LER-1980-045, Forwards LER 80-045/03L-0 |
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| 2491980045R00 - NRC Website |
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5 Commonwea!AEdison Dresden Nuclear -r Station R.R. #1 Mbrris, Illinois 60450 Telephone 815/942-2920
- DJS LTR /181-25 James G *. Keppler, Regicmal Director January 11, 1980 Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Connnission 799 Roosevelt Road Glen Ellyn, IL 60137
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Reportable Occurrence Report f/80-45/03L..,.O,. Docket tf.050-249 is being submitted-to your office in accordance with Dresden Nuclear Power Station Technical Specification.6.6.B.2.(b),* conditions. leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting.condition for operation.
DJS/lg Enclosure Station Superintendent Dresden Nuclear Power Station cc:
Director of Inspection. & Enfo.rcement Director *of. Management. Information & *Program Control U.S. NRC, Document.Mgt.
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i1-111 LICENSEE EVENT REPORT CCNTROL-SLOCK: I.I 10.
(PLEASE PRINT OR TY.LL REQUIRED INFORMATION) 1 6
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LICENSEE CODE 14
- 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T I o I, I 7
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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@
I During normal operation, while performing LPCI valve operability surveillance, the Lill]
!]JI] I drywell spray header outboard isolation valve would not close from the control room.
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I The health and safety of the general public was not endangered because the inboard r;;-rci isolation valve was operable and maintained closed until the outboard valve was L...2....1.§_j.._I ___
[Q))J shut.
This is the first occurrence of this type for this valve.
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SYSTEM CODE Is IF I@
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CAUSE
CAUSE COMP.
CODE suscoDE COMPONENT CODE SU8CPDE
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- 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT
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LE A/RO LVENT YEAR REPORT NO.
CODE TYPE 0
REPORT I 8 I 0 I I. I I 01 41 51 I 0 I 3 I L!:.J I I NUMBER 21 22 23 24 26 27 28 29 30
- 31.
ACTION FUTURE EFFECT SHUTDOWN
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ATTACHMENT NPRD-4 PRIME COMP.
REVISION NO.
lQJ 32 COMPONENT MANUFACTURER TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :;us.
SUPPLIER L!J@W@ W@ LI I 01 01 OJ 01 L!!..I@
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33 34 35 36 37 40 41 42 43 I GI 01s I 01@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
44 47 The suspected cause of failure was a stuck plunger on the closing coil of the valve motor breaker.
The plunger was freed by moving the closing coil by hand.
The valve [ill]
was cycled several times while monitoring the coil.
No problems were noted.
In addi-IJJI1
._I _t_i_o_n_,_s_i_n_c_e_t_h_e_f_a_i_l_u_r_e_t_o_o_p_e_r.,a_t_e~,.,t_h_e_v_a_l_v_e_h_a_s_b_e_e_n_c_y_c_l_e_d_o_n __
th_r_e __ e_d_i._f_f_e_r_e_n_t ___ ___.
[)))) I occasions as part of the required surveillances.
No further action deemed necessary.
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9 FACILITY
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% POWER OTHER STATUS \\::::J DJII W I 1 I 0 I 0 l@I.... _ ___.N...._/..._A __
80 METHOD OF A
DISCOVERY DISCOVERY DESCRIPTION ~
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RELEASED OF RELEASE AMOUNT OF ACTIVITY ITEJ w @ W@I.... ___
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45 46 80 44 45 N/A LOCATION OF RELEASE@
80 PERSONNEL EXPOSURES
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NUMBER
(.:;::;\\TYPE r.;';:;\\ OES.CRIPTION.
ITl2J IO IO IO l~~\\31......... ________ N_/A ________________________________________ ___.
7 8
9 11 12 13 80 PERSONNEL INJURIES
NUMBER DESCRIPTION~
IJJIJ 1010 10 1@)~*------------N_IA ________________________________________ ___.
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 143' TYPE
DESCRIPTION
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10 so NRC USE ONLY PUBLICITY
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PART1(TITLE OF DEVIATION OCCURRED.
LPCI Valve 3-1501-27B Failure to Close 12-19-80 0105 DATE TIME I SYSTEM AFFECTED 1500 PlANl CONDITIONS TESTING LPCI Run 2512 832 CD CJ MODE PWR(MWTl LOAO(MWE)
YES NO
DESCRIPTION OF EVENT
During LPCI valve operability testing, the 3-1501-27B valve could not be closed_ from the control room.
U k DESCRIPTION Of CAUSE n nown at this time.
OTHER APPLICABLE INFORMATION The valve was subsequently closed, after moving the closing coil by hand.
EQUIPMENT OD YES FAILURE ONO OR NO.
