Letter Sequence RAI |
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TAC:MF2574, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |
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MONTHYEARML13247A0802013-08-13013 August 2013 Full Scope Implementation of the Alternative Source Term Project stage: Request ML13247A0782013-08-31031 August 2013 WCAP-17746-NP, Rev. 0 Westinghouse Setpoint Methodology as Applied to the Wolf Creek Generating Station Project stage: Request ML13247A0792013-08-31031 August 2013 WCAP-17602-NP, Rev. 0, Westinghouse Setpoint Calculations for the Wolf Creek Generating Station Control, Protection, and Indication Systems Project stage: Request ML13345B3352013-12-13013 December 2013 Request for Additional Information, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternative Source Term Project stage: RAI ML13357A2502013-12-23023 December 2013 NRR E-mail Capture - FW: Wolf Creek Generating Station - Request for Additional Information Transition to Westinghouse Core Design and Safety Analysis Project stage: RAI ML13357A2522013-12-23023 December 2013 NRR E-mail Capture - Wolf Creek Generating Station - Request for Additional Information Transition to Westinghouse Core Design and Safety Analysis Project stage: RAI ET 14-0003, Operating Corporation - Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-01-28028 January 2014 Operating Corporation - Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Response to RAI ML14028A1702014-01-28028 January 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review 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 Project stage: RAI ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-02-25025 February 2014 Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Response to RAI 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 Project stage: RAI ML14056A1162014-03-0505 March 2014 Request for Withholding Information from Public Disclosure - 8/9/2013 Affidavit Executed by J. Gresham, Westinghouse WCAP-17446-P, Revision 0, and WCAP-17602, Revision 0 Project stage: Withholding Request Acceptance ML14070A0622014-03-14014 March 2014 Request for Withholding Information from Public Disclosure - 2/14/14 Affidavit Executed by J. Gresham, Westinghouse SAP-14-27-P Attachment Project stage: Withholding Request Acceptance WO 14-0031, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-03-20020 March 2014 Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Response to RAI WO 14-0032, Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-03-26026 March 2014 Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Supplement 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 Project stage: RAI 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 Project stage: RAI WO 14-0043, Supplemental Information in Support of the License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Methodologies2014-05-13013 May 2014 Supplemental Information in Support of the License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Methodologies Project stage: Supplement ET 14-0017, Withdrawal of License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-06-18018 June 2014 Withdrawal of License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Withdrawal ML14176A5052014-06-25025 June 2014 Letter, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: Withdrawal ML14176A5202014-06-25025 June 2014 FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: Withdrawal NRC-2014-0054, FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term2014-06-25025 June 2014 FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: Withdrawal 2014-03-20
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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
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OFFICIAL USE ONLY- PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2014 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION RE: TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS (TAC NO. MF2574)
Dear Mr. Sunseri:
By application dated August 13, 2013, to the U.S. Nuclear Regulatory Commission (NRC)
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML13247A075), Wolf Creek Nuclear Operating Corporation (the licensee) requested a license amendment for Wolf Creek Generating Station, to revise the Technical Specifications to support transition to the Westinghouse core design and safety analysis. Portions of the letter dated August 13, 2013, contain proprietary information and, therefore, those portions have been withheld from public disclosure.
The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed questions were provided to Mr. S. Wideman of your staff on January 17, 2014. Please provide a response to the questions by February 28, 2014.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of NRC staff resources. If circumstances result in the need to revise NOTICE: Enclosure 1 to this letter contains Proprietary Information. Upon separation from , this letter is DECONTROLLED.
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
OFFICIAL USE ONLY- PROPRIETARY INFORMATION M. Sunseri the requested response date, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Request for Additional Information (proprietary)
- 2. Request for Additional Information (non-proprietary) cc w/Enclosure 2: Distribution via Listserv OFFICIAL USE ONLY- PROPRIETARY INFORMATION
ENCLOSURE 2 REQUEST FOR ADDITIONAL INFORMATION (NON-PROPRIETARY)
TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
OFFICIAL USE ONLY- PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By letter dated August 13, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13247A075), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) submitted a license amendment request (LAR) to revise Safety Limits (SLs) 2.1.1, "Reactor Core SLs," Technical Specification (TS) 3.3.1, "Reactor Trip System (RTS)
Instrumentation," TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)
Instrumentation," TS 3.3.5, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation,"
TS 3.4.1, "RCS [Reactor Coolant System] Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits," TS 3.7.1, "Main Steam Safety Valves (MSSVs)," and Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," to replace the existing WCNOC methodology for performing core design, non-loss-of-coolant-accident (non-LOCA) and LOCA safety analyses (for Post-LOCA Subcriticality and Cooling only) with standard Westinghouse developed and U.S. Nuclear Regulatory Commission (NRC)-approved analysis methodologies.
As part of the transition to the generic Westinghouse NRC-approved methodologies, the licensee performed instrumentation setpoint and control uncertainty calculations based on the current Westinghouse Setpoint Methodology. This amendment request also includes the adoption of Option A of Technical Specification Task Force (TSTF) TSTF-493-A, Revision 4, "Clarify Application of Setpoint Methodology for LSSS [Limiting Safety System Settings]
Functions."
2.0 REGULATORY REQUIREMENTS The NRC staff evaluated the LAR against the regulatory requirements and guidance listed below to ascertain whether there is reasonable assurance that the systems and components affected by the LAR will perform their required safety functions when called upon to do so.
