ML18139C061
ML18139C061 | |
Person / Time | |
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Site: | Surry, North Anna, 05000000 |
Issue date: | 10/04/1982 |
From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
Shared Package | |
ML18139C060 | List: |
References | |
VEP-FRD-33-ERR, NUDOCS 8210120305 | |
Download: ML18139C061 (1) | |
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 |
Text
- PAGE 1 TABLE 1' ': Summary of Comparisons with THING-I Case I Pressure PotJer Flow I Tin I FQE Axial I Minimum DNBR No. I (psia) (%) (%) I Co F) I Offset I COBRA THING- I
-------- ------- -------1----- ---------1-------- --------
I I 1 2200. 1 12 . 10 0 . 554. I 1. 24 zero I 1. 27 1 . 30 I I 2 2400. 118. 10 0 . 563. I 1 . 03 zero I 1. 30 1. 33 I
3 2400. 101. 10 0 . 563. I 1. 03 large 1. 32 1. 39 positive 4 2400. 81. 7 10 0. 618.4 1. 03 large 1.30 1. 33 negative 5 1855. 11 2 . 90. 515. 1. 03 zero 1. 47 1. 47 6 2220. 100.5 76.5 547. 1. 03 zero 1. 32 1. 32
~':
7 2400. 101. 10 0 . 563. 1.03 large 1. 42 1. 50 positive
- Supplemental information to the letter from R. H. Leasburg (Vepco) to H. R. Denton (NRG), Serial No. 284, dated May 23,1982, entitled "Vepco Reactor Core Thermal Hydraulic Analysis Using the COBRA-IIIc/MIT Computer Code"
.,~aii 0120305 a21004 I* * *PDR -ADOCK 05000280
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