|
---|
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] Category:Schedule and Calendars
MONTHYEARGO2-23-126, 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 GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report GO2-21-039, Plant Decommissioning Fund Status Report2021-03-11011 March 2021 Plant Decommissioning Fund Status Report GO2-20-054, Decommissioning Funds Status Report2020-03-18018 March 2020 Decommissioning Funds Status Report GO2-19-052, Plant Decommissioning Fund Status Report2019-03-19019 March 2019 Plant Decommissioning Fund Status Report ML15006A3222015-01-16016 January 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML11300A1242012-01-0505 January 2012 Schedule Revision for the Environmental Review of the Columbia Generating Station License Renewal Application ML1005416192010-03-0404 March 2010 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Application from Energy Northwest, for Renewal of the Operating Licenses for the Columbia Generating Station GO2-06-118, Voluntary Response to Regulatory Issue Summary 2006-152006-09-13013 September 2006 Voluntary Response to Regulatory Issue Summary 2006-15 ML18191A2841975-09-16016 September 1975 Wppss Nuclear Project No. 2. Mark II Containment - Supporting Program ML18191A2871975-06-0505 June 1975 Wppss Nuclear Project No. 2. BWR Mark II Containment Additional Design Information ML18191A3011975-01-24024 January 1975 Wppss Nuclear Project No. 2, Schedule for Submission of Requested Additional Information 2023-03-15
[Table view] |
Text
fdRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)
CONTROL NO: IP Z FILE FROM. Was ington Public Pwr DATE OF DOC DATE REC'D LTR 'WX RPT OTHER Richland, Wash JJ Stein' 6<<5-'75 6 ORIG CC OTHER SF-NT 1BC PDR XX TO: Butler DR one signed SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXXXXXXX 1 50-397 DESCRIPTION: ENC LOSUR ES:.
Ltr re their 5-8-75 ltr....furnishing addi info with regard to a schedule BONOT REMOVE for submission of lmaterial dealing with Mark II containment design info ZCKWOWLEDGED PLANT NAME: WPPS 82 FOR ACTION/INFORMATION 6-10-75 . ehf f LER (L) SCHWENCER (L) Zl EMANN (L) REGAN (E)
~BUW/copies W/ Copies W/ Copies W/ Copies CLARK (L) STOLZ (L) DICKER (E) LEAR (L)
W/ Copies W/ Copies W/ Copies W/ Copies PARR (L) VASSALLO (L) KNIGHTON (E) SPIES Vd/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNGBLOOD (E) LPM W/ Copies W/ Copies W/ Copies W/ opuses INTERNAL DISTRIBUTION TFCH REVIEW DENTON LIC ASST A/T IND ~
iNRC PDR SCHROEDER G R I MES R. DIGGS (L) B RA ITMAN
~GC, ROOM P-506A MACCARY GAMMILL H. GEARIN (L) SALTZMAN
~OSS I C K/STA F F KNIG HT KASTNER E. GOULBOURNE (L) ME LTZ ENCASE PAWI ICKI BALLARD P. KREUTZER (E)
~ Is<M BUSSO gBOYD SHAO COSTELLO SPANGLER J.
M.
LEE (L)
MAIGRET (L)
PLANS
~MCDONALD MOORE (L) HOUSTON ENVIRO S. REED (E) CHAPMAN
~DEYOUNG (L) +!OVAK MULLER M. SERVICE (L) DUBE (Ltr).
SKOVHOLT (L) cross(>> DICKER KN IG HTON S. SHEPPARD (L)
SLATER (E)
