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| | number = ML083110833 | | | number = ML083110833 |
| | issue date = 11/14/2008 | | | issue date = 11/14/2008 |
| | title = Columbia Generating Station, Request for Additional Information Related to Request for Relief 3ISI-09 | | | title = Request for Additional Information Related to Request for Relief 3ISI-09 |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Parrish J V | | | addressee name = Parrish J |
| | addressee affiliation = Entergy Northwest | | | addressee affiliation = Entergy Northwest |
| | docket = 05000397 | | | docket = 05000397 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555.0001 November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) |
| | Richland, WA 99352-0968 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| COLUMBIA GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850) | | COLUMBIA GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850) |
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| ==Dear Mr. Parrish:== | | ==Dear Mr. Parrish:== |
| By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for NRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program. The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19,2008, to this request for additional information. | | |
| The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for NRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program. |
| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296. | | The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19,2008, to this request for additional information. |
| Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 | | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296. |
| | Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 |
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| ==Enclosure:== | | ==Enclosure:== |
| | As stated cc w/encl: Distribution via ListServ |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NUMBER 50-397 By letter dated October 9, 2008 to the U.S. Nuclear Regulatory Commission (!\IRC), Energy Northwest (the licensee) submitted Relief Request (RR) 31SI-09 for the Columbia Generating Station. The licensee proposes to use an alternative examination which provides less inspection coverage of the weld volume than the volume required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI requirements. The alternative examination is applicable to the welds in the reactor pressure vessel nozzle-to-vessel welds and the nozzle inner radius sections. |
| | The NRC staff requests that the licensee confirm the following related to the welds that are addressed in the RR 3ISI-09. |
| | A. Previous ultrasonic testing results of the subject welds did not reveal any service induced indications. |
| | B. The type of weld metal used in the subject welds is carbon/low alloy steel. |
| | |
| | November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) |
| | Richland, WA 99352-0968 |
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| As stated cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NUMBER 50-397 By letter dated October 9, 2008 to the U.S. Nuclear Regulatory Commission
| | ==SUBJECT:== |
| (!\IRC), Energy Northwest (the licensee) submitted Relief Request (RR) 31SI-09 for the Columbia Generating Station. The licensee proposes to use an alternative examination which provides less inspection coverage of the weld volume than the volume required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI requirements.
| | COLUMBIA GEI\IERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850) |
| The alternative examination is applicable to the welds in the reactor pressure vessel nozzle-to-vessel welds and the nozzle inner radius sections.
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| The NRC staff requests that the licensee confirm the following related to the welds that are addressed in the RR 3ISI-09. A. Previous ultrasonic testing results of the subject welds did not reveal any service induced indications.
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| B. The type of weld metal used in the subject welds is carbon/low alloy steel.
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| November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968 COLUMBIA GEI\IERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850)
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| ==Dear Mr. Parrish:== | | ==Dear Mr. Parrish:== |
| By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for I\IRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program. The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19, 2008, to this request for additional information. | | |
| The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for I\IRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program. |
| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296. | | The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19, 2008, to this request for additional information. |
| Sincerely, IRAI Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 | | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296. |
| | Sincerely, IRAI Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via ListServ DISTRIBUTION: | | As stated cc w/encl: Distribution via ListServ DISTRIBUTION: |
| PUBLIC RidsNrrPMFLyon RidsNrrDciCvib LPLIV Reading RidsNrrLAGLappert GCheruvenki, NRR RidsAcrsAcnw&mMailCenter RidsOgcRp RidsNrrDorlLpl4 RidsRgnMailCenter ADAMS Accession No. ML083110833 | | PUBLIC RidsNrrPMFLyon RidsNrrDciCvib LPLIV Reading RidsNrrLAGLappert GCheruvenki, NRR RidsAcrsAcnw&mMailCenter RidsOgcRp RidsNrrDorlLpl4 RidsRgnMailCenter ADAMS Accession No. ML083110833 / *Memo dated OFFICE NRRlLPL4/PM NRR/LPL4,!lJ ':i. CVIB/BC LPL4/BC NRR/LPL4/PM NAME FLyon )(" GLappert ~ -\ MMitchell* MMarkley "''''_ FLyon ('} |
| / *Memo dated OFFICE NRRlLPL4/PM NRR/LPL4,!lJ | | DATE 11/10108 11/10108 J' ./ 11/5108 lq(~{ol \lJ ,t4 Joil OFFICIAL RECORD COpy}} |
