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LER-1980-017, /03L-0:on 800218,at 100% Power,Vacuum Pump for Process Monitors RH-GW-101 & RM-GW-102 Found Tagged Out of Svc Leading to Release of Unmonitored Gases.Caused by Failure to Perform Procedure Before Taking Pump Out of Svc |
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| 2801980017R03 - NRC Website |
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('7-77) e.lCENSEE EVENT REPORT e.
CONTROL BLOCK: I
! '1' (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1.... _.....___.__.....___.__~-!6 \\...'.)
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LICENSEE CODE.
14, 15 LICENSE NUMBER 25 26 LICENSE TYPE
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- ~~~~~ ~G) I o I s I o I o I o I 2 I s I o 101 o I 2 I 1 I s I a I o !G) l o I 3 I 1 I 4 I a I o I G) 60 61 DOCKET NUMBER 68 69 EV:aNT DATE 74 75 REPORT DATE 80 EVENT D!:SCRIPTION AND PROBABLE CONSEQUENCES@
[I]IJ I With the unit at 100%.power, Liquid Waste Test Tank 1 LW TK llB was inadyertentlv [QJ]J I released without being sampled.
This is contrary to T.S. 3.11.A.4 and reportable per
~
T.S. 6.6.2.b.2.
The operator in the Control Room was monitoring tank level and imme-
~
diately terminated the release when the level in 1-LW-TK-llB changed.
Also, the C2::J]J monitor in the discharge line was operable and would have terminated the release
~
if the activity had exceeded preset limits.
Therefore, the health and safety of
[£))] I the public were not affected.
I 7
8 9
80 [TI}]
7 8
SYSTEM CODE I Ml Al@
9 10 G\\ LEA/RO LVENTYE./1.R
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REPORT ! 8 j O j NUMBER 21 22 CAUS.E
CAUSE
CODE SUBCODE COMPONENT CODE LAJ@ LI@ I z I z I z I z I z I z I@
11 12 13 SEQUENTIAL REPDFjT NO.
I I
I O 11 I 6 I 23 24 26 27 18 OCCURRENCE CODE 10 13 I 28 29 COMP'.
SUBCODE LU 19 REPORT TYPE LJ 30 VALVE SUBCODE [Ll@
20 l.=!
31 REVISION NO.
LQ.J 32 TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED ACTION FUTURE EFFECT SHUTDOWN
~
ATTACHMENT NPRD-4 FORM :;us.
PRIME COMP.
SUPPLIER COMPONENT MANUFACTURER L!!..1@12...J@ ~@ ~
- 1. 0 IO I O I I l!J@
33 34 35 36 31 40 41 l!!J@ ~ I z l9 l9 l9 I@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
42 43 44 47 I Liquid Waste Test Tank 1-LW-TK-llA had been sampled and was ready for release.
- Howevet, ITIJ] I when performing the necessary valve lineups, the discharge valve from 1-LW-P-llB CIII] l,was opened instead of the valve for 1-LW-P-llA, resulting in 1-LW-TK-llB being par-o::r::rJ I tially released.
The release was terminated and tank 1-LW-TK-llB was sampled.
Based [J]1J an estimate was made as to the amount and activit released and veri-1 s g 1.e in allowable limit~
F~~fL~
% POWER OTHER STATUS ~
ITli] L!J@ 11 p p l@I NA 8
9 10 12 13 44 ACTIVITY CONTENT
(.;';;\\
RELEASED OF RELEASE AMOUNT OF ACTIVITY '2;.J GE L.!:..I@ ~@i....l __
._o_oo_o_o4_3_c_i __
7 8
9 10 11 44 PERSONNEL EXPOSURES Q,
80 METHOD OF A
OISCOVERY DISCOVERY DESCRIPTION L.!J~~I __ O-=-pe_r_a_t_o_r_o_b_s_e_r_v_a_t_i_o_n ________ __.
