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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
[Table view] Category:Technical Specifications
MONTHYEARML21119A0642021-06-25025 June 2021 License Amendment 299 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) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) RA-15-030, Submittal of Changes to Technical Specifications Bases2015-04-14014 April 2015 Submittal of Changes to Technical Specifications Bases ML14329A6252015-03-30030 March 2015 Issuance of Amendment Regarding Reactor Building Vital Area Access Control ML1019301722010-09-27027 September 2010 Issuance of Amendment Relocation of Surveillance Requirement Frequencies to a Licensee Controlled Document Based on TSTF-425, Revision 3 RA-10-028, Response to Request for Additional Information, License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document2010-04-16016 April 2010 Response to Request for Additional Information, License Amendment Request Regarding Relocation of Selected Technical Specification Surveillance Frequencies to a Licensee Controlled Document RA-09-029, Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of A..2009-03-30030 March 2009 Supplement to License Amendment Request Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action, and Clarification of A.. RA-08-100, Special Report for Inoperability of Turbine Building High Range Radioactive Noble Gas Monitor2008-11-18018 November 2008 Special Report for Inoperability of Turbine Building High Range Radioactive Noble Gas Monitor ML0824703052008-08-28028 August 2008 Technical Specifications, 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 ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0812303462008-05-30030 May 2008 Tec Specs to Amd 266/License DPF-16/Oyster Creek ML0810505452008-04-30030 April 2008 Technical Specification Pages for License Amendment No. 265 the Incorporation of TSTF-448, Revision 3, Control Room Habitability. (Tac MD5281) RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. RA-08-004, Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)2008-03-10010 March 2008 Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0802901792008-02-0101 February 2008 Oyster Creek,Technical Specifications, Corrected, Revised Pages of Facility Operating License No. DPR-16 RA-08-011, Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement..2008-01-23023 January 2008 Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement.. ML0729202902007-10-18018 October 2007 Technical Specification Change Request No. 374 - Revision to Mechanical Snubber Functional Testing Requirements ML0722501972007-08-0808 August 2007 Technical Specifications Pages Re Annual Radioactive Effluent Release Report Submittal Date ML0721302932007-07-27027 July 2007 Technical Specifications, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0713603392007-05-16016 May 2007 Technical Specification Change Request No. 327 - Modify Technical Specifications for Primary Containment Oxygen Concentration ML0711703892007-04-26026 April 2007 Technical Specifications Application of Alternate Source Term Methodology ML0633201962006-11-27027 November 2006 Technical Specification Change Request No. 341 - Revision to Required Submittal Date for Annual Radioactive Effluent Release Report ML0626101962006-09-13013 September 2006 Technical Specification Pages Re Increase Safety Valve As-Found Setpoint Tolerance from 1 Percent to 3 Percent ML0624404112006-09-0101 September 2006 Tech Spec Pages for Amendment 260 Regarding Revision to Electromatic Relief Valve Surveillance Requirement ML0623704752006-08-25025 August 2006 Technical Specifications - Deletion of Reporting Requirement in Facility Operating License ML0605500582006-02-22022 February 2006 Tech Spec Page for Amendment 258 Regarding Deletion of Reporting Requirement in Facility Operating License ML0600600152006-01-0404 January 2006 Technical Specifications, 1.0 Environmental Monitoring ML0529701902005-10-18018 October 2005 Technical Specification Change Request No. 328 - Modify Surveillance Requirements for Testing of Main Steam Line Electromatic Relief Valves ML0520000612005-07-14014 July 2005 Tech Spec Pages for Amendment 256 Capability Upgrade of a 69-KV Offsite Power Line to 230-KV ML0517802562005-06-23023 June 2005 Tech Spec Pages for Amendment, Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions ML0516002532005-06-0808 June 2005 Tech Spec Page for Amendment 254 Delete the TS Requirements to Submit Monthly Operating Reports and Annual Occupational Radiation Exposure Reports RS-05-006, Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License2005-02-25025 February 2005 Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License ML0505900852005-02-24024 February 2005 Technical Specification Change Request No. 319 - Revision to Table 3.1.1 Notes Aa and Bb Regarding Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions RS-04-157, Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License2004-12-17017 December 2004 Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License ML0430803562004-11-0202 November 2004 Tech Spec Pages for Amendment 250 Main Steam Line Isolation Valve Leakage Testing ML0433100362004-10-20020 October 2004 Technical Specification, Control Rod Scram Time Testing Requirements ML0429203072004-10-13013 