LER-1980-051, /03L-0:on 800821,w/unit in Mode 2,C Feedline Containment Isolation Check Valve 2-FW-126 Did Not Meet Post -maint Valve Cycling Test Requirements.Caused by Failure of Valve to Shut Completely Due to Burr on Pivot Pin Bushing |
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| 3391980051R03 - NRC Website |
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text
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k U.S. NUCLEAR REGULATORY COMMISSION
. LICENSEE EVENT REPORT l CONTROL BLOCE / / / / / / /-(1), (PLEASE' PRINT OR TYPE ALL REQUIRED'INFORMATION)
-/0/1/
/V/A/N/A/S/2/ (2),
/0/0/-/0/0/0/0/0/-/0/0/ (3)
/4/1/1/1/1 (4)
/ / / (5)
LICENSEE CODE LICENSE NUMBER LICENSE TYPE.
CAT V0/1/
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/0/8/2'/1/8/0/ (8) /0 /9 /1/6 /8 /0 / (9) l/L/ (6)'
/0/5/0/0/0/3/3/9/
i-DOCIET NUMBER EVENT DATE REPORT DATE-
. EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10) i
/0/2/
/
On Auaust 28, 1980,- with the Unit in Mode 2, the "C" feedline containment Isol./
1/0/3/ -/
' check valve, 2-FW-126, did not meet the Acceptance Criteria of the post maint- /
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'enance valve cyclina test. On August 21, 1980 it was determined that the sub- /
/0/5/
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Ject valve had not been tested followins maintenance.- 'Both are inconsistent
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with T.S. 3.6.3.1 an'd reportable pursuant to T.S. 6'.9.1.9.b.
Since containment /
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isolation was available from redundant valves via the feedwater isolation'sys- /
/0/8/
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tes the-health'and safety of the-seneral'public were not affected.
/
. SYSTEM
CAUSE
CAUSE COMP.
VALVE 4
' CODE CODE
- - SUBCODE COMPONENT CODE-SUBCODE SUBCODE a
-/0/9/
/H/H/ (11) /E/ (12) /B/ (13) /V/A/L/V/E/X/ (14)' /C/ (15)
/A/ (16)
SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
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~.(17). REPORT NUMBER
/8/0/.
/-/ /0/5/1/
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ACTION.
FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION.
ON PLANT -METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
/B/-(18), /Z/-(19) /A/-(20) /A/ (21) /0/0/4/6/ (22) g/ (23) /N/ (24) /A/ (25) /C/6/6/5/ (26' 1
- - CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)
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Since the valve had not been operability checked following maintenance,a test /
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was written'and performed with unsatisfactory results. The valve did not scet /
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the' Acceptance Criteria because of mechanical problems which prevented the
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valve from seatina. ~With the plant in Mode 5,. maintenance was performed and
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the valve was retested with acc~eptable results.
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FACILITY METHOD OF-i STATUS
% POWER
- - OTHER STATUS
/ (30) DISCOVERY
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DISCOVERY DESCRIPTION (32) t 4
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/B/ (28)
/0/0/0/ (29) /
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/B/-(31)
/ Quality Assurance Inspection /
ACTIVITY-CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)
LOCATION OF RELEASE (36)
./1/6/-
/Z/-(33)
-/Z/ (34)-./
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PERSONNEL EXPOSURES:
NUMBER TYPE' DESCRIPTION (39)
/1/7/-L/0/0/0/(37)/Z/.(38).-/
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PERSONNEL INJURIES NUMBER
~
DESCRIPTION (41)
/1/8/./0/0/0/-(40) /
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LOSS OF.OR DAMAGE TO FACILITY (43)-
TYPE-,
,"L'.SCRIPTION i/1/9/,/Z/ (42),- f NA' -
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c PUBLICIT0.
- ISSUEDE. ~ DESCRIPTION.(45)
NRC USE ONLY
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'NAME'0F PREPARER W.~R.
CARTWRIGHT' PHONE <
(703) 894-5151-g 7-1 ~_
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j Virginia.ElectricLand Power Company-North Anna Power Station, Unit 2 Attachment: Page 1 of 2
. Docker No. 50-339 Report No. LER 80-051/03L-0 P
Description of Event
_. L0n Augusti 21, 1980; Quality Assurance determined.that the "C"
~
feedline containment isolation check valve, 2-FW-126, had not been tested following maintenance..On August 28, 1980, with the anit in mode 2, the subject valve was tested with unsatisfactory results. This-required that the plant be shut down and placed in mode 5sto perform required maintenance on the valve. Upon disassembly of the valve, a burr was found on the pivot pin bushing which prevented the valve ~from closing completely. The component was repaired and the cycling test was 4
. reperformed with acceptable results.
Probable Consequences of Occurrence s=
The feedline check-valves along with other containment isolation valves ensure that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or~ pressurization of the containment. The feedwater isolation valves provide a redundant backup to the feedline check valves in that feedwater is isolated _upon a safety injection signal. High containment pressure will actuate-safety injection which also provides for feedwater isolation. Since feedwater piping design i
pressure is much greater than the containment, it is conservative to assume that the length of piping betssen the feedline check valve and the feedwater isolation valves can maintain integrity above the maximum pressure of the containment. For this reason, the health and safety of the general public were not affected.
Cause of Event
The feedline line check _ valve failed to shut completely due to a burr located on the pivot pin bushing. Maintenance was performed on this valve during construction prior to release of the feedwater system to VEPCO at which time the bushing was damaged.
LImmediate Corrective Action After the valve was-initially tested and failed, the plant entered the action statement of T.S.3.6.3.1 and was in cold shutdown within the required' time period. Maintenance was performed on the valve and the i
valve was retested with satisfactory results.
11 Scheduled Corrective Action A surveillance. test will be performed periodically and upon com-
- - s pletion of all maintenance required on the valve.
S o
,s.
46 '
Attachment: -Page 2 of 2 Actions Taken to Prevent Reccurrence Scheduled. testing of this valve has been placed on the Periodic 'est Program Log to insure that all required testing is. performed.
Generic Implications
- - There are no generic implications.
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| 05000338/LER-1980-001-01, /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | | | 05000338/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000339/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000339/LER-1980-001-03, /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | | | 05000338/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000338/LER-1980-002-01, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | | | 05000339/LER-1980-002-01, /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | | | 05000339/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000339/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-003-03, /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | | | 05000338/LER-1980-003-03, /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | | | 05000338/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000339/LER-1980-004-03, /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | | | 05000338/LER-1980-004-03, /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | | | 05000338/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000338/LER-1980-005-03, /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | | | 05000338/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-005-03, /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | | | 05000339/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000339/LER-1980-006-03, /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | | | 05000338/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000338/LER-1980-006-03, /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | | | 05000338/LER-1980-007-03, /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | | | 05000339/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000339/LER-1980-007-03, /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | | | 05000339/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000338/LER-1980-008-01, /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | | | 05000339/LER-1980-008-03, /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | | | 05000338/LER-1980-009-03, /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | | | 05000339/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000339/LER-1980-009-03, /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | | | 05000338/LER-1980-010-01, /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | | | 05000339/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000339/LER-1980-010-01, /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | | | 05000339/LER-1980-011-03, /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | | | 05000339/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011-03, /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | | | 05000339/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000339/LER-1980-012-03, /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | | | 05000338/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000338/LER-1980-012-03, /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | | | 05000338/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-013-03, /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | | | 05000339/LER-1980-013-03, /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | | | 05000339/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000338/LER-1980-014-03, /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | |
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