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Category:Memoranda
MONTHYEARML22333B0922022-12-21021 December 2022
FY22 Nmss/Duwp Operating Experience Report
ML21060B0202021-03-31031 March 2021
Memo to File: Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Crystal River ISFSI
ML21060B0212021-03-31031 March 2021
Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Crystal River ISFSI
ML19323F8262019-11-20020 November 2019
NEIMA Meeting Summary
ML19183A4332019-07-0909 July 2019
Memo to Frederick Miller, Chief (Acting), Financial Projects Branch, Request for Technical Assistance on a License Transfer Application and Associated Conforming Administrative License Amendment for Crystal River Unit 3 Nuclear Generating P
ML18037A5242018-02-0606 February 2018
CR_3 ISFSI PSP Rev 1 Notice of Safeguards Memo
ML17271A0532017-09-29029 September 2017
2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning
ML17143A0182017-05-28028 May 2017
Staff Review of Crystal River, Unit 3, Physical Security Plan Rev. 3 (Sles NS114954) for Verification of ASM Incorporation (EA-16-005)
ML16356A2182017-01-0909 January 2017
Memo to Beardsley - Work Request for Crystal River Amendment to Remove the Existing Cyber Security License Condition from the Facility Operating License
ML16176A3392016-10-28028 October 2016
Decommissioning Lessons Learned Report and Transmittal Memorandum
ML16224A7822016-08-16016 August 2016
Memo to Anderson, Request for Technical Assistance on License Amendment Request to Approve the Crystal River Unit 3 ISFSI Only Physical Security Plan
ML16201A1352016-08-12012 August 2016
Safety Evaluation Input for Independent Spent Fuel Storage Installation Only Emergency Plan
ML16173A0652016-06-23023 June 2016
Work Request to NSIR, Crystal River ISFSI Only Security Plan
ML16161A5572016-06-16016 June 2016
Memo to Anderson, Work Request for Crystal River ISFSI Only Emergency Plan
ML16160A2782016-06-16016 June 2016
Request for Publication in Biweekly Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (Contro
ML16111B2622016-04-25025 April 2016
Memo from B. Watson (NRC) to J. Andersen (NRC) Re: Request for Assistance for Crystal River Revision to the Security Plan Implementation Schedule Milestone 8
ML15258A4812015-09-16016 September 2015
Request for Technical Assistance on License Amendment Request for Proposed Revision to the Crystal River Unit 3 Permanently Defueled Emergency Plan (TAC No. L53072)
ML13225A1992013-08-13013 August 2013
Correction - 08/29/13 Notice of Forthcoming Meeting with Duke Energy Florida: Crystal River, Unit 3 Nuclear Generating Plant Decommissioning Submittals
ML13099A3012013-04-0909 April 2013
Termination of Resident Inspection Staffing for Crystal River Nuclear Plant Following Certification of Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel
ML13016A1152013-01-16016 January 2013
NRC Oversight of Crystal River, Unit 3, During Extended Shutdown
ML12300A4032012-10-26026 October 2012
11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events
ML12285A3122012-10-15015 October 2012
11/1/12 Forthcoming Meeting Via Conference Call with Duke Energy, Inc. Representing Florida Power Corporate Concerning Generic Letter 2004-02 and Draft Proposed Strainer Fiber Bypass Test Plan for Crystal River
ML12284A4612012-10-12012 October 2012
Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events
ML12270A1482012-09-24024 September 2012
Memo Request for Temporary Exception to the Resident Inspector Staffing Policy for Crystal River Nuclear Plant
ML11286A1592011-10-13013 October 2011
Memo: NRC Oversight of Crystal River Unit 3 During Extended Shutdown
ML1125905462011-09-16016 September 2011
Inspection Plan Memo to Fred Brown During Extended Shutdown
ML11187A1902011-07-18018 July 2011
Summary of Public Meetings Conducted to Discuss the Dseis Related to the Review of the Crystal River 3 Nuclear Generating Plant License Renewal Application
ML11153A1652011-06-0909 June 2011
06/28/11 Notice of Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Crystal River Unit 3 Nuclear Generating Plant
ML1107405412011-03-31031 March 2011
4/21/11 Notice of Forthcoming Meeting with Progress Energy, Crystal River, Unit 3, to Discuss Licensee'S Overall Plans Associated with an EPU Application
ML1108406312011-03-29029 March 2011
Notice of Forthcoming Pre-Application Meeting with Carolina Power & Light Co. and Florida Power Corp., Brunswick Units 1 & 2, Crystal River Unit 3, and H.B. Robinson Unit 2, to Discuss Transition to the Requirements of National Fire..