45 46 45 LOCATIO.N OF RELEASE @
Liquid waste system to river 80 80 NUMBER
~
TYPE DESCRIPTION~
[QI] j O l O I OJ~@L...-__
N_A _____________________
7 8
9 11 12 13 80 NUMBER DESCRIPTION 41 PERSONNEL INJURIES
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[TITI j O ! O I O l@L--___
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8 9
11 12 80 LOss*oF OR DAMAGE TO FACILITY '43' TYPE
DESCRIPTION
~
DJI) ~~1--__
N_A ____________________________________________________ ----1 7
8 9
10 80 PUBLICITY G\\
NRC USE ONLY ISSUED/,;";\\ DESCRIPTION~
0 G:I2] L!!J~L...--NA ___________________ --=-----~
I I I I I I I I I I I I Ii 7
8 9
10
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68 69 80 ;
s 003170~~1:t4' 0
NAME OF PREPARER-..M1W._..1.I-.... Si.,,t.iae~r,,..1a1-1r.... t----------
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ATTACHMENT (PAGE 1 OF.l)
SURRY POWER STATION, UNIT l DOCKET NO: 50-280 REPORT NO: 80-016/03L-O EVENT DATE:
2-18-80 TITLE OF REPORT:
Liquid Waste Inadvertent Release
- 1.
DESCRIPTION OF EVENT
With the unit at 100% power, Liquid Waste Test 1-LW-TK-llb, was inadvertently released without being sampled.
This is contrary to T.S. 3.11.A.4 and reportable per T.S. 6.6.2.b.2.
- 2.
PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:
The operator in the Control Room was monitoring tank level and immediately terminated the release when the level in 1-LW-TK-llB changed.
Also, the monitor in the discharge line was operable and would have terminated the release if the activity had exceeded preset limits.
Therefore, the health and safety of the public were not affected.
- 3.
CAUSE
OF EVENT:
Liquid Waste Test Tank 1-LW-TK-llA had been sampled and was ready for release.
However, when performing the necessary valve lineups, the discharge valve from 1-LW-F-llB was opened instead of the valve for 1-LW-P-l lA, resulting in 1-LW-TK-llB being partially released.
- 4.
IMMEDIATE CORRECTIVE ACTION
s.
The release was terminated and tank 1-LW-TK-llB was sampled.
Based on the sample, an estimate was made as to the amount and activity released and verified to be within allowable limits.
SCHEDULED CORRECTIVE ACTION:
None required.
- 6.
ACTION TAKEN TO PREVENT RECURRENCE:
Operators have been instructed to insure proper valve lineups are performed prior to commencing liquid waste releases.
- 7.
GENERIC IMPLICATIONS:
None.
(7-77) ecENSEE EVENT REPORT e
CONTROL BLOCK: I 10 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1L.. -.L.---'--.L.---'--'---'6
_[il~l IV J A I s Ip I s I 1 101. 01 °1 7
8 9
LICENSEE CODE 14 15
- - I o I o I o I o I o 1-Io I o 1014 I 1 11 11 I 1 101 I I 0 LICENSE NW;18ER 25*
. 26 LICENSE TYPE
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57 CAT 58 CON'T
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7 8
- ~~~~~ L:'.J©I 9 s1 01 01 01 21 s1 0101 01 21 11 s1 s1 ojG)! 01 3! 114 Is lo 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
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I With unit.at 100% power, the vacuum pump for process vent monitors RH-GW-101 and
. I RM-GW-102 was found tagged out of service.
The pump had been out of service for app-I roxima tely two days, and the applicable pr*ocedures were not pe rfonned prior to tag-outf.
This is contrary to T.S. 3.11.B.5 and T.S. Table 3.7-5 and reportable per T.S. 6.6.
2.b.2.
During the period the monitors were out of ser-v*ice, no releases were made
- - 1 I
[]JI] I from the waste gas decay tanks.
A review of the accountability records revealed thatj ITITJ the activity levels released during the period were well within allowable limi*ts.
Th 7
8 9 an sa ety o t e pu ic were not affected.
ITIIl 7
8
'SYSTEM
CAUSE
CAUSE CODE CODE SUBCODE COMPONENT CODE I Mj c1@ ~@ ~@., z I z., z I z I z I z,e 9
10 11 12 13 18 SEQUENTIAL OCCUF1RENCE REPORT NO.
CODE I O I 1 17 I I /I IO 13 I 23 24 26 2 7 28 29
~
LEA/RO c-VENTYE.A.R
\\:.:,J REPORT j 8 j O !
NUMBER 21 22 l:::.I COMP.
