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TAC:MD9538, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action (Approved, Closed) |
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MONTHYEARML0822705152008-08-14014 August 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process Project stage: Request ML0904203012009-02-23023 February 2009 Issuance of Amendment No. 130 - Revision of Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process Project stage: Approval 2008-08-14
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Technical Specifications
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21077A0142021-03-16016 March 2021 License and Technical Specification Pages for Amendment No. 245, Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML19176A0862019-07-30030 July 2019 Issuance of Amendment No. 237 Changes to Containment Oxygen Concentration Requirements ML18344A4522019-01-11011 January 2019 Issuance of Amendment No. 234 Change to Remove Boraflex Credit from Spent Fuel Racks NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. ML18330A0952018-11-30030 November 2018 Correction Duplicate Subparagraph (N) on Technical Specification Page 204 That Occurred in Amendment No. 186 Issued January 25, 2005 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18032A1772018-03-0606 March 2018 Issuance of Amendment No. 166 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 (CAC No. MF9804; EPID L-2017-LLA-0232) NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17324B1782017-12-21021 December 2017 Issuance of Amendment to Allow Greater Flexibility in Performing Surveillance Testing in Modes 1, 2, or 3 of Emergency Diesel Generators(Cac No. MF9579; EPID L-2017-LLA-0203) ML17152A3202017-06-30030 June 2017 Issuance of Amendments Emergency Plans Emergency Action Level HU1.5 ML17055A4512017-03-0909 March 2017 Issuance of Amendment Partial Length Fuel Rod Burnup ML16088A0532016-04-19019 April 2016 Issuance of Amendment License Amendment Request for Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016 Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15341A3362016-01-0505 January 2016 Issuance of Amendment Technical Specifications for Safety Limit Minimum Critical Power Ratio NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015 Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements.... ML15317A3072015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specification Task Force Traveler 425 ML15096A0762015-09-0202 September 2015 Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15167A3152015-07-0808 July 2015 Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators ML15110A0082015-05-26026 May 2015 Issuance of Amendment Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML15075A1592015-03-17017 March 2015 Correction Letter to Amendment No. 217 Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change (Tac No. MF1022) ML15043A2702015-03-12012 March 2015 Issuance of Amendment Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change ML14126A0032014-06-30030 June 2014 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14057A5542014-05-29029 May 2014 Issuance of Amendment Regarding Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1233803362012-11-21021 November 2012 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1133000472011-12-22022 December 2011 NMP2 EPU - Operating License and Technical Specification Pages ML1133000412011-12-22022 December 2011 Cover Letter - Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment Extended Power Uprate ML11208C3952011-07-20020 July 2011 License Amendment Requests Pursuant to 10 CFR 50.90: Revisions to the Technical Specifications Design Features Sections to Reflect Transfer of a Portion of Nine Mile Point Nuclear Station Site Real Property ML1018803332010-07-26026 July 2010 Issuance of Amendment No. 206 Modification of TS Section 3.2.7.1 and 4.2.7.1 ML1008904222010-03-22022 March 2010 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Containment Spray System Nozzle Surveillance Frequency ML0926406812009-09-18018 September 2009 License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Tech. Spec. Sections 3.2.7.1 and 4.2.7.1 2024-09-20
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Keith J.Polson Vice President-Nine Mile Point 0/\Constellation Energy.-,..'*N ine M ile Po int Nuclear Stat ionU.S.Nuclear Regulatory Commission Washington,DC20555-0001 P.O.Box 63 Lycoming ,NewYork13093 315.349.5200315.349.1321Fax August 14 , 2008 ATTENTION:
SUBJECT:
Document Control DeskNineMilePoint Nuclear Station Unit No.2;Docket No.50-410 LicenseNo.NPF-69 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequencyanda Clarification of a Frequency Example Using the Consolidated L ine Item Improvement Process In accordancewiththeprovis ions of 10 CFR 50.90, NineMilePoint Nuclear Station , LLC (NMPNS)is submitting a requestforan amendmenttothe Technical Specifications(TS)forNineMilePointUnit2 (NMP2).The proposed amendmentwould:(1)revisetheTS surveillance requirement (SR)frequencyinTS3.1.3,"Control Rod OPERABILITY,"and(2)revise Example1.4-3inTS1.4,"Frequency" to clarify the applicability ofthe1.25 surveillancetestinterval extension.
