LER 76-064-00 for Dresden, Unit 2 Regarding the Failure of the Unit-2 Diesel Generator to Start Twice During Routine Surveillance| ML17252B485 |
| Person / Time |
|---|
| Site: |
Dresden  |
|---|
| Issue date: |
11/26/1976 |
|---|
| From: |
Commonwealth Edison Co |
|---|
| To: |
NRC/RGN-III |
|---|
| References |
|---|
| LER 76-064-00 |
| Download: ML17252B485 (2) |
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|---|
Category:Licensee Event Report (LER)
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05000237/LER-2016-0042017-01-0909 January 2017
Reactor Building Differential Pressure Less than Technical Specification Requirement, LER 16-004-00 for Dresden Nuclear Power Station, Unit 2, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement
05000249/LER-2016-0012016-08-25025 August 2016
Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire, LER 16-001-00 for Dresden Nuclear Power Station Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire
05000237/LER-2016-0022016-07-15015 July 2016
Unit 2 HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability, LER 16-002-00 for Dresden Nuclear Power Station, Unit 2 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability
05000237/LER-2016-0012016-04-0808 April 2016
Secondary Containment Differential Pressure Transient, LER 16-001-00 for Dresden Nuclear Power Station, Unit 2 and 3 Regarding Secondary Containment Differential Pressure Transient
05000249/LER-2015-0012016-01-22022 January 2016
Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value, LER 15-001-01, Dresden, Unit 3 Main Steam Line Flow Switched Found Outside Tech Spec Allowed Value
ML1015505692009-07-24024 July 2009
Letter LS-AA-1 25-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping for Dresden Units 2 and 3.
ML0602404072004-05-0505 May 2004
Final Precursor Analysis - Dresden Unit 3 - Unit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3
ML0234501722002-12-0202 December 2002
LER 89-029-05, Dresden Unit 2, Elevated HPCI Discharge Piping Temperature Due to Reactor Feedwater System Back Leakage
ML17252B5391981-06-10010 June 1981
LER 81-034/03L-0 for Dresden, Unit 2 Re J-3 CRD Was Tested for Overtravel. the Overtravel Alarm Came Up and Rod Position Indication Was Lost
ML17252B5411981-06-0808 June 1981
LER 81-030/01T-0 for Dresden, Unit 2 Re Operator Noticed the HPCI Steam Line Was Cold and Filled with Water. the HPCI System Was Declared Inoperable
ML17252B5401981-06-0505 June 1981
LER 81-024/03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue
ML17252B5271981-06-0303 June 1981
LER 81-023/03L-0 for Dresden, Unit 2 Re While Running HPCI Pump Test, the Operator Observed Torus Wide Range Level Instrument Reading 0 Inches and Narrow Range Level Instrument Reading, About - 2 Inches and Oscillating
ML17252B5281981-04-14014 April 1981
LER 81-015/03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1
ML17252B5291981-03-23023 March 1981
LER 81-011-03L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered Safe
ML17252B5301981-02-20020 February 1981
LER 81-080/031-0 for Dresden, Unit 2 Re Abnormal Degradation of Systems Other than Those Specified in Item B.1.e Above Designed to Contain Radioactive Material Resulting from the Fission Process
ML17252B5321981-02-17017 February 1981
LER 81-070/03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip
ML17252B5331981-02-0202 February 1981
LER 81-020/03L-0 for Dresden, Unit 2 Re During Refueling Outage LPCI Test Spray Valve Failed to Shut Electrically, One Set of Thermal Contacts Would Not Reset
ML17252B5341981-01-23023 January 1981
LER 80-049/03L-0 for Dresden, Unit 2 Re at Completion of Secondary Containment Leak Rate Test the Reactor Building Ventilation Isolation Valve 2A-5742 Would Not Open
ML17252B5351981-01-23023 January 1981
