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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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 15, 2010 Mr. W.S. Oxenford, Vice President Nuclear Generation and Chief Nuclear Officer Columbia Generating Station Energy Northwest MD PE08 P.O. Box 968 Richland, WA 99352
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION
Dear Mr. Oxenford:
By letter dated January 19, 2010, Energy Northwest submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew Operating License NPF-21 for Columbia Generating Station, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. Abbas Mostala and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4029 or bye-mail at evelyn.gettys@nrc.gov.
Sincerely, Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
As stated cc w/encl: Distribution via Listserv
COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI B.2.A-1 Request for Additional Information (RAil for the Following Aging Management Programs (AMPs):
B.2.12 ("Chemistry Program Effectiveness Inspection")
B.2.14 ("Cooling Units Inspection")
B.2.16 ("Diesel Starting Air Inspection")
B.2.17 ("Diesel System Inspection")
B.2.18 ("Diesel Driven Fire Pumps Inspection")
B.2.27 ("Flexible Connection Inspection")
B.2.30 ("Heat Exchangers Inspection")
B.2.37 ("Lubricating Oil Inspection")
B.2.41 ("Monitoring and Collection Systems Inspection")
B.2.48 ("Service Air Inspection")
B.2.51 ("Supplemental Pipingrrank Inspection")
Background
Under the program element "parameters monitored or inspected," the above applicant AMPs state that "inspections will be performed by qualified personnel using established NDE techniques." GALL Report AMP XI,M32 ("One-Time Inspection") states that inspections are to be performed by qualified personnel following procedures consistent with the requirements of the ASME Code and 10 CFR 50, Appendix B.
Issue The above applicant AMPs do not specifically state that the inspections will be performed in conformance with the requirements of the ASME Code nor does the AMP or AMP basis document reference a site-specific procedure outlining the training requirements for individuals assigned to perform inspections in accordance with the above AMPs.
Request Provide details regarding the training requirements for individuals assigned to perform the inspections described in the above AMPs. Describe how this training program is consistent with training requirements stipulated in the applicable ASME Code requirements.
RAI B.2.A-2 RAI for the Following AMPs:
B.2.12 ("Chemistry Program Effectiveness Inspection")
B.2.14 ("Cooling Units Inspection")
B.2.16 ("Diesel Starting Air Inspection")
ENCLOSURE
-2 B.2.17 ("Diesel System Inspection")
B.2.18 ("Diesel Driven Fire Pumps Inspection")
B.2.27 ("Flexible Connection Inspection")
B.2.30 ("Heat Exchangers Inspection")
B.2.37 ("Lubricating Oil Inspection")
B.2.41 ("Monitoring and Collection Systems Inspection")
B.2.48 ("Service Air Inspection")
B.2.51 ("Supplemental Pipingrrank Inspection")
Background
Under the "detection of aging effects" program element, the above applicant AMPs states that "a sample population will be determined by engineering evaluation based on sound statistical sampling methodology." The GALL Report AMP XI.M32 ("One-Time Inspection") states under this program element that "the inspection includes a representative sample of the system population, and where practical, focuses on the bounding or lead components most susceptible to aging due to time in service, severity of operating conditions, and lowest design margin."
Issue Although the above AMPs require the inspection of a representative sample of the material and environment combinations for systems within the scope of the program, they present no details of the proposed sampling plan and provide no assurance that a representative population of sufficient size and scope will be inspected.
Request Describe the sampling methodology, including how the population for each of the material environment-aging effect combinations is being selected, and what type of engineering, design, or operating experience considerations would be used to select the sample of components for both the scheduled and supplemental inspections.
RAI B.2.49-1
Background
A review of operating experience at Columbia Generating Station (CGS) has indicated that multiple failures of small-bore socket welds have occurred at CGS due to cracking.
Issue GALL Report,Section XI.M35 recommends the use of the One-Time Inspection of ASME Code Class 1 small-bore piping only for those plants that have not experienced cracking of ASME Code Class 1 small-bore piping resulting from stress corrosion or thermal and mechanical loading. For those plants that have experienced cracking, the GALL Report recommends periodic inspection of the subject piping to be managed by a plant-specific AMP.
Request Since cracking of socket welds has occurred at CGS, either provide a plant-specific AMP that includes periodic inspections to manage cracking, or provide justification why a plant-specific AMP that includes periodic inspections is not necessary for ASME Code Class 1 small-bore piping.
-3 RAI 8.2.26-3
Background
Standard Review Plan-License Renewal (SRP-LR) Table 3.3-1, item 84 addresses copper alloy with >15% zinc piping, piping components, piping elements, and heat exchanger components exposed to raw water, treated water, or closed cycle cooling water, and recommends GALL AMP XI.M33, ("Selective Leaching of Materials Program") to manage loss of material due to selective leaching for these components. GALL AMP XI.M33 recommends managing selective leaching of components using a one-time visual inspection and hardness measurement of selected components to determine whether selective leaching is occurring. GALL AMP XI.M27, "Fire Water System Program," does not include activities to manage loss of material due to selective leaching.
License renewal application (LRA) Section B.2.26 states an enhancement to the "acceptance criteria" program element of its Fire Water System Program to include hardness testing, or equivalent, on its sprinkler heads as part of its NFPA testing in order to manage selective leaching. The sprinkler heads are constructed of copper alloy with >15% zinc.
Issue GALL AMP XI.M33 states that if selective leaching is occurring, an engineering evaluation is initiated to determine acceptability of the affected components for further service. GALL AMP XI.M33 also states that, if necessary, the evaluation will include a root cause analysis. In its review of the "detection of aging effects" and "acceptance criteria" program elements described in LRA Section B.2.26 for the Fire Water System Program, and in its basis document, the staff noted that the AMP did not include any details regarding how to detect whether selective leaching has occurred or any acceptance criteria or follow-up evaluations that will be performed if selective leaching is identified.
