements ML14329A6252015-03-30030 March 2015 Issuance of Amendment Regarding Reactor Building Vital Area Access Control ML14295A3002015-01-29029 January 2015 Issuance of Amendments Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. ML14226A9402014-12-24024 December 2014 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training (TAC Nos. MF3003, MF3004, MF3005, MF3006, MF3007, MF3008.. ML14175B5932014-07-31031 July 2014 Proposed Alternative to Utilize Code Case N-786, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping Section XI Division1 ML14008A3502014-05-27027 May 2014 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement... ML14100A3592014-04-30030 April 2014 Peach Bottom... Proposed Alternative to Utilize Code Case N-649, Alternative Requirements for IWE-5240 Visual Examination Section XI ML13175A1112013-08-0707 August 2013 Relief from the Requirements of the ASME Code, Relief Request No. I5R-06 ML13175A1252013-08-0606 August 2013 Relief from the Requirements of the ASME Code, Relief Request No. I5R-07 ML13169A0622013-08-0505 August 2013 Relief from the Requirements of the ASME Code, Relief Request No. I5R-01 ML13175A1002013-08-0505 August 2013 Relief from the Requirements of the ASME Code, Relief Request No. I5R-02 ML13079A3722013-06-20020 June 2013 Issuance of Amendments Staff Qualifications Education and Experience Eligibility Requirments for Licensed Operators (ME9047) ML13092A4012013-04-18018 April 2013 Relief from the Requirements of the ASME Code, Relief Request No. l5R-01 for Expanded Applicability for Use of ASME Code Case N-661-1 ML12145A7032012-06-14014 June 2012 Relief Request to Extend the Fourth Inservice Inspection Interval ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML1208202662012-03-29029 March 2012 Request to Use Later Edition of Code for Listed Plants ML1200503502012-01-24024 January 2012 Relief from the Requirements of the ASME Code, Relief Request No. VR-02 for Fifth Inservice Testing Interval ML1118613412011-08-10010 August 2011 Issuance of License Amendments Regarding Exelon Cyber Security Plan ML1116500972011-06-30030 June 2011 Fleet - Approval of Change from Emergency Action Level Scheme Based on NEI 99-01, Revision 4, to NEI 99-01, Revision 5 ML1113101532011-06-28028 June 2011 Issuance of Amendment Changes to Appendix B, Environmental Technical Specifications ML1111701942011-06-16016 June 2011 Issuance of Amendment Elimination of Daily Testing of an Operable Emergency Diesel Generator ML1024305512010-10-18018 October 2010 Issuance of Amendment Secondary Containment Boundary Definition During Shutdown Conditions ML1019301722010-09-27027 September 2010 Issuance of Amendment Relocation of Surveillance Requirement Frequencies to a Licensee Controlled Document Based on TSTF-425, Revision 3 ML0925305612009-10-22022 October 2009 Issuance of Amendment Control Rod Drive System Rod Notch Testing Frequency ML0925200392009-09-15015 September 2009 Relief Request for Alternative Examination for Reactor Pressure Vessel Circumferential Shell Welds 2021-06-25
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Text
July 27, 2007Mr. Christopher M. CranePresident and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - ISSUANCE OF AMENDMENT RE: REQUEST TO CHANGE TECHNICAL SPECIFICATION DEFINITION OF CHANNEL CALIBRATION, CHANNEL CHECK, AND CHANNEL TEST (TAC NO. MD3133)
Dear Mr. Crane:
The Commission has issued the enclosed Amendment No. 263 to Facility Operating LicenseNo. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), in response to your application dated September 28, 2006. The amendment revises the Oyster Creek Technical Specification definition of ChannelCalibration, Channel Check, and Channel Test consistent with NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications," dated June2004. A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included inthe Commission's biweekly Federal Register notice. Sincerely,/ra/G. Edward Miller, Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-219
Enclosure:
- 1. Amendment No. 263 to DPR-16
- 2. Safety Evaluationcc w/encls: See next page July 27, 2007Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - ISSUANCE OF AMENDMENT RE: REQUEST TO CHANGE TECHNICAL SPECIFICATION DEFINITION OF CHANNEL CALIBRATION, CHANNEL CHECK, AND CHANNEL TEST (TAC NO. MD3133)
Dear Mr. Crane:
The Commission has issued the enclosed Amendment No. 263 to Facility Operating LicenseNo. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), in response to your application dated September 28, 2006. The amendment revises the Oyster Creek Technical Specification definition of ChannelCalibration, Channel Check, and Channel Test consistent with NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications," dated June2004. A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included inthe Commission's biweekly Federal Register notice. Sincerely,/ra/G. Edward Miller, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-219
Enclosure:
- 1. Amendment No. 263 to DPR-16
- 2. Safety Evaluationcc w/encls: See next page DISTRIBUTION
- PUBLICRidsOgcRpRidsNrrDorlDpr LPLI-2 R/FRidsNrrDorlLpl1-2(HChernoff)GHill (2)
TKobetzRidsNrrPMGMillerRidsNrrLAMOBrien RidsAcrsAcnwMailCenterMHamm, NRR CSchulten, NRRRidsRgn1MailCenter(GMatakas)Package Accession Number: ML0711002472Amendment Accession Number: ML0711002397TS(s) Accession Number: ML072130293OFFICELPLI-2/PMLPLI-2/LADIRS/ITSB/BCOGCLPLI-2/BCNAMEGEMillerMO'BrienTKobetzMYoungHChernoff(w/comments)DATE5/10/075/3/076/5/077/16/077/27/07OFFICIAL RECORD COPY
