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List of results

• ML20198D800  + (Forwards Rev 1 to Application for Renewal of Certificate of Compliance 5450 for Models RCC-1,-2,-3 & -4 & Addl Info in Response to NRC 860228 Request Re 851220 Application for Renewal of Certificate of Compliance 5450)
• ML20151M894  + (Forwards Rev 1 to Application for SNM License for Receipt, Possession & Storage of Unirradiated Reactor Fuel.Rev Contains Changes Re Design,Evaluation & Designation of Spent Fuel Racks for Temporary Storage of New Fuel)
• ML20202G904  + (Forwards Rev 1 to Application for SNM License,Including Addl Info Requested in NRC ,Proof of Financial Protection Per 10CFR140.15,clarification of Fuel Storage Areas Involved During New Fuel Receipt & Increase in U-235)
• ML20128C573  + (Forwards Rev 1 to Apr 1978 Monthly Operating Rept for Monticello Nuclear Generating Plant,Correcting Calculational Error)
• ML20128C577  + (Forwards Rev 1 to Apr 1978 Monthly Operating Rept for Monticello Nuclear Generating Plant,Correcting Calculational Error)
• PY-CEI-NRR-0061, Forwards Rev 1 to Aptech Engineering Svcs Rept AES-8211352-1 for Jul 1983, Analysis of Inaccessible & Potentially Rejectable Defects in Perry Plant  + (Forwards Rev 1 to Aptech Engineering Svcs Rept AES-8211352-1 for Jul 1983, Analysis of Inaccessible & Potentially Rejectable Defects in Perry Plant)
• ML20024D143  + (Forwards Rev 1 to Aptech Engineering Svcs Rept AES-8211352-1 for Jul 1983, Analysis of Inaccessible & Potentially Rejectable Defects in Perry Plant.)
• ML20056H595  + (Forwards Rev 1 to Armed Forces Radiobiology Research Inst Reactor Facility Physical Security Plan,Per 10CFR50.54(p)(2).Plan Withheld,Per 10CFR2.790)
• LG-87-053, Forwards Rev 1 to Attachment a of Westinghouse Informing NRC of Actions Taken to Correct Violation Noted in Insp Rept 70-1151/87-12.Rev Corrects Incorrect Refs to Specific Paragraphs in 10CFR61  + (Forwards Rev 1 to Attachment a of Westinghouse Informing NRC of Actions Taken to Correct Violation Noted in Insp Rept 70-1151/87-12.Rev Corrects Incorrect Refs to Specific Paragraphs in 10CFR61)
• ML20128K114  + (Forwards Rev 1 to Attachment to Cygna Energy Svcs Re Phase 4 Open Items - Punching Shear to Omit Ref to Pipe Support Drawing MS-1-002-005-S72R,correct Typo & Revise Statement Describing Approach to Evaluation)
• ML20080S247  + (Forwards Rev 1 to Audit Finding Rept MSA-83-19-11F. Verification of Separate Temp Sensor & Switch Required. Drawings Should Be Revised to Reflect Location of Temp Switch & Sensor)
• ML20127L655  + (Forwards Rev 1 to Aug 1983 Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21))
• ML17289A813  + (Forwards Rev 1 to Augmented Insp Team Charter to Support AEOD Studies of CR Human Factors & Decision Making Process During Reactor Event,After Reviewing 920815 Power Oscillation Event)
• ML20237L124  + (Forwards Rev 1 to Author 870814 Amend Request for Licenses DPR-42 & DPR-60,correcting Typos on Title Sheets for Exhibits a & B)
• ML20059M183  + (Forwards Rev 1 to Auxiliary Feedwater Initiation Event Analysis,Per NRC .Comparisons of Assumptions Used in Design Basis Analysis & Best Estimate Analysis of AFW Flow Needs,Also Encl)
• ML20024C600  + (Forwards Rev 1 to BAW-10075A Multinode Analysis of Small Breaks for B&W 177-FA Nuclear Plants W/Raised Loop Arrangement & Internal Vent Valves)
• ML20212M994  + (Forwards Rev 1 to BAW-10149A, Power Train Hybrid Computer Simulation of B&W Nuclear Power Plant. Responses to NRC Questions During Review Process Included in Rept)
• ML20057A185  + (Forwards Rev 1 to BAW-10156-A, Lynxt Core Transient Thermal-Hydraulic Program. Rept Includes Acceptance Ltr & Accompanying SER & NRC Ltr Re Topical Rept BAW-10156,Rev 1)
• ML20062C615  + (Forwards Rev 1 to BAW-10173P, Mark-BW Reload Safety Analysis for Catawba & McGuire Units. Encl Withheld)
• ML20065M724  + (Forwards Rev 1 to BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire Units)
• ML20116N015  + (Forwards Rev 1 to BAW-10174A, Mark-BW Reload LOCA Analysis for McGuire & Catawba)
• ML20080L741  + (Forwards Rev 1 to BAW-1762, Auxiliary Feedwater Sys Reliability Study for WPPSS Unit 1, in Response to NUREG-0737,Item II.E.1.1)
• ML20197H803  + (Forwards Rev 1 to BAW-1808, B&W J-R Test Procedure for Compact Fracture Toughness Specimen)
• ML20138R202  + (Forwards Rev 1 to BAW-1847, Leak-Before-Break Evaluation of Margins Against Full Break for RCS Primary Piping of B&W-Designed Nuclear Steam Sys.)
• ML20138R200  + (Forwards Rev 1 to BAW-1847, Leak-Before-Break Evaluation of Margins Against Full Break for RCS Primary Piping of B&W-Designed Nuclear Steam Sys)

