ML20064A473

Semiannual Monitoring Rept,Jan-June 1990

ML20064A473
Person / Time
Site:	Point Beach
Issue date:	06/30/1990
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20064A472	List: ML20064A471 ML20064A473 ML20064A474 ML20064A475 ML20064A476
References
NUDOCS 9009100031
Download: ML20064A473 (17)

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WISCONSIN ELECTRIC SEMIANNUAL I POWER COMPANY JANUARY,1990 through JUNE 30,1990 I

POINT BE ACH NUCLE AR PL ANT UNIT NOS.1 AND 2 I

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U.S. Nuclear Regulatory Commis i

gm ~ ' L ' ' ,' f Docket Nos. 50-266 and 50-301 s Facility Operating License Nos.

DPR-24 and DPR-27 i

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PREFACE I

This Semlannual Monitoring Report for the period of' January 1,1990, through June 30,1990, is '

submitted in accordance with Point Beach Nuclear Plant Unit Nos.1 cnd 2 Technical Specification I 15.7.8.4 and filed under Docket Nos. 50-266 and $0-301 for Facility Operation License Nos. DPR-24 and

' DPR 27, respectively. -

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' TABLE OF CONTENTS - -i i

3 Section Jfde Paae i

' a 1.0 Radioactive Liquid Releases 2 r i

'. 2.0 Radioactive Airborne Releases 6 i

, ;4 3.0' Radioactive Solid Waste Shipments 8

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l 4.0 .New and Spent Fuel Shipments 8 i -5.0 Radiological Environmental Monitoring 10

., 6.0 Nonradioactive Chemical Releases 12 ~!

7.0 Circulating Water System Operation 12 j' :8.0  ? Leak Testing of Radioactive Sources . .12 L ? 9.0 , Miscellaneous Reporting Requirements I 14 f

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" ' 1.0 l ' RADIOACTIVE LIQUID RELEASES-

.. The total radioactive liquid release excluding tritium for this reporting period was 2.68E-03 curies.

? <  : This included 3.16E-04 curies in processed radioactive waste and primary coolant system '

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letdown,2.98E-04 curies in Unit 1 steam generator blowdown,1.51E 03 curies in Unit 2 steam generator blowdown and 5.59E44 curies in retention pond effluent.

The total tritium release for this reporting period was 4.14E4 02 curies. This included 4.09E402 curies in processed radioactive waste and primary coolant system letdown, 3.33E 02_curles in

'L Unit 1 steam generator blowdown,3.59E+ 00 curies in Unit 2 steam generator blowdown, and :

,' ~ 8.22E 01 curies in retention pond effluent.

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. All radioactive liquid releases to Lake Michigan were made through the circulating water

discharge system..

1.1 Circulatina Water Radionuclide Release Summarvi

1.1.1 - Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summarized --

by individual source, total, and equivalent curie release on a monthly basis and presented in Table 1 1.

i 1,1.2 - Additions to Previous Semiannual Monitoring Report The following information was not available at the time of the previous report preparation and should be added to Table 1 1 of the Semlannual Monitoring I- Report for July 1,1989 through December 31,1989.

6 MONTH I- EQY pgG- TOTAL g; Total Activity

3 Released (Cl)

Gross Alpha < MDA <MDA 6.51E 05

<MDA

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Strontium 4.67E 06 1.21E 04 Average Diluted

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Discharge Con-centration (pCi/cc)

I Gross Alpha <MDA <MDA

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TABLE 1-1  :

ISOTOPIC COMPOSITION CT CIRCUIATING 10&ER DISCHARGE '

JANUARY 1,1990 THROLGH JUNE 30, 1990. -

JAN' TEB MAR' APR ~MAY' JUN .TUTAL' Total Activit

-Released (Ci)y Gamma Scan 6.12E-04 2.38E-G4 9i21E-04 2.39E-04 4.585-04 2.10E-04 :- 2.68E-0 3 ~

