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Category:Memoranda
MONTHYEARML24124A0342024-05-0101 May 2024
Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris
ML24047A2092024-02-22022 February 2024
Calendar Year 2023 Baseline Inspection Completion
ML23118A2852023-05-0202 May 2023
Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Catawba Nuclear Station, McGuire Nuclear and Oconee Nuclear Station
ML22300A0742023-01-11011 January 2023
Final Environmental Assessment and Finding of No Significant Impact for the Duke Energys Updated Decommissioning Funding Plans Submitted in Accordance with 10 CFR 72.30(C) for Catawba Nuclear Station Independent Spent Fuel Storage Installat
ML21099A0932021-04-0909 April 2021
Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Catawba, McGuire, and Oconee Nuclear Stations
ML20141L4172020-05-20020 May 2020
EOC Public Meeting Summary
ML19098B4482019-04-0808 April 2019
Public Meeting Summary
ML18117A2212018-04-27027 April 2018
Summary of Public Meeting with Catawba Nuclear Station Concerning Annual Assessment of Units 1 and 2 for Period of January 01, 2017 - December 21, 2017
ML17107A0642017-04-17017 April 2017
Summary of Public Meeting with Catawba, Units 1 and 2
ML16111B2472016-04-28028 April 2016
Request for Additional Information Re. License Amendment Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML16081A3352016-03-17017 March 2016
Summary of Meeting with Public Concerning Annual Assessment of Catawba Nuclear Station, Units 1 and 2
ML15253A4032016-03-11011 March 2016
Recommendation for Dispositioning Proposed Generic Issue on the Effects of Downstream Dam Failures on Nuclear Power Plants
ML15244B2522015-08-31031 August 2015
Report on Trip to Catawba on August 26-27, 2015
ML15106A0302015-04-15015 April 2015
Meeting Summary with Public to Discuss the Annual Assessment of Catawba Nuclear Station, Units 1 and 2
ML14126A6792014-05-0606 May 2014
Summary of Public Meeting with Catawba, Units 1 & 2 to Discuss Annual Assessment
ML14077A1312014-03-18018 March 2014
Special Inspection Charter to Evaluate the Abnormal Rotation of the Piston Crankshaft Bearings on the Catawba Unit 1 Diesel Generators
ML13295A3062013-10-22022 October 2013
Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC
ML13135A5962013-05-16016 May 2013
Cancelled 05/23/2013 Notice of Forthcoming Pre-Application Meeting with Duke Energy Carolinas, Llc. to Discuss a Proposed License Amendment Request Concerning Methodology Report DPC-NE-3001-P for Catawba and McGuire Nuclear Stations
ML13127A4352013-05-0909 May 2013
Notice of Forthcoming Pre-Application Meeting with Duke Energy Carolinas, Llc. to Discuss a Proposed License Amendment Request Concerning Methodology Report DPC-NE-3001-P for Catawba and McGuire Nuclear Stations
ML13072B2022013-03-19019 March 2013
Meeting Notice with Duke Energy Concerning NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants License Amendment Request for Catawba, McGuire, and H. B. Robinson
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
ML12284A4612012-10-12012 October 2012
Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events
ML12103A3522012-04-10010 April 2012
Special Inspection Charter to Evaluate Catawba Loss of Offsite Power
ML1106603302011-03-0707 March 2011
Notice of Meeting with Duke Energy to Present Status of Licensing Submittals Regarding Implementation of National Fire Protection Association Standard 805, Requirements at Catawba Nuclear Station, Units 1 and 2 and McGuire Nuclear Station
ML1029306502010-10-20020 October 2010
Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2,
ML1021400692010-08-0404 August 2010
Notice of Meeting with Duke Energy to Discuss Duke Energy'S Assessment of the Results of the Catawba Baseline Inspection Conducted by the NRC
ML1015804072010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of Duke Energy'S Ownership Interest of Catawba, Units 1 and 2, McGuire, Units 1 and 2, and Oconee, Units 1, 2 and 3 on May 20, 2010 - Finding of No Potential Issues in Bank Statement
