ML19331E276: Difference between revisions
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: i. ,' | : i. ,' | ||
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1 w K. | 1 w K. | ||
~ | ~ | ||
..- #;4 , . . , ..a. -4 . ./ ; u;;,%.. ,. g .;., .,:c,,,;,_....L..,_...._ ,. .. . .. _ | ..- #;4 , . . , ..a. -4 . ./ ; u;;,%.. ,. g .;., .,:c,,,;,_....L..,_...._ ,. .. . .. _ | ||
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A | A | ||
-. c.'-....... _ | -. c.'-....... _ | ||
: 1. - .; | : 1. - .; | ||
TAprJ: 1-1 | TAprJ: 1-1 | ||
| Line 266: | Line 259: | ||
,8 7.3GE-04 <MDA <MDA <WA <MM . | ,8 7.3GE-04 <MDA <MDA <WA <MM . | ||
7.965-03 Cs-138 7. 2 3E-03 (MDA 1.80E-04 ; | 7.965-03 Cs-138 7. 2 3E-03 (MDA 1.80E-04 ; | ||
3.78E-05 1.42E-04 <MDA <MDA Da-140 <MtA O | 3.78E-05 1.42E-04 <MDA <MDA Da-140 <MtA O | ||
<MA 3.99E-04 (MDA (MDA (MDA 3.99E-04 8 La-140 <MDA 6.135-06 ' f: | <MA 3.99E-04 (MDA (MDA (MDA 3.99E-04 8 La-140 <MDA 6.135-06 ' f: | ||
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P o | P o | ||
I o | I o | ||
.1 | .1 i | ||
l-7 | |||
= * | = * | ||
= | = | ||
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. ; , , -. a | . ; , , -. a | ||
. y; .Ur*. . | . y; .Ur*. . | ||
J *s | J *s | ||
* - ., . g *:*/ ( l' . + | * - ., . g *:*/ ( l' . + | ||
| Line 355: | Line 345: | ||
* D (Curles/secxind)" 6.07E-04 1.03E-03 2.30E-04 3.20E-03 1.905-04 '3.118-04 * | * D (Curles/secxind)" 6.07E-04 1.03E-03 2.30E-04 3.20E-03 1.905-04 '3.118-04 * | ||
* ';$ 'E^ | * ';$ 'E^ | ||
' g; | ' g; d M>nthly Average Site - | ||
d M>nthly Average Site - | |||
l'; , | l'; , | ||
I ' | I ' | ||
| Line 377: | Line 365: | ||
', | ', | ||
* Expressed as Xe-133 equivalent. [ 3 9 | * Expressed as Xe-133 equivalent. [ 3 9 | ||
I e | I e | ||
. .I I V y | . .I I V y | ||
| Line 494: | Line 481: | ||
..-_s.-- n. , . . . . . .._:.,-- | ..-_s.-- n. , . . . . . .._:.,-- | ||
.. ...~.... . . . . . . . . . | .. ...~.... . . . . . . . . . | ||
No. Sample Type ~ Iow Average High Units Vegetation | No. Sample Type ~ Iow Average High Units Vegetation | ||
., m ' | ., m ' | ||
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s 4 e' | s 4 e' | ||
4 | 4 | ||
.(. * | .(. * | ||
~ | ~ | ||
| Line 621: | Line 606: | ||
j (3) Instrumentation out-of-service. | j (3) Instrumentation out-of-service. | ||
1 (4) Unit 2 was shut down for steam generatar maintenance from February 28, 1980, to March 13, 1980. | 1 (4) Unit 2 was shut down for steam generatar maintenance from February 28, 1980, to March 13, 1980. | ||
} | } | ||
i | i | ||
.q ; ...,7 m_. . - . - - | .q ; ...,7 m_. . - . - - | ||
. . . . . __ . . . . .. .. . . . .}} | . . . . . __ . . . . .. .. . . . .}} | ||
Latest revision as of 12:12, 18 February 2020
| ML19331E276 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/29/1980 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML19331E274 | List: |
| References | |
| NUDOCS 8009090545 | |
| Download: ML19331E276 (15) | |
Text
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~~POINF BEACH NUCLEAR ?LANT ?,
s ,s. r p N A m
-UNITS 1 AND 2 7
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SEMIANNUAL MONITORING t - REPORT .
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!! January 1, 1980 through' June 30, 7.980 Ht t-4 U . ,
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TABIE OF CONTENTS
-i.2 .
