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Category:Technical Specifications
MONTHYEARML24128A2772024-06-0404 June 2024
Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary)
ML23341A0172024-01-12012 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*)
2024-06-04
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-3-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, Section 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 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.304 , are hereby incorporated in the renewed license.The licensee shall operate the facility in accordance with the Technical Specifications.
Renewed License No. DPR-65 Amendment No. 304 APPLICABILITY:
SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 Surveillance Requirements for inservice testing of ASME Code Class 1, 2 and 3 components shall be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) as follows: a. Deleted.b. Surveillance intervals specified in the ASME OM Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME OM Code and applicable Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually Biennially or every 2 years Required frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days At least once per 731 days c. The provisions of Specification 4.0.2 are applicable to the above required frequencies and to other normal and accelerated frequencies specified as 2 years or less in the inservice testing program for performing inservice testing activities.
- d. Performance of the above inservice testing activities shall be in addition to other specified Surveillance Requirements.
- e. Nothing in the ASME OM Code shall be construed to supersede the requirements of any Technical Specification.
- f. The provisions of Specification 4.0.3 are applicable to inservice testing activities.
MILLSTONE
-UNIT 2 3/4 0-3 Amendment No. 6-2, 0, 4-64-, -152, 2-3-0, 24-1-, 27-1-, 304 PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only if their failure or failure of the system on whichthey are installed would have no adverse effect on any safety-related system.APPLICABILITY:
MODES 1, 2, 3, and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.ACTION: With one or more snubbers inoperable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8.d on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for the system.SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of the Inservice Inspection Program.a. Inspection Types As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.b. Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-3. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-3 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 160.c. Visual Inspection Acceptance Criteria Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type MILLSTONE
-UNIT 2 3/4 7-21 Amendment No. 44, 4-1, 52, 96, 44-8, 4-6W,304