Attachment 1 providesadescript ion of the proposed change , the requested confirmation of appl icability , and plant-specific verifications.Attachment 2 provides the existingTSpages marked-uptoshowthe proposed changes.AssociatedTSBaseschangesare marked-up in Attachment 3.TheTSBaseschanges are provided for informationonlyandwillbe processed in accordance withtheNMP2TS5.5.10
,"Technical Specifications(TS)BasesControl Program." Attachment 4 provides a summary of the regulatory commitmentsmadeinthissubmittaL NMPNS requests approval of the proposed License Amendment by February 16 ,2009,withthe amendment being implementation within60days of approval of the amendment.
In accordancewith10CFR50
.91, NMPNS has providedacopy ofthislicense amendmentrequest,with attachments
,tothe appropriate state representative
.
Document Control DeskAugust14,2008Page2Shouldyouhaveany questions regarding the informationinthissubmittal, please contactT.F.Syrell, Licensing Director,at(315)349-5219.Verytrulyyours,STATE OF NEW YORK TO WIT: COUNTY OF OSWEGO I, KeithJ.Polson,beingdulysworn,statethatIamVice President-NineMilePoint,andthatIamduly authorized to executeandfilethis request on behalf of NineMilePoint NuclearStation,LLC.Tothebest of my knowledgeandbelief,the statements containedinthis documentaretrueandcorrect.Totheextentthatthese statementsarenot basedonmy personal knowledge,theyarebased upon information providedbyotherNineMilePoint employees and/or consultants.
Such information has been reviewed in accordance with company practiceandI believeittobereliable.
Subscribedandsworn beforeme,a NotaryPublicinandfortheState ofNewYorkand County ofOswego,this day of OJ....%-*;2008.WITNESSmyHandand Notarial Seal: My Commission Expires:__--'-I_Date KJP/GB/--Notary PublicSANDRAA.OSWALDNotaryPublic
.StateofNewYork No.010S6032276Qualifiedin OswegoCommissionExpires16
<<S'd)ct Attachments:
1.2.3.4.Description and Assessment Proposed Technical Specification Changes (Marked-Up Pages)Proposed Technical Specifications Bases Changes (Marked-Up Pages)Summary of Regulatory Commitmentsmadeinthis Submittal DocumentControlDeskAugust14,2008Page3cc:S.J.Collins,NRC Regional Administrator, Region IR.V.Guzman,Jr.,NRC Project ManagerE.C.Knutson, Senior NRC Resident InspectorJ.P.Spath, NYSERDA ATTACHMENT 1 DESCRIPTION AND ASSESSMENT TABLE OF CONTENTS
1.0DESCRIPTION
2.0ASSESSMENT2.1Applicability ofPublishedSafetyEvaluation2.2OptionalChangesandVariations3.0REGULATORYANALYSIS3.1NoSignificantHazardsConsiderationDetermination3.2VerificationandCommitments4.0ENVIRONMENTALEVALUATIONNineMile Point Nuclear Station, LLC August14,2008 ATTACHMENT 1 DESCRIPTION AND ASSESSMENT
1.0 DESCRIPTION
The proposed amendmentwould:(1)revise the Technical Specification (TS)surveillance requirement(SR3.1.3.2)frequencyinTS3
.1.3,"Control Rod OPERABILITY,"and(2)revise Example1.4-3inTS Section 1.4,"Frequency"to clarify the applicability ofthe1.25 surveillance test interval extension.Thechangesare consistent with Nuclear Regulatory Commission (NRC)approved Industryffechnical Specification Task Force (TSTF)Standard Technical Specification(STS)changeTSTF-475
, Revision 1.The F ederal Register Notice published on November13,2007 announced the availability ofthisTS improvement through the consolidatedlineitem improvement process (CLIIP).2.0 ASSESSMENT
2.1 Applicability
