Letter Sequence RAI |
---|
|
|
MONTHYEARET 08-0045, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2008-10-10010 October 2008 Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Request ML0917403912009-07-0909 July 2009 Request for Additional Information, Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems Project stage: RAI ET 09-0020, Response to Request for Additional Information Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2009-08-17017 August 2009 Response to Request for Additional Information Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Response to RAI ML0926002472009-10-28028 October 2009 Closure Letter for Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Other 2009-10-28
[Table View] |
|
---|
Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 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 ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22361A0052022-12-27027 December 2022 NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements ML22321A2662022-11-16016 November 2022 January 2023 Emergency Preparedness Program Inspection - Request for Information ML22307A1372022-11-0202 November 2022 August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information ML22249A2552022-06-29029 June 2022 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000482/2022012 ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22055A1142022-02-23023 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time ML22045A4512022-02-14014 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling ML22025A3612022-01-21021 January 2022 PI&R RFI Final ML21327A2602021-11-23023 November 2021 NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21271A1952021-09-28028 September 2021 E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021 ML21253A0902021-09-23023 September 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment and Regulatory Exemption for a Risk-Informed Approach to Address GSI-191 (EPIDs L-2021-LLA- 0152 and L-2021-LLE-0039) ML21221A1282021-08-0505 August 2021 NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise ML21132A1032021-05-12012 May 2021 Document Request List, Paperwork Reduction Act Statement ML20302A4782020-10-28028 October 2020 OPC R1 Request for Information ML20262A7512020-09-17017 September 2020 NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425 ML20195A2712020-07-13013 July 2020 Generation Station - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2020012) and Request for Information ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19346E6052019-11-0404 November 2019 Target Set Request for Information for Week of November 4, 2019 ML19224A5242019-08-12012 August 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5 ML18304A1052018-11-0505 November 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML18282A6402018-10-0909 October 2018 NRR E-mail Capture - Request for Additional Information - Wolf Creek Generating Station License Amendment Request for Revision to the Emergency Plan ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses ML18207A4332018-07-24024 July 2018 NRR E-mail Capture - (External_Sender) Draft Request for Additional Information Relief Request from ASME Code N-666-1 Alternate Repair of Essential Service Water Piping Wolf Creek Generating Station, Unit 1 EPID No.:L-2018-LLR-0101 ML18116A6132018-04-25025 April 2018 Operating Corporation - Notification of Inspection (NRC Inspection Report 05000482/2018002) and Request for Information ML17331A1782017-12-0404 December 2017 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML17291A7102017-10-17017 October 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17265A0142017-09-21021 September 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses ML17170A3152017-06-19019 June 2017 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2017008) and Request for Information ML17166A0382017-06-14014 June 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17052A0282017-02-15015 February 2017 NRR E-mail Capture - Wolf Creek Generating Station - Official EAL RAIs ML16319A4282016-11-14014 November 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Requests 13R-14 and 13R-15 ML16300A2662016-10-21021 October 2016 Request for Additional Information - Relief Request I3R-13 Regarding Weld Examination Coverage IR 05000482/20160022016-08-0303 August 2016 NRC Integrated Inspection Report 05000482/2016002 ML16110A3722016-04-25025 April 2016 Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16020A1392016-01-15015 January 2016 Notification of NRC Component Design Bases Inspection (05000482/2016007) and Initial Request for Information ML15135A4862015-05-14014 May 2015 Wc 2015007 17T RFI ML15082A0052015-03-27027 March 2015 Request for Additional Information, Round 2, Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15079A0762015-03-23023 March 2015 Request for Additional Information, Round 2, Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML15040A6252015-02-10010 February 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14323A5742014-12-0404 December 2014 Request for Additional Information, License Amendment Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in USAR ML14230A7572014-08-21021 August 2014 Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML14206A0122014-08-0101 August 2014 Request for Additional Information, Relief Requests I3R-08, RPV Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14197A3362014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval ML14148A3872014-06-0202 June 2014 Request for Additional Information Related to Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML14111A1002014-04-30030 April 2014 Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14083A4002014-04-0303 April 2014 Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14058A0882014-03-0505 March 2014 Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14027A1622014-01-28028 January 2014 Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term 2022-06-29
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 9, 2009 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 WOLF CREEK GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RELATED TO RESPONSE TO GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7896)
Dear Mr. Muench:
By letter dated October 10, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082950487), Wolf Creek Nuclear Operating Corporation (WCNOC) provided a response to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," for Wolf Creek Generating Station. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in letter dated October 10, 2008, and determined that additional information is needed in order to complete the review. A draft copy of the request for additional information was forwarded to Ms. Diane Hooper on June 18, 2009. WCNOC did not request further discussion to clarify the request for additional information and agreed to provide a response within 45 days of the date of this letter. If you have any questions, please contact me at 301-415-3016.
