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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24162A0882024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 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) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2272024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis ML23123A2792023-05-0202 May 2023 License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits and Exemption Request for Use of M5 Cladding ML23013A2242023-01-13013 January 2023 Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure Temperature Limitation Figures ML22362A1022022-12-28028 December 2022 Proposed License Amendment Request to Supplement Spent Fuel Pool Criticality Safety Analysis ML22146A0272022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant. ML22096A2212022-04-0606 April 2022 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21053A3422021-02-22022 February 2021 Proposed License Amendment Request to Clarify Shutdown Bank Technical Specification Requirements and Add Alternative Control Rod Position Monitoring Requirements ML20343A2432020-12-0808 December 2020 Proposed License Amendment Request Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A, Revision 1 ML20343A2592020-12-0808 December 2020 Supplement to Proposed License Amendment Request to Revise the Millstone Unit 2 Technical Specifications for Steam Generator Frequency ML20324A7032020-11-19019 November 2020 Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate ML20310A3242020-11-0505 November 2020 Proposed License Amendment Request, Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) ML20282A5942020-10-0808 October 2020 Proposed License Amendment Request to Revise the Millstone Unit 2 Technical Specifications for Steam Generator Inspection Frequency ML20224A4572020-08-11011 August 2020 Connecticut. Inc. Millstone Power Station Unit 3, Proposed License Amendment Request for a One-Time Extension of the Millstone Unit 3 Steam Generator Inspections ML20121A2172020-04-30030 April 2020 Proposed Technical Specifications Change Battery Surveillance Requirements ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML20065K9762020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20063L8232020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML19353A0222019-12-17017 December 2019 License Amendment Request to Revise TS 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML19304A2942019-10-22022 October 2019 Supplement to Proposed License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Componen ML19217A2082019-07-30030 July 2019 Proposed License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML19109A1002019-04-11011 April 2019 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month. ML19023A4272019-01-17017 January 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18128A0492018-05-0303 May 2018 License Amendment Request Regarding Proposed Technical Specifications Changes for Spent Fuel Storage and New Fuel Storage 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 ML17284A1792017-10-0404 October 2017 Proposed License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML17171A2322017-06-15015 June 2017 License Amendment Request to Revise the Company Name ML17018A0002017-02-0707 February 2017 Issuance of Amendment Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 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 ML16159A2592016-09-0606 September 2016 Enclosure 1 Millstone Power Station, Unit No. 1 Issuance of Amendment Administrative Changes and Corrections to the Technical Specifications ML16153A0262016-05-25025 May 2016 Proposed License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis ML16153A0272016-05-25025 May 2016 ANP-3316(NP), Revision 0, Millstone, Unit 2, M5 Upgrade, Realistic Large Break Loca Analysis Licensing Report. ML16153A2342016-05-23023 May 2016 Supplement to License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications ML16034A3582016-01-26026 January 2016 License Amendment Request, Spent Fuel Pool Heat Load Analysis ML16029A1682016-01-25025 January 2016 License Amendment Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML15246A1172015-08-31031 August 2015 Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program ML15246A1182015-08-31031 August 2015 License Amendment Request to Revise Technical Specification 5.6.3, Fuel Storage Capacity ML15246A1242015-08-27027 August 2015 Connecticut, Inc. Millstone Power Station Unit 2 Supplement to License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML15183A0222015-06-30030 June 2015 License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System ML15134A2442015-05-0808 May 2015 License Amendment Request to Adopt Dominion Core Design and Safety Analysis Methods and to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev. 1, NSAL-15-1, and 06-IC-03 ML15065A3342015-02-26026 February 2015 Changes to Technical Specification Bases ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14310A1872014-10-31031 October 2014 License Amendment Request to Revise the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14188B1892014-06-30030 June 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C. ML14133A0092014-05-0808 May 2014 License Amendment Request, Implementation and Engineered WCAP-15376, Reactor Trip System Instrumentation Test Times and Engineered Safety Feature Actuation System Instrumentation Test and Completion Times ML14093A0282014-03-28028 March 2014 License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications ML14093A0262014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14093A0272014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14070A3462014-03-0606 March 2014 Changes to Technical Specification Bases 2023-09-26
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Text
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Dominion Nuclear Connecticut, Inc.
iLlill<roiic Power Staticin borninion 9 Ihpc t.ci-1.). i i O . l d
'U'.itcrtTird, CI' 06.385 August 23, 2004 U.S. Nuclear Regulatory Commission Serial No. 04-343A Attention: Document Control Desk NL&OS/PRW RO Washington, D.C. 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 CONTROL ROOM ISOLATION RADIATION MONITORING INSTRUMENTATION ADMINISTRATIVE CORRECTION In a letter dated July 15, 2004, Dominion Nuclear Connecticut, Inc. (DNC) requested to amend Operating License DPR-65 for Millstone Power Station Unit 2 to address the resolution of a non-conservative Technical Specification.
