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LER-1979-010, /03L-0 on 790411:while in Hot Shutdown, Reassignment of Personnel to Unit 2 Prevented Surveillances Re Chemistry & Radiological Analysis at Proper Frequency. Missed Surveillances Subsequently Performed |
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| 2891979010R03 - NRC Website |
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. NRC F GJtM 364 U. C. NUCLE A3 KEGUL ATC RY COMMISSION 8777)
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0 to 61 DOCKET NUMSER 68 69 EVENT D ATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O 2 l While in the hot shutdown condition, after refuelirg, precarirn to co critical the I fo m I unit was returned to a' cold shutdown condition and all but the essential personnel l 6
l were assigned to help with 'IMI-2 during and after the March 28, 1979 l
u 4 O s i event. The reassigment of personnel and use of analysis facilities for Unit 2 l
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'Ihe missed surveillances were:
c T.S. Reference Late Date 1.
1301-4.7 A.
Unit Vent sample weekly ETS 2.3.2. Table 2 3-.27-79, 4-03-79 B.
Unit Vent sample nonthly 4-03-79 2.
1301-5.9 Condenser Vac P sanple ETS Table 2, C 4-03-79 p
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1301-4.5 Secondary Coolant activity 4.1.3.5 3-29-79 4.
1301-2 BAMP Boron Analysis 4.1.3.6 3-29-79, 4-05-79 5.
1301-4.4 BNST Boron Analysis
'4.1.3.2 3-29-79 6.
1301-3A RC Cl, F1, Boron, analysis 4.1.3.1.E 4-02-79 1301-3B 4.1.3.1.F 4-02-79 1301-3C 4.1.3.1.C 4-02-79 7.
1301-6.3A WE CST Weekly Cmp.
ETS Table 1A 4-02-79, 4-09-79 8.
1301-9.10 ETS RN Discharge pil ETS 2.2.2.
4-02-79 ETS 2.2.3 4-02-79 ETS 4.2.1 4-02-79 9.
1301-4.8 Primary Coolant Iodine Analysis TS Table 1 Section B 4-06-.79 i
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| 05000320/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000320/LER-1979-001-03, /03L-0 on 790104:reactor Bldg Pressure hi-hi Channel a Functional Test Not Performed,Due to Technician Oversight.Personnel Advised of Procedures | /03L-0 on 790104:reactor Bldg Pressure hi-hi Channel a Functional Test Not Performed,Due to Technician Oversight.Personnel Advised of Procedures | | | 05000289/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000289/LER-1979-001-01, /01T-1 on 780106:informed by B&W That Difference Between Reactor Power as Indicated by out-of-core Instrumentation & as Calculated by Heat Balance May Exceed 4% of Full Power.Tech Spec Change Initiated | /01T-1 on 780106:informed by B&W That Difference Between Reactor Power as Indicated by out-of-core Instrumentation & as Calculated by Heat Balance May Exceed 4% of Full Power.Tech Spec Change Initiated | | | 05000289/LER-1979-001-03, /03L-0 on 790107:during Inservice Insp Test on Decay Heat River Water Pump 1A(DR-P1a),vibration Level Was within Required Action Range. Caused by Imbalance Due to Rag in Pump Section & Perturbed by Shaft Sleeve Wear | /03L-0 on 790107:during Inservice Insp Test on Decay Heat River Water Pump 1A(DR-P1a),vibration Level Was within Required Action Range. Caused by Imbalance Due to Rag in Pump Section & Perturbed by Shaft Sleeve Wear | | | 05000320/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000289/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000289/LER-1979-002-03, /03L-0 on 790112:when Actuation Signal Was Applied to Open Valve from Its mid-position DH-V-58,motor Breaker Tripped. Caused by Motor Brake Not Releasing. Brake Will Be Inspected by 790331 | /03L-0 on 790112:when Actuation Signal Was Applied to Open Valve from Its mid-position DH-V-58,motor Breaker Tripped. Caused by Motor Brake Not Releasing. Brake Will Be Inspected by 790331 | | | 05000320/LER-1979-002-03, /03L-0 on 781226:inadequate Documentation of Surveillance of Calibrators.Caused by Personnel Error. Surveillance Performed & Proper Documentation Obtained | /03L-0 on 781226:inadequate Documentation of Surveillance of Calibrators.Caused by Personnel Error. Surveillance Performed & Proper Documentation Obtained | | | 05000320/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000320/LER-1979-003-03, /03L-0 on 790105:control Rod 6-12 Dropped Into Reactor Core,Quadrant Power Tilt Steady State Limit & Transient Limit Exceeded.Caused by Blown Fuse on B Phase | /03L-0 on 790105:control Rod 6-12 Dropped Into Reactor Core,Quadrant Power Tilt Steady State Limit & Transient Limit Exceeded.Caused by Blown Fuse on B Phase | | | 