October 2004 Table, Run or Startup Mode (Except for Low Power Physics Testing) ML0427902182004-10-0404 October 2004 Technical Specifications, Modify Control Rod Scram Time Testing Surveillance Requirements ML0425301502004-08-27027 August 2004 Station,Technical Specification Change Request No. 331 - Safety Limit Minimum Critical Power Ratio ML0423604742004-08-19019 August 2004 Technical Specification for Oyster Creek ML0422301962004-08-0909 August 2004 Tech Spec for Oyster Creek, License Amendment No. 246, Elimination of Requirements for Hydrogen Monitors ML0421703712004-07-30030 July 2004 Technical Specifications, Sections 3.7 and 4.7, Auxiliary Electrical Power, and Added a New Section 6.8.5, Station Battery Monitoring and Maintenance Program ML0415600412004-07-13013 July 2004 Unit, 1, License Amendments 244 and 250 Re.: Amendments to Delete a License Condition Regarding the Long Range Planning Program ML0415305902004-05-27027 May 2004 Unit 1, Technical Specifications, Reflect Ownership Change ML0409002892004-03-29029 March 2004 Tech Spec Pages for Amendment 241 Regarding Increasing Flexibility in Mode Restraints ML0333201312003-11-24024 November 2003 Tech Spec Pages for Amendment 239 Regarding Startup Transformer and Emergency Diesel Generator Unavailability 2021-06-25
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OFFICIAi,. USE ONLY-SECURITY-RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 30, 2015 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - ISSUANCE OF AMENDMENT REGARDING REACTOR BUILDING VITAL AREA ACCESS CONTROL (TAC NO. MF3295)
Dear Mr. Hanson:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 285 to Renewed Facility Operating License No. DPR-16 for Oyster Creek Nuclear Generating Station (OCNGS), in response to your application dated December 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A245), as supplemented by letters dated January 31, 2014, and November 3, 2014 (ADAMS Accession Nos ML14035A264 and ML14309A615, respectively).
The amendment approves the proposed Security Plan changes to implement an "alternative measure" for satisfying applicable requirements of Title 10 of the Code of Federal Regulations, Section 73.55 related to controlling vital area access for certain portions of the Reactor Building at OCNGS.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
$~
. Lamb, Senior Project Manager Licensing Branch 1-2 Di sion of Operating Reactor Licensing 0 ice of Nuclear Reactor Regulation Docket No. 50-219
Enclosures:
- 1. Amendment No. 285 to DPR-16
- 2. Non-Security-Related Safety Evaluation
- 3. Security-Related Safety Evaluation cc w/encls 1 & 2: Distribution via Listserv Enclosure 3 transmitted herewith contains sensitive unclassified information. When separated from Enclosure 3, this document is decontrolled.
OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 285 Renewed License No. DPR-16
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee), dated December 19, 2013, as supplemented by letters dated January 31, 2014, and November 3, 2014, 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 the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment 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 and security 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 the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Renewed Facility Operating License No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 285, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance. In addition, the licensee shall include the revised information in the next "Physical Security Plan" update, as described in the licensee's application dated December 19, 2013, as supplemented by letters dated January 31, 2014, and November 3, 2014, and evaluated in the NRC staff's evaluation enclosed with this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION Douglas A Broaddus, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: March 30, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 285 RENEWED FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page 3 Page 3
(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, or special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct source, or special nuclear materials without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate such byproduct, source, or special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level Exelon Generation Company is authorized to operate the facility at steady-state power levels not in excess of 1930 megawatts (thermal) (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 285, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated March 3, 1978, and supplements thereto, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Renewed License No. DPR-16 Amendment No. 285
OFFICIAL USE ONLY SECURITY RELATED INFORMATION ENCLOSURE 2 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 285 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-16 REGARDING CONTROLLING VITAL AREA ACCESS TO CERTAIN PORTIONS OF THE BUILDING EXELON GENERATION COMPANY, LLC OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 Security-related information pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations has been redacted from this document.
Redacted information is identified by blank space enclosed within double brackets.
