Letter Sequence Other |
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MONTHYEARML0703306122007-01-31031 January 2007
Technical Specifications, Increase the Allowed Outage Time from 72 Hours to 7 Days for the Inoperability of the Steam Supply to the Turbine-Driven AFW Pump or the Inoperability of the Turbine-Driven AFW
Project stage: Other
ML0703105522007-01-31031 January 2007
Issuance of Amendment Auxiliary Feedwater System Allowed Outage Time
Project stage: Approval
2007-01-31
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Category:Technical Specifications
MONTHYEARML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23072A0892023-05-0101 May 2023
(Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements
ML21280A3282021-10-0707 October 2021
Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
ML20275A0002020-10-14014 October 2020
Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections
ML20237H9952020-09-29029 September 2020
Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program
ML20261H5982020-09-17017 September 2020
Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20191A0042020-08-0707 August 2020
Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity
ML19126A0002019-05-28028 May 2019
Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage
ML19042A2772019-03-21021 March 2019
Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels
ML18100A0552018-04-0404 April 2018
License Amendment Request to Revise Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels
ML17038A0062017-02-0101 February 2017
Technical Specifications 2016 Annual Report
ML17025A2182017-01-24024 January 2017
Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis
ML16354A4242016-12-14014 December 2016
License Amendment Request to Revise Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 for the Remainder of Cycle 24
ML16208A0512016-07-26026 July 2016
Clean Technical Specifications (TS) Pages for Millstone Power Station 1 (Docket No. 05000245), Administrative Changes for TS (L53121)
ML16068A3122016-03-31031 March 2016
Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing
ML16011A4002016-01-29029 January 2016
Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
ML15288A0042015-11-30030 November 2015
Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times
ML15280A2422015-10-29029 October 2015
Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3
ML15245A4822015-10-0707 October 2015
Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses
ML15225A0102015-08-28028 August 2015
Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves
ML15225A0082015-08-26026 August 2015
Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds
ML15187A3262015-07-29029 July 2015
Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C
ML15187A1862015-07-28028 July 2015
Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692)
ML15187A0112015-07-27027 July 2015
Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures
ML15209A7292015-07-21021 July 2015
Response to Second Request for Additional Information Regarding Proposed Technical Specification Change for Spent Fuel Storage
ML15098A0342015-05-20020 May 2015
Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15093A0022015-05-20020 May 2015
Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15093A4412015-05-18018 May 2015
Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies
ML15044A0442015-02-0909 February 2015
Revised Response to Request for Additional Information Regarding License Amendment Request for Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures
ML15021A1282015-01-15015 January 2015
Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
ML14301A1122014-10-22022 October 2014
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3
ML14154A0912014-05-28028 May 2014
Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink.
ML14073A0552014-04-0808 April 2014
Issuance of Amendment Calculated Containment Internal Pressure
ML13346A7672013-12-18018 December 2013
Correction Letter to License Amendment Nos. 256 and 257
ML13155A1402013-05-28028 May 2013
Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage
ML13133A0322013-05-0303 May 2013
License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink.
ML13133A0332013-05-0303 May 2013
License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink.
ML12284A2132012-10-0404 October 2012
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3
ML12250A6642012-08-28028 August 2012
Correction to Proposed Technical Specifications to Adopt TSTF-510
ML12220A0122012-07-31031 July 2012
Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
ML12219A0732012-07-31031 July 2012
Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
ML12202A0402012-07-17017 July 2012
License Amendment Request Regarding Removal of a License Condition, Proposed Technical Specifications Bases Change and FSAR Change for Ultimate Heat Sink Temperature Measurement
ML12110A1142012-04-12012 April 2012
License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair
ML12097A2002012-04-0202 April 2012
License Amendment Request to Revise Snubber Surveillance Requirements
ML12032A2242012-01-25025 January 2012
License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3
ML11329A0032011-11-17017 November 2011
Proposed License Amendment and Exemption Request for Use of Optimized Zirlo Rod Cladding
ML11193A2242011-07-0505 July 2011
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages
ML11193A2232011-07-0505 July 2011
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 1 Through Attachment 3, Marked-up TS Page Changes 3/4 6-22
ML1102802082011-01-20020 January 2011
License Amendment Request to Revise Technical Specification (TS) 6.8.4.g, Steam Generator (SG) Program, and TS 6.9.1.7, Steam Generator Tube Inspection Report for Temporary Alternate Repair Criteria (H*)
ML1022400642010-07-21021 July 2010
License Amendment Request to Revise Technical Specification 3/4.9.3.1, Decay Time
2024-01-12
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Text
Connecticut, in accordance with the procedures and limitations set forth in this renewed operating license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (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 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and 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 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 2700 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2 9 7 , are hereby incorporated in the renewed license.
