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List of results

• ML19305B295  + (Forwards Response to NRC Request for Info Re Welding Process & Heat Treatment in Cladding Vessel Nozzles.Base Matl of All Nozzles Is ASTM A-508,Class 2.Preheat Temp Is 250 F Min & post-heat Temp Is 400 F)
• ML20207C819  + (Forwards Response to NRC Request for Info Re Nuclear Svc Cooling Water (NSCW) Sys Performance Made at 861215 Meeting. Encl Includes NSCW Water Hammer Evaluation)
• ML19323H716  + (Forwards Response to NRC Request for Info Re Facility Mar 1980 Eddy Current Insp.Info Provided Re Number of Eddy Current Indications Recorded in Steam Generator a & B Hot Legs & Distribution by Size & Height Above Tubesheet)
• ML20246C977  + (Forwards Response to NRC Request for Info Re Condition of Drywell Paint,Per Insp Rept 50-271/89-80)
• ML19253C895  + (Forwards Response to NRC Request for Info Re Loss of Offsite Power.Outline of Pertinent Events Encl)
• ML20127A026  + (Forwards Response to NRC Request for Info Re Category C-2 Steam Generator Tube Insps Per NUREG-0844,completing Response to Generic Ltr 85-02)
• BSEP-94-0355, Forwards Response to NRC Request for Info During Telcons W/ Util Re 930125 CRD Scram Accumulator Lar.Ref Noted in 930125 Basis for Amend Request (NEDE-14584, Assurance of Acceptable Scram Through CRD Speed Analysis) Also Encl  + (Forwards Response to NRC Request for Info During Telcons W/ Util Re 930125 CRD Scram Accumulator Lar.Ref Noted in 930125 Basis for Amend Request (NEDE-14584, Assurance of Acceptable Scram Through CRD Speed Analysis) Also Encl)
• ML20126D799  + (Forwards Response to NRC Request for Info on Station Blackout/Electrical Safeguards Upgrade Project,Proposing Addition of Two Safeguards EDGs to Upgrade Safeguards Electrical Distribution Sys)
• ML17309A613  + (Forwards Response to NRC Request for Info Re Adequacy & Availability of Design Bases Info,Per 10CFR50.54(f))
• ML20115B010  + (Forwards Response to NRC Request for Info Re short-term Items Discussed in Util Re Masonry Block Walls, Including Air Tubing Supports,Rwcu Supports,Fuel Oil Small Bore Piping Supports & MSL Radiation Monitor Supports)
• ML13317A620  + (Forwards Response to NRC Request for Info Re Reload Safety Evaluation,San Onofre Nuclear Generating Station,Unit 1, Cycle 8,Revision 2. Transients & Accidents Are Not Adversely Affected by Reduced Reactor Coolant Average Temp)
• B10104, Forwards Response to NRC Request for Info Re SEP Topic VI-5, Combustible Gas Control.Response Re Hydrogen Monitoring Reflects Currently Available.Sys & Procedures & Will Be Improved Per TMI Lessons Learned Requirements  + (Forwards Response to NRC Request for Info Re SEP Topic VI-5, Combustible Gas Control.Response Re Hydrogen Monitoring Reflects Currently Available.Sys & Procedures & Will Be Improved Per TMI Lessons Learned Requirements)
• ML20127D021  + (Forwards Response to NRC Request for Proposal RS-IRM-92-172 Entitled, Archival Record Storage & Related Svcs)
• ML20137R411  + (Forwards Response to NRC Request for Stay & Motion for Reconsideration in Matter of Rl Tetrick)
• ML20137R416  + (Forwards Response to NRC Request for Stay & Motion for Reconsideration in Matter of Rl Tetrick)
• ML20062M456  + (Forwards Response to NRC Request for Supplemental Info Re Elevation Dependent Peaking Factor Vs Core Height Graphs for Unit 1 Cycle 4 & Unit 2 Cycle 1,in Support of Requested Fq Tech Spec Change.Proprietary Info Withheld)
