ML20203G548
From kanterella
| ML20203G548 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 03/31/1986 |
| From: | Richard Anderson, Bosehore K, Robins R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18149A119 | List: |
| References | |
| VEP-NE-1-A, NUDOCS 8604290157 | |
| Download: ML20203G548 (72) | |
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. ML20199H4071997-06-30030 June 1997 Non-proprietary,Rev 1 to WCAP-14733, Probabilistic Analysis of Reduction in Turbine Valve Test Frequency for Nuclear Plants W/W BB-269 Turbines W/Steam Chests ML20116M5361995-11-22022 November 1995 Rv Closure Head Penetration Tube Id Weld Overlay Repair, Westinghouse Owners Group Program Rept 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. ML20072T8311994-07-31031 July 1994 Response to Closure Ltr for NRC GL 92-01,Rev 1 ML20065K1481993-11-30030 November 1993 Nonproprietary Rev 1 of Heatup & Cooldown Limit Curves for Normal Operation for North Anna Unit 1 ML20046B4751993-07-31031 July 1993 Rev 2 to Non-Proprietary Westinghouse Series 44 & 51 SG Generic Sleeving Rept. ML20046B4501993-07-31031 July 1993 Rev 1 to Non-Proprietary Specific Application of Laser Welded Sleeves for North Anna Unit 2 Sg. ML18152A0411992-11-30030 November 1992 Suppl 1 to Pdq Two-Zone Model. ML20115G6701992-09-30030 September 1992 Rev 1 to Response to GL 92-01 VEPCO North Anna Unit 1 & North Anna Unit 2 ML20095L1341992-04-30030 April 1992 Nonproprietary North Anna Unit 1 1992 SG Operating Cycle Evaluation ML20096F2701992-04-30030 April 1992 Nonproprietary North Anna Unit 1 SG Startup Approval Meeting Presentation Matls 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. ML20082N9881991-08-31031 August 1991 Steam Generator Operating Cycle Evaluation ML20081L4951991-02-28028 February 1991 Steam Generator C-3 Startup Approval Meeting Presentation Matls ML20028H0851990-07-31031 July 1990 VEP-NAF-1, Pdq Two Zone Model. ML20059L0761990-07-31031 July 1990 Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code ML20012C0121990-01-31031 January 1990 Analysis of Capsule U from VEPCO North Anna Unit 2 Reactor Vessel Radiation Surveillance Program. ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20246D7641989-07-31031 July 1989 Steam Generator Update Tube Bundle Structural Integrity Presentation ML20012D7661989-05-31031 May 1989 Nonproprietary North Anna Unit 2 Evaluation for Tube Vibration Induced Fatigue. ML20235M9111989-02-20020 February 1989 Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue ML20207L7781988-10-0606 October 1988 Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue ML20207L9261988-09-30030 September 1988 Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) ML20154M2421988-09-30030 September 1988 Simulate-3 Validation & Verification ML20155D1681988-08-31031 August 1988 Safety Evaluation:Zirconium Base Advanced Cladding Matls Usage in North Anna Unit 1 Demonstration Fuel Assemblies 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 ML20196C1281988-05-31031 May 1988 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation ML20154J9831988-04-30030 April 1988 RCS Flow Anomaly Investigation Rept ML20150C5151988-01-31031 January 1988 Rev 3 to North Anna Units 1 & 2 Reactor Vessel Fluence & Ref Temp PTS Evaluations ML20237C4091987-11-30030 November 1987 Nonproprietary Rev 2 to Byron/Braidwood T-Hot Reduction Final Licensing Rept ML20236H7751987-09-30030 September 1987 Cycle 5 Core Performance Rept ML20235K4271987-09-30030 September 1987 Nonproprietary North Anna Unit 1 Steam Tube Rupture & Remedial Actions Technical Evaluation ML20235M4151987-05-31031 May 1987 Cycle 6 Core Performance Rept 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. ML20207H9761986-11-30030 November 1986 Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for Byron 1 & 2 & Braidwood 1 & 2 ML20210A6051986-09-0505 September 1986 Addendum a to Vol II of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification ML20213E0551986-08-31031 August 1986 Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for North Anna Units 1 & 2 ML20155J4911986-05-31031 May 1986 Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block ML20155J5051986-05-31031 May 1986 Rev 1 to Functional Design Requirements for Control Element Assembly Calculator ML20155J5231986-05-31031 May 1986 Rev 1 to Functional Design Requirement for Core Protection Calculator ML20203C7101986-03-31031 March 1986 Reactor Pressure Vessel & Surveillance Program Matls Licensing Info for Surry Units 1 & 2 ML20203G5481986-03-31031 March 1986 Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs 1998-05-31 Category:TEXT-SAFETY REPORT MONTHYEARML20217N9281999-10-20020 October 1999
[Table view]Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 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. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 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 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 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 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with 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 ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With 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 ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With 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 ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year 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 ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr 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 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 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 ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant 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. 1999-09-08 |
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