ML20031C242
| ML20031C242 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/13/1973 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| AO-11-73, NUDOCS 8110060663 | |
| Download: ML20031C242 (3) | |
Text
usoR.us. OCCtRRrve RErm y
,y*'
M A p i d [J ComoL suu:
l 6
FACILITY:
CATFCORT: REPORT TY PF.
SOURCE:
Is0CRET f EVENT DATE:
RFPORT PATT:
B D $. Q ) ' 59 950-9/55; p l_1, 01 4 0 l l I.h 7 ?
.9 n._
l t
60 61 68 69 74 75 M
OfSCRIPTION OF EVENT:
_0_L_
%c S.s v t, sc a c nysmrsa sc c_
o g p. (~,x ggy 7
s9 n
V ALVC LJ E Fb >, O T,
' L e -a C_
F (=r.a W
n.t 7_0_1_.
89 80 04 D
.*)
E% ' D
.t U[ C G$ (_~
{Jq ( f L,,3 % g ff([w s
7 o
o y,
Ob b I. ' L-8 L3" OPCd i M ('A ', '/ L '# k O
'[ ' w er c_./:O a w nri.
n._n m,e,o cm (Ao-Il[73
]
' SYSTEM NO.
~~ ~
d Cf7'PONENT 80
\\
PROK! MATE CAUSE CODE: A-PUSOMNEL ERMR D-PROCEDVRI.S DEFFCTIVE EM F1t B-DESIGN DROR E-CCMPOMENT FAILURE
,j o
a /.3, D, 2""" c"$5
, a,4,
F
'-='
07_
.DESCRIPTIC OF CAUsb I2 13 I
- ?A e JF ha 2 7-V Q C) *, f"C L. O f_ F. L t %"
08 13, td hj @
I 1
I C s O'> ?
80 W
g 10 C L dbC_ g P o_, p o.;
if C Q l F r fkd Fev2,_ TM-5 v % L V C.,
j I
8f C
83
)
7 8
)
go STATLv 0F A-ca m - J 0M F-LOA 5 'CRIV:Es DURIw MFTWOD fAdr f%,dl6M'lVFXT ~
- 1 n
lB-ROUTI%ETEST/IRSPEC.
l RFACTD4 CODE:
B-PR EOP DATIONit., INITIAL ROUTIKE PWD OPERATION OF STp*T"P AND PLM1t ASCE45101 C-SHLTOOI.N (HOT OR COLD, DISCOVD T f C-SPFCI AL TEST /INSPEC.
l 7F5:5 EXCEPT REITELLINC)
' D-FITERNAL SCCRCE I$ *II
~'-
"g
[
C-ROUTINE STARTUP OPDAT101 N-REFUELLINC D-ROUTINE SHLTTI AC D%N OPDATION I-03ER, INCLL" DING SPECIAL f
E-STEADY STATE OPDATIO% AT _Z TESTS (DESCRIBE) 3
_ T I_ _,.. ___.
i GTATUS:
2 PWD:
0:HER STATUS:
DISC.:
DESCRIPT13:
F 8
9 10 2 IJ 44 4 46 N
I FORM OF La LICUID CONTENT hs NCrLE l'AS l ACTIVITY S: SOLID OF
[{ HALOCEN
}
- RELEASED:
C: CAS RI2 EASE: V: PARTICULATF.
AMOL3T OF ACTIVITY:
thCATION OF RELEASES R
e 1
f _,,,,)
t I
e l
7 8
9 10 11 44 45 5J FER$f NNEL EXPOSURES :
l KMER:
DESCRIPTIO1:
,,I_3,,_
r i 1 1 7
8 9 11 12 60 PERSONNEL INJURIES:
j s' NLMf R:
DESCRIPT104:
li lt ie i 0FFSITE bONSENEhCIS:
is r
7 b '9 00
'4L DAMAGE TO FACILITY:
16 7-8 ;9 6) r
, FUBl.ICITY:
17 7-39 ADDITIONAL FACTORS:
i
- 1* g,
-- a 19 7~89 M
RIV. 8/21/73 4
90KOO y
- O S
A
/
o e
@ Consumer Power Company
@@*W a... _....... _...... _.,_............
