IR 05000445/2007003
Download: ML072180641
Text
August 5, 2007
Mike Blevins, Senior Vice President and Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs Comanche Peak Steam Electric Station P.O. Box 1002 Glen Rose, TX 76043
SUBJECT: COMANCHE PEAK STEAM ELECTRIC STATION - NRC INTEGRATEDINSPECTION REPORT 05000445/2007003 AND 05000446/2007003
Dear Mr. Blevins:
On June 22, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection atyour Comanche Peak Steam Electric Station, Units 1 and 2 facility. The enclosed integrated inspection report documents the inspection findings which were discussed on July 9, 2007, with you and other members of your staff.This inspection examined activities conducted under your licenses as they related to safety andcompliance with the Commission's rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.This report documents one NRC-identified finding and two self-revealing findings of very lowsafety significance (Green). Two of the findings were determined to involve violations of NRC requirements. However, because of their very low safety significance and because they were entered into your corrective action program, the NRC is treating these findings as noncited violations (NCV) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest any NCV in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, TX 76011-4005 ; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington DC 20555-0001; and the NRC Resident Inspector at Comanche Peak Steam Electric Station. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be made available electronically for public inspection in the NRC PublicDocument Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
TXU Power-2-Should you have any questions concerning this inspection, we will be pleased to discuss themwith you.
Sincerely,/RA/
Claude Johnson, ChiefProject Branch A Division of Reactor ProjectsDocket Nos.:50-445, 50-446License Nos.:NPF-87, NPF-89
Enclosure:
NRC Inspection Report 05000445/2007003 and 05000446/2007003
w/Attachment:
Supplemental Informationcc w/
Enclosure:
Fred W. Madden, Director Regulatory Affairs TXU Power P.O. Box 1002 Glen Rose, TX 76043George L. Edgar, Esq.Morgan Lewis 1111 Pennsylvania Avenue, NW Washington, DC 20004Terry Parks, Chief InspectorTexas Department of Licensing and Regulation Boiler Program P.O. Box 12157 Austin, TX 78711The Honorable Walter MaynardSomervell County Judge P.O. Box 851 Glen Rose, TX 76043Richard A. Ratliff, ChiefBureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189Environmental and Natural Resources Policy Director Office of the Governor P.O. Box 12428 Austin, TX 78711-3189Brian AlmonPublic Utility Commission William B. Travis Building P.O. Box 13326 Austin, TX 78711-3326Susan M. JablonskiOffice of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P.O. Box 13087 Austin, TX 78711-3087Lisa R. Hammond, ChiefTechnological Hazards Branch National Preparedness Division FEMA Region VI 800 N. Loop 288 Denton, TX 76209 TXU Power-3-Electronic distribution by RIV:Regional Administrator (BSM1)DRP Director (ATH)DRS Director (DDC)DRS Deputy Director (RJC1)DRS Deputy Director (WBJ)Senior Resident Inspector (DBA)Branch Chief, DRP/A (CEJ1)Senior Project Engineer, DRP/A (TRF)Team Leader, DRP/TSS (CJP)RITS Coordinator (MSH3)Only inspection reports to the following:DRS STA (DAP)M. Kunowski, OEDO RIV Coordinator (MAK3)D. Pelton, OEDO RIV Coordinator (DLP)ROPreports CP Site Secretary (ESS)SUNSI Review Completed: __CEJ_ADAMS: YesG No Initials: ___CEJ___ Publicly Available G Non-Publicly Available G Sensitive Non-SensitiveR:\_REACTORS\_CPSES\2007\CP2007-03RP-DBA.wpd RIV:RI:DRP/ASRI:DRP/AC:DRS/EB1C:DRS/OBC:DRS/EB2AASanchezDBAllenDAPowersATGodyLJSmithE-ZKDunhamE-ZKDunham/RA//RA//RA/8/2/078/2/077/23/077/23/077/19/07C:DRS/PSBC:DRP/AMPShannonCEJohnson/RA//RA/7/19/078/5/07OFFICIAL RECORD COPYT=Telephone E=E-mail F=Fax U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDockets:50-445, 50-446Licenses:NPF-87, NPF-89 Report: 05000445/2007003 and 05000446/2007003 Licensee:TXU Generation Company LP Facility:Comanche Peak Steam Electric Station, Units 1 and 2 Location:FM-56, Glen Rose, Texas Dates:March 24, 2007 through June 22, 2007 Inspectors: D. Allen, Senior Resident InspectorA. Sanchez, Resident Inspector P. Goldberg, Reactor Inspector S. Alferink, Reactor Inspector G. Guerra, CHP, Health Physicist D. Stearns, Health Physicist K. Clayton, Operations Engineer A. Fairbanks, Reactor Inspector E. Uribe, Reactor Inspector M. Young, Reactor InspectorApproved by:Claude Johnson, Chief, Project Branch ADivision of Reactor Projects
Attachment:
Supplemental Information Enclosure-2-
SUMMARY OF FINDINGS
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REPORT DETAILS
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REACTOR SAFETY
.......................................................-5-1R01Adverse Weather Protection (71111.01)............................-5-1R04Equipment Alignment (71111.04)..................................-5-1R05Fire Protection (71111.05Q)......................................-6-1R06Flood Protection Measures (71111.06).............................-7-1R07Biennial Heat Sink Performance..................................-8-1R11Licensed Operator Requalification Program (71111.11)...............-11-1R12Maintenance Effectiveness (71111.12)............................-13-1R13Maintenance Risk Assessments and Emergent Work Evaluation (71111.13)..........................................................-13-1R15Operability Evaluations (71111.15)...............................-14-1R17Permanent Plant Modifications (71111.17A)........................-15-
1R19 Postmaintenance Testing
.............................-16-1R20Refueling and Outage Activities (71111.20).........................-16-1R22Surveillance Testing (71111.22)..................................-19-1R23Temporary Modifications (71111.23)..............................-20-RADIATION SAFETY.....................................................-20-2OS1Access Control To Radiologically Significant Areas (71121.01)..........-20-2OS2ALARA Planning and Controls (71121.02)..........................-23-OTHER ACTIVITIES......................................................-25-4OA1Performance Indicator Verification (71151).........................-25-4OA2Problem Identification and Resolution (71152).......................-27-4OA6Meetings, Including Exit........................................-30-4OA7Licensee-Identified Violations...................................-31-