ML19261A814

LER 79-003/01T-0 on 790120:during Normal operation,22A Lower Seal Temp Alarm Was Received & RCS Leak Rate Increased. Caused by Cracked Weld on 22A Lower Seal Pressure Sensing Line.Design Change Is in Progress

ML19261A814
Person / Time
Site:	Calvert Cliffs
Issue date:	02/01/1979
From:	Carroll J, Watkins S BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19261A808	List: ML19261A807 ML19261A814
References
LER-79-003-01T, LER-79-3-1T, NUDOCS 7902080196
Download: ML19261A814 (2)

Text

LICENSEE EVENT REPORT

. CONTROL BLOCK: U 1

l l l l l@

6 (PLE ASE PRINT OR TYPE ALL REQUIRED INF ORMATION)

E L4 01 C l C i n t 2j@l 0 01-10 01010 14 0 - 10i_o_j@l411liliill@l 25 26 LICLNSE TYPE JO $7 C A T $8 i@

7 8 9 LICE NSE E CODE lb LICE NSE NUUtf EH CON'T

?

o i 8

"[,7, l L l@l 0 l 5 l 010 l 0 l 3 l 1 60 61 DOCKET NUMBER 868l@l690 l 1 EVENT 2DATEl0 7l9}@ 0l2l0l1l7I9!@

74 75 HEPOHT DAT E 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 1 Durino normal operation 22A RCP lower seal tennera_ture alaIILwas received at I 1 o 131 l 0129. An aoprox. 2 onm increase in RCS leak rate was also evidenced by I o 4 idecreasino VCT level. The reactor was manually trinned at 0143 when increasing i o s I lower seal tennerature exceeded 195 F. An insnection of 22A RCP revealed a I o e cracked weld on numos' lower seal pressure sensino line. Al though_the crack i op was isolable, due to increased bleedoff flow and fluctuatino seal nressure. I o a i the decision was nade to replace seal assembly. Accordinalv. RCS cooldown (CONT) I 7 8 9 80 C DE CODE SUPCO E COYPONENT CODE SUBCODE SU ODE 7

o 9 8

lC]Bl@ lE @ l C l@ l P l Il Pl E l X l x l@ LA_J@ Lz_l 9 10 11 12 13 18 19 20

_ SE QUE NTI AL OCCUR R E NCE HEPOHT R E VISION LER EVENT YE AR HEPORT NO. CODE TYPE N O.

@ ,agg/RO RT l7 9 [-j l 010 31 l/l l011 lT l l- [0j

_ 21 22 2J 24 26 27 28 29 30 31 32 TAKEN A T N ON PLANT M T4 HOURS 22 SUBMIT D FOR b 8. S PPLI MANUF AC UHER lAlgl34 33 Fl g l sal @ LBJO 3 36 I 011191 it I41 Yl@ l42N l@ W@ l44B l 5 l 8 l 0l@

3/ 40 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i o lUpon investigation the cracked weld was located downstream of the second louer I li t i l l seal sensing line isolation valve. Weld repairs will be nerformed at the next I

, 7 l available outace. The cause of the cracked weld is believed to be due to I

, 3 l vibration faticue. An enoineerino study, as referenced in LERs 78-50 (U-2) i i 4 l and 79-l'IU-2) is underway to recommend desion chances to correct the problem. I 7 8 9 80 ST S  % POWER OTHER STATUS D SCO R DISCOVE RY DESCRIPTION l5 Isl [Ej@ l 0l 9l 0]@l NA l l A l@l Operator Observation l ACTlvlTY CO TENT HE LE ASED OF RE L E ASE AMOUNT OF ACTIVITY LOC ATION OF RELE ASE i 6 Lzj g ogl NA l 45 NA 80 l

7 8 9 10 11 44 PER5ONNE L EXPO 5URES NUYBE R TYPE DE SCHiP TION l i j 7 l l 0 l 0 l 0 l@l Z l@l NA l nnSoN~d'imULS

~UMu R li la l l 0 0 0l@lDESCniPiiO~@ NA l 7 8 9 31 12 80 LOSS OF OH DAMAGE 10 F ACitt TY Q TYPE DE SCRIPTtON N/

NA l 7

1 9 8 9 Zl@l10 80

_. PUBLICITY -

NRC USE ONLY

, o ygf"'"' "

ng 7902080 / % i i i i i i i i i ;ii lj 7 8 9 10 08 69 80 ;

NAME OF PREPARER J. T. Carroll /K. S. Watkins psONe 301 234-7943/7960 {

ATTACHidENT T0:

LER 79-03 DOCKET NO. 50-318 EVENT DATE 01/20/79 REPORT DATE 2/1/79 EVENT DESCRIPTION AND PROBABLE CONSEOUENCES: (CONTINUED) was begun at 2015. LERs 77-15 (U-1) and 79-1 (U-2) describe similar events.