LER-1980-022, /01T-0:on 800624,w/Mayflower 500 Kv Transmission Line Out of Svc & Unit Operating at Full power,500 Kv Mabelvale Line Tripped.Caused by Ground Fault & Overload. Lock-out Relays Were Reset & 500 Kv Bus re-energized |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3131980022R01 - NRC Website |
|
text
\\
NRC F ORM 3E4 U. S. NUCLE AR REGUL ATORY COMMIS$ ION (7 77)
LICENSEE EVENT REPORT EXHIBtT A CONTROL BLOCK: l l l l l l lh (PLE ASE PRINT OR TYPE ALL REQUtREO INFORMATIONI i
6 [irTTl I Aj R l Al Nl 0 l 1lgl 0 l0 l -l0 l0 l 0} Oj 0 p [ 0 l0 lg l1 l 1l1 l 1 lgl l lg 1
a 9 LeCENSEE CODE sa is uCENst huweEh 25 20 tiCtN>E tut Jo b) CAT Se CON'T Iclil C"J IL l@l0 l 5 p 10101311 h l@l 01612141810 l@l ol 71017 I R IO l@
I B
60 61 DOCS 6 ET NuwSEp 68 69 EVENT DATE 3a 75 e4PON T D ATE 80 EVENT DESCRIPTION AND PROBASLE CONSEQUENCES h lo I21 I With the Mayfinwpr 500KV trancmissinn line not of service and the unit 1
io13i i operating at 100% power; the 500 KV Mabelvale line tripped on a ground i
t o la l I fanit-the 900KV Fnet Smith lino nnoned nn the Fnet <mith end. isolatingl ic is t I all but the two 161KV transmission lines from the ANO switchyard.
The i
lo is 1 I Morrilton Fast 161KV line trioned due to the resultant overload, leavina l 10171 i one source of offsite power, Russellville East 161KV line supplying SU i
I c ie I I transfnempr O. which romainod nnprahlo thrnunhnut_the transient.
No I
- similar ggcpyrdncys Rep,g,rgabl e per T.S.3. 7.1.'a & T,.),6.12fl.g.
a CCDE LCCE suecoDE COM*0NENT Cout suW O A s.mtout 1 E I Al @ L,,EJ@ i,,@ l X IX ! X IX l X l XIS L,,zj@ LZj @
ic191 m
5E QUE N T t A s.
OCLus m r t.CE NE rcu r E E vision
@$$! 'iT! d'[
l---J l d'IEi21 y
I d I 11 g
._ 2 n
23 2
x 2,
2 a
3, 3.
TA EN A T CN PLA T wT NOURs 22 s8 iT FO 4 uN SUPPL w ant F ACiveE m LJJ@LZJ@
LAl@
LCJ@
10iO!1lof LYJ@
[jij@
LZj@
lZ[919,9;@
J3 34 3b 36 3J 40 el 4;
43 gg gy CAUSE DESCR4PTION AND CORRECrivE ACTIONS h i > lo i l Transmission lines trinned due to around fault and resultino overload.
I iii,ji The Reactor & Turbine-Generator subsequently trioned.
The.Emeroency li i 21 LDiesel Generators started and loaded per_. design and remained in service until Lock-out relays were reset and 500KV bus re-enercized when unit t
ii,3i tilai linads warp t rane forrod m ngally M sta rtun trans formers.
I hiW7s' ov-Ea si ATus @ !?sES.?v' v owta vasco.E oEscra,noN li i s I (E_J@ l 11 010 l@l NA i
LA.J@l NA l
Ah,v,,
CO' *, E N,
- o AMQuNT CF ACTiv1TV @ lLoci DON OF MEL E ASE @
REM AsED OF RELE AsE l i ic ' LZ_J @ LI._J@l NA l
NA l
,E sonnet E..osets ao cEsc.a,1,0~ @
nu..E.
1,E l i l 71 101 0 l 0l@[2 j@l NA l
EwsoN~E'L,,.3u'a'iEs a
cEsca. Tio~@
Nuu.En lilai 10l010l@l NA l
7 8 9 11 12 PO t yp E DEsCR PT ON l i l o l [2J@l NA l
7 A 9 10 g
piPTIC N W
LY issuEj@DE Newscacer account 1 lllll[llli i ((
LY l
2 o T
S 9
'O cs e,y go Chris N. Shively 501/968-2519 NAME OF PREPARER
,,gyg 8 0071 so 6@;
a.t 1.
~
Reportable Occurrence Report No. 50-313/80-022/01T 12.
Report Date: 7/7/80 3.
Occurrence Date: 6/24/80
~
- - 4
. Facility: ' Arkansas Nuclear One --Unit 0ne Russellville, Arkansas S.
Identification of Occurrence:
Conditions arising from natural events, that as a result of the event
-(partial loss of offsite power due to transmission line failure) require a unit shut down and operation of safety systems or other protective measures (ES bus voltage restored by automatic action of Emergency Diesel Generators).
Reportable per T.S.
6.