PAGE ~[; ' SECTION TITLE Mi i 1.0 RADIOACTIVE LIQUID P2 LEASES 1 i 2.0 RADICACTIVE AIRBORNE RELEASES 4 3.0 RADIOACTIVE SOLID WASTE SHIPMENTS 7 i 4.0 NEW AND SPENT Ft.;EL SHIPMENTS AND RECEIPTS 7 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING B -1 i 1 6.0 NON-RADIOLOGICAL ENVIROtOENTAL MCNITORING 9 7.0 NON-RADIOACTIVE CHEMICAL RELEASES 10 t i 8.0 CIRCULATING WATER SYSTEM OPERATIO:s 12 9.0 LEAK T5 STING CP RADICACTIVE SOURCES 12 I c k Y'
- - . . . - . - - - . . - - - - . . - . . . . . - . - - - . . . , - .. -- I
. . . . . - . . . - - - - . . . . . . - - ~ - - . . .
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l1.0 RADIOACTIVE LIQUID RELEASES ~ { Radioactive' liquid releases via the' circulating water discharge are ' summarized. for total. release"and by individual source on a monthly M a
~ basis in Table 1-1. ' An isotopic breakdown of the -total radioactive '
_ 4'( liquid release is presented in Table 1-2. :{ The . total radioactive liquid release excluding tritium for this ' reporting pcciod was 5.38E-Ol Curies which. included 5.65E-02 Curies of processed radioactive waste and primary coolant system letdown, ? 4.48E-01 Curies of Unit.1 steam generator blowdown, and 3.38E-02 T( Curies of Unit 2 steam _ generator blowdown. There was no measurable - release, other than tritium, via retention pond effluent. The total tritium release for this reporting period was '285.4 Curies, which included 278.5 Curies of processed radioactive waste and primary coolant system letdown, 4.4 Curies of Unit 1 steam generator blowdown, .' 1.0 Curie of Unit 2 steam generator blowdown, and 1.5 Curies of. reten-tion pond effluent. All radioactive liquid releases to Lake Michigan [ were made through the circulating water. discharge. I
~1.1 , Additions to Semiannual Monitoring Report July 1, 1979, through December 31, 1979 The following data which was not available at the ' time of the report preparation should be added to Table 1-1 of the Semi- . ,
annual Monitoring Report July 1, 1979, through December 31, 1979.
. November Total i
Total Activity Released, Ci Gross Alpha <MDA 2.36E-06 - Average Diluted Discharge Concentration, UCi/cc Gross Alpha - - - - 4 MPC ---- The following data which was not available at time of report
-preparation should be added to Table 1-2 of the Semiannual Monitoring Report July.1,1979, through December 31, 1979.
..- November Total, Ci Alpha <MDA 2.36E-06 e
a O A
-. c.'-....... _
- 1. - .;
TAprJ: 1-1
. f:
PADf0 ACTIVE LTOUfD CIWUfATING WATER RELEASE
SUMMARY
PERIOD JANUAPY 1 TO JUNE 30, 1980 - - e. January February, March April M June Total
.. Total Activity peleased, C1 9-Cassia Scan (1) 3.58E-01 5.77E-02 2.82E-02 7. 32E-0 3 5.60s-02. 3.03E-02 5.38E-01 6 * ,
.. Gross Alpha. <MDA <MDA 5.35E-05 3.54E-07 3.18E-05 (3) (3)
Tritium 3.04E+01 5.28E+01 1.las+02 1.595+01 1.48E+01 5.35E+01 2.85E+02 . Total voltanes Released, Gals s
'i.
Processed Waste 5.66E+04 6.66E+04 4.38E+05 1.87E+05 1'.47t+05 5.02E+04- 9.45E+05 " steem Generator slowdown, Unit 1 2.94E+06 3.00E+06 5.24E+05 2.46E+06 2.98E+06 2.72E+06 1.46E+07 Steam Generator Blowdown, Unit 2 2.51E+06 2. 20E +06 1.78E +06 1.01E+06 1.84F'06 3.06E+06 1.24E+C7 ? Retention Pond 2.46E+06 2.20E+06 1.12E+06 1.80E+06 1.37E+06 2.47E+06 1.14E+07 Total 7.97E+06 7.47E+06 3.86E+06 5.48E*06 6.34E+06 8. 30E +06 3.9 4E+'J7 So
-a vblume a Dilution Water, al 3.90E +13 4.14E+13 8.53E+12 1.52E+13 7.38E+13 7.13E+13 2.49E+14 Average oil 4ted Discharge Concentration, DC1/cc Cross Beta-Gama 9.20E-09 1.39E-09 3.31E-09 4. 8 3E-10 7.595-10 4.24E-A0
- MPC 1.03E-01 1.80E-01 1.455-01 6.51E-03 2.35E-02 5.38E-02 ,
Cross Alpha ---- -- 6.26E-12 2.33E-14 4.30E-13 (3) l t e"x 2.09E-02 7.77E-05 1.43E-03 (3) Tritium 7.795-07 1.285-06 1.18E-05 1.0$E-06 2.00E-07 7.50E-07 t Mit' 2.60E-02 4.25E-02 4.61E-01 3.49E-02 6.68E-03 2.50E-02 ;i
- f. Maximum Discharge Concentration
,; During Release Period, DC1/cc 4 .
