IR 05000445/2006005
Download: ML070400368
Text
February 8, 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 05000445/2006005 AND 05000446/2006005
Dear Mr. Blevins:
On December 31, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed aninspection at your Comanche Peak Steam Electric Station, Units 1 and 2 facility. The enclosed integrated inspection report documents the inspection findings which were discussed onJanuary 10, 2007, with Mr. R. Flores 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 self-revealing finding of very low safety significance (Green). Thisfinding was determined to involve a violation of NRC requirements. However, because of thevery low safety significance and because it was entered into your corrective action program, the NRC is treating this finding as a noncited violation (NCV) consistent with Section VI.A.1 of the NRC Enforcement Policy. If you contest the 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, Texas 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 05000445/2006005 and 05000446/2006005
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 78756-3189 TXU Power-3-Environmental 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 78711-3087ChairpersonDenton Field Office Chemical and Nuclear Preparedness and Protection Division Office of Infrastructure Protection Preparedness Directorate Dept. of Homeland Security 800 North Loop 288 Federal Regional Center Denton, TX 76201-3698Technological Services BranchChief FEMA Region VI 800 North Loop 288 Federal Regional Center Denton, Texas 76201-3698 TXU Power-4-Electronic distribution by RIV:Regional Administrator (BSM1)DRP Director (ATH)DRS Director (DDC)DRS Deputy Director (RJC1)Senior Resident Inspector (DBA)Branch Chief, DRP/A (CEJ1)Senior Project Engineer, DRP/A (TRF)Team Leader, DRP/TSS (MAS3)RITS Coordinator (MSH3)Only inspection reports to the following:DRS STA (DAP)D. Cullison, OEDO RIV Coordinator (DGC)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\CP\2006\2006-05RP-DBA.wpdRIV:RI:DRP/ASRI:DRP/AC:DRS/EBC:DRS/OBC:DRS/PEBC:DRS/PSBAASanchezDBAllenWBJonesATGodyLJSmithMPShannonE-CEJE-CEJ/RA//RA//RA//RA/2/1/072/1/071/29/071/26/071/29/071/26/07C:DRP/ACEJohnson/RA/2/8/07OFFICIAL RECORD COPYT=Telephone E=E-mail F=Fax U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDockets:50-445, 50-446Licenses:NPF-87, NPF-89 Report: 05000445/2006005 and 05000446/2006005 Licensee:TXU Generation Company LP Facility:Comanche Peak Steam Electric Station, Units 1 and 2 Location:FM-56, Glen Rose, Texas Dates:September 24, 2006 through December 31, 2006Inspectors: D. Allen, Senior Resident InspectorA. Sanchez, Resident Inspector R. Azua, Reactor Inspector B. Baca, Health PhysicistM. Haire, Resident Inspector (Temporary)
S. Rutenkroger, Regional InspectorApproved by:Claude Johnson, Chief, Project Branch ADivision of Reactor Projects
Attachment:
Supplemental Information Enclosure-2-
SUMMARY OF FINDINGS
..................................................-3-
REPORT DETAILS
........................................................-4-
REACTOR SAFETY
.......................................................-4-1R04Equipment Alignment (71111.04)..................................-4-1R05Fire Protection (71111.05).......................................-6-1R08Inservice Inspection Activities (71111.08)...........................-6-1R11Licensed Operator Requalification Program (71111.11)...............-10-1R12Maintenance Effectiveness (71111.12)............................-10-1R13Maintenance Risk Assessments and Emergent Work Evaluation (71111.13). -11-1R15Operability Evaluations (71111.15)...............................-12-1R17Permanent Plant Modifications (71111.17A)........................-12-1R19Postmaintenance Testing (71111.19).............................-13-1R20Refueling and Outage Activities (71111.20).........................-14-1R22Surveillance Testing (71111.22)..................................-15-1R23Temporary Plant Modifications (71111.23)..........................-16-RADIATION SAFETY.....................................................-16-2OS1Access Control To Radiologically Significant Areas (71121.01)..........-16-2OS2ALARA Planning and Controls (71121.02)..........................-18-OTHER ACTIVITIES......................................................-20-4OA1Performance Indicator Verification (71151).........................-20-4OA2Problem Identification and Resolution (71152).......................-21-4OA3Event Follow-up (71153).......................................-22-4OA5Other Activities...............................................-24-4OA6Meetings, Including Exit........................................-25-