OFFICIAL USE ONLY SeCURITY ReLATeD INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 285 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-16 REGARDING CONTROLLING VITAL AREA ACCESS TO CERTAIN PORTIONS OF THE BUILDING EXELON GENERATION COMPANY. LLC OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
1.0 INTRODUCTION
Exelon Generation Company, LLC (Exelon, or the licensee) holds a renewed license to operate Oyster Creek Nuclear Generating Station (OCNGS), which is located in Forked River, New Jersey.
Pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Exelon submitted a license amendment request (LAR) for OCNGS by letter dated December 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A245), as supplemented by letters dated January 31, 2014, and November 3, 2014 (ADAMS Accession Nos. ML14035A264 and ML14309A615, respectively). The LAR seeks U.S.
Nuclear Regulatory Commission (NRC) review and approval of the use of alternative measures under 10 CFR 73.55(r), to the requirements of 10 CFR 73.55(e)(9)(i) through (iii) relating to control of access to vital areas at OCNGS.
The enclosures to the application and supplement dated November 3, 2014, contained Safeguards Information, which is protected under 10 CFR 73.21 and is withheld from public access pursuant to the requirements of 10 CFR 9.17.
2.0 BACKGROUND
By letter dated January 7, 2011 (ADAMS Accession No. ML110070507), Exelon notified the NRC of its intention to permanently cease operations at OCNGS no later than December 31, 2019, based on its execution of an Administrative Consent Order (ACO) with the New Jersey Department of Environmental Protection (NJDEP), dated December 9, 2010. In consideration of the signed ACO, NJDEP agreed to issue a New Jersey Pollution Discharge Elimination System Surface Water Permit that allows Exelon to operate OCNGS until December 31, 2019, with its existing once-through cooling system, rather than requiring Exelon to construct a new closed-cycle cooling system. Pursuant to 10 CFR 50.82(a)(1 )(i), the letter dated January 7, 2011, to the NRC, certified OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION Exelon's intent to permanently cease operations at OCNGS. In terms of the requirements of 10 CFR 50.4(b)(8), OCNGS shall terminate operations no later than December 31, 2019.
To gain access to OCNGS, individuals are required to undergo a thorough background screening process, conform to the requirements of the Fitness-for-Duty for drug and alcohol, and are subject to a comprehensive behavior observation program for trust-worthiness and reliability. Access to the OCNGS protected area requires individuals to be searched in order to detect, deter, and prevent introduction of firearms, explosives, incendiary devices, or other items which could be used to commit a radiological sabotage.
To gain access to the Reactor Building, the individual must complete nuclear radiation worker training and obtain an electronic self-reading dosimeter (ESRD) as part of plant work authorization.
Access to vital areas inside the building is controlled by a physical structure that is equipped with intrusion detection equipment and locking devices, locks and alarms, as required by 10 CFR 73.55(e)(9)(i) through (iii). However, as discussed in the letter dated December 19, 2013, to the NRC, the licensee specified some vital equipment that is ((
)).
In July 2014, the NRC staff conducted a plant walk-down of the building and observed the equipment discussed in OCNGS's LAR. A summary of the NRC staff's visit to the plant can be found under ADAMS No. ML14220A512. Subsequently, the NRC staff issued a Request for Additional Information (RAI), which can be found under ADAMS No. ML14114A563.
3.0
SUMMARY
OF APPLICATION The proposed changes would institute alternative measures to 10 CFR 73.55(e)(9)(i) through (iii) at OCNGS related to certain portions of the building containing specified vital equipment not located within a designated vital area.
The current access to the building housing this equipment is processed through the physical protection requirements of the site protected area. Work authorization is processed through issuance of an ESRD before allowing access to radiation protection portals located in the building.
Exelon identified a number of (( )), as discussed in Attachment 1 of the LAR. The specific locations discussed are Safeguards Information, which is protected under 10 CFR 73.21 and is withheld from public access pursuant to the requirements of 10 CFR 9.17.
The NRC staff asked the licensee, in an RAI, to ((
)) in 10 CFR 73.55(e)(9)(i). In its response to the NRC staff's RAI, dated November 3, 2014 (ADAMS Accession No. ML14309A615), Exelon identified ((
)). Other physical access locations were reevaluated by the licensee for safety and security interface, including emergency response, to ensure that potential adverse impacts to plant systems and security are considered and addressed prior to implementation of changes to physical layout, facilities, structures, systems, components, and operating procedures. The list of the physical access locations with ((
)) is Safeguards Information, which is protected under 10 CFR 73.21 and is withheld from public access pursuant to the requirements of 10 CFR 9.17.