N/A
- 10627 PART 2 I OPERATING ENGi NEERS COMMENTS Michael Wright RESPONSIBLE SUPERVISOR 12/20/80 DATE Following manual ac.tuation of the closing coil, the valve was successfully cycled three times from the control room.
The 3-1501-28B valve was maintained in the closed position until the
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.3.l-27B valve was closed.
SAFETY-TYPE OF DE'VIATION EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE'
REPORTABLE OCCURRENCE.
- PUBLIC INTEREST VIOLATION OCCURRENCE
. REPO'RT I NG
.WR ISSUED
~-** D 14 DAY D 10CFR21 D
. [!] 30 DAY NOT! Fl CATION 6.6.B.2.b
. REPORTABLE CCCURRENCE ACTION ITEM NO
- NUMBER D:- 80-45/031-0 24-HOUR NRC NOTIFICATION DTPH REGION I I I DATE TIME DTG'v1 REGION I I I & DOL CATE TIME RESPONSIBLE COMPANY* OFFICER INFORMED OF IOCFR21 CONQITIONS AND THEIR REPORT TO NBC REVIEW ANO COMPLETED ACCEPTANCE BY STATION REVIEW AS REQUIRED D"ATE RESOLUTION APPROVED ANO AUTHOR I ZED FOR 0 I STR I BUTI ON 8&~5176 10*77 (FORM IS*sz-~J D
D PROMPT ON-SI TE R. M. Rafi an Tl TLE Tl TLE PROMPT OFF-SI TE F. A. Palmer Tl TLE Tl TLE Tl TLE YES [i]
YES !TI NO D NO NOTIFICATION 12/19/80 DATE DATE NOTIFICATION 12/22/80 DATE DATE DATE 1_2/.20/80 DATE
' DATE D
0600 TIME TIME 10:08 TIME TIME TIME
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| 05000249/LER-1980-001-03, /03L-0:on 800116,loss of Sampling Point Automatic Advance for Drywell Oxygen Analyzer Noted During Normal Operation.Caused by Electrical Failure of Stepping Switch Motor Part 808376.Motor Replaced & Advance Restored | /03L-0:on 800116,loss of Sampling Point Automatic Advance for Drywell Oxygen Analyzer Noted During Normal Operation.Caused by Electrical Failure of Stepping Switch Motor Part 808376.Motor Replaced & Advance Restored | | | 05000237/LER-1980-001, /03L-0 for Dresden, Unit 2 Re While Performing Weekly Turbine Control Valve Exercising, the 1/2 Scram on RPS Channel a Received from the Closure of 3 Turbine Control Valve Would Not Reset | /03L-0 for Dresden, Unit 2 Re While Performing Weekly Turbine Control Valve Exercising, the 1/2 Scram on RPS Channel a Received from the Closure of 3 Turbine Control Valve Would Not Reset | | | 05000010/LER-1980-001-03, /03L-0:on 800303,capacity in Unit 1 Fire Pump Found to Be in Need of Updating in Order to Be Equal to Unit 2/3 Fire Pump.Commitment Made to NRC to Increase Capacity.New Fire Pump Will Be Installed | /03L-0:on 800303,capacity in Unit 1 Fire Pump Found to Be in Need of Updating in Order to Be Equal to Unit 2/3 Fire Pump.Commitment Made to NRC to Increase Capacity.New Fire Pump Will Be Installed | | | 05000010/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000237/LER-1980-002, /03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close | /03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close | | | 05000249/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000010/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000010/LER-1980-002-01, /01T-0:on 800405,while in Shutdown Mode W/Fuel Removed,Contaminated Demineralized Water Was Being Heated & Added to Primary Sys.Tube Leaks in Heat Exchanger Were Found Leaking Water Into River.Caused by Unloader Tube Failure | /01T-0:on 800405,while in Shutdown Mode W/Fuel Removed,Contaminated Demineralized Water Was Being Heated & Added to Primary Sys.Tube Leaks in Heat Exchanger Were Found Leaking Water Into River.Caused by Unloader Tube Failure | | | 05000249/LER-1980-002-03, /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause | /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause | | | 05000010/LER-1980-003-02, Has Been Cancelled | Has Been Cancelled | | | 05000249/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000249/LER-1980-004-03, /03L-0:on 800202,while Increasing Load by 2 Mwe Per Hour,Alarms Received in Control Room Indicating Failed Jet Pump.Jet Pump 13 Failed.Cause & Corrective Action Will Be Described in Supplemental Rept | /03L-0:on 800202,while Increasing Load by 2 Mwe Per Hour,Alarms Received in Control Room Indicating Failed Jet Pump.Jet Pump 13 Failed.Cause & Corrective Action Will Be Described in Supplemental Rept | | | 05000010/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000010/LER-1980-004-03, /03L-0:on 800724,during Outage,While Processing Water in Holdup tank,98-h Elapsed W/O Sampling.Caused by Personnel Failure to Follow Procedure for Sampling Radwaste Storage Tanks.Personnel