Letter Sequence Other |
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EPID:L-2020-LLQ-0003, Reduction in Commitment to the Columbia Operation Quality Assurance Program Description (Open) |
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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
[Table view] Category:Safety Evaluation
MONTHYEARML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds ML23083B4012023-04-27027 April 2023 Issuance of Amendment No. 271 to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B ML22308A0962022-12-15015 December 2022 Issuance of Amendment No. 269 License Amendment to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22263A4452022-11-23023 November 2022 Issuance of Amendment No. 268 to Revise Technical Specification 3.4.11 RCS Pressure and Temperature (P/T) Limits ML22109A0922022-05-18018 May 2022 Correction Letter - Approval for Alternate Disposal Procedures for the Continued Onsite Disposal of Cooling Tower and Spray Pond Sludge in the Existing Sediment Disposal Area ML22098A0642022-05-0909 May 2022 Issuance of Amendment No. 267 to Adopt Technical Specifications Task Force (TSTF) 546, Revision 0, Revise APRM Channel Adjustment Surveillance Requirement ML22004A1852022-03-11011 March 2022 Approval for Alternate Disposal Procedures for the Continued Onsite Disposal of Cooling Tower and Spray Pond Sludge in the Existing Sediment Disposal Area ML21293A1642022-01-13013 January 2022 Issuance of Amendment No. 266 License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) ML21273A1672021-11-22022 November 2021 Issuance of Amendment No. 265 Adoption of TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML21081A1502021-03-25025 March 2021 Approval for Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML21053A3162021-03-0303 March 2021 Issuance of Amendment No. 264 to Revise Technical Specification to Adopt Traveler TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML21005A1782021-01-25025 January 2021 Issuance of Amendment No. 263 to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process ML20302A0262020-12-15015 December 2020 Issuance of Amendment No. 262 to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR ML20282A7322020-10-27027 October 2020 Proposed Alternative Request No. 4ISI-08 Applicable to the Fourth Inservice Inspection Interval ML20242A0022020-09-0404 September 2020 Issuance of Amendment No. 261 Revise Technical Specification 3.8.7, Distribution Systems - Operating (Exigent Circumstances) ML20203K8762020-07-22022 July 2020 Correction to Reduction in Commitment to the Operational Quality Assurance Program Description (EPID L-2020-LLQ-0003 (COVID-19)) ML20181A4452020-07-0707 July 2020 Reduction in Commitment to the Operational Quality Assurance Program Description (EPID L-2020-LLQ-0003)(Covid-19) ML20135H0842020-06-29029 June 2020 Issuance of Amendment No. 260 Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20136A3472020-06-22022 June 2020 Issuance of Amendment No. 259 Revise Technical Specifications Per TSTF-529, Revision 4, Clarify Use and Application Rules ML20125A0802020-05-12012 May 2020 Issuance of Amendment No. 258 Changes to Technical Specification Limiting Conditions for Operation 3.8.4 and 3.8.7 (Exigent Circumstances) ML20113E9842020-05-0404 May 2020 Issuance of Amendment No. 257 to Extend Implementation Date for Amendment No. 255 Control Room Air Conditioning System (Exigent Circumstances) ML19350B5792020-01-0202 January 2020 Generation Station - Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4383; EPID L-2014-JLD-0045) ML19063A5792019-06-20020 June 2019 Issuance of Amendment No. 253 Renewed Facility Operating License and Technical Specification Clean-Up ML18317A0052018-11-27027 November 2018 Correction to Safety Evaluation Pages 5 and 24 for Amendment No. 199 Dated November 27, 2006 Related to Alternative Source Term ML18283A1252018-11-0808 November 2018 Issuance of Amendment No. 252 Update Appendix B to Renewed Facility Operating License to Incorporate the 2017 Biological Opinion ML18255A3502018-10-30030 October 2018 Issuance of Amendment No. 251 Revision to the Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18100A1992018-05-0202 May 2018 Issuance of Amendment No. 249 Change to Technical Specification 3.5.1 ECCS - Operating (CAC No. MG0015; EPID L-2017-LLA-0277) ML17333A8882018-02-22022 February 2018 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17318A0422017-11-20020 November 2017 Relief Request No. 3ISI-17 from the Requirements of the ASME Code, Section XI for the Third 10-Year Inservice Inspection Interval (CAC No. MF8923; EPID L-2016 LLR-0005) ML17290A1272017-10-30030 October 2017 Columbia Generating Station - Issuance of Amendment No. 245 Re: Request for a One-Time Extension of the Residual Heat Removal Train A Completion Time (CAC No. MF8794; EPID L-2016-LLA-0016) ML17188A2302017-08-28028 August 2017 Issuance of Amendment No. 244 Emergency Action Level Scheme Change to Nuclear Energy Institute 99-01, Revision 6 ML17187A2572017-07-24024 July 2017 