Letter Sequence Other |
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MONTHYEARML0635401942006-12-20020 December 2006
Updated List of Documents Describing the Approved Analytical Methods Used to Determine Core Operating Limits
Project stage: Other
ML0702500182007-01-23023 January 2007
Technical Specification Updated List of Documents Describing Approved Analytical Methods Used to Determine Core Operating Limits
Project stage: Other
ML0634805362007-01-23023 January 2007
License Amendment, Updated List of Documents Describing Approved Analytical Methods Used to Determine Core Operating Limits
Project stage: Other
2006-12-20
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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 ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1 R O U TIN E R EPO RT S ...............................................................................................
6-16 STA RTU P REPO RTS ...............................................................................................
6-16 ANNUAL REPORTS .........................................
6-17 ANNUAL RADIOLOGICAL REPORT ....................................................................
6-18 CORE OPERATING LIMITS REPORT ...............................................................
6-18a 6.9.2 SPE C IA L REPO RT S ................................................................................................
6-20 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM ............................
6-20 6.12 HIG H RA D IATION AREA .........................................................................................
6-20a 6.13 SYSTEMS INTEGRITY
........................................
6-23 6.14 IO D IN E M O N ITO RIN G .............................................................................................
6-23 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)...
.............................................
6-24 6.16 RADIOACTIVE WASTE TREATMENT
....................................................................
6-24 6.17 SECONDARY WATER CHEMISTRY
.......................................................................
6-25 6.18 DELETED 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM ...................................
6-26 6.20 RADIOACTIVE EFFULENT CONTROLS PROGRAM ...........................................
6-26 6.21 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .....................
6-28 6.22 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM ................
6-28 6.23 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM ...................
6-28 6.24 DIESEL FUEL OIL TEST PROGRAM .......................................................................
6-29 MILLSTONE
-UNIT 2 XVII Amendment No. -79, 46,63,66,403, 4704, 4-44, 449, 4-5-, 4-6,4-69, 2-39, -MO, 2-6-2, 64, 270, 2,-6, 27-7, 2-96, , 295 DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing 176 rods. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal average enrichment of 4.85 weight percent ofU-235. A fuel rod shall have a maximum enrichment of 5.0 weight percent of U-235.CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 control element assemblies.
The control element assemblies shall be designed and maintained in accordance with the design provisions contained in Section 3.0 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.4 DELETED
MILLSTONE
-UNIT 2 5-4 Amendment No. 3,8, 4-39, 446, 204, 216, 27, 2-4, 280, 295 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (CONT.)8) XN-NF-62 1 (P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nu'clear Company.9) XN-NF-82-06(P)(A), and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company.10) ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Bumups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation.
- 11) XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company.12) ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation.
- 13) EMF-1961 (P)(A), "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation.
- 14) EMF-2130(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP.15) EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation.
- 16) EMF 116(P)(A)
Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation.
- c. The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits)of the safety analysis are met.d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
MILLSTONE
-UNIT 2 6-19 Amendment No. 4-49, +63, 2-2-28, 2-59-2-60, 2 -1+, 21-, 295 ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
- a. Deleted b. Deleted c. Deleted d. ECCS Actuation, Specifications 3.5.2 and 3.5.3.e. Deleted f. Deleted g. RCS Overpressure Mitigation, Specification 3.4.9.3.h. Deleted i. Tendon Surveillance Report, Specification 6.25 j. Steam Generator Tube Inspection, Specification 4.4.5.1.5.
- k. Accident Monitoring Instrumentation, Specification 3.3.3.8.1. Radiation Monitoring Instrumentation, Specification 3.3.3.1.m. Deleted 6.10 Deleted.6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving_personnel radiation exposure.MILLSTONE
-UNIT 2 6-20 Amendment No. 9, -,6, 4-04, 444-, +-48, 4-62,4-63,494,239,24-0,266, 2-7-6, 49, 295 ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and ( b ) of 10 CFR Part 20: 6.12.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area, Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
- b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.MILLSTONE
-UNIT 2A 6-20a Amendment No.2951