Sincerely, Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION RESPONSE TO GENERIC LETTER 2008-01! "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 By letter dated October 10, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082950487), Wolf Creek Nuclear Operating Corporation (WCNOC) provided a response to Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," for Wolf Creek Generating Station (WCGS). The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in letter dated October 10, 2008, and determined that the following additional information is needed in order to complete the review. Guidance on NRC staff expectations is provided in the NRC letter dated May 28, 2009 (Reference 1). As clarified in Nuclear Energy Institute (NEI) communications, this gUidance is generally consistent with NEI guidance provided previously to industry in its letter dated March 20,2008 (Reference 2). The NRC staff recommends that the licensee provides its response to the Request for Additional Information using the guidance provided by Reference
- 1. Potential Gas Intrusion Mechanisms (Section A.2.1 0 of Submittal dated October 10, 2008) The WCNOC response to GL 2008-01 (Reference
- 3) stated that the safety injection (SI) accumulator level is monitored from the plant computer and a pre-determined level change causes an email alert to the system engineer.
Please provide the follow-up actions the system engineer will perform if a pre-determined level change occurs in a SI accumulator and identify the process that ensures the actions. WCNOC did not address the potential for gas to come out of solution as it passes through the containment emergency sump screens where it may collect and then pass into the pipes leading to the pumps. Please provide analysis that supports resolution of this issue. It is not apparent from the WCNOC response that actions are encompassed suitably in procedures so that an acceptable response will be obtained if a decreasing accumulator level is observed.
Please clarify this item. Enclosure
-2 Gas Volume Acceptance Criteria Versus Location (Section A.2.2 of Submittal dated October 10, 2008) WCNOC stated that the current design acceptance criterion for the subject systems is "full," by which it means water-solid.
It further considers that gas volume at high points is an expected condition following a system draindown and refill. Therefore, it uses void criteria that are based on a void fraction at the pump inlet of less than 2 percent even for short-term transients.
If these criteria are met, then a degraded but operable condition is assumed until corrective actions that are tracked in the Corrective Action Plan (CAP) can be completed to remove the gas. With the exception of identification of a 0.25 cubic foot discharge pipe criterion that it considers unlikely to cause water hammer, the criteria and associated gas transport methodology for meeting the 2 percent criterion are not identified.
Please provide the pipe/component acceptance criteria and associated gas transport methodology for meeting the pump inlet 2 percent criterion.
Pump Acceptance Criteria (Section A.2.11 of Submittal dated October 10, 2008) WCNOC is silent regarding the NRC staff Reference 4 criterion for pump response to gas of 1 percent. Please provide reference to a plant-specific document for updating WCGS's criteria, if needed, with respect to the NRC staff's Reference 4 criteria.
If unavailable, please provide plans and schedules for completing the analysis. Please provide a rationale for the inconsistency between the WCGS pump inlet void criterion and the NRC staff's criterion for steady-state void fraction if the efficiency ratio is outside 40 or 120 percent. Long-term industry tasks were identified that will provide additional tools to address GL 2008-01 with respect to pump gas-void ingestion tolerance limits. Please provide reference to a plant-specific document that describes your plan for addressing information that is obtained from long-term industry tasks. Walkdown Acceptance Criteria and Completed Walkdown Results (Section A.2.6 of Submittal dated October 10. 2008) The NRC staff considers the following criteria to be acceptable for obtaining dimensional data for the subject systems: Straight 10 feet or longer piping run. Piping run that has a vent. Horizontal run that has a reducer, reducing tee, valve, or line size change on the same elevation. 10 feet or longer run made up of segments connected by elbows or fittings.
-For any run with a tee, such that if the tee run segment lengths are added to the pipe length, the total is over 10 feet. Pipe 4 inches or greater nominal pipe size of any length. Pipe or tubing that provides cooling to subject system components. Pipe or tubing that is associated with instrumentation if a gas/liquid combination can occur in piping or tubing that is supposed to contain a single phase so that the instrumentation indication is significantly affected. The section of any vertical pipe 1 inch or greater nominal pipe size that is located below a valve that may be closed when in operation so that gas can be trapped below the valve. The WCGS walkdown acceptance criteria differ from the NRC staff's criteria.
Please discuss and justify the effect of the differences. The laser metrology selection criteria focuses on horizontal piping and do not address sloped or vertical configurations.
Please address this focus with respect to the NRC staff's criteria that cover sloped and vertical components as well. Some pipe and component sections may have insulation in place. WCNOC did not describe how these items were dimensionally assessed.