LER 80-050/03L-0 for Dresden, Unit 2 Re the 1501-62D Pressure Switch Actuated at 44.2 Inches of Water Increasing, Tech. Spec. Limit Is Less than or Equal to 41.6 Inches of Water Increasing
ML17252B5371980-12-30030 December 1980
LER 80-046-00 for Dresden 2 Regarding a Failure to Receive CRD Volume During a Reactor Scram
ML17252B5361980-12-29029 December 1980
LER 80-046/03L-0 for Dresden, Unit 2 Re Conditions Leading to on Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation
ML17252B5381980-12-0303 December 1980
LER 80-043/03L-0 for Dresden, Unit 2 Re Surveillance Testing of the Condenser Low Vacuum Switches, Pressure Switch 2-503D Was Found to Have a Trip Point of 22.85 Inches Hg
ML17252B5421980-11-12012 November 1980
LER 80-042/03L-0 for Dresden, Units 2 and 3 Re That Technical Staff Personnel Revealed That the Ultrasonic Testing of the Scram Discharge Volume Was Not Performed During the 1500-2300 Shift
ML17252B5431980-11-12012 November 1980
LER 80-041/03L-0 for Dresden, Unit 2 Re Reactor Building Vent and Refueling Floor Rad Monitor Surveillance (DCP 2007-12) Was Performed
ML17252B1841980-10-31031 October 1980
LER 80-40/01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open
ML17252B5441980-10-29029 October 1980
LER 80-039/03X-1 for Dresden, Unit 2 Re HPCI Inboard Steam Supply Valve Opened and Had a Dual Light Indication
ML17252B5451980-10-23023 October 1980
LER 79-017-01X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety
ML17252B5461980-10-0808 October 1980
LER 80-016/01T-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
ML17252B5471980-10-0707 October 1980
LER 80-036/03L-0 for Dresden, Unit 2 Re Discovery That the Six Month Functional Test Required by Tech. Spec. 4.12.A.1 of the Cardox System Heat Detectors Was Not Performed within the Allowable Surveillance Interval
ML17252B5481980-10-0101 October 1980
LER 80-033/03L-0 for Dresden, Unit 2 Re the Frequency of Water Addition to the Torus Increased. Leak Rate Tests Indicated a Leak in the 2B LPCI Heat Exchanger
ML17252B1861980-08-22022 August 1980
LER 80-032/03L-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
ML17252B5501980-08-19019 August 1980
LER 80-027/03L-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
ML17252B5161980-08-14014 August 1980
LER 80-024/03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d
ML17252B1881980-08-0404 August 1980
LER 80-030/03L-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
ML17252B1911980-06-13013 June 1980
LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches
ML17252B1901980-06-13013 June 1980
LER 80-023/03L-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
ML17252B1921980-06-10010 June 1980
LER 80-025/03L-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
ML17252B5521980-06-0505 June 1980
LER 80-017/03L-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
ML17252B1931980-06-0303 June 1980
LER 80-002/03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close
ML17252B5531980-05-27027 May 1980
LER 80-015/03L-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
ML17252B1941980-05-27027 May 1980
LER 80-022/03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125
ML17252B1951980-05-0808 May 1980
LER 80-021/01T-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 Operability
ML17252B1961980-04-29029 April 1980
LER 80-017/03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start
2020-05-14
[Table view] |
Text
.ICENSEE *EVENT REPORT e CONTROL BLOCK: I I I I *1 I 6"*'*
I [PLEASE PRINT ALL REQUIRED INf=ORMATION) 1 LICENSEE LICENSE EVENT*
NAME LICENSE NUMBER TYPE TYPE
@El II I .LI DIR Is I~ I 10101~10101010101-10101 141 I It I ( 111 10131 7 8 9 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE. SOURCE DOCKET NUMBER EVENT DATE REPORT DATE .
