ML032820042
| ML032820042 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/31/2003 |
| From: | Kuo P NRC/NRR/DRIP/RLEP |
| To: | Mecredy R Rochester Gas & Electric Corp |
| Kuo PT, NRR/DRIP/RLEP, 415-1183 | |
| Shared Package | |
| ML032820021 | List: |
| References | |
| Download: ML032820042 (7) | |
Text
Safety Evaluation Report with Open Items Related to the License Renewal of the R.E. Ginna Nuclear Power Plant Docket No. 50-244 Rochester Gas and Electric Corporation U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555-0001 October 2003
-iii-ABSTRACT This safety evaluation report (SER) documents the technical review of the R.E. Ginna Nuclear Power Plant (Ginna), license renewal application (LRA) by the U.S. Nuclear Regulatory Commission staff (staff). By letter dated July 30, 2002, Rochester Gas and Electric Corporation (RG&E or the applicant) submitted the LRA for Ginna in accordance with Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54 or the Rule). RG&E is requesting renewal of the operating license for Ginna (license number DPR-18) for a period of 20 years beyond the current expiration of midnight, September 18, 2009.
The Ginna plant is located in the Town of Ontario, in the northwest corner of Wayne County, NY, on the south shore of Lake Ontario. The construction permit was issued by the NRC on April 1966, with a provisional operating license on September 19, 1969, and a full-term operating license on December 10, 1984. The Ginna unit consists of a Westinghouse pressurized-water reactor with nuclear steam supply systems designed to operate at core power levels up to 1520 megawatts-thermal, or approximately 490 megawatts-electric.
This SER presents the status of the staffs review of information submitted to the NRC through September 16, 2003, the cutoff date for consideration in the SER. The staff has identified open items that must be resolved before the staff can make a determination on the application.
These items are summarized in Section 1.5 of this report. In order to close these items, the staff requires the additional information identified. The staff will present its final conclusion on its review of the Ginna application in its update to this SER.
The NRC Ginna license renewal project manager is Russell Arrighi. Mr. Arrighi may be reached at 301-415-3936. Written correspondence should be addressed to the license Renewal and Environmental Impacts Program, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
-xii-ABBREVIATIONS A
ampacity AC alternating current ABVS auxiliary building ventilation system ACI American Concrete Institute ACRS Advisory Committee on Reactor Safeguards AEC Atomic Energy Commission AERM aging effect requiring management AFW auxiliary feedwater AISC American Institute of Steel Construction AMP aging management program AMR aging management review AMSAC ATWS mitigation system actuation circuitry ANS American Nuclear Society ANSI American National Standards Institute AOR abnormal occurrence report AR action report ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials ATWS anticipated transient without a scram AVT all-volatile treatment BMI bottom mounted instrument BTP branch technical position B&W Babcock and Wilcox BWR boiling-water reactor C
Celsius CAR corrective action report CASS cast austenitic stainless steel CCW component cooling water CDHR container hydrogen detectors and recombiner CD-ROM compact disk-read only memory CFR Code of Federal Regulations CI confirmatory item CIC contaminant isolation component CLB current licensing basis CMIS Configuration Management Information System C-RAI clarification of request for additional information CREATS control room emergency air treatment system CRD control rod drive CRDM control rod drive mechanism CS containment spray or carbon steel CST condensate storage tank CUF cumulative usage factor CV check valve CVCS chemical and volume control system
-xiii-CW circulating water DAM data acquisition modules DBD design basis document DC direct current D-RAI draft request for additional information ECCS emergency core cooling system EDG emergency diesel generator EDY effective degradation years EFPY effective full-power year EFWST emergency feedwater storage tank EPR ethylene propylene rubber EPRI Electric Power Research Institute EQ environmental qualification ESF engineered safety features ESFAS engineered safety features actuation system F
Fahrenheit FAC flow-accelerated corrosion FCC Federal Communications Commission Fen environmental fatigue multiplier FERC Federal Energy Regulatory Commission FMP Fatigue Monitoring Program FP fire protection FRP fiberglass reinforced plastic FSAR final safety analysis report ft-pd foot-pound GAI Gilbert Associates, Inc.
