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| {{#Wiki_filter:Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 Richland, WA 99352 | | {{#Wiki_filter:ENERGY Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 NORTHWEST Richland, WA 99352-0968 Ph. 509-377-8555 l F. 509-377-4150 aljavorik@energy-northwest.com EA-13-109 10 CFR 50.54(f) |
| -0968 Ph. 509-377-8555 l F. 509-377-4150 aljavorik@energy | | December 13, 2018 GO2-18-145 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 |
| -northwest.com EA-13-109 10 CFR 50.54(f) | |
| December 13, 2018 GO2-18-145 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk | |
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| Washington, DC 20555
| | ==Subject:== |
| -0001 | | COLUMBIA GENERATING STATION, DOCKET NO. 50-397 ENERGY NORTHWESTS DECEMBER 2018 SIX-MONTH STATUS UPDATE REPORT FOR THE IMPLEMENTATION OF NUCLEAR REGULATORY COMMISSION (NRC) ORDER EA-13-109, PHASE 2 ONLY |
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| | ==References:== |
| | : 1. EA-13-109 from E. J. Leeds (NRC) to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," dated June 6, 2013 (ADAMS ML13143A334 (Pkg.) |
| | : 2. Letter GO2-15-175 from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwests Response to NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Vents under Severe Accident Conditions Phases 1 and 2, Revision 1," dated December 16, 2015 (ADAMS ML15351A363) |
| | : 3. Letter GO2-18-080, from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwests June 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only," dated June 21, 2018 (ADAMS ML18176A186) |
| | : 4. Letter GO2-17-147 from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwests Notification of Full Compliance with Order EA 049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events'", dated August 17, 2017 (ADAMS ML17229B506) |
| | : 5. Letter from J. L. Quichocho (NRC) to M. E. Reddemann (Energy Northwest), "Columbia Generating Station - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order |
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| | G02-18-145 Page 2 of 2 EA-13-109 (Severe Accident Capable Hardened Vents) (CAC NO. |
| | MF4383}," dated September 29, 2016 (ADAMS No. ML15266A233) |
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| ==Subject:== | | ==Dear Sir or Madam,== |
| COLUMBIA GENERATING STATION, DOCKET NO. 50
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| -397 ENERGY NORTHWEST'S DECEMBER 2018 SIX-MONTH STATUS UPDATE REPORT FOR THE IMPLEMENTATION OF NUCLEAR
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| REGULATORY COMMISSION (NRC) ORDER EA-13-109, PHASE 2 ONLY
| | By Reference 1 the Nuclear Regulatory Commission (NRG) issued Order EA-13-109 which required licensees to develop an overall integrated plan (OIP) and submit 6-month update reports in regards to installation and operation of a reliable hardened containment vent capable of operation under severe accident conditions. Reference 2 provided the Columbia Generating Station's revised OIP for Phase 1 of Order EA 109 and the initial OIP for Phase 2 of the Order. Reference 3 transmitted the previous 6-month update report for Phase 2 of NRG Order EA-13-109. Reference 4 reported the completion of activities associated with NRG Order EA-12-049 as well as Phase 1 of NRG Order EA-13-109. |
| | The attachment to this letter provides the required 6-month update report for the remaining Phase 2 activities and open items of Order EA-13-109 as of November 30, 2018 including the Phase 2 request for additional information identified in Reference 5 relating to Columbia's overall integrated plan for severe accident capable hardened vents. |
| | No new commitments are being made by this letter or the enclosure. If you have any questions or require additional information, please contact Ms. D. M. Wolfgramm at (509) 377-4792. |
| | I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on this f!/t"- day of /lee< ,rz~ ~ f' , 2018. |
| | Respectfully, |
| | : tli, A. L. Jav |
| | * Vice Pre ident, Engineering |
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| ==References:== | | ==Attachment:== |
