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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

Americium +, Cobalt +, Cesium +, Nitrogen +, Oxygen +, Hydrogen +, Lead +  and Antimony +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.49 +  and 10 CFR 50.51 +

S.1(r) +  and S.2(u) +

00245  +  and 05000245  +

49 FR 45112 +  and 37 FR 25187 +

Office of Nuclear Reactor Regulation +  and James Shea +

ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +, ML20210B004 +...

0.0174 d (0.417 hours, 0.00248 weeks, 5.7075e-4 months)  +, 0.0081 d (0.194 hours, 0.00116 weeks, 2.6635e-4 months)  +, 0.00862 d (0.207 hours, 0.00123 weeks, 2.834725e-4 months)  +, 0.0197 d (0.472 hours, 0.00281 weeks, 6.4685e-4 months)  +, 0.00943 d (0.226 hours, 0.00135 weeks, 3.101075e-4 months)  +, 0.00961 d (0.231 hours, 0.00137 weeks, 3.15815e-4 months)  +, 0.00976 d (0.234 hours, 0.00139 weeks, 3.207615e-4 months)  +, 0.00978 d (0.235 hours, 0.0014 weeks, 3.215225e-4 months)  +, 0.0106 d (0.254 hours, 0.00151 weeks, 3.481575e-4 months)  +, 0.0208 d (0.5 hours, 0.00298 weeks, 6.849e-4 months)  +, 0.0119 d (0.286 hours, 0.0017 weeks, 3.91915e-4 months)  +, 0.012 d (0.289 hours, 0.00172 weeks, 3.9572e-4 months)  +, 0.0121 d (0.29 hours, 0.00173 weeks, 3.976225e-4 months)  +, 0.0129 d (0.309 hours, 0.00184 weeks, 4.23116e-4 months)  +, 0.0132 d (0.317 hours, 0.00188 weeks, 4.3377e-4 months)  +, 0.0141 d (0.338 hours, 0.00201 weeks, 4.62688e-4 months)  +, 0.0141 d (0.339 hours, 0.00202 weeks, 4.6421e-4 months)  +, 0.0142 d (0.341 hours, 0.00203 weeks, 4.668735e-4 months)  +, 0.0145 d (0.349 hours, 0.00208 weeks, 4.775275e-4 months)  +, 0.0119 d (0.286 hours, 0.0017 weeks, 3.91154e-4 months)  +, 0.0145 d (0.347 hours, 0.00207 weeks, 4.75625e-4 months)  +, 0.015 d (0.361 hours, 0.00215 weeks, 4.9465e-4 months)  +, 0.0151 d (0.363 hours, 0.00216 weeks, 4.973135e-4 months)  +, 0.0152 d (0.366 hours, 0.00218 weeks, 5.011185e-4 months)  +, 0.0154 d (0.371 hours, 0.00221 weeks, 5.07587e-4 months)  +, 0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +, 0.0197 d (0.474 hours, 0.00282 weeks, 6.487525e-4 months)  +, 0.0105 d (0.253 hours, 0.0015 weeks, 3.46255e-4 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 0.00365 d (0.0875 hours, 5.208333e-4 weeks, 1.198575e-4 months)  +...

