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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Report
MONTHYEARML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status 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 ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML18256A2002018-10-0303 October 2018 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012) ML18247A2752018-06-18018 June 2018 Technical Requirements Manual ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML15078A2052015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57 ML15078A2082015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End ML15078A2072015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171 ML15078A2062015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13357A3982014-01-24024 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858 ML14006A1592014-01-0808 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859 ML14087A0992013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 2023-07-26
[Table view] Category:Miscellaneous
MONTHYEARML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment 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 ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12362A3922012-11-30030 November 2012 Spent Fuel Pool Criticality Analysis with No Credit for Boraflex. ML12353A2422012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12187A1752012-06-25025 June 2012 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2010 and 2011, and Commitment Change Report for 2010 and 2011 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12046A8362012-01-31031 January 2012 Inservice Inspection Program - Owner'S Activity Report ML12031A1472012-01-25025 January 2012 Day Report for Emergency Core Cooling System Model Changes of 10 CFR 50.46 ML1116002202011-06-13013 June 2011 Exhibit D (Part 3): Millstone 2001 Safstor Cost Analysis (Normal Dollars) ML1028504382010-09-30030 September 2010 Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep ML1019403352010-06-30030 June 2010 Units, 1, 2, 3, & ISFSI, 10 CFR 50.59, 10 CFR 72.48 Change Report for 2008 and 2009, and the Commitment Change Report for 2009 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1009702062010-03-29029 March 2010 Chemistry Procedure, Liquid Waste Sample Sink, Rev. 003-00 ML0931701762009-11-12012 November 2009 Part 3 of 4--Weld Overlay Examination Report 2R19 ML0931701732009-11-12012 November 2009 Part 2 of 4--Weld Overlay Examination Report 2R19 ML0931701662009-11-12012 November 2009 Part 1 of 4--Weld Overlay Examination Report 2R19 ML0931701852009-09-23023 September 2009 Part 4 of 4--Weld Overlay Examination Report 2R19 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913204602009-04-28028 April 2009 2008 Occupational Radiation Exposure Information ML0901303822008-12-26026 December 2008 Revision 002 to CP 3804L Procedure Action Request, Pass Containment Air Sample, Dated 12/26/2008 ML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request ML0819800752008-07-0707 July 2008 Revision to Control Room and OSC Assembly Area Building 475 1st Floor, and SAP Locker ML0818406072008-07-0101 July 2008 Final Evaluation of Weld Overlay Examinations in Refueling Outage 18 ML0727504022007-09-27027 September 2007 Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique LBDCR 07-MP2-034 ML0720003902007-07-13013 July 2007 Attachment 1, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Descriptions, Technical Analysis and Regulatory Analysis for the Proposed Operating License and Technical Specifications Changes ML0715203992007-05-30030 May 2007 Fy 2007 Final Fee Rule Workpapers ML0713501882007-05-17017 May 2007 Review of Steam Generator Tube Inservice Inspection Report for the 2005 Refueling Outage at Millstone Power Station, Unit No. 2 ML0713502492007-05-0808 May 2007 Steam Generator Tube Plugging Report ML0708805652007-03-28028 March 2007 Response to Request for Additional Information Regarding an Alternative for the Weld Overlay of Pressurizer Nozzle Welds ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report 2023-07-26
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b Dominion AUG I 9 2002 Docket Nos. 50-245 50-336 50-423 B18728 RE: 10 CFR 26.71(d)
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3 Semi-Annual Fitness-for-Duty Performance Data January 2002 through June 2002 Dominion Nuclear Connecticut, Inc. (DNC), submits the semi-annual Fitness-for-Duty performance data for Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3, in accordance with the provisions of 10 CFR 26.71(d), for the reporting period January 1, 2002, through June 30,2002.
The provisions of 10 CFR 26.71(d) require power reactor licensees to collect and compile fitness-for-duty program performance data on a standard form and submit this data to the Commission within 60 days of the end of each 6-month reporting period (January - June and July - December). Accordingly, Attachments 1 through 3 contain fitness-for-duty program performance data for January 2002 through June 2002 for the Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3.
The following data is included as required by regulation: random testing rate; drugs tested for and cutoff levels, including results of tests using lower cut-off levels and tests for other drugs; work force populations tested; numbers of tests and results by population and type of test (e.g., pre-access, random, for-cause, etc.); substances identified; summary of management actions; and a list of events reported. Attachment 1 to this letter contains an explanation of the performance data form, a summary of the performance data, a summary of management actions, and significant fitness-for-duty events. Attachment 2 is a compilation of the data collected at Millstone Station.
The drug and alcohol testing data for this testing period has been analyzed and any necessary corrective actions taken. Supporting information is on file at the Millstone Nuclear Power Station.
