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

ASME Section XI +  and ASME Section II +

Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +  and Lead +

10 CFR 50 +, 10 CFR 2 +, 10 CFR 73 +, 10 CFR 100.10 +, 10 CFR 50.54#p +  and 10 CFR 73.40#d +

00358  +  and 05000358  +

GDC 54 +, GDC 2, Design bases for protection against natural phenomena +  and GDC 3, Fire protection +

NRC Generic Letter 81-29, Simulator Examinations +, NRC Generic Letter 81-27, Privacy and Proprietary Material in Emergency Plans +, NRC Generic Letter 81-16, NUREG-0737 Item I.C.1 SER on Abnormal Transient Operating Guidelines (ATOG) +, NRC Generic Letter 81-10, Post-TMI Requirements for the Emergency Operations Facility +  and NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel +

ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +, ML20033A837 +  and ML20033A837 +

ML20011A233 +, ML20009G343 +, ML20009A233 +, ML19343D310 +, ML20010D023 +, ML19350E389 +, ML17053C239 +, ML17053C488 +  and ML19257C407 +

NUREG-0418 +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-528 +, NUREG-0528, Forwards SER (NUREG-0528) & Federal Register Notice of Availability +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +, 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 +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.60 +, Regulatory Guide 1.145 +, Regulatory Guide 1.11 +  and Regulatory Guide 8.14 +

Ohio +, Washington +  and Idaho +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Safety Relief Valve +, Control rod blade +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Reactor Vessel Water Level +, Safe Shutdown Earthquake +, High Energy Line Break +, Scram Discharge Volume +, Loss of Offsite Power +, Safeguards Contingency Plan +, Control of Heavy Loads +, Fire Protection Program +  and Control Room Habitability +