ML060580176
| ML060580176 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/06/2006 |
| From: | Olshan L Plant Licensing Branch III-2 |
| To: | Duke Energy Corp |
| Olshan L N, NRR/DORL, 415-1419 | |
| Shared Package | |
| ML060580201 | List: |
| References | |
| Download: ML060580176 (5) | |
Text
March 6, 2006LICENSEE:DUKE ENERGY CORPORATION (DUKE)
FACILITY:OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (OCONEE)
SUBJECT:
SUMMARY
OF FEBRUARY 7, 2006, MEETING TO DISCUSS HIGH ENERGYLINE BREAK (HELB) AND TORNADO MITIGATIONOn February 7, 2006, the Nuclear Regulatory Commission (NRC) met with Duke (the licensee)to discuss HELB and tornado mitigation at Oconee. Enclosure 1 is a list of the attendees. is the handouts provided by the licensee during the meeting.By letter dated January 31, 2006, the licensee had provided information on plannedmodifications related to HELB and tornado events. In that letter, the licensee stated, "Followingthat meeting, absent verbal or written notification from the Staff that this approach is notsufficient, Duke will proceed with the understanding that implementation of the activitiesdescribed in the Attachment will resolve the NRC staff's concerns regarding Oconee's CLB[current licensing basis] for tornado and HELB events outside containment." The NRC staffstated that it did not have enough specific details to reach a conclusion regarding the CLB fortornado and HELB events. The NRC staff also stated that the licensee should not concludethat the absence of verbal or written notification from the NRC staff constitutes NRC approval ofthe licensee's approach. The licensee stated that it did not intend for the NRC staff to approvethe CLB for tornado and HELB based on the information provided in the January 31, 2006, letter and during this meeting; the licensee was instead asking the NRC staff to identify anyproblems the NRC staff had with the licensee's general approach thus far.The NRC staff r equested that the licensee provide a listing of systems, components, andstructures (SSCs) needed to mitigate tornado and HELB events and to specify for which SSCs protection from these events will be provided and for which SSCs the licensee will provideanalyses to demonstrate that these events can be adequately mitigated. The NRC staff alsorecommended that the licensee provide a failure modes and effect analysis (FMEA) for tornado and HELB events. The licensee agreed to provide the listing of SSCs requested by the NRC staff, and the licensee stated that it would consider providing the FMEA.The licensee discussed the modifications that it is currently planning to implement to mitigatetornado events. The licensee may propose additional plant modifications after completing its review of risk insights for the remaining SSCs. The planned modifications will be desi gned tothe tornado criteria specified for the Standby Shutdown Facility (SSF) in the Updated FinalSafety Analysis Report. The licensee also stated that the upgrade to station auxiliary servicewater (ASW) will be designed to Quality Assurance I requirements. The licensee stated thatwhen the upgrade to station ASW has been completed, it will provide an alternate means fromthe SSF for shutting down the plant. For SSCs not covered by these modifications, the licensee intends to provide risk insights, some of which will be based on TORMIS, a computer model foranalyzing tornado-induced missiles. In addition, the licensee is reviewing a draft regulatory guide, "Draft Regulatory Guide DG-1143, Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants," that has recently been made available for public comment. Thelicensee stated that it will reach a decision by March 1, 2006, regarding possible use ofDG-1143.The licensee stated that it will be using Fiber Reinforced Polymer (FRP) technology forapplication in strengthening selected masonry walls against the effects of tornado wind and differential pressure loads. The licensee will be submitting a license amendment request (LAR)by June 1, 2006, for use of FRP technology. The NRC staff stated that the use of thistechnology will be a first-time review for the NRC staff.The NRC staff also discussed some concerns with tornado mitigation, including the availabilityof steam generator level control and indication after a tornado.For HELB events, the licensee agreed that it will confirm by analysis that cold shutdown can beachieved, but that certain repairs may be needed. The licensee has not yet determined whatcriterion it will use for the time required to reach cold shutdown. The NRC staff agreed with theconcept of making repairs to achieve cold shutdown, but stated that it would need more detailsregarding these repairs and the time needed to make these repairs.The licensee stated that it intends to incorporate NUREG/CR-2913, "Two-Phase Jet Loads,"and Branch Technical Position MEB 3-1 into the Oconee licensing basis for jet impingement from critical cracks. The NRC staff stated that NUREG/CR-2913 was intended for full circularbreaks of pipe and that the licensee would have to