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LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT  and Licensee Event Report

10 CFR 50.73#a2 +  and 10 CFR 50.72#b2 +

05000254  +  and 00254  +

Exelon +, Bax R +  and David Harmon +

05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +, 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +  and 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +

0.00233 d (0.0558 hours, 3.323413e-4 weeks, 7.64805e-5 months)  +, 0.0127 d (0.306 hours, 0.00182 weeks, 4.1855e-4 months)  +, 0.00234 d (0.0561 hours, 3.339947e-4 weeks, 7.6861e-5 months)  +, 0.00235 d (0.0564 hours, 3.356481e-4 weeks, 7.72415e-5 months)  +, 0.00237 d (0.0569 hours, 3.38955e-4 weeks, 7.80025e-5 months)  +, 0.00238 d (0.0572 hours, 3.406085e-4 weeks, 7.8383e-5 months)  +, 0.0024 d (0.0575 hours, 3.422619e-4 weeks, 7.87635e-5 months)  +, 0.00241 d (0.0578 hours, 3.439153e-4 weeks, 7.9144e-5 months)  +, 0.00245 d (0.0589 hours, 3.505291e-4 weeks, 8.0666e-5 months)  +, 0.00248 d (0.0594 hours, 3.53836e-4 weeks, 8.1427e-5 months)  +, 0.00253 d (0.0608 hours, 3.621032e-4 weeks, 8.33295e-5 months)  +, 0.00262 d (0.0628 hours, 3.736772e-4 weeks, 8.5993e-5 months)  +, 0.00265 d (0.0636 hours, 3.786376e-4 weeks, 8.71345e-5 months)  +, 0.00266 d (0.0639 hours, 3.80291e-4 weeks, 8.7515e-5 months)  +, 0.0027 d (0.0647 hours, 3.852513e-4 weeks, 8.86565e-5 months)  +, 0.00273 d (0.0656 hours, 3.902116e-4 weeks, 8.9798e-5 months)  +, 0.00277 d (0.0664 hours, 3.95172e-4 weeks, 9.09395e-5 months)  +, 0.00284 d (0.0681 hours, 4.050926e-4 weeks, 9.32225e-5 months)  +, 0.00367 d (0.0881 hours, 5.241402e-4 weeks, 1.206185e-4 months)  +, 0.00382 d (0.0917 hours, 5.456349e-4 weeks, 1.25565e-4 months)  +, 0.00463 d (0.111 hours, 6.613757e-4 weeks, 1.522e-4 months)  +  and 0.00465 d (0.112 hours, 6.646825e-4 weeks, 1.52961e-4 months)  +

General Electric +  and Foxboro +

10 CFR 50.73(a)(2)(viii) +, 10 CFR 50.73(a)(2) +  and 10 CFR 50.73(c)(2)(iv) +

07-92-004 +  and 66AT-OH +

Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Reactor Pressure Vessel +, Reactor Building Ventilation +, Residual Heat Removal +, Automatic Depressurization System +, Main Steam Line +  and Main Condenser +

https://lersearch.inl.gov/Index.aspx?Page=PDFView?Doc::2541992004R03.pdf  +  and http://pbadupws.nrc.gov/docs/ML2009/ML20090H155.pdf  +