ML20031C290
| ML20031C290 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/13/1971 |
| From: | Fiorelli G, Sniezek J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19219A392 | List: |
| References | |
| 50-155-71-05, 50-155-71-5, NUDOCS 8110070030 | |
| Download: ML20031C290 (8) | |
Text
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> G.g U. S. ATOFIC ENERGY COVPISSION DIVISION OF COPPLIANCE
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REGION III C
INSPECTION REPORT
.s CO Report No.: 71-005
%9 Subj ect: Consumers Power Company Dockat No. 050-0155 Big Rock Point License No. DPR-6 Charlevoix, Michigan Priority Q-Q Category C
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Dates of Inspection: June 8, 9, and 10, 1971
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.m Date of Previous Inspection: May 13, 1971
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Type of Licenses: BWR - 240 Mut (CE) l(:,g.
Type of Inspection: Spa
- 1. A ouped, Principal Inspector:
I.
ezek
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Acccmpanying Inspectors: J. E. Hyder, Radiation Specialist, CO IV l
D. L. Pomeroy, Nuclear Engineer, CO HQ R. S. Cleveland. Health Physicist, CO:HQ Other Accompany g Personnel:
H. S. North, Radiation Specialist, CO V e
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Reviewed By:
F2i/.TioTelli, Senior Reactor Inspector kN
'Date Proprietary Information: None icb I
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8110070030 713716~
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PDR ADOCK 05000155 A
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SECTION I I W:
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E nforcement Action: None
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Licensee's Action on Previously Identified Enforcement Fatters: None required,
- ,u.e Unresolved Items 3,
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Verification of line losses associated with particulate and halogenf
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sampling of stack releases has not been made.
(Paragraph 9)
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Status of Previously Reported Unresolved Items:
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None reported
.tf Unusual Occurrences j.
f Centrol Rod C-3 would not withdraw during control rod exerci6ing on u
May 26, 1971.
(Paragraph 8)
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Persons Contacted The following Consumers Power Company (CP) personnel were contacted during l
the inspection:
C. J. Hartman, Plant Superintendent i
G. C. Tyson, Assistant Superintendent D. Bixel, Reactor Engineer i
R, Doan, Shift Supervisor
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C. Axtell, Chemical and Fadiation Protectica Supervisor i
R. IIaueter, Electric Production Superintendent - Nuclear (Jackson)
E. Purri, Corporate Health Physicist (Jackson)
Management Interview TFe fc!1cwJng subjects uere discussed with Messrs. Ilartman, !!aueter, rysen, Aytell, snd !:urri at the conclusion of the inspection.
A.
Line losses associated with sampling of particulates and halogens during stack releases.
Mr. !!aueter stated that a correlation of line losses weuld be performed. lie also stated that since the percentage of allowable activity releases is so low there is no problen in reeting the license requirements.
(Paragraph 9)..
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B.
Palf unction of Control Rod C-3.
Fr. Hartman stated that the maltunction of another control rod concurrent with the existing inoperable rod would be cause for an immediate controlled shutdown of the reactor.
(Paragraph 8) ff.
C.
Gland Seal Condenser Monitoring. The licensee was informed that
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the analysis of a sample from the gland seal condenser would ist[,
support his assumption that the radioactive gases emitted from the gland seal condenser are insignificant. The licensee plans
(; q to investigate this matter further.
(Paragraph 10)
L' D.
Off-Cas Filter. The licensee was informed that even though credit is not Leing taken for the filter performance, a measure of filter effectiveness at the time of installation would verify proper installation. The licensee plans to investigate this matter
' sp further.
(Paragraph 11) c'7
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-s ii SECTION II
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Additional Subjects Inspected, Not Identified in Section I, Where NL No Deficiencies or linresolved Items Were Found (y[t ;
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General (E
kid r> l a n t oparations are being conducted at 164 '%t with supervisory
- i
- 3 and non-nargaining unit personnel.
Facility operationu are ccutinuing
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as described in CO Report No. 155/71-4.
Ti r TL N.s With tne exception of a short outage of approximately one day, jug June 3, 19/1, for the purpose of turbine drain repairs, the reacter "g
has remained at 164 }'wt since the last inspection.
'1he of f--gas LM release rate is currently _32QO uc/sec.
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Administration and Organization y.
P Personnel Performance 1
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l.ogs and Records Contrcl room log, reactor log, and shift supervisor's Iog -
a.
Itay 24
. lune 5, 1971 S.
11guad effluent records - 1970 I
c.
raseous effluent records - 1970 p
t f
d.
Fttluent nonitor calibration records 1.aborat ery equipment calibration records e.
1.
!meironmental sampling records
.u i n A t y con t rc.) and Core Physics 4.
- t ritx profile i c. f.. e critical heat flux ratio t N tatths/ shutdown margin
- 1; r s - !cus uith rod C-3 inoperable
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5.
Liquid Effluent Managament a.
Sources of parential radwaste F
Disposition of liquid effluent c.
Waste treatment d.
Volume and flow rate determinations e.
Establishment of effluent release rates f.
Establishment of dilution flows A
g.
!!PC Jeterminations
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h.
Reporting accuracy 1.
Monitor locations J.
PMnitor calibrations k.
Background associated with monitor.s 4
Esta*lishment of alarm setpoints W<A 1.