E. COUPE PETERSON GOLLER (L) (Ltr) IPPO LITO M.
P. COLLINS WEDESCO YOUNGBLOOD H. SMITH (L) HARTFIELD (2)
DENISE LONG BEGAN S. TEETS (L) KLECKF R REG OPR ALAINAS PROJECT LDR G. WILLIAMS(E) EISENHUT WILE 5 REGION (2) BENAROYA V. WILSON (L) Wl G G I NTON MIPC VOLLMER HAR LESS R. INGRAM (L)
M. DUNCAH EXTERNAL DISTR I BUTION
~1 LOCAL PDRW~~Io ~ ~i ~~ PD R-SAN/LA/NY
~1 TIC (ABERNATHY) (1)(2)(10) NATIONALLABS 1 BROOKHAVEN NAT LAB
~1 NSIC (BUCHANAN) 1 W. PENNINGTON, Rrn E-201 GT 1 1 ASLB 1 CON SU LTANTS 1 G. ULRIKSON ORNL 1 Newton Anderson 'NEWMARK/B LUME/AGBABIAN Z/'/- ACRS I~++HSENT 7 0 4, 4, g(o.rgb o4
ll Y
~ ~ ~ I 4 y
h
~ ~
REGULATORY DOCKET FILE COPY Washington Public Power Supply System A JOINT OPERATING AGENCY P. 0. BOX 968 3000 GEO WASHINGTON WAY RICHI.ANDWASHINGTON 99252 PHONE (509) 946.968l Docket No. 50-397 June 5, 1975 G02-75-163 Dr. W.R. Butler, Chief BWR-Projects Branch No. 1-2 ~f/pp YLL Directorate of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20545
<ng~~~rg q+ e~,'~ir>
'6,
~r 4,
.,: I g~
~~ ~)
Subject:
WPPSS NUCLEAR PROJECT NO. 2 BWR MARK II CONTAINMENT ADDITIONAL DESIGN INFORMATION I
References:
- 1) Letter, W.R. Butler to J.J. Stein, Oz Suppression pool hydrodynamic loads 90CKETED QSEERC during LOCA, dated April 17, 1975,,
- 2) Letter, W.R. Butler to J.J. Stein, Pool dynamic loads due to relief valve operation, dated April 23, 1975 JUN P "97~
HIIClEAR REGWAT0 02T CnH ~ c> IO I
~
- 3) Letter, J.J. Stein to W.R. Butler, IIIoll SoHlo BWR Mark II Containment Additional Design Information, dated May 8, 1975 .
Dear Dr. Butler:
This letter provides a schedule for the information requested by refer-ences 1 and 2 as promised by our reference 3. The attachment to this letter provides a schedule and program for resolving your concerns with the Boiling Water Reactor Mark II containment concept. The schedule calls for the submittal of containment present-design data in July 1975 and continues through the first quarter of 1976, with the schedule for final assessment of'containment. We believe for to submit it would be inappropriate us a gross assessment of the highly geometry-related phe-nomena identified in other containment configurations for the WPPSS Nuclear Project No. 2 containment design at this time'.
In the event the results of the program reveal a change or modification to the WPPSS Nuclear Project No. 2 Mark II containment is necessary, we
-will inform you. The WPPSS Nuclear Project No. 2 containment is essen-tially 100Ã complete and the construction pressure test required by'he f
6278
I I/
P I
j
~or. W. R. Butler Page 2 June 5, 1975 G02-.75-163
~, ACME Code is being conducted. it If becomes established that a modifi-cation to the containment vessel is required, we have determined, through contact with our authorized inspection agency (Factory Mutual Engineering),
that certain modifications could be accommodated in this ASME Section III containment vessel. Such modifications would be made in accordance with the ASME Section XI requirements. We therefore do not feel that we are precluding the ability to accommodate modifications to the containment vessel if these become necessary in the future.
Very truly yours,
~
~
J. J. STEIN Managing Director JJS:CLF:vlm Attachment cc: DJ Anderson - Bonneville Power Administration JJ Byrnes - Burns and Roe, Inc, FA MacLean - General Electric Company JJ Verderber - Burns and Roe, Inc,
+C 1
t
ATTACHMENT "A" MARK II SCHEDULE 8( PROGRAM LOCA SRV
~Pro ram Schedule guestions questions Submit plant unique suppression pool and July, 1975 ] 5*
relief valve drawings reflecting current design.
- 2. Submit a generic "Preliminary Forcing Sept., 1975 7* 1*,2,4*,6 Function Report" which will provide the time history of pool dynamic forcing functions and the methods for relating these functions to the containment structures and components.
- 3. Submit a description of a suppression pool Oct., 1975 Not. Appl . 7,8,9,10 temperature monitoring system. (Temperature limits and transients will be described in the Final Safety Analysis Report).
- 4. Submit a plant unique preliminary assess- Nov., 1975 3,4,5,6,7*,8 3,4*,5 ment of containment structures and compo-nents based on the Preliminary Forcing Function Report.
- 5. Submit a schedule for the generic test Dec., 1975 program and mathematical models which justify the forcing functions used to assess containment structures and components.
6 ~ Submit a schedule for the final assess- First quarter ment of containment structures and 1976 components.
'I 4 1 0
I 4 1'
4 P
w1
'I
~'
I
~ \ V E
E J
P V
h I
p V
4 '1
~ ~
L f;
d J'