of Published Safety Evaluation NineMilePoint Nuclear Station , LLC (NMPNS)has reviewed the safety evaluation dated November 13 ,2007aspart oftheCLIIP.Thisreviewincludedareview oftheNRC staffs evaluation
,aswellasthe supporting information provided to support TSTF-475, Revision 1.NMPNS has concludedthatthe justifications presentedintheTSTF proposalandthesafety evaluation preparedbytheNRC staff are applicable to Nine Mile PointUnit2(NMP2)and justify this amendmentforthe incorporation of thechangestothe NMP2 TS.2.2 Optional Changes and VariationsNMPNSis proposing to implementthefollowingTS editorial changes whichdifferfromthoseTS changes described in TSTF-475, Revision 1 ,andtheNRC staffs model safety evaluation dated November13,2007.Thechangesdonot adversely impact the considerations or conclusionsinthemodel safety evaluationortheintent of the amendment.
NMPNS chooses to designate Surveillance Requirement(SR)3.1.3.2 as"Deleted"andretain current SR numbersSR3.1.3.3,SR3.1.3.4,andSR3.1.3.5.This proposed variation will alleviate the requirement to make editorialchangeslistedin TSTF-475, Revision1forTS3.1.3,3.1.4and associatedTSBases.Additionally, the TSTF-475, Revision 1 requestedchangetotheTSBasesforSR3.1.3.4(torevise referencestoSR3.1.4.3andSR 3.1.4.4)wasnot includedasthese surveillancesarenot affectedbythe proposed changes.During the NMP2 conversiontotheSTS (NUREG-1433)forTS3.3.1.2,"Source Range Monitor (SRM)Instrumentation
" by Amendment 91 dated February 15 ,2000(TACNo.MA3822), Required Action E.2 was revised and presently reads"Initiate actiontofullyinsertall insertable controlrodsincorecells containingoneormorefuel assemblies."Theterm"fully"wasalso includedinTS Bases 3.3.1.2.Therefore,theseTSTF-475
, Revision 1 changesarenot necessaryforNMP2.3.0 REGULATORY ANALYSIS3.1No Significant Hazards Consideration DeterminationNMPNShas reviewed the proposed no significant hazards consideration determination (NSHCD)publishedinthe Federal Register as part oftheCLIIP.NMPNShas concludedthatthe proposed NSHCD 10f2 ATTACHMENT 1 DESCRIPTION AND ASSESSMENTpresentedinthe Federal RegisternoticeisapplicabletoNMP2andisherebyincorporatedbyreferencetosatisfytherequirements of10CFR50.91(a).
3.2 Verification
and CommitmentsAsdiscussedinthenotice ofavailabilitypublishedinthe Federal Register on November13,2007forthisTSimprovement,NMPNShasverifiedtheapplicability ofTSTF-475toNMP2,andcommitstoestablishingTechnicalSpecificationBasesfortheTSasdescribedinthislicensingamendmentrequest.ThesechangesarebasedonTSTFchangetravelerTSTF-475(Revision1)thatproposesrevisionstotheSTSby: (1)revisingthefrequency ofSR3.1.3.2,notchtesting ofawithdrawncontrolrod,from"7daysafterthecontrolrodiswithdrawnandTHERMALPOWERisgreaterthantheLPSP ofRWM"to"31daysafterthecontrolrodiswithdrawnandTHERMALPOWERisgreaterthantheLPSP ofRWM";and(2)revisingExample1.4-3inSection1.4,"Frequency"toclarifythatthe1.25surveillancetestintervalextensioninSR3.0.2isapplicabletotimeperiodsdiscussedinNOTESinthe"SURVEILLANCE "columninadditiontothetimeperiodsinthe"FREQUENCY" column.4.0 ENVIRONMENTAL EVALUATIONNMPNShasreviewedtheenvironmentalevaluationincludedinthemodelsafetyevaluationdated November 13,2007aspart oftheCLIIP.NMPNShasconcludedthatthe staffsfindingspresentedinthatevaluationareapplicabletoNMP2andtheevaluationisherebyincorporatedbyreferenceforthis application.
