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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
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Sudesh K. Gamobhir ENG Vice President, Technical Services NO TH ES Ph. Richland, WA 99352-0968 vJ- "' P.O. Box 968, PEO4 NORT W ESTPh. 509.377.8313 1 F. 509.377.2354 sgamnbhir@
energy-northwest.corn September 21, 2009 G02-09-132 10 CFR 50.54(f)U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Subject; COLUMBIA GENERATING STATION, DOCKET.NO.
50-397 SUPPLEMENTAL (POST-OUTAGE)
RESPONSE TO NRC GENERIC LETTER 2008-01
References:
- 1. NRC Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling; Decay-Heat Removal, and Containment Spray Systems," dated January 11,.2008 2. Energy Northwest Letter, "Nine-Month Response to NRC Generic Letter 2008-01, 'Managing Gas Accumulation
- in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,'dated October 8, 2008 3. NRC Letter from C.F. Lyon (NRC) to J.V. Parrish (Energy'Northwest),"Columbia Generating Station -Re: Generic Letter 2008-01,'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems' Proposed Alternative Course of Action (TAC No. MD7812)" dated August 21, 2008
Dear Sir or Madam:
The Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01 (Reference
- 1) to request that each licensee evaluate the licensing basis, design, testing, and corrective actions for the emergency core cooling system (ECCS), decay heat removal (DHR), and containment spray systems to ensure that gas accumulation is.maintained less than the amount that challenges operability of these systems, and that appropriate action is taken when conditions adverse to quality are identified.
Please find attached Energy Northwest's post-outage supplementaliresponse to the* nine-month response letter (Reference 2). This supplemental response is being submitted within 90 days of startup from the-refueling outage, as requested by the NRC in Reference 3, for actions that were deferred until the next refuelingoutage.
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'_j ,-SUPPLEMENTAL (POST-OUTAGE)
RESPONSE TO NRC GENERIC LETTER 2008-01 Page 2 In summary., Energy Northwest has concluded that the subject systems at Columbia Generating Station remain operable with respect to the concerns outlined in GL 2008-01 regarding managing gas accumulation in these systems.There are no new commitments being made to the NRC by this letter beyond those previously referenced by Energy Northwest in Reference
- 2. If you have any questions, please contact MC Humphreys, Licensing Supervisor, at (509) 377-4025.I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter.uctfully, SK Gambhir Vice President, Technical Services Attachment cc: EE Collins, Jr. -NRC RIV NJ DiFrancesco
-NRC NRR NRC Senior Resident Inspector/988C WA Horin -Winston & Strawn RN Sherman -BPA/1 399 SUPPLEMENTAL (POST-OUTAGE)
RESPONSE TO NRC GENERIC LETTER 2008-01 Attachment Page 1 of 2 This attachment provides the Supplemental (Post-Outage)
Response to Generic Letter (GL) 2008-01 for actions that were deferred until the next refueling outage as requested by the NRC in Reference 3 of the cover letter.A. EVALUATION RESULTS 1. Design Basis Documents A number of minor clarifications were added to technical analyses based on information from GE Reports that were previously discussed in Energy Northwest's (EN) nine-month response to the GL. In addition, allowable time frames for air to vent from the emergency core cooling system (ECCS) which have either local vent pipes or extended vent pipes directed to floor drains were documented.
- 2. Confirmatory Walkdowns An evaluation was performed regarding the need to walkdown and/or ultrasonic test remaining inaccessible regions of residual heat removal (RHR) B discharge piping as well as all related ECCS, containment spray, and residual heat removal system piping located in the primary containment.
Based on this evaluation, it was concluded that no further walkdowns of the remaining piping were necessary.
This was based on the following:
ECCS (i.e., high pressure core spray (HPCS), low pressure core spray (LPCS), and low pressure coolant injection (LPCI)) discharge piping from the containment penetration into the reactor vessel is located downstream of motor operated injection valves. As documented in EN's nine-month response, an analysis of ECCS piping downstream of the injection valves has concluded that the existence of air voids will have no adverse consequences related to accident conditions.
Containment spray discharge paths downstream of the containment isolation valves are voided by design.ECCS suppression pool discharge (return) paths entering the containment discharge directly into the Suppression Pool through open ended connections that are below the water level. A section of the return piping is above the suppression pool water level. The configuration of these return lines coupled with the atmospheric pressure of the wetwell will keep these lines full of water.SECGCS suppression pool suction between the containment penetration and the suppression pool involves entirely submerged piping." The remaining RHR B discharge piping outside of the containment is inaccessible due to physical restrictions.
Drawing reviews of this 18 inch piping indicates that this section is horizontal and approximately 43 feet in SUPPLEMENTAL (POST-OUTAGE)
RESPONSE TO NRC GENERIC LETTER 2008-01-Attachment Page 2 of 2 length with all branch lines dropping from the bottom of the main piping. The branch line for the test line to the suppression pool originates off this line near the downstream end and is flow tested quarterly.
The minimum required Froude number of 0.60 with 3000 gpm flow will ensure entrained or trapped air is removed from the system. The quarterly test involves flows of at least 7100 gpm into the wetwell. This test was last performed on September 15, 2009.3. Vent Valves Evaluations have been completed regarding two locations on HPCS discharge piping and one location on LPCS discharge piping. Although not required, the conclusion was made that the addition of valves at these locations could aid in venting affected portions of piping when other means were not available (e.g., dynamic flushing).
Plans have been initiated to develop design change packages to support addition of the vent valves.4. Procedures No new procedure changes beyond those documented in Energy Northwest's nine-month response to the GL were required.B. DESCRIPTION OF NECESSARY ADDITIONAL CORRECTIVE ACTIONS 1. Additional Corrective Actions No new corrective actions were identified.
- 2. Corrective Action Updates All corrective actions identified in Columbia's nine month response to the GL have been completed with the exception of the following:
0 Correct HPCS drawing discrepancies. (Currently scheduled for completion on 9/30/09 per AR 00176497-27.)
0 Evaluate the feasibility of adding tubing to RHR B system high point vent.(Currently scheduled for completion on 10/20/09 per AR 00176497-33.)
Conclusion Energy Northwest has evaluated the previously unevaluated portions of the applicable systems at Columbia that perform the functions described in the GL and has concluded that these systems remain operable.