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION In the LAR, the licensee proposed the following five security measures as an alternative measure:
(1) ((
)),
(2) Train general personnel of site security awareness to recognize the ((
)) with limited access to the building, (3) Increase operations, security, security supervisors, and radiation protection personnel walk down (tour) of the plant, (4) Increase security focus awareness training for operations, security, security supervisors, and radiation protection personnel, and (5) Revise security-related procedures to implement these measures.
The licensee asserts that, if approved and implemented, the proposed alternative measures would provide a level of protection at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii), and an acceptable technical basis for OCNGS to revise the site's specific physical security protection plan and supporting procedures under 10 CFR 50.54(p) requirements to meet the performance objective and requirements of 10 CFR 73.55(b).
4.0 REGULATORY EVALUATION
The licensee is requesting the use of alternatives to the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii).
- 10 CFR 73.55(e)(9)(i), states that vital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans.
- 10 CFR 73.55(e)(9)(ii) states that the licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking devices that allow rapid egress during an emergency and satisfy the vital entry control requirements of this section.
In accordance with the requirements of 10 CFR 73.55(r), the NRC may authorize a licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73. 55, if the licensee demonstrates that the measure meets the same performance objectives and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55.
Also, the regulations in 10 CFR 73.55(r)(3) state, in part, that, "[t]he licensee shall submit a technical basis for each proposed alternative measure." The basis must include an analysis or OFFICIAL USE ONlY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION assessment that demonstrates how the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirements.
5.0 TECHNICAL EVALUATION
The NRC staff's technical evaluation considers whether the security measures, as stated in the LAR, provide a level of protection at least equal to the protection provided by the measures required in 73.55(e)(9)(i) through (iii). These specific security measures enable a licensee to meet the performance objectives of 10 CFR 73.55(b) by ensuring that the licensee has the capabilities to detect, assess, interdict, and neutralize threats up to and including the design basis threat of radiological sabotage. The specific security measures of 73.55(e)(9)(i) through (iii) provide two primary security features: (1) physical barriers and (2) intrusion detection.
The physical barrier requirements in Section 73.55(e)(9)(i) through (iii) enable detection by giving security personnel a clear indication of when unauthorized access has occurred (e.g.,
because an unauthorized person is on the wrong side of a physical barrier). Similarly, alarms and intrusion detection systems provide a direct indicator, in the absence of direct observation, that a physical barrier has been breached.
In the LAR, the licensee specified some vital equipment that is ((
)). These systems can be accessed from ((
)), as discussed in Section 2 of Attachment 1 of OCNGS's LAR, which contains Safeguards Information and is protected under 10 CFR 73.21. This Safeguards Information is withheld from public disclosure pursuant to the requirements of 10 CFR 9.17.
The LAR explains that if the request is granted, there would only be (( )) physical barrier at the protected area. The portions of the building that contain the specified vital equipment would be (( )) controlled by the proposed alternative measures, and that there would be
(( )) to the portions of the building that contain the specified vital equipment, except as specified in the LAR and in the licensee's response to the NRC staff RAI. The specific location of the building access portals and emergency exits is Safeguards Information, which is protected under 10 CFR 73.21 and is withheld from public disclosure pursuant to the requirements of 10 CFR 9.17. Instead, the licensee asserts in the LAR that the five proposed security measures, when combined with the physical barrier to the protected area, would provide a level of protection at least equal to compliance with the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii).
The LAR asserts that the five proposed security measures enable the detection of threats.
Security Measure 1: ((
)).
In responding to the NRC staff RAI, the licensee indicated that the use of ((
)) to perform OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION work when a nuclear radiation worker training had not been certified, along with the issuance of the ESRD as part of work authorization, thereby limiting physical access to the building. The use of this proposed security measure would reduce the potential of unauthorized access to the restricted areas, through early detection, as part of work authorization process.
Security Measure 2: Train general personnel of site security awareness to recognize the
(( )) with limited access to the building.
Employees are trained to recognize and be aware of this ((
)) and limited access, and employees are required to report to security upon detecting an unauthorized access to the building. The training and reporting, as discussed in this proposed security measure, serve as an early alarm warning and contribute to the physical barrier protection.
Security Measure 3: Increase operations, security, security supervisors, and radiation protection personnel tours of the plant.
