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Category:Letter
MONTHYEARIR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 L-24-025, Submittal of the Updated Final Safety Analysis Report, Revision 352024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24255A8032024-09-11011 September 2024 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) 2024-09-06
[Table view] Category:Order Modifying License
MONTHYEARL-16-230, Request for Schedule Relief/Relaxation from NRC Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-07-11011 July 2016 Request for Schedule Relief/Relaxation from NRC Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML12054A7352012-03-12012 March 2012 Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML12054A6792012-03-12012 March 2012 Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ML12056A0452012-03-12012 March 2012 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2012-03-12012 March 2012 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML0519603542005-07-15015 July 2005 EA-04-224, Commitments to Be Confirmed by Order Modifying License (Effective Immediately) ML0333605172004-02-26026 February 2004 Letter, Conditions to Be Confirmed by Order Modifying License (Effective Immediately) ML0402201812004-02-20020 February 2004 Issuance of Revised NRC Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0307004282003-03-14014 March 2003 Errata to Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0318204412003-03-0606 March 2003 Email Dated March 6, 2003, from Dr. Ed Siegel to A. Hiser, W. Bateman, and T. Chan, Fwd: Fyi: Questions? Comments? ML0303804702003-02-11011 February 2003 Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0304103852003-02-11011 February 2003 Plant Service Lists Attachment to Order - Reactor Vessel Head and Nozzle Inspection ML0300603602003-01-0707 January 2003 Issuance of Order for Compensatory Measures Related to Access Authorization ML0228700082002-10-16016 October 2002 Enclosures 1 & 2, Order for Interim Safeguards & Compensatory Measures for Dry Independent Spent Fuel Storage Installation & Regulatory Issuance Summary 2002-12D 2016-07-11
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Text
February 26, 2004 EA-03-214 Mr. Lew W. Myers Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - CONDITIONS TO BE CONFIRMED BY ORDER MODIFYING LICENSE (EFFECTIVE IMMEDIATELY)
(TAC NO. MC1335)
Dear Mr. Myers:
As a result of FirstEnergy Nuclear Operating Company (FENOC) identification of extensive degradation of the reactor pressure vessel head, the Nuclear Regulatory Commission (NRC) issued Confirmatory Action Letter (CAL) No. 3-02-001 on March 13, 2002. The CAL documented commitments that FENOC was expected to fulfill prior to restart of the Davis-Besse Nuclear Power Station, Unit 1. These commitments included meeting with the NRC to obtain restart approval.
On November 23, 2003, FENOC submitted the Integrated Report to Support Restart of the Davis-Besse Nuclear Power Station and Request for Restart Approval, and concluded that the plant, programs, and personnel were ready to support safe operation, subject to completion of a few well-defined work activities prior to restart. That letter outlined FENOCs commitments regarding post-restart continuing improvement initiatives and self and external assessments to assure lasting performance improvement and requested that the NRC schedule a meeting as stated in the CAL and then approve restart. A meeting was originally scheduled for December 18, 2003, to discuss restart. However, due to self-revealing equipment and operational problems and issues identified by NRC Restart Readiness Assessment and the Management and Human Performance inspection teams, the meeting was delayed.
During the course of the extended shutdown of Davis-Besse beginning in February 2002, FENOC conducted a number of thorough evaluations and self-assessments. Several examples include the evaluation of system design, the assessment of the completeness and accuracy of docketed information, the evaluation of operational performance deficiencies during the normal operating pressure test, and the evaluation of the failure to comply with technical specification requirements during testing of the steam and feedwater rupture control system. However, self-assessments of operational performance prior to both the normal operating pressure test in September 2003, and the NRCs Restart Readiness Assessment Team Inspection in December 2003 failed to identify a number of deficiencies. Additionally, NRC inspections earlier during the shutdown discovered issues not originally identified through Davis-Besse
L. Myers self-assessments, most notably in the corrective action program, in the quality of engineering evaluations, calculations and analyses, and in safety culture. The NRC recognizes that FENOC has implemented significant corrective actions resulting in improved performance to address the CAL and the NRC Davis-Besse Oversight Panel Restart Checklist. Notwithstanding the improved performance, consistently effective FENOC self-assessments are an important factor in assuring lasting corrective actions for the deficiencies that resulted in the reactor pressure vessel head degradation.
To ensure effective assessment and sustained safe performance in the areas of operations, engineering, and corrective actions at Davis-Besse, the NRC has determined that additional measures are needed to provide the requisite assurance should restart of Davis-Besse be authorized. Therefore, the NRC will issue an Order modifying License No. NPF-3, requiring independent assessments and mid-cycle inspections to provide reasonable assurance that the long-term corrective actions remain effective.
FENOC may inform the NRC whether it will consent to the enclosed conditions by providing written response to the Regional Administrator at NRC Region III, 801 Warrenville Road, Lisle, IL 60532-4351, within five working days of the date of this letter. If you consent, I request that you sign the enclosed Consent and Hearing Waiver form and return it to the above address. By signing the enclosed form, the management of FENOC will agree to have those conditions incorporated into a Confirmatory Order that will be immediately effective upon issuance and FENOC will waive any and all rights to a hearing concerning the Order.
