ML19256A144

From kanterella
Jump to navigation Jump to search
LER 78-100/03L-0:on 781001,during Surveillance Testing, Calculated Value for Unidentified RCS Leakage Exceeded 1 Gallon Per Minute Limit by 0.08 Gallons Per Minute.Caused by Increased Reactor Coolant Pump Seal Leakage
ML19256A144
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 10/27/1978
From: Fulmer S
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19256A143 List:
References
LER-78-100-03L, LER-78-100-3L, NUDOCS 7811030158
Download: ML19256A144 (1)


Text

U. S. NUCLE AR REGULATCRY COMMISSION N RC' F O R *

(7-74 '

LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l 1h 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 0l0l- Q l0 lU lP j F j- 0l3 gl 4 l1 l LICENSE 1 ( 1 TYPE l 1 30l@[51 l lg I lTJT] l 0 l H l D l E l S l 1 14 5 LICENSE NU'/8EH 25 lb ui 56 7 8 3 LICENSEE CODE CON'T 0 i 5[n]lLJgl0l5j0l-[ 0 j 3 l 4 l 6 Q 1 ] O l 0EVENT fd 69 l1DATE l 7 [ 8 g[1 l 0 l2 14 15 l 7D ATE REPORT l 7 l8 l@ SO 1 8 b0 bl COCKET NUYBER 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> on 10/1/78, during perf ormance of surveillance testing, the calculated EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o l

[ol2l l At l

_o # a i value for unidentified Reactor Coolant System (RCS) leakage exceeded the 1 GPM limit o .: lby 0.08 GPM. This placed the unit in the Action Statement of Technical Specification l At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on 10/1/78, the increased leagage was identified by a l

o s l (T.S.) 3.4.6.2.

of the Reactor Coolant Pumps standpipe leak-off. .This reduced the uniden-l 101c] l measurement from the Action Statement of T.S. l l o j 7 ) l tified Icakage to 0.54 GPM, and removed the unit The small leakages were processed through the normal containment sump. l o 3 l3.4.6.2.

7 8 9 #"* #

COveONENT COoE SuSC$DE sus $E W -M G -118)

' C*$oE#'" C 0o e' Su0ci5e 10191 9

I cl Ijg gg iz lg [ zj zl zj zj zj z[g 10 11 12 13 18 19 z[g Iz j@

20 REV8SION 7 8 OCCUR R E NCE REPORT SEQUENTI AL TYPE N O.

,_ EVENT YE AR REPORT NO. CODE

=( g nT pqg 0 10 l-l 1013 l Ll l_] 0]

@ I 7[ 8 l_I 23 l1 24 26 21 26 29 3J 31 32

_ 21 22 8 $ PLI a.' A N FA DER

  • T O HOURS S 8 ITT D FO T

TAKE X

A l zl@ 01 0 01 01 I41 Yl@ l42M i@ l43Zl@ IZ IZ IZ (Z @

I 3.1 l@b@ O J PLl zl@

34 J's 30 3/ 40 44 4; CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Investi-Wgl Increased Reactor Coolant Pump seal leakage is the cause of this occurrence.

J 1i lii I gation into the possibility of installing more accurate seal leakage indication is l

, 2 [

continuing per Facility Change Request 78-357.

1 l i l 31 1 I

I i.141 1 80 7 8 9 ISCO Y DISCOVERY DELRIPTJON 32 OTHER STA TUS STA S  % POWER Test ST 5042.0. l i s WQ l0 { 0 l0 l@l NA l [Bl@l Surveillance A fivlTY CONTENT LOCATION OF RELE ASE RELF ASED OF RELF AW A*.10VNT OF ACTlviTV l NA l l NA 1

i e 8 9 Lzl @ LzJ81t1 10 44 45 80 PERSONNEL E APOSUnES NUPRER l l i l 71 1 0 1 0 1 0 @ ZTYPE "@DESCHIPTION PE RSONNEL INJUHIES NUV9En DESCniPTtON )

i H 101 0101@l12NA gg 7 8 9 11 LOSS OF oH D AM AGE TO F ACILITY TYPE DE SC HID TION l NA 7

i 9 8 9 lZl@l 10 NRC USE ONLY ,

Iss gN@j NA NCn tP TION  ;  ;;;;;;;;;;;; j jyjnj _

6s 69 80 5 7 a 9 to 76[ , M ()[ p g? 419-259-5000. Ext. 276 DVR 78-153 U PHONE:

N ANTE O PREPAHER