20f2 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARKED-UP PAGES)TSPage1.4-4TSPage1.4-5TSPage3.1.3-2 TSPage3.1.3-4NineMile Point Nuclear Station, LLC August14,2008 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)"Thereafter" indicates future performances must be established per SR 3.0.2,butonly after a specified condition is first met (i.e., the lIonce" performance in this example).If reactor powerdecreasesto
<25%RTP, the measurementofboth intervals stops.New intervals start upon reactor power reaching 25%RTP.EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE
NOTE------------------
Notrequiredto be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after25%RTP.Perform channel adjustment.
FREQUENCY7days (continued)
The interval continues whetherornotthe unit operation is<25%RTP between performances.
As the Notemodifiesthe required performanceofthe Surveillance, it isconstruedtobe partofthe"specified Frequency.
" Shouldthe 7 day i nterva 1 be exceeded wh il eoperationis
<25%RTP, this Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches25%RTP to perform the Surveillance.
The Surveillance is stillconsideredto bewithinthe"specified Frequency.
" Therefore, if the Surve ill ance were not performedwithinthe 7 day interval(plusthe extension allowed by SR 3.0.2), but operation was<25%RTP, it would not constitute a failureofthe SR or failure to meet the LCO.Also, no violation of SR 3.0.4 occurs when changing MODES, evenwiththe 7 day Frequencynotmet,provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).\with power25%RTP.(PLus The ex teIJS;O'"
&;:f<6r<3.0.:J)'3 I NMP2 1.4-4 Amendment'"9-i)
1.4 Frequency
EXAMPLES Frequency 1.4 EXAMPLE 1.4-3 (continued)
Once the unit reaches 25%RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed forcompletingthe Surveillance.
If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval, there wou then be a failuretoperforma Surveillance within the specified Frequency, and the SR 3.0.3 wouldapply.\(fLl.5" the..ex\eU61 Q1-'5R 3.0.d;EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE
NOTE------------------
Only requiredtobe met in MODE 1.FREQUENCYVerifyleakage ratesarewithin limits.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Example 1.4-4 specifies that the requirements of this Surveillancedonot havetobe met untiltheunit is in MODE 1.The interval measurement for the Frequency of this Surveillance continues at all times,asdescribedin Example 1.4-1.However, the Note constitutes an"otherwise stated" exceptiontothe Applicability of this Surveillance.
Therefore, if the Surveillance were not performedwithinthe 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval(plusthe extension allowed by SR 3.0.2),butthe unit wasnotin MODE 1, there would be no failure of the SR nor failure to meet the LCO.Therefore, no violation of SR 3.0.4 occurs when changing MODES, evenwiththe 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequencyexceeded,providedthe MODE change was not made into MODE 1.Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency werenotmet), SR 3.0.4 would require satisfying the SR.NMP2 1.4-5 Amendment*)
ACTIONS Control Rod OPERABILITY
3.1.3 CONDITION
REQUIRED ACTION COMPLETION TIME A.(continued)
A.3 Perform SR 3.1.3.2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from--aftEI-SR3.1.3.3fordiscoveryof each withdrawn Condition A OPERABLE control rod.concurrentwith THERMAL POWER greaterthanthe low power setpoint (LPSP)ofthe RWM AND A.4 Perform SR 3.1.1.1.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.Two or more withdrawnB.1 Be in MODE 3.12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />scontrolrods stuck.C.One or more control C.1--------NOTE---------rodsinoperable for RWM may be bypassedreasonsotherthan as allowed by ConditionAor B.LCO 3.3.2.1, if required,toallow insertion of inoperable control rod and continued operation.
