ML20084U318

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AO 72-86:on 721201,passive Containment Sys Crud Activity Increased.Caused by Loss of Hydrogen & Buildup of Oxygen. Primary Effort to Restore Hydrogen,Power Reduced & Improvement in Problem Detection Initiated
ML20084U318
Person / Time
Site: Palisades 
Issue date: 06/17/1974
From: Ashworth G
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Buzy J
US ATOMIC ENERGY COMMISSION (AEC)
References
AO-72-86, NUDOCS 8306280625
Download: ML20084U318 (8)
v • d • e


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{{#Wiki_filter:F c '. ~p. .l J .,U ggggg{g g < A. g' any gg. Palisades Nuclear Plant: Route 2, Box 154, Covert, Michigan 49043 June 17, 1974 Mr. J. Suzy Operator Licensing Branch Divi:Jon of Reactor Licensing Atomic Energy Comission Washing'.on, D. C. 20545

Dear Joe:

Enclosed are copies of Palisados Plant Unusual Incident Report 72-86, PRC minutes of 4 December 1972, and a graph compiling chemistry data from the primary coolant system for the period 25 November through 5 December 1972, all of which pertain to the crud release incident to which you referred in your totecon on 8 Juno. I hope this data will satisfy your needs, but if I can be of further assistance, please call or writo. Sincerely yours, . J. Ashworth Training Coordinator 'f 4 l l t / , V' f /' ['$ DR O COPY SENT REtM00 +"a=

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c -; <..: .~ i% ' * - t [. h= r.[q'?- N,.. TITLE PCS' Crud Release' ~; 3 - 4 DATE 12/1/72 .(.. .' DESCRIFTIOI!;(Use ttacM.cnts as required) ' TIME II/ R '. D [ $c.. .During.the period of 11/29/72 - 12/1/72 it became evident that a sizeable E7.Jv.' amount'.of " crud" had been released to PCS water, due to loss of.hydroge'n and build-3 :...n .up o.f oxygen. ..n. .,a. ..~.a.,,:. n : y.n:. .s. a.:. .,:.m.... .....x... <:.e

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v. t w- ..The effects were seen as follows: ~.y [...:.. f. 7 f. E'? - ~ '... ~.. b. :.. :.:.. .r ..... :- = ;::+a-W.~~ U.:+ e-MP %.? (over) -..p '..? :l'; .,j;,, ~ .; f ~ '.... ] '-i,'.. ; -f li. PCS crud activity increases. v. ,i c.. e. .!1.I7 k.I.'IA THORIZATIO:I FOR 32EDIATE AIID ECESSARY COR?2CTIVE ACTIOHi . 1. ' D,.' i c.c. Com.ni' p.;..C. N' ) I SHIFT SUPE?JISOR All DUTY & CALL SU$RVISca JLewis OTHER (Specify) W J. 3.... C.- Lewi.s 4 >;.. ~' D2GDI TE CORRECTIV3 ACTICI!: (Useattachedpagesasrequired) p.:.~.- 3 -Primary effort was to restore hydrogen cc/kg in the' PCS' vater'. A slight ~ h : * ':, c ' -,- ^ power reduction was taken on 12/2 to ec=pensate for' the possibility of. increased hw. . _. m u,~ ..a.,, c n .c. - q;. . -. ;.". ;,a;.. v. s. ~ .,:\\ y* *;c-f,. ~ ~ + : .l. z 3i s q ;.e. .' 5' ',, 'f N ..., '. 2k*' '.c..; Ne ",:y' ;,' \\ '

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3. ' Decrease in letdoun recen ht. exchanger efficiency.

