LER-1980-007, /01T-0:on 800407,during Maint on Control Room Ventilation Sys,Discovered Leakage Defects Through Shaft of Fan V-36.Fresh Air Damper D-1 Would Not Close.Caused by Inadequate pre-operational Testing of Ventilation Sys |
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text
PALISADES PLANT NRC FORM 366 (7-77)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: j
) G)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
[IT2J I M I I I p I A IL I I 101 0 I 0 I-I 0 I 0 I 0 I 0 I 0 I - 10 I 0 101 4 j l I 1 11 I 1 101 I I 0 7
B 9
LICENSEE CODE 14
~5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T filTI 7
8
=;~~~~ l1._1© I o I 5 I o I o I o I 2 I 5 I 5 101 o I 4 I o 17 I 8 I o I© lo I 4 I 2 11 I s I o I CV 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @
I During maintenance on the control room ventilation system, two defects
((ill I which would have permitted large inleakage of contamination into the
~
I control room under accident conditions were discovered.
The defects were CQJIJ I large leakage through the shaft of fan V-36 and a fresh air damper (D-1)
!Im I which won1 a not f1111;,ir cl ase As a result, during an accident with high
[£]2J I airborne activity outside containment, the control room may not have been ITJ)) I habit able.
Reportable per T*. S. 6. 9. 2. a. 9.
I 7
B 9 80 SYSTEM
CAUSE
CAUSE CODE CODE SUBCOOE COMPONENT CODE ETIJ Is !GI@ lli.J@ W@ lz lzlz lz lzl zl@
7 8
9 10 11 12 13 1B SEQUENTIAL OCCURRENCE REPORT NO.
CODE l=.J 1010111
~ 10111 23 24 26 27 28 29
~
LERIRO CVENTYEAR
\\}..:/ REPORT
~ 10 I NUMBER 21 22 COMP.
SUBCOOE
~@
19 REPORT TYPE l!J 30 VALVE SUBCODE
&J@
20 l:::J 31 PRIME COMP.
REVISION NO.
~
32 COMPONENT ACTION FUTURE EFFECT SHUTDOWN r:;:::;..
ATTACHMENT NPRD-4 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM $UB.
SUPPLIER MANUFACTURER W@~@ W@ W I 010 I 01 01 L.!J@
~@
33 34 35 36 3 7 40 41 42 LU I z I 919 191@
CAUSE DESCRIPTION AND CORR EC rive ACTIONS @
43 44 47 [J]I] I The initial pre-op testing of the control room vent system was apparently OJI] I inadequate.
The defects have been corrected.
ITDJ IJTIJ o:m 7
8 9
FACILITY
STATUS
.% POWER OTHER STATUS ~
EE LQJ@ I 0 JO I 0 l@.__IN_A ____ _
8 9
10 12 13 44 ACTIVITY CONTENT Qi RELEASED OF RELEASE AMOUNT OF ACTIVITY ~
l2El Ul@ W@.__I _N_A ______
7 8
9 10 11 44 PERSONNEL EXPOSURES
(.;;::\\
METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32
~~!Discovered during mainten nee 45 46 NA LOCATIO.N OF RELEASE @
45 80 80 60 NUMBER
~TYPE
DESCRIPTION
UI?.J I al o lo k~W-~--------------------------'
8 9
11 12 13 PERSONNEL INJURIES
(,":;\\
NUMBER DESCRIPTION~
BO [iliJ 01 0 10 I@ NA 8 9.
11 -----------------------------------B~O LOSS O< OR DAMAGE TO FACILITY f4:l\\
TYPE
DESCRIPTION
'\\:.::)
EITJ L_ZJ@
NA
. *7' B
9 1""0---------------------------------------B-'O PUBLICITY Cc\\
ISSUED(,:;\\ DESCRIPTION~
NRC USE ON Ly [ill] LIJ6~=NA=-=--------'----------------J I I I I I I *I I I I I I I 7
B 9
10 68 69 80
consumers Power company General Offices: 212 West Mlcfilgan Avenue, Jackson, Michigan 49201 * (517) 788-0550 April 21, 1980 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 80-006 - PURGE VALVE T-RING AIR SUPPLIES On the reverse side is Licensee Event Report 80-006 which is reportable under Technical Specification 6.9.2.B.4.