@El CON'T I I I Lbd lhJ 101s101~101113171 11 Io I :ll q 1110 I I f I t 12 I GI 71 ~I 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION
@Ifil I DURING: ROUTINE SURV£1LJ.__ANCE TEST1tJG-, THE UNrl-2 'DIES~L 6£ NE (J.ATOR.. I 7 8 9 . 80 IDl31 I FAILED TO START TWLC£. THE F.t=.DUNDANT. UNtr 113 DJ£5£L GtlVER.ATOf?.. I 7 8 9 80 lol41 I WAS. f("1m£L>IATELY VeRtfl~l> To 9£ OPERABJ..,£. I 7 89 .! ) 80
~ I (so-"J.3?fl°t~-b4 I 7 8 9 80 7
m 8 9 PR:ME 80 SYSTEM. CAUSE COMPONENT COMPONENT CODE CODE . COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION
@El 1£1.E~ I I.SJ 1£1NIGI t INIEI ~J 43 '.
1w121q101 44 ,. 47 lltJ 7 8 9 10 11 12 17 48 CAUSE .DESCRIPTION
@I@ I IHG. FAILURE WAS cAU56D BY A MAl-flJNC.:noNJNG- 5HUTDowtJ so1..EJJ01D oAJ I 7 8 9 80.
lol918 9ITHE' 'I>J£SEL GOVERNOR.
7 TH£ SHtJ[DouJN s91.,EN01D PWNGER Wf\.S t=OVND TV I
80 IT@l 8£ OUT OF' AD-:JV$TMENT.
7 . 9'9*
WH( RGVENIED TH£* SHUTDOWN 'ROD FRDY>'I T3EING-(SEE ~TTFIG/4£D S 80 FACILITY METHOD OF STATUS % POWER OTHCR STATUS DISCOVERY DISCOVERY DESCRIPTION EE] lfil 10111s1 NA ~ NA.
7 .8 9 10 . 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT
. 7 rn 8 RELEASED
~
9 OF RELEASE lEj .......
.10 11*
AMOUNT OF ACTIVITY 1 _____......N_._.lt_._ ____.
44 45 NA
- . LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER . TYPE DESCRIPTION
'IT§ 10.10101 ~
7 8-9 11 12 13 80 PERS'ONNEL INJURIES NUMBER DESCRIPTION EE8 9101010111 7 12 80 OFFSITE CONSEQUENCES
.[ili] NA 7 8 9 80 LOSS OR .DAMAGE TO FACILITY TYPE DESCRIPTION
~- .gj '.Ii 7 8 9 10 80 PUBLICITY
[ill] ;VA 7 8 9 BO ADDITIONAL FACTORS
~ JVA 80 7 8 9
[ilil . 80 7 8 9 NAME: \[, B : frlARTl N PHONE: EXT: 91 I GPO 081
'"' .* - 4 CAUSE DESCRIPTION (Continued) picked up. The shutdown solenoid .consequently remained de-energized, pre-cluding the start-up of ihe diesel.
As a result of a similar failure of the Unit-3 diesel in December, 197.S, (R.O. report no. 50-249/1975-47), a maintenance procedure was revised to ensure that the tightneS§l *of the shutdown rod lo.cknut was checked during each six-month inspection. InWJ~aer to check the tightness of the locknut, the shutd,own latch knob must be removed. It has. now . been determined that tpe removal of the latch knob will disturb a sets'~1rew adjustment, which in turn may allow the
- shutdown rod to vibrate out ofadjustment. The Unit-2 failure is believed to*
be directly r~lated to the procedure change described .above. The Unit-3 diesel failure in 1975, the only other incident of this type, ~s considered to have been an.isolated occurrence.
The shutdown soienoid was inspected and readjusted by a vendor representa-
- tive, *and the Unit-.2 diesel was successfully tested and* returned to service.
- As soo~ as practicable, the Unit 2_/3 and Unit-3 diesel governor shutdown solenoids will .be inspected and, -as necessai-y, readjusted by vendor personnel. The above-mentioned iocknut tightness check has been deleted from the six-month inspection procedure to ensure that the shutdown solenoid adjustll_lent r~ains unchanged.
Proper adjustment of the solenoid by means of the existing locknuts and set-
- screws will preclude failures resulting from operational vibration. The s.olenoid is a "de-energize-tci,~.shutdown" type as used on model UG-8 governors manufacture.a by the Woodward Governor Co.
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