Gross Alphs <MDA <MDA <MDA. <MDA <MDA (1)- (1) - W-Tritium 2.41E+01 5.11E+01 6.67E+01 1.84E+01 6.96E+01 1.84E+02 4.14E+02 Strontium (MDA <MDA _. <MDA 9.70E-07 <MDA (1) (1)^

i Total volumes Released (Gal; I _

Processed waste -

3.05E+04 4.80E+04 8.73E+04 1.03E+05 1.36E+05 9.06E404 4.95E+05-2.66E+06 1.27E+07-

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(U1 Steam Generator Blowdown 2.59E+06 1.98E+06 2.76E+06 4.42E+04 2.65E+06 (U2 ))Steam Generator slowdown 2.59E+06 1.97E+06 2.66E+06 2.57E+06 2.59E+06 2.50E+06 1.49E+07 Retention Pond 3.69E+06 3.63E+06 3.89E+06 3.85E+06 3.58E+06 2.87E+06 2.15E+07 -

Total 8.87E+06 7.58E+06- 9.31E+06 6.46E+06 8.82E+06 8.03E+06 4.91E+07 l

volume of Dilution -

l Water (Gal) 9.82E+09 8.87E+09 1.37E+10 1.68E+10 '1.74E+10- 1.66E+10 8.32E+10 W Average Diluted Discharge Concentration (uCi/cc)

Gross Garam 1.67E-11 7.20E-12 1.77E-11 4.64E-12 7.10E 3.33E-12 Gross Alpha (MDA -

<MDA (MDA <MDA <MDA (1)

Tritium 6.48E-07' 1.52E-06 1.28E-06 2.89E-07 1.06E-06 2.92E-06 Strontium (MDA <MDA <MDA 1.52E-14 <MDA (1)

Maximum Discharge Concentration During Release Period (uC1/cc)

Gross Gamma 5.83E-11 5.51E-11 1.07E-09 1.12E-10 8.79E-10 1.423-11 Tritium 1.26E-04 1.45E-04 9.07E-05 5.31E-05 8.45E-05 1.16E-04 Total Equivalent curies Released Co-60 Equivalent Curies 7.69E-04 6.90E-04 5.44E-03' 1.34E-04" 8.69E-04 3.17E-03 '1.11E-02

% Annual RETS Limit 8.12E-04 7.29E-04 5.74E-03 1.41E-049.18E-04 3.35E-03 1.17E-024 I-131 Equivalent curies 9.80E-06 2.48E-06 4.99E-05 1.38E-05' <MDA '< h 7.60E-05

% Annual RETS Limit 3.74E-05 9.47E 1.90E44 5.27E-05 2.90E-04 Tritium Equivalent curies 2.41E+01- 5.11E+01 6.67E+01- 1.84E+01 6.96E+01 1.84E+02 4.14E+02

% Annual RETS Limit 1.25E-01 .2.65E-01 3.46E-01 9.53E-02 3.61E .9.53E-01. 2.14E+00 (1) Information unavailable at time of report preparation.

Note: Dissolved noble gases detected in liquid effluents'aro included'in airborne release totals RETS = Radiological Effluent Technical Specifications.

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1.2' Isotonic Composition of Circulatina Water Discharoes _

1.2.1 Releases During Current Reporting Period ;l The isotopic composition of circulating water discharges during the current

' reporting period is presented in Table 12.

1.2.2 ' Additions to Previous Semlannual Monitoring Report The following information was not available at the time of report preparation and ' , l 1 g. . should be added to Table 12 of the Semlannual Monitoring Report for July 1 .j WL '1989 through December 31,1989.

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'3- 6-MONTH g- HQY pfC- TOTAL (Cl) .,

3.44E 06

' St 89(Cl) . < MDA 3.44E-06 1

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Sr 90(Cl) 1.23E46 <MDA 1.12E 04 f 1.3 jubsoil Drain Syste n Releases of Tritium '

l 1.3.1 , Releases During Current Reporting Period ,j l

The release of tritium via the subsoil drain system during the current' reporting D period is presented in Table 13. >

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, SUBSOIL SYSTEM DRAINS - TRITIUM

SUMMARY

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January 1,1990 through June 30,1990 -

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~~ H_-3 (pCl/cc) . '<MDA <MDA No sample <MDA

!E, Ave. Flow (gpd)' 2.60E+ 03 1.36E + 03 No flow 1.73E+ 04 -

1 , Second Quarter

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[ l H-3 (pCl/cc) <MDA <MDA <MDA <MDA l

. f Ave. Flow (gpd) 9.28E + 03 4.66E + 04 1.16E + 02 1.42E + 04 i ~ Semlannual Totals Total Released (Cl) <MDA <MDA <MDA <MDA < MDA l4: Total Flow (gals) . 1.08E + 0S 4.36E + 06 1.06E + 04 2.85E4 06 8.30E + 06 l 1

