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Category:ARCHIVE RECORDS
MONTHYEARL-94-014, Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression1998-01-30030 January 1998 Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression ML20195D0221998-01-26026 January 1998 Rev 1 to Assessment of Doses in Unit 2 CR Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel ML20195C6421998-01-16016 January 1998 Change 1 to Rev 1 of Calculation 456, Combined BV1-BV2 Control Room Doses Due to Waste Gas Sys Line Rupture Accident at BV1 ML20217J8361997-10-0202 October 1997 Rev 1 to DE&S-SR/EM01, Ampacity Derating Factors of Fire- Protected Conduits L-96-010, Safety Analysis of Eab,Lpz & CR Doses from Main Steam Line Break Outside of CNMT at U2 W/Increased Primary-to-Secondary Leakage (SG Apc)1997-02-25025 February 1997 Safety Analysis of Eab,Lpz & CR Doses from Main Steam Line Break Outside of CNMT at U2 W/Increased Primary-to-Secondary Leakage (SG Apc) L-95-008, Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage1997-02-24024 February 1997 Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage ML20195F2321997-01-24024 January 1997 Rev 0 to Calculation 93C1783.2-03, IPEEE Seismic Fragility (SPRA) Review for Beaver Valley Unit 2 Structures ML20195F2111997-01-23023 January 1997 Rev 0 to Calculation 93C1783.2-02, IPEEE Fragility Evaluation for Beaver Valley Unit 2 Development of Beaver Valley Unit 2 HCLPFs for Flat Bottom Tanks ML20133F3281997-01-13013 January 1997 Press Release I-97-03, NRC Staff to Meet W/Officials of Dl to Discuss Apparent Violations at Bvnp L-96-012, Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity1996-12-19019 December 1996 Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity L-96-011, RCS & SG Isotopic Concentrations,Pre-Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity1996-12-19019 December 1996 RCS & SG Isotopic Concentrations,Pre-Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity L-96-021, Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations1996-12-19019 December 1996 Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations ML20134L2991996-11-20020 November 1996 Press Release I-96-75, Bvnp Rated 'Good' in Three Areas, 'Superior' in Fourth Area of NRC Assessment Rept ML20134D2211996-10-17017 October 1996 Press Release 96-145, NRC Asks Utility Licensees for Info on Concrete Containment Foundations at Nine Nuclear Plants ML20141F3021995-12-13013 December 1995 Battery Chargers & Inverters Anchorage Evaluation ML20141F2761995-11-30030 November 1995 Anchorage Evaluation for Various Instruments ML20096B4351995-11-0606 November 1995 SA of Common CR Doses from MSLB Outside of CNMT at U1 W/ Increased Primary-to-Secondary Leakage ML20141F2821995-10-30030 October 1995 GE Switchgear Anchorage Evaluation ML20141F3071995-05-0101 May 1995 Anchorage Evaluation for BAT-CHG-2 ML20195F1961994-01-31031 January 1994 Rev 0 to Calculation 93C1783-13, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1,Reactor Coolant Pump ML20195F2441994-01-31031 January 1994 Rev 0 to Calculation 93C1783-07, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG,EE-EG-1,2 ML20195F2511994-01-31031 January 1994 Rev 0 to Calculation 93C1783-40, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG Building ML20128E3111992-11-17017 November 1992 Package Consisting of Insp Rept 50-344/PA-92-02 on 921021- 22.No Violations Noted.Major Areas Inspected:Shipping Documentation,Packaging/Package Insp,Labeling,Marking, Placarding,Vehicle Insp,Radiation & Contamination Surveys ML20079N0931989-12-31031 December 1989 Response to Questions Re Beaver Valley Unit 1 Impingement, Entrainment Monitoring rept,890131 Observation of Gizzard Shad Discharge of BVPS,1983 Annual Environment Rept Nonradiological ML20127C7441989-11-0808 November 1989 Partially Deleted Incident Rept 1-89-97 Dose Assessments & Associated Hpes Involvong Rj Brooks & Assoc Steam Generator Fosar Activities at Facility ML20247N1491989-09-26026 September 1989 Handout on Beaver Valley Unit 2 MSIV Mod & Test Program ML20127A5651989-09-11011 September 1989 Package of Handwritten Radiological Work Sheets Re Steam Generator Annulus Secondary Side Hand Hole Insps L-89-021, Rev 0123 to ERS-SFL-89-021, Safety Analysis of Dose Consequences of Locked Rotor Accident at Beaver Valley Power Station 1 w/18% Fuel Failure,Exclusion Area Boundary,Low Population Zone,Control Room1989-07-28028 July 1989 Rev 0123 to ERS-SFL-89-021, Safety Analysis of Dose Consequences of Locked Rotor Accident at Beaver Valley Power Station 1 w/18% Fuel Failure,Exclusion Area Boundary,Low Population Zone,Control Room ML20195E0981988-05-10010 May 1988 Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Habitability Due to Design Bases Accidents (Except LOCA) at BV1 ML20236Y5401987-11-26026 November 1987 RM-GW-101 Tech Spec Change Justification ML20245C6731987-10-0101 October 1987 Rev 1 to Calculation 211X-G(B)-290, Differential Settlement of SWS Lines Between Reactor & Safeguards. Oversize Info Encl ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20207F6471987-04-13013 April 1987 Doses in Combined Unit 1 & 2 CR Due to Waste Gas Sys Rupture at Unit 1 with 500 CFM Normal CR Ventilation ML20151E8051987-02-0202 February 1987 Settlement of SWS Piping - Intake Structure to Valve Pit. W/Four Oversize Encls ML20203H2851986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 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 ML20204J1551986-07-0707 July 1986 Telcon of Significant Deficiency Rept SDR 86-09 Re Erratic Position Indication from Masoneilan Control Valves.Cause Unstated.Operators May Take Inappropriate Actions Based on Faulty Indication.Indicator Arms Upgraded ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20079F1761984-01-13013 January 1984 Amended Slides & Diagrams Utilized During 831220 Meeting W/Nrc Re Cable Separation Program.W/One Oversize Figure. Aperture Card Is Available in PDR ML20133N1301979-04-10010 April 1979 Record of 790320 Telcon W/D Ford of Ucs Re Participation in Facility Pipe Stress Issue 1998-01-30
