ML20203C710
From kanterella
| ML20203C710 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/31/1986 |
| From: | Lowe A BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML18149A089 | List: |
| References | |
| BAW-1909, NUDOCS 8604210225 | |
| Download: ML20203C710 (42) | |
Similar Documents at Surry | |
|---|---|
Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20248F7441998-05-31031 May 1998
[Table view]Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18151A6591997-10-31031 October 1997 Non-proprietary WCAP-14984, Handbook on Flaw Evaluation Surry Units 1 & 2 SGs Upper Shell to Cone Weld Regions. ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML18151A6441995-10-31031 October 1995 Response to GL 92-01,Rev 1,Suppl 1 for Virginia Power North Anna Units 1 & 2 Beltline Matls & Surry Units 1 & 2 Rotterdam Beltline Weld Metals. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML18152A0411992-11-30030 November 1992 Suppl 1 to Pdq Two-Zone Model. ML18153D1641991-12-31031 December 1991 Demonstration of Compliance of Primary Loop Pump Casings of Surry Units 1 & 2 to ASME Code Case N-481. ML18151A8941991-11-30030 November 1991 Reactor Power Distribution Analysis Using Moveable In-Core Detection Sys & Tip/Cecor Computer Code Package. ML20059L0761990-07-31031 July 1990 Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code ML20028H0851990-07-31031 July 1990 VEP-NAF-1, Pdq Two Zone Model. ML20235N2761988-06-30030 June 1988 Analysis of Capsule V from Virginia Power Co Surry Unit 1 Reactor Vessel Radiation Surveillance Program - Surry Unit 1 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation ML20210B4801987-04-30030 April 1987 Rev 1 to Customer Designated Distribution Surry Units 1 & 2 Reactor Vessel Fluence & Ref Temp PTS Evaluations ML20214M0311987-02-28028 February 1987 Analysis of Capsule V from VEPCO Surry Unit 1 Reactor Vessel Radiation Surveillance Program ML18149A5121986-11-30030 November 1986 Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. ML20203G5481986-03-31031 March 1986 Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs ML20203C7101986-03-31031 March 1986 Reactor Pressure Vessel & Surveillance Program Matls Licensing Info for Surry Units 1 & 2 ML20135H9491985-08-31031 August 1985 Rev 1 to Reload Nuclear Design Methodology ML20137W7481985-08-31031 August 1985 Steam Generator Girth Weld 6 Repair Rept ML20133H3591985-07-31031 July 1985 Statistical DNBR Evaluation Methodology ML20128Q2751985-05-31031 May 1985 Revised Nomad Code & Model ML20129E9881985-05-30030 May 1985 VEPCO Reactor Sys Transient Analysis Using Retran Computer Code ML18142A3501985-03-31031 March 1985 Cycle 7 Core Performance Rept. ML18142A1531984-12-31031 December 1984 Nonproprietary Version of Revised VEPCO Evaluation of Control Rod Ejection Transient. ML20140D8891984-10-31031 October 1984 VEPCO Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs ML18141A2581983-10-31031 October 1983 Revised Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code. ML20082M8851983-10-31031 October 1983 Nonproprietary Version of VEPCO Evaluation of Control Rod Ejection Transient ML20078K3361983-09-30030 September 1983 VEPCO Nomad Code & Model ML18141A0541983-07-31031 July 1983 Cycle 6 Core Performance Rept. W/Undated Ltr ML18139C2641983-03-31031 March 1983 Cycle 6 Core Performance Rept. ML18139C0611982-10-0404 October 1982 Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code. ML18139B6631981-12-31031 December 1981 Cycle 5 Core Performance Rept. ML20010B6101981-07-31031 July 1981 Pdq 07 Discrete Model. ML20010B6171981-07-31031 July 1981 Pdq 07 One Zone Model. ML20010B6241981-07-31031 July 1981 VEPCO Flame Model. ML18139B4011981-04-30030 April 1981 Reload Nuclear Design Methodology. ML19352A2791981-03-31031 March 1981 Reactor Sys Transient Analyses Using Retran Computer Code. ML20002D2771980-12-31031 December 1980 Control Rod Reactivity Worth Determination by Rod Swap Technique. ML18139A2941979-12-31031 December 1979 Metallurgical Investigation of Cracks in Steam Generator Feedwater Lines of Surry Station 1. ML18136A0221979-08-31031 August 1979 VEPCO Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code. ML18116A3641979-07-23023 July 1979 GE Vertical Induction Motors Inside Containment Recirculation Spray Pumps. ML18113A7711978-10-31031 October 1978 Vepco Flame Model. Util Developed 3 Dimensional(X,Y,Z) Modified Diffusion Therory Calculational Model Designated as Vepco Flame Model.Accuracy of Model Is Demonstrated Through Comparisons Taken at Units 1 & 2 1998-05-31 Category:TEXT-SAFETY REPORT MONTHYEARML18152A2811999-10-12012 October 1999
[Table view]Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30 |
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