ML20030A553
| ML20030A553 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/09/1976 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101100006 | |
| Download: ML20030A553 (3) | |
Text
.
i
,fE Reguhl0PJ OCK01 [Ik D
j Company j]*1 cenerei ome.: 212 ween e.ucNeon Avenue. Jackson. ucNoen 402ot. Ar.cooo st7 7se-oeso September 9, 1976 hV T
r yg Fat.r.:
SEP &v.R M. :.n )
C4 D?
r.
' v --
/
y y\\
tu..,,, a
~
g'*-
{
hj k8 Ai;:,
.O p
Director of Nuclear Reactor Regulati k bg,hg$Y US Nuclear Regulatory Commission
/' ;
Washington, DC 20555
{
i Ch,*,
DOCKET 50-155, LICENSE DPR A g
BIG ROCK POINT PLANI m
CP By letter dated June 10, 1974 to the Director of Licensing, Consumers Power Company reported that preliminary measurements had shown that the plant exhaust fan flow rate (plant stack flow rate) was approximately h0,000 cfm instead of the 30,000 cfm we had assumed since plant operation in 1962 based on design data. On November 1, 197h, Consumers Power Company submitted information describing how particulate and iodine release data would be corrected based on the assumption that the stack flow was 40,000 cfm instead of 30,000 cfm.
Since that time, at the request of the Safety and Audit Review Board, additional testing has been performed to identify the actual stack flow rate, This testing was performed by a transverse of one diameter axis of the ventilation stack cross section. The flow measurements were made with a Model 60 Anemothern Air Meter and the axis was divided into equal areas. There were two (2) objectives for this study. One was to measure the gas flow of each fan under normal operating condi-tions. The second was to make the same type of measurement with a containment isolation and then a radvaste isolation condition. The purpose of the isolation study was to determine the effect on the operation of the makeup air inlet damper.
The results of the test are shown in the following table:
STACK FLOW RATE Operation Mode Fan No 1 Fan No 2 Normal Operation:
October 15, 1975 31,000 i h,600 29,000 1 2,200 April 13, 1976 28,000 1 7,000 30,000 i h,200 Containment Isolation 23,000 1 6,000 27,000 1 5,100 Radvaste Isolation 27,000 1 T,600 29,000 1 5,300 Average 27,000 1 5,900 29,000 1 3,500
(
NO f
I flotic oco6
(;.
2 In none of these tests were flow rates observed at 40,000 cfm as were measured utilizing a helium dilution technique in 1973 Further, upon reviewing the 1973 work, it appears that the measurement utilizing a helium dilution technique may have resulted in lack of total mixing prior to sampling and, therefore, caused the reported 40,000 cfm value to be in er ror.
We have concluded that the use of a stac1 flow rate of 30,000 cfm approximates the actual stack. flow rate and, therefor #, in the future will base iodine and particulate release rates and total rele tses on a stack flow of 30,000 ccm. As the previous iodine and particulate release data based on 40,000 cfm is conserva-tive and a small percentage of release limits, we do not plan to correct previous release data for the new stack flow rate l
/
Ralph B Sewell Nuclear Licensing Administrator CC: JGKeppler, USNRC i
l l
~_
NHCFcRM 195 u.s. NUCLt AQ CtCULATORY COMMISSION ooCKtTNUM003 f
_ 50-155 6 is.7e
. NRC OlSTRIBUTION ron PART 50 DOCKET MATERIAL L:
FROM:
CPC DATE or ooCUMtNT NRC 9-9-76 Jackson, MiCh.
49201 Ralph B. Sewell DATE RECF.tVE o 9-13-76
~
- Levrea ONoTOnt2Eo PROP INPUT FORM NU.Mst R OF COPILS RE CEIVE r, OcnlOINAL EUNCLAS$1Fito 1 signed 39 CC O cor Y,
ocSCniets:N Ltr re their 6-10-74 Itr...furn addl tNCLoSu nt info on plant exhaust fan flow rate of the BigiRoCk Pt. Plant....
~
r l
Jm0WIlEl
~
PLANT NAME:
Big Rock Pt.
e.
NI kN)
SAFETY FOR ACTION / INFORM ATION EINIRO DMT.
C-N-M I
AS S.I.GIID_AD :
{
, ASSIGNED AD:
BRANCll CllIEF:
, _b.,I.tehld.AfM BRAliCILCILIEE:
PROJECT MANAGER:
. g C y C_S_
PROJECUiAll4GF.R:_
q LIC. ASST.:
t gg S 1,1C.JSSL :
a a
b-INTERNAL DISTRIBUTION
[IEG FII.h SYSTidSAFFTi
_FIAMLSYSTEMR SI_1T_SAFETI_&
NRC l'DR _,
IIEINEMAN TEDESCO ENVIRO A!!A_LLSIS q
q SCl!ROEDER B_ENAR_0YA DEtjIQ;{_h_}WT H R I&E q
q
!OELD L41;MS GOSSICK & STAFF ENGINEERING TPPOLITO _
ENVIR0__TECII -
y MIPC MACCARRY KJ3}g&OD _
ERNST CASE KNICllT BALLARD llANAUER SIIIWEIL M ERATING RE_ACT_0AS_ __SPANGLER lLARitESS PAULICKI STELLO
~~
R T TE._TEClf _
yROJECT MANAGE!!EliT REACTOR SAFETY GPERA_TJt(Q_IECll.
gat?!ILL I
P_uCOI. LINS NOVAK
[SitA0 '~
STEEP l
BOYD ROSS EISI:Nittrr ltULIBM I
IIOUSTON ROS7.TOCZY BAER d
PETI:ltSON CllECK Btrri.ER SITF._ ANALYSIS HELTZ-
_gRJtti:;S VOLLMER 9EI.TEttES AT & I
- _EUNCll
~ ~ ~ ~ ~ ~SKOVitO!.T SAI.T7. MAN L
F
]
H D I P I LI A O._ceLLlus
'IttrrnERC I
'l i-1 U fil D 111 M LX11.ltNAL Ul:ilitillU llON
~
ritECtg
~
CON illOL NUMtti.it I.PDR() ae Leun11f #7M3AT_f.An:.
_Jiit00xilAyi:n.14AT_LAIL.
f TIC:
i lu:C. VIE 111.RIKSON(ORNJ,)
,/
f3 SIC:
.I A l'DR 238 ASI.n.
CON';t!I. TAN TS X ACnS/6&S_ammeil-EN(r4 ~z.s.
s,.l a to,,, m i-1 1
.. _ _.