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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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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>DISTRIBUTION FOR INCOMING MATERIAL TOPREP QRG: SOBON L J DOCDATE: 07/07/78 GEN ELEC DATE RCVD: 07/ii/78 REC: STOLZ J F NRC DQCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
REQUESTING WITHHOLDING PURSUANT TO 2.790 INFO...FORWARDING PROPRIETARY INFO CONSISTING OF MARK I I CONTAINMENT PROGRAM LTR REPT'LEAD PLANT CONTAINMENT R-SPONSE TO IMPROVED CHUGGING LOAD DEFINITION," JUNE i978.REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: P DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS PROPRIETARY TOPICAL RPTS RE MARK II CONTAINMENT (DISTRIBUTION CODE PT02)INTERNAL: Wllbhw I'W/~~2 MZ(REG FILE~~W/0 ENCL 50-322 FILE++LTR ONLY" 50-353 FILE++LTR ONLY FML~LTKJ35I Y 50-397 FILE++LTR 0 N-FBv~-T NL CQNTAINMENT SYSTEMS++W/7 ENCL C ANDERSON++W/ENCL M D LYNCI-I~~W/ENCL A BQURNIA++4l/ENCL S M INERT<W/ENCL DEPUTY DIR DPM++LTR ONLY LWR¹2 CHI EF4+LTR ONLY LWR¹i CHIEF++LTR ONLY M RUSHBROOK++LTR ONLY LWR¹4 CHIEF++LTR ONLY CENTRAL F ILE<<+W/2 ENCL 0"/4 50-352 FILE++LTR ONLY 50-358 FILE<<LTR ONLY 50-374 FILE4+LTR ONLY 50-4i0 FILE~~LTR ONLY STRUCTURAL ENG BR++M/2 ENCL AD FOR ENG++W/2 ENCL Qgqt I PELTIER~~N/ENCL
~"j J SNELL4+W/ENCL W KANE>>W/ENCL D TIBBETTS++W/ENCL+
j~D VASSALLO++LTR ONLY LWR¹3 CHIEF44LTR ONLY AD FOR PLANT SYSTEMS>+LTR ONLY W PIKE++LTR ONLY EXTERNAL: LPDR S PORT JEFFERSON-PDR++LTR OhlLY POTTSTQWN)
PA-PDR~+LTR ONLY BATAVIAi OH-PDR+4LTR ONLY CHESTERTON)
IN-PDR++LTR ONLY OGLESBYr IL PDR++LTR ONLY RICHLANDI WA-PDR++LTR ONLY OSWEGO'Y-PDR++LTR ONLY TERA++LTR ONLY NSIC++LTR ONLY L DREHER W/AFF++LTR ONLY ACRS CAT++W/lb Eh(CL~ZETA~~7 DISTRIBUTION:
LTR 65 ENCL 37 S I ZE: 2P+44P CONTROL NBR: 78i920 4i THE END GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 681, (408)925-3495 1 PROJECTS DIVISION MFtI-280-78 July 7, 1978 U.S.Nuclear Regulatory Commission Division of Project Management Office of Nuclear Reactor Regulation Washington, D.C.20555 Attention:
Gentlemen:
SUBJECT:
Mr.John F.Stolz, Chief Light Water Reactor Branch No.1 MARK II CONTAINMENT PROGRAM LETTER REPORT,"LEAD PLANT CONTAINMENT RESPONSE TO IMPROVED CHUGGING LOAD DEFINITION," JUNE 1978 Twenty (20)copies of the subject letter report are being provided by General Electric Company on behalf of the Mark II Owners Group for information as part of the Mark II Containment Supporting Program, Task A.16.This letter report provides the results of a comparison of the Mark II containment response to the lead plant 4T Bounding Loads Report chugging load specification with that for an improved load specification based on an impulse chug source at the vent.This com-parison was done for a pre-stress concrete, reinforced concrete, and steel containment to show that the 4T bounding load specification is conservative and suitable for lead plant application.
In addition, this study introduces aspects of'mprovement in this load definition for consideration in subsequent plant evaluations.
The enclosed report contains information which the General Electric Company customarily maintains in confidence and withholds from public disclosure.
The information has been handled and classified proprietary by General Electric as indicated in the affidavit submitted with report~i~c s~~iO(~4l'W P(c 0'Vp g GEiIERAL" ELECTRIC J.F.Stol z Page 2 July 7, 1978 NEDE-23617-P by my letter to 0.D.Parr dated August 11, 1977.The request is hereby made that letter report"Lead Plant Containment Response to Improved Chugging Load Definition" be withheld from public disclosure in accordance with 10CFR2.790.
Since this letter report has not been assigned an alpha-numerical identifi-cation and is being provided for your information, we do not intend to submit a non-proprietary version.Very truly urs, L.J.Sobon, Manager BWR Containment Licensing LJS:sj/251"252 Enclosures cc: C.J.Anderson (NRC)I.A.Peltier (NRC)R.L.Tedesco (NRC)H.Chau (Mk II Owners Group)H.C.Brinkman (Mark II Owners Group)L.S.Gifford (GE, Bethesda)Fi 1 e: 3.2.7