| : 1. EA-13-109 from E. J. Leeds (NRC) to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," dated June 6, 2013 (ADAMS ML13143A334 (Pkg.) 2. Letter GO2 175 from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwest's Response to NRC Order EA 109 - Overall Integrated Plan for Reliable Hardened Containment Vents under Severe Accident Conditions Phases 1 and 2, Revision 1," dated December 16, 2015 (ADAMS ML15351A363) | | As stated cc: NRG RIV Regional Administrator CD Sonoda - BPAf1399 (email) |
| : 3. Letter GO2-18-080, from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwest's June 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only," dated June 21, 2018 (ADAMS ML18176A186) 4. Letter GO2 147 from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwest's Notification of Full Compliance with Order EA 049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events'
| | NRG NRR Project Manager WA Horin - Winston & Strawn NRG Senior Resident lnspector/988C |
| ", dat e d August 17, 2017 (ADAMS ML17229B506) 5. Letter from J. L. Quichocho (NRC) to M. E. Reddemann (Energy Northwest), "Columbia Generating Station - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order
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| GO2-18-145 Attachment Page 1 of 4 1.0 Introduction By Reference 1, the Nuclear Regulatory Commission (NRC) issued Order EA-13-109 to Columbia Generating Station (Columbia). The Order contained requirements for the installation of a reliable containment hardened vent capable of operation under severe accident conditions. Reference 1 also required submittal of an Overall Integrated Plan (OIP) describing how compliance with the requirements described in the Order will be achieved and required the submittal of status reports at six month intervals. This attachment provides Energy Northwest's six-month status repo rt for the remaining Phase 2 milestones, open items, and any changes to the compliance method or schedule. | | GO2-18-145 Attachment Page 1 of 4 1.0 Introduction By Reference 1, the Nuclear Regulatory Commission (NRC) issued Order EA-13-109 to Columbia Generating Station (Columbia). The Order contained requirements for the installation of a reliable containment hardened vent capable of operation under severe accident conditions. Reference 1 also required submittal of an Overall Integrated Plan (OIP) describing how compliance with the requirements described in the Order will be achieved and required the submittal of status reports at six month intervals. This attachment provides Energy Northwests six-month status report for the remaining Phase 2 milestones, open items, and any changes to the compliance method or schedule. |
| 2.0 Milestone Accomplishments As listed below. | | 2.0 Milestone Accomplishments As listed below. |
| 3.0 Milestone Schedule Status The following table provides a listing of the remaining reports associated with NRC Order EA-13-109 as o f November 30, 2018. Correspondence and Reports Milestone Target Completion Date Activity Status Comments (Include date changes in this column) 6-month update for Order EA 109 Phase 2 Dec. 2017 Complete GO2-17-201 6-month update for Order EA 109 Phase 2 June 2018 Completed GO2-18-080 6-month update for Order EA 109 Phase 2 Dec. 2018 Completed This Letter 6-month update for Order EA 109 Phase 2 June 2019 Not Started Issuance of Energy Northwest's letter of compliance with NRC Order EA 109, Phase 2 Aug. 2019 Not Started The following is the status of the overall integrated plan for reliable hardened containment vents (HCV) under severe accident conditions milestones as of November 30, 2018. | | 3.0 Milestone Schedule Status The following table provides a listing of the remaining reports associated with NRC Order EA-13-109 as of November 30, 2018. |
| | Correspondence and Reports Target Comments Activity (Include date Milestone Completion Status changes in this Date column) 6-month update for Order EA-13-109 Dec. 2017 Complete GO2-17-201 Phase 2 6-month update for Order EA-13-109 June 2018 Completed GO2-18-080 Phase 2 6-month update for Order EA-13-109 Dec. 2018 Completed This Letter Phase 2 6-month update for Order EA-13-109 June 2019 Not Started Phase 2 Issuance of Energy Northwest's letter of compliance with NRC Order EA- Aug. 2019 Not Started 13-109, Phase 2 The following is the status of the overall integrated plan for reliable hardened containment vents (HCV) under severe accident conditions milestones as of November 30, 2018. |
| HCV Phase 1 Milestone Schedule: | | HCV Phase 1 Milestone Schedule: |