[Table view] Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20133F3281997-01-13013 January 1997 Press Release I-97-03, NRC Staff to Meet W/Officials of Dl to Discuss Apparent Violations at Bvnp ML20134L2991996-11-20020 November 1996 Press Release I-96-75, Bvnp Rated 'Good' in Three Areas, 'Superior' in Fourth Area of NRC Assessment Rept ML20134D2211996-10-17017 October 1996 Press Release 96-145, NRC Asks Utility Licensees for Info on Concrete Containment Foundations at Nine Nuclear Plants 1997-01-13
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. United States Nuclear Regulatory Commission l ,
"' Office of Public Affairs, Region I 475 Allendale Road King of Prussia, PA 19401 l Phone: 610/337-5330 Fax: 610/337-5241 Internet: dps@nrc. gov or nas@nrc. gov l
! I-96-75 November 20, 1996 i
Contact:
Diane Screnci FOR IMMEDIATE RELEASE i
Neil A. Sheehan l BEAVER VALLEY NUCLEAR PLANT RATED " GOOD" IN THREE AREAS, j " SUPERIOR" IN FOURTH AREA OF NRC ASSESSMENT REPORT
! The Beaver Valley nuclear power plant received performance I ratings of " good" in three areas and " superior" in the fourth area l of the Nuclear Regulatory Commission's latest systematic assessment of licensee performance (SALP) of the facility. ,
l The SALP report was sent November 15 to Duquense Light l Company, which operates the facility near Shippingport,
! Pennsylvania. It evaluates the plant's performance from June 4, l 1995, through September 28 of this year. .
NRC systematic assessment reports rate licensees in four functional areas - plant operations, maintenance, engineering, and plant support - and assign ratings of Category 1, 2 or 3 depending on whether performance in those areas was superior, good or adequate. The report on Beaver Valley gives the plant a Category 1 (superior) rating in maintenance, and a Category 2 rating in operations, engineering and plant support, indicating " good" performance.
In a letter to Duquesne Light, NRC Regional Administrator Hubert J. Miller said, "Overall, the NRC observed good safety performance at Beaver Valley Power Station. Senior station management demonstrated a conservative operating philosophy and has l taken steps to improve performance standards and expectations. The J problem identification and corrective action processes generally j have been effective in identifying and correcting material deficiencies and human performance issues."
The administrator had these comments on Beaver Valley's performance in the four rated categories:
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200128 9611200234 961120 m re)
PDR PRESS R RO~E-96-075 9\
PDR oh
OPERATIONS overall performance in operations was good and has improved since the last assessment period. Operator knowledge, skills, and handling of normal plant startup and shutdown evolutions were very good. Operator response to degraded plant conditions and transients was also good. Operators usually displayed a questioning attitude in identifying problems. Some problems in routine control room activities occurred early in the assessment period; however, emphasis on self-checking practices led to improved performance later in the period. Strained senior reactor operator (SRO) staffing levels contributed to some performance problems, such as missed surveillances. NRC will follow closely the effectiveness of current management steps to improve SRO staffing.
MAINTENANCE Maintenance programs have been effectively implemented with excellent management oversight ensuring reliable operation of plant safety equipment. Improvements were noted in procurement and non-outage backlog management. We will follow your current efforts to improve maintenance planning and work control processes as they are important to further backlog reduction. Some weaknesses were noted in the quality and scheduling of equipment testing, and in vendor oversight.
ENGINEERING Engineering performance was good. Management attention to engineering activities and improvement initiatives was considered a strength. The quality of technical work and design changes was good; however, some corrective actions for identified deficiencies were not timely. A number of equipment problems impacting plant operations occurred during the period underscoring the importance of directing system engineering focus on plant material condition.
PLANT SUPPORT The radiological controls program was generally aggressive and properly focused, but was not successful in obtaining consistent worker adherence to controls. Superior performance was exhibited in the effluent controls and environmental monitoring areas. The security program continued to be effective. The EP program maintained excellent offsite rapport with offsite agencies and an excellent training program, but exercises revealed some weaknesses in response and technical assessment.
EDITORS: A copy of the full SALP report is available from this j office. ALP reports are also available on the NRC's Internet web site (http://www.nrc. gov /OPA) and by e-mail subscription. To receive SALP reports by e-mail as they are issued, send an e-mail to listproc@nrc. gov with the j following message: subscribe salp yourfirstname yourlastname, e
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