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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

ANSI B30.9 7 +  and ANSI B30.2 +

Copper +, Hydrogen +  and Lead +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 50.6 +, 10 CFR 50.49#48 +, 10 CFR 50.61#b3 +  and 10 CFR 50.63#c3 +

SECY 86-97 +, SECY 88-272 +, SECY 83-288 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY-84-119 +, SECY 88-772 +, SECY 89-177 +  and L 1980 +

05000237  +, 05000295  +, 05000304  +, 00295  +, 00304  +  and 00495  +

54 FR 52946 +  and 49 FR 26045 +

Chandu Patel +  and Office of Nuclear Reactor Regulation +

GDC 16 +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 79-57, Acceptance Criteria for the Mark I Containment Long Term Program +, NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 81-03, Implementation of NUREG-0313,Technical Report on Material Selection & Processing GL for BWR Coolant Press Boundary Piping +, NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +, NRC Generic Letter 83-42, Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" +, 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) +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +, NRC Generic Letter 87-03, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 89-12, Operator Licensing Examination +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 14-04 +

ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +, ML20033E239 +  and ML20033E239 +

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 723 +  and IEEE 323 +

Westinghouse +  and Bliss +

NUREG-0993 +, NUREG-0774 +, NUREG/CR-0054 +, NUREG-4776 +, NUREG/CR-4261 +, NUREG/CR-3922 +, NUREG/CR-4470 +, NUREG-0644 +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG-1289, Submits Revised Agenda for CRGR Meeting 141 on 880714 in Bethesda,Md.Items for Review Include Proposed Generic Ltr on Instrument Air Problems & Proposed Draft Rule to Require College Degrees for Senior Reactor Operators +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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 +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1174, Summary of CRGR Meeting 163 on 890524 Re Proposed Generic Ltr on Emergency Response Data Sys,Usi A-17 on Sys Interactions,Generic Issue A-30 on safety-related Dc Power Sys & USI A-47 on Control Sys +, 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-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-1211, Informs of CRGR Meeting 98 Agenda Mod +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG/CR-8761 +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG-1217, Forwards NRC Resolution of USI A-47, Safety Implications of Control Sys, for Info.Resolution Consists of NUREG-1217, Evaluation of Safety Implications...Technical Findings Re USI A-47 & NUREG-1218, Regulatory Analysis.... W/O Encls +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +, NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +, NUREG-1218, Disapproves 900320 Response to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

CP-4776 +  and AM +

Regulatory Guide 1.155 +, Regulatory Guide 1.45 +, Regulatory Guide 1.139 +, Regulatory Guide 1.113 +  and Regulatory Guide 1.154 +

SECY 86-97 +, SECY 88-272 +, SECY 83-288 +, SECY 82-465 +, SECY 81-687 +, SECY 84-119 +, SECY-84-119 +, SECY 88-772 +  and SECY 89-177 +

88UREG-1109 +  and 98W-PWR +

Dresden +  and Zion +

Steam Generator +, Feedwater +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Circulating Water System +  and Decay Heat Removal +

Safe Shutdown +, Control of Heavy Loads +, Pressure Boundary Leakage +, Backfit +, Water hammer +  and Leak Before Break +