SUBCODE L21 19 REPORT TYPE
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30 VALVE SUBCODE
~@
20 l=1 31 ACTION FUTURE EFFECT SHUTDOWN
~
ATTACHMENT NPRD-4 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :;us.
PRIMEC::OMP.
SUPPLIER
~@L:J@ ~@ U I. 9 9. 9 9 LJ@ LI@
33 34 35 36 31 40 41 42 CAUSE DESCRIPTiON AND CORRECTIVE ACTIONS @
LI@
43 REVISION NO.
~
32 COMPONENT MANUFACTURER 80 j Zj 9j 9! 9!@)
44 47 The failure to perform the applicable procedure prior to taking the vacuum pump out of(*
OJI]
service led to the release of unmonitored gases.
The immediate action taken was.to O:I[f perform AP-5.16, Radiation Monitoring System Process Vent Particulate & Gaseous Mal-
[II)) I function, noti_fy Health Physics and analyze the accountability data.
The system was.
o:r:rJ I returned to normal operation, i.e. the vacuum pump was returned to* service.
7 8
9 FACILITY
'Jo' STATUS
% POWER OTHER STATUS \\:::::J METHOD OF
(.;;\\
80 [IE] L..!J@ 11 1 ° I O l@.... I NA _____
8 9
10 12 1"3 OISCOVERY DISCOVERY DESCRIPTION ~
LI""l _Op....;;..e_r_a_t_o_r_o_h_s_e_rv_a_t_i_o_n ________ _..
ACTIVITY CONTENT
~
RELE2SED OF RELEASE AMOUNT OF ACTIVITY ~
DJI) l:J@) l..:J(§._j ___
NA ____
7 8
9 10 11 44 7
45 46 44 NA LOCATION OF RELl;ASE @
80*
45 80 PERSONNEL EXPOSURES t::;:;,.
NUMBER
,,;:;,.. TYPE
DESCRIPTION
!JJI] I o, I ~~@.__ ___
NA _______________
.....,... ______ ~
7 8
9 11 12 13 80 PERSONNEL INJURIES
~
cruMaER DESCRIPTION 41
~
I I I 0 1@.__ _________________ -,-------~
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY ~
TYPE
DESCRIPTION
'..::::J
~
~(§}L--_NA ___ ~----------'----------...;.._-------------~
1 s Is 10 so PUBLICITY
(';";;\\
NRC USE ONLY ISSU~D~ DESCRIPTION~
0 [ill] l.::J~......__N_A ___________________ ___.
I I I I I I I I 11 I I I~
7 8
9 10 68 69 80 ai NAME OF PREPARER w I, Stewart PHON E:---(...igM.0"'14-+)-J~j~7f-,,!.JMl~i..+4--
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ATTACHMENT (PAGE 1 OF 1)
SURRY POWER STATION, UNIT 1 DOCKET NO:
50-280 REPORT NO: 80-017/03L-O EVENT DATE:
2-18-80 TITLE OF REPORT:
Inoperability of Radiation Monitors (RH-GW-101, 102)
- 1.
DESCRIPTION OF EVENT
With the unit at 100% power, the vacuum pump for process vent monitors RM-GW-101 and RM-GW-102 was found tagged out of service.
Further in-vestigation revealed the pump had been out of service for approximately two days and that the applicable procedure was not performed prior to the tag-out.
Titis is contrary to T.S. 3.11.B.5 and T.S. Table 3.7-5, and is reportable per T.S. 6.6.2.b.2.
- 2.
PROBABLE CONSEQUENCES/STATUS OF R~DUNDANT SYSTEMS:
- 3.
- 4.
During the period the monitors were out of service, no releases were made from the waste gas decay tanks and the H.P. accountability sampling system was in operation.
- A review of the accountability records revealed that
.the activity levels released during the period were well within allowable limits.
Therefore, the health and safety of the general public were not affected.
CAUSE OF EVENT
The failure to perform the applicable procedure prior to taking the vacuum pump out of service led to the release of unmonitored gases, although that which was released was well within the allowable activity limits.
IMMEDIATE CORRECTIVE ACTION
The immediate a~tion taken was to perform AP-5.16, Radiation Monitoring System Process Vent Particulate and Gaseous Malfunction, notify Health Physics and analyze the accountability data.
- 5.
