IR 05000400/2006009

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November 14, 2006

EA-06-216 Carolina Power and Light CompanyATTN: Mr. C. J. Gannon, Jr.

Vice President - Harris Plant Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165

SUBJECT: FINAL SIGNIFICANCE DETERMINATION FOR A GREEN FINDING WITHNON-CITED VIOLATION (SHEARON HARRIS NUCLEAR POWER PLANT -

NRC INSPECTION REPORT NO. 05000400/2006009)

Dear Mr. Gannon:

The purpose of this letter is to provide you with the Nuclear Regulatory Commission's (NRC)final significance determination for a finding involving the train "A" Essential Services Chilled Water (ESCW) System Chiller. The finding was documented in NRC Inspection Report No. 05000400/2006003 dated July 28, 2006. The NRC's letter of September 11, 2006, informed Carolina Power and Light Company (CP&L) that the finding was assessed under the significance determination process as a preliminary White issue (i.e., an issue of low to moderate safety significance which may require additional NRC inspection), and provided CP&L an opportunity to request a regulatory conference on this matter. The details of the NRC's preliminary estimate of the change in core damage frequency for this finding were also provided to CP&L by letter on September 11, 2006. In response, CP&L chose to attend a regulatory conference, which was held in the NRC'sRegion II Office on October 13, 2006. During the conference, CP&L acknowledged that a performance deficiency and a violation occurred in that maintenance procedures were inadequate to ensure the compressor vane control shaft was secured in the correct position for starting following maintenance activities in May 2006 which led to the compressor failing to start on June 1, 2006. However, CP&L stated its disagreement with the NRC's conclusion that the issue resulted in a preliminary White finding. CP&L performed their own GOTHIC charging pump room heatup calculations and risk analysis based on plant specific information, and concluded that the change in Core Damage Frequency (CDF) supported a Green (very lowsafety significance) finding. CP&L also stated that three additional Probabilistic Safety Analysis (PSA) inputs (plant specific fire ignition frequency, loss of emergency bus frequency, and protected train assumption) show risk reduction that were not included in the NRC Significance Determination Process (SDP) analysis.Based upon the additional input provided by your staff at the Regulatory Conference, the NRChas concluded that the final significance of the finding is appropriately characterized as Green (i.e., a finding of very low safety significance), in the Mitigating System cornerstone. The final significance determination incorporated the protected train protocol normally employed by the station, a more accurate number of credible ignition sources in the 6.9 KV Bus B compartment, and the use of a temporary fan to cool the High Head Safety Injection/Charging Pump in CP&L2response to a loss of the chiller. The final determination included a revised loss of 6.9 KV Businitiating event frequency consistent with NUREG/CR-5750, Rates of Initiating Events at U.S.

Nuclear Power Plants: 1987 - 1995. The frequency was not divided by two as your staff recommended. Also, the success criteria associated with the initiating events of a Medium Break Loss of Coolant Accident and the Loss of Component Cooling Water were not altered from the preliminary significance determination.The NRC determined that one violation occurred, involving the requirements of TS 6.8.1 for an inadequate maintenance procedure. Because of the very low safety significance of this violation and because the issue was entered into your corrective action program, the NRC is treating the violation as a non-cited violation (NCV) consistent with Section VI.A of the NRC Enforcement Policy. If you contest this NCV, you should provide a response within 30 days of the date of this letter, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC, 20555-0001; with copies to the Regional Administrator Region III; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC, 20555-0001; and the NRC Resident Inspector at the Shearon Harris Nuclear Plant.For administrative purposes, this letter is issued as a separate NRC Inspection Report,No. 05000400/2006009 and the above NCV is identified as NCV 05000400/2006009-01, Failure to Maintain Adequate Procedures Such That a Required Torque Was Not Provided for a Threaded Fastener on an ESCW System Chiller. Accordingly, apparent violation (AV)05000400/2006003-01 and Licensee Event Report 05000400/2006-002-00, ESCW Inoperable for a Period Longer than Allowed by Technical Specifications Due to Inadequate Procedure, are closed.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosures will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (thePublic Electronic Reading Room).Should you have any questions regarding this letter, please contact Randall Musser, Chief,Reactor Projects Branch 4, at 404-562-4603.

Sincerely,/RA/Charles D. Casto, DirectorDivision of Reactor ProjectsDocket No. 50-400License No. NPF-63 CP&L2response to a loss of the chiller. The final determination included a revised loss of 6.9 KV Bus initiating eventfrequency consistent with NUREG/CR-5750, Rates of Initiating Events at U.S. Nuclear Power Plants: 1987 - 1995.