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TABLE'1-2 I.;OTOPIC' COMPOSITION OF CIRCULATING WATER DISCHARGES JANUARY 1, 1990 THROUGH JUNE-30, 1990 NUCLIDES JAN TEB MAR AFR MAY JUN TOTAL 3ELEASED (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) .(Curies)

, Tritium ' 2.41E+01 5.11E+01 6.67E401 1.84E+01 6.96E+01 1.84E+02 4.14E+02-I-132 <MDA 4.45E-05 <MDA <MDA (MDA ~ <MDA 4.45E-05 I-133 4.44E-05 (MDA 2.26E-04 6.22E-05 <MDA <MDA '3.33E F-18 5.09E 1.36E-04 1.98E-04 -1.42E 2.99E-04 (MDA- 1.28E-03 Ag-210m . <MDA  :<MDA 8.73E-06  :<MDA (MDA ' <MDA 3.73E-06 Co-58 <MDA ' 1.68E-06 1.23E-05 (MDA <MDA <MDA- 1.40E-05 Co-60 9.36E-06 1.12E-05 1116E-04 2.73E-05 .1.07E-04 (MDA 2.71E-04 Cs-137 4.98E-05 4.48E-05 3.52E-04 6.90E-06 5.02E-05 2.10E-04 7.14E-04 ,

Mn-54 <MDA (MDA 9.01E-06 .<MDA (MDA' <MDA- 9.01E-06 Nb-97 (MDA -(MDA (MDA <MDA 2.44E-06 <MDA 2.44E-06 Sr-89 <MDA (MDA. (MDA- (MDA (MDA. (1) -(1)

Sr-90 <MDA- -(MDA <MDA- 9.70E-07 <MDA (1) (1)

(1) Information unavailable at time v2 . sport preparation.

Note: Dissolved noble gases detected in liquid effluents ^are included ~1n airborne release-totals.

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1.4 Land Application of Sewage Sludge -

Trace amounts of radionuclides may be land appiled with sewage sludges on various l I Department of Natural Resources approved Wisconsin Electric Power. Company properties surrounding the Point Beach Nuclear Plant in accordance with approved

, methodologies pursuant to 10 CFR 20.302. The amounts discharged in the sewage during this reporting period are presented in Table 14. o I q TABLE 14 l

II- SEWAGE SLUDGE' LAND APPLICATIONS a

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. January 1,1990 through June 30,1990 Date of Anotication ,GAEQDs Sjlg ActMtv Released (Cl)

May 30,1990 15,000 PB-01 <MDA L

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!W , , ' 2.0 RADIOACTIVE AIRBORNE RELEASES

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!g The release paths contributing to radioactive airborne release totals during this reporting period .

";g wera the auxHlary buildinq vent stack, drumming area vent stack, gas stripper building vent a stack, Unit 1-containmers purge stack, Unit 2 containment purge stack, combined air ejector; q decay duct exhaust, and turbine building ventuation exhaust.

There was one gas decay 'ank released during this reporting period.

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. 2.1 Radioactive Airborne Reiense Summarv

>, 2.1.1 Releases During Current Reporting Period e RadioactMty released in airborne effluents for the current reporting period are 4

summarized in Table 2-1.

2.1.2 Additions to Previous Semlannual Monitoring Report f

The following information was not available at time of the last report preparation -

[ and should be added to Table 21 of the Semiannual Monitoring Report for  ;

E 7 July 1,1989 through December 31,1989.

i t i 6-MONTH

. .dVL AQQ .Sff .QQI RQY .QEQ TOTAL (Ci) J j {

Strontium

(, (Cl) -<MDA <MDA <MDA <MDA <MDA < MDA <MDA I

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SUMMARY

JANUARY 1,-1990 THROUGH JUNE 30, 1990

--JAN FEB MAR .APR- MAY JUN TOTAL Total Noble Gases (Ci):(2) 2.16E-01 2.23E-01 3.73E-01: 2.62E-01 1.46E-01' 1.46E-01 -1.37E+00 Total Radiolodines (Ci): 1.17E-0 6 -- 4.13E-06 3.19E-05 8.64E-06 2.00E-07 <MDA 4.60E-05 Total Particulates (Ci): 3.37E-06 - 7.45E 7.87E-06 ' 1.97E-05 9.47E-06 <MDA _1.15E-04 Alpha (Ci): _ 6.73E-08 7.34E-05 7.44E-11 (MDA . (MLA~ (MDA :7. 3 5E-0 5 Strontium (Cil: <MDA -(MDA (MDA (1) _(1) (1) - (1)