• ML20032A079  + (Forwards Response to NRC Request for Unresolved Safety Issue A-44 Effort to Determine Reliability of Onsite Standby Diesel Generators.Info Summarizes Operations Data & Down Time for Diesel Generator from 1976-80)
• ML20079G176  + (Forwards Response to NRC Request for settlement-related Analyses for Diesel Generator Bldg, Structural Stresses Induced by Differential Settlement of Diesel Generator Bldg)
• ML18102A176  + (Forwards Response to NRC Request to Clarify,In marked-up TS Pages,Submitted Change to Containment Leak Rate Testing Utilizing Option B as Applied to Type a Testing)
• ML18102A177  + (Forwards Response to NRC Request to Clarify,In marked-up TS Pages,Submitted Change to Containment Leak Rate Testing Utilizing Option B as Applied to Type a Testing)
• AECM-85-0410, Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks  + (Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks)
• DCL-84-067, Forwards Response to NRC Request to Identify & Provide Basis for Acceptance of Welded ASTM A-325 Bolting in Pipe Support Design,Per 840119 Site Visit  + (Forwards Response to NRC Request to Identify & Provide Basis for Acceptance of Welded ASTM A-325 Bolting in Pipe Support Design,Per 840119 Site Visit)
• ML20134C995  + (Forwards Response to NRC Request to Identify Addl Justification for Keeping Data Submitted as Proprietary.Encl Withheld)
• HL-5282, Forwards Response to NRC Request to Provide Info Re Adequacy & Availability of Design Bases Info for Ei Hatch Nuclear Plant  + (Forwards Response to NRC Request to Provide Info Re Adequacy & Availability of Design Bases Info for Ei Hatch Nuclear Plant)
• ML19331B918  + (Forwards Response to NRC Request,Made During 800801 Meeting, Re Independent Safety Engineering Group)

• L-81-410, Forwards Response to NRC Requesting Addl Info Re Core Thermal Hydraulics  + (Forwards Response to NRC Requesting Addl Info Re Core Thermal Hydraulics)

• ML19260B247  + (Forwards Response to NRC Requesting Addl Info Re Small Break LOCAs)
• TXX-6677, Forwards Response to NRC Requesting Addl Info on Groundwater Withdrawal Rates from 1979 to Present,Per Util 870429 Request for Extension of CP CPPR-127.Info Suppls Table 5.1 of Plant Fes (NUREG-0775)  + (Forwards Response to NRC Requesting Addl Info on Groundwater Withdrawal Rates from 1979 to Present,Per Util 870429 Request for Extension of CP CPPR-127.Info Suppls Table 5.1 of Plant Fes (NUREG-0775))
• ML18081A345  + (Forwards Response to NRC Requesting Addl Info Re IE Bulletin 79-07.W/o Encl)
• ML17326A285  + (Forwards Response to NRC Requesting Addl Info Re IE Bulletins 79-06A & 79-06A,Revision 1.Discusses Surveillance Procedure for Locked safety-related Valves & Procedures for Dealing W/Hydrogen Gas within Containment)
• ML18081A358  + (Forwards Response to NRC Requesting Addl Info Re Lessons Learned & Emergency Preparedness Resulting from Review of TMI-2 Accident)
• L-81-243, Forwards Response to NRC Requesting Addl Info Re Adequacy of Station Electric Distribution Sys Voltages. Calculated Voltages Were All Less than Measured Voltages  + (Forwards Response to NRC Requesting Addl Info Re Adequacy of Station Electric Distribution Sys Voltages. Calculated Voltages Were All Less than Measured Voltages)
• ML19296D368  + (Forwards Response to NRC Requesting Addl Info Re Modified Spent Fuel Pin Storage.Conclusion Re Personnel Exposure Not Adversely Affected by Varying Radiation Levels in Spent Fuel Pool)