AMERGEN ENERGY COMPANY, LLC DOCKET NO. 50-219OYSTER CREEK NUCLEAR GENERATING STATIONAMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 263License No. DPR-161.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by AmerGen Energy Company, LLC, (thelicensee), dated September 28, 2006, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance: (i) that the activities authorized by thisamendment 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 andsecurity 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 theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the Facility Operating License is amended by changes to the TechnicalSpecifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby amended to read as follows.(2)Technical SpecificationsThe Technical Specifications contained in Appendices A and B, as revisedthrough Amendment No. 263, are hereby incorporated in the license. AmerGen Energy Company, LLC, 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 beimplemented within 60 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/ra/Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical SpecificationsDate of Issuance: July 27, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 263 FACILITY OPERATING LICENSE NO. DPR-16DOCKET NO. 50-219Replace page 3 of Facility Operating License No. DPR-16 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicatingthe area of change.Replace the following pages of the Technical Specifications with the attached pages. Therevised pages are identified by amendment number and contain marginal lines indicating theareas of change. RemoveInsert1.0-41.0-43.1-193.1-19 4.1-94.1-9 4.3-24.3-2 4.4-14.4-1 4.12-14.12-1 4.12-24.12-2 4.13-14.13-1 4.13-24.13-2 4.15-24.15-2 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 263TO FACILITY OPERATING LICENSE NO. DPR-16AMERGEN ENERGY COMPANY, LCCOYSTER CREEK NUCLEAR GENERATING STATIONDOCKET NO. 50-21
91.0INTRODUCTION
By application dated September 28, 2006, AmerGen Energy Company, LLC (AmerGen or thelicensee) requested changes to the Facility Operating License for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would revise the Oyster Creek Technical Specification (TS) definition for Channel Calibration, Channel Check, and ChannelTest consistent with NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications," June 2004. The proposed changes to the current definitions of Channel Calibration, Channel Check, andChannel Test in Section 1.19 of the Oyster Creek TSs will apply to all instrument functions in the TSs, including Reactor Protection System (RPS) instruments. The proposed changes would allow for overlapping or sequential testing of all instrumentation channels. Among other things, this manner of testing would minimize the time the RPS would be in a half-scram condition during surveillance testing, thereby minimizing the chance of a full scram due to spurious half scram signals from the opposite channel.
2.0REGULATORY EVALUATION
The licensee identified the applicable regulatory requirements in Section 5.2 of Attachment 1 ofits submittal. The criteria against which the Nuclear Regulatory Commission (NRC) staff evaluated the proposed change are Title 10 of the Code of Federal Regulations (10 CFR), Part50, Appendix A, General Design Criterion (GDC) 21, "Protection System Reliability and Testability," and 10 CFR 50.55a(h), "Protection and safety systems." GDC 21 states as follows: The protection system shall be designed for high functional reliability andinservice testability commensurate with the safety functions to be performed. Redundancy and independence designed into the protection system shall besufficient to assure that (1) no single failure results in loss of the protection function and (2) removal from service of any component or channel does not result in loss of the required minimum redundancy unless the acceptable reliability of operation of the protection system can be otherwise demonstrated.
The protection system shall be designed to permit periodic testing of its functioning when the reactor is in operation, including a capability to test channels independently to determine failures and losses of redundance that may have occurred. Since Oyster Creek was designed, built, and began operation prior to the codification of theGDCs, they were not a part of the original design basis for the plant. However, the Updated Final Safety Analysis Report (UFSAR) was subsequently revised to describe conformance with the GDC, including GDC 21. Further, 10 CFR 50.55a(h) lists the codes and standards that licensees must adhere to withregard to protection and safety systems. Currently, this regulation endorses Institute of Electrical and Electronics Engineers (IEEE) Standard 603, 1991 edition, including the correctionsheet dated January 30, 1995. For those nuclear power plants whose construction permits were issued after January 1, 1971, but before May 13, 1999, the regulation requires that plant protection systems must meet either IEEE Standard 279 or IEEE 603, 1991 edition, including the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, protection systems must be consistent with their licensing bases. Although the Oyster Creek construction permit was issued prior to January 1, 1971, and theissuance of IEEE 279, the licensing basis as described in the Oyster Creek UFSAR has since been updated to reflect IEEE 279 as the design basis for Oyster Creek.
