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MONTHYEARML0624904892006-08-30030 August 2006 Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1, Project stage: Meeting ML0622803042006-09-14014 September 2006 Issuance of Amendment Relocation of Technical Specifications Project stage: Approval 2006-08-30
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Category:Letter
MONTHYEARL-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 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 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 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 ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application 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 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 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 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 ML22104A0542022-04-30030 April 2022 LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22152A2592022-04-25025 April 2022 Zaccagnini Letter Dated 04/25/22 ML22152A2642022-04-19019 April 2022 Flynn Letter Dated 04/19/22 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. ML22130A6762022-03-14014 March 2022 Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station ML22041B0762022-03-0707 March 2022 03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay ML22054A2962022-02-23023 February 2022 Annual ISFSI Radioactive Effluent Release Report for 2021 2024-02-02
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML21148A1992021-05-28028 May 2021 Supplemental Information to Correct License Amendment Request to Revise Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool ML21103A0552021-05-12012 May 2021 May 2021 Pilgrim Nuclear Power Station Issuance of Amendment 254 to Revise the Physical Security Plan Alternative Measures, Cover Letter and Amendment ML21076A4042021-03-17017 March 2021 License Amendment Request to Revise Pilgrim Nuclear Power Station Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool L-21-036, Proposed Independent Spent Fuel Storage Installation-Only Security, Training and Qualification, Safeguards Contingency Plan2021-03-17017 March 2021 Proposed Independent Spent Fuel Storage Installation-Only Security, Training and Qualification, Safeguards Contingency Plan L-21-008, License Amendment Request to Approve Pilgrim Nuclear Power Station Independent Spent Fuel Storage Installation Only Emergency Plan2021-02-18018 February 2021 License Amendment Request to Approve Pilgrim Nuclear Power Station Independent Spent Fuel Storage Installation Only Emergency Plan L-20-024, Attachments 1 - 3: Summary of Evaluation of Proposed Changes, Proposed Change to PNPS Renewed Facility License Condition 3.G (Mark-up) and (Clean Copy)2020-04-0202 April 2020 Attachments 1 - 3: Summary of Evaluation of Proposed Changes, Proposed Change to PNPS Renewed Facility License Condition 3.G (Mark-up) and (Clean Copy) ML19170A1492019-08-22022 August 2019 Enclosure 2, Draft Conforming Amendment for Direct and Indirect Transfer of Renewed Facility Operating License to Holtec Pilgrim, LLC, Owner and Holtec Decommissioning International, LLC, Operator (L-2018-LLO-0003) CNRO-2018-00047, Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment; and Request for Exemption from 10 CFR 50.82(a)(8)(i)(A)2018-11-16016 November 2018 Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment; and Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) ML18218A1742018-08-0101 August 2018 Revised the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML18023A6912018-01-12012 January 2018 Revise the Pilgrim Emergency Plan to Address the Permanently Defueled Condition ML18023A6872018-01-12012 January 2018 License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition ML17101A6082017-03-30030 March 2017 License Amendment Request - Cyber Security Plan Implementation Schedule ML17053A4682017-02-14014 February 2017 Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition ML16021A4592016-01-14014 January 2016 Proposed License Amendment Request to Modify Emergency Response Organization (ERO) Training for the On-Shift Chemistry Technician ML15205A2872015-07-15015 July 2015 License Amendment Request - Cyber Security Plan Implementation Schedule ML14042A1662014-01-31031 January 2014 License Amendment Request - Cyber Security Plan Implementation Schedule ML13346A0262013-11-26026 November 2013 Proposed License Amendment Request to Modify Technical Specification 4.3.4, Heavy Loads to Facilitate Dry Storage Handling Operations ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel ML13108A2172013-04-0505 April 2013 Proposed License Amendment: Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open (PRFO) Transient Reported by General Electric Nuclear Energy in Accordance with 10 CFR 21.21(d) ML12005A1982011-12-29029 December 2011 Cycle-Specific License Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowance to Allow Reactor Startup ML11312A0512011-10-28028 October 2011 Proposed License Amendment: Revision to Technical Specification (TS) Table 3.2.B for the Condensate Storage Tank (CST) Low Level Trip Setpoint & Corrections to Typographical Errors Incurred During Prior License Amendment. ML1100502982011-01-26026 January 2011 Issuance of Amendment Regarding Revised Pressure and Temperature (P-T) Limit Curves and Relocation of P-T Curves to the PTLR ML1102000582011-01-0707 January 2011 License Renewal Application, Supplemental Information ML1019703592010-07-15015 July 2010 Submittal of License Amendment Request, Cyber Security Plan ML1002700542010-01-24024 January 2010 Proposed License Amendment to Technical Specifications: Revised P-T Limit Curves and Relocation of Pressure-Temperatures (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions ML0828301352008-09-30030 September 2008 Request for License Amendment for Licensee Name Changes ML0734600622007-11-29029 November 2007 Request for License Amendment - Control Room Envelope Habitability (TSTF-7448, Revision 3) ML0721906112007-07-30030 July 2007 License Renewal Application Amendment 19 ML0717304672007-06-21021 June 2007 License Renewal Application Amendment 18 ML0715503102007-05-17017 May 2007 License Renewal Application Amendment 17 ML0707903162007-03-13013 March 2007 License Renewal Application Amendment 15 ML0706503502007-02-23023 February 2007 License Renewal Application Amendment 14 ML0703702982007-01-30030 January 2007 E-MAIL: (PD) Pilgrim LRA Amendment 13 ML0703802272007-01-17017 January 2007 E-MAIL: (PD) Pilgrim LRA Amendment 12 ML0702302862007-01-16016 January 2007 License Renewal Application Amendment 12 ML0702302932007-01-15015 January 2007 Proposed Change to Applicability of Pilgrim'S Pressure - Temperature Curves as Described in Technical Specification Figures 3.6.1, 3.6.2, and 3.6.3, Revision 1 ML0702501752007-01-10010 January 2007 License Renewal Application Amendment 11 ML0701105012007-01-0404 January 2007 Technical Specification Revisions for Control Rod Operability Scram Insertion Times and Control Rod Accumulator Requirements ML0700404412006-12-27027 December 2006 License Amendment Request for Adoption of TSTF-484 Revision 0, Use TS 3.10.1 for Scram Time Testing Activities ML0701004102006-12-12012 December 2006 2006/12/12-Letter from Entergy to NRC Dated 12 December, 2006 (Including Attached PNPS MACCS2 Input Files -attached Cd) Regarding License Renewal Application Amendment for Pilgrim Station Operating License ML0631303512006-11-0202 November 2006 Application for Technical Specification (TS) Change to Add LCO 3.0.8 on the Inoperability of Snubbers (and Adoption of TS Bases for LCO 3.0.8) Using the Consolidated Line Item Improvement Process (CLIIP) ML0635601142006-10-25025 October 2006 Reactor Pressure Vessel Fluence Evaluation at End of Cycle 15 and 54 EFPY (Non-Proprietary) ML0625001172006-08-30030 August 2006 2006/08/30-Pilgrim, Response to Requests for Additional Information Re License Renewal Application Amendment 7 ML0624904892006-08-30030 August 2006 Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1, ML0619401752006-07-0505 July 2006 2006/07/05-Pilgrim - License Renewal Application Amendment 3 ML0618704692006-06-30030 June 2006 Technical Specifications Amendment Request to Revise the Surveillance Requirements for the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems ML0610908322006-04-12012 April 2006 Proposed License Amendment to Change Technical Specification 3.6.A.2, Pressure-Temperature Limit Curves ML0603000282006-01-25025 January 2006 2006/01/25-Pilgrim Nuclear Power Station License Renewal Application ML0530404502005-10-18018 October 2005 Technical Specifications Amendment Request for Single Control Withdrawal Allowances, TS 3/4.14 Special Operations. 2021-05-28
