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LER-1981-008, /03L-0:on 810206,output Amperage for RM-CC-106 Reduced in Nonconservative Direction.Caused by Failed Remote Indicator Module in Auxiliary Bldg.Module Isolated & RM-CC-106 Recalibr.Monitor Will Be Repaired |
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| 2811981008R03 - NRC Website |
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NRC FORM 366,.
(7,771 LICENSEE EVENT REPORT.
.UCI.E~R REGULATORY COMMISSION CONTROL BLOCK: I 10 IPLEASS PRINT OR TYPE ALL REQUIREC INFORMATION)
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60 61 COCKET NUMBER 68 69 EVENT CATE 74 75 REPORT CA, c 80 EVENT OESCrllPTl°ON ANO PROBASLE.CONSECUENCES @*
! With Unit 2 operatin.g:*steady state.at 100%. power, a scheduled calibration of RM-CC-
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I 106 disclosed a failed remote indicator (in Aux. building) producing an error in
[))TI I RM-CC-106 output in a non-conservative direction.
Operating in. this condition, the L lirI] I Component eooling System's surge tank vent valves wouldn6t have automatically closed
[]JI} iat twice background as per T.S. 3.7, Table 3.z;-s.
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DJ:Il. !The remote indicator module.failed resulting in a reduced output signal.
CIII] 1was isolated and RM-CC-106 was recalibrated.
REVISION:
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ATTACHMENT*, PAGE 1 of 1 SURRY POWER STATION, UNIT 2 DOCKET NO:
~0-281 REPORT NO:
81-008/03L-O EVENT DATE:
02-06-81 e
TITLE OF EVENT:
RADIATION MONITOR (RM-CC-106) ERRONEOUS SIGNAL
- 1.
DISCRIPTION* OF EVENT:
With Unit* 2 operating steady state at 100% power; a--scheduled-*cal**ibr*atiC>n* *-*--*--- -.. -. -
of R..'111-CC-106 disclosed a failed remote indicator* module (in Aux. Building) producing an error in the output of RM-CC-106 in a *non'-c-o*nservative d:Lrecfioff~- -----**......
Operating in this condition, the Component Cooling System's surge tank vent valves would not* have automatically closed at twice background *a:s-per-T~ S.
3.7, Table 3.7-5.
This event is reportable in* accordance with Tech. Spec. 6.6.2.b.(2)~
2 *. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:
The failed module resulted in a radiation reading less than actual (approximately 2/3 of actual). This would not prevent the Component Cooling System's surge tank vent valves cillosing automatically.
However, a. value slightly higher than the Tech. Spec. limit would have been required.
Thus*
the health and safety of the public were not affected.
- 3.
CAUSE
The remote indicator module for RM-CC-106 failed r~sulting_in reduced output amperage (displayed in counts per minute).
This output also supplies the alarm/valve actuation circuits*
- 4.
IMMEDIATE CORRECTIVE ACTION
The failed module was isolated fromt:the system and RM-CC-106 recalibrated.
Indication and alarm displays were still available_ in th.e.. controL room *. --
. --- -----~
5 *. SCHEDULED CORRECTIVE ACTION:
The failed monitor will be repaired and retw;ned..-to -sePTiee-. - - - ***-** --... ---* --*--------------
- 6.
ACTION TAKEN TO PREVENT RECURRENCE:.
None-
- 7.
GENERIC. Il1PLICATIONS :
This was considered a random event and possesses no generic implications.
--t.--..