ML1015804682010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot Check Review of North Carolina Electric Membership Corporation'S Ownership Interest of Catawba Nuclear Station Units 1 and 2 on May 20, 2010 - Finding of No Potential Issues in Bank Statements
ML1015900402010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of Piedmont Municipal Power Agency'S Ownership Interest of Catawba Nuclear Station Units 1 and 2 on May 19, 2010 - Finding of No Potential Issues in Bank Statements
ML1012604632010-05-0707 May 2010
Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke) to Discuss Duke'S Responses to Generic Letter 2004-02 at Catawba 1 and 2 and McGuire 1 and 2
ML0926700202009-10-0707 October 2009
Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02
ML0925404602009-09-10010 September 2009
Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ
ML0922908922009-08-18018 August 2009
Notice of Conference Call with Duke Energy Carolinas, LLC (Duke), Regarding Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2) and McGuire Nuclear Station Units 1 and 2
ML0831009482008-11-10010 November 2008
Notice of Meeting with Duke Energy Carolinas, LLC, (Duke), Catawba, Units 1 and 2, and McGuire, Units 1 and 2
ML0831107952008-11-0606 November 2008
Cancellation of Meeting with Duke Energy Carolinas, LLC, to Discuss the Request for Additional Information Generic Letter 2004-04, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents.
ML0829701832008-10-30030 October 2008
Notice of Meeting with Duke Energy Carolinas, LLC, to Discuss the Request for Additional Information Generic Letter 2004-04, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents ...
ML0818301542008-07-0101 July 2008
Notice of Meeting with Duke Energy Carolinas, LLC to Discuss Transition to ASME NQA-1-1994
ML0817903662008-06-27027 June 2008
Safety Evaluation by the Office of Nuclear Reactor Regulation Application for Direct Transfer of Facility Operating License Catawaba Nuclear Station, Unit 1
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0800201632008-01-0303 January 2008
Cancelled - Meeting with Duke Power Company
ML0800202162008-01-0303 January 2008
Forthcoming Meeting with Duke Power Company LLC Catawba Nuclear Station to Discuss the Relief Request Dated October 26, 2006 (Agencywide Documents Access and Management System Accession No. ML063120211)
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
ML0628401062006-10-18018 October 2006
Staff'S Review of CLIIP Amendment to Adopt TSTF-372
ML0614505462006-05-25025 May 2006
Revised Augmented Inspection Team Charter
ML0614303612006-05-23023 May 2006
Augmented Inspection Team Charter for Catawba, Units 1 and 2
ML0533900722005-12-0707 December 2005
Notice of Forthcoming Meeting with Duke Energy Corporation, to Discuss Reload Design and Safety Analysis Methodology Report Submittals
ML0524103052005-09-0606 September 2005
08/18/05 - Summary of Public Meeting on Mspi/Rop Topics for August 17/18, 2005
ML0524503412005-09-0202 September 2005
Notice of Meeting with Duke Energy Corp, Regarding RAIs on Nuclear Service Water System for Catawba, Units 1 and 2
2024-05-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 April 10, 2012 MEMORANDUM TO: Curtis W. Rapp Senior Project Engineer FROM: Victor M. McCree /RA By Leonard D. Wert, Jr. For/
Regional Administrator
SUBJECT:
SPECIAL INSPECTION CHARTER TO EVALUATE CATAWBA LOSS OF OFFSITE POWER You have been selected to lead a Special Inspection (SI) to assess the circumstances concerning a loss of offsite power which occurred on April 4, 2012, at Catawba Nuclear Station Units 1 and 2. Catawba declared a Notice of Unusual Event (NOUE) due to loss of all offsite power to essential busses. Your onsite inspection should begin on April 10, 2012. Pauline Braxton and Jonathan Montgomery will be supporting you in this inspection.
A. Basis On Wednesday, April 4, 2012, at 8:12 p.m., Catawba declared a NOUE due to a loss of all offsite power to essential busses. Prior to the loss of power, Unit 1 was operating at 100 percent power and Unit 2 was in Mode 5 with essential busses powered from Unit 1.