David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Palisades APR 2 3 1980
PALISADES PLANT NRC FORM366 l7-n1 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I IQ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
[B:!J I Ml I Ip I A IL 11 101 0 I 0 I - I 0 I 0 I 0 10 I 0 I - 10 I 0 1014 11 11 111 i 101 I J © 7
8 II LICENSEE CODE 14
,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [BI]
7 8
~~~~~~ ~I o I 5 I o I o I o I 2 I 5 I 5 K?)l l I 111 I o I 7 I 9 @I o 14 I 2 11 I 8 I 0 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I During routine surveillance of containment purge valves, it was found that!
the redundant T-rjng air supplies for the 12-incb and 48-incb purge valves!
~
had leakage in excess of acceptance criteria.
Normal air supply was [Q))J operable.
Condition classified reportable under TS 6.9.2.B.4 on 3-21-80.
l1TIJ
~
((ill 7
B 9 SYSTEM
CAUSE
CAUSE CODE CODE SUBCODE COMPONENT CODE IITIJ ISIDI@ ~@ ~@ !V!AIL1V1E1X1@
7 B
9 10 11 12 13 18 SEOUENTIAL OCCUR REN CE REPORT NO.
COOE 1010161 10131 23 2*
26 27 28 29 t::::..
LE R /RO LVENT YEAR
\\!:.,/ REPORT I 8 I 0 I NUMBER 21 22 COMP.
VALVE SUB CODE SUBCODE w w@
19 20 REPORT TYPE L!:.J 30 l=l 31 PRIME COMP.
REVISION NO.
LQJ 32 COMPONENT so TAKEN ACTIOll/
ON PLANT METHOD HOURS 22 SUBMITTED ACTION FUTURE EFFECT SHUTDOWN
~
ATTACHMENT NPRO-<l FORM SUB.
SUPPLIER MANUFACTURER lEJ@LBJ@
lz.J@
~ I o I o I o I I L!U@
33 34 35 36 37 40 41 l.IJ§ W IF 11 I 215 I@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
42 43 47
[)))) I Leaks were primarily through fittings and valve packings.
Replaceinent [II3J of CV-1806 and CV-1807 with blank flanges has been completed.
Repairs [JJ))
to T-ring air supplies to CV-1812 and 1814 will be completed prior to ITTIJ I start-up.
IIill 7
8 9
OTHERSTATUS @
FACILITY STATUS
% POWER EE W@ la I a I al@l~N
.... A ____
~
METHOD OF A
DISCOVERY DISCOVERY DESCRIPTION 6 LBJ@! Rlral1rn+ion of Test Res111ts 80 8
9 10 12 13 44 ACTIVITY CONTENT C,.
45*
46 80 RE LEASED OF RELEASE AMOUNT OF ACTIVITY ~
~
LzJ@ lzj@.._I _,N=A.___ _____
7 8
9 10 11 LOCATION OF RELEASE @
NA 45 80 PERSONNEL EXPOSURES r:;;::;..