The licensee shall operate the facility in accordance with the Technical Specifications.
Renewed License No. DPR-65
PLANT SYSTEMS AUXILIARY FEEDWATER PUMPS LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three steam generator auxiliary feedwater pumps shall be OPERABLE with:
- a. Two feedwater pumps capable of being powered from separate OPERABLE emergency busses, and
- b. One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
Inoperable Equipment Required ACTION I
- a. Turbine-driven auxiliary feedwater pump due to one steam supply being inoperable.
- a. Restore affected equipment to OPERABLE status within 7 days. If these ACTIONS are not met, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT I
SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. b. Restore affected equipment to OPERABLE status within 7 days. If these ACTIONS are not met, be in at least
NOTE - -- - HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Only applicable if MODE 2 has not been entered following REFUELING One turbine-driven auxiliary feedwater pump in MODE 3 following REFUELING
- c. One auxiliary feedwater pump c. Restore the auxiliary feedwater pump to OPERABLE in MODE 1, 2, or 3 for reasons status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If these ACTIONS are not met, other than a. or b. above, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- d. Two auxiliary feedwater d. Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in pumps in MODE 1, 2, or 3. HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MILLSTONE - UNIT 2 3/4 7-4 Amendment No. 64, 6, 90, 44-, -236, 297
PLANT SYSTEMS AUXILIARY FEEDWATER PUMPS LIMITING CONDITION FOR OPERATION ACTION: (Continued)
Inoperable Equipment Required ACTION
- e. Three auxiliary feedwater e.
pumps in MODE 1, 2, or 3.
- - - - - -- NOTE LCO 3.0.3 and all other LCO required ACTIONS requiring MODE changes are suspended until one AFW pump is restored to OPERABLE status.
Immediately initiate ACTION to restore one auxiliary feedwater pump to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying each auxiliary feedwater manual, power operated, and automatic valve in each water flow path and in each steam supply flow path to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.
- b. By verifying the developed head of each auxiliary feedwater pump at the flow test point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5. (Not required to be performed for the steam turbine driven auxiliary feedwater pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 800 psig in the steam generators. The provisions of Specification 4.0.4 are not applicable to the steam turbine driven auxiliary feedwater pump for entry into MODE 3.)
MILLSTONE - UNIT 2 3/4 7-5 Amendment No. *--, 6-3, 28Z, 2 9 7
PLANT SYSTEMS AUXILIARY FEEDWATER PUMPS SURVEILLANCE REQUIREMENTS (Continued)
- c. At least once per 18 months by verifying each auxiliary feedwater automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position, as designed, on an actual or simulated actuation signal.
- d. At least once per 18 months by verifying each auxiliary feedwater pump starts automatically, as designed, on an actual or simulated actuation signal.
- e. By verifying the proper alignment of the required auxiliary feedwater flow paths by verifying flow from the condensate storage tank to each steam generator prior to entering MODE 2 whenever the unit has been in MODE 5, MODE 6, or defueled for a cumulative period of greater than 30 days.
MILLSTONE - UNIT 2 3/4 7-5a Amendment No. 297 1
