ML17252A200

From kanterella
Jump to navigation Jump to search
Transmittal of Reportable Occurrence No. 50-249/1976-7
ML17252A200
Person / Time
Site: Dresden  
Issue date: 05/27/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. /t412-76 50-249/1976-7
Download: ML17252A200 (3)


Text

".

Commonwec4t Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. /t412-76 May 27, 1976 Mr. James G. Keppler, Regional Director Directorate of R~gulatory Operations -Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois.

60137 Enclosed please find Reportable Occurrence number 50-249/1976-7.

This. report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B.

BBS:smp Enclosure

~lrlf<~

~. :B. Stephenson f"' Station'-£uperintendent Dresden Nuclear.Power Station cc:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC JUM 5807

e LICENSEE E~ENT REPORT e

i.

CONTROL BLOCK: l 1 I I I I I I

[PLEASE PRINT ALL REQUIRED INFORMATION]

LICENSEE NAME

@EJ 1.:i: I L I DIR IS 131 7

8 9 14 REPORT CATEGORY

@ill CON'T I I I n:EJ 7

8 57 58 59 EVENT DESCRIPTION 6

LICENSE.

LICENSE NUMBER TYPE 10101-10101010101-10101 14 I / I I I ) I /1 15 25 26 30 REPORT SOURCE LbJ 60 DOCKET NUMBER 101s1.o 1-10 IZ.14191 EVENT OATE 10141 ~1817161 61 68 69 74 75 EVENT TYPE

~131 31 32 REPORT OATE I I I 80

[filfil I Oo>-1)1! !.?:~>:~I !?/~Mf?E1 7 -F,1/ow111\\.J. 7hc: _>>*e~vo../ o-£ zhe. ____ Jf:~C:~'t"* _ __

80 la13i ~-"r--~* s:+~>'VL

£r.~

Se..;~~-~--~--------~n

~Q..:... r-.:-;,_--t--.-e)(

fo io ~

'*1 7

8 9"'-. _ _,.;-

'\\------.... -

  • .---;,.-*-~-*-*., ___.-

*~.

80 iali ! occ11"'r-'\\d

\\'Yl 7he. 3-B __.. a~£.9s s S)' s/en=t.

7he--~hetc.oa. ~ -.

ad

@Ifil la:..A-~o,(j?s.,YS

f,-L'Te.Ys

\\.veYe.

h:-1c:tLS:Sed Q._J o J?o ho<1>-S1 I 7 a 9

/

T~,.._.

1 J a

(§]ID Ji,*-#,*

c::t.. c:t.

\\.:1..--e..Ye r-ec~*,.\\.... ~d hJi'ti11e 7

8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE f Ohi COMPONENT CODE SUPPLIER MANUFACTURER

@0 IMIBI 12-12'.l'i!l~l~l-ZI LAJ IZl91'1191 VIOLATION LM 7

8 9 10 11 12 17 43 44 47 48 CAUSE PESCRIPTION ialaJ ! J~e. Ca.vSe ~-f~?!e. ~!~~f> nct:(... ~~o~; j bowe.ve.~: ;/,-s ad

~

_:_Q..

4~~+. lh;_~ 'h J.1ro ~

  • I

~-A I

Y\\ I °f'L

-~

-~'

  • 7 8 9

~"-';-"'-~,~-

--,.._,._.::1_,r;- - --- - --

- -----?----._)

mg I C&...us~.J

\\,,... 1 s7"cA-'Tr<:.. e)e<!-Tv1*c.irv.

(c.o°"'7\\V\\veJ) 7 89' 7

80 I

80 FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOVERY l.£1 lo ISi 71

,v /1

~

EEl DISCOVERY DESCRIPTION A/J 7

8 9

1 a 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT RELEASED OF R~L_EASE AMOUNT OF ACTIVITY rn l@J

  • lM I 2..B z..s c,'

d LOCATIPN OF;;R LEASE (

~l_l!~~~,_*J_.....ZI--~R~x__..B~J_J~----~e,...~h.~'*~~-M~~-,Y~--1 45 J

80 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION N A EEJ* IO 10101. ~ _I ________________ _, ______ !

7 8 9 11 12 13 80 PERS'ONNEL INJURIES NUMBER DESCRIPTION

[iEJ IOIO 10 I l _____.,....-__

,v_,4 _______________ _

7 8 9 11 12 ea*

OFFSITE CONSEQUEt>)CES Eifil I 'Ib ~Tia:h J. G S.E. p 7

8 9 o-:T-fs r Je S a"" n /e eo!/tt1~I r

BO LOSS OR DAMAGE TO FACILITY

  • TYPE Elfil. ~

DESCRIPTION I

Al A

7.

8 9 10 80 PUBL[CITY EI?.l I fuss I

7 8 9 80 ADDITIONAL FACTORS

~ I

  • Pa >"b'C.v fo..Te.

ye, J-<.a.:Je.

I 7

8 9

80.

NAME: ____,,,;::C _ _.!i

........ _.... S_o.._.y""'"V+-fl..-=---n-__ -_J _____ PHONE: 9-9-Z..- e.. 2 ~o

.GPO 881*667

EVENT DESCRIPTION (continued) and reactor power was reduced. to clear the alarms..

After tne* al*arms had. cleare.d, power was slowly increased until 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />, when an apparent off-gas.explosion occurred.

Reactor power was further reduced to approximately 360 MWe.

Standby steam jet air ejector (SJAE)

"3Awas placed in service; However, further investigation indicated that the rupture diaphragm in both SJAE's had been damaged, and a unit shutdown was initiated and completed by 1038 hours0.012 days <br />0.288 hours <br />0.00172 weeks <br />3.94959e-4 months <br />.

Off-gas.

system explosions have occurred previously on both units 2 and 3.

'corrective action implemented was replacement of the failed diaphragms and the "3B" off-gas filter.

.(050-249/76-17£))

CAUSE DESCRIPTION _(continued)*

The explosion apparently failed both SJAE diaphragms at the same time.

It is assumed that *the pressure wave failed the rupture diaphragms in*

both the operating SJAE "3B'i andQthe standby SJAE "3A" due to leakage through the discharge valve.

  • Although personnel on shift at the time reported hearing two expiosions, no evidence could be found to support this theory.

The "3B" off:....gas filter ir].: service at the time of the explosion. was damaged and subsequently '*~eplaced. Prior to the unit startup,* lDOth f:i,l_ters were tested. ancf 6fr-gas system valve lineups were verified to be correct.

An investig~tion of this ~nd other.. previous off-gas explosions has been initiated.

The investigation wil.l address the origin and prevention of off-gas syst.em explosiqns.


~--, - -- - - -

~,,,. '.

1

. \\_:

~ ~.