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MONTHYEARML0809801352008-04-0808 April 2008 Request for Additional Information Regarding Operability Requirements for Reactor Coolant System Isolation Valves Project stage: RAI ML0816403172008-06-0505 June 2008 Transmittal of Supplemental Information Request Project stage: Supplement ML0824203962008-08-27027 August 2008 Technical Specifications, Issuance of Amendment Revised Operability Requirements for Reactor Coolant System Isolation Valves Project stage: Approval ML0822503472008-08-27027 August 2008 Issuance of Amendment Revised Operability Requirements for Reactor Coolant System Isolation Valves Project stage: Approval 2008-06-05
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Category:Technical Specifications
MONTHYEARML23289A0122023-12-0606 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 ML0919504152009-07-0202 July 2009 License Amendment Request to Remove Position Indication for Relief Valves and Safety Valves from Technical Specifications ML0905605222009-02-11011 February 2009 Units, 1 & 2, License Amendment Request for Adoption of TSTF-511-A Rev. 0 Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. 2023-08-30
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-3-(3) Pursuant to the Act and 10 CFR Parts -30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;(4) Pursuant to the Act and 10. CFR Parts 30, 40 and.70, to receive, possess.and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components.
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below: (1) Maximum Power Level.The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 197, is hereby incorporated into this license..
Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications.
(3) Deleted eRdnt wd LiNns, NEo. DPR 63 Amendment No. 191, 192, 193, 194, 1 95, 197 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES 4.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES Applicability:
Applies to the operating status of the system of isolation valves on lines connected to the reactor.coolant system.Objective:
To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear steam supply system, and to minimize potential leakage paths from the primary containment in the event of a loss-of-coolant accident.Specification:
- a. Whenever fuel is in the reactor vessel and the reactor coolant temperature is greater than 212 0 F, all reactor coolant system isolation valves on lines connected to the reactor coolant system shall be operable except as specified in Specification 3.2.7.b below.b. In the event any isolation valve becomes inoperable whenever fuel is in the reactor vessel and the reactor coolant temperature is greater than 2-12'F, the system shall be considered operable;provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one valve in each line having an inoperable valve is in the mode corresponding to the isolated condition, except as noted in Specification 3.1.1.e.Applicability:
Applies to the periodic testing requirement for the reactor coolant system isolation valves.Obiective:
To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the.event of a rupture of a line connected to the. nuclear steam supply system, and to limit potential leakage paths from the primary containment in the event ofa, : loss-of-coolant accident.Specification:
The reactor coolant system isolation valves surveillance shall be performed as indicated below..a.. At least once per operating cycle the operable:, automatically initiated power-operated isolation valves shall be tested for automatic initiation and closure times.b. Additional surveillances shall be performed as required by. Specification 6.5.4.AMENDMENT NO.142145, 17-374-84.
197 108 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT
- c. If Specifications 3.2.7a and b above are not met, initiate normal orderly shutdown within one hour and have reactor in the cold shutdown condition within ten hours.d. Whenever fuel is in the reactor vessel and the reactor coolant temperature is less.than or equal to 2.12 0 F, the isolation valves on the shutdown cooling system lines connected to the reactor coolant system shall be operable except as specified in Specification 3.2.7.e below.e. In the event any shutdown cooling system isolation valve becomes inoperable whenever fuel is. in the reactor vessel and the reactor coolant temperature is less than or equal to 212'F, the system shall be considered operable provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, at least one valve in each line having an inoperable valve is in the mode. corresponding to the isolated condition.
- f. If Specifications 3.2.7.d and 3.2.7.e above are not met, either:.(1) Immediately initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs);
or (2) Immediately initiate action to restore the valve(s)to operable status.c. At least once per quarter the feedwater and main-steam line power-operated isolation valves shall be exercised.by partial closure and* subsequent reopening.
- d. At least once per plant cold shutdown the feedwater and main steam line power-operated isolation valves shall be fully closed and* reopened, unless this test has been performed within the previous.92 days..AMENDMENT NO. -142. 197 109 TABLE 3.6.2b INSTRUMENTATION THAT INITIATES PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Limiting Condition for Operation Minimum No. of Operable Instrument Minimum No. Channels per of Tripped or Operable Operable Trip Systems Trip System Set Point Reactor Mode Switch Position in Which Function Must Be Operable'Parameter 0 co"=C,, 41 0.C Cu 4-'U) ~PRIMARY COOLANT ISOLATION (Main Steam, Cleanup, and Shutdown Cooling)(1) Low-Low Reactor Water Level (a) Main Steam and Cleanup 2 (b) Shutdown Cooling 2(j)2()2(00)> 5 inches (Indicator Scale)*5 inches (Indicator Scale)(i) x x x x x x (2) Manual MAIN-STEAM-LINE ISOLATION (3) High Steam Flow Main-Steam Line 2 1 x x x X 2 2(f)< 105 psid x x AMENDMENT NO. 4-42, 197 205 TABLE 3.6.2b (cont'd)INSTRUMENTATION THAT INITIATES, PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Limitina Condition for Operation Minimum No.of Tripped or Operable Trip Systems Minimum No. of Operable Instrument Channels per Operable Trip System Reactor Mode Switch Position in Which Function Must Be Operable Parameter Set Point C-(I)0..1~Co CLEANUP SYSTEM ISOLATION (8) High Area Temperature SHUTDOWN COOLING SYSTEM ISOLATION (9) High Area Temperature CONTAINMENT ISOLATION 1 2(g)< 190OF.(i)x X,-.,.1 1<- 170°F (i)x x (10) Low-Low Reactor Water*2 2(f)> 5 inches (Indicator Scale)(c)x x AMENDMENT NO. 1.42, 197 207 TABLE 4.6.2b INSTRUMENTATION THAT INITIATES PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Surveillance Requirement Parameter Sensor Check Instrument Channel Test Instrument Channel Calibration PRIMARY COOLANT ISOLATION (Main Steam, Cleanup and Shutdown Cooling)(1) Low-Low Reactor Water Level Once/day Once per 3 months(d)Once during each major refueling outage Once per 3 months(d)(2) Manual MAIN-STEAM-LINE ISOLATION (3) High Steam Flow Main-Steam Line Once/day Once per.3 rnonths 4 a)Once per 3 months(d)(4) Deleted (5) Low Reactor Pressure Once/day Once per 3 months(d)Once per 3 months(d)AMENDMENT NO. 142-4, 197 209 NOTES FOR TABLES 3.6.2b and 4.6.2b (g). A channel may be placed in an inoperable status forup to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillances without placing the Trip System in tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that Parameter:
With the number of Operable channels one less than required by the Minimum Number of Operable Instrument Channels for the Operable.
Trip System, either 1 Place the inoperable channel(s) in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..or 2. Take the ACTION required by Specification 3.6.2a for that Parameter.(h) Only applicable during startup mode while operating in IRM range 10.(i) May be bypassed in the cold shutdown condition.(j) In the cold shutdown and refueling conditions, only one Operable Trip System is required provided shutdown cooling system integrity is maintained.
With one of the two required Operable Channels in the required Trip System not operable, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Otherwise,.
either: 1. Immediately initiate action to restore the channel to operable status.or 2. Immediately initiate action to isolate the shutdown cooling system.AMENDMENT NO. 142_183, 197 213