[Table view] Category:Technical Specifications
MONTHYEARML20328A2972020-12-0101 December 2020 Amendment No. 253 - Non-Safeguards Version ML19276C4202020-01-0202 January 2020 Issuance of Amendment No. 252, Request to Remove Cyber Security Plan Requirements for the Permanently Defueled Condition ML19235A0502019-08-27027 August 2019 Issuance of Amendment No. 249 Order Approving Direct Transfer of Renewed Facility Operating License and ISFSI General License and Conforming Amendment ML17163A1812017-05-25025 May 2017 Supplemental to Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition ML17053A4682017-02-14014 February 2017 Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition ML16363A2662017-01-10010 January 2017 Correction to Amendment No. 234 Change in Technical Specification Measurement Frequency from 18 Months to 24 Months ML16250A2232016-10-28028 October 2016 Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician ML15114A0212015-05-0606 May 2015 Issuance of Amendment Regarding the Minimum Critical Power Ratio License Amendment Request ML14272A0702015-03-12012 March 2015 Issuance of Amendment 242 Re Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open Transient ML14295A6852014-10-31031 October 2014 Issuance of Amendment Regarding Heavy Loads to Facilitate Dry Storage Handling Operations ML14259A3812014-09-11011 September 2014 Supplement to Proposed License Amendment Request to Modify Technical Specification 4.3.4, Heavy Loads to Facilitate Dry Storage Handling Operations ML13108A2172013-04-0505 April 2013 Proposed License Amendment: Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open (PRFO) Transient Reported by General Electric Nuclear Energy in Accordance with 10 CFR 21.21(d) CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications ML12005A1982011-12-29029 December 2011 Cycle-Specific License Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowance to Allow Reactor Startup ML0731004782007-11-0505 November 2007 Technical Specifications, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements ML0726101972007-09-18018 September 2007 Technical Specifications, Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers ML0726102002007-05-17017 May 2007 Technical Specifications, Corrected Page II (Fixed Administrative Error) ML0715605422007-04-25025 April 2007 Tech Spec Pages for Amendment 228 Single Control Rod Withdrawal Allowances ML0714303052007-04-25025 April 2007 Technical Specifications, Limiting Conditions for Operation ML0708603592007-03-26026 March 2007 Technical Specifications, Issuance of License Amendment 226 Adoption of Technical Specification Task Force (TSTF) Change TSTF-484 Use of TS 3.10.1 for Scram Time Testing Activities. ML0708603392007-02-22022 February 2007 Technical Specifications, Modify the TSs to Extend the Use of the Current Pressure-Temperature Limits as Specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 Through the End of Operating Cycle 18 ML0702302932007-01-15015 January 2007 Proposed Change to Applicability of Pilgrim'S Pressure - Temperature Curves as Described in Technical Specification Figures 3.6.1, 3.6.2, and 3.6.3, Revision 1 ML0631303512006-11-0202 November 2006 Application for Technical Specification (TS) Change to Add LCO 3.0.8 on the Inoperability of Snubbers (and Adoption of TS Bases for LCO 3.0.8) Using the Consolidated Line Item Improvement Process (CLIIP) ML0626405822006-09-20020 September 2006 Tech Spec Pages for Amendment 225 Regarding Revised Reactor Coolant System Leakage Detection Instrumentation Requirements and Actions ML0626202402006-09-14014 September 2006 Technical Specification Pages Re Relocation of Technical Specifications Structural Integrity Requirements to Final Safety Analysis Report ML0624904892006-08-30030 August 2006 Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1, ML0622800132006-08-0909 August 2006 Tech Spec Pages for Amendment 