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

Boron +, Iodine +, Carbon +, Hydrogen +  and Lead +

10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.62 +  and 10 CFR 50.34#g +

SECY-84-134 +  and SECY 85-60 +

00470  +  and 05000470  +

Turbine Trip +  and Reactor Trip +

GDC 16 +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +  and NRC Generic Letter 85-01, Fire Protection Policy Steering Committee Report +

ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +, ML20234C645 +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +

IEEE 384 +, IEEE 323 +  and IEEE 279 +

Iodine-131 +  and Cobalt-60 +

Feedwater +, ML20024E392 +, ML17298B537 +, ML20106D277 +, LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days +, LD-85-039, Informs That Vendor Will Add Interface to CESSAR App B Item III.A.1.2 (Upgrade Emergency Support Facilities) to Facilitate Closeout of SPDS Issue.Requirement Will Be Added to CESSAR in Amend 10 or 11 +, LD-85-042, Requests That Encl Forward Referenceability Provision Be Included in 850802 Application for Amend to CESSAR Final Design Approval,Per Section 8.3.6(1) of Commission Policy Statement on Severe Reactor Accidents.. +, LD-85-034, Forwards Responses to 850710 Questions Re Review of CESSAR Sys 80 Tech Specs Covering Reactor Protective Sys Trip Setpoint Limits +, LD-85-033, Forwards Comments on Proof & Review Tech Specs,Per 850703 Request.Concurs W/Proposed Tech Specs.Ltr from Northeast Utils to NRC & marked-up Tech Specs Encl.Responses to Questions Per Being Prepared +, LD-87-009, Forwards Response to 851029 Request for Addl Info Re Review of CESSAR Confirmatory Issues on Natural Circulation Cooldown & Steam Generator Tube Rupture.Info Needed to Complete Review +, LD-85-024, Forwards Proposed Final Version of CESSAR Chapter 16 Sys 80 Tech Specs,Per 850502 Meeting W/Nrc.Completion of Review of Tech Specs Requested by End of June 1985 to Include Revs in Amend 10 to CESSAR +, LD-85-028, Forwards CESSAR FSAR Clarifications Re Safety Injection Sys Delay Time.Changes Identified as Part of Cleanup Effort to Close Out Amend 10 +, LD-85-029, Forwards Results of CESSAR Analysis of Increased Blowdown for Pressurizer Safety Valves,Per Reactor Sys Branch Request.Analysis Consistent W/Analysis Submitted by Arizona Public Svc +, LD-85-022, Responds to 841126 Request for Addl Info Re Modified Acceptance Criteria for CESSAR-F Section 14.2.12.5.17 on Main & Emergency Feedwater Sys Test.Listed Criterion Will Be Added to Future Amend +, LD-85-020, Requests Finalization of CESSAR Chapter 16 Tech Specs & Meeting in Bethesda,Md to Discuss Scope of Review.Impact of Review Should Be Minimized Based on Tech Specs Compared on word-by-word Basis W/Palo Verde Tech Specs +, LD-85-019, Forwards Comparison of NRC Secondary Water Chemistry Guidance W/Palo Verde/Cessar Proposed Water Chemistry & Response to NRC Questions Re Chemistry Program.Condenser Inservice Insp Program Beyond Scope of CESSAR Design +, LD-85-004, Forwards Palo Verde Technical Audit of Safety Analysis & Applicable CESSAR-F Analyses,Per .No Serious Technical Errors,Safety Concerns or Systematic Error Patterns found.C-E Design Process Adequate +, LD-85-013, Discusses CESSAR Confirmatory Issues 1 & 2 Re Single Failure Vulnerability of Auxiliary Pressurizer Spray.Power Supply Isolators for Valves CH-239 & CH-240 Will Be Added If Sufficient to Close Confirmatory Issues 1 & 2 +, LD-84-055, Advises That Requested Addl Info Re SER Confirmatory Issue 4 Listed in Suppl 2 to NUREG-0852 Concerning Inadequate Core Cooling Instrumentation Will Be Submitted by Dec 1984 +, LD-84-051, Discusses Potential Single Failure of Sys 80 Auxiliary Pressurizer Spray Sys.Potential Failure Involves Possibility of Valve CH-240 Sticking in Full Open Position.Info Closes Out CESSAR Confirmatory Issues 1 & 2,per NUREG-0852 +, LD-84-049, Forwards Response to Mechanical Engineering Branch 840424 Request for Addl Info Re Operability of Shutdown Cooling Sys Relief Valves Used on Sys 80 Std Plant.Valves in Question Will Function Under Anticipated Design Conditions +, LD-84-041, Responds to 840327 Request for Info Re Potential Single Failure in Auxiliary Pressurizer Spray sys.C-E Completed Preliminary Review of Info Requested.Info Expected to Be Provided by Sept 1984 +, LD-84-060, Forwards Minor Mods to CESSAR Chapter 14 to Facilitate Improved Testing Procedure.Changes Only Affect Tests Performed After Fuel Loading & Do Not Affect NRC Requirements.Mods Will Be Incorporated Into Amend to CESSAR +, LD-84-012, Forwards for Review,Amend 9 to C-E Std Sar.Major Changes Result from Response to Confirmatory Items & NRC Questions +, LD-84-009, Forwards Interface Requirements Re Block Valves on Atmospheric Dump Valves to Close Out Confirmatory Item 2 of Sser 2 Re Steam Generator Tube Rupture Analysis +, LD-83-108, Forwards Responses to NRC Comments on Leak Before Break Evaluation of Main Loop Piping of C-E RCS, Per 831026 Meeting & 830614 Submittal.Max Seismic Moment Has No Impact on Loading of Axial Slot in Elbow +, LD-83-085, Discusses Impact of Problems W/Reactor Coolant Pumps, Resistance Temp Detector Thermowells,Safety Injection Nozzle Thermal Sleeves & Control Element Assembly Identified During Palo Verde Hot Functional Testing +, LD-83-074, Forwards Computer Simulation of Natural Circulation Cooldown +, LD-83-066, Forwards Reanalysis of Steam Generator Tube Rupture Event W/Loss of Offsite Power & Addl Single Failure,Per NRC 830426 Request.Info Completes SER Confirmatory Item 18 +...

NUREG-0852, Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values +, NUREG-1044, Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys +, NUREG-852 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +  and NUREG-0857, Supplement No. 8 Safety Evaluate on Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 +

ST +, CP +, CH-240 +, CH-501 +, CH-203 +, CH-503 +, CH-524 +, CH-536 +, CH-239 +  and CH-205 +

ML20234C645 +  and ML20234C645 +

Regulatory Guide 1.45 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.20 +

SECY-84-134 +  and SECY 85-60 +

Arizona +, Washington +  and California +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

Safe Shutdown +, Boric Acid +, Safe Shutdown Earthquake +, Hydrostatic +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Pressure boundary leak +, Leak-Before-Break +  and Leak Before Break +

WCAP-9558 +  and WCAP-9787 +

WCAP-9558 +  and WCAP-9787 +