Letter Sequence Approval |
|---|
|
|
MONTHYEARML0603200022006-02-14014 February 2006
RAI, Proposed Technical Specification Changes on Addition of Analytical Methodology to the Core Operating Limits Report
Project stage: RAI
ML0609006312006-03-30030 March 2006
Response to Request for Additional Information on Proposed Technical Specification Changes on Addition of Analytical Methodology to the Core Operating Limits Report
Project stage: Response to RAI
ML0610400622006-04-13013 April 2006
Proposed Technical Specifications Changes on Addition of Analytical Methodology to the Core Operating Limits Report Administrative Correction
Project stage: Request
ML0613104952006-05-11011 May 2006
Response to Request for Additional Information on Proposed Technical Specification Changes on Addition of Analytical Methodology to the Core Operating Limits Report
Project stage: Response to RAI
ML0620200052006-07-18018 July 2006
License Amendment, Issuance of Amendments on Changes to Analytical Methodology and Core Operating Limits Report, MC7526 and MC7527
Project stage: Approval
ML0620604672006-07-18018 July 2006
Technical Specifications, Issuance of Amendments on Changes to Analytical Methodology and Core Operating Limits Report, MC7526 and MC7527
Project stage: Approval
2006-04-13
[Table View] |
|
|---|
Category:Technical Specifications
MONTHYEARML23072A0892023-05-0101 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
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
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
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
ML19156A2072019-05-24024 May 2019
Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01
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
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
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
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
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
ML15083A4362015-05-14014 May 2015
Issuance of Amendments Regarding Alternate Control Rod Position Monitoring
ML15041A6672015-02-0404 February 2015
Proposed License Amendment Request Re Alternate Control Rod Position Monitoring
ML14188C4532014-08-27027 August 2014
Issuance of Amendments Regarding Modification of Control Bank Sequence and Overlap Technical Specifications
ML14169A3592014-08-12012 August 2014
Stations, Units 1 and 2, Issuance of Amendments Regarding Addition of an Analytical Methodology to the Core Operating Limits Reports and an Increase to the Surry Minimum Temperature for Criticality
ML14183B3182014-06-30030 June 2014
Proposed License Amendment Request Permanent Fifteen-Year Type a Test Interval
ML13302B8922013-10-0202 October 2013
Technical Specification Bases
ML12356A2982012-12-13013 December 2012
Supplemental Information for 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.
ML12219A0722012-07-30030 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
ML12136A4512012-05-11011 May 2012
Proposed License Amendment Request - Temporary Change to Allow Two Inoperable Demand Position Indicators Per Control Bank
PLA-6842, Response to E-mail (Dated March 30, 2012), Request for Additional Information on Proposed Amendment Number 2812012-04-0202 April 2012
Response to E-mail (Dated March 30, 2012), Request for Additional Information on Proposed Amendment Number 281
ML1111900932011-04-27027 April 2011
License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.
ML1029804472010-10-21021 October 2010
Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA)
ML0935004002010-03-0303 March 2010
Issuance of Amendments to Adopt TSTF-490, Revision 0, Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Using the Consolidated Line Item Improvement Process
ML0920503812009-07-23023 July 2009
License Amendment Request, One Time Extension of the Completion Time for 1 J - 480 Volt AC Distribution Subsystem
ML0909000552009-03-26026 March 2009
License Amendment Request, Measurement Uncertainty Recapture Power Uprate
ML0904004652009-02-0606 February 2009
License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Work Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0815106502008-06-30030 June 2008
Technical Specifications, Issuance of Amendment Regarding One-Time 5-Year Extension to Type a Test Interval
ML0735202472007-12-17017 December 2007
Proposed License Amendment Request, One-time Risk-Informed Extension to the Completion Time for EDG Fuel Oil Storage Tank Recoating
ML0730604062007-10-31031 October 2007
Tech Spec Pages for Amendments 252 and 232 Control Room Habitability, Using the Technical Specification Task Force Traveler, TSTF-448, Revision 3
ML0730304002007-10-17017 October 2007
Tech Pages for Amendments 251 and 231 Technical Specification Change to Add Limiting Condition for Operation 3.0.8 on the Inoperability of Snubbers, Using the Consolidated Line Item Improvement Process, TSTF-372, Rev 4
ML0715001452007-05-29029 May 2007
Proposed License Amendment Request, Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
ML0714104632007-05-21021 May 2007
