|
---|
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
uS f4/ep REGULATORY INFORMATION DISTR I BUTIGt I SY TEM (RIDS )
DISTRIBUTION FOR INCOMING IIATERIAL TOPRFP PFC: KNIGHT J P ORG: SQBGhl L J DGCDATE: 05/ 01/78 NRC GEN ELEC DATE RCVD: 05/1 1/78 DGCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 El'lCL 70 FORWARD ING G. E. E XECT I VE SUi IMARY REPT AND SUPPLEI'IENT ENT I TLED: "TECH IN I CAL BASIS FGR THE SRSS METHOD OF COMBINING DYNAtI I C RESPONSE" r DTD APRIL( 1: 78r IN SUPPORT OF THE MARK II SUBJECT REPT AND FGR GENERIC CQNSIDERATIGN.
REVIEWER INITIAL: X Jt'I DISTRIBUTOR IN 1TIAL: ~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS TOPICAL RPTS 8. CORRESPONDENCE RE MARK
<DISTRIBUTION CODE TOO2J Il CONTAINMENT INTERNAL: REG FILE<<<<IJ/0 ENCL CENTRAL FILE<<<<IJ/2 ENCL 50-322 FILE<<<<LTR ONLY 50-352 FILE<<<<LTP. ONLY 50-353 FILE<<<<LTR ONLY 50-358 FILE<<<<LTR ONLY 50-367 FILE<<<<LTR ONLY FILE<<<<LTR ONLY 50-374 FILE<<<<LTR ONLY -3'> ILE<<<<LTR GhlLY 50-410 FILE<<<LTR ONLY I SIHWEIL<<<<W/2 ENCL G i PDR<<<<W/ENCL LAINAS<<<<W/7 ENCL J KNIGHT<<<<W/2 ENCL C ANDERSON<<-:~W/EllCL I PELT IER<<<<W/ ENCL M D LYNCH<<<<IJf ENCL J SNELL++W/ENCL A BOURNIA+>W/ENCL M . KANE<<<<W fENCL TIBBETTS<<<<W/ENCL S MINER<<<<W/ENCL D R DEYGUt IG~<<LTR ONL (
D VA SALLO<<<<LTR ONLY K KNIEL<<<<LTR OhlLY Q PARR+<<LTR ONLY J STGLZ-:~<<LTR ONLY R TEDESCO4;<<J TR ghlLY M RUSHBRGGI<<<<<LTR ONLY W PIKE<<-:~LTR ONLY S VARGA<<<<LTR GNI Y EXTERNAL: I PDR S PORT JEFFFRSON-PDR<<<<M/EhlCL PGTTSTOWNi PA-PDR<<<<W/ENCL BATAVIA, OH-PDR<<W/ ENCL CHFSTERTON, IN-PDR<<<<W/ENCL GGLESBY. Il -PDR<<<<M/ENCL RICHLANDi WA-PDR+<<W/ENCL OSWEGO NY-PDR<<<<IJ/ENCL T I C<<-:~W/ENCL NSIC<<<<M/ EhlCL ACRS CAT <<"W/16 ENCL DISTRIBUTlON: LTR 65 ENCL 47 CONTROL NBR:
S I ZF: 2P+48P V
-'t "'I-8 6 4<<<<<<<<-'8+6 ++iHH<<'8 f<<+ 50%<<<<<<-H 0 THE END 781310029'<<<<<<<<<<%<<<<%<<<<<<<<%<<<<<<<<<<<<<<<<<<<<<<<<<<4:.
<<r;-'i
0 ~ ~
6 E M E R AL ' E I. E C QglJgg(Y gft ENERGY PROJECTS DIVISION GENERAL'ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MFN-180- 78 MC 681, (408) 925-3495 Nay 1, 1978
~~ ~J
~P.l U. S. Nuclear Regulatory Commission Division of Systems Safety Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Nr. J. P. Knight Assistant Director For Engineering f1'entlemen:
SUBJECT:
EXECUTIVE
SUMMARY
REPORT AND SUPPLEMENT ENTITLED, "TECHNICAL BASIS FOR THE SRSS METHOD OF COMBINING DYNAMIC RESPONSE", DATED APRIL 1978
Reference:
Letter, LJ Sobon to Olan Parr, dated 8/1/77 transmitting GE Report NEDE-24010-P, "Technical Basis For The Use Of The Square- Root Of The Sum Of Squares (SRSS) Method For Combining Dynamic Loads On Mark II Plants-July 1977" Seventy copies of the subject Summary Report are being provided by General Electric in support of the above referenced Nark II report and for generic consideration.
The purpose of this Executive Summary Report is to highlight the signi-ficant results and conclusions of the Mark II SRSS study and to present important information from subsequent technical studies. A key result that quantitatively demonstrates the dynamic design margin inherent in nuclear plant structures designed to meet ASNE Code (or equivalent) stress limits is shown to be related to the energy absorption capability of the component. For structures exhibiting even moderately ductile behavior, this margin is significantly greater than the ratio of static failure stress to code allowable, and therefore assures sufficient addi-tional margin to protect against structural failure even in the unlikely event that peak combined dynamic response exceeds the SRSS value. Based on the material presented in this Summary Report, it is concluded that the use of SRSS method is technically justifiable and represents a prudent and practical engineering approach for the combination of dynamic responses originating from earthquake, LOCA transient and SRV discharge loadings.
78 1 310029 ~( 0 q 0
~
g
4 GENERAL O'LECTRIC U. S. Nuclear Regulatory Commission Mr. J. P. Knight May 1, 1978 Page 2 Any questions regarding this Summary Report should be directed to K. G. Hazifotis, Containment Licensing Engineer, (408) 925-2209.
Sincerely, L. J. Sobon, Manager BWR Containment Licensing Containment Improvement Programs ,
LJS;gmm/901-902
Enclosures:
Seventy cc: R. J. Mattson (NRC)
R. L. Tedesco (NRC C. Anderson (NRC)
T. M. Su (NRC)
I. Sihweil (NRC)
R. J. Bosnak (NRC)
J. C. Guibert (NRC)
R. S. Boyd (NRC)
R. C. DeYoung (NRC)
L. S. Gifford (GE-BETH)
File 2.10