ML17252A292

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Letter Submitting Reportable Occurrence Number 050-249/1977-17 in Accordance with Technical Specifications, Section 6.6.B
ML17252A292
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/21/1977
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS77-543 050-249/1977-17
Download: ML17252A292 (3)


Text

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-t' Commonwealt.ison Dresden Nuclear Power Station R.R. #1

  • Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltt~ II 77-543 Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations - Region U. S. Nuclear Regulatory Commission 799 Roosevelt Road June 21, 1977

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  • Glen Ellyn, Illinois 60137 Enclosedplease find Reportable Occurrence report number 50-249/1977-17.

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

  • BBS:sm
  • Enclosure

.cc: Director of Inspection & Enforcement

- Q+/-l_1YJ~.

  • ~~. B. Stephenson r ~tation Superint.endent Dresden Nuclear Power Station Director of Management Information & Program Control
File/NRC I

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[P~E PRINT AU. REQU-IRED INFORMATIO *~ :.

LICENSEE

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-@E] I I :1 L ID I RI s I 3 I 7 - 8 9 14 CATEGORY

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57 sa REPORT

-T'YPE-w 59 EVENT DESCRIPTION Jo;.

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25 REPORT SOURCE DOCKET NUMBER

-LICENSE TYPE -

l4 f 1 11 I l I 1 I 26 30 EVENT CATE -.

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74 EVENT TYPE -

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31 32 REPORT OATe 10 16 12 I 117 75 7!

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--- @El I The Technical Specificatioru( state that an APRM _is considered -inoperable if it is 7 89:;--------~---~---=----~-____ -:._~--~--~~--------__;,~-----------=-----~----...:...---~-

@El I receiving less that so% o"f its normal complement of i.PRM inputs. --During normal a~

7 - 8 9 fo141 plant operation, APRM 114 was found to generate an i'INOP" when 60% of the LPRM inputs sf 7

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60.

lolsl I were -bypassed.

Because-APRM 114 has 20 LPRM inputs, -the "INOP" should have been 7

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  • W I I IN I s I TI RI ul

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I GI o I 8 f o I UJ 1 a s 10 11 12 11 43 -

44 47 49 CAUSE DESCRIPTION-The trip reference card for APRM 114

-~ I The event-was attributed to-electronic -drift.

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was adjusted to obtain the -"INOP" indication when the APRM was receiving less than.

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-El§] I -50% of its normal-complement of LPRM inputs.

Although this type of failure has so I

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_1 - as FAc:uTY

- - STATUS METHOD OF DISCOVERY (continued)SG

"-POWER DISCOVERY DESCRIPTION

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__ I ol 7f o J OTHER_ STATUS NA LU NA 1 a-s 10 12' 13 44 45 46 BO

.FORM OF-ACTIVITY -

- CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY rn w LzJ __, _____ -_.-N""""A----~.;._j' 1 a s

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'. - LOCATION OF RELEASE NA

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BG PERSONNEL EXPOSURES

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TYPE

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i2 PERSONNEL INJURIES

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- OFFSITE-CONSEQUENCES EE NA J

- 1 as Su LOSS OR DAMAGE TO FACILITY

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  • 'EVENT' DESCRIPTION (Continued) of this event were minimal since the remaining two APRM instrument channels in the "B" Reac.tor Protection System would. have provided the required reactor scram.

(50-249/1971..;.17)

CAUSE DESCRIPTION (Continued) occurred before,* the APRM "INOP'.' points will continue.to lbe checked via DIS 700-6; a monthly surveillance, to ensure t{µieiy identification of a~y re~urring problem.

The.trip reference cards are General Electric type GE136Bl319Gl