Columbia Generating Station - Issuance of Amendment No. 243 Re: Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 (CAC No. MF8148) ML17131A0712017-06-27027 June 2017 Columbia Generating Station - Issuance of Amendment No. 242 Re: Reduction of Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, "Reactor Core SLs (Safety Limits)" (CAC No. MF8116) ML17095A1172017-05-11011 May 2017 Columbia Generating Station - Issuance Of Amendment No. 241 Re: Measurement Uncertainty Recapture (CAC No. MF8060) ML17046A5072017-02-16016 February 2017 Relief Request for Alternative 4ISI-07 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML16357A6462017-01-31031 January 2017 Issuance of Amendment No. 239, Adopt Technical Specification Task Force (TSTF)-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML17018A0822017-01-24024 January 2017 Relief Request for Alternative 4ISI-05 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML16292A8722016-11-0303 November 2016 Relief Request 4ISI-06, Use of Code Case N-666-1 on Socket Welded Connections Requiring Repair Due to Vibration Fatigue, Fourth 10-Year Inservice Inspection Interval ML16295A2122016-10-31031 October 2016 Relief Request 4ISI-02, Use of Code Case N-795 Following Repair/Replacement Activities, Fourth 10-Year Inservice Inspection Interval ML16263A2332016-10-0505 October 2016 Relief Request 4ISI-04, Reduced Percentage Requirements for Nozzle to Vessel Welds and Inner Radius Exams, for the Fourth 10-Year Inservice Inspection Interval ML16175A4602016-06-24024 June 2016 Relief Request 4ISI-03, Relief from ASME Code Requirements to Allow Use of Existing Procedures That Implement Repair/Replacement Activities, for the Fourth 10-Year ISI Interval ML16020A0312016-02-16016 February 2016 Issuance of Amendment No. 237, Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability, Using Consolidated Line Item Improvement Process ML15216A2662016-02-0303 February 2016 Issuance of Amendment No. 236, Adoption of Technical Specification Task Force Traveler TSTF-423, Revision 1, Technical Specifications End States, as Part of Consolidated Line Item Improvement Process ML15154A8002015-06-11011 June 2015 Issuance of Amendment No. 235, Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1, Function 7, Scram Discharge Volume Water Level - High (Exigent Circumstances) ML15098A2542015-05-11011 May 2015 Issuance of Amendment No. 234, Request to Revise Technical Specification 2.1.1.2 to Change Safety Limit Minimum Critical Power Ratio Values ML15076A1222015-04-15015 April 2015 Issuance of Amendment No. 233, Request to Revise Technical Specification Surveillance Requirement 3.7.1.1 Related to the Ultimate Heat Sink ML15042A4642015-03-27027 March 2015 Issuance of Amendment No. 231, Request to Revise License Condition Related to Approval of Revised Cyber Security Plan Implementation Schedule ML15063A0102015-03-27027 March 2015 Issuance of Amendment No. 232, Request to Revise Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High 2023-06-27
[Table view] |
Text
July 7, 2020 Mr. Bradley J. Sawatzke Chief Executive Officer Energy Northwest 76 North Power Plant Loop P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION - REDUCTION IN COMMITMENT TO THE OPERATIONAL QUALITY ASSURANCE PROGRAM DESCRIPTION (EPID L-2020-LLQ-0003 [COVID-19])
Dear Mr. Sawatzke:
By letter dated May 18, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20139A225), as supplemented by letter dated June 1, 2020 (ADAMS Accession No. ML20153A471), Energy Northwest (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for approval of a revision to the Columbia Generating Stations (Columbia) Operational Quality Assurance Program Description (OQAPD) that results in a reduction of commitment to the previously accepted quality assurance program in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Section 50.54(a)(4).
Specifically, Energy Northwests submittal requested to implement guidance found in the Electric Power Research Institutes (EPRIs) Technical Report 3002019436, Remote Source Verification During a Pandemic or Similar State of Emergency: Screening Criteria and Process Guidance, for performing remote source verification. The EPRI Technical Report 3002019436 was developed with industry stakeholders, which included NRC staff, to provide the option within a licensees or vendors quality assurance program for remote performance when a source verification is required. Energy Northwests proposed change does not apply to vendor audits or surveys and specifically addresses the vendor surveillance portion of source verification activities identified in the OQAPD. The proposed change provides guidance for the application of video and other real-time communication technologies for the successful performance of remote vendor surveillance. Energy Northwests proposed use of this method of source verification will only be applicable when a pandemic or a similar state of emergency has been declared restricting access or travel to and/or from those locations affected by the declaration.