NUMBER
~TYPE
DESCRIPTION
[!TI] I o I ol o llz.j@..___-=N=A ____________________
7 B
9 11 12 13 PERSONNEL INJURIES f,;';\\
80 NUMBER DESCRIPTION~
~
lol olol@)......_ ___
__._,i..c..__ ____________________
~
7 8
9 11 12 LOSS Q< OR DAMAGE TO FACILITY '43' TYPE
DESCRIPTION
~
BO NA
~W@
7 8
9
~10----------------------~--~~~~~~------~~~~~~~~~~~~~~~~~---'80 PUBLICITY C\\
ISSUED(.";\\ DESCRIPTION~
~
LN.J~~~~~~~~--'-'-'=---~~~~~~~~~~~~~~ I I I I I I I I I I I I I NRC USE ONLY B
II 10 68 69 80 I'
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| 05000255/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000255/LER-1980-001-01, /01T-0:on 800109,pipe & Pipe Support Stress Analyses Per IE Bulletin 79-14 Identified Lines Not Meeting FSAR Criteria for SSE or Obe.Apparently Caused by Differences in Design Documents & as-built Conditions | /01T-0:on 800109,pipe & Pipe Support Stress Analyses Per IE Bulletin 79-14 Identified Lines Not Meeting FSAR Criteria for SSE or Obe.Apparently Caused by Differences in Design Documents & as-built Conditions | | | 05000255/LER-1980-002-03, /03L-0:on 791023,during Routine Testing of Hydraulic Snubbers,Snubber S-6,located on Main Steam Line, Failed to Meet Test Acceptance Criteria.Caused by Loose Accumulator Oil Fill Fitting.Snubber Replaced | /03L-0:on 791023,during Routine Testing of Hydraulic Snubbers,Snubber S-6,located on Main Steam Line, Failed to Meet Test Acceptance Criteria.Caused by Loose Accumulator Oil Fill Fitting.Snubber Replaced | | | 05000255/LER-1980-002, Notifies That Current Main Steam Line Break Analysis Requested in NRC Cannot Be Completed Until Containment Spray Problem Identified in LER 80-002,is Resolved | Notifies That Current Main Steam Line Break Analysis Requested in NRC Cannot Be Completed Until Containment Spray Problem Identified in LER 80-002,is Resolved | | | 05000255/LER-1980-003-01, During Evaluation of SEP Topic VI-3,incorrect Assumptions for Initiation of Containment Spray Were Determined to Have Resulted in Lower Predicted Peak Pressures.Reanalysis Corrected Calculations | During Evaluation of SEP Topic VI-3,incorrect Assumptions for Initiation of Containment Spray Were Determined to Have Resulted in Lower Predicted Peak Pressures.Reanalysis Corrected Calculations | | | 05000255/LER-1980-003, Forwards Revised Page 3-36 to Basis of Tech Spec Section 3.4 Re Containment Cooling,Submitted in 861020 Change Request.Error in Original Submittal Resulted from LER 80-003 Re Description of Main Steam Line Break Results | Forwards Revised Page 3-36 to Basis of Tech Spec Section 3.4 Re Containment Cooling,Submitted in 861020 Change Request.Error in Original Submittal Resulted from LER 80-003 Re Description of Main Steam Line Break Results | | | 05000255/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000255/LER-1980-004-01, /01T-0:on 800327,during Review of Tech Spec Surveillance Procedures,Discovered Procedure MO-19 Requiring Isolation of Both Containment Spray Headers During Test Violated.Cause Not Stated.Procedure Rewritten | /01T-0:on 800327,during Review of Tech Spec Surveillance Procedures,Discovered Procedure MO-19 Requiring Isolation of Both Containment Spray Headers During Test Violated.Cause Not Stated.Procedure Rewritten | | | 05000255/LER-1980-005-01, /01T-0:on 800327,during Review of Tech Spec Surveillance Procedures,Discovered That Procedures QO-2 & MO-23 Require Stroking Sirw Tank Outlet Valves.Amend to OL or Clarification of Tech Spec Requirements Will Be Sought | /01T-0:on 800327,during Review of Tech Spec Surveillance Procedures,Discovered That Procedures QO-2 & MO-23 Require Stroking Sirw Tank Outlet Valves.Amend to OL or Clarification of Tech Spec Requirements Will Be Sought | | | 05000255/LER-1980-005, Forwards LER 80-005/01T-0 | Forwards LER 80-005/01T-0 | | | 05000255/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000255/LER-1980-006-03, Discovered That T-ring Air Supplies for 12-inch & 48-inch Purge Valves Had Leakage in Excess of Acceptance Criteria.Caused by Poor Fittings & Packings | Discovered That T-ring Air Supplies for 12-inch & 48-inch Purge Valves Had Leakage in Excess of Acceptance Criteria.Caused by Poor Fittings & Packings | | | 05000255/LER-1980-007-01, /01T-0:on 800407,during Maint on Control Room Ventilation Sys,Discovered Leakage Defects Through Shaft of Fan V-36.Fresh Air Damper D-1 Would Not Close.Caused by Inadequate pre-operational Testing of Ventilation Sys | /01T-0:on 800407,during Maint on Control Room Ventilation Sys,Discovered Leakage Defects Through Shaft of Fan V-36.Fresh Air Damper D-1 Would Not Close.Caused by Inadequate pre-operational Testing of Ventilation Sys | | | 05000255/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000255/LER-1980-008, Forwards Updated LER 80-008/01X-1 | Forwards Updated LER 80-008/01X-1 | | | 05000255/LER-1980-008-01, Test Results of Type C Containment Leak Tests Indicated Local Leakage in Excess of Tech Specs.Caused by Deterioration of Valve Internals | Test Results of Type C Containment Leak Tests Indicated Local Leakage in Excess of Tech Specs.Caused by Deterioration of Valve Internals | | | 05000255/LER-1980-009-01, /01T-0:on 800424,during Walkdowns of safety- Related Sys Conducted to Verify P&ID Accuracy,Ventilation Supply Damper CV-1812 to West Safeguards Equipment Room Could Not Be Located.Cause Unknown | /01T-0:on 800424,during Walkdowns of safety- Related Sys Conducted to Verify P&ID Accuracy,Ventilation Supply Damper CV-1812 to West Safeguards Equipment Room Could Not Be Located.Cause Unknown | | | 05000255/LER-1980-010-01, /01T-0:on 800326,during Calibr of Sirw Tank Low Level Switches,Reactor Analysis & Safety Setpoint Were Determined to Have Exceeded Tech Specs Limit.Caused by Error in Acceptance Criteria.Reportability Determined 800428 | /01T-0:on 800326,during Calibr of Sirw Tank Low Level Switches,Reactor Analysis & Safety Setpoint Were Determined to Have Exceeded Tech Specs Limit.Caused by Error in Acceptance Criteria.Reportability Determined 800428 | | | 05000255/LER-1980-011-03, /03L-0:on 800416,following Mods to Power Operated Relief Valve Supplies,Valves Were Declared Operable Before Administrative Reviews Were Completed.Caused by Misunderstanding of Review Requirements | /03L-0:on 800416,following Mods to Power Operated Relief Valve Supplies,Valves Were Declared Operable Before Administrative Reviews Were Completed.Caused by Misunderstanding of Review Requirements | | | 05000255/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000255/LER-1980-012, Licensee Event Report 80-012 Regarding Bottom Half of the Barrier for Fire Penetration HO-12 Was Missing During Inspection of Fire Barriers | Licensee Event Report 80-012 Regarding Bottom Half of the Barrier for Fire Penetration HO-12 Was Missing During Inspection of Fire Barriers | | | 05000255/LER-1980-012-03, /03L-0:on 800417,during Insp of Fire Barriers, Discovered That Bottom Half of Barrier for Fire Penetration Was Missing.Cause Undetermined.Barrier Restored to Operable Status | /03L-0:on 800417,during Insp of Fire Barriers, Discovered That Bottom Half of Barrier for Fire Penetration Was Missing.Cause Undetermined.Barrier Restored to Operable Status | | | 05000255/LER-1980-013-01, /01T-0:on 800521,HPSI Flow Indication for Loop 2A Was Inoperable.Caused by Ruptured Bellows.Transmitter Was Replaced to Restore Operability | /01T-0:on 800521,HPSI Flow Indication for Loop 2A Was Inoperable.Caused by Ruptured Bellows.Transmitter Was Replaced to Restore Operability | | | 05000255/LER-1980-013, Forwards