U.S. Nuclear Regulatory Commission B18728/Page 2 Also included with this submittal, as Attachment 3, is data collected by Westinghouse Electric who conducts pre-access drug and alcohol testing for individuals requiring unescorted access to the Millstone Nuclear Power Station. Westinghouse Electric Corporation has a fitness-for-duty program that has been audited and accepted by DNC.
There are no regulatory commitments contained within this submittal.
If you have any questions regarding this submittal, please contact Mr. Paul Willoughby at (860) 447-l 791, extension 3655.
Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.
cSite Vi e President - Millstone Attachments (3) cc: H. J. Miller, Region I Administrator J. B. Hickman, NRC Project Manager, Millstone Unit No. 1 J. R. Wray, NRC Inspector, Region I, Millstone Unit No. 1 R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2 V. Nerses, NRC Senior Project Manager, Millstone Unit No. 3 NRC Senior Resident Inspector, Millstone Unit No. 3
Docket Nos. 50-245 50-336 50-423 B18728 Attachment 1 Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3 Performance Data Form Explanation Summary of Performance Data/Management Actions Significant Fitness-for-Duty Events
U.S. Nuclear Regulatory Commission B18728/Attachment 1/Page 1 Performance Data Form Explanation Summary of Performance Data/Management Actions Significant Fitness-for-Duty Events Performance Data Form Explanation
- Cutoffs Dominion Nuclear Connecticut, Inc. (DNC) cutoff levels differ from the U.S.
Nuclear Regulatory Commission (NRC) standard cutoff levels in the marijuana category only. DNC uses a 50 ng/ml screening cutoff level which is more conservative than the regulatory standard.
- Substances DNCs testing program includes the National Institute of Drug Abuse (NIDA) 5 substances and all specimens are tested for Nitrites.
- Contractor Personnel DNC does not maintain records for separate categories of contractors.
Consequently, all contractor data is recorded under the short-term contractor personnel category.
- Confirmed Positive Tests for Specific Substances This section contains the number of confirmed positive tests, recorded by substance, during the reporting period. Please note that there may be no direct correlation between the sum of these numbers and the number of positives entered on the front of the form. Positive tests for multiple substances per individual are recorded as separate items in this table.
- Regulatory and DNC Cutoff Levels Since DNC uses a cutoff level for marijuana which is more conservative than the NRC, the positive column for that substance only is split; the left side indicates confirmed positives based on NRC cutoff levels and the right side indicates the confirmed positives based on DNCs more conservative cutoff level.
- For-Cause vs. Post Accident This category has been separated to recognize the difference in testing for-cause when observed unusual or aberrant behavior indicates possible substance abuse, odor of alcohol is detected or drugs or alcohol have been discovered on an individual, vs. post accident testing following an accident which may have been the result of failure in individual performance.
U.S. Nuclear Regulatory Commission B18728/Attachment 1/Page 2
- Other This category is used to record supplemental and/or witnessed tests performed during the report period. Supplemental tests are re-collections of specimens which, for technical reasons, could not be processed by the NIDA laboratory. Examples of reasons for not processing include specimen leakage and insufficient specimen. Witnessed tests are re-collected under direct observation when the initial collection is reported as DILUTE and a requested Limits of Detection reports that an illegal substance is found in the urine.
Summary of Performance Data
- 571 tests were random Average population = 2028 Annual 50 percent minimum random testing rate achieved (571/2028 =
28.1 % X 2 (because this report is done semi-annually) = 56 %).
- Percent Confirmed Positive Rates:
Pre-access = 1.5 percent (70 percent of confirmed positives were in this category.)
Random = 0.5 percent Overall = 1.0 percent There were nineteen confirmed positive tests from seventeen individuals. Two individuals tested positive for two substances. One individual refused an opportunity to meet with the Medical Review Officer (MRO). This individual is included in the breakdown below under Administrative.
Breakdown:
Marijuana 7 (41 percent)
Cocaine 6 (35 percent)
Opiates (Heroin) 1 (5 percent)
Alcohol 4 (23 percent)
Administrative 1 (5 percent)
There were no verified confirmed positive tests for any other substance.
- Regulatory vs. DNC Cutoff Levels (Marijuana)
A total of seven individuals tested confirmed positive for marijuana. Of the seven samples, five screened at a level of 100 ng/ml or greater (NRC limit), and two screened at 50ng/ml (DNC limit).
U.S. Nuclear Regulatory Commission B18728/Attachment 1/Page 3 Management Actions Fourteen contractor personnel tested confirmed positive for drugs or alcohol.
Twelve of these were during the pre-badging process, one was tested for-cause, and one was a follow-up. All were denied unescorted access. Of the fourteen, thirteen were verified confirmed positives and one was an administrative positive.
Twelve of these individuals tested positive for the first time and will not be considered for unescorted access for a period of at least five years. Two tested positive for the second time and shall be permanently denied access. Two individuals tested positive for two substances.
No candidate for employment with DNC tested confirmed positive in a pre-employment test.