SCHEDULED CORRECTIVE ACTION:
The system was returned to normal operation, i.e. the vacuum pump was returned to service.
- 6.
ACTION TAKEN TO PREVENT RECURRENCE:
Operations personnel were reinstructed to insure that the appropriate procedures are performed prior to removing the process vent monitors -
from service.
- 7.
GENERIC IMPLICATIONS:
None.
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| 05000281/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000281/LER-1980-001-01, /01T-0:on 800310,review of Delta Flux Computer Program Revealed Deficiency in Periodic Test 28.9, Incore- Excore Hi Calibr. Caused by Failure to Extend Calibr of Control Board Delta Flux Meters to 120% Power Range | /01T-0:on 800310,review of Delta Flux Computer Program Revealed Deficiency in Periodic Test 28.9, Incore- Excore Hi Calibr. Caused by Failure to Extend Calibr of Control Board Delta Flux Meters to 120% Power Range | | | 05000280/LER-1980-001-03, /03L-0:on 800101,w/unit at Cold Shutdown,Snubber 1-WFPD-HSS-14 Found W/Empty Reservoir & Declared Inoperable Per Tech Spec.Caused by Leakage Around Pipe Nipple Threads on Valve Block & Extended Seal Washers.Snubber Replaced | /03L-0:on 800101,w/unit at Cold Shutdown,Snubber 1-WFPD-HSS-14 Found W/Empty Reservoir & Declared Inoperable Per Tech Spec.Caused by Leakage Around Pipe Nipple Threads on Valve Block & Extended Seal Washers.Snubber Replaced | | | 05000280/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000280/LER-1980-002-03, /03L-0:on 800106,during Routine Release of Lwtt 80-95,LW Effluent Flow Recorder Paper Did Not Rotate & Thus No Record of Flow Note Was Obtained.Caused by Inadequate Mesh Between Recorder Drive Gears & Recorder Paper Roll | /03L-0:on 800106,during Routine Release of Lwtt 80-95,LW Effluent Flow Recorder Paper Did Not Rotate & Thus No Record of Flow Note Was Obtained.Caused by Inadequate Mesh Between Recorder Drive Gears & Recorder Paper Roll | | | 05000280/LER-1980-002-01, /01T-0:on 800320,insp of Containment Following Type a Leak Rate Revealed Eight 1/4 Inch Holders Drilled Through Containment Liner.Caused by Improper Interpretation of Procedure During Design Change 78-48.Repair Planned | /01T-0:on 800320,insp of Containment Following Type a Leak Rate Revealed Eight 1/4 Inch Holders Drilled Through Containment Liner.Caused by Improper Interpretation of Procedure During Design Change 78-48.Repair Planned | | | 05000281/LER-1980-003, Forwards Updated LER 80-003/03L-1 & LER 80-046/03L-0 | Forwards Updated LER 80-003/03L-1 & LER 80-046/03L-0 | | | 05000280/LER-1980-003-03, /03L-0:on 800107,during Prestartup Testing, Feedwater Bypass Valve HCV-FW-155B Did Not Fail Closed Upon Loss of Instrument Air as Per Design.Caused by Sticking, Dirty Pilot Valve.Valve Cleaned & Returned to Svc | /03L-0:on 800107,during Prestartup Testing, Feedwater Bypass Valve HCV-FW-155B Did Not Fail Closed Upon Loss of Instrument Air as Per Design.Caused by Sticking, Dirty Pilot Valve.Valve Cleaned & Returned to Svc | | | 05000281/LER-1980-003-03, MOV-CW-200B Found Inoperable.Caused by Electrical Malfunction Due to Mechanical Repair in Progress.Redundant Water Box Inlet Valve MOV-CW-206B Was Shut | MOV-CW-200B Found Inoperable.Caused by Electrical Malfunction Due to Mechanical Repair in Progress.Redundant Water Box Inlet Valve MOV-CW-206B Was Shut | | | 05000280/LER-1980-004-01, /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve | /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve | | | 05000280/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000281/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000281/LER-1980-004-01, /01T:on 800521,during Cold Shutdown,Pressure Transmitter 458 Inoperable Due to Wiring Problem & Isolation Valve for Pressure Transmitter 403 Found Closed,Negating Overpressure Mitigating Sys.Caused by Cable Problem | /01T:on 800521,during Cold Shutdown,Pressure Transmitter 458 Inoperable Due to Wiring Problem & Isolation Valve for Pressure Transmitter 403 Found Closed,Negating Overpressure Mitigating Sys.Caused by Cable Problem | | | 05000280/LER-1980-005-03, /03L-0:on 800120,while Conducting PT 27D Heat Tracing Sys,Discovered That Circuit 17A Panel 9 Was Inoperative.Caused by Thermostat Failure.Maint Rept Initiated.Defective Thermostat Replaced | /03L-0:on 800120,while Conducting PT 27D Heat Tracing Sys,Discovered That Circuit 17A Panel 9 Was Inoperative.Caused by Thermostat Failure.Maint Rept Initiated.Defective Thermostat Replaced | | | 05000281/LER-1980-005-01, Type a Testing Revealed Leakage Through Recirculation Spray Diaphragm Plate Seal Welds.Caused by Lack of Fusion & Slag Inclusion in Weld Areas.Defects Repaired | Type a Testing Revealed Leakage Through Recirculation Spray Diaphragm Plate Seal Welds.Caused by Lack of Fusion & Slag Inclusion in Weld Areas.Defects Repaired | | | 05000280/LER-1980-006, Forwards Updated LER 80-006/03X-1 | Forwards Updated LER 80-006/03X-1 | | | 05000280/LER-1980-006-03, /03L-0:on 800115,during Routine Surveillance of Liquid Waste Release,Discovered That Unsampled Waste from Tank 5A Was Being Pumped to Tank 5B.Caused by Inadvertent Operation of Transfer Pump.Waste Release Terminated | /03L-0:on 800115,during Routine Surveillance of Liquid Waste Release,Discovered That Unsampled Waste from Tank 5A Was Being Pumped to Tank 5B.Caused by Inadvertent Operation of Transfer Pump.Waste Release Terminated | | | 05000281/LER-1980-006-03, /03L-0:on 800527,contrary to Tech Spec 3.1.G.2.b. (1),Containment 2 Pressurizer Level Exceeded 33% W/O Mitigation Protection.Caused by Addition of Water to Primary Sys to Maintain Level Indication.Rcs Drained | /03L-0:on 800527,contrary to Tech Spec 3.1.G.2.b. (1),Containment 2 Pressurizer Level Exceeded 33% W/O Mitigation Protection.Caused by Addition of Water to Primary Sys to Maintain Level Indication.Rcs Drained | | | 05000281/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000280/LER-1980-007-03, /03L-0:on 800116,during Normal Operation,Heat Tracing Circuit 4 on Line 1-CH-56-152,boric Acid Supply to Blender Failed.Caused by Water Penetration of Heat Tracing Tape.Tape Replaced W/Higher Water Resistant Tape | /03L-0:on 800116,during Normal Operation,Heat Tracing Circuit 4 on Line 1-CH-56-152,boric Acid Supply to Blender Failed.Caused by Water Penetration of Heat Tracing Tape.Tape Replaced W/Higher Water Resistant Tape | | | 05000280/LER-1980-007, Forwards Updated LER 80-007/03X-1 | Forwards Updated LER 80-007/03X-1 | | | 05000281/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000281/LER-1980-007-03, /03L-0:on 800606,w/unit in Cold Shutdown,Smoke Detectors Found Inoperable.Caused by Breaker Trip at Motor Control Ctr Which Feeds Detectors.Cause of Breaker Trip Unknown | /03L-0:on 800606,w/unit in Cold Shutdown,Smoke Detectors Found Inoperable.Caused by Breaker Trip at Motor Control Ctr Which Feeds Detectors.Cause of Breaker Trip Unknown | | | 05000280/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000281/LER-1980-008-03, /03L-0:on 800623,while Performing Periodic Test 26.1,found Air Ejector Monitor Alarm Setpoint Above Tech Spec Requirement.Caused by Instrument Drift.Alarm Setpoint Recalibr | /03L-0:on 800623,while Performing Periodic Test 26.1,found Air Ejector Monitor Alarm Setpoint Above Tech Spec Requirement.Caused by Instrument Drift.Alarm Setpoint Recalibr | | | 05000280/LER-1980-008-01, /01T-0:on 800116,during Power Operation,Valve Inadvertently Closed,Preventing Boric Acid Flow in