Fully insert 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> inoperable control rod.AND C.2 Disarm the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CRD.(continued)
I NMP2 3.1.3-2 Amendment"'*j Control Rod OPERABILITY
3.1.3 SURVEILLANCE
REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.1.3.2 SR 3.1.3.3-------------------NOTE--------------------
Notrequiredtobe performed until 31 days after the controlrodis withdrawn and THERMAL POWER is greaterthanthe LPSP of the RWM.Insert withdrawn control rod 31 days at least one notch.I SR 3.1.3.4 NMP2 Verify each control rod scram time from fully withdrawntonotch position 05 is7 seconds.3.1.3-4 In accordance with SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)
Amendment-*)
ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS BASES CHANGES (MARKED-UP PAGES)TSBasesPageB3
.1.3-4 TS BasesPageB3.1.3-7 TS BasesPageB3.1.3-8NineMilePoint NuclearStation,LLC August 14,2008 BASES ACTIONS Control Rod OPERABILITY B 3.1.3 A.I.A.2.A.3.and A.4 (continued) control rod separation criteriaarenotmet.
Therefore, a verification that the separation criteria are met must beperformedimmediately.
The stuck control rod separation criteriaarenot met if:a)the stuck control rod occupies a location adjacent to two"slow" control rods,b)the stuck controlrodoccupiesa location adjacenttoone"slow" control rod, andtheone"slow" control rod is also adjacent to another"slow" controlrod,orc)if the stuck control rod occupies a location adjacenttoone"slow" control rod when there is another pair of"slow" controlrodselsewhereinthecore adjacenttoone another.The description of"slow" control rods isprovidedin LCD 3.1.4,"Control Rod ScramTimes."In addition, the associated control rod drivemustbedisarmed within2hours.The allowed Completion Timeof2hours is acceptable, considering the reactor can stillbeshut down, assuming no additional control rods fail to insert, and provides a reasonable amount oftimetoperformtheRequiredActionin an orderly manner.The control rod must be isolated frombothscram and normal insert and withdraw pressure.Isolating the control rod from scram and normal insert and withdraw pressure prevents damagetothe CROM or reactor internals.
The control rod isolation method should also ensure coolingwatertothe CRO is maintained.Monitoringofthe insertion capability for each withdrawn control rod must also be performed within24hours from discoveryofCondition A concurrent with THERMAL POWER greaterthanthe low (LPSP)of the RWM.SR 3.1.3.2SR 3.1.3.3 periodic tests of the control rod insertion capabilityofwithdrawn control rods.Testing each withdrawn control rod ensures that a genericproblemdoesnot exist.This Completion Time also allows for an exceptiontothe normal"timezero" forbeginningtheallowedoutagetime"clock." TheRequiredActionA.3 Completion Timeonlybegins upon discovery of Condition A concurrent with THERMAL POWER greater than the actual LPSP of the RWM, sincethenotch insertions maynotbe compatiblewiththe requirementsofrod pattern control (LCD 3.1.6)and the RWM (LCD 3.3.2.1).TheallowedCompletion Time provides a reasonabletimeto test the control rods , considering the potential foraneedtoreduce powertoperform the tests.(continued)
NMP2 B 3.1.3-4 Revi s ion.e; Control Rod OPERABILITY B 3.1.3 BASES ACTIONS E.1 (continued)
If anyRequiredAction and associated Completion Time of Condition A, C,orDarenot metornineor more inoperable control rods exist, the plant mustbebroughttoa MODE in which the LCOdoesnotapply.
To achieve this status, the plant mustbebroughtto MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.This ensures all insertable controlrodsare inserted and places the reactorina condition thatdoesnot require the active function (i.e., scram)ofthe control rods.The number of control rods permittedtobe inoperable when operating above 10%RTP (i.e., no CRDA considerations)couldbe more thanthevalue specified, but the occurrenceofa large number of inoperable controlrodscouldbe indicativeofa generic problem, and investigation and resolutionofthe potential problemshouldbe undertaken.