justify the use of this NUREG for pipecracks. The NRC staff also stated the licensee should not just address selected items in MEB3-1, but should address all the items in MEB 3-1.The licensee provided its schedule for implementing the planned modifications and stated that itwould provide additional justification for modifications that are scheduled to be completed later than December 31, 2007. The NRC stated that it was encouraged by the licensee's plans forresolving these issues. /RA/Leonard N. Olshan, Project ManagerPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-269, 50-270, and 50-287 Nuclear Power Plants," that has recently been made available for public comment. Thelicensee stated that it will reach a decision by March 1, 2006, regarding possible use ofDG-1143.The licensee stated that it will be using Fiber Reinforced Polymer (FRP) technology forapplication in strengthening selected masonry walls against the effects of tornado wind and differential pressure loads. The licensee will be submitting a license amendment request (LAR)by June 1, 2006, for use of FRP technology. The NRC staff stated that the use of thistechnology will be a first-time review for the NRC staff.The NRC staff also discussed some concerns with tornado mitigation, including the availabilityof steam generator level control and indication after a tornado.For HELB events, the licensee agreed that it will confirm by analysis that cold shutdown can beachieved, but that certain repairs may be needed. The licensee has not yet determined whatcriterion it will use for the time required to reach cold shutdown. The NRC staff agreed with theconcept of making repairs to achieve cold shutdown, but stated that it would need more detailsregarding these repairs and the time needed to make these repairs.The licensee stated that it intends to incorporate NUREG/CR-2913, "Two-Phase Jet Loads,"and Branch Technical Position MEB 3-1 into the Oconee licensing basis for jet impingement from critical cracks. The NRC staff stated that NUREG/CR-2913 was intended for full circularbreaks of pipe and that the licensee would have to justify the use of this NUREG for pipecracks. The NRC staff also stated the licensee should not just address selected items in MEB3-1, but should address all the items in MEB 3-1.The licensee provided its schedule for implementing the planned modifications and stated that itwould provide additional justification for modifications that are scheduled to be completed later than December 31, 2007. The NRC stated that it was encouraged by the licensee's plans forresolving these issues. /RA/Leonard N. Olshan, Project ManagerPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-269, 50-270, and 50-287 Distribution
- PublicBWetzel, Rgn IICDoutt LPL2-1 r/fRidsRgn2MailCenter(MErnstes)JSheaRidsNrrDorlLplc(EMarinos)RidsNrrAdro(BBoger)RCarroll RidsOgcRpJTatumRSchin RidsAcrsAcnwMailCenterJFairMShannon RidsNrrDorl(CHaney/EHackett)MTschiltzRJasinski RidsNrrPMLOlshanEImbroSJones RidsNrrLAMO'BrienBHarveyPackage: ML060580201Meeting Handouts: ML060580237Meeting Summary: ML060580176Meeting Notice: ML060240613NRC-001OFFICENRR/LPL2-1/PMNRR/LPL2-1/BCNAMELOlshanEMarinosDATE3/6/063/6/06OFFICIAL RECORD COPY LIST OF ATTENDEESMEETING TO DISCUSS OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3HIGH ENERGY LINE BREAK AND TORNADO MITIGATIONFEBRUARY 7, 2006
NRCDUKEB. BogerR. JonesC. HaneyB. Hamilton E. HackettM. Glover E. MarinosG. Davenport J. TatumJ. Fuller L. OlshanG. McAninch J. FairL. Kanipe M. TschiltzJ. Robertson E. ImbroL. Nicholson B. HarveyJ. Fisicaro S. JonesR. Freudenberger C. Doutt M. Ernstes*
J. Shea*
R. Carroll*OTHERR. Schin*
M. Shannon*T. Bacon, Areva*By phone Oconee Nuclear Station, Units 1, 2, and 3 cc:
Ms. Lisa F. VaughnDuke Energy Corporation 526 South Church Street P. O. Box 1006 Mail Code = EC07H Charlotte, North Carolina 28201-1006Manager, LISNUS Corporation 2650 McCormick Dr., 3rd Floor Clearwater, FL 34619-1035Senior Resident InspectorU.S. Nuclear Regulatory Commission 7812B Rochester Highway Seneca, SC 29672Mr. Henry Porter, DirectorDivision of Radioactive Waste Management Bureau of Land and Waste Management Dept. of Health and Env. Control 2600 Bull St.
Columbia, SC 29201-1708Mr. Michael A. SchoppmanFramatome ANP 1911 North Ft. Myer Dr.
Suite 705 Rosslyn, VA 22209Mr. B. G. DavenportRegulatory Compliance Manager Oconee Nuclear Site Duke Energy Corporation ON03RC 7800 Rochester Highway Seneca, SC 29672Ms. Karen E. LongAssistant Attorney General NC Department of Justice
P.O. Box 629 Raleigh, NC 27602Mr. R. L. Gill, Jr.Manager - Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 S. Church St.
Mail Stop EC05P Charlotte, NC 28202Division of Radiation ProtectionNC Dept of Environment, Health, & Natural Resources 3825 Barrett Dr.
Raleigh, NC 27609-7721Mr. Peter R. Harden, IVVP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, NC 28210Mr. Henry BarronGroup Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006Mr. Bruce H. HamiltonVice President, Oconee Site Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672