ML1104200212011-03-21021 March 2011
Summary of Telephone Conference Call Held on 11/22/10, Between the USNRC and FPC, Concerning Draft Request for Additional Information Related to the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application
ML1034706512010-12-15015 December 2010
Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal (Crystal River), January 12, 2011
ML1027404282010-10-0101 October 2010
Notice of Forthcoming Meeting with Florida Power Corporation (Progress Energy) to Discuss the Crystal River Proposed License Amendment Request to Support Implementation of the Independent Spent Fuel Storage Facility (ISFSI) Project
ML1022302872010-08-18018 August 2010
Memo Approval of Reactor Oversight Program Reduced Sample Size for Crystal River Unit 3 in Calender Year 2010
ML1021703312010-08-0505 August 2010
Memo - Completion of ROP Baseline Inspections for Extended Shutdown of Crystal River in Calendar Yr. 2010
ML1016601412010-06-17017 June 2010
Notice of Forthcoming Meeting with Progress Energy to Discuss Licensee'S Plans for Repairing the Containment at Crystal River, Unit 3
ML1000900502010-03-0101 March 2010
Summary of Telephone Conference Call Held on November 11, 2009, Between the U.S. NRC and Florida Power Corporation, Concerning a Draft RAI and the Applicant'S Response to a RAI Pertaining to the Crystal River Unit 3 Nuclear Generating Plant
ML1003200362010-02-19019 February 2010
Summary of Telephone Conference Call Held on December 23, 2009, Between the U.S. NRC and Florida Power Corporation, Concerning Applicant'S Response to a RAI Pertaining to the Crystal River Unit 3 Nuclear Generating Plant License Renewal..
ML1001415932010-02-16016 February 2010
Summary of Tele Conference Call Held on 12/1/09, Btw the USNRC and Florida Power Corp, Concerning Licensee Response to a RAI Pertaining to the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application
ML1000703172010-02-0202 February 2010
Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Florida Power Corporation, Concerning the Applicant'S Response to a Request for Additional Information Pertaining to the Crystal River, Unit 3
ML0934513952010-01-0404 January 2010
Summary of Telephone Conference Call on 10/29/09, Between the USNRC and Florida Power Corporation, Concerning Licensee Response to a Request for Information Related to the Crystal River Unit 3 Nuclear Generating Plant License Renewal Applic
ML1007503972009-10-13013 October 2009
Email from M. Franke to M. Sykes, Subj: FW: Crystal River SI Charter
ML0928608132009-10-13013 October 2009
Special Inspection Charter to Evaluate Crystal River Containment Building
ML1007503992009-10-13013 October 2009
Email from C. Morrison to L. Reyes, Et Al, Subj: Special Inspection Charter to Evaluate CR Containment Bldg
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0807102572008-03-11011 March 2008
Request for Additional Information - Weld Overlay of the Decay Heat Drop Line Relief Request #08-001-RR, Revision 0
ML0733711662007-12-0303 December 2007
Notice of Meeting with Progress Energy & Duke Energy Regarding Fire Probabilistic Risk Assessment for the Pilot Plants Transitioning to the National Fire Protection Association Standard NFPA 805
ML0723500152007-08-23023 August 2007
Notice of Meeting with Progress Energy Florida to Discuss the Status of the Power Uprates at Crystal River, Unit 3
ML0707500422007-03-16016 March 2007
03/23/07 Meeting Cancellation - Crystal River Unit 3, Meeting with Progress Energy Florida Notice Plans for Power Uprate, License Renewal, Steam Generator Replacement, and Installation of an Independent Spent Fuel Storage Facility
ML0627700652006-10-0505 October 2006
Forthcoming Meeting with Florida Power Corporation (Progress Energy) to Discuss Pre-Application Review of Missile Shield Amendment for Crystal River Unit 3
2022-12-21
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 October 13, 2009 MEMORANDUM TO: Louis F. Lake, Team Leader Special Inspection FROM: Luis A. Reyes /RA/
Regional Administrator
SUBJECT:
SPECIAL INSPECTION CHARTER TO EVALUATE CRYSTAL RIVER CONTAINMENT BUILDING You have been selected to lead a Special Inspection to assess the circumstances associated with a delamination discovered in the concrete of the containment building at Crystal River Unit
- 3. Your onsite inspection should begin on October 13, 2009. Robert Carrion, Senior Reactor Inspector, George Thomas of NRR, Anthony Masters, Senior Construction Inspector, and an independent Structural Engineering Contractor (TBD) will assist you in this inspection.
