ML17037C416
ML17037C416 | |
Person / Time | |
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Site: | Nine Mile Point |
Issue date: | 07/14/1977 |
From: | Rhode G K Niagara Mohawk Power Corp |
To: | Office of Nuclear Reactor Regulation |
References | |
Download: ML17037C416 (12) | |
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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0720504232007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process 2024-07-31 Category:Amendment MONTHYEARML24103A2042024-04-12012 April 2024
[Table view]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 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 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 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-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018 Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 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 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 NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0536202882005-12-16016 December 2005 License Amendment Request: Proposed Changes to Technical Specification 4.1.4 Regarding Core Spray Instrumentation ML0511100732005-04-19019 April 2005 Tech Spec Pages for Amendment 115 and 188 Reporting Requirements for Annual Radiological Environmental Operating Report ML0510204002005-04-0101 April 2005 License Amendment Request Pursuant to 1O CFR 50.90: Request for Amendment to Extend Completion Time for Emergency Uninterruptible Power Supply Inverters ML0503304712005-01-24024 January 2005 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports ML0424003162004-08-17017 August 2004 Unit I, License Amendment Request Pursuant to 10 CFR 50.90: Addition of 24 Hours for Restoration of Primary Containment Oxygen Concentration ML0421103812004-07-16016 July 2004 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Intermediate Range Monitor Surveillance Frequency and Relocation of Selected Instrumentation Requirements to a License-Controlled Document ML0403302112004-01-27027 January 2004 TS Amendment Pages for License No. NPF-069 ML0330305992003-10-27027 October 2003 TS Pages Amendment 183 ML0324608472003-08-15015 August 2003 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Reactor Pressure Vessel Pressure-Temperature Limits ML0233807302002-11-22022 November 2002 Facility Operating License DPR-63, License Amendment Request: Technical Specifications Section 6.0, Administrative Controls - Response to RA Information TAC No. MB2441 ML0229603382002-10-0707 October 2002 Application for Technical Specification Change Regarding Missed Surveillances Using the Consolidated Line Item Improvement Process ML0217101682002-06-0707 June 2002 Application for Technical Specification Improvement to Eliminate the Requirements for the Post Accident Sampling System Using the Consolidated Line Item Improvement Process ML0207305992002-03-13013 March 2002 Technical Specifications, Issuance of Amendment Safety Limit Minimum Critical Power Ratio (Tac No. MB3327) ML0206302682002-03-0101 March 2002 Technical Specifications for Amendment No. 103 ML0204301512002-02-11011 February 2002 Issuance of Amendment Ventilation Requirements During Irradiated Fuel Handling ML18018B0461978-03-22022 March 1978 Letter Transmitting an Application for Amendment to Appendix a of the Operating License ML17037C4331977-08-0808 August 1977 Letter Regarding Surveillance Requirements and Limiting Conditions for Operations and Requesting an Application for Amendment to the Operating License That Will Change the Technical Specifications ML17037C4131977-07-22022 July 1977 Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization ML17037C4141977-07-18018 July 1977 Letter Enclosing an Application for Amendment to Operating License and Proposed Changes to the Technical Specifications to Provide for More Flexible Operation and Concerning Load Line Limit Analysis ML17037C4161977-07-14014 July 1977 Application for Amendment to Operating License and Proposed Change to Technical Specification Concerning the Emergency Cooling System ML17037C4181977-05-19019 May 1977 Letter Enclosing an Application to Amend Operating License and a Requested Change in the Technical Specifications Relating to Instrumentation Used to Monitor Drywell Suppression Chamber Differential Pressure and Suppression .. ML17037C4341977-03-0404 March 1977 Letter Regarding a Preliminary Review of the December 7, 1976 Request for Technical Specification Changes to Reactor Operating Limits After Reload for Cycle 5 Operation and Requesting Additional Information to Complete Review ML17037C4391976-09-30030 September 1976 Letter Requesting Submittal of an Application for License Amendment to Incorporate the Requirements of the Model Technical Specifications ML17037C4531976-01-19019 January 1976 Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications (Appendix a) to Clarify Cloride and Oxygen Levels ML17037C1771975-12-19019 December 1975 Letter Enclosing a Corrected Attachment to License Amendment No. 11 Change No. 27 to the Technical Specifications Provisional Operating License No. DPR-16 ML17037C1831975-11-0303 November 1975 Letter Regarding Application for Amendment to Technical Specifications and an Inadvertent Error Not Made on the Persons Listed in the Certificate of Service ML17037C4681975-09-23023 September 1975 Letter Regarding a Stress Assisted Corrosion Problem and an Enclosed Safety Evaluation by the Office of NRR - Supporting Amendment to License No. DPR-63 and Changes to the Technical Specifications Inoperable Control Rod .. 2024-04-12 |
