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 |
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L'OENSEE EVENT REPORT
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SO DOCKET NUMBER EVENT DATE REPORT DATE
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EVENT DESCRIPTION
O2 l See attached sheet.
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7 89 pswE 80 E[E ODE COMPONENT CODE MANuF CT o
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FACrJTY METHOD OF STATUS
% POWER OTHER STATUS DECOVERY DGCOVERY DESCRIPTON W
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10 12 13 44 45 46 80 ACTr. STY CO$ TENT RE' EASED OF RELEASE AMOUNT OF ACTfVITY LOCATON OF RELE SE 8
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10 11 44 45 80 PERSONNEL EXPOSURES NUVEER TYPE DESCRIPTON 13 1 01 01 of LZl I
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1 7 89 80 ADD:TIONAL FACTORS 8I I
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James L. St'aub GEM g a g, pgggg
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U LER 76-08/010
EVENT DESCRIPTION
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During nonnal operation a review of the Rod Ejection Accident analysis
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revealed an error in the method used for the Core XI analysis. The I
present core (Core XII) analysis is based on the Core XI analysis. A re-analysis revea16d that the maximum allowable' 2ero power ejected rod worth is 0.75% p vice that calculated for Core XI reload of 1.0% p.
This constitutes a violation of Technical Specification Section E.2.a.(8).
I and is identified as Reportable Occurrence 76-08. A review of the predicted and measured worths for Core XII indicates that the rod worth could not exceed 0.75% p.
]
CAUSE DESCRIPTION 4
A review of the Core XI Rod Ejection Accident Analysis was being performed coincident with that-for the Core XIII Reload Analysis.
This revealed an error in the methods and application of the' analysis codes. Following a thorough review of the Rod Ejection Analysis, a; Technical Specification change was submitted for the present core.
i To prevent errors in future accident analysis calculations, a system r
of doctmentation review and control has been initiated within the.
accident analysis group at the Nuclear Services Division in the-Westboro Office.
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U.7. NUCLE AR REGUL ATORY Comp':StoN OoCKET NUMDER V
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50-29 re-70 FILE NUMBE R N.RC DISTRIBUTION FoR PART 50 DOCKET MATERI AL INCIDENT REPORT TO:
FROM:
e DATE oF DOCUMENT Yankee Atomic Electric Co.
9/29/76 Mr. J. P. O'Reilly Rowe, Mass.
og7, ngeg,ygg Mr. Herbert A. Autio 10/1/76 MLETTE R ONoToR: ZED PROP INPUT FORM NUMDER OF CoPIEC RECEIVED D ORIGIN AL NUNC L AS$1FI E D One signcd copy S oPY l ENCLOSURE orSCRIPTION Ltr. trans the following:
Licensee Event Report (RO 50-29/76-08/010) on 7/30/76 (update report) concerning a review of the Rod Efection Accident analysis revealin;,
an error in the method used for the core XI RQNOT REMOVE
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ACF_NOWLEDGED (1-e>
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PLANT N/Js.
NOTE:
IF PERSO"NEL EXPOSUPS IS INVOLVED SENDDIRECTLYTOKREGER/J,.COLLIUS Yankee Rowe FOR ACTION /lNFORMATION 10/1/76 RJL 1
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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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