All Others (Ci): 3.30E-06 1.10E-06 7.87E-06 1.97E-05 9.47E-06 <MDA 4.14E-05 Total Tritium (Ci): 1.05E+01 8.09E+00 1.27E+01 1.42E+01 1.06E+01 9.23E+00 6.53E+01-N Maximum Hourly Average -

Release Rate (3) 2.07E-04 2.36E-04 1.78E-04 2.72E-05 2.27E-04 3.80E-07 (Curies /Second)-

Total Equivalent Curies Released Co-60 Equivalent curies 7.54E-06 8.99E-06 5.23E-06 2.09E-05 7.53E-06 (MDA 5.02E-05 -i

% Annual RETS Limit 4.38E-04 5.23E-04 3.04E*04 1.22E-03 4.38E-04 ~ 0 -- ' 2.92E-03' 1-131 Equivalent Curies 1.17E-06 2.96E-06 1.34E-05 6.39E-06 1.08E-07 <MDA 2.40E-05

% Annual RETS Limit 3.32E-04 8.41E-04 3 . 81E--03 1.82E-03 3.07E-05 6.83E-03 Xe-133 Equivalent Curies (2) 2.86E+00 3.78E+00- 3.53E400 1.55E+00 2.27t+00 - 2.23E+00 .1.62E+01

% Annual RETS Limit . 2.75E-04 3.63E-04 3.39E-04 1.49E-04 2.18E-04 2.14E-04 1.56E-03.

Tritium Equivalent Curies 1.05E+01 -8.09E+00 1.27E+01' . 1.42E+01 1.06E+01 9.23E+00 6.53E+01

% Annual RETS Limit 3.62E-02 2.79E-02 4.38E ' 4.90E-02 3.66E-02 - 3.18E-02 .2.25E-01 1 f (1) Information unavailable at time of' report preparation but values. typically do not' alter monthly totals.

(2) Includes noble.ges contribution:from liquid releases.

(3) Expressed as Xe-133 equivalents.

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~t 2.2 - jagtoplc 6ttthEDe Releases 2.2,1. ' Releases During Current Reporting Period :

. The monthly isotopic airborne releases for the current reporting period are _

presented in Table 2 2.' {

'2.2.2 Additions to' Previous Semlannual Monitoring Report _ -!

n The following information was not available at the time of previous report:

preparation and should be added to Table 2 2 of the Semlannual Monitoring

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l i.=, Report covering the period July 1,1989 through December 31,1989.

. . MONTH.

.duk AUSt . GEE ,QQI h.Qy , EQ . TOTAL (Cil' -;

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Sr 89(Cl) . <MDA <MDA <MDA <MDA ~ <MDA- '<MDA' <MDA. .

Sr 90(Cl) <MDA. <MDA -<MDA <MDA <MDA <MDA < MDA

+ ' 3.0 RADIOACTIVE SOLID WASTE SHIPMENTS

- Solid wastes shipped for burial during this reporting period were as follows:

DATE OF!

gI . SHIPMENT

.T.O BURIAL VOLUME (CUBIC FEET)

TOTAL ACTIVITY :

(CURIES)

BURIAL SITE L5ll -

02/09/90 180.1 (1)l 180,1 (2) 6.92E 02 ' . Barnwell, S.C.

02/21/90 1.40E + 00 ~ Bamwell. S.C.

L _ 02/21/90 180.1 (2) 1.68E+ 00 Barnwell, S.C. 4 E {* 02/27/90 180.1 (2) 2.43E + 00 .. - Barnwell, S.C. I I

'06/25/90 92.5 (1) ' . 6.98E-02 Hanford, WA .

p: .06/25/90 96.0 (1) 6.66E-01 Hanford, WA .;

TOTAL 908.9 6.32E + 00 l . (1) Dry Active Waste L l (2) Evaporator Concentrates I 4.0 NEW & SPENT FUEL SHIPMENTS AND RECEIPTS I' = During this reporting period, a total of 29 new fuel assemblies were received from Westinghouse

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Electric Corporation for Unit 1. The new fuel assemblies received for Unit 1 were used for the. I spring 1990 refueling. '

dF There were no spent fuel shipments made from Point Beach Nuclear Plant during this reporting

- period.

