ML17252B194

LER 80-022/03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125

ML17252B194
Person / Time
Site:	Dresden
Issue date:	05/27/1980
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR 380-440 LER 80-022/03L-0
Download: ML17252B194 (2)

Text

CommonwealtEdison.

Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920

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May 27, 1980 BBS LTR*ltB0-440 James. G. Keppler, Regional Director

• Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Connnission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report lt.80'-22/03L-0, Docket f/050.:..249, is .being submitted to your office in accordance with Dresden Nuclear 'Power -,

Station Technical *Specification. 6.6.B.2. (b) ,. conditions leading to operation iir...a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limitin.g condition for opera-tion.

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Station Superintendent Dresden Nuclear Power Station BBS:lcg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

'771 LICENSEE EVENT REPORT .

,.,**~~,[RQ,h BLOCK: .___..._.......___._ _.__.._I-__, 0 * (PLEASE PRIN~ OR TYPE AL.EQUIF.lED INFORMATION) 6 I J:D' I I IL ID 8 9 IR Is LICENSEE *CODE 13 101 14 15 0I 0 I -1 0 I 0 I 0 I 0 I 0 I - I 0 I 0 IQ)I LICENSE NUMBER .25 26*

41 :q ii ll .1101 LICENSE TYPE .. JO I.

57 CAT 58 10

1*;, . :~~i~iHl1-1©1° js-,0-r0--r0..:-r2--T4--19---1e1*0-c1-~--l-Ll--~Ls 8 . 60 61. -. DOCKET NUMBER . 68 69 EVENT DATE

• 1 o 1G::}1 o 15 1.2 1 s 1s: 10 74 75.- -* REPORT-DA:r:E. ___89 I© EVENT DESCRIPTION AND PROBABl:.E CONSEQUENCES@ . , . . . . - - - ----*

JI] I ~ring normal shutdown conditions, IRM 12 downscale rod block was found to. trip at tJIJ 1 4/125. Tech. Spec. Table 3.2.3 requires. trip point to be*> I =-.S/125 ... This .was of

!J}J. I minimal safety significance since the remaining channels in 'the "A" safety system .and till. I all. of the. channels in the "B"

• safety system were operable. There* was no effect on I iJ]J* I public heal th or safety. Previous occurrences:. R.O~s 75:...45/03L~b,*78-l/03L-0, 79-11 tl2J.~a_n_d_._1_2_1_0_3_1-_o__. ___________________~----------------..,..,...---'-----------.,..,.-~----------__,

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SYSTEM CAUSE CAUSE COMP.

• VALVE CODE CODE SUBCODE COMPONENT CODE. sue CODE suacoDE tm 11' IA I@ L!J@*~@ 11 IN js l_T IR 1u I@ ~ ~J@

B* 9 10 11 12 . 13 *18 - 19 20 SEQUENTIAL '.OCCURRENCE REPORT* REVISION

(,':;\ LE A/AO CEVENT YEAR REPORT NO. CODE TYPE NO.

~ _REPORT I8 I0 I l=:J I o 12 ., 2 I I oI 3 I ~ l2.J NUMBER .

21 22 23 24 26 27 . 28 29 30 . 31 32 ACTION F.UTURE *EFFECT . SHUTDOWN r:;::;..,. ATTACHMENT. NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :;us. .SUPPLIER MANUFAC_TURER .

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33 34 35 36 37 40 41 . 42 .. 43 44 47 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @

f:))J !The cause was due to electronic drift of IRM 12. The trip point was immediately re-*

tDJ 1adjusted to 6 percent decreasing and DIS 700-4 'was. successfully completed. *DIS 700-,.4 I tITl 1 will continue to be performed weekly.

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STATUS  % POWER OTHER STATUS ~ DISCOVERY . DISCOVERY DESCRIPTION. '231

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80 ACTIVITY CONTENT *

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-r-;-,RELEASED. OF RELEASE . . AMOUNT OF ACTIVITY l(V LOCATION OF RELEASE @*

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. 8 9 10 . 11 -44. 45. 80 PERSONNEL EXPOSURES ~

. NUMBER (':;".:;\TYPE DESCRIPTION

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ao PERSONNEL INJURIES ~

NUMBER .DESCRIPTION\~2l E I 01 01 Oj@L...-_.;_*_ _N_l_A..:...*--------------~--------------'

8 9* 11 12 8()

LOSS OF OR DAMAGE TO FACILITY Q I v:::;

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~,0-------------------------------------------------------'80 PUBLICITY . . G\ NRC us.E ONLY ISSUED a DESCRIPTION~ "'

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