Letter Sequence Request |
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TAC:MD3579, Addition of LCO 3.0.8, Inoperability of Snubbers (Approved, Closed) |
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MONTHYEARML0631303512006-11-0202 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) Project stage: Request ML0708711652007-05-14014 May 2007 Issuance of Amendment 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 Project stage: Approval 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 Project stage: Other 2007-05-14
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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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Text
Entergy Nuclear Operations, Inc.
~ Entergy Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Michael A. Balduzzi Site Vice President November 2, 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 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)
LETTER NUMBER: 2.06.082
Dear Sir or Madam:
In accordance with the provisions of 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) is submitting a request for an amendment to the Technical Specifications (TS) for Pilgrim Nuclear Power Station.
The proposed amendment would modify TS requirements for inoperable snubbers by adding Limiting Condition for Operation (LCO) 3.0.8. In conjunction with the proposed change, TS Bases for LCO 3.0.8 will be added consistent with Bases Control Program as described in Section 5.5.6 of the Pilgrim Technical Specifications.
Attachment 1 provides a description of the proposed change, the requested confirmation of applicability, and the plant-specific verifications. Attachment 2 provides the existing TS pages marked up to show the proposed change. Proposed TS Bases for LCO 3.0.8 are included in Attachment 2 for information only. Attachment 3 provides a summary of the regulatory commitments made in this submittal.
Entergy requests approval of the proposed License Amendment by September 30, 2007, with the amendment being implemented within 60 days.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Commonwealth of Massachusetts Official.
4o0
Entergy Nuclear Operations, Inc. Letter Number: 2.06.082 Pilgrim Nuclear Power Station Page 2 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 __ ,,-, ___of ,,_____,, __,_ 2006.
Sincerely, Michael A. Balduzzi WGL/dl Attachments: 1. Description of Proposed Change (3 pages)
- 2. Proposed Technical Specification Changes (4 pages)
- 3. Regulatory Commitments (one page) cc: Mr. James Shea, Project Manager Mr. Robert Walker, Director Plant Licensing Branch I-1 Massachusetts Department of Public Division of Operator Reactor Licensing Health Office of Nuclear Reactor Regulation Radiation Control Program U.S. Nuclear Regulatory Commission 90 Washington Street, 2 nd Floor One White Flint North O-8C2 Dorchester, MA 02121 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region 1 Ms Cristine McCombs, Director U.S. Nuclear Regulator Commission Mass. Emergency Management Agency 475 Allendale Road 400 Worcester Road King of Prussia, PA 19406 Framingham, MA 01702 Senior Resident Inspector Pilgrim Nuclear Power Station
ATTACHMENT 1 (3 Pages)
Subject:
Description of Proposed Change
1.0 DESCRIPTION
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation 2.2 Optional Changes and Variations
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration 3.2 Verification of Commitments 4.0 ENVIRONMENTAL EVALUATION
5.0 REFERENCES
Description of Proposed Change
1.0 DESCRIPTION
The proposed amendment would modify Pilgrim Technical Specifications (TS) for inoperable snubbers by adding LCO 3.0.8. In conjunction with the proposed change, TS Bases for LCO 3.0.8 will be added consistent with Bases Control Program as described in Section 5.5.6 of the Pilgrim Technical Specifications.
The proposed addition of LCO 3.0.8 is consistent with Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) change TSTF-372, Revision 4. The availability of this TS improvement was published in the Federal Register on April 4, 2005 as part of the Consolidated Line Item Improvement Process (CLIIP) (Reference 1).
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation Entergy has reviewed the safety evaluation published as part of the CLIIP. This review included a review of the NRC staff's evaluation, as well as the supporting information provided to support TSTF-372, Revision 4. Entergy has concluded that the justifications provided in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Pilgrim Nuclear Power Station and justify this amendment for the incorporation of the changes to the Pilgrim TS.
2.2 Optional Changes and Variations Entergy is not proposing any variations or deviations from the TS changes described in TSTF-372, Revision 4 or the NRC staff's model safety evaluation published in the Federal Register, dated April 4, 2005.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination Entergy has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register on April 4, 2005 as part of the CLIIP.
Entergy has concluded that the proposed NSHCD presented in the Federal Register Notice is applicable to Pilgrim and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).
3.2. Verification and Commitments As discussed in the notice of availability published in the Federal Register on April 4, 2005 for this TS improvement, plant-specific verifications were performed as follows:
Entergy is adopting the TS Bases for LCO 3.0.8, which provide guidance and details on how to implement the new requirements. LCO 3.0.8 requires that risk be managed and assessed. The Bases also state that while the Industry and NRC guidance on implementation of 10 CFR 50.65(a)(4), the Maintenance Rule, does not address seismic risk, LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that
maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative assessment of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.
Entergy will establish TS Bases for LCO 3.0.8 in accordance with the Bases Control Program consistent with Section 5.5.6 of the Pilgrim Technical Specifications.
4.0 ENVIRONMENTAL EVALUATION Entergy has reviewed the environmental evaluation included in the model safety evaluation published in the Federal Register on April 4, 2005 as part of the CLIIP.