In addition to the security tour of the plant conducted by armed security personnel and security supervisors, operations and radiation protection personnel are required to document and verify the configuration readiness of vital equipment at locations identified in the LAR, to address potential tempering of equipment for security protection, as part of the plant tour. These required actions are implemented in the plant security protection procedures. The net effect of the proposed security measure provides a security presence in the building on a 24-hour, 7-day a week basis, to detect unauthorized access and to timely respond to potential threats through communication with the Central Alarm Station.
Security Measure 4: Increase security focus awareness training for operations, security, security supervisors, and radiation protection personnel.
As discussed above, the focused training and awareness of vital equipment with emphasis on equipment tempering protection, along with increased security tours enhance detections of intrusion to the building and of an unauthorized access to vital equipment. The net effect of the proposed Security Measures 3 and 4 is a constant security presence in the building to detect unauthorized access and to timely respond to potential threats, through communication with the Central Alarm Station.
Security Measure 5: Revise security-related procedures to implement the alternative measures.
This action formalizes the proposed alternative measures, through the plant specific security implementation procedures, to ensure that roles and responsibilities are defined, effective knowledge base is identified, and success criteria are defined.
The NRC staff finds that these proposed alternative measures would enable the detection, assessment, response, interdiction, and neutralization of security threats, because the proposed alternative measures provide for limited access, frequent visual observation, and a means of visually distinguishing unauthorized personnel in the vicinity of the vital equipment, by ensuring that individuals with training in detection and awareness will be observing the vital equipment OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAb USE ONbY SECURITY REbATED INFORMATION frequently. Therefore, the NRC staff concludes that these proposed alternative measures meet the performance objectives and requirements of 10 CFR 73.55(b ).
As discussed above, the requirements in 10 CFR 73.55(e)(9)(i) through (iii) enable detection of unauthorized entry access to vital equipment. In addition, the licensee's proposed alternative provides a means of visually distinguishing unauthorized access to the vital equipment, limiting access to the building, as well as increasing the number of around the clock trained observers.
Therefore, the NRC staff finds that the proposed alternative provides a detection capability at least equal to that provided by the specific measures required by 10 CFR 73.55(e)(9)(i) through (iii).
Based on the factors discussed above, the NRC staff concludes that the licensee's proposed alternative measures meets the same performance objectives specified in 10 CFR 73.55(b ), and that they provide a level of protection that is at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii). Therefore, the NRC staff finds the proposed alternative measures acceptable.
6.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment. The State official had no comments.
7.0 ENVIRONMENTAL CONSIDERATION
This amendment relates solely to safeguards matters and does not involve any significant construction impacts. 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 (79 FR 25901, May 6, 2014). Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
8.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that 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 Contributor: David Diec Date: March 30, 2015 OFFICIAb USE ONbY SECURITY REbATED INFORMATION
ML14035A264 and ML14309A615, respectively).
The amendment approves the proposed Security Plan changes to implement an "alternative measure" for satisfying applicable requirements of Title 10 of the Code of Federal Regulations, Section 73.55 related to controlling vital area access for certain portions of the Reactor Building at OCNGS.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA/
John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosures:
- 1. Amendment No. 285 to DPR-16
- 2. Non-Security-Related Safety Evaluation
- 3. Security-Related Safety Evaluation cc w/encls 1 & 2: Distribution via Listserv Enclosure 3 transmitted herewith contains sensitive unclassified information. When separated from Enclosure 3, this document is decontrolled.
DISTRIBUTION:
RidsNrrDorlDpr Resource RidsRgn1 MailCenter Resource RidsRgn 1MailCenter Resource RidsNrrDorlLpl1-2 Resource RidsNrrLAABaxter Resource PLee, NSIR RidsAcrsAcnw_ MailCTR LPL 1-2 R/F PUBLIC DDiec, NSIR ADimitriadis, RI JKulp, RI APatel, RI JCherubini, RI ADAMS Accession Nos. ML14329A625 Security-Related SE: ML14329A872 Non-Securib -Related SE: ML15054A242 *via e-mail OFFICE LPL 1-2/PM LPL 1-2/LA NSIR/BC OGC - NLO LPL 1-2/BC LPL 1-2/PM NAME JLamb ABaxter
- DHuyck* SClark DBroaddus JLamb (MKhanna for)
DATE 11/28/2014 11/28/2014 02/18/2015 02/13/2015 03/25/2015 03/30/2015