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List of results

• ML20084H100  + (Responds to NRC Re SALP Repts 50-321/84-01, 50-366/84-01,50-424/84-01 & 50-425/84-01.Occurrences Contributing to Low Ratings in Maint,Operations & QA Areas Clarified)
• ML17228B456  + (Responds to NRC Re SALP Repts 50-335/95-99 & 50-389/95-99 for Period from 940102-960106)
• AECM-85-0267, Responds to NRC Re SALP Repts 50-416/85-12 & 50-417/85-03 for Oct 1983 - Apr 1985.Corrective Actions: Procedure 10-S-01-05 Revised to Resolve NRC Concerns & Rev 10 to Emergency Plan Expected by Sept 1985  + (Responds to NRC Re SALP Repts 50-416/85-12 & 50-417/85-03 for Oct 1983 - Apr 1985.Corrective Actions: Procedure 10-S-01-05 Revised to Resolve NRC Concerns & Rev 10 to Emergency Plan Expected by Sept 1985)
• ML20003A904  + (Responds to NRC Re SEP Lead Topic Approach Proposed by SEP Owners Group.Licensee May Not Have Adequate Time to Comment on Safety Evaluation.Written Notification Will Be Provided to Request Addl Time)
• ML20005C118  + (Responds to NRC Re SEP Topic III-5.A, Effects of Pipe Break on Structures,Sys & Components Inside Containment. Addl Evaluations Will Be Completed by 811230, Including Dynamic Effects of Pipe Whip)
• ML19256G194  + (Responds to NRC Re SEP Topic III-8.C, Irradiation Damage,Use of Sensitized Steel & Fatigue Resistance. Portion of Evaluation,Re Brazes on Control Rod Spider,Requires Revision to Maintain Factual Accuracy)
• ML17193B503  + (Responds to NRC Re SEP Topic VI-4 on Containment Isolation Sys.Sys Lineups Are Performed According to Valve Checklist Prior to Operation Following Outage.Aperture Card & Oversize Drawing Encl.Aperture Cards Are in PDR)
• ML17258A750  + (Responds to NRC Re SEP Topic VII-1.a, Reactor Protection Sys Isolation. Agrees W/Assessment Info. Topic Designated Complete)
• ML17257A461  + (Responds to NRC Re SEP Topic VIII-3.A, Station Battery Capacity Test Requirements. Tech Spec 4.6.2 Specifies Battery Svc Test to Be Conducted at 12-month Intervals.Copy of Eg&G Battery Capacity Tests Requested)
• A01159, Responds to NRC Re SEP Topics III-10.A,V-II.A, VI-4,VI-7.C.1 & VIII-3.B.Concurs W/Nrc Conclusions,Except for Topic VIII.3.B.Control Room Contains Battery Fuse Open Alarm in Addition to Alarms Noted in NRC Assessment  + (Responds to NRC Re SEP Topics III-10.A,V-II.A, VI-4,VI-7.C.1 & VIII-3.B.Concurs W/Nrc Conclusions,Except for Topic VIII.3.B.Control Room Contains Battery Fuse Open Alarm in Addition to Alarms Noted in NRC Assessment)
• ML20215L415  + (Responds to NRC Re SER on ATWS Mitigating Sys Actuation Circuitry Generic Design Package.Final Design Description Will Be Submitted by 870123)
• ML20086A081  + (Responds to NRC Re SER on Masonry Wall Design Evaluation Performed Per IE Bulletin 80-11.Five Walls Using Joint Reinforcement Will Be Modified by Adding Structural Steel Reinforcement Sections)
• ML20005B610  + (Responds to NRC Re Safety Concerns Associated W/Pipe Breaks in BWR Scram Sys.Consequences of NUREG-0785 Scenario Are Not Applicable.Containment Temp Sensors Are Located in Area of SDV Piping Headers)
• ML20076M368  + (Responds to NRC Re Safety Evaluation of Seven Alternatives Proposed by BWR Owners Group to Modify Present Automatic Depressurization Sys Logic Per NUREG-0737,Item II.K.3.18.Mods Will Be Implemented During Refueling Outage)
• ML20244A675  + (Responds to NRC Re Safety Significant Matters Found in SSOMI During Wks of 890213 & 27)
• ML20214K008  + (Responds to NRC Re Schedule for Implementation of 10CFR50.48 Fire Protection Mods.Mods Completed W/Exception of Four Listed Items.Items 1 & 2 Will Be Completed by 1988 Refueling Outage.Items 3 & 4 Will Be Completed by 871231)