• ML20071M606  + (Forwards Response to NRC Requesting Addl Info Re Preliminary Draft Ser,Section 4.2, Fuel Sys Design. Cladding Collapse Not Predicted Until EFPH Exceeds Anticipated Lifetime of Fuel)
• L-81-181, Forwards Response to NRC Requesting Addl Info for Review of Environ Rept.Includes Sea Turtle Data & Recreational Usage Info  + (Forwards Response to NRC Requesting Addl Info for Review of Environ Rept.Includes Sea Turtle Data & Recreational Usage Info)
• ML17250A320  + (Forwards Response to NRC Requesting Addl Info Re SEP Design Basis Events.Topics Cover Steady State & Instrument Errors,Single Failure Analysis,Steam Line Break Analyses & Primary Pump Rotor Seizure)
• ML17261A209  + (Forwards Response to NRC Requesting Addl Info Re Auxiliary Feedwater Sys Flow Requirements.Response to Request for Info Re Evaluation of Auxiliary Feedwater Sys Requirements Was Provided 791128)
• ML19210D548  + (Forwards Response to NRC Requesting Addl Info Re Loss of Offsite Power Events.Five LERs Indicating Loss of Offsite Power Were Actually Support Sys Failures.Affidavit Encl)
• ML20066A982  + (Forwards Response to NRC Requesting Addl Info on NUREG-0737,Item II.D.1, Testing of Relief & Safety Valves)
• ML19305C424  + (Forwards Response to NRC Requesting Addl Info Re Core Thermohydraulic Effects)
• ML20127J354  + (Forwards Response to NRC Requesting Addl Info on Weaknesses Noted in Insp Repts 50-348/91-201 & 50-364/91-201 Re Mov,Per GL 89-10.Insp Repts 50-348/92-30 & 50-364/92-30, Closed Five of Seven Items & RAI)
• ML18081B023  + (Forwards Response to NRC Requesting Addl Info Re Accountability of Auxiliary Feedwater Flow in Containment Overpressurization Analysis.Auxiliary Feedwater Sys Assumed to Be Actuated at Time of Break & Pumping at Max Capacity)
• ML20101C429  + (Forwards Response to NRC Requesting Addl Info Re SG Alternate Plugging Criteria)
• ST-HL-AE-5779, Forwards Response to NRC Requesting Addl Info on Thimble Guide Tube Nut Replacement  + (Forwards Response to NRC Requesting Addl Info on Thimble Guide Tube Nut Replacement)
• ML19210A819  + (Forwards Response to NRC Requesting Addl Info Concerning Tech Spec Change 9 Re Revised Power Versus Rod Withdrawal Limit Curves)
• L-82-203, Forwards Response to NRC Requesting Addl Info Re Control of Unit Through Total Loss of Ac Power  + (Forwards Response to NRC Requesting Addl Info Re Control of Unit Through Total Loss of Ac Power)
• ML19309H896  + (Forwards Response to NRC Requesting Addl Info Re Requirements of 10CFR50,App J)
• TXX-6859, Forwards Response to NRC Requesting Addl Info Re Util Results Rept for Rev 3 to Issue Specific Action Plan Ii.C, Maint of Air Gab Between Concrete Structures  + (Forwards Response to NRC Requesting Addl Info Re Util Results Rept for Rev 3 to Issue Specific Action Plan Ii.C, Maint of Air Gab Between Concrete Structures)
• ML19269C825  + (Forwards Response to NRC Requesting Addl Info Re Core Spray Distribution Program.W/Encl Chart Showing Current Planned Schedule for Design of BWR Core Spray Sys)
• ML20095D378  + (Forwards Response to NRC Requesting Addl Info Re Ampacity Derating Evaluations for Thermo-Lag Fire Barriers Installed at Facility)
• L-82-413, Forwards Response to NRC Requesting Addl Info Re Environ Qualification of TMI Action Items Contained in NUREG-0737  + (Forwards Response to NRC Requesting Addl Info Re Environ Qualification of TMI Action Items Contained in NUREG-0737)