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Mcnitor sensttivities Activity *:elease calculations 4
6 Gaseous Eftluent Management
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Sources of potential r-dioactive effluents
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Tres* ment of effluents
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c.
- 1troent and dilution flow rate deterrnitiat ions d.
Activit y release rates
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Fon it o r locatiens i.
.u c rn ss.t points i
g.
\\;-ier setpaints for waltors Monit>r calilirations i
1.
l.cpcrtin. accuracy 1
t'ha rc oa l 1ilter anJ efficiency i
F u t i td,r e t ilt er and ef f iciency f.
1.
.Itat sen.,itivities c_:E fg ge. lures
.. at' sar..piing 01 3iquid efiluents a
.d... cling of gaseou,. eftiuents i ! atactun ut beta counting equipmcut m.
it-at i,. ei ganma countJng equiprent
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. - am f o rre.o l u
.wed tor data r e h.c. t : n
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..el at et > >c' I t ( v i t y :ind in.;L i... uni i
s.a.s..tr p2 Led daripl es supp ' *.! i y
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[r LA Details of..ubje:t s Dincu' ed in i:ect ion !
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R eactivity Centrol and sore Physics pg t
8.
Control Red f.-J.'blfunction
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c.%
The inferrut tan reported previously to ifcadquarters was reviewed f 7 and fou'ri.: % cecutat e.
li e llecnsee has rtported the iralfunctio, c(6 m to Dkt ' n a it.tter i rotu !!aueter te Nrra s dt.ted June 7,1971.
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43.
During aaily esercising of the control tods at 0030 on May 26, 1971, if with the reactor at 16 'i !% t, it was discovered that control rod
, ' l.j C-3 ceall be freerted but nar wf t.hdraten.
1r riectri.:al and hydraulic troublesi. outing of the problem did not
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rcweal the cause of the malf unction.
All other control rods operated 7
properly.
1/. : 2 I,9;;r A t. 0350, courtel re: C-3 was tsoleted pursuant to the requirer ents f.
of Technical Specification 5.2.2(f)(2).
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H.1 C -- 3 13 presently at notel Its normal position is notch (tully sei ta a rawn).
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of the base data relating to nut d c n c argin, "tlii n, power dist ribution, and rod worths indicates
. hat.
,,.nu.ed cperation with control rod C-1 valve.1 out of service
.ae rc:.aatit t w itl. t he req a l t <r. e n t.4 of Ll.e facility license.
c,.-d o u :.2 results, at t roubic !.oo t ing, thz Jicensee has concirded t a tt a sce l l *.rcfp clject is probably iodyed 1,ct'.een the index ir iing in tbc.t. ore support plate through whit.h
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. i,c o ', tc.i t t er t r ep:ii r s to the nalfunctioning
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red do 1.1 t
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- ref oc. Iing outage scheduled for I,
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. !. t < r e ; r2 wlsthet t 1.c r e are p:i r t icula te u n.: t:1 t h the ex t t t. t.g.nr. p ! i ng t
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w e this relatio.s'ip htti.een particulate and iodine activities in the air flowing ap to ri- < tack and the measurements cf the activity
[7; collected bv the barcoal and particulate sample filters located i
at the ba,e vi' ene stack is not confirmed by test.
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During 1970, :ne telease of halogens and particulates via the stack 2-as n eas.cri i v (ne licensee was 0.348% of allowable.
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The lice niec pteviously relocated the charcoal and particulate sample I'
filters tr2m the radwaste area to the baee of the stack thus ellminatiny - 120 feet of pioing run and many right argle bends.
(:n>pect2ca cepart: 155/70-4 and 155/71-1.)
4, piat T :. liscos2e has assuned that thera are no significant losses of 1~J 1 dia: n r particulate activities sithin the sample probe and the jij JeliJers ines to the manitoring paints, y,i g
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.\\ resteu at the drawing associated with the isokinetic proba i %g Jg in '
sted tb at there are several right angle bends incorporated
.2 probe desisn.
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ol.n_d eat iar.i.i w r_ 'enft. -.in _k I
i Ib s 1..n! sea:
anJe ase r g.t.sc.s arc released to the stack after
- p; r axiva t e !" 00 sec cnds decay tiec.
There are presently no sample pointe i
,ea-e:2ng activity released from the gland seal condenser
- r. t. : In y the ventilation 8 tack.
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- ti:J. c c by i3, the licensec considers this source of c.. s e...i
. i g n i t' le o n t (less than 1%) when compared to that
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'- ter.
51though any activity released from the tr-afi
..uld I,e monitored by the stack effluent i
oct tc included in the tabulated stack effluent i
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.. t r.s e e bases als determinations of stack effluent
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a:ples et che oft-gas prior to dilution with the r-ventilarion slow.
'nri cre.! t! at monitoring the activity from the ta., pot check basis would confirm that it
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in et* a..
3 t i-fa= particulate tilter located in the
!,: t.t.ied at cpproxirately 6 to 8 week intervals..
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The ef ficiency c,f et:c ef f-gas filter is not a consideration in computation of the s.. aunt of radioactive particulate activity released via the stack.
'he sampling point is located downstream of the off-gas filter.
The licenses. deca not check the filter effectiveness after filter cliain,ccut. The i t cc usee w:is inf artr ed that testing the filter for A
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e f f e e t. s 2 :- uc.a changecut would verify proper filter installation.
Tm 11:e ist e plces to inve.etigate this matter further.
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