| Reported complete in letter GO2 147, dated August 17, 2017 - no longer reported. | | Reported complete in letter GO2-17-147, dated August 17, 2017 - no longer reported. |
| | |
| | GO2-18-145 Attachment Page 2 of 4 HCV Phase 2 Milestone Schedule: |
| | Target Comments Activity (Include date Milestone Completion Status changes in this Date column) |
| | This date was Hold preliminary/conceptual design changed to July July 2016 Complete meeting 2017 in letter GO2-16-171 Nov. 2018 Design Engineering On-site/Complete July 2018 Complete No modifications required Operations Procedure Changes Jan. 2019 May 2019 Developed Site Specific Maintenance Procedure Jan. 2019 Developed Training Complete Apr. 2019 Implementation Outage May 2019 Procedure Changes Active May 2019 Walk Through June 2019 Demonstration/Functional Test 4.0 Changes/Updates to Overall Integrated Plan None 5.0 Need for Relief/Relaxation and Basis for the Relief/Relaxation None 6.0 Open Items from Overall Integrated Plan, Interim Staff Evaluation, and Audits The following tables provide an update of the status of the remaining open items as of November 30, 2018. |
| | List of Overall HCV Integrated Plan Open Items HCV OIP Action Status Comment/Update Open Item Provide site-specific details of the EOPs when available. |
| | OI-HCV-10 OPEN Develop procedures for SAWA and SAWM |
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| | GO2-18-145 Attachment Page 3 of 4 List of Overall HCV Integrated Plan Open Items HCV OIP Action Status Comment/Update Open Item SAWA/SAWM flow is controlled using hose installed valves and mechanical flow elements (EA-12-049 actions). |
| | OI-HCV-12 OPEN Location of these valves and flow elements will need to be considered per HCVS-FAQ-12. |
| | Reconcile the out-of-service provisions for HCVS/SAWA with the provisions OI-HCV-13 documented in Columbias PPM OPEN 1.5.18, Managing B.5.b and FLEX Equipment Unavailability. |
| | Complete the evaluation to determine accessibility, habitability, staffing OI-HCV-14 OPEN sufficiency, and communication capability during SAWA/SAWM Perform MAPP analysis for NEI 13-02 OI-HCV-15 figures C-2 through C-6 and determine OPEN the time sensitive SAWM actions Incorporate approved language of OIP OI-HCV-20 Attachment 2.1.D into site SAMG OPEN procedure(s) |
| | Response to the Phase 2 Request for Additional Information RAI Number ISE Report Action Status Comment Section Licensee to determine the location of 1 the FLEX hose installed valves and flow elements, which will be used to OPEN Section 3.2.1 control SAWA/SAWM flow. |
| | Licensee to evaluate the SAWA equipment and controls, as well as 2 |
| | ingress and egress paths for the Section OPEN expected severe accident conditions 3.3.2.3 (temperature, humidity, radiation) for the sustained operating period. |
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| GO2-18-145 Attachment Page 2 of 4 HCV Phase 2 Milestone Schedule: Milestone Target Completion Date Activity Status Comments (Include date changes in this column) Hold preliminary/conceptual design meeting July 2016 Complete This date was changed to July 2017 in letter GO2-16-171 Design Engineering On
| | GO2-18-145 Attachment Page 4 of 4 Response to the Phase 2 Request for Additional Information RAI Number ISE Report Action Status Comment Section Licensee to demonstrate that containment failure as a result of 3 overpressure can be prevented OPEN Section 3.3.3 without a drywell vent during severe accident conditions. |
| -site/Complete July 2018 Complete Nov. 2018 No modifications required Operations Procedure Changes Developed Jan. 2019 May 2019 Site Specific Maintenance Procedure Developed Jan. 2019 Training Complete Apr. 2019 Implementation Outage May 2019 Procedure Changes Active May 2019 Walk Through Demonstration/Functional Test June 2019 4.0 Changes/Updates to Overall Integrated Plan None 5.0 Need for Relief/Relaxation and Basis for the Relief/Relaxation None 6.0 Open Items from Overall Integrated Plan , Interim Staff Evaluation, and Audits The following table s provide an update of the status of the remaining open items as of November 30, 2018. List of Overall HCV Integrated Plan Open Items HCV OIP Open Item Action Status Comment/Update OI-HCV-10 Provide site
| | Licensee shall demonstrate how the plant is bounded by the reference 4 |
| -specific details of the EOPs when available.