j . Gross Beta-Cama (1) 1.76E-07 2.11E-08 8.35E-08 1.64E-09 8.30E-08 4.60E-09 l Tritium 7.27E-05 1.12E-04 1.35E-04 5.45E-05 4.013-05 6.465-05 i r NOTESs (1) Not including Strontitse results whic h generally have a negligible effect. (2) Sumation of the individual isotopic 10 CFR 20, Appendix B Table 11 MPC's. (3) r,ata unavailable at tims of report writing. , e
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Isot'OPIC COMPOSITION OF CIPCtit,ATING WARR DISCHARGES *
? ? . -- [+
PEPIOD JANUARY 1 TO JUNE 30. 1980 , ' I c! Nuclides . January February March April
-(Curies)
May (Curies) f one
,Osries)
. Total (Curies) .,
.j{I ;
h Released. (Curies) (Curtes)- _( Curies) 4: 1.59E+01 - 1.48E+01 5.35E+01- 2.85E+02< J=
- 3.04E+01 -5.28E+01 1.18E+02
- H-3.
3.875-04 <MDA 2.45E-03 6.47E-03.
;F-18 1.242-03 1.01E-03 1.38E-03 2.73E-01
' ;--a ' ; h 2.70E-05 _< MA < MM <MM - . (MDA. .y Na-24 ' 2.7 3Et01 1.60E-03 -r= ,{.
<Mm ' 1.56E-03 3.415-05 9.75E-06 <MDA Cr-51 <MDA *
[, Mn-54 <MDA- <MDA 1.428-03 2.41E-04 2.935-04.
?
,. (MDA 1 95E-03 1.60E-04; ;e
' J4 1.0 3E-04 <MDA 5.66E-05 (MDA' <
'Co-57 IttDA <MaA 3.328-06 1.01E-02 1.00E-03 6 92E-04 CO '3.47E-06 <WA 8.40E-03 8.14E-04 1.79E-0 3 1.19E-03 '
1.74E-04 4.13E *
~
~
' '.0 "? l [
Co-60' 1.5 3E -0 4 4.57E-06~ (MDA (MM (MIA . 1.97E-06' I; Kr-85m <ma <MDA 1.97E-06
<MDA < MM <MDA <MDA~ 1.555-04 - e q,, 4' Kr-87 1.55E-04 <MDA
<MDA (MDA. 7.36E ,
<MDA < MM Rb-e8' 7. 36E-02 <MDA (1) (1)
'3 %
.5.545-07 8.53E-05 8.25E-05 <ch .
St- 89 5.05E 1.03E-03 2.72E-04 1.10E-04 (1) '(1)
"I. '
St-90 <MDA <MDA ' 1.71E-04 <MDA (HD4 (MDA 2.13E-04 c
. zr-95 4.17E-05 < P *.
5.188-04 (MDA <M A 2.04E-04 4.10E-06 2.30E-04 <MDA Nb-95 3. 33E-06 7.34E-07 1.96E-05 1
<MuA <MDA <MDA 1.55E-05 ,'
s Ru-103 3.30E-05 <MDA 3.30E-05 b ~
. <MDA <MDA (MDA <MDA '
Y Ro-106 <MDA 'l.90E-06 2.61E-06
<MLW <MDA 7.09E-07 <MDA ,
.' 5
) A9-110m
<MDA <MDA <MDA (MDA 2.98E-06 . ,
- ' Sn-113 2.90E-06 <PDA 7.72E-06 <MDA 7.48E-05 -
' 4 l.4 -l{
<MIA 5.77E-05 9.345-06
'[ Sb-125 I-131
<MDA 6.75E-04 1.51E-02 3.19E-0 3 1.76E-05 <MDA 7.75E-03 2.67E-02 7.062-03 ei 2.Ing-03 6.85E-05 <Mm 1.42E-03 I-132 2.124.-04 3.10E-03 3.39E-02
* '8-2.04E-02 3.57E-04 4.46E-04 (MDA 1.00E-02 -U 1-133 1.88E-0 3 9.67E-04 9 67E-04 I-134 <McA <MDA <MDA <MDA <MDA 5.11E-03' 1.22E-02 .!,'
I-1 35 <mA 6.27E-03 1.94E-04 6.45E-04 <MDA' -' 3.548-06 <Mm <MDA <MDA - 3.54E-06 Te-132 <MDA <MDA
<Mr# (MDA (HDA (MDA 2.38E-05 ?