223 Regarding Administrative Changes and Relocation of Certain Technical Specification Responsibilities ML0622301672006-08-0404 August 2006 Tech Spec Pages for Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature ML0618704692006-06-30030 June 2006 Technical Specifications Amendment Request to Revise the Surveillance Requirements for the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems ML0613000952006-05-0505 May 2006 Correction to Amendment No. 221 Revised Rod Worth Minimizer Bypass Allowances - Technical Specifications ML0610702152006-04-13013 April 2006 Technical Specification Page, Deletes the Main Steam Isolation Valve Twice Per Week Partial Stroke Testing Surveillance Specified in Technical Specification 4.7.A.2.b.1.c ML0610702042006-04-13013 April 2006 Technical Specification Page Re Revised Rod Worth Minimizer Bypass Allowances ML0610908322006-04-12012 April 2006 Proposed License Amendment to Change Technical Specification 3.6.A.2, Pressure-Temperature Limit Curves ML0610701672006-04-12012 April 2006 Tech Spec Pages for Amendment 219 Regarding Single Recirculation Loop Operation ML0611402652006-04-10010 April 2006 Technical Specification Pages Re Revised Applicability for Containment Oxygen and Differential Pressure Limits ML0524301522005-08-29029 August 2005 Technical Specification Pages Re Surveillance Frequency Improvements ML0521400792005-07-29029 July 2005 Technical Specifications, Revised Action for Scram Discharge Volume Vent and Drain Valves ML0515204742005-05-24024 May 2005 Technical Specifications Amendment Request to Revise Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Applicability Requirements ML0515204582005-05-24024 May 2005 Technical Specifications Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowances ML0515204732005-05-24024 May 2005 Request for Amendment to the Technical Specifications to Delete Requirement Related to NRC Approval of Engineering Evaluation for Elevated Safety Relief Valve Discharge Pipe Temperature ML0512200952005-04-28028 April 2005 Technical Specifications, Eliminates Secondary Containment Operability Requirements When Handling Sufficiently Decayed Irradiated Fuel or Performing Core Alterations ML0510400322005-04-12012 April 2005 Technical Specifications, Revision to Surveillance Requirement Frequency for Containment and Suppression Pool Spray Headers and Nozzles ML0509004102005-03-30030 March 2005 Technical Specifications, Allows One-time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML0507601772005-03-16016 March 2005 Tech Spec Pages for Amendment No. 211, Revise Reactor Vessel Hydrostatic and Leak Testing Requirements ML0503800052005-02-0202 February 2005 Tech Spec Page for Amendment 210 Changes to Technical Specifications Table 3.2.C-1 ML0500701552005-01-0505 January 2005 Technical Specification Pages for Amendment No. 209 to License No. DPR-35 ML0423206092004-08-17017 August 2004 Technical Specifications, Issuance of Amendment Re.: Multiple Control Rod Removal, Limiting Condition for Operation 3/4.10.D ML0420502772004-07-22022 July 2004 Tech Spec Pages for Amendment 206 Elimination of Requirements for Hydrogen Analyzers ML0403307902004-01-30030 January 2004 License Amendment, Tech Spec Pages ML0332100752003-11-14014 November 2003 Revised TS Page 5.0-7, Eliminating Requirements for Post-Accident Sampling System 2020-12-01
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'ýEn teWg Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Michael A. Balduzzi Site Vice President August 30, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
SUBJECT:
Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 REFERENCE LETTER NUMBER:
Dear Sir or Madam:
Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1.(TAC MC5421)1. Entergy Letter to NRC 2.04.104, 'Technical Specification Amendment Request to Relocate Various Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), dated December 14, 2004. (TAC MC5421)2.06.073 By this letter, Entergy proposes to revise the license amendment request that was submitted to the NRC by Reference
- 1. The proposed revision reduces the scope of the original license amendment request by reducing the number of individual items proposed for relocation.
