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TECHNICAL SPECIFICATIONS  and TECHNICAL SPECIFICATIONS & TEST REPORTS

Boron +  and Sodium +

10 CFR 50.73 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.92 +, 10 CFR 50.55a +, 10 CFR 50.73#a2iB +  and 10 CFR 50.55a#f +

JPN-89-076, Forwards Criteria to Be Used to Interpret Term Verify Operable, Per Util 890531 Proposed Tech Spec Changes, Reflecting LPCI Mods During Reload 1/Cycle 2 Refueling Outage & Eliminating Need for Redundant Surveillance Tests +, SECY-88-304 +, JPTS-90-003 +, JPN 95-053 +, JPTS 93-003 +, JPN-95 053 +, JPN 95 053 +, JPTS-93-003 +  and JPN-95-053, Forwards Application for Amend to License DPR-59,revising TSs to Incorporate IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code +

05000333  +  and 00333  +

ML20095F709 +, ML20095F709 +, ML20095F709 +, ML20095F709 +, ML20095F709 +, ML20095F709 +, ML20095F709 +, ML20095F709 +, ML20095F709 +  and ML20095F709 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

JPN-89-076, Forwards Criteria to Be Used to Interpret Term Verify Operable, Per Util 890531 Proposed Tech Spec Changes, Reflecting LPCI Mods During Reload 1/Cycle 2 Refueling Outage & Eliminating Need for Redundant Surveillance Tests +, JPN 95-053 +, JPN-95 053 +, JPN 95 053 +  and JPN-95-053, Forwards Application for Amend to License DPR-59,revising TSs to Incorporate IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code +

JPTS-90-003 +, JPTS 93-003 +  and JPTS-93-003 +

115KV +  and 4kV +

SR-3.5.1.2 +, SR-3.4 +, SR-3.6.1.8.2 +, SR-4.5.F.1 +, SR-4.5 +, SR-3.1 +, SR-4.7.A +, SR-4.3.C.3 +, SR-4.7.D.1 +, SR-4.7.A.4 +, SR-4.4.A +, SR-4.3.C +, SR-4.5.A.1 +, SR-4.5.E.1 +, SR-4.5.B.1 +, SR-4.5.G.3 +, SR-4.7.D +, SR-4.4.A.2 +, SR-4.4.A.1 +, SR-4.4.A.3 +, SR-4.7.D.2 +, SR-4.5.8.1 +, SR-4.5.F.2 +, SR-4.5.A +, SR-4.5.F.5 +, SR-4.11.D.1 +, SR-4.0.E +, SR-4.7.A.5 +, SR-4.4.A.6 +, SR-4.4.A.7 +...

3A-2 +, 27AOV-114 +, 27AOV-117 +, 27AOV-118 +, 27AOV-113 +, 27AOV-116 +, 27AOV-111 +, 27AOV-115 +, 27AOV-112 +, 02-3LT-101 +, 02-3PT-55A +, 94PS-200A +, 29PNS-80A2 +, 05PT-12A +, 29PNS-86A2 +, 94PNS-101 +, 94PS-2OOA +, 2SPNS-86A2 +  and 54c7-need +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Reactor Building Closed Loop Cooling +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6.1.3 +, TS-3.0 +, TS-3.5.G +, TS-3.0.B +, TS-1.0.T +, TS-4.0.E +  and TS-3.0.F +

High Radiation Area +, Stroke time +, Hydrostatic +, Scram Discharge Volume +, Excess Flow Check Valve +, Fuel cladding +, Offsite Circuit +, Fire Protection Program +  and Grace period +