LER 80-013/01T-0 | Forwards LER 80-013/01T-0 | | | 05000255/LER-1980-014, Licensee Event Reports 80-014, 80-015, and 80-016 Regarding Oil Level in Snubbers No. 5, 9, and 7 Were Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers | Licensee Event Reports 80-014, 80-015, and 80-016 Regarding Oil Level in Snubbers No. 5, 9, and 7 Were Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers | | | 05000255/LER-1980-014-03, /03L-0:on 800512,during Routine Testing of Hydraulic Snubbers,Oil Level in Snubber 5 Found to Be Less than Zero.Caused by Rust Combined W/Vibrator,Accelerating Seal Failure.Rust Found Inside Accumalator | /03L-0:on 800512,during Routine Testing of Hydraulic Snubbers,Oil Level in Snubber 5 Found to Be Less than Zero.Caused by Rust Combined W/Vibrator,Accelerating Seal Failure.Rust Found Inside Accumalator | | | 05000255/LER-1980-015-03, /03L-0:on 800512,during Routine Testing of Hydraulic Snubber,Oil Level in Snubber 9 Found to Be Less than Zero.Cause of Seal Damage Unknown;Normal Wear Suspected.Accumulator Plunger Seal Found to Be Damaged | /03L-0:on 800512,during Routine Testing of Hydraulic Snubber,Oil Level in Snubber 9 Found to Be Less than Zero.Cause of Seal Damage Unknown;Normal Wear Suspected.Accumulator Plunger Seal Found to Be Damaged | | | 05000255/LER-1980-016-03, /03L-0:on 800515,during Testing of Hydraulic Snubber,Oil Level in Snubber 7 Found to Be Less than Zero. Caused by Seal Degradation.Snubber Will Be Disassembled to Confirm Cause | /03L-0:on 800515,during Testing of Hydraulic Snubber,Oil Level in Snubber 7 Found to Be Less than Zero. Caused by Seal Degradation.Snubber Will Be Disassembled to Confirm Cause | | | 05000255/LER-1980-017-03, Ps Testing Procedures Review Revealed Setpoint of PS-1801 Through 1804 to Be Lower than Permitted by Tech Specs.Caused by Faulty Procedure. Procedures Revised to Conform W/Tech Specs | Ps Testing Procedures Review Revealed Setpoint of PS-1801 Through 1804 to Be Lower than Permitted by Tech Specs.Caused by Faulty Procedure. Procedures Revised to Conform W/Tech Specs | | | 05000255/LER-1980-017, Forwards Updated LER 80-017/03X-1 | Forwards Updated LER 80-017/03X-1 | | | 05000255/LER-1980-018-03, /03L-0:on 800522,during Routine Testing of Hydraulic Snubbers,Oil Level in Snubber 2 Was Found to Be Less than Zero & Was Declared Inoperable.Apparently Caused by Seal Degradation | /03L-0:on 800522,during Routine Testing of Hydraulic Snubbers,Oil Level in Snubber 2 Was Found to Be Less than Zero & Was Declared Inoperable.Apparently Caused by Seal Degradation | | | 05000255/LER-1980-018, Licensee Event Report 80-018 Regarding Oil Level in Snubber No. 2 Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers | Licensee Event Report 80-018 Regarding Oil Level in Snubber No. 2 Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers | | | 05000255/LER-1980-019-01, /01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation | /01T-0:on 800609,during Tech Spec Review,Tech Spec 3.3 Determined to Provide Too Little Borated Water for Safety Injection.Caused by Imprecise Wording of Tech Spec. Low Level Alarm Setpoint Changed,Tech Spec Under Evaluation | | | 05000255/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000255/LER-1980-020-01, /01T-0:on 800711,control Rod Drive Mechanism Failed to Operate Properly,Resulting in Rod Being Misaligned for Approx Five Minutes.Caused by Dirty Control Relay Armatures & Contractor Interlock Which Resulted in Sticking | /01T-0:on 800711,control Rod Drive Mechanism Failed to Operate Properly,Resulting in Rod Being Misaligned for Approx Five Minutes.Caused by Dirty Control Relay Armatures & Contractor Interlock Which Resulted in Sticking | | | 05000255/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000255/LER-1980-021-01, /01X-1:on 