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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

Boron +, Iodine +  and Nitrogen +

NRC 30 +, TXX-4708 +, TXX-4499 +, TXX-4169 +, TXX-4284, Forwards Response to 840827 Request for Info Re Status of Human Engineering Deficiencies & Clarifications to Control Room Design Review Implementation Audit +, TXX-4417 +, TXX-4400, Requests Approval for Use of ASME Code Case N-378 Re bottom-mounted Instrumentation Seal Tables.Application of Code Case N-378 Will Not Result in Significant Reduction in Plant Safety +, TXX-4392, Forwards Summary Description of balance-of-plant Mechanical Equipment Qualification Program.No Corrective Action Necessary as Result of Environ Qualification Study for safety-related Equipment in Potentially Harsh Environs +, TXX-4399, Forwards Updated Engineering & Const Status Rept.Pages Deleted for Items Whose Deferral Beyond Fuel Load Has Been Accepted by NRC +, TXX-4452, Emergency Dose Assessment Model, Program Documentation +, TXX-4384, Forwards Partial Rev to Response to NRC Question 033.1 Describing Mod to Design of Core Cooling Monitor/Spds Interface as Interim Justification for Operation During First Operating Cycle +, TXX-4382, Forwards Addl Info to Justify Acceptability of Plant Design for Several Accident Monitoring Parameters.Commitment Provided to Modify Design Re Safety Injection Accumulator Pressure & Pressurizer Heater Status +, TXX-4385, Responds to 841106 Request for Addl Info Re Safe Shutdown & Alternate Safe Shutdown Design of Facilities.Util Will Complete Associated Circuit Analysis & Rept Prior to Exceeding 5% Power +, TXX-4381, Forwards Vols 1 & 2 of Fire Protection Program Review, in Response to 841106 Questions Re Safe Shutdown Following Postulated Fires +, TXX-4303, Informs That Comparison Demonstrating Applicability of Diablo Canyon Natural Circulation/Boron Mixing Prototype Test Results to Facility Will Be Provided.Test Will Be Performed If Results Unsatisfactory +, TXX-4307, Forwards Safety Parameter Display Sys for Comanche Peak Steam Electric Station Units 1 & 2,Emergency Response Facility Computer Sys,Sar, Per +, TXX-4283, Forwards Response to NRC 840807 Request for Addl Info Re Safety Parameter Display Sys.List of Parameters Available in Each Mode of Operation (Normal,Heat Up/Cool Down &/Or Cold Shutdown) Encl +, TXX-4275, Informs That Steam Generator Tube Rupture Reevaluation Will Include Calculations to Determine Margin to Overfill & Equilibrium Breakflow Showing Time to Overfill Is Greater than Time to Equalization,Per NRC 840409 Request +, TXX-4328, Informs That Suppl to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station Will Be Submitted Prior to Startup for Second Operating Cycle for Unit 1 +, TXX-4202, Forwards Description & Summary Evaluation of Seventh Test Proposed for Deferment Re Completion of Preoperational Air Flow Balancing of Control Room,Per 840514 Commitment.Safety Evaluation Included.Requests Concurrence +, TXX-4199, Forwards Description & Summary Evaluation of Deferred Preoperational Thermal Expansion Testing,Per 840514 Commitment.Concurrence Requested to Defer Test Until After Fuel Load +, TXX-4191, Forwards Description & Summary Evaluation of Deferred Preoperational Testing of Turbine Driven Auxiliary Feedwater Pump Steam Supply Line Check & Drain Pot Level Control Valves & Reactor Coolant Pump Seal Performance +, TXX-4182, Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review +, TXX-4216, Rev 3 to Procedure ODA-204, Preparation of Emergency Response Guidelines +  and TXX-4067, Forwards Test Results Re Fire Rating of Watertight Doors, Verifying Acceptability of Std Industrial Watertight Doors Utilized at Facility as 3 H Fire Barriers +

05000445  +  and 05000446  +

Noonan V +  and NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM) +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +  and NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants +

ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +, ML20211C452 +  and ML20211C452 +

NRC Inspection Manual 2513 +  and NRC Inspection Manual 2514 +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +

ST +, IAP +, AM-12 +, AM-21 +, AM-25 +, CP-84-27 +, CP-84-33 +, CP-84-24 +, CP-85-06 +, CP-85-07 +, CP-84-12 +, CP-84-30 +, CP-84-32 +, CP-84-22 +, CP-85-03 +, CP-85-01 +, CP-84-29 +, CP-85-09 +, CP-85-10 +, CP-85-12 +, CP-85-11 +, CP-84-34 +, CP-85-04 +, CP-85-08 +, CP-85-05 +, CP-84-31 +, CP-85-02 +, CP-84-26N +  and CP-84-28R +