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| 05000280/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000280/LER-1981-001-01, /01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired | /01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired | | | 05000281/LER-1981-001-03, /03L-0:on 810102,one Boric Acid Flow Path to Core Inoperable.Caused by Personnel Inadvertently Closing Valve 2-CH-226.Flow Path Restored & Personnel Reinstructed | /03L-0:on 810102,one Boric Acid Flow Path to Core Inoperable.Caused by Personnel Inadvertently Closing Valve 2-CH-226.Flow Path Restored & Personnel Reinstructed | | | 05000280/LER-1981-002-03, /03L-0:on 810122,radiation Alarm Setpoint for Component Cooling Sys Found Greater than Twice Background. 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Monitor Reset to Proper Setpoint & Returned to Svc | | | 05000281/LER-1981-006-03, /03L-0:on 810114,at Full Power,C Safety Injection Accumulator Found to Have Boron Concentration of 1943 Ppm, 7 Ppm Below Required Limit.Caused by Leakage Through Check Valve 1-SI-144.Valve Isolated | /03L-0:on 810114,at Full Power,C Safety Injection Accumulator Found to Have Boron Concentration of 1943 Ppm, 7 Ppm Below Required Limit.Caused by Leakage Through Check Valve 1-SI-144.Valve Isolated | | | 05000280/LER-1981-007-03, W/Unit 1 Defueled & 2 at 100% Power,Power for Several Radiation Monitors Lost.Caused by Shorting of Test Lead to Ground Causing Supply Fuse to Blow.Fuse Replaced.Monitors Returned to Svc | W/Unit 1 Defueled & 2 at 100% Power,Power for Several Radiation Monitors Lost.Caused by Shorting of Test Lead to Ground Causing Supply Fuse to Blow.Fuse Replaced.Monitors Returned to Svc | | | 05000281/LER-1981-007-03, /03L-0:on 810114,at 100% power,PT-27 (Heat Tracing) Revealed Amp Readings for 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Filter Banks Were Found to Be Less Efficient than Required by Tech Spec.Caused by Formation of Void Areas Due to Settling of Charcoal in Filters.Charcoal Added | | | 05000280/LER-1981-015, Forwards LER 81-015/03L-0,updated LER 81-035/03X-1 & Corrected LER 81-036/03L-0 | Forwards LER 81-015/03L-0,updated LER 81-035/03X-1 & Corrected LER 81-036/03L-0 | | | 05000280/LER-1981-015-03, /03L-0:on 810603,spent Fuel Pit Overflowed Into New Fuel Handling Area & Outside to Storm Drain.Caused by Leaking Diaphragm Valve & Defeated High Level Alarm Annunciator.Valve Repaired | /03L-0:on 810603,spent Fuel Pit Overflowed Into New Fuel Handling Area & Outside to Storm Drain.Caused by Leaking Diaphragm Valve & Defeated High Level Alarm Annunciator.Valve Repaired | | | 05000281/LER-1981-015-03, /03L-0:on 810315,PT-26.1 Revealed That Process Vent Radiation Monitor Pump Failed to Rotate.Caused by Failure of Pump Bearings.Pump Replaced | /03L-0:on 810315,PT-26.1 Revealed That Process Vent Radiation Monitor 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RCS Pressure Reduced Below Setpoint | | | 05000281/LER-1981-018-03, /03L-0:on 810318,amp Readings for Heat Tracing Panel 10,circuit 4A,were Below Acceptance Criteria Per PT-27.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested | /03L-0:on 810318,amp Readings for Heat Tracing Panel 10,circuit 4A,were Below Acceptance Criteria Per PT-27.Caused by Excessive Heat.Defective Heat Tracing Replaced & Tested | | | 05000280/LER-1981-019-01, /01T-0:on 810707,urgent Failure Alarm for Control Rods Occurred,Indicating Rods Were Inoperrable.Caused by Blown Fuse in Power Cabinet.Fuse Replaced | /01T-0:on 810707,urgent Failure Alarm for Control Rods Occurred,Indicating Rods Were Inoperrable.Caused by Blown Fuse in Power Cabinet.Fuse Replaced | | | 05000281/LER-1981-019-03, /03L-0:on 810218,amp Readings for Heat Tracing Panel 9,circuit 6A Were Low.Caused by Excessive Heat.Heat Tracing Replaced | /03L-0:on 810218,amp Readings for Heat Tracing Panel 9,circuit 6A Were Low.Caused by Excessive Heat.Heat Tracing Replaced | | | 05000281/LER-1981-020-03, /03L-0:on 810223,during Full power,RM-CC-106 Alert & High Alarm Lights Energized W/O Initiating Required Automatic Action.Caused by Failed Card in Alarm Circuit.Card Replaced & Tested | /03L-0:on 810223,during Full power,RM-CC-106 Alert & High Alarm Lights Energized W/O Initiating Required Automatic Action.Caused by Failed Card in Alarm Circuit.Card Replaced & Tested | | | 05000280/LER-1981-020-03, Ae Notified Util of Seven Masonry Block Wall Sections in Fuel Bldg Not Meeting IE Bulletin 80-11 Design Requirements.Cause Not Stated.Block Walls Will Be Replaced | Ae Notified Util of Seven Masonry Block Wall Sections in Fuel Bldg Not Meeting IE Bulletin 80-11 Design Requirements.Cause Not Stated.Block Walls Will Be Replaced | | | 05000281/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000280/LER-1981-021-03, /03L-0:on 810704,chemical Addition Tank Found to Contain 86% of Vol Required,Following Level Transmitter Recalibr.Caused by Use of Pure Water Instead of Sodium Hydroxide Solution in Original Calibr Procedure | /03L-0:on 810704,chemical Addition Tank Found to Contain 86% of Vol Required,Following Level Transmitter Recalibr.Caused by Use of Pure Water Instead of Sodium Hydroxide Solution in Original Calibr Procedure | | | 05000280/LER-1981-021, Forwards LER 81-021/03L-0.W/o Encl LERs 81-022/03L-0 & 81-028/03L-0 | Forwards LER 81-021/03L-0.W/o Encl LERs 81-022/03L-0 & 81-028/03L-0 | |
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