One of Two Flow Paths to Core for Approx 3-h.Caused Not Stated. Valve Opened & Boric Acid Flow Verified | /01T-0:on 800116,during Power Operation,Valve Inadvertently Closed,Preventing Boric Acid Flow in One of Two Flow Paths to Core for Approx 3-h.Caused Not Stated. Valve Opened & Boric Acid Flow Verified | | | 05000281/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000280/LER-1980-009-01, Westinghouse LOCA-ECCS Reanalysis Indicated Residual Penalty of 0.007 in Fq Exists from Fuel Rod Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve | Westinghouse LOCA-ECCS Reanalysis Indicated Residual Penalty of 0.007 in Fq Exists from Fuel Rod Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve | | | 05000280/LER-1980-009, Forwards LERs 82-049/03L-0,82-080/03L-0 & Updated LER 80-009/01X-1 | Forwards LERs 82-049/03L-0,82-080/03L-0 & Updated LER 80-009/01X-1 | | | 05000280/LER-1980-009-03, /03L-0:on 800123,during Normal Operation,Boric Acid Transfer Pump 1-CH-P-2A Lost Flow.Caused by Broken Pump Shaft Inside Pump Casing.Caused by Improper Installation.Pump a Replaced & Maint Procedures Revised | /03L-0:on 800123,during Normal Operation,Boric Acid Transfer Pump 1-CH-P-2A Lost Flow.Caused by Broken Pump Shaft Inside Pump Casing.Caused by Improper Installation.Pump a Replaced & Maint Procedures Revised | | | 05000281/LER-1980-009, Forwards LER 80-009/01T-0 | Forwards LER 80-009/01T-0 | | | 05000281/LER-1980-009-01, /01T-0:on 800718,Westinghouse LOCA ECCS Reanalysis Indicated Error in Fuel Clad Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve & Results in Earlier Clad Burst.Limit Will Be Controlled | /01T-0:on 800718,Westinghouse LOCA ECCS Reanalysis Indicated Error in Fuel Clad Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve & Results in Earlier Clad Burst.Limit Will Be Controlled | | | 05000281/LER-1980-010-01, Containment Gaseous & Particulate Radiation Monitor Found to Have One Automatic Function Incapable of Operating During Fuel Movement.Caused by Bypass of Containment Exhaust Fan Relay in Design Change | Containment Gaseous & Particulate Radiation Monitor Found to Have One Automatic Function Incapable of Operating During Fuel Movement.Caused by Bypass of Containment Exhaust Fan Relay in Design Change | | | 05000280/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000280/LER-1980-010-01, Overstress on 18-inch Line CC-9-121,unit 2 Supply to RHR Exchanger,Found During Pipe Stress Reanalysis on Show Cause Lines.Caused by Supports Installed to Prevent Overstress During DBE | Overstress on 18-inch Line CC-9-121,unit 2 Supply to RHR Exchanger,Found During Pipe Stress Reanalysis on Show Cause Lines.Caused by Supports Installed to Prevent Overstress During DBE | | | 05000280/LER-1980-011-03, /03L-0:on 800128,during Normal Operations,Heat Tracing Strip Heater on 1-CH-P-2A Circuit 25A (Panel 9) Failed.Caused by Penetration of Water Leakage from Pump Flange.Strip Heater Replaced & Leak Repair Requested | /03L-0:on 800128,during Normal Operations,Heat Tracing Strip Heater on 1-CH-P-2A Circuit 25A (Panel 9) Failed.Caused by Penetration of Water Leakage from Pump Flange.Strip Heater Replaced & Leak Repair Requested | | | 05000281/LER-1980-011-01, /01T-0:on 800819,at 12% Power,Steam Flow Transmitters (FI-474,475,484,485,494 & 495) Isolated Contrary to Tech Spec-3.7.B.Caused by Transmitters Being Isolated Following Containment Integrated Leak Rate Test | /01T-0:on 800819,at 12% Power,Steam Flow Transmitters (FI-474,475,484,485,494 & 495) Isolated Contrary to Tech Spec-3.7.B.Caused by Transmitters Being Isolated Following Containment Integrated Leak Rate Test | | | 05000280/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000281/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000281/LER-1980-012-03, /03L-0:on 