1XX-4430-3 +, 1XX-4386 +, 8a32-06U +  and 8a31-05(f) +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +  and Containment Spray +

TXX-4708 +, TXX-4499 +, TXX-4169 +, TXX-4284, Forwards Response to 840827 Request for Info Re Status of Human Engineering Deficiencies & Clarifications to Control Room Design Review Implementation Audit +, TXX-4417 +, TXX-4400, Requests Approval for Use of ASME Code Case N-378 Re bottom-mounted Instrumentation Seal Tables.Application of Code Case N-378 Will Not Result in Significant Reduction in Plant Safety +, TXX-4392, Forwards Summary Description of balance-of-plant Mechanical Equipment Qualification Program.No Corrective Action Necessary as Result of Environ Qualification Study for safety-related Equipment in Potentially Harsh Environs +, TXX-4399, Forwards Updated Engineering & Const Status Rept.Pages Deleted for Items Whose Deferral Beyond Fuel Load Has Been Accepted by NRC +, TXX-4452, Emergency Dose Assessment Model, Program Documentation +, TXX-4384, Forwards Partial Rev to Response to NRC Question 033.1 Describing Mod to Design of Core Cooling Monitor/Spds Interface as Interim Justification for Operation During First Operating Cycle +, TXX-4382, Forwards Addl Info to Justify Acceptability of Plant Design for Several Accident Monitoring Parameters.Commitment Provided to Modify Design Re Safety Injection Accumulator Pressure & Pressurizer Heater Status +, TXX-4385, Responds to 841106 Request for Addl Info Re Safe Shutdown & Alternate Safe Shutdown Design of Facilities.Util Will Complete Associated Circuit Analysis & Rept Prior to Exceeding 5% Power +, TXX-4381, Forwards Vols 1 & 2 of Fire Protection Program Review, in Response to 841106 Questions Re Safe Shutdown Following Postulated Fires +, TXX-4303, Informs That Comparison Demonstrating Applicability of Diablo Canyon Natural Circulation/Boron Mixing Prototype Test Results to Facility Will Be Provided.Test Will Be Performed If Results Unsatisfactory +, TXX-4307, Forwards Safety Parameter Display Sys for Comanche Peak Steam Electric Station Units 1 & 2,Emergency Response Facility Computer Sys,Sar, Per +, TXX-4283, Forwards Response to NRC 840807 Request for Addl Info Re Safety Parameter Display Sys.List of Parameters Available in Each Mode of Operation (Normal,Heat Up/Cool Down &/Or Cold Shutdown) Encl +, TXX-4275, Informs That Steam Generator Tube Rupture Reevaluation Will Include Calculations to Determine Margin to Overfill & Equilibrium Breakflow Showing Time to Overfill Is Greater than Time to Equalization,Per NRC 840409 Request +, TXX-4328, Informs That Suppl to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station Will Be Submitted Prior to Startup for Second Operating Cycle for Unit 1 +, TXX-4202, Forwards Description & Summary Evaluation of Seventh Test Proposed for Deferment Re Completion of Preoperational Air Flow Balancing of Control Room,Per 840514 Commitment.Safety Evaluation Included.Requests Concurrence +, TXX-4199, Forwards Description & Summary Evaluation of Deferred Preoperational Thermal Expansion Testing,Per 840514 Commitment.Concurrence Requested to Defer Test Until After Fuel Load +, TXX-4191, Forwards Description & Summary Evaluation of Deferred Preoperational Testing of Turbine Driven Auxiliary Feedwater Pump Steam Supply Line Check & Drain Pot Level Control Valves & Reactor Coolant Pump Seal Performance +, TXX-4182, Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review +, TXX-4216, Rev 3 to Procedure ODA-204, Preparation of Emergency Response Guidelines +  and TXX-4067, Forwards Test Results Re Fire Rating of Watertight Doors, Verifying Acceptability of Std Industrial Watertight Doors Utilized at Facility as 3 H Fire Barriers +

NRC +, Jordan E +, Eisenhut D +  and Novak T +

Safe Shutdown +, Fire Barrier +, Coatings +, Emergency Lighting +, High Energy Line Break +, Containment high range radiation monitor +, Fire Protection Program +, Backfit +  and Affidavit +