A. Basis Recently, the plant was shut down for a planned refueling outage as well as to replace the steam generators inside containment. In order to move the steam generators into containment, workers began removing concrete to create the necessary opening.
During that work, a small gap was found while making approximately a 25 foot x 25 foot concrete cut (liner is still intact). The gap is about one half inch wide and 10 inches inward from the outside edge of the concrete and located just at the layer of horizontal tendons. The Crystal River containment is about 42 inches thick, contains both horizontal and vertical tensioned steel tendons, and is lined with steel plate.
The licensee is evaluating the extent of the condition. The discovery of this gap in the concrete does not represent an immediate safety concern because the plant is shut down.
In accordance with Management Directive 8.3, NRC Incident Investigation Program, deterministic and conditional risk criteria were used to evaluate the level of NRC response for this event.
Based on the deterministic criteria that this issue involved possible adverse generic implications, the event was evaluated for risk in accordance with Management Directive 8.3. Due to lack of information on the structural integrity of the concrete containment and how it would interact with the free-standing steel liner during a seismic event in its current condition, a risk analysis was not able to be performed at this time. However, if CONTACT: Mark Franke, RII/DRS 404-562-6349
_________________________ G SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRS RII:DRP RII:DRS RII:DRS RII:DRP HQ:NRR SIGNATURE SON FMF1 MDS MEF1 HChristensen for JMunday for MKK by email NAME SNinh CFletcher MSykes MFranke KKennedy LWert MKhanna DATE 10/09/2009 10/09/2009 10/09/2009 10/09/2009 10/09/2009 10/09/2009 10/12/2009 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICE RII:DRS SIGNATURE LFL NAME LLake DATE 10/13/2009 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO L. Lake 2 the concrete containment reacted adversely with the free-standing steel liner during a seismic event, LERF would be adversely affected and a Special Inspection would be warranted. Therefore, Region II has determined that the appropriate level of NRC response is to conduct a Special Inspection.
B. Scope The inspection is expected to perform data gathering and fact-finding in order to address the following:
- 1. Develop a complete description of the problems and circumstances surrounding the gap in the containment building.
- 2. Verify that the licensee has appropriately evaluated Operability and Reportability.
- 3. Review structural integrity testing data of the containment.
- 4. Assess the adequacy of the licensees maintenance and inspection programs related to this event.
- 5. Assess the licensees activities related to the problem investigation (e.g., root cause analysis, extent of condition, etc).
- 6. Assess the licensees corrective action/fix in addressing the containment delamination issue.
- 7. Collect data necessary to develop and assess the safety significance of any findings in accordance with IMC 0609, Significance Determination Process.
- 8. Determine potential generic issues or any design and construction inadequacies and make recommendations for appropriate follow-up actions (e.g., Information Notices, Generic Letters, and Bulletins).
C. Guidance Inspection Procedure 93812, "Special Inspection," provides additional guidance to be used during the conduct of the Special Inspection. Your duties will be as described in Inspection Procedure 93812. The inspection should emphasize fact-finding in its review of the circumstances surrounding the event. Safety or security concerns identified that are not directly related to the event should be reported to the Region II office for appropriate action.
Your team will report to the site, conduct an entrance, and begin inspection no later than October 13, 2009. In accordance with IP 93812, you should promptly recommend a change in inspection scope or escalation if information indicates that the assumptions utilized in the MD 8.3 risk analysis were not accurate. A report documenting the results of the inspection should be issued within 45 days of the completion of the inspection. A copy of the inspection report shall be forwarded to the Crystal River Unit 3 License Renewal Inspection Team. The report should address all applicable areas specified in
L. Lake 3 Section 3.02 of Inspection Procedure 93812. At the completion of the inspection, you should provide recommendations for improving the Reactor Oversight Process baseline inspection procedures and the Special Inspection process based on any lessons learned.
This charter may be modified should you develop significant new information that warrants review. Should you have any question concerning this charter, contact Mark Franke at (404) 562-6349.
Docket No.: 50-302 License No.: DPR-72
References:
Inspection Procedure 93812, Special Inspection Management Directive 8.3, NRC Incident Investigation Program Inspection Manual Chapter 0609, Significance Determination Process Inspection Manual Chapter 0612, Power Reactor Inspection Reports cc: R. Borchardt, EDO B. Mallett, DEDR L. Reyes, RII V. McCree, RII J. Munday, RII M. Sykes, RII L. Wert, RII T. Boyce, NRR F. Saba, NRR K. Kennedy, RII H. Christensen, RII S. Ninh, RII C. Fletcher, RII M. Franke, RII M. Khanna, NRR