| | plant analysis that shows the SAWM Section OPEN strategy is successful in making it 3.3.3.1 unlikely that a drywell vent is needed. |
| Develop procedures for SAWA and SAWM OPEN GO2-18-145 Attachment Page 3 of 4 List of Overall HCV Integrated Plan Open Items HCV OIP Open Item Action Status Comment/Update OI-HCV-12 SAWA/SAWM flow is controlled using hose installed valves and mechanical flow elements (EA 049 actions).
| | Licensee to demonstrate that there is 5 adequate communication between Section the MCR and the operator at the OPEN 3.3.3.4 FLEX pump during severe accident conditions. |
| Location of these valves and flow elements will need to be considered per HCVS-FAQ-12. OPEN OI-HCV-13 Reconcile the out
| | Licensee to demonstrate the SAWM 6 flow instrumentation qualification for Section the expected environmental OPEN 3.3.3.4 conditions. |
| -of-service provisions for HCVS/SAWA with the provisions documented in Columbia's PPM 1.5.18, Managing B.5.b and FLEX Equipment Unavailability.
| | 7.0 Reference |
| OPEN OI-HCV-14 Complete the evaluation to determine accessibility, habitability, staffing sufficiency, and communication capability during SAWA/SAWM OPEN OI-HCV-15 Perform MAPP analysis for NEI 13
| | : 1. EA-13-109 from E. J. Leeds (NRC) to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," dated June 6, 2013 (ADAMS ML13143A334 (Pkg.)}} |
| -02 figures C-2 through C
| |
| -6 and determine the time sensitive SAWM actions OPEN OI-HCV-20 Incorporate approved language of OIP Attachment 2.1.D into site SAMG procedure(s)
| |
| OPEN Response to the Phase 2 Request for Additional Information RAI Number ISE Report Section Action Status Comment 1 Section 3.2.1 Licensee to determine the location of the FLEX hose installed valves and flow elements, which will be used to control SAWA/SAWM flow.
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| OPEN 2 Section 3.3.2.3 Licensee to evaluate the SAWA equipment and controls, as well as ingress and egress paths for the expected severe accident conditions (temperature, humidity, radiation) for the sustained operating period.
| |
| OPEN GO2-18-145 Attachment Page 4 of 4 Response to the Phase 2 Request for Additional Information RAI Number ISE Report Section Action Status Comment 3 Section 3.3.3 Licensee to demonstrate that containment failure as a result of overpressure can be prevented without a drywell vent during severe accident conditions.
| |
| OPEN 4 Section 3.3.3.1 Licensee shall demonstrate how the plant is bounded by the reference plant analysis that shows the SAWM strategy is successful in making it unlikely that a drywell vent is needed. OPEN 5 Section 3.3.3.4 Licensee to demonstrate that there is adequate communication between the MCR and the operator at the FLEX pump during severe accident conditions.
| |
| OPEN 6 Section 3.3.3.4 Licensee to demonstrate the SAWM flow instrumentation qualification for the expected environmental conditions.