There are no.new items proposed for relocation in this revision therefore, the No Significant Hazards Consideration performed for the original license amendment request is unaffected and remains bounding.Commitments made in this letter are contained in Attachment
- 3. Entergy will implement the amendment within 90 days following NRC approval.If you have any questions or require additional information, please contact Bryan Ford at (508) 830-8403.I declare under penalty of perjury that the foregoing is true and correct.Executed on the L7Y 'of ,7' C 2" 2006.Sincerely, Michael A. Balduzzi ERS/dm I400 I Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Letter Number: 2.06.073 Page 2 Attachments:
- 1. Evaluation of the Proposed Change (4 pages)2. Mark-up of Technical Specification pages (4 pages)3. List of Regulatory Commitments (1 page)cc: Mr. James Shea, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North O-8C2 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region 1 U.S. Nuclear Regulator Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Robert Walker, Director Massachusetts Department of Public Health Radiation Control Program 90 Washington Street, 2 nd Floor Dorchester, MA 02121 Ms Cristine McCombs, Director Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 Senior Resident Inspector Pilgrim Nuclear Power Station ATTACHMENT 1 Evaluation of the Proposed Chanae
Subject:
Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii)
- 1. DESCRIPTION
- 2. PROPOSED CHANGE 3. BACKGROUND
- 4. TECHNICAL ANALYSIS 5. REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration
5.2 Environmental
Consideration
- 6. PRECEDENTS
- 7. REFERENCES Letter 2.06.073 Attachment 1 Page 1 of 4 Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii) 1 .DESCRIPTION Pursuant to 10 CFR 50.90, Entergy proposes to amend the Technical Specifications (TS) for Pilgrim Nuclear Power Station. The proposed change relocates the structural integrity requirements contained in TS 3/4.G to the Pilgrim UFSAR.2. PROPOSED CHANGE The structural integrity requirements of TS 3.6.G and 4.6.G are proposed for relocation to the UFSAR. The TS and TS Bases pages marked up to reflect the proposed changes are contained in Attachment
- 2. The marked up TS Bases are provided for information only.3. BACKGROUND The Pilgrim Nuclear Power Station Inservice Inspection Program conforms to the requirements of 10 CFR 50.55a(g).
Where practical, the inspection of ASME Section Xl Class 1, 2, and 3 components conforms to the edition and addenda of Section XI of the ASME Boiler and Pressure Vessel Code required by 10 CFR 50.55a(g).
When implementation of an ASME Code required inspection is determined to be impractical for PNPS, a request for relief from the inspection requirement is submitted to the NRC in accordance with 10 CFR 50.55a(g)(5)(iii).
Requests for relief from the ASME Code inspection requirements are submitted to the NRC prior to the beginning of each 10-year inspection interval for which the inspection requirement is known to be impractical.
Requests for relief from inspection requirements that are identified to be impractical during the course of the inspection interval are reported to the NRC throughout the inspection interval.4. TECHNICAL ANALYSIS Section 182a of the Atomic Energy Act of 1954, as amended (the Act) requires applicants for nuclear power plant operating licenses to include the TS as part of the license. The Commission's regulatory requirements related to the content for the TS are set forth in 10 CFR 50.36. That regulation requires that the TS include items in eight specific categories.
The categories are (1) safety limits, limiting safety system settings, and limiting control settings;(2) limiting conditions for operation; (3) surveillance requirements; (4) design features;(5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports.However, the regulation does not specify the particular requirements to be included in a plant's TS.The Commission amended 10 CFR 50.36 (60 FR 36593, July 19,1995), and codified four criteria to be used in determining whether a particular matter is required to be included in a limiting condition for operation (LCO), as follows: (1) Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; (2) a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier; (3) a structure, system, or component that is part of the primary success path and which functions or Letter 2.06.073 Attachment 1 Page 2 of 4 actuates to mitigate a design-basis accident or transient that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier; or (4) a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety. LCOs and related requirements that fall within or satisfy any of the criteria in the regulation must be retained in the TS, while those requirements that do not fall within or satisfy these criteria may be relocated to licensee-controlled documents.
The PNPS UFSAR is one such licensee-controlled document.Consistent with these criteria, Entergy proposes to relocate the structural integrity requirements from the PNPS TS to the UFSAR. The four criteria of 10 CFR 50.36 are addressed for the proposed change.(1) TS 3.6.G and 4.6.G establish the programmatic elements for conducting ASME Code Class 1, 2, and 3 component inspections by reference to Section Xl of the ASME Code.The safety basis for establishing programmatic requirements on structural integrity in TS relates to prevention of component degradation and continued long-term maintenance of acceptable structural conditions.
Therefore, structural integrity of safety systems are not operational limits that are an initial assumption of any DBA or transient analysis.Additionally, the inspections stipulated by this specification are not used to detect and indicate in the control room a significant abnormal degradation of the reactor coolant pressure boundary.(2) The inspections stipulated by TS 3.6.G and 4.6.G do not monitor process variables that are initial assumptions in a DBA or transient analysis.(3) The ASME Code Class 1, 2, and 3 components inspected per TS 3.6.G and 4.6.G are assumed to function to mitigate accidents.
