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Category:ARCHIVE RECORDS
MONTHYEARML17264B0451997-09-19019 September 1997 Rev 3 to 86-1234820-03, Low Temp Overpressure Analyses Summary. ML17265A6891997-06-30030 June 1997 Rev 1 to Calculation 96190-C-68, Pressure Locking Analysis for Valve(S) 871A/B. ML17264A9261997-06-10010 June 1997 Low Temp Overpressure Analyses Summary Rept, Calculational Summary Sheet 86-1234820-01 ML20132A3921996-12-13013 December 1996 Press Release I-96-81, NRC Staff Proposes to Fine Rg&E $100,000 for Alleged Violations at Ginna Nuclear Plant ML20129B7031996-10-22022 October 1996 Press Release I-96-69,informing That NRC Has Rescheduled Meeting W/Officials of Rg&E to Discuss Latest Systematic Assessment of Licensee Performance at Gnpp ML20128M2981996-10-15015 October 1996 Press Release I-96-68, NRC Staff Rates Ginna Good in Three Areas & Excellent in One Category on Latest SALP Rept ML17264A6131996-08-0202 August 1996 Rev 0 to Verification of Pressure Locking Analysis Program Preslok. ML17264A2651995-11-16016 November 1995 Gamma-Body Offsite Dose Calculation. ML17264A6111993-12-23023 December 1993 Rev 1 to Valve Thrust Calculation for 6x4x6 Class 300# Anchor Darling Gate Valve,857A,B & C & 860A,B,C & D. ML20085M5451991-11-11011 November 1991 Responses to NUMARC Aquatic Resources Survey & Socioeconomic Question in Support of NRC License Renewal Rulemaking ML17262A4511991-04-10010 April 1991 Devonrue Calculation Re Plant Atmospheric Relief Valve (ARV) Area Ambient Temp rise-revised Methodology ML17262A4531990-06-0505 June 1990 Devonrue Calculation Re Plant Turbine Driven Auxiliary Feedwater Pump Area Ambient Temp Rise ML17251A4791989-04-14014 April 1989 Prv Block Valve Thrust Calculation. ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 ML20203H2851986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 ML20132D2121985-06-24024 June 1985 Human Factors Engineering Dcrdr In-Progress Audit,Re Ginna Nuclear Power Plant ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML17256A8381982-03-23023 March 1982 Slide Presentation from 820323 Meeting Re Steam Generator Repair Activities at Facility ML17261A5941966-09-16016 September 1966 Package of Incomplete Brookwood Project Requirement Outline Repts Re Instruments & Equipment 1997-09-19
[Table view] Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20132A3921996-12-13013 December 1996 Press Release I-96-81, NRC Staff Proposes to Fine Rg&E $100,000 for Alleged Violations at Ginna Nuclear Plant ML20129B7031996-10-22022 October 1996 Press Release I-96-69,informing That NRC Has Rescheduled Meeting W/Officials of Rg&E to Discuss Latest Systematic Assessment of Licensee Performance at Gnpp ML20128M2981996-10-15015 October 1996 Press Release I-96-68, NRC Staff Rates Ginna Good in Three Areas & Excellent in One Category on Latest SALP Rept 1996-12-13
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- 8 United States Nuclear Rrgulstory Commission Offica of Public Affairs, Region I 475 Allendale Road King of Prussia, PA 19401 Phones 610/337-5330 Fax: 610/337-5241 l Internet dps@nrc. gov or nas@nrc. gov I-96-81 December 13, 1996
Contact:
Diane Screnci FOR IMMEDIATE RELEASE Neil A. Sheehan NRC STAFF PROPOSES TO FINE RG&E $100,000 FOR ALLEGED VIOLATIONS AT GINNA NUCLEAR PLANT j The Nuclear Regulatory Commission has proposed a $100,000 fine against the operator of the Robert E. Ginna nuclear power plant for two alleged violations involving safety valves at the Ontario, N.Y., facility, j i
The first alleged violation facing Rochester Gas & Electric (RG&E) ;
Corporation stems from a failure to adequately verify the ability of the '
plant's two residual heat removal system core deluge valves to open when necessary. Located in the plant's containment structure in two parallel lines that discharge into the reactor vessel, the valves, upon receipt of a safety signal, would need to open and allow the injection of water from the residual heat removal system into the vessel. They also serve a pressure isolation function for the vessel. Failure of these valves to operate properly would l significantly degrade the ability of the emergency core cooling system to perform as required during an accident.
RG&E's failure to adequately correct the condition despite past opportunities to do so constituted the second alleged violation. <
Since the discovery of the alleged violations, during special NRC inspections conducted last July and August, the utility has modified the valves to assure they perform as intended. Also, RG&E conducted significant additional testing and re-analyses of the valves and concluded they were, in fact, operable prior to modifications in August 1996.
l NRC Region 1 Administrator Hubert J. Miller expressed concern that RG&E l had not performed adequate analysis and verification of the valves
- i capabilities prior to August 1996, despite indications that further analysis was warranted. Mr. Miller also said that given the regulatory significance and duration of the infractions, as well as the impact on plant safety if the i valves had not functioned as needed, they have been catergorized as a Severity Level III problem that warrants a civil penalty. '
"These findings demonstrate the importance of management taking appropriate action to assure that 1.) design inputs for safety-related components are adequately analyzed, and appropriately verified; and 2.)
indications of adverse condicions, including inadequate analysis, are promptly identified and corrected," Mr. Miller wrote in a letter to RG&E.
The utility has 30 days to pay the proposed fine or to request in j writing that part or all of the penalty be withdrawn. j 9612160048 961213 PINT PRESS R RC-I-96-081 PDR-130111 pgc>l cis