Entergy has concluded that the staff's findings presented in that evaluation are applicable to Pilgrim and the evaluation is hereby incorporated by reference for this application.
5.0 REFERENCES
- 1. Federal Register Notice, "Notice of Availability of Model Application Concerning Technical Specification Improvement To Modify Requirements Regarding the Addition of Limiting Condition for Operation 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process," published April 4, 2005 (70 FR 23252).
Entergy Letter 2.06.082 Attachment 2 Proposed Technical Specifications Changes (Mark-up)
(4 pages)
3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0.1 Not Used 3.0.2 Not Used 3.0.3 Not Used 3.0.4 Not Used 3.0.5 Not Used 3.0.6 Not Used 3.0.7 Special Operations LCOs in Section 3.14 allow specified Technical Specifications requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all-other Technical Specification requirements remain unchanged. Compliance with Special Operations LCOs is optional. When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met. When a Special Operations LCO is not desired to be met, entry into a Mode or other specified condition Inthe
....Applicability shall only be made in acc rdance with the other applicable Specifications.
4.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 4.0.1 Not Used 4.0.2 Not Used 4.0.3 If it is discovered that a Surveillance was not performed within its specified Surveillance Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Surveillance Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
Amendment 203,44- 3/4.0-1
Attachment 2 to Entergy Letter 2.06.082 INSERT 1:
3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:
- a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.
BASES:
3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0.1 Not Used 3.0.2 Not Used 3.0.3 Not Used 2 3.0.4 Not Used 3.0.5 Not Used 3.0.6 Not Used 3.0.7 There are certain special tests and operations required to be performed at various times over the life of the unit. These special tests and operations are necessary to demonstrate select unit performance characteristics, to perform special maintenance activities, and to perform special evolutions. Special Operations LCOs in Section 3.14 allow specified Technical Specification requirements to be changed to permit performances of these special tests and operations, which otherwise could not be performed if required to comply with those Technical Specification requirements. Unless otherwise specified, all the other
......................... Technical Specification requirements remain unchanged. Tis esiures- .
all appropriate requirements of the Mode or other specified condition, not directly associated with or required to be changed to perform the special test or operation, will remain in effect.
The Applicability of a Special Operations LCO represents a condition not necessarily in compliance with the normal requirements of the Technical Specifications. Compliance-w*ith Special Operations LCOs is optional. A special operation may be performed either under the provisions of the appropriate Special Operations LCO or under the other applicable Technical Specification requirements. If it is desired to perform the special operation under the provisions of the Special Operations LCO, the requirements of the Special Operations LCO shall be followed. When a Special Operations LCO requires another LCO to be met, only the requirements of the LCO statement are required to be met regardless of that LCO's Applicability (i.e., should the requirements of this other LCO not be met, the ACTIONS of the Special Operations LCO apply, not the ACTIONS of the other LCO). However, there are instances where the Special Operations LCO ACTIONS may direct the other LCOs' ACTIONS be met.
It is not required to meet the Surveillances of the other LCO, unless specified in the Special Operations LCO. If conditions exist such that the Applicability of any other LCO is mlet, all the other LCO's requirements (ACTIONS and Surveillance Requirements) are required to be met concurrent with the requirements of the Special Operations LCO.
Revision 24-h z340 51- o Revision 244-,-2&1-- 8&34.0-1
Attachment 2 to Entergy Letter 2.06.082 INSERT 2 LCO 3.0.8 Bases 3.0.8 LCO 3.0.8 establishes conditions under which systems are considered to remain capable of performing their intended safety function when associated snubbers are not capable of providing their associated support function(s). This LCO states that the supported system is not considered to be inoperable solely due to one or more snubbers not being capable of performing their associated support function(s). This is appropriate because a limited length of time is allowed for maintenance, testing, or repair of one or more snubbers not capable of performing their associated support function(s) and appropriate compensatory measures are specified in the snubber requirements, which are located outside of the Technical Specifications (TS) under licensee control. The snubber requirements do not meet the criteria in 10 CFR 50.36(c)(2)(ii), and, as such, are appropriate for control by the licensee.
If the allowed time expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's LCO(s) must be declared not met and the conditions and required actions entered.
LCO 3.0.8.a applies when one or more snubbers are not capable of providing their associated support function(s) to a single train or subsystem of a multiple train or subsystem supported system or to a single train or subsystem supported system.
LCO 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function and due to the availability of the redundant train of the supported system.
LCO 3.0.8.b applies when one or more snubbers are not capable of providing their associated support function(s) to more than one train or subsystem of a multiple train or subsystem supported system. LCO 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function.
LCO 3.0.8 requires that risk be assessed and managed. Industry and NRC guidance on the implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk.- However, use of LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.
Entergy Letter 2.06.082 Attachment 3 Reciulatory Commitments (one page)
The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
LIST OF REGULATORY COMMITMENTS Regulatory Commitment Due Date Entergy will establish the Technical Specification Complete within 60 Bases for LCO 3.0.8 as adopted with the approved days of approved License Amendment. amendment