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Letter, Report  and Technical

Iodine +, Nitrogen +  and Hydrogen +

10 CFR 50.67 +, 10 CFR 26 +, 10 CFR 50.59 +, 10 CFR 50.71 +, 10 CFR 72.48 +, 10 CFR 72.212 +, 10 CFR 50.55a +, 10 CFR 50.91#a +, 10 CFR 50.59#d2 +  and 10 CFR 50.71#e +

05000206  +, 05000361  +, 05000362  +, 07200041  +, 00206  +, 00362  +  and 00361  +

Southern California Edison +  and Bates A +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 90-04, Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 2003-01, Control Room Habitability +

ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +, ML19158A092 +  and ML19158A092 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

NRC Generic Letter 1980-11 +, 05000361/LER-1983-155-03, /03L-0:on 831221,control Element Assembly Calculator (Ceac) 1 Inoperable Due to Spurious Position Indication on Control Element Assembly 20.Cause Undetermined.Test Performed Satisfactorily +  and ML13309B264 +

Limitorque +  and Westinghouse +

NEI 96-07 +, NEI 08-05 +, NEI 07-07, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

NRC Bulletin 79-27 +, NRC Bulletin 88-11 +, NRC Bulletin 88-10 +, NRC Bulletin 90-01 +, NRC Bulletin 83-01 +, NRC Bulletin 79-09 +, NRC Bulletin 81-01 +  and NRC Bulletin 79-13, Cracking in Feedwater System Piping +

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-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +  and NUREG-0829, Summary of 890501 Meeting W/Util Re full-term OL Items, Thermal Shield & Items Requiring Resolution Before Startup. Attendance List,Nrc Agenda & Util Viewgraphs Encl +

Regulatory Guide 1.183 +, Regulatory Guide 1.147 +  and Regulatory Guide 1.129 +

SR-3.1.1.1 +, SR-3.8.4.2 +  and SR-3.5.2.4 +

1Q83-03-001 +  and 200Z-11-008 +

Washington +  and California +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Qualified Safety Parameter Display System +, Decay Heat Removal +, Main Steam Line +  and Containment Spray +

TS-3.8.6 +, TS-3.7.11 +, TS-4.3.1 +  and TS-5.4.4 +

Office of Nuclear Material Safety and Safeguards +, Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Tornado Missile +, Emergency Lighting +, Incorporated by reference +, High Energy Line Break +, Eddy Current Testing +, Severe Accident Management Guideline +, Control of Heavy Loads +, Fuel cladding +, Backfit +, Core Exit Thermocouple +, Affidavit +, Control Room Habitability +, Spent fuel rack +, Gas accumulation +  and Leak-Before-Break +