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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements 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 NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-12-18018 December 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-12-26026 December 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.2019-10-31031 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications2019-06-26026 June 2019 License Amendment Request - Administrative Changes to the Technical Specifications RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate2019-05-31031 May 2019 License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances2018-12-0606 December 2018 Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration2018-06-26026 June 2018 License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration 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 RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks2018-02-0909 February 2018 License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-15015 December 2017 License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2017-11-0303 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP1L3158, Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 12017-05-31031 May 2017 Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 1 NMP2L2641, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02017-05-31031 May 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 ML17164A1532017-05-31031 May 2017 Enclosure 4B - EAL Red-Line Basis Document for Nine Mile Point Nuclear Station, Unit 1 ML17164A1552017-05-31031 May 2017 Enclosure 4D - EAL Front Matter for Nine Mile Point Nuclear Station, Unit 1 ML17164A1542017-05-31031 May 2017 Enclosure 4C - EAL Basis Document for Nine Mile Point Nuclear Station, Unit 1 JAFP-17-0050, Exigent License Amendment Request to Revise Emergency Action Level HU1.52017-05-19019 May 2017 Exigent License Amendment Request to Revise Emergency Action Level HU1.5 ML17037C4192017-05-11011 May 2017 Amendment to Operating License/Change to Appendix a of Technical Specification Concerning Certain Repairs at Facility and Concomitantly to Allow a Continuation of a Slightly Lower Water Level in the Reactor... NMP2L2643, License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes2017-04-0505 April 2017 License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-032017-02-17017 February 2017 Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03 NMP1L3122, License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup2017-01-0303 January 2017 License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup NMP2L2584, License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-032016-12-13013 December 2016 License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03 NMP2L2634, Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications2016-11-26026 November 2016 Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications 2023-08-21
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U.S. NUCLEAR REGULATORV COMMISSIO I
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OCK T NUMBF R FILE NUMBER NRC DISTRIBuTION FoR PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Niagara Mohawk Power Corp. 5/6/77 Mr. ST Nowicki Syracuse, New York DATE RECEIVED Wi Ri D'Angelo 5/12/77 e-'TTE R ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED
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I c A)RIGINAl NC LASS IF I E D Ocor v PX ENCLOSURE INo letter of transmittal received: Amdto to OL/cfiange to Appendix A tech:.
I specs'otorized 5/6/T7. cqncerns request.
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Nine Mile Point Unit No 1 RJL, g)O Qg)Q SAFETY FOR ACTION/INFORMATION ASSIGNED AD:
NQ 0 EC MANA E PROJECT'ANAGER.
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- SYSTEMS SAFETY PLANT SYSTEMS SITE SAFE HR~I)R '- HEINEMAN..-
TEDESCO I &E SCHROEDER 0 OELD GOSSICK & STAFF ENGINEERING IPPOLITO E 0 MIPC MACAI'~Y ERNST CASE BOSNlau , BALLARD SIHWEIL OPERATING REACTORS YOUNGBLOOD HARLESS PAWLICK STELLO SITE TECH PROJECT MANAGEMENT REACTOR SAFE OPERATING TECH GA~LL BOYD ROSS EISENHUT STEPP P COLLINS NOVAK HULHAN HOUSTON ROSZTOCZY PETERSON CHECK BUTLE SITE ANALYSIS MELTZ VOLLtIER HELTEMES AT& I BUNCH SKOVHOLT SALTZHAN J COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR 5, NAT LAB TIC: REG V IE ULR KSON OR NSIC: LA PDR 330025 ASLB! CONSULTANTS:
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yoxation, hoX,dex of. Feci3.$ ,ty Opex'etang Licenei Ho. BPR-63, hex'aby requests tbnt Seccioee R,.X.X, and 3.X..6 oZ the Techn9.ca%, Specifications and Bases set forth in ApyeocKv A
@o that. License be amended. This px'oposed change bee been coacuxxed wS.th by the Si.t:e Operations Revtew Comndtgee end Safety Reviepz and. Audit: Beoz4.