800725,during Valve Inservice Insp, Operator Opened Containment Sump Valve CV-3030.Valve Stayed Open 36-h.Caused by Operator Error.Valve Closed,Operator Counseled & Shift Turnover Checklist Revised | /01X-1:on 800725,during Valve Inservice Insp, Operator Opened Containment Sump Valve CV-3030.Valve Stayed Open 36-h.Caused by Operator Error.Valve Closed,Operator Counseled & Shift Turnover Checklist Revised | | | 05000255/LER-1980-021, Forwards Corrected App C, Calculations of Radiological Effects as Results of Hypothetical Accident W/CV-3030 Open, to 800820 LER 80-021,Revision 1.Corrected Apps E & F Also Encl | Forwards Corrected App C, Calculations of Radiological Effects as Results of Hypothetical Accident W/CV-3030 Open, to 800820 LER 80-021,Revision 1.Corrected Apps E & F Also Encl | | | 05000255/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000255/LER-1980-022-03, /03L-0:on 800710,2-h After Reactor Criticality, Channel NI-03 Not Declared Operable Prior to Reactor Startup.Caused by Failure of Shift Supervisor to Check Control Mechanism | /03L-0:on 800710,2-h After Reactor Criticality, Channel NI-03 Not Declared Operable Prior to Reactor Startup.Caused by Failure of Shift Supervisor to Check Control Mechanism | | | 05000255/LER-1980-023-03, Containment High Radiation Detectors Re 1805 & 1807 Determined Inoperable.No Apparent Cause for Failure.Detectors Disassembled,Cleaned & Recoated & Are Now Functional | Containment High Radiation Detectors Re 1805 & 1807 Determined Inoperable.No Apparent Cause for Failure.Detectors Disassembled,Cleaned & Recoated & Are Now Functional | | | 05000255/LER-1980-023, Forwards Updated LER 80-023/03X-1 | Forwards Updated LER 80-023/03X-1 | | | 05000255/LER-1980-024, Forwards LER 80-024/01T-0 | Forwards LER 80-024/01T-0 | | | 05000255/LER-1980-024-01, /01T-0:on 800731,w/diesel Generator & Charging Pump P-55A Inoperable,Backup Pump P-55B Failed.Diesel Generator Restored in One Hour.Caused by Pump Packing Failure on P-55B.Pump Repacked & Restored to Svc | /01T-0:on 800731,w/diesel Generator & Charging Pump P-55A Inoperable,Backup Pump P-55B Failed.Diesel Generator Restored in One Hour.Caused by Pump Packing Failure on P-55B.Pump Repacked & Restored to Svc | | | 05000255/LER-1980-025, Forwards LER 80-025/01T-0 | Forwards LER 80-025/01T-0 | | | 05000255/LER-1980-025-01, /01T-0:on 800801,during Vol Control Tank Venting, Unplanned Gaseous Release Occurred W/O 15-day Min Holdup. Caused by Either Dirt Trapped in Head Plate & Diaphragm or Uneven Tightening of Compressor Head Bolts | /01T-0:on 800801,during Vol Control Tank Venting, Unplanned Gaseous Release Occurred W/O 15-day Min Holdup. Caused by Either Dirt Trapped in Head Plate & Diaphragm or Uneven Tightening of Compressor Head Bolts | | | 05000255/LER-1980-026, Forwards LER 80-026/03L-0 | Forwards LER 80-026/03L-0 | | | 05000255/LER-1980-026-03, /03L-0:on 800719,during Refilling of Safety Injection tanks,FT-0313 Found Inoperable.Caused by Failure to Close Instrument Equalizing Valve During Recent Calibr | /03L-0:on 800719,during Refilling of Safety Injection tanks,FT-0313 Found Inoperable.Caused by Failure to Close Instrument Equalizing Valve During Recent Calibr | | | 05000255/LER-1980-027-01, During Venting of Quench Tank to Waste Gas Surge Tank,Gaseous Release Occurred W/O 15 Day Min Holdup.Caused by Leaking Isolation Valve & Valve Pin Disassembly.Pin Replaced | During Venting of Quench Tank to Waste Gas Surge Tank,Gaseous Release Occurred W/O 15 Day Min Holdup.Caused by Leaking Isolation Valve & Valve Pin Disassembly.Pin Replaced | | | 05000255/LER-1980-027, Forwards Updated LER 80-027/01X-1 | Forwards Updated LER 80-027/01X-1 | |
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