Initial investigation by the licensee determined that the 1D reactor coolant pump tripped which led to a reactor trip due to low flow conditions. By design, the turbine tripped and the main generator circuit breakers opened. However, although the main generator was disconnected from the switchyard, a decrease in the main generator frequency caused an under-frequency relay to open the switchyard power circuit breakers (PCBs) isolating offsite power from both units essential busses. All four emergency diesel generators started and supplied power to their essential busses. The Standby Shutdown Facility (SSF) diesel generator also started, but failed to reach rated voltage. This condition did not appear to affect any plant safety system response or the recovery of offsite power.
The NOUE was exited on Thursday April 5, 2012, at 1:37 a.m., following restoration of offsite power to one essential bus on each unit.
The specific issues of concern are:
- The loss of offsite power to both units that resulted from a single unit trip
- The failure of the SSF diesel generator, which is utilized by both units for certain events and conditions, to produce rated voltage.
CONTACT: Jonathan H. Bartley, RII/DRP (404) 997-4607
C. Rapp 2 In accordance with MD 8.3, NRC Incident Investigation Program, deterministic and conditional risk criteria were used to evaluate the level of NRC response for this operational event. The event involved the deterministic criterion of significant unexpected system interactions. The updated Conditional Core Damage Probability (CCDP) for the event was in the overlap region of a Special Inspection and an Augmented Inspection Team. A Special Inspection was deemed appropriate in this case. Accordingly, the inspection objectives are to determine the facts surrounding the loss of offsite power at Catawba, evaluate the licensees response to the event, determine the impact of the Zone G digital relay modification, and assess any site specific and/or generic implications.
B. Scope To accomplish these objectives, the following will be performed:
- 1. Develop timelines associated with the installation of the digital relay modification (Zone G) and the event, including the design and implementation of the relay modification and the response of Catawba Units 1 and 2 to the loss of offsite power initiator.
- 2. Asses the apparent causes and licensee follow-up actions for:
2.1 The 1D reactor coolant pump trip.
2.2 Factors which allowed the reactor coolant pump failure to propagate to the main switchyard breakers and opening the PCBs.
2.3 The licensees design and implementation of the Zone G relay modification, including the design, implementation, and testing phases of the modification.
2.4 Whether the Zone G modification errors have potential generic risk implications.
2.5 The common SSF diesel generator (DG) not achieving its 600V design rating.
- 3. Assess the licensees activities related to the problem investigation performed to date (e.g., root cause analysis, extent of condition, additional equipment failure mechanisms, adequacy of operator actions etc.).
- 4. Determine the impact of the SSF DG low voltage and any significance affecting plant recovery from the LOSP.
- 5. Document the inspection findings and conclusions in an inspection report within 45 days of the inspection which should address all applicable areas specified in section 3.02 of IP 93812.
- 6. Conduct an entrance and exit meeting.
C. Rapp 3 C. Guidance Inspection Procedure (IP) 93812, Special Inspection, provides additional guidance to be used during the conduct of the inspection. Your duties will be as described in IP 93812 and should emphasize fact-finding in its review of the circumstances surrounding the degraded condition. Safety or security concerns identified that are not directly related to the event should be reported to the Region II office for appropriate action.
You will report to the site, conduct an entrance, and begin inspection no later than April 10, 2012. It is anticipated that the on-site portion of the inspection will be completed during the same week. An initial briefing of Region II management will be provided the second day on-site at approximately 4:00 p.m. In accordance with IP 93812, you should promptly recommend a change in inspection scope or escalation if information indicates that the assumptions used in the MD 8.3 risk analysis were not accurate. 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 questions concerning this charter, contact Jonathan H. Bartley at (404) 997-4607.
Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52
_______________ G SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP RII:DRP RII:ORA RII:ORA SIGNATURE ?RA By E-Mail/ /RA By E-mail/ /RA/ /RA/ /RA By LWert For/
NAME CRapp JBartley RCroteau LWert VMcCree DATE 04/ 10 /2012 04/ 10 /2012 04/10 /2012 04/10 /2012 04/10 /2012 E-MAIL COPY? YES NO YES NO YES NO YES NO