Three DNC employees tested positive.
Two individuals tested positive for the first time; access was suspended. One employee was placed on a 30 day unpaid suspension. Disciplinary action for the second employee was administered via an Employment Decision Day, in accordance with DNC policy. Both employees were referred to EAP for evaluation and placed in the follow-up program.
One individual tested positive for the second time. This employee was terminated and access denied permanently.
Significant Fitness-for-Duty Events There was one Significant Fitness-for Duty Event during this reporting period.
Proficiency Testing A total of 247 blind proficiency specimens were processed for this 6-month period.
There were no false negatives and no false positives. All data regarding proficiency testing is on file with the Process Assistant Four/Fitness-for-Duty.
Docket Nos. 50-245 50-336 50-423 B18728 Attachment 2 Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3 Millstone Power Station Semi-Annual Fitness-for-Duty Performance Data
U.S. Nuclear Regulatory Commission B18728/Attachment 2/Page 1 Fitness-for-Duty Program Performance Data for Personnel Subject to 10 CFR 26 Millstone Power Station June 30, 2002 Company 6 Months Ending 156 Rope Ferry Rd, Waterford, CT 06385 Location Cora Quinn-Ross (860) 437-5914 Contact Name Area code and Phone #
Cutoffs: Screen/Confirmation (ng/ml) Appendix A to 10CFR26 Marijuana: 50/15 Amphetamines: 1000/500 : /
Cocaine: 300/150 Phencyclidines: 25/25 : /
Opiates: 300/300 Alcohol (%BAC): 0.040d : /
TESTING RESULTS Licensee Employee Contractor Personnel Average Number with Unescorted Access 1455 573 CATEGORIES # Tested # Positive # Tested # Positive Pre-Access 16 0 746 12 Pre-Employment 42 0 0 0 For Cause 0 0 5 1 Random 372 3 199 0 Follow-Up 12 0 7 1 Infrequent Visitor 0 0 54 0 Post Accident 3 0 10 0 TOTAL 445 3 1021 14
U.S. Nuclear Regulatory Commission B18728/Attachment 2/Page 2 Fitness-for-Duty Program Performance Data for Personnel Subject to 10 CFR 26 BREAKDOWN OF CONFIRMED POSITIVE TEST FOR SPECIFIC SUBSTANCES Categories Licensee Employees Contractor Personnel Sub Total NRC Limits DNC Limits NRC Limits DNC Limits NRC Limits DNC Limits Marijuana 1 0 4 2 5 2 Cocaine 1 5 6 Opiates 0 1 1 Amphetamines 0 0 0 Phencyclidine 0 0 0 Alcohol 2 2 4 Refusal to Test 0 0 0 Administrative 0 1 1 Positive Nitrite Positive 0 0 0 Substituted 0 0 0 Urine Sub Total 4 15 19
Docket Nos. 50-245 50-336 50-423 B18728 Attachment 3 Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3 Westinghouse Electric Corporation Semi-Annual Fitness-for-Duty Performance Data Compilation
U.S. Nuclear Regulatory Commission B18728/Attachment 3/Page 1 Fitness-for-Duty Program Performance Data for Personnel Subject to 10 CFR 26 1 Westinghouse Electric Company 2 June 30, 2002 Company 6 Months Ending 3 P.O. Box 158, BIN 38, Madison, PA 15663 Location 4 Peter J. Defillippi 5 (724) 722-5721/5718 Contact Name Area code and Phone #
6 Cutoffs: Screen/Confirmation (ng/ml) Appendix A to 10CFR26 Marijuana: 20/15 Amphetamines: 300/300 Barbiturates 300/300 Cocaine: 300/150 Phencyclidines: 25/25 Benzodiazepines 300/300 Opiates: 300/300 Alcohol (%BAC): 0.04% Methadone 300/300 Methaqualone 300/300 Testing Results Westinghouse Long-Term Short-Term Employees Contractor Personnel Contractor Personnel 7 Average Number with Unescorted 700 0 840 Access 8 Categories # Tested # Positive # Tested # Positive # Tested # Positive Pre-Access 3 0 0 0 0 0 For Post Accident 0 0 0 0 0 0 Cause Observed behavior 0 0 0 0 0 0 Random 0 0 0 0 0 0 Follow-up 0 0 0 0 0 0 Other 0 0 0 0 0 0 Total 3 0 0 0 0 0
U.S. Nuclear Regulatory Commission B18728/Attachment 3/Page 2 9 Marijuana Cocaine Opiates Amphet- Phency- Alcohol Refusal to Adulterants 1 2 3 4 amines clidine Test Employees 0 0 0 0 0 0 0 0 0 0 0 0 Long-Term Contractors 0 0 0 0 0 0 0 0 0 0 0 0 Short-Term Contractors 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 LEGEND:
1 = Barbiturates 2 = Benzodiazepines 3 = Methadone 4 = Methaqualone