ML17173A616

Forwards LER 79-005/03L-0

ML17173A616
Person / Time
Site:	Dresden
Issue date:	02/09/1979
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A617	List: ML17173A616 ML19263C362
References
NUDOCS 7902220036
Download: ML17173A616 (4)

Text

e Commonwealth Edison Dresden Nuclear Power Station R.R. #1

• Morris, Illinois 60450 Telephone 815/942-2920 February*9, 1979 BBS LTR /179-139 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory CoUllllission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report #79-5/03L-0 Docket #050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B~2.(b), condtions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

ti, 71?. Ji,_~far- ¥,3 B.B. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:.lcg Enclosure cc: Director of Inspection & Enforcement*

Director .of Management Information & Program*Control File/NRC

11,.:11d w.

9 l , .

NTROL BLOCK: ._I_..___.___.I_*

I

__._l_..__l~ll~SEE EVE!:::.::~::OR TYPE ALL REOUIREO INFORMATION!

• 6 j [IE]' I I I LI DI RI s I 2 l(~I 0 I 0 I - I 0 I 0 I 0 I 0 I 0 I - I 0 I 0 IG)l 4 11 11 11 I 1 101 I 10

.j 7 . B 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58

~ .

~~~~~~ ~©I oI s I o I o I o I 2 I 3 I 7 101 o I i I 1 I 9 I 7 I 9 I© I o 12 I o I 9 I 1 I9 10

---* 60 ** ---***- 61.-.... DOCKET NUMBER 68 69 *EVENT DATE 74 75 REPORT DATE BO 1 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@

((J]J I During normal operation, D MSL downscale condition annunciated and shortly thereafter 1I

] [ill] a D MSt High Rad alarm and half scram occurred. Upon resetting both alarms, operator i [QJ}J I noted that both High Rad and the downscale lights were on. (T.S. Table 3.2.1 requires I 1

i CQ:II]

MSL high rad setpt. be< =.3 I I X backgro~nd radiation level at rated pwr.)

• Safety impli-1

((I)) cations minimal because three remaining MSL Rad Monitors would have performed as re-

, [ITI] I quired. Previous event ref. under R.O. #50-249/1977-43.

1 IIW I

BO j 7 B 9 SYSTEM CODE

• CAUSE CODE CAUSE SUBCODE COMPONENT CODE COMP.

SUBCODE VALVE SUBCOOE l le ID I@ L.:J@ ~@ 11 NI s1 Tl RI u1e L..:J@) ~@

I 9 10 11 12 13 1B 19 20

! LEA/RO CVENT YEAR SEQUENTIAL REPORT NO.

OCCURRENCE CODE REPORT TYPE REVISION NO.

@ REPORT NUMBER

• I 71 91 I I I 0 I0 15 I I /I I 0I 3 I L::j L=l *~

21 22 '23 24 26 . 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPR0-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED

• FOAM SUB. SUPPUEA MANUFACTURER

~@~@

33 34

~@

35 GJ 36 .

101010 37 I I ~@

40 41 LU@

42

.L~J@

. 43 -

I 44 GI 0 I 8 I 0 I@

47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @

DJ)) I Upon second occurrence of same event on 1/19/79 at 2000 hrs, D MSL Log Rad Monitor re- I rr::m placed with functional calibrated span>.. MSL .Log Rad Monitor which was removed later o::IIl found to have open circuit._ Monitor ~epaired and tested ~atisfactorily per DIS. 700-:1.

[IE) 7 B 9 BO FACILITY ljQ\ METHOD OF

• STATUS %POWER OTHERSTATUS v::::J DISCOVERY DISCOVERY DESCRIPTION @

ITTIJ ~@ I 0 I 8 I 8 1@)1-I_u_-_3_i_n_sh_u_t_do_wn~ ~@I Operational Event I

7 B 9 10 12 11 44 45 46 BO

' ACTIVITY CONTENT t::';;\

I RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE@

~ 1.21 @) l:.J(§ 1. . . - - - *_N_A_ _ _ __, 1* NA 7 B 9 10 11 44 45 BO

. PERSONNEL EXPOSURES ~ * .,-*

NUMBER (.;;\TYPE DESCRIPTION.

ITEl I 01 0 I 016L:J@L---_ _ _N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-:--__.

7 B 9 11 12 13 80 PERSONNEL INJURIES (.":\

NUMBER DESCRIPTION6 (QTI 01 01 01@)'-l_ _ _ _ _N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.....--------~

7 B 9 11 12 BO LOSS OF OR DAMAGE TO FACILITY t4J\

TYPE DESCRIPTION i.::.::J Em 7 ~

L.:J@I 9 10 NA PUBLICITY ISSUED(,;";;\ DESCRIPTION~

G\

~,.no222

';:J 00~ C) 0 NRC USE ON Ly 80 ITI2Ja LlU6.I 7

9 NA

~10______________.:.;:;.:;___ _ _~--~----------------~6B I I I I I I I I I I I I I~

69 BO* c;

. .* "'* Carl L;i.ndberg X-289 0 NAMEOFPRE?ARER----------------*~---'------- PHONE:---------------

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"Gbmmonwealth Edison PART 1[ .TI .!LE_., OF DEVIATION

• ID DEVIATION REPORT DVR NO.

D-12 STA UNIT YEAR 2 NO.

6 OCCURRED

-.1/19/79 1933 MSL __p_'._'_ !:_Iigh Ri'idi_ation - 1/2 Scram DATE TIME SYSTEM AFFECTED 1700 PLANT CONDITIONS TESTING MSL Process Rad: - - CJ -QQ Run 2222 -

725 MODE PWR (MWT) LOAD{MWE) YES NO DESCRIPTION OF EVENT , 1 At 1933 operator.got annunciation of D MSLRad monitor downscale. He immediately reset thE down scale and returned to the main control board. At that time he received a "D" 11SL Hi -Rad and 1(_2 scram. The operator immediately reset the 1/2 scram. Wheri he reset the .-Bi Rad *on "D" MSL he DESCRIPTION OF G:\USE (over)

Spiking on "D" MSL Rad MonitoL n-i(R APPL I CABLE I NFORMAT I-ON This occured a second time at 2000 hrs on the same day.

EQU(PMENT GU YES DR NO. WR NO.

T. Lang 1/19/79 FAILURE ONO NA 491 _ RE_SPQNSIBLE SUPERVISOR _DATE PART 2 I OPERATING.ENGINEERS COMMENTS Remaining three monitors would have performed the intended reactor safety function.

SAFETY-TYPE OF DEVIATION EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE ANNUAL - RELATED REPORTABLE OCCURRENCE PUBLIC INTEREST VIOLATION OCCURRENCE REPORTING WR ISSUED

.D 14 DAY D- 10CFR21 c;,.._._*o--- []** ......

YES W YES_ W

_J?\[] 30 DAY - ~~~1.~l.~~~I QN

i~ci;.'D-- -

i:. *~cL>O

~' -~lREPORTABLE cccu'F#~ENCE-

---*- _NUMBER ;;'.:'/':***

• -*: .".~.'..:; i'S:*::':): .. .'

~- *.

J .*

B8§6RIPTION OF EVENT

• noted that both the Hi *Rad & the downscale lights were tripped.

) ~~** .: . *.. '***.

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