3.0TECHNICAL EVALUATION
3.1Description of Proposed Change 3.1.1Channel Check The proposed change would revise the definition of Channel Check from: A qualitative determination of acceptable operability by observation of channelbehavior during operation. This determination shall include, where possible, comparison of the channel with other independent channels measuring the same variableto: A CHANNEL CHECK shall be the qualitative assessment, by observation, ofchannel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications orstatus derived from independent instrument channels measuring the same parameter. 3.1.2Channel TestThe proposed change would rename a Channel Test as a Channel Functional Test and revisethe definition from: Injection of a simulated signal into the channel to verify its proper responseincluding where applicable, alarm and/or trip initiating action.to: A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actualsignal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.
The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps. 3.1.3Channel Calibration The proposed change would revise the definition of Channel Calibration from: Adjustment of channel output such that it responds, with acceptable range andaccuracy to known values or the parameter which the channel measures.
Calibration shall encompass the entire channel, including equipment actuation, alarm or trip. to: A CHANNEL CALIBRATION shall be the adjustment as necessary, of thechannel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps. 3.2.1Evaluation of Proposed Definition Changes In its application, AmerGen stated that the Oyster Creek TSs were reviewed for all sectionsreferencing and/or using the instrument terms check, test, functional test, and calibrate/calibration in the context of using the proposed definitions of Channel Check, Channel Calibration, and Channel Functional Test. Further, AmerGen stated that the differences resulting from the proposed definitions were consistent with the existing TS definitions for checking, testing, and calibrating instrument channels while allowing for alternate and improved testing methodologies and maintaining the performance requirements of the instrumentation and associated surveillance frequencies. The NRC staff reviewed the impact of the proposed definition revisions to confirm the licensee'sassertion that the proposed revision will allow flexibility in testing methodologies, while continuing to verify the operability of the instrument channels. The NRC staff finds that the proposed changes will allow for performing overlapping or sequential testing that will continue to test the entire channel, consistent with IEEE 279. Further, the proposed amendment does not modify the time intervals for Surveillance Requirements (SRs), required action times for failure to meet Limiting Conditions for Operation, or Limiting Safety System Settings.
Therefore, the proposed change will continue to meet the design-basis standard of IEEE 279 for Oyster Creek . Additionally, AmerGen stated that complying with the current Oyster Creek TS definitions ofChannel Calibration, Channel Check, and Channel Test for the RPS requires placing the RPSin a half-scram condition during some SR testing. This situation creates a condition where a full-scram would occur while the reactor is at power and within operating limits if the opposite channel of the RPS received a spurious scram signal. By implementing the proposed definitions, overlapping or sequential testing of the RPS channels would be permissible, thus minimizing the time a half-scram condition exists during testing. Minimizing this time reduces the likelihood of a spurious scram at power, improving the reliability of the RPS. Given that the proposed changes will continue to meet the design-basis standard of IEEE 279,while improving the reliability of the RPS, the NRC staff finds the proposed change acceptable. 3.2.2Update of Wording in Associated Specifications Revising the definitions of Channel Check, Channel calibration, and Channel functional Testalso necessitates updating those sections of the TSs that reference the terms. The NRC staff reviewed the current Oyster Creek TSs and the proposed revisions and finds that the licensee appropriately identified those areas in the TSs needing revision and has proposed changes to these areas consistent with the definition changes discussed above. Therefore, the NRC staff finds the proposed revisions to be acceptable.
4.0STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified ofthe proposed issuance of the amendment. The State official had no comments.
5.0ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 such finding (71 FR 67392). 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.
6.0CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) thereis 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 Commission's 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 Contributors: M. Hamm, G. E. Miller Date: July 27, 2007 Oyster Creek Nuclear Generating StationSite Vice President - Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731Senior Vice President of Operations AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348Kathryn M. Sutton, EsquireMorgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004Kent Tosch, ChiefNew Jersey Department of Environmental Protection Bureau of Nuclear Engineering
CN 415 Trenton, NJ 08625Vice President - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Regional Administrator, Region IU.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406-1415Mayor of Lacey Township818 West Lacey Road Forked River, NJ 08731Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731Director - Licensing and Regulatory AffairsAmerGen Energy Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348Manager Licensing - Oyster CreekExelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348Regulatory Assurance Manager Oyster Creek AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731Assistant General CounselAmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348Ron Bellamy, Region IU.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406-1415Correspondence Control DeskAmerGen Energy Company, LLC 200 Exelon Way, KSA 1--1 Kennett Square, PA 19348Oyster Creek Nuclear Generating StationPlant Manager AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731