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| OPEN 7.0 Reference 1. EA-13-109 from E. J. Leeds (NRC) to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," dated June 6, 2013 (ADAMS ML13143A334 (Pkg.)}}
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Letter Sequence Other |
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Results
Other: GO2-17-201, Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only, GO2-18-145, Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only, GO2-19-082, Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only, GO2-19-100, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109), ML18081A870, NLS2017093, Seventh Six-Month Status Report in Response to Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), NLS2018020, Nebraska Public Power District'S Eighth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, NLS2018058, Nebraska Public Power District'S Ninth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..., NLS2019001, Completion of Required Action for NRC Order EA-13-109 - Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Cooper Nuclear Station, Docket No. 50-298, DPR-46
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MONTHYEARNLS2017093, Seventh Six-Month Status Report in Response to Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2017-12-21021 December 2017
Seventh Six-Month Status Report in Response to Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
Project stage: Other
GO2-17-201, Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2017-12-28028 December 2017
Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
Project stage: Other
ML18081A8702018-03-29029 March 2018
Report for the Audit of Licensee Responses to Interim Staff Evaluations Open Items Related to NRC Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents
Project stage: Other
NLS2018020, Nebraska Public Power District'S Eighth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-06-26026 June 2018
Nebraska Public Power District'S Eighth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
Project stage: Other
ML18215A2042018-08-0606 August 2018
Report for the Audit of Licensee Responses to Interim Staff Evaluations Open Items Related to NRC Order EA-13-109 to Modify Licenses with Re. to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
Project stage: Acceptance Review
NLS2018058, Nebraska Public Power District'S Ninth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ...2018-12-0404 December 2018
Nebraska Public Power District'S Ninth Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ...
Project stage: Other
GO2-18-145, Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2018-12-13013 December 2018
Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
Project stage: Other
NLS2019001, Completion of Required Action for NRC Order EA-13-109 - Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Cooper Nuclear Station, Docket No. 50-298, DPR-462019-01-14014 January 2019
Completion of Required Action for NRC Order EA-13-109 - Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Cooper Nuclear Station, Docket No. 50-298, DPR-46
Project stage: Other
ML19079A0702019-05-0707 May 2019
Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4384; EPID No. L-2014-JLD-0046)
Project stage: Approval
GO2-19-082, Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2019-06-24024 June 2019
Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
Project stage: Other
GO2-19-100, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109)2019-08-20020 August 2019
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109)
Project stage: Other
ML19350B5792020-01-0202 January 2020
Generation Station - Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4383; EPID L-2014-JLD-0045)
Project stage: Approval
2018-06-26
[Table View] |
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Category:Letter type:GO
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024
License Amendment Request to Revise Emergency Plan
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
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
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
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)
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
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
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
GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023
Notification of NPDES Permit Issuance
GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023
Cycle 27 Core Operating Limits Report
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
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
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
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
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
GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023
Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023
Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01
GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022
Guarantee of Payment of Deferred Premium
GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022
Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022
Status of License Renewal Commitments
GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022
Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor
GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022
Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022
Docket No. 50-397, Evacuation Time Estimate Analysis
GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022
Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves
GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022
Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing
GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process
GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022
Registration of Spent Fuel Cask Use
GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022
Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors
GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022
Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report
GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022
Registration of Spent Fuel Cask Use
GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022
2021 Annual Environmental Operating Report
GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022
2021 Annual Radioactive Effluent Release Report
GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022
Registration of Spent Fuel Cask Use
GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022
Level of Financial Protection - Annual Reporting Requirement
GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022
Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46
GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022
Response to Audit Plan and Online Reference Portal Request
GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022
Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report
GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022
License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022
Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report
2024-01-08
[Table view]
Category:Status Report
MONTHYEARGO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023
Plant Decommissioning Fund Status Report
GO2-20-054, Decommissioning Funds Status Report2020-03-18018 March 2020
Decommissioning Funds Status Report
GO2-19-082, Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2019-06-24024 June 2019
Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
GO2-19-052, Plant Decommissioning Fund Status Report2019-03-19019 March 2019
Plant Decommissioning Fund Status Report
GO2-18-145, Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2018-12-13013 December 2018
Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
GO2-18-050, Plant Decommissioning Fund Status Report2018-03-22022 March 2018
Plant Decommissioning Fund Status Report
GO2-17-201, Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2017-12-28028 December 2017
Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
GO2-17-210, Anchor Darling Double Disc Gate Valve Information and Status2017-12-21021 December 2017
Anchor Darling Double Disc Gate Valve Information and Status
GO2-17-118, Second Combined Six-Month Status Update Report for the Implementation of NRC Orders EA-12-049 and EA-13-1092017-06-27027 June 2017
Second Combined Six-Month Status Update Report for the Implementation of NRC Orders EA-12-049 and EA-13-109
GO2-17-058, Confirmatory Order EA-14-240, Element V.J.1 - Sixth Status Update2017-03-14014 March 2017
Confirmatory Order EA-14-240, Element V.J.1 - Sixth Status Update
GO2-16-171, Combined Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Orders EA-12-049 and EA-13-1092016-12-29029 December 2016
Combined Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Orders EA-12-049 and EA-13-109
GO2-16-170, Confirmatory Order EA-14-420, Element V.J.1-Fifth Status Update2016-12-21021 December 2016
Confirmatory Order EA-14-420, Element V.J.1-Fifth Status Update
GO2-16-125, Seventh Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond Design Basis External Events2016-08-30030 August 2016
Seventh Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond Design Basis External Events
GO2-16-098, Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2016-06-30030 June 2016
Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
GO2-16-052, Confirmatory Order EA-14-240, Element V.J.1 - Second Status Update2016-03-24024 March 2016
Confirmatory Order EA-14-240, Element V.J.1 - Second Status Update
GO2-16-037, Sixth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events2016-02-24024 February 2016
Sixth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events
GO2-15-124, Fifth Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events2015-08-25025 August 2015
Fifth Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events
GO2-15-093, Second Six-Month Status Update Report for the Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Vents Under Severe Accident Conditions2015-06-30030 June 2015
Second Six-Month Status Update Report for the Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Vents Under Severe Accident Conditions
GO2-15-034, Northwest'S Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events2015-03-0202 March 2015
Northwest'S Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events
GO2-15-032, Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2015-02-27027 February 2015
Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation
GO2-14-175, First Six-Month Status Update Report for Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Events Under Severe Accident Conditions2014-12-17017 December 2014
First Six-Month Status Update Report for Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Events Under Severe Accident Conditions
GO2-14-105, Cyber Security Plan - Milestone 1-7 Completion Status2014-06-19019 June 2014
Cyber Security Plan - Milestone 1-7 Completion Status
GO2-14-030, Northwest'S Second Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2014-02-27027 February 2014
Northwest'S Second Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation
GO2-13-121, First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2013-08-23023 August 2013
First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation
GO2-13-051, Decommissioning Fund Status Report2013-03-28028 March 2013
Decommissioning Fund Status Report
GO2-12-151, Energy Northwest'S Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation2012-10-25025 October 2012
Energy Northwest'S Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
GO2-07-057, Decommissioning Fund Status Report2007-03-27027 March 2007
Decommissioning Fund Status Report
GO2-05-062, Decommissioning Fund Status Report2005-03-30030 March 2005
Decommissioning Fund Status Report
ML0419402742003-06-16016 June 2003
Event Notification 39945 for Columbia Unit 2
ML0418904332003-06-0909 June 2003
Event # 39910, Columbia Generating Station Re Temporary Loss of Residual Heat Removal Pump Used for Shutdown Cooling
2023-03-15
[Table view] |
Text
ENERGY Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 NORTHWEST Richland, WA 99352-0968 Ph. 509-377-8555 l F. 509-377-4150 aljavorik@energy-northwest.com EA-13-109 10 CFR 50.54(f)
December 13, 2018 GO2-18-145 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 ENERGY NORTHWESTS DECEMBER 2018 SIX-MONTH STATUS UPDATE REPORT FOR THE IMPLEMENTATION OF NUCLEAR REGULATORY COMMISSION (NRC) ORDER EA-13-109, PHASE 2 ONLY
References:
- 1. EA-13-109 from E. J. Leeds (NRC) to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," dated June 6, 2013 (ADAMS ML13143A334 (Pkg.)
