ML19261A561

From kanterella
Revision as of 22:07, 1 February 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
LER 79-003/01X-0 on 790120:22A Radiological Control Program Lower Seal Temp Alarm & 2 Gal Per Minute Increase in RCS Leak Rate Resulted in Manually Tripping of Reactor.Cause of Event Will Be Discussed in Followup Rept
ML19261A561
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 01/22/1979
From: Carroll J
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-79-003-01X, LER-79-3-1X, NUDOCS 7901260203
Download: ML19261A561 (2)


Text

Whi ~ T LICENSEE EVENT REPORT Ct NTROL BLOCK: l l l 1 l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o i 8 9 lMlDIClClN]2 @l010l-l010 0 l 010 l- 0 10 @l4 1Il1111l@l LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO l

$7 CAT 58 l@

con'T

?

o 1 8

3OORc 60 l L 61l@l 0 lDOCKET 510 NUMB l 0 ER l 0 l 3 l681 l 698 l@l 0 lDATE EVENT 1 l 210 l 7 75i 9 l@l0 74 R EPORT lDATE 1 l 2 l80217 I 9 l@

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 I Durina nomal coeration 22A RCP lower seal tercerature alam was received at I o 3 l0129. An approx. 2 gom increase in RCS leak rate was also evidenced by decreas- I o 4 lino VCT level. The reactor was manually tripoed at 0143 when increasina lower i o s I seal temperature exceeded 1950 F. An insoection of 22A RCP revealed a cracked I o s l weld on oumos lower seal oressure sensino line. Althouah the crack was isolable. I o 7 l due to increased bleedoff flow and fluctuatino seal oressure the decision was I o a Imade to replace seal assembly. Accordinaly, RCS cooldown was becun at 2015. (CONT) I 80 7 8 9 E CODE SUSC E COMPONENT CODE SL8 CODE S E 7

o 9 8

l C lB l@ lE l@ l Cl@ l Pl Ul Ml Pl Xl XI@ l B l@ lZ l@

9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE N O.

LE R/RO

@ ,aEg

_ l217l229]

l-l 23 l O i 01 31 24 26 1/l 27

[0]1l 28 29 lX l 30 l-l 31 32 0l A N A ON ON PLANT ME HOURS 22 S S I D FOR 8. SUPPL ER MANUFACTURER l33A lgl34 Fj g l5 3

Alg gj@

36 37 01 1 l 21 l 40

[g 41 l N jg 42 l43N l@ lBl5l8l0]@

44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS ro lCause of the event and corrective actions will be detailed in the follow-up I i 1i l report. I I

1 2 l 1 3 l i 4 1 I 7 8 9 80 STA  % POWER OTHER STATUS DISCO RY DISCOVERY DESCRIPTION Ooerator Observation i s lE @ l0l9l0l@l ' "

NA l l A l@l l

A$riviTY COTTENT aEt aSED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 1 6 8 9 l l @ l Zlgl to 11 NA 44 l

45 NA 80 l

7 PERSONNEL EXPOSURES ,

TYPE DESCRIPTION

  • NUMBER NA i 7 101010 l@l Z l@l l

[j

  • l

,ERSO~NE L ,N;u'!,ES

~u eER i x 1010l0lgloESCRIPTiO~@ NA ,

7 8 3 11 12 LOSS 05 OR D Au AGE TO FACIL!TY

'] 80 TveE D E SC RIPTION i 9 l Z lgl NA l

'SbE7v 7 Y i. M M 3 NRC USE ONLY ,

o I Y,f@o,3c,,,,,gy l @ NA l ll lllllll ll jj 7 8 9 to 68 E9 80 5

~

NAME OF PREP ARER PHONE:

. ~

PROMPT REPORT FOR:

LER 79-03 DOCKET N0. 50-318 EVENT DATE 01/20/79 REPORT DATE 01/22/79 ATTACHMENT EVENT DESCRIPTION AND PROBABLE CONSE0VENCES: (CONTINUED)

LERs 77-15 (U-)) and 79-1 (U-2) describe similar events.

.