Proposed License Amendment Request Addition of LCO 3.0.8 - Inoperability of Snubbers Using the Consolidated Line Item Improvement Process Technical Specification Improvement
ML0702202192007-01-19019 January 2007
Technical Specifications Corrected Page for Amendment Nos. 249 and 229
ML0701003492007-01-0909 January 2007
Technical Specifications, Relocated the ASTM Standard Used to Test the Total Particulate Concentration of the Stored Fuel Oil from TS 5.5.12, Emergency Diesel Generator Fuel Oil Testing Program to a Licensee-controlled Program
ML0634502592006-12-11011 December 2006
Tech Spec Pages for Amendments 249 and 229 Regarding Diesel Fuel Oil Testing Program
ML0630000282006-10-16016 October 2006
Tech Spec Pages for Amendments 248 and 228 Regarding Consolidated Line Item Improvement Process for the Steam Generator Tube Integrity
ML0627700182006-09-25025 September 2006
Technical Specification Bases Pages
ML0620604672006-07-18018 July 2006
Technical Specifications, Issuance of Amendments on Changes to Analytical Methodology and Core Operating Limits Report, MC7526 and MC7527
ML0615101992006-05-30030 May 2006
Proposed Technical Specifications Change Diesel Fuel Oil Testing Program
ML0533502792005-11-21021 November 2005
10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency
ML0529900852005-10-25025 October 2005
Enclosure, Technical Specifications, Amd MC7612, Equation for Over-Temperature Delta T Function Allowable Value
ML0529900152005-10-24024 October 2005
Technical Specifications, Revised Test Frequency of P-4 Interlock Function
ML0526301042005-09-15015 September 2005
Tech Spec Pages for Amendment Nos. 243 and 224, Revise the Administrative Controls Section
ML0519604352005-07-14014 July 2005
Proposed Technical Specification Changes Correction to Equation for Overtemperature T Function Allowable Value
ML0518900342005-07-0505 July 2005
Proposed Technical Specification Changes Addition of Analytical Methodology to COLR
2023-05-01
[Table view] |
Text
(2) Pursuant to the Act and 10 CFR Part 70, VEPCO 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 Updated Final Safety Analysis Report; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO 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, VEPCO 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 calibration or associated with radioactive apparatus or component; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, VEPCO 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 I: 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; 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 VEPCO Is authorized to operate the North Anna Power Station, Unit No. 1, at reactor core power levels not In excess of 2893 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained In Appendix A, as revised through Amendment No.' 24 7are hereby Incorporated In the renewed license.
The licensee shall operate the facility In accordance with the Technical Specifications..
Renewed License No. NPF-4 Amendment No. 247
(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO 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, VEPCO 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 calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified In the Commission's regulations as set forth In 10 CFR Chapter Iand 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 VEPCO Is authorized to operate the facility at steady state reactor core power levels not In excess of 2893 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2 2 7 are hereby Incorporated In the renewed license.
The licensee shall operate the facility In accordance with the Technical Specifications.
(3) Additional Conditions The matters specified In the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the Issuance of the condition or within the operational restrictions Indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission:
- a. if VEPCO plans to remove or to make significant changes In the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Power Station, the Renewed License No. NPF-7 Amendment No. 227
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- b. (continued)
- 14. BAW-10199P-A, "The BWU Critical Heat Flux Correlations."
- 15. BAW-10170P-A, "Statistical Core Design for Mixing Vane Cores."
- 16. EMF-2103 (P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors."
- 17. EMF-96-029 (P)(A), "Reactor Analysis System for PWRs."
- 18. BAW-10168P-A, "RSG LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants,"
Volume II only (SBLOCA models).
- 19. DOM-NAF-2-A, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code," including Appendix A, "Qualification of the F-ANP BWU CHF Correlations in the Dominion VIPRE-D Computer Code."
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 PAM Report When a report is required by Condition B of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Steam Generator Tube Inspection Report
- a. Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Nuclear Regulatory Commission within 15 days.
North Anna Units I and 2 5.6-4 Amendment Nos.
247, 227