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TABLE 2-2

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l RADIOACTIVE AIRBORNE RELEASE'

SUMMARY

-JANUARY 1,' 1990 THROUGH JUNE 30, 1990 NUCLIDES JAN TEB MAR APR' MAY JUN' TOTAL RELEASED (Curies) -(Curies) (Curies). (Curies) (Curies) (Curies) ( Cu rie s ) '~

-s Tritium 1.05E+01 8.09E+00 1.27E+01 1.42E+01 1.06E+01 9.23E+00 6.53E+01 Xe-133 8.06E-02 7.22E-02 2.37E-01' ' 1.36E-01 5.62E-02 6.06E-02 6.43E-01 Kr-85m 1.47E-03: 3.39E-03 2.71E-03 1.12E-03 1.89E-03 1.14E-03 1.17E-02 Kr-88 4.34E-03 7.93E-03 4.71E-03 ~1.72E-03 5.84E-03 2.88E-03 2.74E-02 Xe-133m 3.80E 1.51E-03 2.58E-03 2.91E-03 6.71E-05 4.41E-04 7.55E-03' Xe-135 1.68E-02 2.37E-02 2.42E-02 1.27E-02 1.54E-02 1.34E-02 1.06E-01 Xe-138 1.67E-02 3.84E-02 2.14E 7.43E-03 2.15E-02 1.21E 1.18E-01' e Kr-87 3.41E-03 7.32E-03 4.18E-03 1.51E-03 4.39E-03 2.63E-03 '2.34E-02' Xe-135m 5.39E-03 1.12E-02 6.42E-03 2.35E-03 6.62E-03 3.81E-03 3.58E-02.

Ar-41 6.06E-02 5.76E-02 7.00E-02 3.17E-02 3.37E-02 4.92E-02' 3.03E-01 Kr-85 '2.71E-02 <MDA (MDA 6.44E-02 (MDA' .(MDA 9.15E-02 I-131 1.17E-06 2.,60 E-0 4 7.68E-06 5.68E-06 7.90E-08 <MDA' 1.72E-05' I-133 .<MDA 1.53E-06 2.42E-05 2.96E-06 1.21E-07 (MDA 2.88E-05 F-18 2.33E-06 <MDA 6.33E-06 (MDA 1.51E-06 <MDA' 1.02E-05 Cs-137 6.45E-07 7.87E-07 3.58E-07 1.26E-06 4.21E-07 (MDA- 3.47E n6 Co-58 3.26E-07' 2.12E-07 7.88E-07 1.83E-05 7.53E-06 kMDA. 2.72E-05 Co-60 5.18E-10 1.08E-07 4.00E-07 2.18E-07 <MDA. (MDA '7.27E-07 Sr-89 (MDA (MDA (MDA. -(1).. (1) (1) (1)

Sr-90 -<MDA (MDA (MDA (1): (1) ~(1) (1)

Alpha 6.73E-08 ' 7.34E-05 7.44E-11 <MDA <MDA L.<MDA . 7.35E-05

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(1) Information unavailatle at time of report preparation but values typically do not alter monthly totals reported in Table _2-1.

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s 5.0l RADIOLOGICAL ENVIRONMENTAL MONITORING r >

Radiolo0ical environmental monitoring conducted at Point Beach Nuclear Plant from January 1, -

1990 through June 30,' 1990 consisted of air filters, milk, lake water, well water, sol, fish,

, . shoreline sediments, algae, vegetation, and TLDs. .

o 1 No siginficant deviations from normal results, attributable to the operation of the Point Beach  !