The NRC staff has reviewed Energy Northwests submittal. Based on the enclosed safety evaluation, the NRC staff concludes that there is reasonable assurance that Columbias OQAPD will continue to meet the requirements of Criterion VII Control of Purchased Material, Equipment, and Services, of Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Therefore, the NRC staff finds the proposed changes to Columbias OQAPD for remote source verification during exigent conditions acceptable.
B. Sawatzke If you have any questions regarding this matter, please contact me at (301) 415-8371 or via e-mail at Mahesh.Chawla@nrc.gov.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
As stated cc: Listserv
ML20181A445
- SE memo via email **via email OFFICE NRR/DORL/LPL4/PM** NRR/DORL/LPL4/LA** NRR/DRO/IQVB/BC* NRR/DORL/LPL4/BC** NRR/DORL/LPL4/PM**
JDixon-Herrity NAME MChawla PBlechman KKavanagh (SLee for) MChawla DATE 6/29/2020 7/6/2020 6/12/2020 7/6/2020 7/7/2020 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR CHANGE TO THE COLUMBIA OPERATIONAL QUALITY ASSURANCE PROGRAM DESCRIPTION ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397
1.0 INTRODUCTION
By letter dated May 18, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20139A225), as supplemented by letter dated June 1, 2020 (ADAMS Accession No. ML20153A471), Energy Northwest (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for approval of a revision to the Columbia Generating Stations (Columbia) Operational Quality Assurance Program Description (OQAPD) that results in a reduction of commitment to the previously accepted quality assurance (QA) program in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Section 50.54(a)(4).
Specifically, Energy Northwests submittal requested to implement guidance found in Electric Power Research Institutes (EPRIs), Technical Report (TR) 3002019436, Remote Source Verification During a Pandemic or Similar State of Emergency, for performing remote source verification. The EPRI TR 3002019436 was developed with industry stakeholders, which included NRC staff, to provide the option within a licensees or vendors QA program for remote performance of a source verification when required during exigent conditions. Energy Northwests proposed change does not apply to vendor audits or surveys and specifically addresses the vendor surveillances portion of source verification activities identified in the OQAPD. The proposed change provides guidance for the application of video and other real-time communication technologies for the successful performance of remote vendor surveillance
[EPRIs source verification]. Energy Northwests proposed use of this method of source verification will only be applicable when a pandemic or similar state of emergency has been declared restricting access or travel to and/or from those locations affected by the declaration.
2.0 REGULATORY BASIS The regulation in 10 CFR 50.54(a)(4) sets forth the NRCs regulatory requirements regarding changes to a QA program description. Changes to a QA program description that reduce the licensees commitments must be submitted and receive NRC approval prior to implementation.
This includes changes made to the QA program description as presented in the safety analysis Enclosure
report or in a topical report that must be submitted as specified in 10 CFR 50.54(a)(4). The submittal of a change to the QA program description must include all pages affected by that change and must be accompanied by a forwarding letter identifying the change, the reason for the change, and the basis for concluding that the revised program incorporating the change continues to satisfy the criteria of Appendix B to 10 CFR Part 50, and the QA program description commitments previously accepted by the NRC.
The regulatory requirement for QA program audits of suppliers is set forth in Criterion VII of Appendix B to 10 CFR Part 50. Criterion VII requires, in part, the establishing of measures for assuring that purchased material, equipment, and services, whether purchased directly or through contractors and subcontractors, conform to the procurement documents. These measures shall include provisions, as appropriate, for source evaluation and selection, objective evidence of quality furnished by the contractor or subcontractor, inspection at the contractor or subcontractor source, and examination of products upon delivery.
3.0 TECHNICAL EVALUATION
Source verifications are typically performed to verify successful completion of certain fabrication and testing activities related to equipment that are complex, expensive, or designated for use in nuclear safety-related applications. Regulatory requirements and guidance related to the use of source verification to accept a basic component for use, either with or without commercial-grade dedication, are provided in Criterion VII of Appendix B to 10 CFR Part 50; NRC Inspection Procedure 43004, Inspection of Commercial-Grade Dedication Programs (ADAMS Accession No. ML16344A092); and EPRI TR 3002002982, Revision 1 to EPRI NP-5652 and TR-102260, Plant Engineering: Guideline for the Acceptance of Commercial-Grade Items in Nuclear Safety-Related Applications, dated September 2014, which was endorsed by NRC Regulatory Guide 1.164, Dedication of Commercial-Grade Items for Use in Nuclear Power Plants, Revision 0, dated June 2017 (ADAMS Accession No. ML17041A206), and defines source verification. In all cases, both the regulatory requirements and guidance refer to source verifications being performed at the contractor or subcontractor source, by direct observation, or at the location of material procurement or manufacture, respectively.
