LER-1976-010, /01T-0:on 760830,during Review of Core 12 Analysis,Error Found in Figure 8-1 of Tech Specs.Caused by Gamma Heating Correction Omitted by Error in Application of Computer Codes |
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EVENT DESCRIPTION
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COCE CCMPONENT CODE E l: 1Zl W lZlZlZlZlZlZl (Zj lZl9l9l9l
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m.ATON 7 89 10 11 12 17 43 44 CAUSE DESCRIPTION 47 48 [Tne accarent cause of this event was the inadverta 7 89 l to account for the fact that gamma enerev is not included in the UiGR 3
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FERSONNEL EXPOSURES 80 N;;VSEA TYPE CESCA# TON 1D l 0101 01
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PUEUCITY 80 1
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ACOilONAL FACTORS 80 Q[ (See attached sheet) 7 89 l
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EVENT DESCRIPTION
On August 30, 1976 during a review of the Core XII analysis and in preparation for Core XIIIanalysis, an error was discovered in Fig. 8-1 of the Technical Specification D.2.c.1.
This curve delineates the alldiable peak WGR and was found to be non-conservative by 2.7%.
The allowable peak W GR culve, Fig. 8.1 as originally evaluated did not include a correction for the fact that only.0.973 of the heat is generated in the fuel (P.C. 125 Table 6-1) and'0.027 is due to gamma energy. Therefore, on applying the 0.973 multiplier, so that the curve will be consistent with measured numbers, the curve (Fig.'8.1) will be reduced by 2.7%.
To detemine whether the Mf/FT limits were actually exceeded, the measured data for Core XII was re-examined. The re-examination j
shows that the correct limiting WGR has been exceeded only for i
12 days out of the 221 power days of operation from startup of Core XII to August 30, 1976. During those 12 days (which occurred in June,1976) the actual peak WGR was between 10.24 and 10.41 Mf/FT.
t compared to the correct limit of 10.22 (Mf/Fr.
From INCORE run YR-XII-13 covering the period-of interest, it was found that only 4 fuel rods cut of 17734 in the core were in excess of the correct limiting W GR for each of the 12 days.
The plant load was reduced immediately by 2.7% in order to correct for this error.
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A'I ERROR WAS DISCOVERED IN FIG 8-10F THE TECH SPEC THE CURVE DELINEATES THE ALLOWAELE PEAK LHGR AND WAS EDUND B TO BE NON-CONSERVAT EY 2.7%..................
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| 05000029/LER-1976-001, Forwards LER 76-001/03L-0 | Forwards LER 76-001/03L-0 | | | 05000029/LER-1976-001-03, /03L-0:on 760204,slight Leakage from Charging Pump 3 Found in Two Areas,Relief Valve Discharge Flange & Pump Suction Tee to Valve Line Welds.Caused by Vibration Induced Fatigue Failure.Flange & Tee Replaced | /03L-0:on 760204,slight Leakage from Charging Pump 3 Found in Two Areas,Relief Valve Discharge Flange & Pump Suction Tee to Valve Line Welds.Caused by Vibration Induced Fatigue Failure.Flange & Tee Replaced | | | 05000029/LER-1976-002, Forwards LER 76-002/03L-0 | Forwards LER 76-002/03L-0 | | | 05000029/LER-1976-002-03, /03L-0:on 760210,auxiliary Operator Noted Leak in Weld on Reducer Discharge Header of Charging Pump 3.Caused by Vibration Induced Fatigue Failure,Due to Continuous Operation of Displacement Charging Pump | /03L-0:on 760210,auxiliary Operator Noted Leak in Weld on Reducer Discharge Header of Charging Pump 3.Caused by Vibration Induced Fatigue Failure,Due to Continuous Operation of Displacement Charging Pump | | | 05000029/LER-1976-003, Forwards LER 76-003/01T-0 | Forwards LER 76-003/01T-0 | | | 05000029/LER-1976-003-01, /01T-0:on 760513,review of ECCS Analysis Found Error in Accident Analysis.Caused by Error in Assumption of Accident Analysis.Reanalysis Performed.Proposed Change to Tech Specs Submitted | /01T-0:on 760513,review of ECCS Analysis Found Error in Accident Analysis.Caused by Error in Assumption of Accident Analysis.Reanalysis Performed.Proposed Change to Tech Specs Submitted | | | 05000029/LER-1976-004, Forwards LER 76-004/03L-0 | Forwards LER 76-004/03L-0 | | | 05000029/LER-1976-004-03, /03L-0:on 761216,during Monthly Test,Hpsi Pump 1 Shaft Housing Seal Was Found to Leak Lightly.Caused by Cut in Gasket.Defective Gasket Replaced | /03L-0:on 761216,during Monthly Test,Hpsi Pump 1 Shaft Housing Seal Was Found to Leak Lightly.Caused by Cut in Gasket.Defective Gasket Replaced | | | 05000029/LER-1976-005-03, /03L-0:on 760520,auxiliary Operator Noted Slight Leakage from Weld on Inlet Charging Pump 3 Relief Valve. Caused by Pullback Gap Not Allowed During Installation of Pipe & Vibration Induced Fatigue Failure | /03L-0:on 760520,auxiliary Operator Noted Slight Leakage from Weld on Inlet Charging Pump 3 Relief Valve. Caused by Pullback Gap Not Allowed During Installation of Pipe & Vibration Induced Fatigue Failure | | | 05000029/LER-1976-005-30, /030-1:on 760520,weld on Inlet to Charging Pump 3 Relief Valve Found Leaking.Caused by Error in Installation of Pipe in Which Full 1/16 Inch Pullback Not Allowed | /030-1:on 760520,weld on Inlet to Charging Pump 3 Relief Valve Found Leaking.Caused by Error in Installation of Pipe in Which Full 1/16 Inch Pullback Not Allowed | | | 05000029/LER-1976-005, Forwards LER 76-005/03L-0 | Forwards LER 76-005/03L-0 | | | 05000029/LER-1976-006, Forwards LER 76-006/01T-0 | Forwards LER 76-006/01T-0 | | | 05000029/LER-1976-006-01, /01T-0:on 760624,during Normal Operation,Routine Safety Injection Tank Makeup Was Performed Per Plant Procedure.Acceptance Criteria Not Met.Caused by Change 117, Suppl 3,requiring Limits on Boron Concentration | /01T-0:on 760624,during Normal Operation,Routine Safety Injection Tank Makeup Was Performed Per Plant Procedure.Acceptance Criteria Not Met.Caused by Change 117, Suppl 3,requiring Limits on Boron Concentration | | | 05000029/LER-1976-007-01, /01T-0:on 760624,investigation of RO 76-06 Revealed That Assumed Boron Concentration of LOCA Analysis Was Exceeded During Hydrostatic Leak Test of Reactor Vessel. Caused by Personnel Error.Personnel Reinstructed | /01T-0:on 760624,investigation of RO 76-06 Revealed That Assumed Boron Concentration of LOCA Analysis Was Exceeded During Hydrostatic Leak Test of Reactor Vessel. Caused by Personnel Error.Personnel Reinstructed | | | 05000029/LER-1976-007, Forwards LER 76-007/01T-0 | Forwards LER 76-007/01T-0 | | | 05000029/LER-1976-008, Updated LER 76-008/010-0:on 760730,review of Rod Ejection Accident Analysis Revealed Error in Method Used for Core 11 Analysis.Caused by Error in Methods & Application of Analysis Codes.Sys of Documentation Control Initiated | Updated LER 76-008/010-0:on 760730,review of Rod Ejection Accident Analysis Revealed Error in Method Used for Core 11 Analysis.Caused by Error in Methods & Application of Analysis Codes.Sys of Documentation Control Initiated | | | 05000029/LER-1976-010, Forwards LER 76-010/01T-0 | Forwards LER 76-010/01T-0 | | | 05000029/LER-1976-010-01, /01T-0:on 760830,during Review of Core 12 Analysis,Error Found in Figure 8-1 of Tech Specs.Caused by Gamma Heating Correction Omitted by Error in Application of Computer Codes | /01T-0:on 760830,during Review of Core 12 Analysis,Error Found in Figure 8-1 of Tech Specs.Caused by Gamma Heating Correction Omitted by Error in Application of Computer Codes | | | 05000029/LER-1976-011, Forwards LER 76-011/03L-0 | Forwards LER 76-011/03L-0 | | | 05000029/LER-1976-011-03, /03L-0:on 760907,slight Leakage Noted from Welded Nipple on Charging Pump 3 Discharge Heater Line.Caused by Failure to Allow 1/16-inch Pull Back Gap During Installation of Weld.Pump Isolated & Nipple Replaced | /03L-0:on 760907,slight Leakage Noted from Welded Nipple on Charging Pump 3 Discharge Heater Line.Caused by Failure to Allow 1/16-inch Pull Back Gap During Installation of Weld.Pump Isolated & Nipple Replaced | | | 05000029/LER-1976-012-01, /01T-0:on 761119,safety Injection Accumulator for Boron Was 30 Ppm Over Tech Specs & 80 Ppm Over Administrative Limits.Investigation Revealed That Std Sodium Hydroxide Titrant Had Concentrations Lower than Predicted | /01T-0:on 761119,safety Injection Accumulator for Boron Was 30 Ppm Over Tech Specs & 80 Ppm Over Administrative Limits.Investigation Revealed That Std Sodium Hydroxide Titrant Had Concentrations Lower than Predicted | | | 05000029/LER-1976-012, Forwards LER 76-012/01T-0 | Forwards LER 76-012/01T-0 | | | 05000029/LER-1976-013-01, /01T-0:on 761128,following Plant Trip from Power, Main Collant Pump 3 Inadvertently Restarted During Scram Recovery.Caused by Jammed Trip Mechanism on Air Circuit Breaker.New Trip Coil Installed | /01T-0:on 761128,following Plant Trip from Power, Main Collant Pump 3 Inadvertently Restarted During Scram Recovery.Caused by Jammed Trip Mechanism on Air Circuit Breaker.New Trip Coil Installed | | | 05000029/LER-1976-013, Forwards LER 76-013/01T-0 | Forwards LER 76-013/01T-0 | | | 05000029/LER-1976-014-03, /03L-0:on 761216,during Performance of OP-4204, Monthly Test of Safety Injection Pumps,High Pressure Safety Injection Pump Shaft Housing Seal Found Leaking.Caused by Cut in Gasket.Defective Gasket Replaced | /03L-0:on 761216,during Performance of OP-4204, Monthly Test of Safety Injection Pumps,High Pressure Safety Injection Pump Shaft Housing Seal Found Leaking.Caused by Cut in Gasket.Defective Gasket Replaced | |
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