![ .g. -1 Nuclear Plant, were identified durin0 this six month reporting period ' Low, levels of Sr-90 and

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Os-137, resulting from Chemobyl and atmospheric weapons tests, stil persist in milk (Sr 90) as T 1well as in fish and sol (Cs-137) samples. The first quarter elevated H 3 concentrations in take-I

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J water from two sites north of PBNP were not the result of PBNP operations because 1) the 1

- predominant current direction in this area of the lake la from north to south,2) the concentrations increased with distance northward away from PBNP,3) the elevated

{m' concentrations first appeared at the sampling site furthest north, and 4) no H 3 concentrations -

above the LLD were found in the discharge fiume samples (collected weekly) and at sampling .;

sites south of PBNP,

} A Samole Tvoe ' igg Averaos .ttg!) . .QQts

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g 1 44 ^ Environmental Radiation ~0.58 1.05io.17 1,42 mR/7 days -

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156 Gross beta 0.01 0.02io.01 0.05 - pCl/m 3 156  : Radiolodine all <0.03 ' pCl/m3 12 - Cs 137 all <0.01 pCl/m3 I? '12 12 Other Gamma Emitters Cs-134 all <0.01 all <0.01 pCl/m 3 pCl/m3 5 .l

18 Radiolodine all < 0.5 pCl/l E '18 Sr-89 . all < 5 pCl/l 3~' 18 Sr-90 0.8 1.410.4 2.3 pCl/l 18 Cs-134 all < 5 - ' pCl/l 18 Cs-137 all <5 pCl/l I 18

.18 Other Gamma Emitters Ba-La 140 all ' < 5 all < 5 pCl/l pCl/l Q

1 Lake Water 30 Gross Bet:: 1.7 2.6i0.8 6.1 pCi/l 10 Tritium <500 <677i434 1856 pCl/l 10 Sr-89 all <5 pCi/l 10 Sr-90 all <1 pCl/l I

.. m o 30 Radiciodine all < 0.5 pCi/l

=g 30 Mn all < 10 pCl/l 30 Fe-59 all <30 pCi/l 30 Co-58 all < 10 pCi/l )

30 Co-60 all <10 pCi/l  ;

5 30 Zn-65 all <30 pCi/l I 30 Zr Nt> 95 all < 15 pCl/l 30 Cs-134 all <10 pCl/l I. 30 30 Cs-137 Ba-La-140 all <10 all < 15 pCl/l pCl/l l

30 Other Gamma Emitters all <30 pCl/l 10

5;

~ ~

, , g t

, t

~

, .A: ' Samnie Typt - Jm/, . Average High .MORg '

,. ,Well Water -

]

! 2- . Gross Beta- < 3.5 < 4,1 i o.8 4.6 - pCl/l *

. 2- H-3 " all <500 ' pCl/l . a 2 ' St-89 ' all < 5 pCl/l . 1 j 2! ' St-90 all < 1 : pCl/l t W 2 1-131- all <0.5 pCi/l .

. 2 Mn-54 all <10 pCl/l - 'l 2 Fe-59 all <30 pCl/l  !

2' Co-5B all < 10 - pCi/l 2i Co40 all <10 ' pCl/l ~a; 2" Zn45 all <30 pCl/l .

i 2 Zr-Nb-95 all <15 pCl/l

.I- 2 Cs-134 all <10 pCl/l '

u' 2 Cs-137 all <10 pCl/l i 2 Ba La 140 all <15 pCl/l s 2- Other Gamma Emitters all <30 pCl/l Egb .

3 Gross Beta - 2.1 2.910.8 3.7 . pCi/g wet :

3- Mn all <0.13 pCl/g wet R3 3 Fe-59 all < 0.26 ' pCl/g wet h3; 3- Co-58 all <0.13 - - pCl/g wat ;

!c 3- Co40 all <0.13 - pCl/g wet L T 3 Zn-65 all <0.26 - pCl/g wet

[. 3' Cs-134 all <0.13 pCl/g wet 3 Cs-137 . <0.15 <0.17 0.04 - 0.22 pCl/g wet 3 Other Gamma Emitters all < 0.5 ' pC:/g wet -

1Q!!

l L

I -8

-8:

8 Gross Beta '

.Cs-137 -

Other Gamma Emitters

.17.3 0.17 24.Si5.4 0.36 i 0.19 all <0.15 35.0

-0.41 pCl/g dry .

pCl/g dry pCi/g dry j

-i' Shoreline Sediment

f. Gross Beta 6.4 7.6i0.9 8.8 pCl/g dry

.gj 5 , Cs-137 all <0.15 pCl/g Wy 1 Wl 5 Other Gamma Emitters all <0.15 pCl/g dry j

l': Veaetation

<' 8 Gross Beta 5.0, 6.210.9 7.5 pCl/g wet l 8- Cs-137 all <0.08 pCl/g wet

! 8 Cs-134 all <0.06 pCi/g wet l

8- l-131 all <0.06 pCl/g wet i

.; 8' Other Gamma Emitters all <0.25 pCl/g wet '

I' 1

I I

u

_ , - - - - . - - . -- c ..

gdf.f .