xe-131m 2. 30E-05 <MDA 4.09E-04 5.205-02
?
69E-03 1.46E-03 2.30E-04 4.80E-02 ' Xe-133 1.70E-04 4.50E-04 A <tDA <MDA 4.50E-04 <MDA
<MDA
-{
Xe-133m 3.14E 3.58E-03 3.78E-05 f.ME-05 3.22E-05 3.10E-05 3.10E-0 3 Xe-135 3.04E-04 2.80E-04 6.16E-03 y Cs-134 7.51E-05 .75E-03 '1.25E-03 5.598-04
- 1.62E-0 3
- 5.74E-04 1.45E-02 g.
Cs-137 1.05E-04 3.43E-03 4.85E-0 3 1.85E-03 ,
,8 7.3GE-04 <MDA <MDA <WA <MM .
7.965-03 Cs-138 7. 2 3E-03 (MDA 1.80E-04 ; 3.78E-05 1.42E-04 <MDA <MDA Da-140 <MtA O
<MA 3.99E-04 (MDA (MDA (MDA 3.99E-04 8 La-140 <MDA 6.135-06 ' f:
<MnA <MDA <Mr A (MDA 6.13E-06 <MDA 4 ,
Co-141 6.87E-05
- t '!
<MDA <MDA 1.71E-05 2.14E-06 4.955-05 <MDA Ce-144 (1) (1) i
<MDA (MDA 5.35E-05 3.54E-07 3.18E-05 Alpha
-------- - === - - 5.38E-01(2) 107AI. -
1 .g
'I ,
NOES: <MDA - Less than minimum detectable activity. F (1) - Data unavailable at report tiro. F (2) - Total does not include tritium, strontium, or alpha. , l 2i
* *a.
4 4 I e a: _ . . . . . . O n1> '
/ . ]-
d ?di%.43 ,. gu-- ,,
. , , : p p
i 2.0 RADIOACTIVE AIRBORNE RELEASES ' d-.
..s-R&da 7 active airborne releases during' normal plant operation are T.
, - reported by total release in Table 2-1, and summarized by isotope @
in Table 2-2. The release paths contributing to radioactive air-borne releases during this reporting period were the auxiliary f(c
- i;-
building vent stack, Unit 1 containment purge stack, Unit 2 contain- ..MS ' ment purge stack, drumming area vent stack, gas stripper building f6P ventilation exhaust, combined air ejector decay duct exhaust and s turbine building ventilation exhaust. j.R
,3-
.m There were four gas decay tank releases. during this report period. [ ,*[
2.1 Additions to the Semiannual Monitoring Report, Julv 1, 1979, throuch December 31, 1979 m : The following data which was not available at the time of the !. report preparation should be added to Table 2-2 in Section 2.0 ' of the Semiannual Monitoring Report covering the period ~l
- July 1,1979, through December 31,-1979.
~
October Novertber December Total, Ci i-Sr-89 3.53E-07 3.47E-07 3.45E-07 2.45E-06 Sr-90 2.05E-07 1.99E-07 2.05E-07 8. 6 3E-07 e P o I o
.1 i
l-7
= *
=
- _. ~ - -
;-- .~ ,, _
l .
. ; , , -. a
. y; .Ur*. .
