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LER-1981-056, /03L-0:on 810716,torus Water Temp Exceeded 95 F. Caused by Elevated Cooling Water Temp Due to Hot Weather Conditions.Torus Cooling Procedures Performed in Early Morning |
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| 3661981056R03 - NRC Website |
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NRC F ORM 36G U. S. NUCLE AR REGULATORY COMMISSION (7 7{}
LICENSEE EVENT REPORT
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8 60 61 DOCK ET NUMBER 6h b9 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h i0i2, puring normal operation, torus water temperature exceeded 95 F.
No sig-1 nificant occurrence took place as a result'of this event.
This type I
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g pvent is applicable to both units and was last reported by report no.
I io,,jp0-321/1981-078.
This event temporarily degraded the quenching ability 1
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This event posed no threat to public health or safe-l g o ;, j i y.
No redundant system exists for the torus.
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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h FriUJ lThe cause of this event can be attributed to hot weather conditions.
I [High river water temperatures reduce the effectiveness of torus water I
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Corrective actions which have been taken are describedI lin the attached narrative.
No further corrective actions will be taken.]
,, i No further reporting is required.
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LER #:
50-366/1981-056 Licensee:
Georgia Power Company Facility Name:
Edwin I. Hatch Docket #:
50-366
Narrative
Report for LER 50-366/1981-056 During normal unit operation it was noted that torus water Lemperature had reached 940F, and torus air temperature had reached 1050F.
At this point torus water cooling procedures were initiated.
This action causes torus water to be routed through residual heat removal system heat exchangers and then back to the torus.
The result of this action was a temporary increase in torus water temperature to a maximum of 980F.
Continued cooling operations then brought the water temperat-ure back down to below the Tech Specs limit of 950F.
The consequence of this occurrence was a temporary degradation of the steam quenching capability of the torus water.
The magni-tude of this degradation was small, and this occurrence did not significantly reduce the safety factors associated with containment integrity.
No redundant system exists for the torus.
This event posed no threat to public health or safe-ty.
This type event is applicable to both units and was last reported by LER #50-321/1981-078.
The cause of this event is mainly attributable to the elevated cooling water temperatures common to this time of year.
The temperature increase that occurred upon initiation of torus water cooling operations was a result of heat transfer from torus air to torus water which occurred due to return water spraying; normally, removal of heat from the torus water by the RHR heat exchangers would account for this effect with a final result of water temperature reduction.
However, high cooling water temperature reduced the effectiveness of this function.
In order to minimize the frequency of this type of occurrence torus cooling procedures are performed in the early morning when cooling water temperatures are lowest.
Also cooled water can be returned directly into the torus water uithout spraying it thru the torus air.
Which return path to use is determined by the shift foreman prior to commencement of cooling procedures.
This ensures that every attempt is made to maintain the torus water at the lowest possible temperature without ever exceeding the high temperature limit.
Since this is a seasonal effect no further procedure changes or design modifications will alleviate the problem.
Therefore, no further corrective actions will be initiated.
No further reporting is required.
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| 05000366/LER-1981-001-03, /03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris | /03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris | | | 05000366/LER-1981-001, Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | | | 05000321/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000321/LER-1981-001-01, /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | | | 05000366/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000366/LER-1981-002-03, /03L-0:on 810106,reactor Core Isolation Cooling Steamline Pressure Switches 2E51-NO19A & C Were Found to Actuate Below Tech Spec Limits.Caused by Setpoint Drift. 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Caused by Misalignment of Cam Follower Contact W/Main Programming Cam.Follower Adjusted to Maintain Contact W/Cam | | | 05000321/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000366/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000366/LER-1981-006-03, /03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed | /03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed | | | 05000321/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000321/LER-1981-006-03, /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-007-03, /03L-0:on 810203 & 19,unit 1 Cable Spread Room Sprinkler Sys Was Inoperable for Period Greater than 14 Days & Special Repts Were Not Issued.Caused by Personnel Error. 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05000366/LER-1981-012-02, /02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced | /02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced | | | 05000366/LER-1981-012, Forwards LER 81-012/02L-0 | Forwards LER 81-012/02L-0 | | | 05000366/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000321/LER-1981-013-03, /03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired | /03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired | |
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