Given technological advances since the requirements of Appendix B were first promogulated, Energy Northwest requested to modify the Columbia OQAPD to utilize the guidance in EPRI TR 3002019436 in lieu of the regulatory requirements of Criterion VII for performing source verifications. The proposed change does not apply to vendor audits or surveys and specifically addresses being limited to remote source verification activities. The change will provide guidance for the application of video and other real-time communication technologies for the successful performance of remote source verification. The use of this method of verification will only be applicable when a pandemic or similar state of emergency has been declared restricting access or travel to and/or from those locations affected by the declaration.
The proposed change will provide an alternate method of performing source verification at the contractor or subcontractor source under certain conditions. During its review, the NRC staff noted that Columbias OQAPD definitions differed from those used in the EPRI TR 3002019436 in that source verification at Columbia includes vendor surveillance, inspections and audits. In the supplemental letter dated June 1, 2020, Energy Northwest clarified the use of the term vendor surveillance which is the existing OQAPD terminology, and its equivalent to the EPRIs term source verification. The functional description of these two terms are the same for Columbias submittal. The use of this method of verification will only be applicable when a pandemic or similar state of
emergency has been declared restricting access or travel to and/or from those locations affected by State and national declarations. The proposed change would not apply to other quality assurance activities, such as vendor audits or surveys used to qualify a vendors QA program.
To incorporate the use of remote source verification, Energy Northwest implemented the following changes to the Columbia OQAPD: (1) Section 7.2.5 was revised to reflect that remote source verification will be performed in accordance with the guidance in EPRI TR 3002019436; (2) the EPRI technical report was incorporated by reference in the Columbia OQAPD; (3) guidance will be used for dedication or as an acceptance method for safety-related purchase orders or contracts; and (4) the application of the guidance will be limited by the application of the EPRI TRs screening questions.
As previously stated, the EPRI TR 3002019436 was prepared to provide licensees and vendors with guidance for using remote communication and video capabilities to perform remote source verification in extreme circumstances where it is not possible to perform onsite source verification due to conditions that threaten the health and safety of individuals performing the verification. The NRC staff reviewed EPRI TR 3002019436 and the quality controls recommended to utilize the technical report guidance. By incorporating the EPRI TR 3002019436 into the Columbia OQAPD, Energy Northwest committed to implementing quality controls that will be in place prior to witnessing the vendor surveillance [source verification], such as:
The ability to review the actual documents and procedures online, as well as preparations, equipment, personnel, and other things going on in the vicinity of the activity.
The ability to ask questions during the process, request adjustments, and doublecheck measurements.
The verifiers field of vision and ability to observe and verify can be adjusted by the frame of the camera or video screen.
The ability to verify the capabilities of the video equipment and individuals operating the video equipment prior to performance of the remote source verification.
EPRI TR 3002019436 provides a screening of the specific source verification to be performed to determine if remote source verification is appropriate for the activities being verified prior to conducting the activity remotely. The EPRI TR 3002019436 required screening employs the following six attributes with associated guidance provided:
- 1. Is it possible to do onsite surveillance?
- 2. Is the activity an assessment?
- 3. Can the activity be surveilled remotely?
- 4. Can progress and results be captured and communicated in real-time?
- 5. Can a maintainable record be created for objective evidence? and
- 6. Does initiating entity concur with the use of remote surveillance?
Further, the screening questions included in Section 4 of EPRI TR 3002019436 were included in Columbias implementing procedure SQI-7-4, Source Surveillance Activities.
The licensee stated that the application of the second screening question of the EPRI TR 3002019436 (Is the activity an assessment?) will ensure that remote source verifications are not used for assessment of activities such as audits or surveys.
Based on the quality controls in place, the NRC staff concluded that remote source verification will be an effective alternative for source verification activities during exigent conditions at Columbia. Although remote source verification cannot fully replace the ability to observe and verify activities at the source, as discussed above, the use of modern communication technologies permits a remote source verification plan to be developed and implemented that will continue to satisfy the relevant criteria of Appendix B to 10 CFR Part 50, providing an equivalent, and therefore, an acceptable level of quality control. As stated above, the proposed change will only apply to source verification activities that can be justified by applying the controls described in the EPRI TR 3002019436.
4.0 CONCLUSION
The NRC staff has reviewed Energy Northwests submittal for implementation of EPRI TR 3002019436 in Columbias OQAPD provided in the letter dated May 18, 2020, as supplemented with clarifications in the letter dated June 1, 2020. Although remote source verification is not intended to replace the ability to observe and verify activities at the source, the NRC staff finds that available technologies can be effectively applied to sufficiently and successfully verify certain activities in extreme circumstances. The NRC staff has reviewed Columbias submittals and the guidance in EPRI TR 3002019436.
The NRC staff has determined that the implementation of EPRI TR 3002019436, as outlined in Energy Northwests submittal, will continue to meet the requirements of Criterion VII of Appendix B to 10 CFR Part 50, and, therefore, is acceptable.
Principal Contributor: Aaron Armstrong Date: July 7, 2020