ML20196C128
From kanterella
ML20196C128 | |
Person / Time | |
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Site: | North Anna |
Issue date: | 05/31/1988 |
From: | Palusamy S, Schmertz J, Yanichko S WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
To: | |
Shared Package | |
ML20196B903 | List: |
References | |
WCAP-11791, NUDOCS 8812070182 | |
Download: ML20196C128 (36) | |
Similar Documents at North Anna | |
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
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[Table view]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 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. 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 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 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. ML20012C0121990-01-31031 January 1990 Analysis of Capsule U from VEPCO North Anna Unit 2 Reactor Vessel Radiation Surveillance Program. 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. ML20155D1681988-08-31031 August 1988 Safety Evaluation:Zirconium Base Advanced Cladding Matls Usage in North Anna Unit 1 Demonstration Fuel Assemblies ML20196C1281988-05-31031 May 1988 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation ML20150C5151988-01-31031 January 1988 Rev 3 to North Anna Units 1 & 2 Reactor Vessel Fluence & Ref Temp PTS Evaluations ML20235K4271987-09-30030 September 1987 Nonproprietary North Anna Unit 1 Steam Tube Rupture & Remedial Actions Technical Evaluation ML20236H7751987-09-30030 September 1987 Cycle 5 Core Performance Rept ML20235M4151987-05-31031 May 1987 Cycle 6 Core Performance Rept ML18149A5121986-11-30030 November 1986 Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. 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ML20082M8851983-10-31031 October 1983 Nonproprietary Version of VEPCO Evaluation of Control Rod Ejection Transient ML20100G2621983-10-31031 October 1983 Study of Effects of Reduced Number of Thimbles on Results of In-Core Flux Map Analysis ML20078K3361983-09-30030 September 1983 VEPCO Nomad Code & Model ML20065Q4581982-10-31031 October 1982 Steam Generator Impacted Tube Ends Recovery Evaluation ML18139C0611982-10-0404 October 1982 Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code. ML20077J9621982-07-31031 July 1982 Cycle 3 Core Performance Rept ML20010B6241981-07-31031 July 1981 VEPCO Flame Model. ML20010B6171981-07-31031 July 1981 Pdq 07 One Zone Model. ML20010B6101981-07-31031 July 1981 Pdq 07 Discrete Model. 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[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. 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