05000289/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000289/LER-1979-003-03, /03L-0 on 790217:during post-shutdown Operations, While Performing Emergency Sequence & Power Transfer Test, High Pressure Injection Pump MU-P-1C Tripped on Overload. Caused by Failed Lead Between Winding & Motor.Lead Repair | /03L-0 on 790217:during post-shutdown Operations, While Performing Emergency Sequence & Power Transfer Test, High Pressure Injection Pump MU-P-1C Tripped on Overload. Caused by Failed Lead Between Winding & Motor.Lead Repaired | | | 05000320/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000289/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000320/LER-1979-004-03, /03L-0 on 790105:control Room Indication & Operator Observation Disagreed Re Position of Bs-V-1B,due to Bent Valve Stem | /03L-0 on 790105:control Room Indication & Operator Observation Disagreed Re Position of Bs-V-1B,due to Bent Valve Stem | | | 05000289/LER-1979-004-03, /03L-0 on 790217:emergency Diesel Tripped on Overspeed During Emergency Loading & Power Transfer Test. Caused by Governor Not Shutting Off Fuel When Set Speed Reached.Maint Procedures Revised | /03L-0 on 790217:emergency Diesel Tripped on Overspeed During Emergency Loading & Power Transfer Test. Caused by Governor Not Shutting Off Fuel When Set Speed Reached.Maint Procedures Revised | | | 05000289/LER-1979-005-03, /03L-0 on 790225:during Leakage Surveillance on Decay Heat Removal Sys,Total Measured Leakage Exceeded Tech Specs.Caused by Leakage from Valve Packing Glands in Valves DH-V-15 A/B,DH-V-6A,DH-V-5A & BS-V-3B.Glands Adjusted | /03L-0 on 790225:during Leakage Surveillance on Decay Heat Removal Sys,Total Measured Leakage Exceeded Tech Specs.Caused by Leakage from Valve Packing Glands in Valves DH-V-15 A/B,DH-V-6A,DH-V-5A & BS-V-3B.Glands Adjusted | | | 05000320/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000289/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000320/LER-1979-005-03, /03L-0 on 790108:during Mode 1,leakage Reported Around DH-R-9B.Caused by Small Crack in Piping Weld Upstream of Valve,Due to Vibration | /03L-0 on 790108:during Mode 1,leakage Reported Around DH-R-9B.Caused by Small Crack in Piping Weld Upstream of Valve,Due to Vibration | | | 05000320/LER-1979-006-03, /03L-0 on 790103:surveillance Procedure 2304-W1 Had Not Been Performed on Schedule.Personnel Responsible Instructed to Assure Event Does Not Recur | /03L-0 on 790103:surveillance Procedure 2304-W1 Had Not Been Performed on Schedule.Personnel Responsible Instructed to Assure Event Does Not Recur | | | 05000320/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000289/LER-1979-006-03, /03L-0 on 790228:during Refueling Frequency Local Leak Rate Testing,Valve CA-V5B Did Not Fully Close.Caused by Bent Valve Stem Resulting in Binding in Packing Gland.Stem Was Straightened & Valve Satisfactorily Leak Tested | /03L-0 on 790228:during Refueling Frequency Local Leak Rate Testing,Valve CA-V5B Did Not Fully Close.Caused by Bent Valve Stem Resulting in Binding in Packing Gland.Stem Was Straightened & Valve Satisfactorily Leak Tested | | | 05000289/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000320/LER-1979-007-03, /03L-0 on 790126:while in Mode 5,travelling Water Screens Inoperable Due to Buildup of Debris Causing High Differential Level Across Idle Screen Sys | /03L-0 on 790126:while in Mode 5,travelling Water Screens Inoperable Due to Buildup of Debris Causing High Differential Level Across Idle Screen Sys | | | 05000320/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000320/LER-1979-008-03, /03L-0 on 790117:setpoints to Two Feedwater Line Rupture Detection Pressure Switches Found Outside Tech Spec Limits.Caused by Either Instrument Drift or Steam Leakage | /03L-0 on 790117:setpoints to Two Feedwater Line Rupture Detection Pressure Switches Found Outside Tech Spec Limits.Caused by Either Instrument Drift or Steam Leakage | | | 05000289/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000289/LER-1979-008-03, /03L-0 on 790310:during Refueling Frequency Local Leak Rate Test,Excessive Leakage Noted Across Valve AH-V1B. Caused by Loose Valve Seat Retaining Screws in Valve.Screws Tightened & Valve Tested Satisfactorily | /03L-0 on 790310:during Refueling Frequency Local Leak Rate Test,Excessive Leakage Noted Across Valve AH-V1B. Caused by Loose Valve Seat Retaining Screws in Valve.Screws Tightened & Valve Tested Satisfactorily | | | 05000320/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000289/LER-1979-009-03, /03L-0 