J *s
* - ., . g *:*/ ( l' . +
6-
;, lf;, ,,<
9
- TABLE 2-1 l;
11 M RADIOACTIVE AIY20RNE PE12ASE SWMARY PERIOD JANUARY 1 TO JtHE 30, 1980
]*dI
; e -
e tai
; , : , s f,,#;*) 4 /
.g+ ~, , s g
;; y
; January February March ?.pril g ' June. Total j- y}
.l . ,..;,
Total Curies Released -4 + . A 8.20E+01 8.73E+01 3.67E+02' i } 7;. Ly( (Excluding Tritium) 3.37E el 2.62E +01 9.,06E+01 4.74E+01 ,a p Total Xe-133 Equivalent '. 3*
. Curles Releasedl' 3.47E+02 2.21E+02 3.373+02 2.65E+02 5.46t+02 6.40E+02 2.36E+03 ..
f..
' l[,M . k. i'
. i,-
Average Release Rate ; lf * .
. f. , (Curies /Second)2 1.30E-04 0. WOE-05 1.265-04 1.02E-04 2.04E-04 2.475-04 [
4
},
. 4 > gj. p 8
Percent of Annual Tech- ;~ ., se +. l,- nical specification Limits 3 6.48E-02 4.41E-02 6.28E-02 5.125-02 1.025-01 1.235-01 " : e I, ; 21 ji *
. . . . , * ' *l[b*
Maximum Hourly Average
; ' ' - h' a q helease Rate
- D (Curles/secxind)" 6.07E-04 1.03E-03 2.30E-04 3.20E-03 1.905-04 '3.118-04 *
* ';$ 'E^
' g; d M>nthly Average Site -
l'; , I '
. Boundary Concentration ; -
(pC1/cc) 2 1.9SE-10 1.32E-10 1.88E-10 1.54E-10 3.06E-10 3.70E-10 *
,! ! q' ' ;j
).
, i
** i e
,9 1 i; y-
, Pi.I,"
I All gaseous and particulate releases are converted to "Xe-133 equivalent" for calculational purposes using , h5 ;l t the ratio MPC e-133/MPC1 X MPC's for isotopes of iodine and particulate with half-lives longer than eight ,'l l Q g e days are reduced by a factor of 700. ,
.l< , ,
, ,t!
- 2 Averaged over one aunth and based on Xe-133 equivalent. '
3 Annual average Technical specification limits are 0.2 C1/sec Xe-133 based on.X/O - 1.5 X 10~6 sec/m3 . , Knximum Technical Specification limits are 2.0 C1/sec Xe-133 based on X/Q - 1.5 X 10-6 ,,ef,3,
',
- Expressed as Xe-133 equivalent. [ 3 9
I e
. .I I V y
- i 2
l . i
,4),
,~ , I 8 Je&A*A'4 9 W 'sY - % g l g , ,,-- *4,'g Q, y , Ly. f y g,p_ ggf A ..< . . . ~ . - -
-- --= -- ___
~
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. - ~
. .-. . ~
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TABIJI 2-2 RADIchCTIVE ATPSCENE RE!. EASE
SUMMARY
PERIOD JA'4UARY l TO JWE 30, 1980 March April May June Total
. January February- - (Curies) .
(Curies)_ (Curfes) (curies) (Curies)_ (Curie s) _( Curies) 4.38E+01 5.48E+01 2.72E+01 4.5CE+02 1.162+02 1.27E+02 8.68E+01 Tritius . .. Noble Gases 5.89E+00 - 2.58E+00 1. 85E +00 2.49E+01 Ar-41 3.82E+00 2.06E+00 8.68E+00 3.60E+01 3.04E+01' 1.32E+00 9. 9 3E-01 1.2 3E+00 Kr-85 2.88E-01 1.77E+00 2.68E+01 1.75E+00 2. 9 3E+00 8.20E+00 9.0$E+C0 Kr-85m 2.88E+00 1.98E+00 1.23E+01 6.67E-01 1.14E+00 3.16E+00 3.97E+00 Kr-87 2.10E+00 1.28E+00 3.99E+01 2.05E+00 3.71E+00 1.19E+01 1.39E+01 Kr-88 4.83E+00 3.47E+00 1.59E+01 7. 49E +01 2.21E+00 2.98E+01 1.00E+01 1.51E+01 ze-133 1.88E+00 1.86E-02 3.22E+00 1.60E-01 1. 38E+00 4.51E-01 1.19E+00 xe-133a 1.71E-02 3.78E+01 1.26E+02 1.06E+01 1.39E+01 1.74E+01 3.34E+01 ze-135 1.26E+01 1.39E+00 8.84E+00 1.05E+00 7.82E-01 1.57E+00 2.10E+00 Xe-135m 1.95E+00 2.21E+00 1.41E +01 3.32E+00 1.67E+00 1.15E+00 2.34E+00 3.33E+00 xe-138 . Particlates with Half Lives Less Than E19ht Days 6.48E-01 ; 6.7 3E-04 5.60E-06 9CA 6.47E-01 7.07E-04 <MDA ' F-18 <MDA <MCA 1.74E-07 Na-24 <MDA 1.74E-07 9CA <MDA 2.82E-04 9.80E-04 1.38E-04 2.23E-03 f Pb-88 4.79E-04 3.48E-04 (MDA 1.32E-07 l-
