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{{#Wiki_filter:- -                          .                                                  - -
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gl            Reactor Coolant Pu=p 1-1-2 tripped removing one of the two Reactor                                                                      j i as                                                                                                                                                    so Eles          Coolant Pu=ps of the loo; froc operation. Station in Action Statement                                                                      [
w      t.
f 81, of Technical Specificatien 3.4.1.                                                            OTP-33-77-641 l
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LCJBJ 49 to LBJ  la Lit l2 I o 1 TI o 1 RJg1                        tsj 43            44            43 LNJ 44 1                        CAUM Of5CmartsoN oi    [ The B&C phase surge, capacitors were discovered' to be damaged. ' Wes'tinghousq dl*has. determined this is due to a design deficiency. A Facility Change                                                                                so es g (Request has been prepared which requests modifications be made.                                                                    ,
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                                                                                                                                                                              ,o Jacque Lingenfelter/ T. Beeler                                                                (419) 259-5000, Ext. 251 DVR 123-1
 
i TOLEDO EDIS0N COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR TIR NP-33-77-64 t
DATE OF EVENT _: August 27, 1977 j                  FACILITY: Davis-Besse Unit 1 Reactor Coolant Pump Motor 1-1-2 was declared IDENTIFICATION OF OCCURRENCE:
inoperable on August 27, 1977.
The plant was in Mode 2, with Power (MWT) = 125 i                      Conditions Prior to Occurrende_:
i and Load (MWE) = 0.
Reactor Coolant Pump Motor 1-1-2 tripped at 1740 hours Description27, of Occurrence 1977,              _:with instantaneous ground (50GS) and differential current on August                                                                            This placed the Station into the relay (87m/A-B-C) targets indicating the fault.
Action Statement of Technical Specification 3.4.1 since one of the two Reactor Coolant Pumps in the loop were not in operation.
Upon inspection of the Reactor        d l
Designation of Apparent Cause of Occurrence:                                                    Coolant It has been determined        Pump 1-1-2 moto by Westing-1                B&C phase surge capacitors to be damaged. house the desian of th J
There was no danger to the health and safety of the Analysis of Occurrence:                              The thermal power was at a low valus and the i
l
^
public or Station personnel. remaining three Reactor Coolant Pumps were s The high flux and the flux-delta-flux setpoints were reset for    i l Specification Corrective Action:
three pump operation as required by the Action Statement of Techn ca 3.4.1.
Station maintenance personnel replaced C-phase surge capacitors and re-installed B-phase surge capacitors after caulking the crack in the porcelain an opening in the seas with RTV silicone sealant.
Reactor Coolant Pump 1-1-2 was declared operable.
At 0058 hours on August 31, 1977, This removed the station from Action Statemr at of Technical Specification 3.4 an inspection was made on the remaining reactor coolant pump On August 29, 1977, motors.
A defective              capacitor was found in A phase for Reactor Coolant Pump                                A 1-2-2 Station maintenance personnel                            replaced A phase surge capacitor with a new one.
78-470, has been prepared which requests all the RCP Facility Change Request,                                                                                      by Westinghouse.
1 motor capacitors be modified to the new mounting design recommended Failure Data:_ No previous similar events have occurred.
        .. . , _            -_-        ..    - - , - _              -}}

Latest revision as of 23:47, 26 February 2020

RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped Removing One of Two Reactor Coolant Pumps of Loop from Operation.B&C Phase Surge Capacitors Were Discovered to Be Damaged Due to Design Deficiency
ML20027A375
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 09/22/1978
From: Beeler T, Lingenfelter J
TOLEDO EDISON CO.
To:
Shared Package
ML20027A371 List:
References
NUDOCS 7811210382
Download: ML20027A375 (2)


Text

- - . - -

I I 1

LICENSEE EVENT REPORT CoNinot stoCa

.L L.1 I I f_J.

'v.~:e ..--s........ ~we c ,n .~,-

@ 0 (H l DlB l S ilj , l OJ -j 010 l N1 P lF l -l0 l 3) 4l11,1j ll1 }

.....o.v

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eo . m. ~u... . .N.~. ... ...o.,o...

con'1 l [ 0l3l 0 1 034 1 1 16 l8 f2 17 !71_7 10191 212 17 17 t vtNT 081CasPf eon .

gl Reactor Coolant Pu=p 1-1-2 tripped removing one of the two Reactor j i as so Eles Coolant Pu=ps of the loo; froc operation. Station in Action Statement [

w t.

f 81, of Technical Specificatien 3.4.1. OTP-33-77-641 l

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  • ITA" c'T! co. n-, ~, c on, 'd.Wr' I.r ,7.~,'u"', .

tw 11 1210 i v....... .

8)

LCJBJ 49 to LBJ la Lit l2 I o 1 TI o 1 RJg1 tsj 43 44 43 LNJ 44 1 CAUM Of5CmartsoN oi [ The B&C phase surge, capacitors were discovered' to be damaged. ' Wes'tinghousq dl*has. determined this is due to a design deficiency. A Facility Change so es g (Request has been prepared which requests modifications be made. ,

m a as

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,o Jacque Lingenfelter/ T. Beeler (419) 259-5000, Ext. 251 DVR 123-1

i TOLEDO EDIS0N COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR TIR NP-33-77-64 t

DATE OF EVENT _: August 27, 1977 j FACILITY: Davis-Besse Unit 1 Reactor Coolant Pump Motor 1-1-2 was declared IDENTIFICATION OF OCCURRENCE:

inoperable on August 27, 1977.

The plant was in Mode 2, with Power (MWT) = 125 i Conditions Prior to Occurrende_:

i and Load (MWE) = 0.

Reactor Coolant Pump Motor 1-1-2 tripped at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> Description27, of Occurrence 1977, _:with instantaneous ground (50GS) and differential current on August This placed the Station into the relay (87m/A-B-C) targets indicating the fault.

Action Statement of Technical Specification 3.4.1 since one of the two Reactor Coolant Pumps in the loop were not in operation.

Upon inspection of the Reactor d l

Designation of Apparent Cause of Occurrence: Coolant It has been determined Pump 1-1-2 moto by Westing-1 B&C phase surge capacitors to be damaged. house the desian of th J

There was no danger to the health and safety of the Analysis of Occurrence: The thermal power was at a low valus and the i

l

^

public or Station personnel. remaining three Reactor Coolant Pumps were s The high flux and the flux-delta-flux setpoints were reset for i l Specification Corrective Action:

three pump operation as required by the Action Statement of Techn ca 3.4.1.

Station maintenance personnel replaced C-phase surge capacitors and re-installed B-phase surge capacitors after caulking the crack in the porcelain an opening in the seas with RTV silicone sealant.

Reactor Coolant Pump 1-1-2 was declared operable.

At 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br /> on August 31, 1977, This removed the station from Action Statemr at of Technical Specification 3.4 an inspection was made on the remaining reactor coolant pump On August 29, 1977, motors.

A defective capacitor was found in A phase for Reactor Coolant Pump A 1-2-2 Station maintenance personnel replaced A phase surge capacitor with a new one.78-470, has been prepared which requests all the RCP Facility Change Request, by Westinghouse.

1 motor capacitors be modified to the new mounting design recommended Failure Data:_ No previous similar events have occurred.

.. . , _ -_- .. - - , - _ -