Letter Sequence Other |
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MONTHYEARML0701704532007-01-0404 January 2007
License Amendment Request Pursuant to 10 CFR 50.90: Revision of Service Water and Ultimate Heat Sink Temperature Requirements - Technical Specification 3.7.1
Project stage: Request
ML0708500462007-03-29029 March 2007
RAI, Revision to Service Water System and Ultimate Heat Sink Temperature Requirements
Project stage: RAI
ML0712805172007-04-27027 April 2007
License Amendment Request Pursuant to 10 CFR 50.90: Revision of Service Water and Ultimate Heat Sink Temperature Requirements - Technical Specification 3.7.1 - Response to NRC Request for Additional Information
Project stage: Response to RAI
ML0715000632007-05-22022 May 2007
License Amendment Request: Revision of Service Water and Ultimate Heat Sink Temperature Requirements - Technical Specification 3.7.1 - Supplemental Information in Response to NRC Request for Additional Information
Project stage: Supplement
ML0721300202007-07-23023 July 2007
License Amendment Request Pursuant to 10 CFR 50.90: Revision of Service Water and Ultimate Heat Sink Temperature Requirements - Technical Specification 3.7.1 - Supplemental Information in Response to NRC Request For.
Project stage: Supplement
ML0724802572007-09-0404 September 2007
Tech Spec Pages for Amendment 119, Technical Specification 3.7.1 Regarding Ultimate Heat Sink Temperature Limits
Project stage: Other
ML0717700812007-09-0404 September 2007
Issuance of Amendment 119, Technical Specification 3.7.1 Regarding Ultimate Heat Sink Temperature Limits
Project stage: Approval
2007-04-27
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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 Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022
Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va
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
[Table view] |
Text
-4-(1) Maximum Power Level Nine Mile Point Nuclear Station, LLC, is authorized to operate the facility at reactor core power levels not in excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 119 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.(3) Fuel Storage and Handling (Section 9.1, SSER 4)*a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.(4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER)The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.(Submitted by NMPC letter dated October 30, 1989, from C.D. Terry and approved by NRC letter dated March 15, 1990, from Robert Martin to Mr. Lawrence Burkhardt, Ill).The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-69 Amrh.t N:). 119 SW System and UHS 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Service Water (SW) System and Ultimate Heat Sink (UHS)LCO 3.7.1 a. Division 1 and 2 SW subsystems and UHS shall be OPERABLE.I AND b.1 Four OPERABLE SW pumps shall be in operation when water temperature of one or two SW subsystem supply headers is < 82°F.OR b.2 Five OPERABLE SW pumps shall be in operation when water temperature of one or two SW subsystem supply headers is > 82°F and < 84 0 F.APPLICABILITY:
MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SW supply header A. 1 Open the SW supply 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cross connect valve header cross connect inoperable, valve.AND A.2 Restore the SW supply 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> header. cross connect valve to OPERABLE status.'B. One or more non-safety B.1 Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> related SW flow paths non-safety related SW with one SW isolation flow path(s).valve inoperable.
C. One SW subsystem C.1 Restore SW subsystem 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable for reasons to OPERABLE status.other than Conditions A and 0. d B (continued)
Amendment 04, 119 NMP2 3.7.1-1 SW System and UHS 3.7.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. One division of intake D.1 Restore intake deicer 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> deicer heaters heater division to inoperable.
OPERABLE status.E. One required SW pump E.1 Restore required SW 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> not in operation.
pump to operation.
F. Two or more required F.1 Restore all but one 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SW pumps not in required SW pump to operation.
operation.
G. Required Action and -----NOTE.associated Completion Enter applicable Conditions Time of Condition A, and Required Actions of B, C, D, E, or F not LCO 3.4.9, "Residual Heat met. Removal (RHR) Shutdown Cooling System -Hot OR Shutdown," for RHR Shutdown Cooling subsystem(s) made Both SW subsystems inoperable by SW System or inoperable for reasons UHS.other than Conditions A, B, and C. G.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR AND UHS inoperable G.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for reasons other than Condition D.I I I I NMP2 3.7.1-2 Amendment 94,-113, 119 SW System and UHS.3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 NOTE Not required to be met if SR 3.7.1.5 and SR 3.7.1.8 satisfied.
Verify the water temperature of the intake 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> tunnels is _ 38 0 F.SR 3.7.1.2 Verify the water level in the SW pump 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> intake bay is -a 233.1 ft.SR 3.7.1.3 Verify the water temperature bf 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> each SW subsystem supply header is 840F.AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when supply header water temperature is>_ 78 0 F SR 3.7.1.4 Verify each required SW pump is in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operation.(continued)
I I NMP2 3.7.1-3 Amendment 94, 119