• ML19262A412  + (Responds to NRC Re Schedule for Implementation of TMI-2 Operational QA Program at TMI-1.Schedule to Be Issued No Later than 30 Days After TMI-2 Program Is Implemented at Unit 2)
• ML20054F199  + (Responds to NRC Re Schedule for Installation of Public Notification Sys.Final Design & Installation Schedule Have Not Been Finalized.Info Will Be Submitted by 820730)
• ML20090H402  + (Responds to NRC Re Schedule for Meeting Emergency Response Capability Requirements.Const Schedule Will Permit Fuel Loading by 840801.Full Scale Emergency Preparedness Exercise Rescheduled to 840725)
• 1CAN028314, Responds to NRC Re Schedule for Response Concerning Electrical Equipment.Completed Response Will Not Be Provided within 30 Days.Justification for Interim Operation Encl  + (Responds to NRC Re Schedule for Response Concerning Electrical Equipment.Completed Response Will Not Be Provided within 30 Days.Justification for Interim Operation Encl)
• ML20112F663  + (Responds to NRC Re Schedule for Submitting Supplemental Summary Rept for Detailed Control Room Design Review & Status of Special Studies.Addl Info Will Be Discussed During Preimplementation Audit in Late Apr 1985)
• ML19210E257  + (Responds to NRC Re Schedules for Completing Licensing Conditions.Tech Specs Revision Submitted 791127. Description of long-term Mods & Tech Specs for Surveillance Requirements Due 90 Days Before Refueling Outage)
• A01594, Responds to NRC Re Scram Discharge Evaluation Per BWR Owners Group Criteria Re IE Bulletin 80-17.Required long-term Mod Scheduled for Next Refueling Outage.Further Evaluation of Common Cause Failures Necessary  + (Responds to NRC Re Scram Discharge Evaluation Per BWR Owners Group Criteria Re IE Bulletin 80-17.Required long-term Mod Scheduled for Next Refueling Outage.Further Evaluation of Common Cause Failures Necessary)
• ML19338G084  + (Responds to NRC Re Scram Sys.Study of long-term Sys Reliability Initiated.Results of Evaluation & Proposed Mods Will Be Submitted by 801215)
• ML19319C023  + (Responds to NRC Re Secondary Sys Fluid Flow Instability in Pwrs.Requested Info Under Review for Applicability to Facility & Associated Nuclear Steam Supply Sys.Expected Response Date 750707)

• SNRC-2098, Responds to NRC Re Security Concern at Snps Unit 1  + (Responds to NRC Re Security Concern at Snps Unit 1)

• ML20044E712  + (Responds to NRC Re Security Program Violation Noted in Insp Rept 50-247/93-08.Encl Withheld,Per 10CFR73.21)
• ML19206A861  + (Responds to NRC Re Security.Identifies Problem Re Access from Plant Under Const to Operating Plant.Recommends Same Security Regulations Should Apply to Both)
• ML19296B699  + (Responds to NRC Re Seismic & Environ Qualification of Class IE Electrical Equipment.Util Has Determined That Some Asco Valves Are Not Fully Qualified. Lists Valves Which Have Been Replaced W/Qualified Valves)
• ML13330B352  + (Responds to NRC Re Seismic Analyses for Operating Basis Earthquake.Sphere Encl Bldg & Diesel Generator Bldg Not Part of SEP Seismic Reviews.Original Seismic Design Analyses Continue to Be Seismic Design Bases for Structures)
• ML20009G806  + (Responds to NRC Re Selection of Appropriate Seismic Design Basis for Facility.Probabilistic Risk Analysis of Plant Upgraded to Composite Spectrum Shows Risk Is Lower than Typical WASH-1400 Plant.Spectrum Is Adequate)
• ML17173B004  + (Responds to NRC Re Sep.Forwards Addl Info Re Topic VIII-3.B,onsite Dc Battery Sys)
• ML19256G058  + (Responds to NRC Re Separation of Electrical Equipment & Sys.Util Commits to Complying W/Requirements)
• ML20147E117  + (Responds to NRC Re Sequoyah Design Calculation Review.Actions Required to Respond to Insp Findings Identified & Being Implemented)
