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Category:Letter type:GO
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan 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 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 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 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) 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 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 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 GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report 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 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 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 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 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 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022 Docket No. 50-397, Evacuation Time Estimate Analysis GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022 Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022 Registration of Spent Fuel Cask Use GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022 Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022 Registration of Spent Fuel Cask Use GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022 2021 Annual Environmental Operating Report GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022 2021 Annual Radioactive Effluent Release Report GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022 Registration of Spent Fuel Cask Use GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022 Level of Financial Protection - Annual Reporting Requirement GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022 Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022 Response to Audit Plan and Online Reference Portal Request GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022 Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022 Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report 2024-01-08
[Table view] Category:Quality Assurance Program
[Table view] |
Text
ENERGY NORTHWEST PO. Box 968
- Richland, Washington 99352-0968 October 23, 2003 G02-03-165 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397, REDUCTION OF COMMITMENT TO THE OPERATIONAL QUALITY ASSURANCE PROGRAM DESCRIPTION
Dear Sir or Madam:
Energy Northwest, in accordance with 10 CFR 50.54(a)(4), is proposing changes to the NRC approved topical report "Operational Quality Assurance Program Description (OQAPD)
(WPPSS-QA-004)" and hereby requests NRC approval because this proposed revision would result in a reduction of commitment.
This revision to the OQAPD is necessary to update Appendix III, Additional Quality Program Requirements, Section 2.1.6.e, regarding Plant Operations Committee (POC) responsibilities.
The attachment provides a mark-up of the proposed changes.
Appendix III, Section 2.1.6.e of the OQAPD currently contains a commitment for POC to investigate all violations of the plant or ISFSI Technical Specifications, including the preparation and forwarding of reports covering the evaluation and recommendations to prevent recurrence, to the Chief Nuclear Officer (CNO) and to the Corporate Nuclear Safety Review Board (CNSRB).
The proposed change to this section would reduce POC responsibilities to a review function, maintain POC as an independent review body, and allow POC to concentrate on issues that affect nuclear safety as described by ANSI N18.7-1976 and endorsed by Regulatory Guide 1.33, "Quality Assurance Program Requirements (Operation)."
ANSI N18.7-1976, Section 4.3.4 states that "The following subjects shall be reviewed by the independent review body." Of these review subjects, Section 4.3.4(4) describes "Violations, deviations and reportable events, which require reporting to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, such as: (a) Violations of applicable codes, regulations, orders, technical specifications, license requirements, internal procedures or instructions having safety significance."
REDUCTION OF COMMITMENT TO THE OPERATIONAL QUALITY ASSURANCE PROGRAM DESCRIPTION Page 2 Investigations of violations that affect nuclear safety are conducted by line organizations, in accordance with the corrective action program, under the guidance of the performance Management Department. The Performance Management Department reports directly to the Vice President, Nuclear Generation. The results of these investigations, including recommendations to prevent recurrence, are forwarded for review to POC, the CNO, and the CNSRB.
Should the NRC provide written approval of this request or if no response is received from the NRC during the 60 days following this letter, Energy Northwest will implement the changes described in the OQAPD in accordance with 10 CFR 50.54(a)(4)(iv).
Should you have any questions or desire additional information regarding this matter, please call Ms. CL Perino at (509) 377-2075.
Respectfully, DW Coleman, Manager Performance Assessment and Regulatory Programs Mail Drop PE20 Attachment cc: BS Mallett - NRC - RIV TC Poindexter - Winston & Strawn NRC Sr. Resident Inspector - 988C BJ Benney - NRC - NRR RN Sherman - BPA/1399
ENERGY NORTHWEST PAGE 11-2 OPERATIONAL REV.
QUALITY ASSURANCE PROGRAM DESCRITON _ ____ _
1.1.5 Written records of activities associated with independent technical reviews shall be prepared, maintained, and forwarded to the manager responsible for quality assurance.
2.0 REVIEW AND AUDIT 2.1 PLANT OPERATIONS COMMITTEE (POC)
The POC shall function to advise the manager responsible for plant operations and ISFSI on all matters related to nuclear safety.
2.1.1 The POC shall be composed of individuals experienced in one of the following functional areas:
Operations Administrative Services Maintenance Radiation Protection Engineering Technical Services Quality Chemistry 2.1.2 The manager responsible for plant operations and ISFSI, the POC Chairman, shall appoint, in writing, the POC Vice Chairman, and individual members.
The qualifications of all members shall meet the requirements of ANSI/ANS-3.1-1981, Section 4.7, and have cumulative expertise in the areas listed in 2.1.1, as a minimum.
2.1.3 All POC alternate members shall be appointed in writing by the POC Chairman or Vice Chairman to serve on a temporary basis.
2.1.4 The Plant Operations Committee shall meet at least once per calendar month and as convened by the POC Chairman or his designated alternate.
2.1.5 The quorum of the POC necessary for the performance of the POC responsibility and authority provisions of these requirements shall consist of the Chairman or Vice Chairman and four members including alternates. No more than two alternates shall make up the quorum.
2.1.6 The POC shall be responsible for:
- a. Review of 10CFR50.59 and 10CFR72.48 Evaluations associated with procedures and programs required by plant and ISFSI Technical Specifications and changes thereto;
- b. Review of all proposed tests and experiments that affect nuclear safety;
- c. Review of all proposed changes to the plant or ISFSI Technical Specifications; 25060 W:XOQAPD\OQAPDAPP.111
r1 ENERGY NORTH WEST PAGE-3 OPERATIONAL REV. Xo QUALITY ASSURANCE PROGRAM DESCRIPTION I
- d. Review of all proposed changes or modifications to plant or ISFSI system or equipment that affect nuclear safety; e.
f.
N
'In stigation of all 'lations of tnblant or ISFS echnical
- Specifiations, includin ve preparatib and forwar g of reports
{ covering0 uation and re Chief Nucekar Officer and the Rev woard;N endatiori§ to prevent r rrence, to Nuclear S ty Review of all REPORTABLE EVENTS, as specified in 10CFR50.73 I
and 10CFR72.75;
- g. Review of plant and ISFSI operations to detect potential hazards to CZ M nuclear safety;
- h. Performance of special reviews, investigations, or analyses and Co reports thereon as requested by the manager responsible for plant operations and ISFSI or the Corporate Nuclear Safety Review Board;
- i. Review of the Security Plan and submittal of recommended changes hi i j.
to the Corporate Nuclear Safety Review Board; Review of the Emergency Plan and submittal of recommended changes to the Corporate Nuclear Safety Review Board;
.- k. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Chief Nuclear
- 4) 4 Officer and to the Corporate Nuclear Safety Review Board; and
.- 0
- l. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
4)-
2.1.7 The POC shall:
Cu 13 o C a. Recommend in writing to the manager responsible for plant operations and ISFSI approval or disapproval of items considered under Appendix III, 2.1.6a. through d. prior to their implementation.
0
- b. Render determinations in writing with regard to whether or not each item considered under Appendix III, 2.1.6a. through e. requires prior NRC approval as defined in IOCFR50.59 and 10CFR72.48.
W:%OQAPD\OQAPDAPP.III