ML20084D858

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Ro:On 700810,deficient Standby Liquid Control Pumping Circuits Discovered.Caused by Crystallized Borate Solution on Discharge Relief Valve.Valve Cleaned & Reinstalled
ML20084D858
Person / Time
Site: Dresden 
Issue date: 08/25/1970
From: Hoyt H
COMMONWEALTH EDISON CO.
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
References
03211, 3211, NUDOCS 8304120493
Download: ML20084D858 (2)


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ILLINORS AdJn.n ts,4 to-POST OffICL kOX 787 /; C if l C A G O, li t t N O l$ a0690 Drordca Nuclenr icuor Station R. R. El l' orris, Illinois 60450 tea ~,

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August 25, 1970

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Dr. P e Le r i.. Jerris, Director

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.s Division of Ronctor Licensing g'<cA, q U. S. Ato::ic Znorgy Comission

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Dear Dr. :

orris:

SUN:7'T:

lienrme ET.9-19 I'c ~ aen "nel w c cmor St-tion Unit 2, Section 6.6.C.3 of thn iec'cM en?.b neificati one This is to report a corrlition r olating to the opern u cas of the statio-s'd eh one cf the ~ Luo n:y liquid Control rumping circuits (P.lO was fou: d Lo havc; a testa specified in section 4.4.A.l.ecptcity deficiency during the nonthly surveillance Proide" nrd Initini Action On l'onday, August 10, 1970, the routino nonthly surveillanco was perfor.,:cd on the standby liquid control system.

The results on 2A punp were satisfactory; but 23 pump indicated approximately half of rated ca-pacity.

Investigation revealed that the 23 pur.p dischargo relief valve uns lifting at approxinate3y 1100).

This resulted in dilution of the stand-by liquid control tank uith n350 gnl. of clean deninoralised unter, raising the level to 82%.

Standby liquid control pu:np 23 uns decla cd inopornble.

Daily surveillance uric begun on the redundant punp 2A.

The tank was sanulod and boron cencontration uns found to bo 12.4%.

The tank level was'lowored to ?!d to br$ng it back within normal level requiremonts.

Investi~ntion nnd Corrective Action

.03211 The valve was removed on August 12, 1970, by :naintenance and I

found to be hold epen ly crystallizcd borate solution.

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The valvo was cleaned and reinstalled, a satisfactory test on g

B pump was conducted on Auguct 12, 1970.

8304120493 700825 PDR ADOCK 05000237 g

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1 Dr. Poter A. :' orris Auguct 25, 1970

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!. Station Revicu Board review concluded that the safety of the i

plant was not jropardicc0 because the systen uns operable uithin the re-I ouironent of tho Technical Specifications nrd the redundant cenponents 1

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j operability uas demonstrated daily ~as required by the Technical Specifi-cctions.

Station personnel perfor,ed satisfactorily and in accordance with approved procedures.

It was also concluded that the crystallization at tho valve could not have nrevented its intendca relief function, and prob-ably,:ould not rescat after unintentianally exceoding its sol pressuro 3

J during the surveillance test.

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