Their capability to perform this function is addressed by other TS. TS 3.6.G and 4.6.G, however, only specifies inspection requirements for these components.
Therefore, Criterion 3 is not satisfied.
(4) The TS 3.6.G and 4.6.G requirement is currently covered by 10 CFR 50.55a and the PNPS Inservice Inspection Program. Duplicating regulatory requirements in TS is not a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.The structural integrity requirements of TS 3.6.G and 4.6.G requirements will be relocated to the UFSAR. Any changes to these requirements will be strictly controlled by the provisions of 10 CFR 50.59, as well as 10 CFR 50.55a(g).
Letter 2.06.073 Attachment 1 Page 3 of 4 5. REGULATORY SAFETY ANALYSIS 5.1 No Siqnificant Hazards Consideration Entergy Nuclear Operations, Inc. (Entergy) is proposing to modify the Pilgrim Technical Specifications (TS) to relocate the structural integrity requirements from the TS to the Final Safety Analysis Report (FSAR) or TS Bases. These requirements do not meet the criteria for inclusion in the TS as presented in 10 CFR 50.36(c)(2)(ii).
Entergy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No. The proposed relocation is administrative in nature and does not involve the modification of any plant equipment or affect basic plant operation.
The associated instrumentation and inspections are not assumed to be an initiator of any analyzed event, nor are these limits assumed in the mitigation of consequences of accidents.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No. The proposed change does not involve any physical alteration of plant equipment and does not change the method by which any safety-related system performs its function.
As such, no new or different types of equipment will be installed, and the basic operation of installed equipment is unchanged.
The methods governing plant operation and testing remain consistent with current safety analysis assumptions.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?Response:
No. The proposed change to relocate current TS requirements to the FSAR, consistent with regulatory guidance and previously approved changes for other stations, is administrative in nature. The change does not negate any existing requirement, and does not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis.
As such, there are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety as a result of the proposed change. Margins of safety are unaffected by requirements that are retained, but relocated from the Technical Specifications to the FSAR. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Letter 2.06.073 Attachment 1 Page 4 of 4 Based on the above, Pilgrim concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Environmental
Consideration A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement.
However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the proposed amendment.
- 6. PRECENDENTS The NRC has approved similar changes (e.g., relocation of specifications which do not meet the criteria of 10 CFR 50.36(c)(2)(ii))
in a number of amendments.
An Example is James A. FitzPatrick conversion to Standard TS, Amendment 274, dated July 3, 2002.7. REFERENCES
- 1. Entergy Letter to NRC 2.04.104, 'Technical Specification Amendment Request to Relocate Various Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), dated December 14, 2004. (TAC MC5421)2. NUREG-1433, Rev. 3, "Standard Technical Specifications, General Electric Plants, BWR/4" ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATION AND BASES PAGES (4 pages)TOC page ii TS page 3/4.6-8 TS Bases page B3/4.6-11 TS Bases page B3/4.6-12 TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
3.6 PRIMARY
SYSTEM BOUNDARY 4.6 3/4.6-1 A. Thermal and Pressurization Limitations A 3/4.6-1 B. Coolant Chemistry B 3/4.6-3 C. Coolant Leakage C 3/4.6-4 D. Safety and Relief Valves D 3/4.6-6 E. Jet Pumps E 3/4.6-7 F. Recirculation Loops Operating e- F 3/4.6-8 G. Str,'turaI Ga O'4.,-8 BASES B3/4.6-1 3.7 CONTAINMENT SYSTEMS 4.7 3/4.7-1 A. Primary Containment A 3/4.7-1 B. Standby Gas Treatment System and Control B Room High Efficiency Air Filtration System 3/4.7-11 C. Secondary Containment C 3/4.7-16 BASES B3/4.7-1 3.8 PLANT SYSTEMS 4.8 3/4.8-1 3.8.1 Main Condenser Offgas 4.8.1 3/4.8-1 3.8.2- MechanicalVacuum Pump-- -.. ....... .- 4.8.2- ...............