Reinstructed | /03L-0:on 800724,during Outage,While Processing Water in Holdup tank,98-h Elapsed W/O Sampling.Caused by Personnel Failure to Follow Procedure for Sampling Radwaste Storage Tanks.Personnel Reinstructed | | | 05000249/LER-1980-005-01, /01T-0:on 800213,while in S/D Mode,Msiv Scram Limit Switches Were Checked & of 16 Limit Switches,Two Found to Have Setpoints Greater than 10%.Caused by Switch Out of Calibr.Limit Switches Readjusted | /01T-0:on 800213,while in S/D Mode,Msiv Scram Limit Switches Were Checked & of 16 Limit Switches,Two Found to Have Setpoints Greater than 10%.Caused by Switch Out of Calibr.Limit Switches Readjusted | | | 05000249/LER-1980-005, Forwards LER 80-005/01T-0 | Forwards LER 80-005/01T-0 | | | 05000249/LER-1980-006-03, /03L-0:on 800215,during Local Leak Rate Test Performed on a Feedwater Inboard Check Valve 3-220-58A Measured Leakage Exceeded Tech Specs.Caused by Worn Seat/ Disc Assembly Pins | /03L-0:on 800215,during Local Leak Rate Test Performed on a Feedwater Inboard Check Valve 3-220-58A Measured Leakage Exceeded Tech Specs.Caused by Worn Seat/ Disc Assembly Pins | | | 05000249/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000249/LER-1980-007-03, /03L-0:on 800209,during Local Leak Rate Test of Containment Vent Line,Measured Leakage Exceeded Tech Specs. Investigation Showed Valve AO-3-1601-23 Leaking Through. Caused by Normal Expected Wear of Rubber Seats | /03L-0:on 800209,during Local Leak Rate Test of Containment Vent Line,Measured Leakage Exceeded Tech Specs. Investigation Showed Valve AO-3-1601-23 Leaking Through. Caused by Normal Expected Wear of Rubber Seats | | | 05000249/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000249/LER-1980-008-03, /03L-0:on 800307,during Refueling Outage While Performing Temp Switch Calibr Surveillance,Three Temp Switches Failed to Trip Per Specs.Caused by Drift,Excessive Gap Between Actuator & Switch Plunger or Dirty Contacts | /03L-0:on 800307,during Refueling Outage While Performing Temp Switch Calibr Surveillance,Three Temp Switches Failed to Trip Per Specs.Caused by Drift,Excessive Gap Between Actuator & Switch Plunger or Dirty Contacts | | | 05000237/LER-1980-008, /03L-0 for Dresden, Unit 2 Re Equipment Operator Discovered Level in the 2/3 Diesel Generator Coolant Water Expansion Head Tank Overflowing Thru the Vent Line | /03L-0 for Dresden, Unit 2 Re Equipment Operator Discovered Level in the 2/3 Diesel Generator Coolant Water Expansion Head Tank Overflowing Thru the Vent Line | | | 05000249/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000249/LER-1980-009-03, /03L-0:on 800306,during Refueling Outage,While Performing LPCI Logic Tests,Injection Valve Mo 3-1501-22A Failed to Open.Caused by Loose Wire on Terminal Block in MCC-38-7 Due to Stripped Brass Screw | /03L-0:on 800306,during Refueling Outage,While Performing LPCI Logic Tests,Injection Valve Mo 3-1501-22A Failed to Open.Caused by Loose Wire on Terminal Block in MCC-38-7 Due to Stripped Brass Screw | | | 05000249/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000249/LER-1980-010, /03L-0 for Dresden Unit 3 Regarding Relief Valves Rv 1105A and 1105B Actuating at 1525 and 1520 PSIG Respectively | /03L-0 for Dresden Unit 3 Regarding Relief Valves Rv 1105A and 1105B Actuating at 1525 and 1520 PSIG Respectively | | | 05000249/LER-1980-011-03, /03L-0:on 800305,while Conducting Steam Line Area Temp Switch Calibr Surveillance,Temp Switch TS 3-261-17B Tripped Above Tech Specs.Caused by Dirt Deposits on Switch Actuation Plunger.Switch Cleaned,Adjusted & Tested | /03L-0:on 800305,while Conducting Steam Line Area Temp Switch Calibr Surveillance,Temp Switch TS 3-261-17B Tripped Above Tech Specs.Caused by Dirt Deposits on Switch Actuation Plunger.Switch Cleaned,Adjusted & Tested | | | 05000249/LER-1980-011, /03L-0 for Dresden Unit 3 Regarding Temperature Switch TS 3-261-17B Tripping at 203.1 Degrees Fahrenheit Which Is Above the Technical Specification | /03L-0 for Dresden Unit 3 Regarding Temperature Switch TS 3-261-17B Tripping at 203.1 Degrees Fahrenheit Which Is Above the Technical Specification | | | 05000249/LER-1980-012, /03L-0 for Dresden Unit 3 Regarding Fuel Pool Area ARM Channels a and B Tripping at Levels Exceeding the Technical Specification | /03L-0 for Dresden Unit 3 Regarding Fuel Pool Area ARM Channels a and B Tripping at Levels Exceeding the Technical Specification | | | 05000249/LER-1980-013, /03L-0 for Dresden Unit 3 Regarding B Feedwater Outboard Check Valve 3-220-62B Leakage Exceeding Limit for a Single Isolation Valve | /03L-0 for Dresden Unit 3 Regarding B Feedwater Outboard Check Valve 3-220-62B Leakage Exceeding Limit for a Single Isolation Valve | | | 05000249/LER-1980-015, /01T-0 for Dresden Unit 3 Regarding Discovery of Reactor Water Cleanup Mechanical Snubber Fully Retracted | /01T-0 for Dresden Unit 3 Regarding Discovery of Reactor Water Cleanup Mechanical Snubber Fully Retracted | | | 05000237/LER-1980-015, /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance | /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance | | | 05000237/LER-1980-016, /01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line | /01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line | | | 05000237/LER-1980-017, /03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close | /03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close | | | 05000249/LER-1980-017, /03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start | /03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start | | | 05000249/LER-1980-019-03, /03L-0:on 800420,during Switch Calibr Surveillance,Target Rock Relief Valve Press Switch PS-3-203-3A Tripped Below Tech Specs Limit.Caused by Setpoint Drift.Switch Readjusted within Tech Specs Limit | /03L-0:on 800420,during Switch Calibr Surveillance,Target Rock Relief Valve Press Switch PS-3-203-3A Tripped Below Tech Specs Limit.Caused by Setpoint Drift.Switch Readjusted within Tech Specs Limit | | | 05000249/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000249/LER-1980-021, /01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operabil | /01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operability Surveilla | | | 05000249/LER-1980-021-01, /01T-0:on 800425,combinations of 3A Target Rock Valve & 3B,3C & 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure.Caused by Improper Bolted Air Operator,Pilot Valve Problems & Jammed Cutout Switch | /01T-0:on 800425,combinations of 3A Target Rock Valve & 3B,3C & 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure.Caused by Improper Bolted Air Operator,Pilot Valve Problems & Jammed Cutout Switch | | | 05000237/LER-1980-022, /03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125 | /03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125 | | | 05000237/LER-1980-023, /03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches | /03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches | | | 05000237/LER-1980-024, /03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d | /03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d | | | 05000237/LER-1980-025, /03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 | /03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 | | | 05000237/LER-1980-027, /03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator | /03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator | | | 05000249/LER-1980-028, Forwards LER 80-028/03L-0 | Forwards LER 80-028/03L-0 | | | 05000249/LER-1980-028-03, /03L-0:on 800718,during Setpoint Surveillance, Solenoid Valve for Torus to Reactor Bldg Vacuum Breaker 3-1601-20A Determined Inoperative,Preventing Valve from Opening.Caused by Mechanical Failure.Valve Replaced | /03L-0:on 800718,during Setpoint Surveillance, Solenoid Valve for Torus to Reactor Bldg Vacuum Breaker 3-1601-20A Determined Inoperative,Preventing Valve from Opening.Caused by Mechanical Failure.Valve Replaced | | | 05000249/LER-1980-030, /03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds | /03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds | | | 05000249/LER-1980-032, /03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block | /03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block | | | 05000249/LER-1980-033, Forwards LER 80-033/03L-0 | Forwards LER 80-033/03L-0 | | | 05000249/LER-1980-033-03, /03L-0:on 800724,during Normal operations,1/4-inch through-wall Leak Discovered in 3A Component Cooling Svc Water Pump Casing.Caused by Casting Hole on Bottom of Casing.Pump Removed & Hole Plugged | /03L-0:on 800724,during Normal operations,1/4-inch through-wall Leak Discovered in 3A Component Cooling Svc Water Pump Casing.Caused by Casting Hole on Bottom of Casing.Pump Removed & Hole Plugged | |
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