| ':i. CVIB/BC LPL4/BC NRR/LPL4/PM NAME FLyon )(" GLappert -\ MMitchell* | |
| MMarkley "''''_ FLyon ('} DATE 11/10108 11/10108 J' ./ 11/5108 | |
| \lJ ,t4 J oil OFFICIAL RECORD COpy}}
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Letter Sequence RAI |
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MONTHYEARNG-08-0135, Request for NRC Approval of Alternative to Nozzle to Vessel Weld and Inner Radius Examinations2008-02-28028 February 2008
Request for NRC Approval of Alternative to Nozzle to Vessel Weld and Inner Radius Examinations
Project stage: Request
L-08-111, Inservice Inspection Program Relief Request IR-0542008-03-31031 March 2008
Inservice Inspection Program Relief Request IR-054
Project stage: Request
ML0819806282008-07-31031 July 2008
Request for Additional Information, Inservice Inspection Relief Request IR-054
Project stage: RAI
ML0820400462008-08-29029 August 2008
Safety Evaluation for Request for Alternative to Reactor Pressure Vessel Nozzle to Vessel Weld and Inner Radius Examinations Tac MD8193)
Project stage: Approval
L-08-270, Response to Request for Additional Information Regarding Relief Request IR-054, Revision 02008-09-17017 September 2008
Response to Request for Additional Information Regarding Relief Request IR-054, Revision 0
Project stage: Response to RAI
ML0831104542008-11-0606 November 2008
E-Mail Acceptance Review for Columbia Relief Request
Project stage: Acceptance Review
ML0831108332008-11-14014 November 2008
Request for Additional Information Related to Request for Relief 3ISI-09
Project stage: RAI
RS-08-156, Proposed Alternative to 10CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections2008-12-0303 December 2008
Proposed Alternative to 10CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
Project stage: Request
ML0829607292008-12-29029 December 2008
Request for Relief Related to Inservice Inspection Relief Request IR-054
Project stage: Other
ML0902700232009-01-27027 January 2009
Acceptance Review of Proposed Alternative 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
Project stage: Acceptance Review
RS-09-044, Request for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations2009-03-13013 March 2009
Request for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations
Project stage: Request
ML0923003942009-08-24024 August 2009
Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
Project stage: Other
ML0929404362009-11-0303 November 2009
Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations
Project stage: Other
ML1003500962010-02-0101 February 2010
Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 an BWRVIP-108
Project stage: Other
ML1020202572010-07-13013 July 2010
Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108
Project stage: Response to RAI
ML1022901632010-08-25025 August 2010
Relief Request PRR-20, Alternative Examination Requirements for Nozzle-To-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 - Pilgrim Nuclear Power Station
Project stage: Other
JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011
Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP
Project stage: Request
2008-09-17
[Table View] |
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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
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24011A1522024-01-10010 January 2024
March 2024 Emergency Preparedness Exercise Inspection-Request for Information
ML23110A2642023-04-20020 April 2023
Request for Information License Renewal Phase 2 Inspection
ML22343A1802022-12-0808 December 2022
February 2023 Emergency Preparedness Program Inspection - Request for Information
ML22301A1432022-10-28028 October 2022
NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Adopt TSTF-505 - EPID L-2022-LLA-0023
ML22242A1082022-08-30030 August 2022
Information Request, Information Request, Security IR 2022404
ML22235A1052022-08-22022 August 2022
August 2022 Emergency Preparedness Exercise Inspection Request for Information
ML22145A4462022-06-0606 June 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000397/2022401
ML22144A0342022-05-18018 May 2022
NRR E-mail Capture - Draft - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191
ML22041A4572022-02-10010 February 2022
Notification of NRC Design Bases Assurance Inspection (Team) (05000397/2022010) and Request for Information
ML21277A3572021-10-12012 October 2021
CGS Brq RFI Letter, Columbia Generating Station - Notification of Inspection (NRC Inspection Report 05000397/2021004) and Request for Information
ML21216A0502021-08-0303 August 2021
NRR E-mail Capture - Final - Request for Additional Information - Columbia - License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO EPID L-2021-LLA-0259
ML21209A9792021-07-28028 July 2021
NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) - EPID L-2021-LLA-0074
ML21120A1182021-04-30030 April 2021
NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - On-Site Cooling System Sediment Disposal Approval Request - EPID L-2020-LLL-0031
ML21068A2842021-03-0404 March 2021
2021002 Inservice Inspection (ISI) Request for Information (RFI)
ML20336A1852020-11-30030 November 2020
NRR E-mail Capture - Final - RAI - Columbia - One -Time Exemption from 10 CFR 73, App B, Sect VI, Subsection C.3.(l)(1) Regarding Annual Force-On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172
ML20325A0402020-11-19019 November 2020
NRR E-mail Capture - Draft - RAI - Columbia - One -Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force -On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172
ML20267A5162020-09-23023 September 2020
NRR E-mail Capture - Columbia Generating Station - Final - Request for Additional Information - Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-09 - EPID L-2020-LLR-0068
ML20245E2822020-08-31031 August 2020
NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time
ML20239A9702020-08-26026 August 2020
NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time
ML20149K4362020-05-26026 May 2020
NRR E-mail Capture - Formal RAIs for Columbia (COVID-19) QA Plan Change Surveillance, Request Response by Tuesday June 2, 2020
ML20112F4572020-04-21021 April 2020
NRR E-mail Capture - Official Release of NRC RAIs for Columbia Covid Exigent Due Friday April 24, 2020
ML20034E6082020-02-0303 February 2020
NRR E-mail Capture - RAI Formal Release Columbia TSTF 563 LAR, 30 Day Response Period Due March 3, 2020
ML20028E1512020-01-27027 January 2020
Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000397/2020002) and Request for Information
ML19267A1842019-09-24024 September 2019
Request for Information for Upcoming Open Phase Condition Inspection at Columbia Generating Station
ML19232A2282019-08-20020 August 2019
NRR E-mail Capture - Formal Release of RAIs Ref: Columbia Exigent Amendment - One Electrical RAI,
ML19183A4752019-07-0202 July 2019
NRR E-mail Capture - Formal Release of RAIs Ref: Columbia HVAC LAR L-2019-LLA-0034
ML18088A0152018-03-29029 March 2018
Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment Plans (05000397/2018010) and Request for
ML17341B0272017-12-0707 December 2017
NRR E-mail Capture - RAI Associated with Columbia Amendment Request Revise Tech Spec 5.5.12 for Permanent Extension of Type a and Type C Containment Testing Frequencies for MF9469, EPID: L-2017-LLA-0197, ILRT, LLRT LAR - New RAI Response Da
ML17292A0572017-10-18018 October 2017
NRR E-mail Capture - New RWCU RAI Due Date Now November 24, 2017
ML17249A6882017-09-0606 September 2017
NRR E-mail Capture - RAIs for Columbia Relief Request RAI (MF8925), 3ISI-19
ML17205A3152017-07-20020 July 2017
Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000397/2017004) and Request for Information
ML17193A2192017-07-12012 July 2017
NRR E-mail Capture - Columbia RWCU LAR MF8318, Formal Release of RAIs
ML17144A1702017-05-24024 May 2017
NRR E-mail Capture - NRC RAIs for Columbia Relief Request MF8922, 3ISI-16
ML17047A7492017-02-16016 February 2017
Response to Request for Additional Information, Columbia Mur LAR Evib Rais
ML17006A0922017-01-0404 January 2017
NRR E-mail Capture - Eicb RAIs for Columbia Mur
ML17006A0902017-01-0404 January 2017
NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate
ML16356A1382016-12-21021 December 2016
NRR E-mail Capture - Columbia Mur LAR Evib RAIs Non - Proprietary Version - Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate
ML16342C4322016-12-0707 December 2016
NRR E-mail Capture - Columbia Measurement Uncertainty Recapture Power Uprate LAR Rais: Human Performance: MF8060, Formal Release for Response on Monday January 9, 2017
ML16327A1842016-11-22022 November 2016
NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate
ML16323A1192016-11-16016 November 2016
NRR E-mail Capture - Eicb RAIs for Columbia Mur
ML16218A3902016-08-0808 August 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action, Request for Measurement Uncertainty Recapture (Mur) Power Uprate (from 3486 Mwt to 3544 Mwt)
ML16194A3702016-07-11011 July 2016
Notification of NRC Triennial Heat Sink Performance Inspection 05000397/2016003 and Request for Information
ML16069A3592016-03-0909 March 2016
NRR E-mail Capture - Second Round Rais: Columbia MF6042 LAR TSTF-425
ML16061A5542016-03-0101 March 2016
Notification of NRC Design Bases Inspection (05000397/2016007) and Initial Request for Information
ML16061A5662016-03-0101 March 2016
Notification of Design Bases Inspection (Programs)(Inspection Report 05000397/2016008) and Initial Request for Information
ML15254A2572015-09-16016 September 2015
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Reevaluations
ML15215A0432015-08-18018 August 2015
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations
ML14262A3412014-09-24024 September 2014
Request for Additional Information, Round 2, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High
ML14192B0312014-08-13013 August 2014
Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows
ML14206A0112014-07-31031 July 2014
Request for Additional Information, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High
2024-01-10
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850)
Dear Mr. Parrish:
By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for NRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19,2008, to this request for additional information.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
As stated cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NUMBER 50-397 By letter dated October 9, 2008 to the U.S. Nuclear Regulatory Commission (!\IRC), Energy Northwest (the licensee) submitted Relief Request (RR) 31SI-09 for the Columbia Generating Station. The licensee proposes to use an alternative examination which provides less inspection coverage of the weld volume than the volume required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements. The alternative examination is applicable to the welds in the reactor pressure vessel nozzle-to-vessel welds and the nozzle inner radius sections.
The NRC staff requests that the licensee confirm the following related to the welds that are addressed in the RR 3ISI-09.
A. Previous ultrasonic testing results of the subject welds did not reveal any service induced indications.
B. The type of weld metal used in the subject welds is carbon/low alloy steel.
November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GEI\IERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850)
Dear Mr. Parrish:
By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for I\IRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19, 2008, to this request for additional information.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.
Sincerely, IRAI Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
As stated cc w/encl: Distribution via ListServ DISTRIBUTION:
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