- 2. Letter GO2-15-175 from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwests Response to NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Vents under Severe Accident Conditions Phases 1 and 2, Revision 1," dated December 16, 2015 (ADAMS ML15351A363)
- 3. Letter GO2-18-080, from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwests June 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only," dated June 21, 2018 (ADAMS ML18176A186)
- 4. Letter GO2-17-147 from A. L. Javorik (Energy Northwest) to NRC, "Energy Northwests Notification of Full Compliance with Order EA 049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events'", dated August 17, 2017 (ADAMS ML17229B506)
- 5. Letter from J. L. Quichocho (NRC) to M. E. Reddemann (Energy Northwest), "Columbia Generating Station - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order
G02-18-145 Page 2 of 2 EA-13-109 (Severe Accident Capable Hardened Vents) (CAC NO.
MF4383}," dated September 29, 2016 (ADAMS No. ML15266A233)
Dear Sir or Madam,
By Reference 1 the Nuclear Regulatory Commission (NRG) issued Order EA-13-109 which required licensees to develop an overall integrated plan (OIP) and submit 6-month update reports in regards to installation and operation of a reliable hardened containment vent capable of operation under severe accident conditions. Reference 2 provided the Columbia Generating Station's revised OIP for Phase 1 of Order EA 109 and the initial OIP for Phase 2 of the Order. Reference 3 transmitted the previous 6-month update report for Phase 2 of NRG Order EA-13-109. Reference 4 reported the completion of activities associated with NRG Order EA-12-049 as well as Phase 1 of NRG Order EA-13-109.
The attachment to this letter provides the required 6-month update report for the remaining Phase 2 activities and open items of Order EA-13-109 as of November 30, 2018 including the Phase 2 request for additional information identified in Reference 5 relating to Columbia's overall integrated plan for severe accident capable hardened vents.
No new commitments are being made by this letter or the enclosure. If you have any questions or require additional information, please contact Ms. D. M. Wolfgramm at (509) 377-4792.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this f!/t"- day of /lee< ,rz~ ~ f' , 2018.
Respectfully,
- tli, A. L. Jav
- Vice Pre ident, Engineering
Attachment:
As stated cc: NRG RIV Regional Administrator CD Sonoda - BPAf1399 (email)
NRG NRR Project Manager WA Horin - Winston & Strawn NRG Senior Resident lnspector/988C
GO2-18-145 Attachment Page 1 of 4 1.0 Introduction By Reference 1, the Nuclear Regulatory Commission (NRC) issued Order EA-13-109 to Columbia Generating Station (Columbia). The Order contained requirements for the installation of a reliable containment hardened vent capable of operation under severe accident conditions. Reference 1 also required submittal of an Overall Integrated Plan (OIP) describing how compliance with the requirements described in the Order will be achieved and required the submittal of status reports at six month intervals. This attachment provides Energy Northwests six-month status report for the remaining Phase 2 milestones, open items, and any changes to the compliance method or schedule.
2.0 Milestone Accomplishments As listed below.
3.0 Milestone Schedule Status The following table provides a listing of the remaining reports associated with NRC Order EA-13-109 as of November 30, 2018.
Correspondence and Reports Target Comments Activity (Include date Milestone Completion Status changes in this Date column) 6-month update for Order EA-13-109 Dec. 2017 Complete GO2-17-201 Phase 2 6-month update for Order EA-13-109 June 2018 Completed GO2-18-080 Phase 2 6-month update for Order EA-13-109 Dec. 2018 Completed This Letter Phase 2 6-month update for Order EA-13-109 June 2019 Not Started Phase 2 Issuance of Energy Northwest's letter of compliance with NRC Order EA- Aug. 2019 Not Started 13-109, Phase 2 The following is the status of the overall integrated plan for reliable hardened containment vents (HCV) under severe accident conditions milestones as of November 30, 2018.