2.1 Regulatory Requirements The NRC staff considered the following regulatory requirements:
Title 10 of the Code of Federal Regulations ( 10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," establishes the fundamental regulatory requirements.
Specifically, Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 provides, in part, that
... an application for a design certification, combined license, design approval, or manufacturing license, respectively, must include the principal design criteria for a proposed facility. The principal design criteria establish the minimum necessary design, fabrication, construction, testing, and performance OFFICIAL USE ONLY- PROPRIETARY INFORMATION
OFFICIAL USE ONLY- PROPRIETARY INFORMATION requirements for structures, systems, and components important to safety; that is, structures, systems, and components that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.
General Design Criterion (GDC) 13, "Instrumentation and Control," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires that instrumentation be provided to monitor variables and systems and that controls be provided to maintain these variables and systems within prescribed operating ranges.
GDC 20, "Protection System Functions," of Appendix A to 10 CFR Part 50 requires that the protection system be designed to initiate the operation of appropriate systems to ensure that specified acceptable fuel design limits are not exceeded.
In 10 CFR 50.36, "Technical Specifications," the Commission established its regulatory requirements related to the contents of the TS. Specifically, 10 CFR 50.36 states that "each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section." Specifically, the regulations in 10 CFR 50.36(c)(1 )(ii)(A) state, in part, that Where a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded. If, during operation, it is determined that the automatic safety system does not function as required, the licensee shall take appropriate action, which may include shutting down the reactor.
Additionally, 10 CFR 50.36(c)(3) states, Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
The NRC staff reviewed the proposed LAR against these requirements to ensure that there is reasonable assurance that the systems affected by the proposed LAR will perform their required safety functions.
2.2 Regulatory Guidance Regulatory Guide (RG) 1.1 05, Revision 3, "Setpoints for Safety-Related Instrumentation,"
December 1999 (ADAMS Accession No. ML993560062), describes a method that the NRC staff finds acceptable for use in complying with the NRC's regulations for ensuring that setpoints for safety-related instrumentation are initially within, and will remain within, the TS limits. RG 1.105 endorses Part I of Instrument Society of America (ISA)-S67.04-1994, "Setpoints for Nuclear Safety Instrumentation," which is subject to NRC staff clarifications.
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
OFFICIAL USE ONLY- PROPRIETARY INFORMATION In Regulatory Issue Summary (RIS) 2006-17, "NRC Staff Position on the Requirements of 10 CFR 50.36, "Technical Specifications," Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels," dated August 24, 2006 (ADAMS Accession No. ML051810077), the NRC addresses requirements on limiting safety system settings that are assessed during the periodic testing and calibration of instrumentation.
By letter dated September 7, 2005, from Patrick L. Hiland (NRC) to the Nuclear Energy Institute's Setpoint Methods Task Force, "Technical Specification for Addressing Issues Related to Setpoint Allowable Values" (ADAMS Accession No. ML052500004), footnotes are described that should be added to surveillance requirements related to setpoint verification for instrument functions on which a safety limit has been placed. This letter also addresses the information that should be included within TSs to ensure operability of the instruments following surveillance tests related to instrument setpoints.
2.3 Supplemental Guidance The PWR [Pressurized-Water Reactor] and BWR [Boiling-Water Reactor] Owner's Groups' TSTF-493, Revision 4, dated January 5, 2011, and an errata sheet dated April 23, 2010 (ADAMS Accession No. ML100060064), addresses the NRC staff's concerns stated in RIS 2006-17, and the May 11, 2010, "Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-493, Revision 4, 'Clarify Application of Setpoint Methodology for LSSS Functions"' (75 FR 26294), documents NRC's position on adoption of TSTF-493, Revision 4.
3.0 REQUEST FOR ADDITIONAL INFORMATION The NRC staff has reviewed the instrumentation and controls aspects of the licensee's LAR and concludes that additional information is needed to complete the review:
EICB-RAI-1 On page 56 of WCAP-17602-P, Revision 0, "Westinghouse Setpoint Calculations for the Wolf Creek Generating Station Control, Protection, and Indication Systems," August 2013 (non-proprietary version available in ADAMS at Accession No. ML13247A079), for ((
)) Please provide the necessary information to demonstrate how these numbers have been established to comply with the 95/95 confidence level specified in RG 1.1 05. If they are based on plant drift analysis, then please provide sample calculations to demonstrate the validity of the data.
EICB-RAI-2 Please provide similar information for ((
)) Explain how THE same value for AL T and AFT will provide adequate detection of instrument system degradation during surveillance testing. Provide the criteria beyond which AL T and AFT are assigned different values.
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
OFFICIAL USE ONLY- PROPRIETARY INFORMATION EICB-RAI-3 Please provide samples of plant procedures to demonstrate that adequate measures are being implemented to ensure compliance to TSTF-493-A, Revision 4, Option A, requirements.
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
ML14027A053 (proprietary); ML14027A164 (non-proprietary); *memo dated 1/14/14 OFFICE NRRIDORULPL4-1/PM N RR/DORULPL4-1/LA NRR/DE/EICB/BC* NRRIDORULPL4-1/BC NRR/DORULPL4-1/PM NAME Flyon JBurkhardt JThorp MMarkley Flyon DATE 1/27/14 1/27/14 1/14/14 1/28/14 1/28/14