3/4.8-2--BASES B3/4.8-1 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 3/4.9-1 A. Auxiliary Electrical Equipment A 3/4.9-1 B. Operation with Inoperable Equipment B 3/4.9-4 BASES B3/4.9-1 3.10 CORE ALTERATIONS 4.10 3/4.10-1 A. Refueling Interlocks A 3/4.10-1 B. Core Monitoring B 3/4.10-1 C. Spent Fuel Pool Water Level C 3/4.10-2 D. Multiple Control Rod Removal D 3/4.10-2 BASES B3/4.10-1 3.11 REACTOR FUEL ASSEMBLY 4.11 3/4.11-1 A. Average Planar Linear Heat Generation Rate A (APLHGR) 3/4.11-1 B. Linear Heat Generation Rate (LHGR) B 3/4.11-2 C. Minimum Critical Power Ratio (MCPR) C 3/4.11-2 D. Power/Flow Relationship During Power D Operation 3/4.11-4 BASES B3/4.11-1 PNPS ii Amendment No.--7, -240-I 11MITIKII%-
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'.UII rlIU I 3.6 PRIMARY SYSTEM BOUNDARY (Cont) 4.6 PRIMARY SYSTEM BOUNDARY (Cont)F. Recirculation Loops Operatina F. Recirculation Loops Operating During operation in the Run and Startup Recirculation pump speeds shall be Modes, at least one recirculation pump shall checked and logged at least once per day.be operating.
- 1. Whenever both recirculation pumps are in operation, pump speeds shall be maintained within 10% of each other when power level is greater than 80%and within 15% of each other when power level is less than or equal to 80%.2. Whenever a single recirculation loop is operating, the following limits are applied when the associated LCO is applicable:
a) LCO 3.11.A, "Average Planar Linear Heat Generation Rate (APLHGR)," single loop operation limits specified in the COLR, b) LCO 3.11.C, "Minimum Critical-Power Ratio (MCPR)," single loop operation limits specified in the COLR, and c) LCO 3.1, "Reactor Protection System," Average Power Range Monitor High Flux function, trip level setting for the flow bias function is reset for single loop operation per Table 3.1.1.3. If the requirements of Specification 3.6.F.1 or 3.6.F.2 are not met, restore.compliance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If compliance is not restored or with no l recirculation pumps in operation the reactor shall be in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.G. "tctural Inteqrity
"-G. St Inteqdrit 1. Th tructural integrity of the primary Inservic inspection of components shall be syste oundary shall be maintained at performed accordance with the PNPS the level uired by the ASME Boiler Inservice Ins ion Program. The results and Pressure essel Code,Section XI obtained from co liance with this program'Rules for Inserv lnspection of will be evaluated a e completion of each Nuclear Power Plan mponents," ten year interval.
The onclusions of this Articles IWA, IWB, IWO, D and IWF evaluation will be review with the NRC.and mandatory appendic required by 10CFR5O.55a(g), except re specific relief has been granted he NRC pursuant to 1OCFR5O.55a(g)(Amendment No. 19, 93,133,4+9-1 3/4.6-8 3/4. PRIMARY SYSTEM BOUNDARY (Cant The Pilgrim clear Power Station Inservice Inspection Program nforms to the requirements of 1 OCFR5O.55
).Where practical, the inspection of ASME Secti Xl Class 1, 2, and 3 components confo s to the edition and addenda of Section XI of the ME Boiler and Pressure Vessel Co required by 1 OCFR5O.55a(g).
When implementati of an ASME Code required inspection has een determined to be impractical for PNPS, a requ t for relief from the inspection requiremen Is submitted to the NRC in accordance with 10CFR .55a(g)(5)(iii).
Requests for relief from the ASCode inspection requirements will be submitted t the NRC prior to the beginning of ea ch 10 r inspection interval for which the inspection requi ment is known to be impractical.
Requests relief from inspection requirements which are ide 'fied to be impractical during the course of the i ection interval will be reported to the NRC on an annual basis throughout the inspection int al.P(11-0ý1) , ý tekle-
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ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS List of Regulatory.Commitments The following table identifies those actions committed to by Pilgrim in this document.
Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
REGULATORY COMMITMENT DUE DATE Relocate specified requirements to the Within 90 days of license amendment approval.UFSAR.