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
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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
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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
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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.
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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
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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
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
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
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
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
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
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
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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
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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
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
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
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
2024-01-19
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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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