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U.S.NUCLEAR REGULATORY MISSION'NRC FORM+195 , (2-76)C NRC DISTRIBUTION FQR PART 60 DOCKET MATERIAL DOCKET NUMBER FILE NUMBER TO: I No Ro Co P5 ETTER%ORIGINAL CI COPY QkNOTO R I Z E D JRUNCLASSIFIED FROM: Niagara Mohowk Power Corp, Syracuse, New York Gerald Ki Rhode PROP INPUT FORM DATE OF DOCUMENT not dated DATE REf)IMP NUMBER OF COPIES RECEIVED s t aeHu po+g op l~msmr7/wZ lID0ÃOT REMOVE/Imtfggg~@
ENCLOSURE License No.DPR-63'Appl for Amend: tech specs proposed change concerning the Emergency Cooling Systemi~inotorized 7/14/77~~~~~(5-P)..PLANT NAME: Nine Mile Point Unit No, 1 RJL 7/18/77 FOR ACTION/INFORMATION ENVIRHNMENTAL ECT MANAGER: CENSING ASSXSTANT:
ASSIGNED AD: V MOORE LTR BRANCH CHIEF: PROJECT MANAGER: LICENSING ASSISTANT:
Bi HARLESS INTERNAL DISTRIBUTION
~TFMS SAFETY HEIN&IAN EDER ENGINEERING PLANT SYSTEMS TEDESCO BENAROYA IPPOLITO OPERATING REACTORS SITE SAFETY&ENVIRON ANALYSIS DENTON Bi MULLER ENVIRO TECH ERNST BALLARD 0 G BLOOD Z)CZY CHECK AT I ALTZMAN TBERG EXTERNAL DISTRIBUTION BAER BUTLER.GRIME GAMMILL 2 SITE ANALYSIS VOLQIER BUNCH Ji COLLINS KREGER CONTROL NUMBER TIC REG IV J HANCHETT 16 CYS ACRS SENT CAT GO NRC FORM 196 (2.76)iVSIC 77i9902O8,
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of)))NIAGARA MOHAWK POWER CORPORATION
)(Nine Mile Point Nuclear Station)Unit No.1))Docket No.50-220.Re ato APPLICATION FOR AMENDMENT TO QQX~~o&~C~OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Cor-poration, holder of Faci,lity Operating License No.DPR-63, hereby requests that Secti.ons 3.1.3 and 4.1.3 of the Technic'al Specifications set forth in Appendix A to that License be amended.Thes'e'proposed changes have been concurred with by the.'Site Operations Review Committee and the Safety Revi.ew and Audi,t Board.The proposed Techni,cal Specification changes are set forth in Attachment A to this appli,cation.
Supporting Information, which'demonstrates that the proposed changes do not involve a significant hazards consideration, is set forth in Attachment B.The proposed changes would not authorize any change in the types or any increase in the amounts of effluents or any change i.n the authorized power level of the f"cility.771990208 I 4 WHEREFORE, Applicant respectfully requests that'ppendix A to Facility Operating License No.DPR-63 be amended in the form attached hereto as Attachment A.NIAGARA MOHAWK POWER CORPORATION By Gexald K.Rhode Vice President-Engineering Subscribed apd sworn to befoxe me this/4N~day of July, 1977.CPi NOTARY PUBLTC t'llYLLIS D.VQYTKOtery Public ln the Qt~te of New Yorg.uetitied in Onon, Co, No, 34 548553+~'4v Cnmmieetnrr Evotree t4erch 30, 19~
~5 ATTACHMENT A Niagara Mohawk Power Corporation License No.DPR-63 Docket No.50-220~Pro osed Chan'e'o'echn'ica1 S e'cification Attached are revised Pages 47 and 48.
~4 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT EMiERGENCY COOLING SYSTEM 4.1.3 EMERGENCY COOLING SYSTEM~iii i iii: i App1 i es to the operating status of the emergency cooling system.iiiii Applies to periodic testing requirements for the emergency cooling system.Ob ective: To assure the capability, of the emergency cooling system to cool the reactor coolant in the event the normal reactor heat sink is not available.
Ob ective: To assure he capability of the emergency cooling system for cooling of the reactor coolant.S ecification:
a.During power operating conditions and whenever the reactor coolant temperature is greater than 212F, both emergency cooling systems shall be operable except as specified in 3.1.3.b and c.b.During Cycle 5, with one emergency cooling system inoperable, Specification 3.1.3.a shall be con-sidered fulfilled, provided the additional surveillance required is performed.
S ecification:
a~At least once ever five vears-The system heat removal capability shall be determined.
b.At least once dail The shell side water level and mak tank plater level.shall be checked.The emergency cooling system surveillance shall be performed as indicated.
below: c~During Cycle 6 and subsequent cycles'f one emergency cooling system becomes inoperable, Specification 3.1.3.a shall be considered fulfilled, pr'ovided that the inoperable system is returned to an operable condition within 7 days and the additional surveillance required is performed.
C.At 1 east once r month-The makeup tank level control valv shall be manually opened and close 47
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT Makeup water shall be available from the two gravity feed makeup water tanks.If Specifications 3.1.3a, b, c or d are not met, a normal orderly shutdown shall be initiated within one hour and the reactor shall be in the cold shutdown condition within ten hours.d.At least once each shift-The area temperature shall be checked.e.During each major refuelin outa e-Automatic actuation and functional system testing shall be performed during each major refueling outage and whenever major repairs are completed on the system.Surveillance with an Ino erable S stem During Cycle 5 with one of the emergency cooling systems inoperable, the level control valve and the motor-operated isolation valve in the operable system shall be demonstrated to be operable immediately and weekly thereafter.
During Cycle 6 and subsequent cycles,<shen one of the emergency cooling systems is inoperable, the level control valve and the motor-operated isolation valve in the operable system shall be demonstrated to be operable immediately and daily thereafter.
48 5~W