<MDA <MDA 1.32E-07 CCA Te-132 <MDA <MDA l 9CA 3.342-05 1.79E-03 9.542-06 3.27E-03 Cs-138 1.42E-03 1.74E-05 t Particulates with Half Lives Greater Than Eight Days and lodines 5.33E-07 1.50E-08 <MDA <MDA 5.48E-07 Cr-51 QCA <MDA 9CA 1.62E-09 4.99E-07 <MDA 5.01E-07 Mn-54 (MDA <MDA 8.28E-06 2.21E-06 1.45E-06 3.15E-07 2.91E-05 Co-58 1.68E-05 7.01E-11 2.043-05 1.83E-05 2.25E-05 3.23E-06 9.82E-05 Co-60 2.25E-05 1.12E-05 1.24E-08
<MDA <MDA (MDA cDA 1.24E-08 g<MDA En-65 (1)
(MDA 9CA (1) (1) Sr-89 <MDA (1) (1) Sr-90 <MDA 9CA 9CA (1) 3.24E-07 <MDA <MDA <MDA 3.24E-07 Nb-95 <MDA <MDA
<MDA 7.26E-08 1.55E-09 <MDA oCA 7.425-08 Er-95 <MDA 3.12E-07 oCA <MDA <MCA 3.123-07 Rw.103 '9CA (MDA
<MDA <MDA 7.21E-06 oCA 7.21E-06 Cd-109 <MDA (MDA 9tDA 9CA oCA 3.90E-08 oCA 3.90E-08 Sn-113 <MDA 5.36E-07 CCA <MDA CCA 5.36E-07 Sb-125 9CA <MDA
- 1. 5 4E-04 1.782-05 2.51E-05 8.95E-06 3.41E-05 4.38E-05 1-131 2.44E-05 4.26E-04 4.26E-44 1.29E-08 <MDA <MDA 1-132 9CA- 2.26E-07 3.31E-10 9CA 9CA CCA 3.31E-10 oCA Ba-133 9CA 1.62E-04 3.64E-05 3.44E-05 1.16E-08 4.70E-06 2.49E-05 6.llE-05 1-133 1.74E-06 7.97E-10. 3.45E-07 7. 35E-07 oCA 6.645-07 <MDA Cs-134 <MDA oCA 2.18E-07 l 1-1 34 90h 2.18E-07 9CA <MDA
- 1. 37E-08 <MDA CCA oCA 4.53E-07 l 1-135 9CA 4.39E-07 2.35E-06 5.4EE-08 5.45E-06 8.80E-07 1.07E-05 ,
Cs-137 1.51E-07 1.77E-06 7.45E-07 <MDA oCA oCA 9.88E-07 Ba-140 <MDA 2.43E-07 6.66E-06 <MDA <MDA <MDA 1.83E-05 Ce-141 -<MDA 1.16E-05 2.02E-07 1. 4E-Q* 2.06E-08 2.54E-06 4.46E-06 Alpha 1.68E-06 (MDA
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tons: <MDA , I4ss than mini:mn detectable activity. * * (1) - Data unavailable at report time.
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O - f j s 3.0 ' RADICACTIVE SOLID WASTE SHIPMENTS
.1 Shipments offsite of solid waste for burial during this reporting period were as follows: j, 4
'Date volume (Pt. 3) Total Activity (Ci) -f 4
01-11-80 275.2 0.103- z 01-25 '52.5 0.996 02-07-80 60.0 5.89E-09 {, 02-13 247.5 0.1r 6 ' 02-19-80 3,267.6 2. 3 *. 02-21-80 1,633.8 1.99 9 02-28-80 -1,653.0 2.64 . 03-05-80 1,633.8 1.84 74 03-10 ~1,653.0 1.32 1-7 03-11-80 315.0 0.775 03-19-80 '87.0 1.55
. 04-08-80 555.0- 0.949 3 05-20-80 555.0 0.760 05-28-80 85.0 351(1) - -
06-03-80 64.7 1.28 -
'06-10-80 64.7 9.37 06-13-80 64.7 9.9 06-24 551.8 0.58
'12,819.3 387.5 (1) Involved spent' ren.!.n 4.0 NEW AND SPENT FUEL SHIPPEN'IS AND RECEIPTS -
During this reporting period, a total of 32 new fuel assemblies were received from Westinghouse Electric Corporation for Unit 2. No new fuel assemblies were' received for Unit l. No spent assemblies were shipped from Unit 1 or 2. a e
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~5.0i RADIOLOGICAL ENVIRONMENTAL MONITORING . .. . . .