This letter does not imply that permission from the NRC to restart will be forthcoming.
However, NRC restart authorization is contingent upon the conditions in the Order being in effect. The NRC plans to issue the Order regardless of your consent.
If you have any questions, please call me at 630-829-9657.
Sincerely,
/RA/
James L. Caldwell Regional Administrator Docket No. 50-346
Enclosures:
- 1. Consent and Hearing Waiver Form
- 2. Conditions to be confirmed by Order See Attached Distribution
ML033360517 *Previously concurred OFFICE PDIII-2/PM PDIII-2/LA PDIII-2/SC Tech Ed PDIII/D DLPM/D NAME FLyon* PCoates* AMendiola** PKleene* WRuland* LMarsh*
DATE 2/6/04 2/6/04 2/11/04 2/6/04 2/18/04 2/17/04 OFFICE OE OGC 0350 NRR/ADPT NRR/D DEDO RIII/RA NAME DNelson* SBurns* JGrobe** BSheron JDyer SCollins* JCaldwell for FCongel for LChandler BBorchardt for DATE 2/18/04 2/18/04 2/11/04 2/18/04 2/19/04 02/24/04 L. Myers cc w/encl: The Honorable Dennis Kucinich G. Leidich, President - FENOC Plant Manager Manager - Regulatory Affairs M. OReilly, Attorney, FirstEnergy Ohio State Liaison Officer R. Owen, Administrator, Ohio Department of Health Public Utilities Commission of Ohio President, Board of County Commissioners Of Lucas County C. Koebel, President, Ottawa County Board of Commissioners D. Lochbaum, Union Of Concerned Scientists J. Riccio, Greenpeace P. Gunter, N.I.R.S.
L. Myers ADAMS Distribution:
PUBLIC PDIII-2 r/f OGC SJC1 JBH1 WHR BWS AJM DFT SPS1 JED2 DJN LBM CFL OEMAIL LBC RidsNrrDipmIipb JLC1 GEG JAG HBC CST1 DRPIII DRSIII PLB1 JRK1 DB0350
CONSENT AND HEARING WAIVER FORM FirstEnergy Nuclear Operating Company (FENOC) hereby agrees to incorporation of such conditions described in the NRCs letter dated February 26, 2004, into a Confirmatory Order that will be immediately effective upon issuance. In signing below, I recognize that FENOC consents to the issuance of the Confirmatory Order, effective immediately, and that pursuant to 10 CFR 2.202(a)(3) and (d), FENOC waives the right to request a hearing on all or any part of the Order.
___________________________________ Executed on _____________
Name and Title Date
CONDITIONS TO BE CONFIRMED BY ORDER Accordingly, pursuant to Sections 103, 161b, 161i, 161o, 182 and 186 of the Atomic Energy Act of 1954, as amended, and the Commissions regulations in 10 CFR 2.202 and 10 CFR Part 50, IT IS HEREBY ORDERED, EFFECTIVE IMMEDIATELY, THAT LICENSE NO.
NPF-3 IS MODIFIED AS FOLLOWS:
DRAFT
- 1. FENOC shall contract with independent outside organizations to conduct comprehensive assessments of the Davis-Besse operations performance, organizational safety culture, including safety conscious work environment, corrective action program implementation, and engineering program effectiveness. Ninety days prior to the assessments, FENOC shall inform the Regional Administrator, NRC Region III, in writing, of the identity of its outside assessment organizations, including the qualifications of the assessors, and the planned scope and depth of the assessments. These outside independent assessments at Davis-Besse shall be completed before the end of the 4th calendar quarter of 2004 and annually thereafter for 5 years. Within 45 days of completion of the assessments, the Licensee shall submit by letter to the Regional Administrator, NRC Region III, all assessment results and any action plans intended to address issues raised by the assessment results.
- 2. FENOC shall conduct a visual examination of the reactor pressure vessel upper head bare metal surface, including the head-to-penetration interfaces; the reactor pressure vessel lower head bare metal surface, including DRAFT PROVIDED ONLY TO OBTAIN CONSENT ON A CONFIRMATORY ORDER
the head-to-penetration interfaces; and the control rod drive mechanism flanges, using VT-2 qualified personnel and procedures during the Cycle 14 midcycle outage. The results and evaluation of the inspections will be reported by letter to the Regional Administrator, NRC Region III, prior to restart from the mid-cycle outage, and any evidence of reactor coolant leakage found during the DRAFT inspections will be reported by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery to the Regional Administrator, NRC Region III, or designee.
If the Licensee determines that submittals made in accordance with these conditions contain proprietary information as defined by 10 CFR 2.390, the Licensee shall also provide a nonproprietary version in accordance with 10 CFR 2.390(b)(1)(ii). The Regional Administrator, NRC Region III, may, in writing, relax or rescind any of the above conditions upon demonstration by the Licensee of good cause.
DRAFT PROVIDED ONLY TO OBTAIN CONSENT ON A CONFIRMATORY ORDER