Conditions ' Prior to Occurrence:
Steady-State Power X
Reactor Power 2568 MWth Hot Standby Net Output-780 MWe Cold Shutdown Percent of Full Power 100 %
Refueling Shutdown Load Changes During Routine Power Operation Routine Startup s0peration Routine Shutdown Operation-Other (specify)
Steady state power operation with the Mayflower 500KV line (one of three 500KV lines) out of service.
7.
Description of Occurrence:
. At 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br />, switchyard circuit breakers tripped apparently due to a ground fault isolating the Mabelvale.500KV line.
The unit's generation, along with Unit.Two's generation, was transferred to the Fort Smith 500 KV line which. tripped open at the Fort Smith end,-as a result of feeder overload. The Mabelvale line became available again, but did not close R
into the ANO switchyard 500KV ring bus because of inability to sync-check.
The Morrilton East-161KV line-tripped on overload, following Unit Two's
. Reactor / Turbine trip, leaving only the 500K7 bus segment feeding the
.autotransformer and the Russellville East 161XV line carrying power generation.
Startup transformer #1 remained energized from the auto-transformer and startup transformer #2 remained tied to the 161KV bus.
5
- - s t
n--
,w-
_.,.=
Reportable Occurrence No. 313/80-022/01T
. Description of Occurrences (Continued):
A manual runback of reactor power was initiated following an automatic.
runback of generator output.
The reactor / turbine subsequently tripped,
- - and' auxiliary loads transferred to startup transformer #1 which was.already experiencing 'a low output voltage.
The auto transformer bank received lockout relay operation from an apparent-faulted relay, resulting in lockout relay-operation of startup transformer #1 (and Unit Two's startup transformer
- 3), placing both units without auxiliary bus voltage.
At this point, the switchyard-busses were de-energized except for the Russellvillle East tie to startup? transformer #2 (one source of offsite power), which remained energized.
_u a
1 4
.b!
Reportable Occurrence Report No. 50-313/80-022/01 T 8.
Designation of Apparent Cause of Occurrence:
Design Procedure.
Manufacture Unusual Service Condition y
Including Environmental
. Installation /-
Construction.-
Component Failure -
X (See Failure Data)
Operator Other (specify)-
Occurrence was caused by a loss of offsite transmission linetand aggravated by the resultant grid degradation.
9.
Analysis of Occurrence:
Coincident with the lock-out relay operation of Esartup transformer #1, both 'Dnergency Diesel Generators auto-started and re-energized ES buses A-3 and A-4.
At about 65 minutes from occurrence initiation, house loads were begun to.be ' sequenced back to Startup transformer #1.
The Reactor Coolant Pumps were sequenced on.
The reactor was fed by natural circulation.for approximately 100 minutes.
The final
- - plant conditions was hot standby.
n
.a
--.....L-- - --...--
J
ji
- {J Reportable ~0ccurrence. Report-No. _50-313/80-022/01 T
- 10. -Corrective Action:
AP&L Transmission line fault was clear 5d.
No plant site corrective action required as all plant systems operated per design.
11.
Failure Data:
Not applicable.
4
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000368/LER-1980-001-03, /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | | | 05000313/LER-1980-001-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | | | 05000368/LER-1980-002-03, /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | | | 05000313/LER-1980-002-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | | | 05000313/LER-1980-003-01, /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | | | 05000313/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000368/LER-1980-003-03, /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | | | 05000368/LER-1980-004-03, /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | | | 05000313/LER-1980-004-03, /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | | | 05000313/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000368/LER-1980-005, Forwards Revised LER 80-005/03X-1 | Forwards Revised LER 80-005/03X-1 | | | 05000368/LER-1980-005-03, /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | | | 05000313/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000313/LER-1980-005-03, /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | | | 05000313/LER-1980-006, Forwards LER 80-006/04L-0 | Forwards LER 80-006/04L-0 | | | 05000368/LER-1980-006-03, /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | | | 05000313/LER-1980-006-04, /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | | | 05000313/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000313/LER-1980-007-99, Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | | | 05000313/LER-1980-007-01, /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | | | 05000368/LER-1980-007-03, /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | | | 05000313/LER-1980-008-03, /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | | | 05000368/LER-1980-008-03, /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | | | 05000313/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000313/LER-1980-009-03, /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | | | 05000313/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009-03, /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | | | 05000368/LER-1980-010-03, /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | | | 05000313/LER-1980-010-03, /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | | | 05000313/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000313/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000313/LER-1980-011-03, /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | | | 05000368/LER-1980-011-03, /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | | | 05000368/LER-1980-012, Forwards Updated LER 80-012/03X-2 | Forwards Updated LER 80-012/03X-2 | | | 05000313/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000313/LER-1980-012-03, /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | | | 05000368/LER-1980-012-03, /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | | | 05000313/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000368/LER-1980-013-03, /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | | | 05000368/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000313/LER-1980-013-03, /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | | | 05000368/LER-1980-014-03, /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | | | 05000368/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014-03, /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | | | 05000368/LER-1980-015, Forward LER 80-015/99X-0 | Forward LER 80-015/99X-0 | | | 05000368/LER-1980-015-99, /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | | | 05000313/LER-1980-015, Forwards LER 80-015/01T-0 | Forwards LER 80-015/01T-0 | | | 05000313/LER-1980-015-01, /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | |
|