Similar Documents at Byron |
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Category:ARCHIVE RECORDS
MONTHYEARML20151W1801998-08-25025 August 1998 Rev 2 to BYR98-109/BRW-98-0339-E, Base Line Ampacity Values for Std Fire Wrap Configurations ML20203J7501997-12-0909 December 1997 Plant Issues Matrix IA-97-451, Plant Issues Matrix1997-12-0909 December 1997 Plant Issues Matrix ML20211H3081997-09-30030 September 1997 Rev 3 to Allowable Leakrate Calculation for SG Interim Plugging Criteria ML20211H3211997-09-30030 September 1997 Rev 4 to CR Thyroid Dose from MSLB Event ML20211H3021997-09-30030 September 1997 Rev 2 to CR Dose for MSLB Accident ML20211H2941997-09-30030 September 1997 Rev 4 to Allowable Leakrate Calculation for SG Interim Plugging Criteria ML20210P1391997-08-22022 August 1997 Rev 0 to BYR97-332, CR Dose for MSLB Accident ML20210P1601997-08-21021 August 1997 Rev 1 to ATD-0410, Allowable Leakrate Calculation for Steam Generator Interim Plugging Criteria ML20148T7281997-06-27027 June 1997 Rev 4 to BWR-97-0339-M, Byron & Braidwood CR Heat Up Evaluation ML20148T7421997-06-25025 June 1997 Rev 4 to BRW-97-0624-M, Determination of Div 11 & 12 Miscellaneous Electrical Equipment Rooms Transient Temp Profiles Following Loss of Ventilation ML20140D3901997-03-12012 March 1997 Determination of 2-Dimensional Pressure Distribution on Byron/Braidwood D4 SG Tube Support Plate During Mslb ML20133K4621997-01-17017 January 1997 Press Release III-97-05, NRC to Hold Predecisional Enforcement Conference W/Comm Ed on Apparent Violations at Byron Plant ML20129G5221996-10-0202 October 1996 Press Release III-96-61, Byron Nuclear Plant Rated Superior in Two Areas, Good in Two Areas in NRC Performance Assessment ML20115F3681996-06-0303 June 1996 Ampacity Derating for Std Fire Wrap Configurations ML20115F3531996-04-19019 April 1996 Verification of Models for Fire-Wrapped Conduits & Cable Trays Against Test Data ML20092B1611995-09-0404 September 1995 Calculation of Byron D4 SG Tube Support Plate Differential Pressures During MSLB W/RELAP5M2 ML20080H5231995-01-23023 January 1995 Darmatt Firewrap Matl Cable Ampacity Derating Factor Calculation ML20062N8191993-12-29029 December 1993 Battery Sizing Calculation ML20062N8211993-12-0909 December 1993 Battery Sizing Calculation ML20085M4691991-11-11011 November 1991 Responds to Aquatic Resource Questions Re NUMARC Survey in Support of NRC License Renewal Rulemaking ML20133P0461985-08-0101 August 1985 Rev 0 to Calculation Q-13, Calculations for Justification of Electrical Separation Distance Between Safety-Related & Nonsafety-Related Raceways ML20133P0931985-08-0101 August 1985 Rev 0 to Calculation Q-14, Calculation for Justification for Electrical Separation Between Safety-Related & Nonsafety-Related Cables When One in Free Air & Other in Raceway ML20091M8221983-01-28028 January 1983 D-3 SG Downcomer Flow Rates ML20091M8391983-01-28028 January 1983 Model D-3 Preheater Temps ML20091M8611983-01-28028 January 1983 Comparison of Ringhals & Transflo Pressure Drops Through D-3 Preheater ML20011A5591981-10-0202 October 1981 Transcript of 811002 Telcon W/Aslb,Util,Nrc Ofc of Executive Legal Director,Dekalb Area Alliance for Responsible Energy & Safe Energy for New Haven.Notice of Filing & Certificate of Svc Encl 1998-08-25
[Table view] Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20133K4621997-01-17017 January 1997 Press Release III-97-05, NRC to Hold Predecisional Enforcement Conference W/Comm Ed on Apparent Violations at Byron Plant ML20129G5221996-10-0202 October 1996 Press Release III-96-61, Byron Nuclear Plant Rated Superior in Two Areas, Good in Two Areas in NRC Performance Assessment 1997-01-17
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i U.S. NUCLEAR REGULATORY COMMISSION ;
Region 111 Office of Public Aff irs l 801 Warrenville Road, Liste IL 60332-4351 NEWS ANNOUf4 CEMENT: Rill-96-61 October 2,1996 l CONTACT: Jan Strasma 630/829-9663 I Angela Dauginas 630/829-9662 E-mail: opa3@nrc. gov BYRON NUCLEAR PLANT RATED " SUPERIOR" IN TWO AREAS," GOOD" IN TWO AREAS IN NRC PERFORMANCE ASSESSMENT The Byron Nuclear Power Station, operated by Commonwealth Edison Co., has received performance ratings of
" superior" in maintenance and engineering and " good" in operations and plant support in the Nuclear Regulatory Commission staffs latest Systematic Assessment of Licensee Performance (SALP) report for the facility.
l The assessment covers the period August 21,1994, through August 17 of this year. l The NRC staff and Commonwealth Edison officials will discuss the evaluation during a meeting set for 10 a.m. on October 8 at the Training Building at the Byron plant site. The meeting will be open for public observation. NRC officials will be available afterwards to speak with reporters, state and local officials, and members of the public.
NRC SALP reports rate utilities in four functional areas - plant operations, maintenance, engineering, and plant support - and assign ratings of Category 1,2, or 3 depending on whether their performance in those areas was superior, good or acceptable. The report on Byron gives the plant a " Category 1" rating in maintenance and engineering, indicating superior performance. It assigns a rating of " Category 2" to operations and plant support, indicating good performance.
NRC Regional Administrator A. Bill Beach, in a letter to the utility, said: " Conduct of nuclear activities at Byron, while excellent overall, declined in operations and plant support when compared to the last SALP period."
He continued,"The decline was due to the continuation of operator errors, examples of a less conservative safety focus and evaluation of risk considerations in planned activities, and significant weaknesses in the chemistry program."
l
- Byron's overall performance was characterized by excellent communications and by active teamwork tc solve plant problems," Mr. Beach said. Material condition was, with few exceptions, excellent; equipment was reliable and available; work planning was thorough, systematic, and effective. Engineering provided excellent support for extensive steam generator inspections and aggressive followup on generic issues."
The ratings for each functional area of this report and the previous report were:
1 Functional Area Current Period Previous Period i Operations 2 1 Maintenance 1 1 4 Engineering 1 1 Plant Support 2 1 l
The full SALP report is available on the NRC's intemet web site at: <http //www.nrc. gov /OPA>. SALP reports for all nuclear plants are also available as they are issued through an electronic mailing list. To receive these reports send an e-mail message to listproc@nrc. gov with no subject and with the following message: subscribe salp youtfirstname yourlastname.
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