Tke pxopoee8 Technical. Sgocif9.cat:ion. change is set forth in Attachment A cp thin applkeatioA. 8'uppox'tixlg XnÃoxmacS.oa, +M,cb demonstrates Chac t: he proposed change does not imroIve. a QigoiHcoot 4aw'ard8 ooneMex'et.'J.on, 9e set forth kn Attachment S. 'Axe propoeek change mcn~X8 not:
authorise. any change in the types: oe pay increaee 9n the amounts of off'keone9. or any change in the euthaxizocX p~er
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QHEREPORE, hppl,$ .can x'aepecg&alky gequegt6 thee Appendix A to Pec9.lity Opexatinp License No. DPI,>>63 be amended h the farm eteaat>ed hex'eto ae Ateacbmen A,.
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QPR-63'ocket No. 50-220 Pxoposed. Changes to Technical Speci&.ca@9.oas Aeeached are revisions Co Pages 6 and 53a of Appendix. A to DPR-63.
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The neutron flux shall not exceed its scram d, The reactor mter lm level scram trip.
setting for longer than 1.5 seconds as indicated setting shall be no lawe than 12 inches by the process computer, >lhen the process (53 inches indicator scale) relative tq ccmputer is out of service, a saf'eg limit the minimum novi ~ater level (X2'9"),
riolation shall be assmed if the neutron flux exc efs the scram setting and control rod e. The reactor mter lm1mr level setting for scram does noi occur. cor spray initiation shall be no less than -5 feet (5 inches indicator scale)
To ensure thai the Safety Limi. established relative to the minimum normal water level in Specifications 2.l.la and 2.1.]b is not glevation 308'9"}.
exceeded, each required scram shall be initiated by expec.H scram signal. The Safe.y limit shall '.s
- f. The Row biased APHR rod block trip settings be assumed to be exc~ded ~hen scrm~ is accom- shall be less than or equal to that shee plished by a means other than the ~aspect% in Figure 2.1,].
scram signai.
Nenever the. reactor is in the shutdee condition xi@ irradiated gael in the reactor vessel, the eater level shall not be more than 7 feet ll inches (127.1 inches indicator scale} below minimmi normal eater level (Elevation 302'9"), "c pt as specified in "e" helen For the purpose of performing major mainienanc8 (not to exceed 12 xe Rs in duration) on the rector vessel, the reactor water level Nay be leered the annum nodal water level (Elevation 9'elm 302'9"). 'Nenever the reactor pater level is Xo be lowered helen '.he lm-i~low level set point redundant instrumentation will be provided Zo monitor the reactor eater level.
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3URVHLutcK"RKPUBEÃNT For the purpose of perfoWng major maintenance (not to exceed 12 meks in duration) on the reactor vessel, the. reactor water level my be leered to g'elow the minimum normal water level {elevation 30K'9"). Mhenever the reactor water level is to be lerei 4 beiaw the le-law-law level set, point redundant instrumntation will be provided to monitor the reactor water level and written pro-c dures will be developed and folletad whenever the reactor water level is lawered below the low-lm level set point. The- procedures will define tne valves that all be used to lover the vessel eater level. Nl other valves, that have the poteniial of lowerin the vessel water level mll be identified by val ve number in the procedures and Nese- valves sill be red tagged to preclude their operation dur',ng the major mintenance with the wa er level belcw the law-.law level set point.
During the period of major maintenance requiring lowering the water level to mre than 7 fe 4 ll inches helm minirm normal eater level (127,1 inches indicator sca)e), either boih Core Spray 5ys.ems must be operable or, if one Core Spray Sys~ is inoporab'le because of the maintananc , all of the rdundani c~i nenes of the other Cor Spray System must be operable.
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NXAQABA Y>OHAHK POW08. CORPORA'EXON Lf.conic No. QPK'63 Docket Bo. 50-RRO Su oaten lnfoxmation Our submittal of Nay 9, 1977 requested e change which would allow 3.owerinp of the reactor vessel miter Revel belch the low-low-low level set: point. Thi.s mes required so that maintenance could be performed an the feedeater spax'gers nnd noaalee.
The maintenance work on the spaxsers and oozzles has been slowex than anti.cf.pated. Also, nrJditional woxk has been found to be necessary an the control roC dr;Lve hydraulic return line, Therefoxe, a chan8e in the dura-tion from 6 to 1R wrecks is necesonry.
Since the core decay heat peneretion. is constantly decreasing, the consequences of a LOCA, whi3.e in the shutdown condition w3.13. continue to be less sever@.
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