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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
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REGULATOR Y DESTRIBUTEGhl FOR REC: STOLZ J F h!RC oq oC/~y INFORMATION DISTRIBUTIOhl SYSTEN (RIDS)INCGt<ItIG MATERIAL TOPREP Q<6=OBOtJ L J DGCDATE: 06/30/7-GEhl FLEC DATE RCVD: 07/06/7 DQCTYPE: LETTER NOTARE"ED:
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GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 (408)925-3495 PROJECTS DIVISION MFN-262-78 June 30, 1978 U.S.Nuclear Regulatory Commission Division of Reactor Licensing Office of Nuclear Reactor Regulation Washington, D.C.20555 Attention:
Gentlemen:
SUBJECT:
Reference:
Mr.John F.Stolz, Chief Light Water Reactors Branch No.1 MARK II CONTAINMENT DYNAMIC FORCING FUNCTIONS INFORMATION REPORT (DFFR), NEDO 21061, REV.3, DATED JUNE 1978 Letter with report,"Mark II Containment Dynamic Forcing Functions Information Report (DFFR), NEDO/NEDE 21061$Rev.2, September 19763," to R.F.Boyd, (NRC)from L.J.Sobon (GE), dated September 1, 1976 Seventy (70)copies of the subject report (NEDO 21061)are being provided by General Electric Company for the Mark II Owners Group for your review as part of the Mark II Containment Supporting Program, Task C.1.This revision to the DFFR updates DFFR Rev.2 (reference) through incorporation of information documented in separate submittals through March 1978.The Revision 3 changes to the DFFR encompass all six (6)Sections of the main text, Appendix B, and the Proprietary Supplement, NEDE 21061-P.(This supplement is being submitted separately.)
Specifically, Sections 1 through 6, while retaining the original format and subject matter', have been extensively rewritten to included information derived from the continuing Mark II Supporting Program, and have been restructured to facilitate a technological flow of topics based on program development.
Significant editorial changes have been made to ensure continuity in view of modifications and additions and to reflect responses to NRC Requests for Additional Information that had been previously incorporated into the DFFR in Appendix A as Amendments 1 and 2 and their Supplements.
Appendix A remains unchanged and is not being replaced at this time.However, the Amendments and Supplements comprising Appendix A are being consolidated and will be submitted later.78187OOPg 0 E,'IE!Ill.ELE Cital C Mr.John C.Stolz June 20, 1978 Page 2 Appendix B previously (in Revision 2)consisted of 162 sheets of computer-generated parametric information; these tables are unchanged but are included in the Revision 3 package for completeness..
Thirty (30)figures providing graphic representation of the data in the Appendix B tables have been relocated from the main text to Appendix B without change except for figure numbering.
The Proprietary Supplement (NEDE 21061-P)has been revised in the same context as the main body of the DFFR.General modification to the report includes the following:
Listing of all DFFR references and Mark II Program-related source documents in a single table in Section 2, rather than following each Section as in previous DFFR revisions; total inclusion of documents submitted as Applications Memorandum such that these documents may be withdrawn as Mark II reference material, if desired in the future;specific identification of referenced material supporting the methodologies described, particularly in the area of confirmatory tests;and the addition of vertical bars in the right side margin numbered to identify Revisions 0 (no bar), 1, 2 and 3.The enclosed report correlates completely with DFFR Revision 2 except for Appendix A (to be consolidated and submitted later)and the Proprietary Supplement (submitted by separate letter).While Revision 3 could entirely supersede Revision 2, the earlier revision is intended to remain an active document, as determined by the individual Mark II Owners to preclude extensive non-technical editorial changes to other plant-specific submittals that reference the DFFR.Future revisions to the DFFR will be provided as significant elements of the Mark II Supporting Program are completed.
Any questions regarding this report should be directed to L.H.Frauenholz, the Mark II Containment Licensing Engineer, telephone number (408)925-2623.Sincerel L.J.Sobon, Manager BWR Containment Licensing LJS:pab/949-950
Enclosures:
70 cc: C.J.Anderson (NRC)H.C.Brinkmann (Mark II Owners Group)H.C.Chau (Mark II Owners Group)L.S.Gifford (GE, Bethesda)I.A.Peltier (NRC)R.L.Tedesco (NRC)Fi 1 e: 3.2.7.c 3.4.4.1 0 I