05000249/LER-1978-001, /03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109%

/03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109%

ML17252A345
Person / Time
Site:	Dresden
Issue date:	03/06/1978
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR # 215-78 LER 78-001/03L-0
Download: ML17252A345 (2)

LER-1978-001, /03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109%

Event date:
Report date:
2491978001R00 - NRC Website

text

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I Commonwea.Edison Dresden Nuclear er Station R.R. #1 Morris,,;irlinois 60450 Telepho~*e 815/942-2920 BBS LTR # 215-78 I

James G. Keppler, Regional Director l

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Directorate of Regulatory Operations ~ Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence 'Report /178-001/031'-0, Docket f/050.... 249 is hereby submitted to your office ~n accordance with Dresden Nuclear Power Sta-tion Technical Specification 6,fr.B,2.(b), conditions leading to ~pera t;i.on in a _d_~g:r!3,-_ded mod_~- pg_r:_mij:_te4,_J>y __ _§l limiting condition for operation *

• • -----... ::~-_------------.** :-

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."" ----=---

BBS:dlz Enclosure p e Station Superintendent Dresden Nuclear Power Station cc:

Director of Inspection & Enfo*rcement Di-rector of Management Information.,& Program Control File/NRC

}1i1~R G 1978

U.S. NUCLEAR REGULATORY COMMISSION

• ecENSEE EVENT REPORT...

CONTROL s4ocK: I I

1 G)

1

~~....__..~......___..___._~6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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I I I ~l n I RI s I 3 IG)I o I o I -1 o I o I o I *a I o I - Io lo l(i)I 41 ll ll 1 I 1 101 I I G) 8 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE *JO 57 CAT 58 CON'T

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~~~~~~ LJJ© I o I 5 I o I o I o I 2 I 4 I 9 101 o I 2 I o-I 2 I 1 I s 101 o I 3 I & I i I 1 I s I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@.

C£J]J I While performing monthly surv. DIS 700-4,. IRM 1115 & 16 were found to~trip at 109%,

CQJI]

T.S. (Table 3.2~3) requires trip of </= 108/125 of full scale, Safety implications.

minimal ~;ince remaining channels *in "Au safety system and all channels in "B" safety i )"

system were operable and* found within existing Dresden setpt. limits(~ t/-1%.

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similar event occurred on ILDRS2~ Docket 050..-237, LER 1177-7.*

CITIJ ITTIJ 7

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SYSTEM CODE I If Al@

9 10 t:":;\\

LER/RO LEVENT YEAR.

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REPORT I 71 Bl NUMBER 21 22

CAUSE

CAUSE CODE SUBCODE COMPONENT CODE w@ w@

rl NI sl Tl RI ul@

• 11 12 13 lB SEQUENTIAL OCCURRENCE REPO.RT NO.

CODE I I 1010111 I/I fo/31 23 24 26 27 28 29 COMP.

SUB CODE w

19 REPORT TYPE

.L!;j 30 VALVE SUBCODE w@

20 31 ACTION FUTURE EFFECT SHUTDOWN

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ATTACHMENT NPRD-4 PRIME COMP.

SUPPLIER REVISION NO.

LQJ 32 COMPONENT MANUFACTURER 80 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :iUB.

Li@W@ W@ W I al al al al Lill{§* LNJ@

33

. 34 35 36 3 7 40 41

. 42 UJ@ I c I a I s I al CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

43 44

.47 I Cause - instrument drift.

IRM' s 1115 & 1116 were readjusted to 107% and procedure DIS CIIIJ I 700-4 successfully completed, Rod block would still have occurred at 108% (i.e. re-

((I1] I maining channels in spec).c:.:t& provide adequate tolerance for possible. electronic drift

. *f

.ITIIJ I and/or human interpretation errors, all IRM rod block set pt' s will be lowered to 106 ITIIJ I +/- 1%.

I~W s will continue to be tested monthly, 7

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FACILITY STATUS

% POWER OTHER STATUS METHOD'OF

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80 ITli] W... I ol 61 ol@I..... __

'""""NA=-_

8 9

10

'12 11 DISCOVERY

. DISCOVERY DESCRIPTION ~

l__ai~~'~~~~~R~o~u~t~i~n~e._.,S~u~r~y~e~1.*1.1~a~nu.-.c~e~~~~....;..~~

ACTIVITY CONTENT

(.:;;;\\

RELEASED OF RELEASE

,. AMOUNT OF ACTIVITY [ill] W @) LI@'-1 ___

N=A.:,.__ _

7 8

9 10 11 45 46 80 7

44 LOCATION OF RELEASE @

44 45 NA 80 PERSONNEL EXPOSURES r.:;:;..

NUMBER * ~TYPE

DESCRIPTION

[!TI] 1 o 1*a1 o J0w@1---__._. ______

...:;.:N=A-* ______________

7 8

9 11 12 13 BO PERSONNEL INJURIES

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NUMBER

. DESCRIPTION~

filI] I 0 I 0 I 0 l@i__ ____

.. ------~N!!,!A;__ ________________ ____.

8 9

11 12 80 LOSS OF OR DAMAGE TO FACILITY 143' TYPE

DESCRIPTION

v::.::;

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~@)1-..------------,..---___:N~A:__ ______________

8 9

10 so ISSU=~~~gCRIPTION@

'NRC USE ONLY.

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N_A_*------~. II 1111111111*1~

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68 69 80 ;

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