LER-1978-012, /01T-0 on 781209:primary Loop a Resistance Temp Detector Manifold Isolated to Replace Leaking Orifice Flange Gasket.Took 2 of 4 Overtemp & Overpower Temp Difference Channels Out of Svc.Caused by Personnel Error |
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N C FOR 366 U. S. NUCLEAR REGULATORY COMMISSION mi LICENSEE EVENT REPORT
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ATTACHMENT TO LICENSEE EVENT REPORT NO. 78-012/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301 With the reactor just critical at zero power during a scheduled outage on December 9, 1978, the reactor coolant system (RCS) loop "A" RTD (resistance temperature detector) manifold was manually isolated at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> to replace a leaking orifice flange gasket.
This removed two out of the four overtemperature AT and overpower AT channels from service and left only the minimum number of AT channels to trip (two) in service.
The reactor was taken subcritical at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> to facilitate rod position indication calibration and then returned to zero power criticality at 1444 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.49442e-4 months <br />.
The RTD manifold was valved back into service at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> returning the instrumentation to full redundancy.
Technical Specification 15.3.5.C in conjunction with Items 5 and 6 of Technical Specification Table 15.3.5-2 requires a hot shutdown if the minimum number of operable channels (three) or the minimum degree of redundancy (two) cannot be met.
This event occurred due to an oversight on the part of the operating personnel.
To prevent recurrence, operating personnel have been instructed to more carefully evaluate the effects of changing the position of reactor coolant system valves while the reactor is critical.
Also, a copy of this licensee event report will be routed to all licensed operating personnel per normal plant practice.
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| 05000301/LER-1978-009-03, /03L-0 on 780913:on 2 occasions,2 of 3 Charging Pumps Were isolated.2 3/4 Crosby Relief Valves Leaked Through Causing Temporary Loss of Charging Flow.Charging Pump Relief Valve Replaced & a Pump Returned to Svc | /03L-0 on 780913:on 2 occasions,2 of 3 Charging Pumps Were isolated.2 3/4 Crosby Relief Valves Leaked Through Causing Temporary Loss of Charging Flow.Charging Pump Relief Valve Replaced & a Pump Returned to Svc | | | 05000301/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000301/LER-1978-010, Forwards LER 78-010/01T-0 | Forwards LER 78-010/01T-0 | | | 05000301/LER-1978-010-01, /01T-0 on 780928:reactor Coolant Sys Pressure Began Dropping at 25 Psi Per Minute;Pressurizer Spray Value 431B Found Partially Open Despite Shut Signal Due to 0 Set Point Drift Caused by Heat Degradation in Transducer | /01T-0 on 780928:reactor Coolant Sys Pressure Began Dropping at 25 Psi Per Minute;Pressurizer Spray Value 431B Found Partially Open Despite Shut Signal Due to 0 Set Point Drift Caused by Heat Degradation in Transducer | | | 05000266/LER-1978-010-01, /01T-1 on 780528:Indication of primary-to- Secondary Leak of 145 Gpd in the a SG Was Noted on 780524. Source of Leak Due to Failure of Tube at Position R44C35. Tube Plugged & Unit Returned to Svc | /01T-1 on 780528:Indication of primary-to- Secondary Leak of 145 Gpd in the a SG Was Noted on 780524. Source of Leak Due to Failure of Tube at Position R44C35. Tube Plugged & Unit Returned to Svc | | | 05000301/LER-1978-011, Cancelled | Cancelled | | | 05000301/LER-1978-012, Forwards LER 78-012/01T-0 | Forwards LER 78-012/01T-0 | | | 05000266/LER-1978-012, Forwards LER 78-012/01X-0 | Forwards LER 78-012/01X-0 | | | 05000266/LER-1978-012-01, /01X-0:on 780627,during Visual Insp of Fire Barrier Penetration Seals,Horizontal Seals Found Constructed Differently than Specified.Caused by Change in Const Drawings | /01X-0:on 780627,during