Letter Sequence Request |
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MONTHYEARML0602502612006-01-26026 January 2006
Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call
Project stage: Draft RAI
ML0602700882006-01-31031 January 2006
Facsimile Transmission Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call (Tac No. MC8327)
Project stage: Draft RAI
ML0604005082006-03-0202 March 2006
Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call
Project stage: Draft RAI
ML0620005092006-07-25025 July 2006
Request for Withholding Information from Public Disclosure for Stone and Webster
Project stage: Withholding Request Acceptance
ML0626404642006-09-15015 September 2006
Technical Specification, Incorporate a Full-Scope Application of an Alternate Source Term Methodology
Project stage: Request
ML0622201602006-09-20020 September 2006
Issuance of Amendment Recirculation Spray System
Project stage: Approval
ML0626404622006-09-20020 September 2006
Technical Specification, Revise Surveillance Requirements for Recirculation Spray System
Project stage: Other
2006-03-02
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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
[Table view] |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3.7-3 STEAM LINE SAFETY VALVES PER LOOP ................................... 3/4 7-3 Auxiliary Feedwater System ................................................................ 3/4 7-4 Demineralized Water Storage Tank ....................................................... 3/4 7-6 Specific A ctivity .................................................................................... 3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM ................... 3/4 7-8 Main Steam Line Isolation Valves ........................................................ 3/4 7-9 Steam Generator Atmospheric Relief Bypass Lines ............................. 3/4 7-9a 3/4.7.2 DELETED ............................................................................................. 3/4 7-10 3/4.7.3 REACTOR PLANT COMPONENT COOLING WATER SYSTEM ..3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM ........................... 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK ...................................................................... 3/4 7-13 3/4.7.6 D ELETED ............................................................................................. 3/4 7-14 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM ......... 3/4 7-15 3/4.7.8 DELETED ............................................................................................. 3/4 7-18 3/4.7.9 AUXILIARY BUILDING FILTER SYSTEM ..................................... 3/4 7-20 3/4.7.10 SN UBBERS .......................................................................................... 3/4 7-22 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL ................................ 3/4 7-27 FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST .............. 3/4 7-29 3/4.7.11 DELETED ............................................................................................. 3/4 7-30 3/4.7.12 DELETED TABLE 3.7-4 DELETED TABLE 3.7-5 DELETED 3/4.7.13 DELETED 3/4.7.14 AREA TEMPERATURE MONITORING ........................................... 3/4 7-32 TABLE 3.7-6 AREA TEMPERATURE MONITORING ........................................... 3/4 7-33 MILLSTONE - UNIT 3 x Amendment No. 6-2, 84, 400, 4-60, 244, 232
INDEX BASES SECTION PAGE TABLE B 3/4.4-1 REACTOR VESSEL FRACTURE TOUGHNESS PROPERTIES .... B 3/4 4-9 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>IMeV) AS A FUNCTION OF FULL POWER SERVICE LIFE ......................................................... B 3/4 4-10 3/4.4.10 DELETED ................................................................................................... B 3/4 4-15 3/4.4.11 DELETED ................................................................................................... B 3/4 4-15 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUM ULATORS ..................................................................................... B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS ........................................................................ B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK .................................................. B 3/4 5-2 3/4.5.5 pH TRISODIUM PHOSPHATE STORAGE BASKETS ............................ B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT ..................................................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ............................... B 3/4 6-2 3/4.6.3 CONTAINMENT ISOLATION VALVES ................................................... B 3/4 6-3 3/4.6.4 DELETED 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM ........................ B 3/4 6-3d 3/4.6.6 SECONDARY CONTAINMENT ............................................................... B 3/4 6-4
'1/4-7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE ...................................................................................... B 3/4 7-1 3/4.7.2 DELETED .............................. .............................. B 3/4 7-7 3/4.7.3 REACTOR PLANT COMPONENT COOLING WATER SYSTEM ........ B 3/4 7-7 3/4.7.4 SERVICE WATER SYSTEM ...................................................................... B 3/4 7-7 3/4.7.5 ULTIMATE HEAT SINK ............................................................................ B 3/4 7-8 3/4.7.6 DELETED ................................................................................................... B 3/4 7-10 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM ............... B 3/1 7-10 3/4.7.8 DELETED ................................................................................................... B 3/4 7-17 I 3/4.7.9 AUXILIARY BUILDING FILTER SYSTEM ............................................ B 3/4 7-23 3/4.7.10 SNUBBERS ................................................................................................. B 3/4 7-23 MILLSTONE - UNIT 3 xiv Amendment No. 49, 89,44-5,449, 4-36, 2"M, *-26,244,24-6, 224, 232
DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
- a. All penetrations required to be closed during accident conditions are either:
- 1. Capable of being closed by an OPERABLE containment automatic isolation valve system*, or
- 2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are opened under administrative control as permitted by Specification 3.6.3.
- b. All equipment hatches are closed and sealed,
- c. Each air lock is in compliance with the requirements of Specification 3.6.1.3,
- d. The containment leakage rates are within the limits of the Containment Leakage Rate Testing Program, and
- e. The sealing mechanism associated with each penetration (e.g., welds, bellows, or O-rings) is OPERABLE.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATIONS 1.9 CORE ALTERATIONS shall be the movement of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
DOSE EOUIVALENT 1-131 1.10 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same CDE-thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed under "Inhalation" in Federal Guidance Report No. 11 (FGR 11),
"Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion."
- In MODE 4, the requirement for an OPERABLE containment isolation valve system is satisfied by use of the containment isolation actuation pushbuttons.
MILLSTONE - UNIT 3 1-2 Amendment No. 2-, -44, 4-6, 246, 232
THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 7-18 Amendment No. 48+-, 20a3, 2-9, 232
THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 7-19 Amendment No. 4243, 24, 206, 232
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- 2) Pre-planned operating procedures and backup instrumentation to be used if one or more monitoring instruments become inoperable, and
- 3) Administrative procedures for returning inoperable instruments to OPERABLE status as soon as practicable.
- f. Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testingof the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions*. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 38.57 psig.
The maximum allowable containment leakage rate La, at Pa, shall be 0.3 percent by weight of the containment air per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
Leakage rate acceptance criteria are:
- 1) Containment overall leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the combined Type B and Type C tests, and <0.06 La for all penetrations that are Secondary Containment bypass leakage paths, and < 0.75 La for Type A tests;
- 2) Air lock testing acceptance criteria are:
- a. Overall air lock leakage rate is
- 0.05 La when tested at 2!Pa"
- b. For each door, seal leakage rate is < 0.01 La when pressurized to
> Pa The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
- An exemption to Appendix J, Option A, paragraph III.D.2(b)(ii), of 10 CFR Part 50, as approved by the NRC on December 6, 1985.
MILLSTONE - UNIT 3 6-17 Amendment No. 69, -86,