November 13, 1973
, g. f) klCt 40 g
g g NOV 151973 Y
%k3 Ig C
Et. AT88tt tager 3
4-Causustas N
Mr. John F. O'Imary, Director ase sesas Re: Docket No 50-155 8
License No DPR-6 pa'!
Directorate of Licensing IS Atomic Energy Cor=11sr'.on C
. i Vashington, DC 20545 Lear Mr. O' Leary:
The following are abnor=al occurrences at Big Rock Point during 6,.
the surveillance shutdovn of November 1, 2 and 3, 1973:
d e
fl AO-11-73 N3 On November 1, prior to performing maintenance on the conde-: -
A.f off-gas system, the 6" off-gas bypass valve was found to be in the rpen J
- csition. Investigation indicated the valve had been in the open posi-p tion since start-up after the refueling outage in April 1973 4
M Operating practice is to use this valve in the open position y
for vi.iting purposes during shutdown periods when replacing the off-gas "y
filter assembly at the stack base. The valve is equipped for locking and
~, -
l its condition is normally controlled by logbook ent ry. The oversight O
occu:. red following the investigation of the off-gas holdup piping sys-W tes during the April refueling outage.
If a high off-gas release rate were to occur during operation vith the bypass valve open, the open bypass valve vould preclude auto-
[
=atic isolation of the off-cas system. However, during this period of l
c;eration with the bypass valve open, adninistrative controls were in effect to limit off-gas release rates to well below the set point for y
automatic isolation. (Refer to our letter to the Directorate of Licensing O
dated June 26, 19T2.) The open bypass va17e did not jeopardize the abil-l L
y of the plant staff to implement these administrative controls.
i s
To preclude thiu from recurring, the valve vill be adied to P..;
- .fi l
a plant start-up checkoff list that vill require appropriate position f
verificatien.
L,,
s l
[
82i30 I-
o n.
O I
2 Nk D
g AO-12-73 During calibration tests on November 2,1973, the four high condenser pressure scram bypass pressure switches (RE15A, RE15B, RE150 and RE15D) were found to be set higher than the 350 psig set point limit specified in Technical Specification 6.1.3(E). RE15A operated at 362 psig. RE15B operated at 395 psig, RE150 operated at 352 psig and RE15D operated et.160 a.M g.
The instruments were being checked as a result of a Plant Review Coraittee reco==endation following previous set point drift problems as reported in our letter to the Directorate of Licensing dated May 8, 1973 These switches have been reset at 3k0 psig and vill be checked again during the nert outage is an attempt to detemine if drift is occurring.
A0-13-73 During checkoff procedures on hbvember 3,1973 for the neu-tron monitoring system, the co=pensating power supply for the Channel h log N/ period neutron monitor was found to be reversed in polarity.
In-vestigation revealed that the reversal was the result of installing a spare power supply during corrective maintenance procedures on June h, 1973 Operatienal checks cancot be adequately performed at high flux levels and thus the problem was not discovered until the subsequent re-actor shutdown t.nd its required start-up checkoffs on Novecher 3, 1973
-[
T Operation of this chann?1 with the co=pensating voltage polarity g
reversed recultc in icproper gc.==a cc pensation. At the power levels
.x associated with power operation, the effect is not noticeable and power
?
level informatien is provided by other instrumentation. At lover power g
levels, the error is noticeable and period indication is effected. The w
sect 'd channel was found to be operating properly durind the period that Jg the compensating voltage polarity was reversed on the first. Only one f
of two channels is required to initiate a period trip signal. The log N/ period neutron monitors are required to be operable during start-up
%yf from approximately 10~5", to about 5% of rated power. For operation above approxicately 5% of rated power, logarithmic neutron flux level informa-M tion and period scram protection are not required.
%g To preclude recurrence of thic type of problem, the instrument j
maintenance procedures vill be changed to include verified checks of the 125 status of the power supplies for co=pensated ion chamber channels when NI replaced during power operation.
'ina Yours very truly, IM Ralph B. Sewell (Signed) a
.f RBS/ cap Ralph B. Sewell
,((4 Nuclear Licencing Adminictrator CC: JBKeppler USAEC w
A-*3