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Category:Letter type:ET
MONTHYEARET 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 ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
[Table view] Category:Status Report
MONTHYEARWM 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) ML17361A0732017-12-20020 December 2017 Submittal of Anchor Darling Double Disc Gate Valve Information and Status ET 16-0018, Seventh Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.2016-08-18018 August 2016 Seventh Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. ET 16-0008, Sixth Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.2016-02-17017 February 2016 Sixth Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. ET 15-0006, Operating Corporation, Fourth Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.2015-02-24024 February 2015 Operating Corporation, Fourth Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. ET 15-0005, Operating Corporation'S Fourth Six - Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-02-24024 February 2015 Operating Corporation'S Fourth Six - Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ET 14-0025, Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.2014-08-21021 August 2014 Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. ET 14-0010, Operating Corporation'S Second Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation2014-02-26026 February 2014 Operating Corporation'S Second Six-Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ET 13-0026, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13102A3012013-03-29029 March 2013 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(0)(1) ML11181A1492011-06-23023 June 2011 Revision of Information Provided in 10 CFR 50.75 Report on Status of Decommissioning Funding ML1109506592011-03-29029 March 2011 CFR 50.75 Report on Status of Decommissioning Funding ML0910002882009-03-31031 March 2009 CFR 50.75 Report on Status of Decommissioning Funding ML0807300242008-02-22022 February 2008 Status Report and Proposed Agenda for the ACRS Subcommittee on March 5, 2008 Related to the License Renewal Application of Wolf Creek Generating Stations Unit 1 ML0709900532007-03-29029 March 2007 CFR 50.75 Report on Status of Decommissioning Funding ML0509603662005-03-30030 March 2005 10 CFR 50.75 Report on Status of Decommissioning Funding ML0224007812002-01-18018 January 2002 E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report 2023-05-10
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W$LFCREEK NUCLEAR OPERATING CORPORATION John P. Broschak Vice President Engineering February 26, 2014 ET 14-0010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
- 1) Letter dated March 12, 2012, from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Issuance of Order to Modify Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation"
- 2) NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order EA-12-051, "Reliable Spent Fuel Pool Instrumentation," Revision 0, dated August 29, 2012
- 3) NEI 12-02, "Industry Guidance for Compliance with NRC Order EA 051, 'To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation,"' Revision 1, dated August 2012
- 4) Letter ET 12-0028, dated October 29, 2012, from J. P. Broschak, WCNOC, to USNRC
- 5) Letter WO 13-0015, dated February 28, 2013, from R. A. Smith, WCNOC, to USNRC
- 6) Letter ET 13-0026, dated August 28, 2013, from J. P. Broschak, WCNOC, to USNRC
Subject:
Docket No. 50-482: Wolf Creek Nuclear Operating Corporation's Second Six-Month Status Report for the Implementation of Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation" Gentlemen:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Order EA-12-051 (Reference 1) to Wolf Creek Nuclear Operating Corporation (WCNOC). Reference 1 was immediately effective and directs WCNOC to install reliable spent fuel pool level instrumentation. Specific requirements are outlined in Attachment 2 of Reference 1.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 AccI An Equal Opportunity Employer M/F/HCNET o \(_
ET 14-0010 Page 2 of 3 Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an Overall Integrated Plan (OIP) pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-02, Revision 1 (Reference 3) with clarifications and exceptions identified in Reference 2.
Reference 4 provided the WCNOC initial status report regarding mitigation strategies.
Reference 5 provided the WCNOC OIP. Reference 6 provided the first six-month status report for the implementation of Order EA-1 2-051.
Reference 1 requires submission of a status report at six-month intervals following submittal of the OIP. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the second six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The attached report provides an update of milestone accomplishments since the submittal of Reference 6, including any changes to the compliance method, schedule, or need for relief and the basis for requests for relief, if any.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4085, or Mr. Michael J. Westman at (620) 364-4009.
Sincerely, John P. Broschak JPB/rlt Attachment cc: M. L. Dapas (NRC), w/a C. F. Lyon (NRC), w/a N. F. O'Keefe (NRC), w/a Senior Resident Inspector (NRC), w/a
ET 14-0010 Page 3 of 3 STATE OF KANSAS )
COUNTY OF COFFEY )
John P. Broschak, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Jo . Broschak Vi President Engineering SUBSCRIBED and sworn to before me this 2z-V day of re ,2014.