t Radiological environmental monitoring conducted by Point Beach Nuclear 1 Plant for the period January 1,1980, through June 30, 1980, consisted J. of ' air filters, gamma dose, -vegetation, lake water, well water, :nilk, ' shoreline silt, soil, algae, and fish samples collected and analyzed in accordance with Technical Specification 15.4.10. All measurements obtained during this period were well within the J. normal range except for two lakewater samples (locations E-05 and E-09) which yielded tritium concentration which were somewhat -[' - t i elevated but still within the 10CFR20 and Technical Specifications ,
~ limits. Since our investigations and observations did not pinpoint f
a specific cause or source of these concentrations and since similar . observations were made elsewhere in the Great Lakes, it is concluded that these concentrations are attributable to natural phenomena and not related to the operation of Point Beach Nuclear Plant.'
~No. ' Sample Tyoc _
Low Average High Units-TLDs 32 Quarterly 0.54 1,.05i0.24 1.39 mR/wk Air Filters 162 Gross Beta 0.01 0.026+ 0.037 0.07 pCi/m3 e 162 %dioicdine ---- all <0.03 --- pCi/m3 ' 18 samma Scan --- all <0.01 ---- pCi/n3 Milk 18 Radiciodine ---- all <0.5 ---- pCi/l 18 Er-89 ---- all <0.5 -- pCi/1
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18 Sr-90 1. 2. 4 pC1/1 18 2.111.4 Gamma Scan - - - all <5 - - - pCi/l Lake Water 30 Gross Beta <1 3.212.3 6.4 pCi/l ' 30 . Gema Scan - - - all <10 ---- pCi/1 15 Tritium <0.5. <0.912.3 3.7 pCi/ml 15 'Sr-89 --- all <5 ---- pCi/1 15 Sr-90 <1- <1+2 1 pCi/1 L Well Water 2 Gross Beta 2.5 2.8 3.2 pC1/1 2 Gamma Scan ---- both <10 ---- pCi/l 2 Tritium ---- both <0.5 ---- pCi/ml 2 Sr-89 ---- both <5 --- pCi/1 a 2 Sr-90 --- both <1 - - - pC1/1 ,
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No. Sample Type ~ Iow Average High Units Vegetation
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*- 8 Gross Beta 4.0 6.115.8 11.6 pCi/g (wet) -
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'Cs-137 <0.25 <0.2910.16' 'O.4 pCi/g (wet)
Others --- - all <0.25 --- pCi/g (wet) Soil } 8 Gross Beta 11 24115 30 pCi/g (dry) 8 Gamma Scan ' Cs-137 <1 <110.3 1.4 pCi/g (dry) Others ---- all <1 ---- pCi/g (dry) , 4 Algae 2' Gross Beta 2.6 4.6 6.6 pCi/g (wet) 2 Gamma Scan ---- both <0.25 ---- pCi/g (wet) , l Fish I 1 Gross Seta ---- 3.210.1 ---- pCi/g (wet) 1 Gamma Scan ---- <0.5 ---- pCi/g (wet) ,}t
- b Shoreline Silt ]
7$ 5 Gross seta 3.9 5.314.0 7.1 pCi/g (dry) 5 Gamma Scan ----
- all <1 ----
pCi/g (dry) 6.0 NON-PADIOLOGICAL ENVIRONMENTAL MONITORD;G PROGRAM k In accordance with Amendr.ent r.urters 29 and 33 to Facility Operating Licenses DPR-24 and DPR-27 rupectively, dated November 4, 1977, the ! Environmental Technical-Specifications for the Pcint Beach Nuclear Plant Units 1 and 2 were modified to allow tetsorary suspension of the non-radiological environmental monitoring program pending NRC review
.of the su=ary report of the five years of menitoring. As a result, -
the semiannutl report specified by item 16.6.2.a of the Technical Specification _is not' applicable. I 6
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. 4 7.0 NON-RADIOACTIVE CHEMICAL RELEASES ;
7.1 ' Scheduled Chemical Waste Releases . , Scheduled chemical waste releases to the circulating water h; I- system;for the period of. 01-01-80 to 06-30-80 included 3,294,102 ,1 I gallons of neutralized clear water waste. - The waste water ~g contained -817 pounds of suspended- solids and 194,157 pounds of sit dissolved solids.* When averaged over the reporting period, o4 these discharges represented 55.09% of the Technical Specification limit for dissolved solids and 0.510% of the Technical ' ~ ~ Specification limit for suspended solids.** The concentration increases of chemical waste in the circulating water system during the period of chemical releases ranged from 0.23 to 9.34 ppm dissolved solids and from 1.09E-03 to 9.40E-02 ppm suspended solids.** Plant chemical records ~ indicated that the following amounts of chemicals were released in the form of neutralized waste: f;
. Sodium 48,420 pounds -
J/5 Sulfate 154,165 pounds t
- Chemical releases calculated are based upon neutralized tank analysis prior to discharge.