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$v'q s -~ O / .O. {.A,,4 ~ = > l CONSUIERS P0h'ER COMPANY Palisades nuclear Plant ',I s PLANT REVIEW CCS!ITEE MEETING Members Present: December 4, 1972 e IMiausler - Chairman TWEiward GJAshworth JGLewis JRSchepers - Construction GHHein 'FTPeyton JAMeincke DRHughes IMLangschwager BRChurchill REMcCaleb - Scribe FEFlynn - C.E. -.A. OLD BUSINESS ^ ~~ ~ 1. _ Chlorination of Service Water The chlorination of the service water system was not completed this I past Scturday as calm did not prevail on the lake to allow cample gathering. Per the PRC's apprcval last'wcek this event will be scheduled for the first Saturday on which the lake is calm. / p .i ! 2. Eellows Clutch Modification for CRDM's .)- Per the C.E. uruduelion model testing prop, rams, three production model bellows were undergoing the 10,000 cycle fatigue testing when one clutch failed to disengage after approximately 7,000 cycles. Subsequent investigation by C.E. has indicated that the cause of failure was excessive wear on the clutch jaws. The testing set-up used by C.E. has a continously driving motor. This can cause abnormal wear on the teeth of the clutch mating faces when the clutch is energized. It is believed that this abnormal wear en the clutch teeth caused a break down of the protective coating and'albwed metal-metal contact i-between the mating faces. The binding foice that resulted from this contact did not allow the clutch to disengage. Further investi-gation is being conducted by C.E. ~ 3 Facility Changes 137-5&6 (T-99 tie in to T-29 and T 80) T'hese' tie-ins will be delayed until just before the next refueling outage. They will be discussed at that time. 5 B. Na1 BUSINESS 4 f Incident 72-86 PCS Crud Release (see attached Report) u i j A substantial crud release in,the Primary Coolant System during the r? peried of 11/29 through 12/1 necessitated the dilution of the reactor - l Ij , coolant by approximate 40 ppm boren to maintain constant power.

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Subsequent investigation of this incident revealed that the PCS ? had fallen significantly prior to the crud release t dissolved H2 (See table I.) On11/29theChemistrydepartmentnotifiedOperations of the lou disolved Hp and suggested they investigate. Operations found the bottles on the H2 manifold to be empty. These were blanket on the replaced and attempts ~were made to restore the H2 Volume Control Tank. Later chemistry reports showed the dissolved to still be very low as late as 12/1. Operations continued to H2 review the problem and on 12/1 closed the second isolation valve for the N2 purge to the VCT. Subsequent dilutions became less frequent a and the chemistry results for the next day (12/2) shoved near-nomal dissolved H2-The PRC was particulary concerned with the reasons that allowed such c condition to develop and prevented its earlier detection. A local alarm is provided on the hydrogen control system for the generator. This alam, although not on the line to the VCT, would sense low pressure in H2 manifold. Operations informed the committee that the set point for this alarm isd75 psig but because we have been operating at less than full power (6073), the generator is maintained with 45-50 psig H. Therefore the alarm is continously in 2 and is paid no heed. This s.ituation should be remedied. Earlier / detection would have been possible (the attached table shcus the sharp drop of dissolved Hg) if it had been more dramatically presented. Currently the chemistry department furnishes operations with a daily sheet of numbcrc. Potentially serious problems could be more easily detected if these daily sheets were limited to fewer parameters and if these parameters were presented in chart form so that a trend could be readily ident,1fied. The present system hinders such early identification. The committee made-recommendations as follows: 1.' Engineering should study the hydrogen system and either add an alam to identify low supply pressure to the VCT or change the existing alam set point on the-generator H2 system so that lou pressure in the H2 manifold will be recognized. 2. With C.E.'s consultation, the more important chemistry parameters should be identified and only these parameters should be " presented on the daily chemistry sheet to Operations. The daily chemistry sheet should be modified to present-these parameters in graphic fom so trends can be identified. ~ 3 Operations should be alerted that this incident and the resulting , net 40ppmdilutionhasaddedapproximately$'/onegativereactivity i to the core. This process maybe reversible and borations equalling $8/> reactivity may be necessary in the future to maintain constant - power. e. e 6 s y .m.. ...u,

r. _,. O-O i i l i i I H sw s, s Plant Review Committec MeetinS / 4. .C.E. suggested that the current plan of dropping fourteen control rods once during each tuo week period be reviewed. The small crud burst associated with each single rod drop may be severly compounded by dropping fourteen rods in a short time pericd. The one rod a day dropping procedure may reduce the severity of the crud problem. PCS DISSOLVED GAS TABLE TABLE 1 c All Units in.cc/Kg Date Total 02 N2 Hp Actions 11/25 33.89 o 14.54 16.94 11/27 30 5 o 20.69 4.99 11/28 31.15 o 27.22 1.82 11/29 31.02 .25 28.72 0.60 H2 bottles found / cmpty and replaced 11/30 32 5 .09 27.93 o.'69 12/1 h2.42 .15 37 14 1.05 2nd N is lation 2 valve closed. 12/2 3 56 19.6 13.2 22/3 41 9 12.1 28.8 C. ' FACIIJTY CF.A*.'3P.3 '5 n....,. O k ^*

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