Letter Sequence Response to RAI |
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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
ML23136B1392023-06-29029 June 2023
Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications
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
ML22300A1882022-10-27027 October 2022
License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information
ML21253A0632021-11-19019 November 2021
Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis
ML21232A2172021-10-19019 October 2021
Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing
ML21280A3282021-10-0707 October 2021
Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
ML21277A0652021-09-30030 September 2021
Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer
ML21175A1852021-08-20020 August 2021
Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines
ML21106A2792021-05-0404 May 2021
Technical Specifications
ML20325A0952021-03-19019 March 2021
Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary)
ML20302A1792020-10-29029 October 2020
Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology
ML20301A4522020-10-28028 October 2020
Non-Proprietary, Issuance of Amendment Nos. 300 and 300 to Revise Technical Specifications 6.2.C, Core Operating Limits Report
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
ML20115E2372020-05-0707 May 2020
Issuance of Exigent Amendments Nos. 299 and 299, to Revise TS 6.4.Q, Steam Generator (SG) Program, to Allow a One-Time Deferral of the Inspection of Surry Unit 2 Sg B Spring 2020 Refueling Outage
ML19238A1272019-09-12012 September 2019
Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection
ML19196A1102019-07-0909 July 2019
Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages
ML19126A0002019-05-28028 May 2019
Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage
ML19156A2072019-05-24024 May 2019
Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01
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
ML17326A2252018-02-0909 February 2018
Issuance of Amendments Regarding License Amendment Request to Revise Residual Heat Removal and Component Cooling System Technical Specifications Requirements (CAC Nos. MF9124 and MF9125; EPID L-2017-LLA-0166)
ML17187A1322017-06-28028 June 2017
Submittal of Topical Report VEP-NE-1, Revision 0.2-A, Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications for Information Only
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
ML16252A4782016-10-17017 October 2016
Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0
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
ML16013A4442016-02-22022 February 2016
(NAPS) - Issuance of Amendment for Changes to Technical Specification (TS) 3.8.1 - AC Sources, Operating Revised Surveillance Requirement
ML15307A3002016-02-0202 February 2016
(NAPS) - Issuance of Amendments for Changes to the Emergency Action Level Revisions - Correction of Equipment Mark Number
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
ML15133A3812015-06-16016 June 2015
Issuance of Amendments to Extended Type a Test Frequency to 15 Years
ML15147A0292015-05-22022 May 2015
Proposed License Amendment Request (Lar), TS 3.8.1 - AC Sources - Operating, Revised Surveillance Requirement
ML15093A0022015-05-20020 May 2015
Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15098A0342015-05-20020 May 2015
Issuance of Amendment No. 261, 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
ML15083A4362015-05-14014 May 2015
Issuance of Amendments Regarding Alternate Control Rod Position Monitoring
2024-01-12
[Table view] |
Text
Serial No.05-251 Response to Request for Additional Information ENCLOSURE 1 RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION REVISED TECHNICAL SPECIFICATION REPLACEMENT PAGES DOMINION NUCLEAR CONNECTICUT, INC.
VIRGINIA ELECTRIC AND POWER COMPANY
5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The designated officer shall be responsible for overall operation of the Millstone Station Site and shall delegate, in writing, the succession to this responsibility. The designated manager shall be responsible for overall Unit safe operation and shall delegate in writing the succession of this responsibility.
5.1.2 The Shift Manager shall be responsible for the control room command function.
5.1.3 Unless otherwise defined, the technical specification titles for members of the staff are generic titles. Unit-specific titles for the functions and responsibilities associated with these generic titles are identified in appropriate administrative documents.
MILLSTONE-UNIT 1 5.0-1 Amendment No. 106, 111,
ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. Exceptions to this requirement are specified in the Quality Assurance Program.
5.3.2 The operations manager or assistant operations manager shall be a CERTIFIED FUEL HANDLER.
MILLSTONE-UNIT 1 5.0-5 Amendment No. 106, 111,
ADMINISTRATIVE CONTROLS FACILITY STAFF (CONTINUED)
- d. A radiation protection technician shall be on site when fuel is in the reactor. (Table 6.2-1)
- e. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
- f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971* for comparable positions. Exceptions to this requirement are specified in the Quality Assurance Program.
6.3.2 If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 2, then the operations manager shall have held a senior reactor operator license at a Pressurized Water Reactor and an individual serving in the capacity of the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 2.
- As of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000.
MILLSTONE - UNIT 2 6-2 Amendment No. 136, 142, 163, 178, 190, 191 255, 270,
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971* for comparable positions. Exceptions to this requirement are specified in the Quality Assurance Program.
6.3.2 If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the operations manager shall have held a senior reactor operator license at a pressurized water reactor, and the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 3.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff that meets or exceeds the requirements as specified in the Quality Assurance Program and 10 CFR Part 55.59 shall be maintained.
6.4.2 Deleted.
6.5 Deleted.
- As of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000.
MILLSTONE - UNIT 3 6-5 Amendment No. 36, 69, 84, 90, 94, 130, 132, 135, 171, 173, 199, 212,
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI 3.1 (12/79 Draft) for the comparable positions. Exceptions to this requirement are specified in Dominions QA Program. The SM, Unit Supervisor, Control Room Operator, and the individual providing advisory technical support to the unit operations shift crew, shall meet or exceed the minimum qualifications of 10 CFR 55.59(c) and 55.31(a)(4).
5.3.2 For the purpose of 10 CFR 55.4, a licensed SRO and a licensed RO are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).
North Anna Units 1 and 2 5.3-1
TS 6.1-2
- 2. Unit Staff The unit staff organization shall include the following:
- a. Each on-duty shift shall be composed of at least the minimum shift crew composition for each unit as shown in Table 6.1-1.
- b. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the position.
- c. All core alterations shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling who has no other concurrent responsibilities during this operation.
- d. The operations manager shall hold (or have previously held) a Senior Reactor Operator License for Surry Power Station or a similar design Pressurized Water Reactor plant. The Supervisor Nuclear Shift Operations shall hold an active Senior Reactor Operator License for Surry Power Station.
- e. Procedures will be established to insure that NRC policy statement guidelines regarding working hours established for employees are followed. In addition, procedures will provide for documentation of authorized deviations from those guidelines and that the documentation is available for NRC review.
6.1.3 Unit Staff Qualifications
- 1. Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI 3.1 (12/79 Draft) for comparable positions.
Exceptions to this requirement are specified in Dominions QA Program.
Incumbents in the positions of Shift Manager, Unit Supervisor (SRO),
Control Room Operator (RO), and the individual providing advisory technical support to the unit operations shift crew, shall meet or exceed the requirements of 10 CFR 55.59(c) and 55.31(a)(4).
- 2. For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator and a licensed Reactor Operator are those individuals who, in addition to meeting the requirements of TS 6.1.3.1 perform the functions described in 10 CFR 50.54(m).
Amendment Nos.