• A10316, Responds to NRC Re Settlement Agreements Executed Between Util & Two Named Individuals.Util Considers Agreements Confidential & Requests That Agreements Be Withheld (Ref 10CFR2.790(a)(4) & (6))  + (Responds to NRC Re Settlement Agreements Executed Between Util & Two Named Individuals.Util Considers Agreements Confidential & Requests That Agreements Be Withheld (Ref 10CFR2.790(a)(4) & (6)))
• ML19305B341  + (Responds to NRC Re Seven Losses of Offsite Power Events.One Event Caused by Line Which Supplies Auxiliary Power Tripping When Line Relay Panel Was Bumped by Station Personnel.Second Event Caused by Transformer Trip)
• ML20151E898  + (Responds to NRC Re Severity Level IV Violations Noted in Insp Repts 50-413/88-18 & 50-414/88-18.Corrective Actions:New Stopwatches That Can Be Calibrated Bought & Put in Svc & Calibr Schedule Established W/Mfg)
• ML20207G548  + (Responds to NRC Re Severity Level IV Violation Noted in Insp Repts 50-413/88-22 & 50-414/88-22 Concerning Misinterpretation of Tech Specs)
• ML18139A761  + (Responds to NRC Re Shift Staffing Requirements. Shift Staffing Determined in Compliance W/Criteria)
• ML20066K704  + (Responds to NRC Re Shift Staffing Requirements. Staffing Problems Due to Shortage of Licensed Operators. Three Station Operators Due to Take Exam in Jan 1983)
• ML19338F055  + (Responds to NRC Re Side Effects of Iodine.Effects Have Been Grossly Exaggerated.Consideration Should Be Given to Panic Which Might Be Engendered in City or Urban Area Where Neither Shelter Nor Evacuation Is Possible)
• ML19350D769  + (Responds to NRC Re Significant Findings Noted in IE Health Physics Appraisal Repts 50-348/80-41 & 50-364/80-52.Corrective Actions:Qualification Requirements Established for Documenting Health Physics Knowledge)
• ML19331B506  + (Responds to NRC Re Significant Regulatory Developments & Forwards Addl Info Re TMI-1 Restart Proceedings)
• ML19325C975  + (Responds to NRC Re Significant Weaknesses Noted in Safety Insp Repts 50-295/89-13 & 50-304/89-13 on 890318- 0508.Corrective Actions:Procedures P/M016-2N & P/M016-6N Re Limitorque Operators Size SMB-000 Changed)
• ML20031D757  + (Responds to NRC Re Simulator Exams.No Exams Scheduled for Remainder of 1981.Written Exams Will Be Initially Administered During Wk of 820412 & Simulator Portion During Wk of 820426)
• ML20041D407  + (Responds to NRC Re Single Failure Assumptions in ECCS Analyses.Estimate Analyses Show Actual Peak Clad Temps Will Not Be Affected.Calculations Are Conservative to Best Estimate Calculations by Several Hundreds of Degrees)
• ML19210E086  + (Responds to NRC Re Small Break LOCA Case Causing RCS to Repressurize to Power Operated Relief Valve Setpoint. Addresses Effect of non-condensible Gasses on Small Break LOCA Analysis)
• ML19257D052  + (Responds to NRC Re Small Break LOCA Operator Guidelines Mod.Auxiliary Feedwater Flow Criteria Review Indicated That Revised Criteria Do Not Conflict W/Other Operational Restrictions in Force)
• ML19273C110  + (Responds to NRC Re Small Break LOCA analysis.C-E Rept, Review of Small Break Transients in C-E Nuclear Steam Supply Sys, CEN-114-P,constitutes Response to Request for Addl Info)
• ML20198D830  + (Responds to NRC Re Soil Sample Isotopic U Analysis & Request for Action & Schedule for Completion of Soil Decontamination Efforts.Addl Soil Removal Being Conducted.Details of Effort Encl.W/O Schedule)
• ML19331D215  + (Responds to NRC Re Special Inquiry Group Concerns on TMI Accident.Special Mental Health Program for Citizens in Community Would Be Justified Only If Existing Resources Are Insufficient to Meet Such Needs)