The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditionsinan orderly manner and without challenging plant systems.(continued)
SURVEILLANCE REQUIREMENTS SR 3.1.3.1 The positionofeach control rod must be determined, toensureadequate information on control rod position is availabletothe operator for determining control rod OPERABILITY and controlling rod patterns.Controlrod position maybedetermined bytheuseof OPERABLE position indicators, by moving controlrodstoa positionwithan OPERABLE indicator, (full-in, full-out, or numeric indicator), by verifying the indicatorsonenotch"out" and onenotch"in"are OPERABLE, or bytheuseof other appropriate methods.The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR is based on operating experience relatedtoexpectedchangesin control rod position and the availability of control rod position indications in the control room.-SR aRe-SR 3.1.3.3 I-L-hJ\{No"t'e5R 3.'.3.a hfls ce e JControlrod insertion capability is demonstrated by inserting each partially or fully withdrawn controlrodat least one notch and observing that the control rod moves.The control rod maythenbe returned to its original position.Thisensuresthe control rod is not stuck andfreeto insert on a scram signal.not required when THERMAL POWER is lh I S SuRve, u,
'I S NMP2 B 3.1.3-7 Revi s i on..Q-J BASES SURVEILLANCE REQUIREMENTS Control Rod OPERABILITY B 3.1.3 SR aRS SR 3.1.3.3 (continued) actual LPSPofthe RWM sincethenotch insertions maynotbecompatiblewiththe requirementsofthe banked positionwithdrawalsequence (BPWS)(LCD 3.1.6)and the RWM (LCD 3.3.2.1).TAe 7 day sf J.l.J.2 is eases eR sperating related te tAe cAaRges lA eRD fwll¥witRQraWR cSRtrel regs, Partiilly witRQraWR fods are tested at a 31 gay gases SR tRe redijctieR to allew tAe ceRtrel rod* aRS cSRsideriRg large testiRg of SR 3.1.3.4 Verifying the scramtimeforeach controlrodtonotch position 05 is7secondsprovides reasonable assurance that the control rod will insert when requiredduringa DBA or transient, thereby completing its shutdown function.This SR is performed in conjunctionwiththe control rod scram time testing of SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4.The LOGIC SYSTEM FUNCTIONAL TEST in LCD 3.3.1.1,"Reactor Protection System (RPS)Instrumentation," and the functional testing of SDV vent and drainvalvesin LCD 3.1.8,"Scram Discharge Volume (SOV)Vent andDrainValves,"overlap this Surveillance to provide complete testingofthe assumed safety function.The associatedFrequenciesare acceptable, considering the more frequent testingperformedtodemonstrate other aspects of control rod OPERABILITY and operating experience, which shows scramtimesdonot significantly changeoveran operating cycle.(continued) r , r NMP2 B 3.1.3-8 Rev is i ATTACHMENT 4
SUMMARY
OF REGULATORY COMMITMENTSMADEIN THIS SUBMITTALNineMile Point Nuclear Station, LLC August14,2008 ATTACHMENT 4
SUMMARY
OF REGULATORY COMMITMENTS MADE IN mrs SUBMITTAL LIST OF REGULATORY COMMITMENTS The following table identifies those actions committedtoby NMPNSinthis document.Any other statementsinthis submittal are provided for information purposesandarenot consideredtobe regulatory commitments.
Please direct questions regarding these commitmentstoT.F.Syrell, Licensing Director , at (315)349-5219.REGULATORY COMMITMENT DUE DATE NMPNS will establish the Technical Specifications Bases for This commitment will beTSB3.1.3 consistent with those shown in TSTF-475, implemented within60daysfrom Revision 1,"Control Rod Notch Testing Frequency and SRMthedate of the approval of the Insert Control Rod Action" as describedinthe license proposed amendment.
amendment request.1 of 1