ML20038A051

From kanterella
Jump to navigation Jump to search
RO 2-76:on 760202,power Supplies to Motor Operated Backup Core Not Tagged in de-energized Position Per Tech Specs. Caused by Nonadherence to Tech Specs.Procedure Re Reactor Vessel Head Removal Will Be Modified
ML20038A051
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/01/1976
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
RO-2-76, NUDOCS 8109110228
Download: ML20038A051 (2)


Text

{{#Wiki_filter::

r:

Consumers ~ .) Power s Company l WwJ U o.ae. om... si e w., u ~,.. a.. . m m.m u., ~,...w. 4,.. c...,,... March 1, 1976 sa { F{-{ R (b c e Mr James G. Keppler Oelice of Inspection Enforcement g N g Region III LG Nuclear Regulatory Ccunission t b T99 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-155, DPR-6 LIB-2 LACK OF PROCEDURAL CONTROL BIG ROCK POLTr PLANT TT Attached is LER-2-76. This event occurred on february 2,1976 during reactor (, vessel head re= oval. R. B. Sewell (Signed) R R. Seve11 Nuclear Licensing A&sinistrator e 2065 \\ 8109110228 760301 PDR ADOCK 05000155 S PDR

s a / l / w I i ,/ N s f / i 8

a m n.,4....y.g x.y ,ya c.ypr w w..w. w y % h 2.L.s;L.4 %,i * - ccNm..udsnillIf OAllPU.= G. i '1 ~ evtwf azzpanes rc * -treMas estassen Jm auAse . Tv=e tree ., @ l Ml Il 3l R l P l 1_l. l 0lJ l. l 0l 0 ] 0l 0l 0 l-l0 l 0l Al!* l l'j ll1l1l _ O 3,g y; ' 0 7 ea 14 13 25 29 30 31 i so omt g QCONT l l l y.l 0l 5 l 0l-10l1l5 l S l l0l2l0l2l7l6l l 0 l 310 l 1l 7 l6 l 7 e 57 sa Se tio si se se 74 75 eo 'hion o. rin.T resetor vessel head removal %v - ^ for refueling, the power supplies l s 80 @ lto the ector-operated backup ' core ' spray valves were not' tar.ged'in the'de-energized l 7 89 80 ? O9 The redundant system was -- "' - " l Q l position as required by & Tech Specs. 80 7 89 o loperable. W ~ 4 -- CE" mt kated cooling flow would have been delivered to thel 2 feore. The valves power supplies were tagged upon discovery of the N NIL Mk 80 7 89 assas s,. caus. cem caot cow ow., coo. .,.u- . a, c,.a v.wo., I si rl LA] I zi z i zl ziz i zi LzJ 1z1919191 W o? 7 89 10 11 12 17 43 44 47 46 CAUSE DESCRIPTION A L __. N memo issued to all operating Q l Event caused by nonadherence to Tech Specs. BOk 7 89 l personnel to apprise thes of the incident. n d ii ' _ _ -- 1 f. _. a : - t E ^ - -' ' ~ lT 09 ggggg g p ". e0 .7 89 l j - ^' - ic '. --~ i.n. change vill be made to the reactor vessel head re= oval s _ '80 ' '7 89 6 00 o, s status % powen OTw a status 06Covtav C6Covter CascwicN 8 LHJ lololol I "A I izJ l NA ] 7 8 9 10 12 13 44 4S 46 6 soseA op acivftv CON?t%t 54 LEA 5&O 08 attE ASE A&#0VNT Of ACTNffy LOCATON CF e4 LEA $4 / y Wl NA l l NA 17 7 8 9 10 11 44 45 PERGCN.'EL EXPCSURES e.uweim tvrt CE SCNY CN gg l 0 l 0 l 0 l Wl NA l 7 89 11 12 13 PERSONNEL NJURif estamm a C15CM TCh l Ol 0l 0l l NA 14 0 7 89 11 12 PP.0 SABLE CONSEQUENCES g l m.is conditica could have cc.used personnel injuries and equi; ent da:ses. e 7 89 LCL OR DAMAGE TO FACUTY ts pe cascwTcm 8 Lil I "^ g sa 7 89 10 PUBLCTTY BE I NA I 7 e9 r"2-c so D / ACCfTICNAL FACTORS g l I', TIT OIOCRIPTIO:i (Ocn;,d) c h en 2-9-76. l 7 89 ] l ?A';3I T3:? :0:1 (0:r.td) nrocedure prior to the next use of the procedure. l 7 89 g _ _ _.}}