|
|---|
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] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >
DISTRIBUTION FOR INCOMING MATERIAL TOPREP REC: STOLZ J F QRG: SOBON L J DOCDATE: 07/07/78 NRC GEN ELEC DATE RCVD: 07/ii/78 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: REG FILE~~W/0 ENCL CENTRAL F ILE<<+W/2 ENCL 0" /4 50-322 FILE++LTR ONLY" 50-352 FILE++LTR ONLY 50-353 FILE++LTR ONLY 50-358 FILE<<LTR ONLY FML~LTKJ35I Y 50-374 FILE4+LTR ONLY 50-397 FILE++LTR 0 50-4i0 FILE~~LTR ONLY N FBv~ -T NL STRUCTURAL ENG BR++M/2 ENCL Wllbhw I' CQNTAINMENT SYSTEMS++W/7 ENCL C ANDERSON++W/ENCL AD FOR ENG++W/2 ENCL I PELTIER~~N/ENCL ~"jQgqt W/ M D LYNCI-I~~W/ENCL J SNELL4+W/ENCL
~~2 A BQURNIA++4l/ENCL W KANE>>W/ENCL MZ( DEPUTY S M INERT< W/ENCL DIR DPM++LTR ONLY D
D TIBBETTS++W/ENCL+ j~
VASSALLO++LTR ONLY LWR¹2 CHI EF4 +LTR ONLY LWR¹3 CHIEF44LTR ONLY LWR¹i CHIEF++LTR ONLY AD FOR PLANT SYSTEMS>+LTR ONLY M RUSHBROOK++LTR ONLY W PIKE++LTR ONLY LWR¹4 CHIEF++LTR ONLY EXTERNAL: LPDR S PORT JEFFERSON-PDR++LTR OhlLY POTTSTQWN) PA-PDR~+LTR ONLY BATAVIAiOH-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 CONTROL NBR: 78i920 4i S I ZE: 2P+44P THE END
PROJECTS DIVISION GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MFtI-280-78 MC 681, (408) 925-3495 1
July 7, 1978 U. S. Nuclear Regulatory Commission Division of Project Management Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. John F. Stolz, Chief Light Water Reactor Branch No. 1 Gentlemen:
SUBJECT:
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 'Vp 0
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