on 790410:during Surveillance Testing on turbine-driven Emergency Feedpump,Steam Regulating Valve Found Closed.Caused by Maint Procedure Not Specifying Opening of Valve | /03L-0 on 790410:during Surveillance Testing on turbine-driven Emergency Feedpump,Steam Regulating Valve Found Closed.Caused by Maint Procedure Not Specifying Opening of Valve | | | 05000289/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000320/LER-1979-009-03, /03L-0 on 790130:surveillance Required by Tech Specs for Mode 5 Not Performed After Pumps Tagged Out.Caused by Lack of Clarity in Shutdown Procedure.Procedure Revised | /03L-0 on 790130:surveillance Required by Tech Specs for Mode 5 Not Performed After Pumps Tagged Out.Caused by Lack of Clarity in Shutdown Procedure.Procedure Revised | | | 05000320/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000320/LER-1979-010, Forwards LER 79-010/01T-0 | Forwards LER 79-010/01T-0 | | | 05000289/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000320/LER-1979-010-01, /01T-0:on 790214,during Mode 1,B Concentration in Boric Acid Mix Tank Exceeded Tech Spec Limit.Caused by Personnel Error | /01T-0:on 790214,during Mode 1,B Concentration in Boric Acid Mix Tank Exceeded Tech Spec Limit.Caused by Personnel Error | | | 05000289/LER-1979-010-03, /03L-0 on 790411:while in Hot Shutdown, Reassignment of Personnel to Unit 2 Prevented Surveillances Re Chemistry & Radiological Analysis at Proper Frequency. Missed Surveillances Subsequently Performed | /03L-0 on 790411:while in Hot Shutdown, Reassignment of Personnel to Unit 2 Prevented Surveillances Re Chemistry & Radiological Analysis at Proper Frequency. Missed Surveillances Subsequently Performed | | | 05000289/LER-1979-011-03, /03L-0 on 790405:leaks Noted in Spent Fuel Pool Cooling Sys Piping.Caused by Intergranular Stress Corrosion Cracking.Areas of Leakage Isolated;Stress Analyses Will Be Performed | /03L-0 on 790405:leaks Noted in Spent Fuel Pool Cooling Sys Piping.Caused by Intergranular Stress Corrosion Cracking.Areas of Leakage Isolated;Stress Analyses Will Be Performed | | | 05000289/LER-1979-011, Updates LER 79-011/03X-0,dtd 790516,re Abnormal Degradation of Spent Fuel Cooling Sys.Cracks in Valve SF-V17 Were Caused by Intergranular Stress Corrosion.Crack Sections Will Be Replaced w/304L,stainless Steel | Updates LER 79-011/03X-0,dtd 790516,re Abnormal Degradation of Spent Fuel Cooling Sys.Cracks in Valve SF-V17 Were Caused by Intergranular Stress Corrosion.Crack Sections Will Be Replaced w/304L,stainless Steel | | | 05000320/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000320/LER-1979-011-03, /03L-0 on 790217:diesel Generator DF-X-1B Output Power Fluctuated Until Reversed Power Caused It to Trip. Unable to Determine Definite Cause | /03L-0 on 790217:diesel Generator DF-X-1B Output Power Fluctuated Until Reversed Power Caused It to Trip. Unable to Determine Definite Cause | | | 05000320/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000320/LER-1979-012-03, /03L-0:on 790305,fire Barrier Seals Made of Firewall 50 Cracked,Spalled & Separated While in Mode 1, Making Seals Nonfunctional.Caused by Cracks Developing in Fire Barrier Penetration Seals.Continuous Fire Watch Begun | /03L-0:on 790305,fire Barrier Seals Made of Firewall 50 Cracked,Spalled & Separated While in Mode 1, Making Seals Nonfunctional.Caused by Cracks Developing in Fire Barrier Penetration Seals.Continuous Fire Watch Begun | | | 05000289/LER-1979-012-01, /01T-0 on 790618:relay 62x2B/RC1A Failed to Drop Out When Coil Was de-energized.Caused by Notch in Operating Rod.Of 48 Relays inspected,25 Notches Were Found & Removed | /01T-0 on 790618:relay 62x2B/RC1A Failed to Drop Out When Coil Was de-energized.Caused by Notch in Operating Rod.Of 48 Relays inspected,25 Notches Were Found & Removed | | | 05000289/LER-1979-012, Forwards LER 79-012/01T-0 | Forwards LER 79-012/01T-0 | | | 05000289/LER-1979-013, Forwards LER 79-013/01T-0 | Forwards LER 79-013/01T-0 | | | 05000289/LER-1979-013-01, /01T-0 on 790620:leakage Discovered on 10-inch Suction Piping from Borated Water Storage Tank Between Valves DH-V5A/B & MU-V14A/B.Caused by Residual Weld Stresses | /01T-0 on 790620:leakage Discovered on 10-inch Suction Piping from Borated Water Storage Tank Between Valves DH-V5A/B & MU-V14A/B.Caused by Residual Weld Stresses | | | 05000320/LER-1979-013, Has Been Cancelled | Has Been Cancelled | |
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