Visual Insp of Fire Barrier Penetration Seals,Horizontal Seals Found Constructed Differently than Specified.Caused by Change in Const Drawings | | | 05000301/LER-1978-012-01, /01T-0 on 781209:primary Loop a Resistance Temp Detector Manifold Isolated to Replace Leaking Orifice Flange Gasket.Took 2 of 4 Overtemp & Overpower Temp Difference Channels Out of Svc.Caused by Personnel Error | /01T-0 on 781209:primary Loop a Resistance Temp Detector Manifold Isolated to Replace Leaking Orifice Flange Gasket.Took 2 of 4 Overtemp & Overpower Temp Difference Channels Out of Svc.Caused by Personnel Error | | | 05000266/LER-1978-014-01, /01T-0:on 780920,primary-to-secondary Leakage Noted During Normal Operation.Caused by Two Leaking Tubes & One Leaking Plug on Inlet Side of Steam Generator A.Tubes Will Be Plugged & Plug Will Be Weld Repaired | /01T-0:on 780920,primary-to-secondary Leakage Noted During Normal Operation.Caused by Two Leaking Tubes & One Leaking Plug on Inlet Side of Steam Generator A.Tubes Will Be Plugged & Plug Will Be Weld Repaired | | | 05000266/LER-1978-014, Forwards LER 78-014/01T-0 | Forwards LER 78-014/01T-0 | | | 05000266/LER-1978-015, Forwards LER 78-015/01T-0 | Forwards LER 78-015/01T-0 | | | 05000266/LER-1978-015-01, /01T-0 on 781009:snubber on Pressurizer Relief Line Was Found Inoperable.Grinnel Model HS-17,21/2 Inch X 5 Inch Bore & Stroke Snubber Failed for Undetermined Cause. Snubber Replaced & Surveillance Prog Expanded | /01T-0 on 781009:snubber on Pressurizer Relief Line Was Found Inoperable.Grinnel Model HS-17,21/2 Inch X 5 Inch Bore & Stroke Snubber Failed for Undetermined Cause. Snubber Replaced & Surveillance Prog Expanded | | | 05000266/LER-1978-016-01, /01T-0 on 781106:turbine Runback Resulted from Safeguards Bus Tie Breaker Trip.Westinghouse Model CV-7 Undervoltage Relay on Tie Breaker Tripped Causing Breaker to Open.No Line Voltage Surges Detected | /01T-0 on 781106:turbine Runback Resulted from Safeguards Bus Tie Breaker Trip.Westinghouse Model CV-7 Undervoltage Relay on Tie Breaker Tripped Causing Breaker to Open.No Line Voltage Surges Detected | | | 05000266/LER-1978-017-01, /01T-0 on 781206:control Rod K-7 Control Bank D Became Misaligned More than 15 in & Caused Quadrant Flux Tilt of More than 2%.Caused by Personnel Error | /01T-0 on 781206:control Rod K-7 Control Bank D Became Misaligned More than 15 in & Caused Quadrant Flux Tilt of More than 2%.Caused by Personnel Error | | | 05000266/LER-1978-017, Forwards LER 78-017/01T-0 | Forwards LER 78-017/01T-0 | | | 05000266/LER-1978-018, Forwards LER 78-018/01T-0 | Forwards LER 78-018/01T-0 | | | 05000266/LER-1978-018-01, /01T-0 on 781219:during Normal Power Operation, Power Range Channel 44 Failed,Causing 20% Turbine Runback. Failure of Power Designs,Inc,Model UPMP-X54W Power Supply Caused Instrument to Fail | /01T-0 on 781219:during Normal Power Operation, Power Range Channel 44 Failed,Causing 20% Turbine Runback. Failure of Power Designs,Inc,Model UPMP-X54W Power Supply Caused Instrument to Fail | | | 05000266/LER-1978-019-01, /01T-0 on 7901228:both Heat Tracing Circuits of Circuit 47 of the Boric Acid Sys Were Inoperable Due to Defective Potentiometers in the Thermon Model SCR Controller for Each Circuit | /01T-0 on 7901228:both Heat Tracing Circuits of Circuit 47 of the Boric Acid Sys Were Inoperable Due to Defective Potentiometers in the Thermon Model SCR Controller for Each Circuit | | | 05000266/LER-1978-019, Forwards LER 78-019/01T-0 | Forwards LER 78-019/01T-0 | | | 05000266/LER-1978-073-03, /03L on 781121:failure to Submit RO 50-366/78-55 W/In 30 Days.Caused by Deviation Rept 2-78-79 Not Received by Responsible Dept Head Nor Superintendent of Plant Engr Svcs.Personnel Were Reminded of Procedures | /03L on 781121:failure to Submit RO 50-366/78-55 W/In 30 Days.Caused by Deviation Rept 2-78-79 Not Received by Responsible Dept Head Nor Superintendent of Plant Engr Svcs.Personnel Were Reminded of Procedures | |
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