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TECHNICAL SPECIFICATIONS  and TECHNICAL SPECIFICATIONS & TEST REPORTS

Boron +, Uranium +, Oxygen +, Hydrogen +, Chlorine +, Chloride +, Lead +  and Plutonium +

10 CFR 50.73 +, 10 CFR 55 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 19 +, 10 CFR 50.92 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 20.106 +, 10 CFR 20.407 +, 10 CFR 20.203#c2 +, 10 CFR 50.54#m1 +, 10 CFR 100.3#a +, 10 CFR 100.3#b +, 10 CFR 50.59#b2 +, 10 CFR 50.59#b +, 10 CFR 70.39#c +, 10 CFR 73.55#g4 +, 10 CFR 50#54 +  and 10 CFR 35.39 +

05000312  +  and 00312  +

NRC Generic Letter 89-14, Line-Item Improvements in Technical Specifications - Removal of 3.25 Limit on Extending Surveillance Intervals +, NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +  and NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification +

ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +, ML20005E343 +  and ML20005E343 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Tritium +, U-235 +, I-131 +  and Iodine-131 +

ML20027B539 +  and 05000312/LER-1988-021, :on 880615,potential Loss of Equipment Necessary to Mitigate Consequences of Accident Due to Postulated Implosion of Junction Boxed Noted.Caused by Failure to Apply Changes.Weepholes Installed +

NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +

Regulatory Guide 1.155 +, Regulatory Guide 1.16 +, Regulatory Guide 4.15 +  and Regulatory Guide 1.8 +

California +  and Washington +

Steam Generator +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Emergency Feedwater Initiation and Control +  and Control Rod +

TS-3.9.1 +, TS-3.13 +, TS-6.9 +  and TS-3.13.2 +

Boric Acid +, Shutdown Margin +, High Radiation Area +, Offsite Dose Calculation Manual +, Time to boil +, Safe Shutdown Earthquake +, Design basis earthquake +, Shift Technical Advisor +, Annual Radiological Environmental Operating Report +, Process Control Program +, Control of Heavy Loads +  and Spent fuel rack +