• ML20057B523  + (Forwards Rev 1 to BAW-2108, Fluence Tracking Sys)

• ML15245A253  + (Forwards Rev 1 to BAW-2128, Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit 3)
• ML20115G661  + (Forwards Rev 1 to BAW-2168, Response to GL 92-01 for VEPCO North Anna Unit 1 & North Anna Unit 2. Changes in Revised Rept Detailed in Util)
• ML20045H141  + (Forwards Rev 1 to BAW-2178, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level C & D Svc Loads)
• ML17353A432  + (Forwards Rev 1 to BAW-2245, Initial RT of Linde 80 Welds Based on Fracture Toughness in Transition Range. Rev Corrects Several Typographical Errors & Replaces BAW-2245, Marked Obsolete)
• ML17353A433  + (Forwards Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. Rev Corrects Several Typographical Errors & Replaces BAW-2245, Marked Obsolete)
• ML20217D451  + (Forwards Rev 1 to BAW-2295A, Justification for Extension of Allowed Outage Time for Low Pressure Injection & Reactor Building Spray Systems, Providing Deterministic & Risk Assessment to Support AOT)
• ML20205J117  + (Forwards Rev 1 to BAW-2325, Response to RAI Re RPV Integrity, Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rev Includes Corrected Values in Calculations)
• ML20079G918  + (Forwards Rev 1 to BCL-382-85-1, Exam,Testing & Evaluation of Specimens from 210-Degree Irradiated Pressure Vessel Surveillance Capsule for Oyster Creek... Per SEP Topics III-2 Re Wind & Tornado Loadings & III-7.B Re Design Codes)
• ML18038B264  + (Forwards Rev 1 to Bfnp Unit 2,Cycle 8 Colr. Rev Increases APRM Flow Biased Rod Block/Upscale Alarm Setpoint)
• ML18038B265  + (Forwards Rev 1 to Bfnp Unit 2,Cycle 8 Colr. Rev Increases APRM Flow Biased Rod Block/Upscale Alarm Setpoint)
• ML20236P054  + (Forwards Rev 1 to Big Rock Point IGSCC Insp Program. Addl Review Determined That Seven Welds Not Previously Listed Partially Susceptible to Igscc.All Addl Welds Branch Connected to Stainless Steel Pipe)
• ML20138H286  + (Forwards Rev 1 to Bmo 97-03, Tech Specs for Offsite Power & Bmo 97-18, Compliance W/Sbo Regulation)
• ML20138H292  + (Forwards Rev 1 to Bmo 97-03, Tech Specs for Offsite Power & Bmo 97-18, Compliance W/Sbo Regulation.)
• ML20236Y535  + (Forwards Rev 1 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan. Outage Scheduled to Begin 980905)
• ML20091L018  + (Forwards Rev 1 to Braidwood Unit 2 Cycle 5 Operating Limits Rept)
• BSEP-95-0382, Forwards Rev 1 to Brunswick Unit 2,Cycle 11,COLR  + (Forwards Rev 1 to Brunswick Unit 2,Cycle 11,COLR)
• ML20246N733  + (Forwards Rev 1 to Brunswick Unit 2,Cycle 8 Core Operating Limits Rept & Brunswick Unit 1,Cycle 7 Core Operating Limits Rept for Mar 1989.Repts Provided to Coincide W/ Implementation of Amends 131 & 161 to Licenses)
• ML20058H302  + (Forwards Rev 1 to Brunswick Unit 2,Cycle 9 Core Operating Limits Rept. Rev Issued to Implement Change to Rod Block Monitor Sys Setpoints)
• ML20091L083  + (Forwards Rev 1 to Byron Unit 2 Cycle 6 Operating Limits Rept)
• ML20069F266  + (Forwards Rev 1 to CCNPP COLR for Unit 1,Cycle 12 & Rev 1 to CCNPP COLR for Unit 2,Cycle 10, Per TS 6.9.1.9)
• ML18026B216  + (Forwards Rev 1 to CEB-83-34, Browns Ferry Nuclear Plant Torus Integrity Long-Term Program Plant-Unique Analysis Rept)
• ML18026B217  + (Forwards Rev 1 to CEB-83-34, Browns Ferry Nuclear Plant Torus Integrity Long-Term Program Plant-Unique Analysis Rept.)
• ML20133D349  + (Forwards Rev 1 to CEC-20-013, Evaluation & Disposition of Flaws at Quad-Cities Nuclear Power Plant Unit 2 & Summary of Spring 1985 Inservice Insp Results,Per NRC 850516 Request for Addl Info for Completion of SER)
• ML20133D351  + (Forwards Rev 1 to CEC-20-013, Evaluation & Disposition of Flaws at Quad-Cities Nuclear Power Plant Unit 2 & Summary of Spring 1985 Inservice Insp Results,Per NRC 850516 Request for Addl Info for Completion of SER)
• ML20214V804  + (Forwards Rev 1 to CEN-268, Justification of Trip Two/Leave Two Reactor Coolant Pump ... & Proprietary & Nonproprietary Rev 1 to Suppls 1-P & 1-NP,respectively,to Response to Addl Info.... Proprietary Rept Withheld (Ref 10CFR2.790))