GAYLE SHEPHEARD Notaryaublio Z Notary Public - State of Kansas My Appt. Expires Q A,-.L Expiration Date I
'A/2L/~T/
Attachment ET 14-0010 Page 1 of 3 Wolf Creek Nuclear Operating Corporation's Second Six-Month Status Report for the Implementation of Order EA-12-051, "Issuance of Order to Modify Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation" Wolf Creek Nuclear Operating Corporation (WCNOC) developed an Overall Integrated Plan (OIP) (Reference 1), documenting the modification with regard to Reliable Spent Fuel Pool (SFP) Instrumentation in response to Reference 2. This attachment provides an update of milestone accomplishments since submittal of the first six-month status report, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
- 1. Milestone Accomplishments WCNOC has selected and entered into a purchase agreement to procure SFP level instruments that, when installed, will meet criteria designated in the OIP (Reference 1).
- 2. Milestone Schedule Status There are no changes to the status of the milestones submitted in the OIP (Reference 1).
Provided is the activity status of each item, and whether the expected completion date has changed. The dates are planning dates and are subject to change as design and implementation details are developed.
Target Revised Milestone Completion Activity Status Target Date Completion Date Commence Engineering and Design 1 Q2013 Complete Complete Design 4Q2013 Complete Submit 6 Month Updates:
Update 1 Aug 2013 Complete Update 2 Feb 2014 Complete Update 3 Aug 2014 Not Started Update 4 Feb 2015 Not Started Receipt of SFP Instruments 3Q2014 Not Started Complete SFP Instrumentation Procedures 4Q2014 Not Started
& Training SFP Instruments Operational 1Q2015 Not Started
Attachment ET 14-0010 Page 2 of 3
- 3. Changes to Compliance Method WCNOC will no longer pursue installation of a wireless spent fuel pool level indication (SFPLI) system and will instead install a wired SFPLI system. The overall operation and layout of the system remains the same however, the level signal is now provided via installed robust cabling to the readout panels.
- 4. Need for RelieflRelaxation and Basis for the Relief/Relaxation WCNOC expects to comply with the order implementation date and no relief/relaxation is required at this time.
- 5. Open Request for Additional Information (RAI)
Reference 4 provided WCNOC's responses to an NRC RAI (Reference 3). In Reference 4, WCNOC indicated that additional information would be provided in the February 2014 6-month status update report. Subsequently, the NRC issued the Interim Staff Evaluation (Reference 6) which was based, in part, on information provided in References 4 and 5. As noted in Reference 6, new RAI questions were developed based on the information provided in References 4 and 5. Reference 6 indicated that responses to the RAI questions should be provided in the 6-month status updates, as the information becomes available. WCNOC is still developing the information for responding to the RAI questions identified in Reference 6 and will provide the information no later than the requested date of July 31, 2014.
References
- 1. WCNOC Letter WO 13-0015, "Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements For Reliable Spent Fuel Pool Instrumentation," February 28, 2013. ADAMS Accession No. ML13071A419.
- 2. Letter from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Issuance of Order to Modify Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation," March 12, 2012. ADAMS Accession No. ML12056A044.
- 3. Letter from C. F. Lyon, USNRC, to M. W. Sunseri, WCNOC, "Wolf Creek Generating Station - Request for Additional Information RE: Overall Integrated Plan in Response to Order EA-12-051, 'Reliable Spent Fuel Pool Instrumentation' (TAC NO. MF0781)," July 17, 2013. ADAMS Accession No. ML13197A205.
- 4. WCNOC Letter ET 13-0025, "Wolf Creek Nuclear Operating Corporation's Response to Request for Additional Information Regarding Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Level Instrumentation," August 15, 2013.
- 5. WCNOC Letter ET 13-0026, "Wolf Creek Nuclear Operating Corporation's First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)," August 28, 2013.
ADAMS Accession No. ML13252A238.
Attachment ET 14-0010 Page 3 of 3
- 6. Letter from C. F. Lyon, USNRC, to M. W. Sunseri, WCNOC, "Wolf Creek Generating Station - Interim Staff Evaluation and Request for Additional Information RE: Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Instrumentation (TAC NO. MF0781)," October 29, 2013. ADAMS Accession No. ML13295A681.