Describe the dimensional assessment of pipes and component sections that have insulation in place. A 10-foot length of 6-inch diameter pipe could contain 0.5 cubic feet of gas if full at one end and empty at the other due to being sloped. This is inconsistent with the 0.25 cubic feet acceptance criterion that WCNOC previously stated it would apply to voids. The NRC staff uses a criterion of 4-inch diameter that avoids this discrepancy.
Please discuss and provide a resolution. Containment Spray (CS) system discharge piping segments were not considered for walkdowns because they are not required to be filled with water prior to system actuation.
The CS header and nozzles are stated to be designed to withstand the impulse of a water hammer at the commencement of flow. However, WCNOC did not address potential low elevations in the piping where a water slug could collect with a potential for water hammer. Evaluate the potential for water to collect and cause a water hammer in low points in CS system discharge piping or establish that such low points do not exist. Incomplete Items and Completion Schedule (Section A.2.6 of Submittal dated October 10, 2008) Following vent installations, the potential cumulative unventable gas void volumes created by slopes in horizontal pipes is stated to be less than 3 cubic feet for systems discharge piping, and less than 0.5 cubic feet for suction piping. These values are
-inconsistent with the 0.25 cubic feet criterion.
Please address and resolve these differences.
Surveillance Procedures (Section A.2.2 of Submittal dated October 10, 2008) Please address accessibility criteria based on potential radiological dose and potential heat stress hazard. Please contrast this with the need for surveillances to ensure subject system operability since coverage appears to be limited to accessible locations.
Please include a definition of "accessible locations" and associated criteria.
Please discuss how system operability is assured for inaccessible locations.
Training Training was not identified in the GL but is considered to be a necessary part of applying procedures and other activities when addressing the issues identified in the GL. This was identified in the NEI template (Reference
- 2) as an item that should be addressed in the GL responses and was discussed in the NEI workshop (Reference 5). This is not addressed in the WCNOC response.
Please provide a brief description of planned training and its schedule.
REFERENCES William H. Ruland, U.S. Nuclear Regulatory Commission, to James H. Riley, Nuclear Energy Institute, "Preliminary Assessment of Responses to Generic Letter 2008-01, 'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,'
and Future NRC Staff Review Plans," dated May 28,2009 (ADAMS Accession No. ML091390637). Nuclear Energy Institute (NEI), "Generic Letter (GL) 2008-01, 'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Contain Spray Systems' Evaluation and 3 Month Response Template," Letter to Administrative Points of Contact from Director, Engineering, Nuclear Generation Division, NEI, Enclosure 2, "Generic Letter 2008-01 Response Guidance," dated March 20,2008. Terry J. Garrett, Wolf Creek Nuclear Operating Corporation, to U.S. Nuclear Regulatory Commission, "Docket No. 50-482: 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 10,2008 (ADAMS Accession No. ML082950487). Warren C. Lyon, U.S. Nuclear Regulatory Commission, "Revision 2 to NRC Staff Criteria for Gas Movement in Suction Lines and Pump Response to Gas," dated March 26, 2009 (ADAMS Accession No. ML090900136). Nuclear Energy Institute, "System Gas Accumulation Management Workshop," Laguna Cliffs Spa &Resort, Dana Point, CA, February 11-12,2009.
July Mr. Rick A. President and Chief Executive Wolf Creek Nuclear Operating Post Office Box Burlington, KS WOLF CREEK GENERATING STATION -REQUEST FOR INFORMATION RELATED TO RESPONSE TO GENERIC LETTER "MANAGING GAS ACCUMULATION IN EMERGENCY CORE DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" NO.
Dear Mr. Muench:
By letter dated October 10, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082950487), Wolf Creek Nuclear Operating Corporation (WCNOC) provided a response to Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," for Wolf Creek Generating Station. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in letter dated October 10, 2008, and determined that additional information is needed in order to complete the review. A draft copy of the request for additional information was forwarded to Ms. Diane Hooper on June 18, 2009. WCNOC did not request further discussion to clarify the request for additional information and agreed to provide a response within 45 days of the date of this letter. If you have any questions, please contact me at 301-415-3016.
Sincerely, IRA by James R. Hall fori Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAJBurkhardt Resource LPLIV Reading RidsNrrPMWolfCreek Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource RidsNrrDssSrxb Resource WLyon, NRRIDSS/SRXB ADAMS Accession No ML091740391
- Memo dated 6/17/2009 OFFICE NRRlLPL4/PM NRRlLPL4/LA DSS/SRXB/BC NRR/LPL4/BC NRRlLPL4/PM NAME BSingal .IBurkhardt GCranston*
MMarkley BSingal JRHall for DATE 6/29/09 6/26/09 6/17/09 7/8109 7/9/09 OFFICIAL RECORD COPY