800815,review of Unit 2 Pipe Support Showed That Seismic Support for Charging Pump 2-CH-P-1B Had Not Been Installed.Caused by Administrative Error.Support Installed | /03L-0:on 800815,review of Unit 2 Pipe Support Showed That Seismic Support for Charging Pump 2-CH-P-1B Had Not Been Installed.Caused by Administrative Error.Support Installed | | | 05000280/LER-1980-012-03, /03L-0:on 800202,while Performing PT-27D,amperage Readings for Circuit 25A,panels 1 & 2,were Below Acceptance Criteria.Repairs to Tape Not Completed within 2-h Limit.Unit Rampdown Intiated.Caused by Water Penetration | /03L-0:on 800202,while Performing PT-27D,amperage Readings for Circuit 25A,panels 1 & 2,were Below Acceptance Criteria.Repairs to Tape Not Completed within 2-h Limit.Unit Rampdown Intiated.Caused by Water Penetration | | | 05000280/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000280/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000281/LER-1980-013-03, /03L-0:on 800815,during Startup Testing,Boric Acid Concentration of 13.8% Was Reported in 1-CH-TK-1C & 2-SI-TK- 2.Caused by Pumping Boric Acid from Boron Evaporator Bottoms Tank to Boric Acid Storage Tank W/O Sampling | /03L-0:on 800815,during Startup Testing,Boric Acid Concentration of 13.8% Was Reported in 1-CH-TK-1C & 2-SI-TK- 2.Caused by Pumping Boric Acid from Boron Evaporator Bottoms Tank to Boric Acid Storage Tank W/O Sampling | | | 05000280/LER-1980-013-03, Valve HCV-1852A to Tank 1-SI-TK-1A Delayed Closing 30-50 Secs,Resulting in Tank Draining Below Tech Spec Level.Caused by Moisture in Air Lines Feeding Valve Operator.Tank Filled to Tech Spec Level | Valve HCV-1852A to Tank 1-SI-TK-1A Delayed Closing 30-50 Secs,Resulting in Tank Draining Below Tech Spec Level.Caused by Moisture in Air Lines Feeding Valve Operator.Tank Filled to Tech Spec Level | | | 05000280/LER-1980-014-01, /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned | /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned | | | 05000280/LER-1980-014-03, /03L-0:on 800816,w/reactor Critical,Discovered Level in Refueling Water Storage Tank & Cat Below Min Set by Tech Specs.Caused by Excessive Makeup to B SI Accumulator W/O Refilling | /03L-0:on 800816,w/reactor Critical,Discovered Level in Refueling Water Storage Tank & Cat Below Min Set by Tech Specs.Caused by Excessive Makeup to B SI Accumulator W/O Refilling | | | 05000280/LER-1980-015-03, During Radiation Monitoring Test,Radiation Alarm Setpoint for Component Cooling Sys Found Greater than Twice Background.Caused by Instrument Drift.Activity Levels Verified | During Radiation Monitoring Test,Radiation Alarm Setpoint for Component Cooling Sys Found Greater than Twice Background.Caused by Instrument Drift.Activity Levels Verified | | | 05000281/LER-1980-015-03, /03L-0:on 800816,after Pressurization of Accumulator Tanks,Level Indicator for B SI Accumulator Indicated 61% Level,Above Tech Spec Max of 58.3%.Caused by Condensation & High Pressure in Nitrogen Feed Line | /03L-0:on 800816,after Pressurization of Accumulator Tanks,Level Indicator for B SI Accumulator Indicated 61% Level,Above Tech Spec Max of 58.3%.Caused by Condensation & High Pressure in Nitrogen Feed Line | | | 05000280/LER-1980-016-03, /03L-0:on 800916,w/unit Operating Steady State at 100% power,TV-SS-201B Would Not Remain Closed When Control Switch Was Released.Cause Undetermined.Inside Trip Valve Closed & Air Secured to TV-SS-201B | /03L-0:on 800916,w/unit Operating Steady State at 100% power,TV-SS-201B Would Not Remain Closed When Control Switch Was Released.Cause Undetermined.Inside Trip Valve Closed & Air Secured to TV-SS-201B | |
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