ML20141E752 +, ML20138K097 +, IR 05000245/1985011 +, ML20126K007 +, A05577, Forwards Response to 860211 Request for Addl Info on SPDS Beyond Info in .Device Used to Electrically Isolate Described.Verifies Max Credible Faults,Pass/Fail Acceptance Criteria & Environ Qualification Compliance +, A05481, Forwards Addl Info Re Main Steam Line Support Failures, Including Drawings & Figures of Main Steam Lines,Associated Supports & Monitoring Instrumentation Recently Installed. Failure Believed to Be Result of Operating Transient +, B11931, Advises That Mods to Valve Operator & Limit Switch Logic of Return Line Valve MOV 1-IC-3 to Address Dominant Predicted Causes of Isolation Condenser Failure,Described in Probablistic Safety Study,Completed +, B11936, Forwards Status Rept Re Implementation of Seismic Interaction Program.Tasks Include:Anchorage Adequacy for Nonseismic Equipment in Seismic Category I Bldgs & Structural Integrity of Piping,Per Sser 4 (NUREG-1031) +, B11923, Informs of Intention to Propose Amend to License DPR-21 on or Before 860701,authorizing Rev to Pressure Temp Operating Limit Curves.Amend Will Be Based on Util Evaluation of Curves Prepared by GE +, B11839, Advises of Intent to Conduct Type a Tests During Mar 1988, Jan 1991 & Mar 1995,per 10CFR50,App J,Section III.A.6(a). Recent Type a Test Exceeds Max Leakage Rate Specified in Tech Specs.Schedule Ensures Primary Containment Integrity +, B11918, Provides Informational Update on Findings of Recent Insp. Probability of Turbine Damage & Subsequent Missile Generation,Which Could Lead to Damage to Critical Control Components,Remains Acceptably Low +, B12006, Advises That 850830 Calibr Block Review Request Being Evaluated Via NRC Review of Inservice Insp & Testing Program,Per Insp 50-336/85-08.Action on Request Considered Complete +, A04826, Submits Supplementary Response to Generic Ltr 83-28,Item 4.5.3,per 850417 Request.Response Based on C-E Owners Group Evaluation of Recommended Reactor Trip Sys Test Intervals for C-E Plants,Published in CE NPSD-277, Reactor.. +, B11725, Forwards Rev to FSAR Clarifying Definition of Single Failure Criterion.Rev Clarifies Requirements for Postulating Single Active Failures When Evaluating Interactions Occurring w/dual-purpose Safe Shutdown Sys +, B11713, Forwards Results of Revised Instrument Uncertainty Analysis in Response to Question 492.7 Re RCS Flow Measurement Capability,Per 850910 Telcon.Ser Open Item 8 Considered Closed +, B11620, Forwards Updated Sys Component Evaluation Worksheets for safety-related Electrical Equipment Located in Harsh Environ & Rev 1 to Environ Qualification Rept,Per 850702 Meeting W/Nrc,S&W & Westinghouse +, A04615, Advises of Initiation of Design Mods to Provide Redundant Parallel Control Power Fusing Circuits for Essential Hot Standby Equipment,In Response to Generic Ltr 81-12 Re Alternate Shutdown Design,Per 850326 Meeting +, B11540, Application for Amend to Licenses DPR-21 & DPR-65, Incorporating Encl Proposed Rev 3 to Suitability,Training & Qualification Plan.Encl Withheld (Ref 10CFR2.790 & 73.21). Fee Paid +, 05000423/LER-1986-001, :on 860116,during Hot Standby Mode,Reactor Tripped Due to Safety Injection Signal from Rate Compensated Steam Line Low Pressure of Steam Generator A.Caused by Quick Opening of Atmospheric Steam Dump Valve +, 05000245/LER-1985-031, :on 851215,condensate Booster Pump a Failed to Automatically Start During Loss of Normal Power/Max Credible Accident Testing.Caused by Relay in Autoclose Circuit for Booster Pump +, 05000423/LER-1985-001-01, :on 851209,during Cold Shutdown,Small Perforation Discovered in Fuel Oil Header Pressure Return Line Tubing of Emergency Diesel Generator A.Caused by Cyclic Vibration & Chafing Against Skid Frame +  and 05000245/LER-1981-042, Forwards LER 81-042/03L-0.Detailed Event Analysis Encl +

NUREG-0824, Safety Evaluation Concluding Util 831228,840111 & 0202 Responses to NUREG-0824,Section 4.12 Re Design Codes,Design Criteria & Loading Combinations Complete Except for Listed Issues Requiring Resolution +, NUREG-1143, Forwards full-term OL DPR-21,authorizing Operation at steady-state Reactor Core Power Levels Up to 2,011 Mwt & Notice of Issuance,Per 720901 Application.Safety Evaluation Supporting full-term OL Issued as NUREG-1143 +  and NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +

AM +  and MP-1 +

Connecticut +, Maryland +, Washington +, New Jersey +  and New York +

Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Main Turbine +, Shutdown Cooling +, Main Steam Line +, Control Rod +  and Main Steam +

Safe Shutdown +, Fire Barrier +, Weld Overlay +, Probabilistic Risk Assessment +, Reserve Station Service Transformer +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Exemption Request +, Turbine Missile +  and Fire Protection Program +