GALL Generic Aging Lessons Learned (Report)
GEIS generic environmental impact statement GL generic letter GSI generic safety issue GTR generic technical report HELB high energy line break HEPA high efficiency particulate air HIC high integrity container HRRM high-range radiation monitor HSLAS high strength low alloy steel HTK high temperature kerite HVAC heating, ventilation, and air conditioning I&C instrumentation and controls IASCC irradiation-assisted stress-corrosion cracking ID inner diameter
-xiv-IDR inspection discrepancy report IEB inspection and enforcement bulletin IGA intergranular attack IGSCC intergranular stress-corrosion cracking IN information notice INPO Institute of Nuclear Power Operations IPA integrated plant assessment IR insulation resistance ISG Interim staff guidance ISI inservice inspection J
joule Kip one thousand pounds KV kilovolt LBB leak before break LER licensee event report LOCA loss-of-coolant accident LR license renewal LRA license renewal application MeV one million electron volts MIC microbiologically influenced corrosion MRP Materials Reliability Program MRV minimum required value MSIV main steam isolation valve MSL mean sea level MT magnetic particle test MWe megawatt-electric NACE National Association of Corrosion Engineers NaOH sodium hydroxide NCR nonconformance report NDE nondestructive examination ND-QAP Quality Assurance Program for Station Operation NEI Nuclear Energy Institute NEPA National Environmental Policy Act of 1969 NFPA National Fire Protection Association NIS nuclear instrumentation system NNS non-nuclear safety NPAR nuclear plant aging research NPS nominal pipe size NRC U.S. Nuclear Regulatory Commission NSR non-safety-related
-xv-NSSS nuclear steam supply system OD outside diameter ODSCC outside diameter stress-corrosion cracking OI open item OPPD Omaha Public Power District OPT operability test P&ID piping and instrumentation diagram PLL predicted lower limit PMT post-maintenance test PORV power operated relief valve ppm parts per million psi pounds per square inch PSPM Periodic Surveillance and Preventive Maintenance Program PT penetrant test P/T pressure and temperature PTS pressurized thermal shock PVC polyvinyl chloride PWR pressurized-water reactor PWSCC primary water stress-corrosion cracking QA quality assurance QAPSO Quality Assurance Program for Station Operator RAI request for additional information RCCA rod cluster control assembly RCP reactor coolant pump RCPB reactor coolant pressure boundary RCS reactor coolant system RG regulatory guide RG&E Rochester Gas and Electric Corp.
RHR residual heat removal RPV reactor pressure vessel RTD resistance temperature detector RTPTS reference temperature for pressurized thermal shock RTNDT reference nil ductility transition temperature RV reactor vessel RVI reactor vessel internals RVID Reactor Vessel Integrity Database RWST refueling water storage tank Sa stress intensity SAFW standby auxiliary feedwater SBO station blackout SC structure and component
-xvi-SC-1 safety class 1 SC-2 safety class 2 SC-3 safety class 3 SCC stress-corrosion cracking SEP Systematic Evaluation Program SER safety evaluation report SFP spent fuel pool SFC&FS spent fuel cooling and fuel storage SFR system function report SG steam generator SI safety injection SIT structural integrity test SOC Statements of Consideration SOER significant operating event report SPL steam and power conversion SPCS steam and power conversion systems SPING system-level particulate, iodine, and noble gas monitors SRP Standard Review Plan SRP-LR standard review planlicense renewal SS safety significant or stainless steel SSC structures, systems and components SW service water SWSROP Service Water System Reliability Optimization Program TDAFW turbine-driven auxiliary feedwater TLAA time-limited aging analysis TR topical report TRM technical requirements manual TSC technical support center TS technical specification UFSAR updated final safety analysis report USAS United States of America Standards USE upper-shelf energy UT ultrasonic testing UV ultraviolet V
volt VAC volts alternating current VT visual test WCAP Westinghouse Commercial Atomic Power (report)
WOG Westinghouse Owners Group