** Based on calculations during times of actual discharges.
7.2 Miscellaneous Chemical Waste Releases { Miscellaneous chemical waste releases to the circulating water system from the retention pond for the r-eriod of 01-01-80 to 06-30-80 included 11,400,000 gallens of clear water waste. The waste water contained 2,420 pounds of - : ended solids and 86,000 pounds of dissolved solids.* When avc d over the reporting period, these discharges were 2.25% of e Technical Specification limit for dissolved solids and 0.136% ce the limit for suspended solids. Retention pond analysis and plant chemical records indicate that the following chemicals were released in the form of clear water . waste from the. retention pond. Sodium 8,821 pounds Chloride 13,613 pounds Phosphate 107 pounds The balance of the dissolved solids were in the form of soluble calcium and magnesium cotpounds resulting from the plant makeup
-water cold lime sof tening process.
- Chemical release calculations are based on retention pond analyses during the period. 01-01-80 to 06-30-80.
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. t 7.3 Correction to Semi-Annual Report, July 1, 1979, through i 4
December 31,~1979 Y t Section* 7.0 (Non-Radioactive Chemical Releases) , subsection 7.1 (Scheduled Chemical Waste Releases), paragraph two should be e '1/ corrected to read as follows: -
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"The concentration increases ' of chemical' waste in the circulation !
water system during the period of chemical releases ranged from ^ ?- 0.0846 tc 7.89 ppm dissolved solids and from 3.14E-04 to 8.45E-02 1. ppa suspended solids." - 3 F
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' 8.0 . CIRCULATING WATER SYSTEM CPERATIONS .
,c3 The circulating water. system operatfon during this reporting period for periods of plant operation is der.y* Sed in Table 8-1. I- .
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9.0 LEAK TESTING OF RADICACTIVE SOURCES _ During the reporting period, all applicable sealed radioactive sources were leak tested according to Technical Specification requirement
'15.4.12. Results of the leak testing showed no removable centamination greater than 0.005 microcuries from sealed radioactive sources. '
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i ( i ' TABLE 8-1 CIRCULATING WATER SYSTEM OPERATION I May June January Februa ry March April I 357.6 625.6 626.7 Average Volume Cooling UNIT 1 363.2 339.1 240.6 . Water Discharge, UNIT 2 314.3 333.5(4) 335.1{1) 465.7(l) ,585.8 Ndllion Gal /Dar 320.0 4
' UNIT 1 47.7 50.3 37.1
' 43.5 48.1- 52.8 Average Cooling Water Intake Temperature )
39.2 4)
) 49.1 Degrees F Unit 2 48.3 51.3' 42.1 52.5 i
- d. Average Cocling Water UNIT 1 70.3 72.8 37.7 64.6 60.8 65.5 1 Y Discharge Temperature Degrees F UNIT 2 79.8 81.1 66.2(4} 65.7(1) 65.7(1) 68.6 l.
i e j' Average Anbient UNIT 1 34.3 33.9 34.8 41.2 45.6 50 j Temperature Degrees F UNIT 2 (3) (3) ( 3) (3) (3) (3)
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i 1 (1) Unit 2 was shut down for refueling from April 11, 1980, to May 14, 1980. 4 l (2) Unit 1 was shut down for steam generator maintenance from February 28, 1980, to April 5, 1980. j (3) Instrumentation out-of-service. 1 (4) Unit 2 was shut down for steam generatar maintenance from February 28, 1980, to March 13, 1980.
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