Request Describe how selective leaching of copper alloy with >15% zinc components will be detected by hardness testing or equivalent methods, and define the acceptance criteria and follow-up actions that will be implemented if selective leaching is identified as part of the activities performed in the Fire Water System Program.
RAJ 3.3.2.2.13-1
Background
GALL Report Section IKF defines wear as follows: "Wear is defined as the removal of surface layers due to relative motion between two surfaces or under the influence of hard abrasive particles. Wear occurs in parts that experience intermittent relative motion, frequent manipulation, or in clamped joints where relative motion is not intended but may occur due to a loss of the clamping force." SRP-LR, Section 3.3.2.2.13, states that loss of material due to wear could occur in the elastomer seals and components exposed to air-indoor uncontrolled (internal or external). The GALL Report recommends further evaluation to ensure that these aging effects are adequately managed. Acceptance criteria are described in Branch Technical Position RLSB-1 (Appendix A.1 of this SRP-LR.)
-4 LRA Section 3.3.2.2.13 refers to LRA Table 3.3.1, item 3.3.1-34, and addresses loss of material due to wear for elastomer seals and components exposed to air-indoor uncontrolled (internal or external). The applicant addressed the further evaluation criteria of the SRP-LR by stating that wear of elastomer seals and components exposed to air-indoor was not identified as an aging effect requiring management. The applicant also stated that loss of material due to wear is the result of relative motion between two surfaces in contact and wear occurs during the performance of an active function as a result of improper design, application or operation; or to a very small degree with insignificant consequences, and therefore, loss of material due to wear is not an aging effect requiring management for elastomers exposed to air-indoor uncontrolled.
Issue The staff does not have sufficient information to determine that improper design, application or operation is not a factor resulting in loss of material due to wear in elastomeric components exposed to air-indoor uncontrolled.
Request Provide justification why improper design, application or operation is not a factor resulting in the loss of material due to wear for elastomeric components exposed to an air-indoor uncontrolled environment, or provide an AMP to manage this aging effect.
RAI 3.3.2.3-1 Backqround The GALL Report does not contain a recommended AMR line item for elastomers exposed to lubricating oil or fuel oil. However, in LRA Tables 3.3.2-20 and 3.3.2-22, the applicant stated that for elastomer flexible connections exposed to lubricating or fuel oil there is no aging effect and no AMP is proposed.
Issue Resistance of natural rubber to lubricating or fuel oil is poor (P.A. Schweitzer, - Corrosion Resistance Tables - Metals, Nonmetals, Coatings, Mortars, Plastics, Elastomers and Linings, and Fabrics, Fifth Edition, Marcel Dekker, 2004). The staff does not have sufficient information to determine that there is no aging effect for this material/environment combination.
Request Provide additional information (e.g., elastomer material type, fuel oil and lube oil composition) that would demonstrate that the plant-specific applications for the elastomer and fuel or lube oil environment does not have an aging effect requiring management during the extended period of operation or provide an AMP to manage any applicable aging effect.
RAI 3.5.2.3-1
Background
GALL Report Table III A6, Group 6 Structures (Water-Control Structures), line item III.A6-12 (TP-7) recommends that AMP XI.S6, ("Structures Monitoring Program"), should be used to manage the aging effects of loss of sealing/deterioration of seals, gaskets, and moisture barriers
-5 (caulking, flashing, and other sealants) for elastomers exposed to various environments. In LRA Table 3.5.2-13, Bulk Commodities, Waterstops, the applicant stated that for elastomer waterstops exposed to air-indoor (within walls, floors, or foundation) there is no aging effect and no proposed AMP.
Issue Continuous waterstops are provided in the reactor building at all horizontal and vertical construction joints in exterior walls and interior walls between and including the top of the foundation mat. High temperature and radiation could exist in the reactor building walls, floors, and foundation mat, and could cause hardening and loss of strength for the elastomer components. The staff does not have sufficient information to determine that there is no aging effect for this material/environment combination.
Request Provide justification why hardening and loss of strength due to elastomer degradation for elastomer waterstops exposed to air-indoor (within walls, floors, or foundation) is not considered an aging effect requiring aging management.
Time Limited Aging Analysis (TLAA)
RAI4.2.1-1
Background
Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," states that the core neutron source should be determined by the power distribution, the power level, and the fuel management scheme.
Issue LRA Section 4.2.1 states that 54 effective full power year (EFPY) fluence values were extrapolated from 51.6 EFPY fluence values.
Request Please confirm that the flux used for this extrapolation was that assumed for post-Cycle 11, uprated operation. If it is not, please provide the basis for the assumed flux value and justify its use.
July 15, 2010 Mr. W.S. Oxenford, Vice President Nuclear Generation and Chief Nuclear Officer Columbia Generating Station Energy Northwest MD PE08 P.O. Box 968 Richland, WA 99352
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION
Dear Mr. Oxenford:
By letter dated January 19, 2010, Energy Northwest submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew Operating License NPF-21 for Columbia Generating Station, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. Abbas Mostala and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4029 or bye-mail at evelyn.gettys@nrc.gov.
Sincerely, IRA!
Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
See next page ADAMS Accession No ..'ML101900125 OFFICE PM:RPB1:DLR LA:DLR BC: RPB1 :DLR PM:RPB1:DLR NAME EGettys SFigueroa BPham EGettys IDATE 07/12/10 07/12/10 07/14/10 07/15/10 OFFICIAL RECORD COpy
Letter to W.S. Oxenford from Evelyn H. Gettys dated July 15, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION DISTRI BUTION:
HARDCOPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource EGettys DDoyle FLyon WWalker, RIV RCohen, RIV LSubin,OGC