The frequency was not divided by two as your staff recommended. Also, the success criteria associated with theinitiating events of a Medium Break Loss of Coolant Accident and the Loss of Component Cooling Water were notaltered from the preliminary significance determination.The NRC determined that one violation occurred, involving the requirements of TS 6.8.1 for an inadequatemaintenance procedure. Because of the very low safety significance of this violation and because the issue wasentered into your corrective action program, the NRC is treating the violation as a non-cited violation (NCV)consistent with Section VI.A of the NRC Enforcement Policy. If you contest this NCV, you should provide a response within 30 days of the date of this letter, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN:Document Control Desk, Washington, DC, 20555-0001; with copies to the Regional Administrator Region III; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC, 20555-0001; andthe NRC Resident Inspector at the Shearon Harris Nuclear Plant.For administrative purposes, this letter is issued as a separate NRC Inspection Report,No. 05000400/2006009 and the above NCV is identified as NCV 05000400/2006009-01, Failure to Maintain Adequate Procedures Such That a Required Torque Was Not Provided for a Threaded Fastener on an ESCWSystem Chiller. Accordingly, apparent violation (AV)05000400/2006003-01 and Licensee Event Report05000400/2006-002-00, ESCW Inoperable for a Period Longer than Allowed by Technical Specifications Due toInadequate Procedure, are closed.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosures will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's document system(ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (thePublic Electronic Reading Room).Should you have any questions regarding this letter, please contact Randall Musser, Chief, Reactor Projects Branch4, at 404-562-4603.

Sincerely,/RA/Charles D. Casto, ChiefDivision of Reactor ProjectsDocket No. 50-400License No. NPF-63G PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLEG SENSITIVE G NON-SENSITIVEADAMS: G YesACCESSION NUMBER:_________________________OFFICERII:DRPRII:DRPRII:DRSRII:DRPRII:EICSRII:DRPSIGNATURERXM1RPSWGR1SONCFE for (email)PBO (email)NAMERMusserRSchinWRogersSNinhSSparksPO'BryanDATE11/13/200611/08/200611/13/200611/13/200611/08/200611/08/200611/ /2006 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO OFFICIAL RECORD COPY DOCUMENT NAME: C:\FileNet\ML063180410.wpd CP&L3cc w/encl:Chris L. Burton, Manager Performance Evaluation and Regulatory Affairs CPB 9 Carolina Power & Light Company Electronic Mail DistributionRobert J. Duncan IIDirector of Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail DistributionEric McCartneyPlant General Manager--Harris Plant Progress Energy Carolinas, Inc.

Shearon Harris Nuclear Power Plant Electronic Mail DistributionJ. Wayne GurganiousTraining Manager-Harris Plant Progress Energy Carolinas, Inc.

Harris Energy & Environmental Center Electronic Mail DistributionChristos Kamilaris, ManagerSupport Services Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail DistributionDavid H. Corlett, SupervisorLicensing/Regulatory Programs Carolina Power & Light Company Shearon Harris Nuclear Power Plant Electronic Mail DistributionDavid T. ConleyAssociate General Counsel - Legal Department Progress Energy Service Company, LLC Electronic Mail DistributionJohn H. O'Neill, Jr.Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW Washington, DC 20037-1128Beverly Hall, Chief, Radiation Protection Section N. C. Department of Environmental Commerce & Natural Resources Electronic Mail DistributionPublic Service CommissionState of South Carolina P. O. Box 11649 Columbia, SC 29211Chairman of the North Carolina Utilities Commission c/o Sam Watson, Staff Attorney Electronic Mail DistributionRobert P. GruberExecutive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326Herb Council, ChairBoard of County Commissioners of Wake County P. O. Box 550 Raleigh, NC 27602Tommy Emerson, ChairBoard of County Commissioners of Chatham County Electronic Mail DistributionDistribution (See page 4)

CP&L4Letter to C. J. Gannon, Jr. from Charles D. Casto dated November 14, 2006

SUBJECT: FINAL SIGNIFICANCE DETERMINATION FOR A GREEN FINDING WITHNON-CITED VIOLATION (SHARON HARRIS NUCLEAR POWER PLANT -

NRC INSPECTION REPORT NO. 05000400/2006009)Distribution w/encl:C. Patel, NRR C. Evans (Part 72 Only)

L. Slack, RII EICS RIDSNRRDIRS OE Mail (email address if applicable)

PUBLIC