During a review of the correspondence, it was determined that additional pages, not part of the requested changes, were inadvertently included as part of Attachment 3 of the letter. Therefore, DNC requests that Attachment 3 of the subject letter be withdrawn and that the enclosure to this letter be inserted in its place.
The substitution of the enclosure to this letter in place of Attachment 3 of the July 15, 2004 letter does not alter the proposed amendment or the Significant Hazards Consideration pursuant to the provisions of 10 CFR 50.92 found in Attachment 1 of the July 15, 2004 letter.
In accordance with 10CFR50.91(b), a copy of this letter is being provided to the State of Connecticut.
If you should have any questions regarding this submittal, please contact Mr. Paul R.
Willoughby at (804) 273-3572.
Very truly yours, U
Eugene S. Grecheck Vice President - Nuclear Support Services
Serial No. 04-343A Page 2
Enclosure:
- 1. Substitute Attachment 3 to July 15, 2004 letter: Re-typed Pages Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No. 04-343A Docket No. 50-336 Control Room Isolation Radiation Monitoring Instrumentation COMMONWEALTH OF VIRGINIA )
1 COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Eugene S. Grecheck, who is Vice President -
Nuclear Support Services, of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this day of ,2004.
My Commission Expires:
3/31102 U SEAL
Serial No. 04-343A Control Room Isolation Radiation Monitoring Instrumentation ENCLOSURE LICENSE AMENDMENT REQUEST RELATED TO CONTROL ROOM ISOLATION RADIATION MONITORING INSTRUMENTATION ADMINISTRATIVE CORRECTION SUBSTITUTE ATTACHMENT 3 LETTER SERIAL NO.04-343 MILLSTONE POWER STATION, UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC
Serial No.04-343 Control Room Isolation Radiation Monitoring Instrumentation ATTACHMENT 3 LICENSE AMENDMENT REQUEST RELATED TO CONTROL ROOM ISOLATION RADIATION MONITORING INSTRUMENTATION RE-TYPED PAGES MILLSTONE POWER STATION, UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC
TABLE3.3-6 r DIqTION MONITORING INSTRUMENTATION (A
MINLMLTM 8 CHANNELS APPLICABLE ALARM/TRP MEASUREMENT 5
2 INSTRUMENT
- 1. AREAMONITORS
- a. Spent Fuel Storage OPERABLE 2
- MODES SETPOINT 100 mR/hr RANGE 10 1 0 4 mR/hr ACTION 13 4
w and Ventilation System Isolation
- b. Control Room Isolation 2 ALL MODES 2 m lo- - ldmR/hr 16 I
- c. Containment High Range 1 1,2,3,&4 100 R/hr 100 - 108 Rkr 17 y 2. PROCESSMONITORS P
- a. Containment 1 ALL the value 10 - 14 x
VI Atmosphere-Particulate MODES** determined in accordance with cpm specification 4.3.3.1.2
- b. Containment 1 ALL the value 10 - cpm 14 Atmosphere-Gaseous MODES*
- determined in accordance with i
0 a
Specification 4.3.3.1.2 a c. Noble Gas Effluent 1 1,2,3,&4 2 10-l uci/cc 1 0 --~lo5 uci/cc 17 2 Monitor (high range) z I .
(Unit 2 stack)
?
- With fuel in storage building.
- These radiation monitors are not required to be operable during Type A Integrated Leak Rate testing.
s
TABLE 3.3-6 (Continued)
TABLE NOTATION (a) DELETED ACTION 13 - With the number of area monitors OPERABLE less than required by the MINIMUM CHANNELS OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 14 - With the number of process monitors OPERABLE less than required by the MINIMUM CHANNELS OPERABLE requirement either (a) obtain and analyze grab samples of the monitored parameter at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (b) use a Constant Air Monitor to monitor the parameter.
ACTION 15 - DELETED ACTION 16 - 1. With the number of OPERABLE channels one less than required by the MINIMUM CHANNELS OPERABLE requirement, restore the inoperable channel to OPERABLE status within 7 days or initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
- 2. With the number of OPERABLE channels two less than required by the MINIMUM CHANNELS OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
ACTION 17 - With the number of OPERABLE channels less than required by the MINIMUM CHANNELS OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- 1. either restore the inoperable channel(s) to OPERABLE status within 7 days of the discovery or
- 2. prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2within 14 days following discovery outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
MILLSTONE - UNIT 2 314 3-26 Amendment No. 25,W, 4243, M,
=,