HCV Phase 1 Milestone Schedule:
Reported complete in letter GO2-17-147, dated August 17, 2017 - no longer reported.
GO2-18-145 Attachment Page 2 of 4 HCV Phase 2 Milestone Schedule:
Target Comments Activity (Include date Milestone Completion Status changes in this Date column)
This date was Hold preliminary/conceptual design changed to July July 2016 Complete meeting 2017 in letter GO2-16-171 Nov. 2018 Design Engineering On-site/Complete July 2018 Complete No modifications required Operations Procedure Changes Jan. 2019 May 2019 Developed Site Specific Maintenance Procedure Jan. 2019 Developed Training Complete Apr. 2019 Implementation Outage May 2019 Procedure Changes Active May 2019 Walk Through June 2019 Demonstration/Functional Test 4.0 Changes/Updates to Overall Integrated Plan None 5.0 Need for Relief/Relaxation and Basis for the Relief/Relaxation None 6.0 Open Items from Overall Integrated Plan, Interim Staff Evaluation, and Audits The following tables provide an update of the status of the remaining open items as of November 30, 2018.
List of Overall HCV Integrated Plan Open Items HCV OIP Action Status Comment/Update Open Item Provide site-specific details of the EOPs when available.
OI-HCV-10 OPEN Develop procedures for SAWA and SAWM
GO2-18-145 Attachment Page 3 of 4 List of Overall HCV Integrated Plan Open Items HCV OIP Action Status Comment/Update Open Item SAWA/SAWM flow is controlled using hose installed valves and mechanical flow elements (EA-12-049 actions).
OI-HCV-12 OPEN Location of these valves and flow elements will need to be considered per HCVS-FAQ-12.
Reconcile the out-of-service provisions for HCVS/SAWA with the provisions OI-HCV-13 documented in Columbias PPM OPEN 1.5.18, Managing B.5.b and FLEX Equipment Unavailability.
Complete the evaluation to determine accessibility, habitability, staffing OI-HCV-14 OPEN sufficiency, and communication capability during SAWA/SAWM Perform MAPP analysis for NEI 13-02 OI-HCV-15 figures C-2 through C-6 and determine OPEN the time sensitive SAWM actions Incorporate approved language of OIP OI-HCV-20 Attachment 2.1.D into site SAMG OPEN procedure(s)
Response to the Phase 2 Request for Additional Information RAI Number ISE Report Action Status Comment Section Licensee to determine the location of 1 the FLEX hose installed valves and flow elements, which will be used to OPEN Section 3.2.1 control SAWA/SAWM flow.
Licensee to evaluate the SAWA equipment and controls, as well as 2
ingress and egress paths for the Section OPEN expected severe accident conditions 3.3.2.3 (temperature, humidity, radiation) for the sustained operating period.
GO2-18-145 Attachment Page 4 of 4 Response to the Phase 2 Request for Additional Information RAI Number ISE Report Action Status Comment Section Licensee to demonstrate that containment failure as a result of 3 overpressure can be prevented OPEN Section 3.3.3 without a drywell vent during severe accident conditions.
Licensee shall demonstrate how the plant is bounded by the reference 4
plant analysis that shows the SAWM Section OPEN strategy is successful in making it 3.3.3.1 unlikely that a drywell vent is needed.
Licensee to demonstrate that there is 5 adequate communication between Section the MCR and the operator at the OPEN 3.3.3.4 FLEX pump during severe accident conditions.
Licensee to demonstrate the SAWM 6 flow instrumentation qualification for Section the expected environmental OPEN 3.3.3.4 conditions.
7.0 Reference
- 1. EA-13-109 from E. J. Leeds (NRC) to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," dated June 6, 2013 (ADAMS ML13143A334 (Pkg.)