4 1 e

p;(W

'j p[

3,

.L

'*i 4 g Samole Tvoe igg Average Illgb i .U.Dh5 k Algag j

W '2 Gross Beta 4.7 4.910.2 . 5.0 pCl/g wet

( ,C 2 Co . all . < 0.25 pCl/g wet -  !

pg 2 'Co40 ~a ll < 0.25 pCl/g wet i 5' 2 2

C' '34 Cs 137

'*'i <0.25 all <0.25 pCi/g wei pCl/g wet i 2 Other Gamma Emitters all <0.25 pCl/g wet -

}

6.0 NONRADIOACTIVE CHEMICAL RELEASES a

' 6.1 Scheduled Chemical Waste Releases s

I Scheduled chemical waste releases to the circulating water system from January 1, 1990 to June 30,1990 Included 5.03E+ 06 gallons of neutralized wastewater.: The wastewater contained 3.24E+02 pounds of suspended solids and 4.20E + 05 pounds of dissolved solids.

I

• Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralizing tanks.

a 6.2 Miscellaneous Chemical Waste Releases 4 ll Miscellaneous chemical waste releases from the retention pond (based on effluent L analyses) to the circulating water for January 1,1990 to June 30,1990 included l b=<>

2,15E+07 gallons of clear wastewater. The wastewater contained 1.83E+03 pounds of suspended solids. .

!

• Miscellaneous chemical waste released directly to the circulating water, based on ,

a amount of chemicals used for January 1,1990 to June 30,1990 included 1.15E+ 04

)g pounds of sodium bisulfite and 5.92E+ 03 pounds of sodium hypochlorite. '

Lg .7.0 ;

A p ' CIRCULATING WATER SYSTEM OPERATION L L The circulating water system operation during this reporting period for periods of plant operation l Is described in Table 71. '

t E

g 8.0 LEAK TESTING OF RADIOACTIVE SOUR 0ES During this reporting period all applicable sealed radioactive sources were leak tested in  !

; accordance with Technical Specification 15.4.12. Leak test results were all <0.005 pCl.

L  ;

I 12 t

.. w

~

1 TABLE 7-1 4 >

CIRCULATING WATER SYSTEM OPERATION-January 1,1990 to June 30, '1990 -

JAN f18 .t&E* ; APR* ,jfE* JyN-i . .

Average Volume Cooling U1 316.8 - 316.8' 436.4 313.9 504.3 ' '554.4-Water Discharge

' (Million Dal/ day) l U2 316.8 316.8 449.0 561.8 561.9 ' 554.4 -

Average Cooling Water Ut 36.1 - 35.8 38.5 39.9- . 48.7 - 48.9-

'i - Intake Temperature l-

. (Degrees F) U2 36.1 35.8- 38.5 41:9[ '47.4 48.8 Average Cooling Water UI- 67.6 67.2 58.7 - 42.5 63.2 67.5 Discharge Temperature

.. (Degrees F) U2 67.9 68.2 59.8 59.1 64.9 68.9 J . Average Ambient Lake Temperature I (Degrees F) . 35.0 34.5 37.2 41.5 46.6 ' 47.0 )

tg (* = Unit 1 refueling shutdown from March,31,1990 to May 13,1990) il ll f

L .i l ..

I ,

i l: la

y ,

=--

! yt ,

n 9.0. ; MISCELLANEOUS REPORTING REQUIREMENTS 11"~

9.1' Revisions to the PBNP Offalla Dose Calculation Manual (ODCM) and Process Control 1 Proaram (PCP) '

if Revisions were made.to the'ODCM, Environmental Manual and PCP during this I

reporting period.1 Complete copies are being sent to the NRC. The changes are 1 summarized below.~ .

.Two improvements were made to the PCP to address the following: '

i 4 1,1 revised Wisconsin Electric Quality Procedures for vendor approval, ,

3'

2. concerns regarding waste solidification as expressed by the NRC at its s solidification workshop.

Changes and improvements made to the Environmental Manual consist of the following:. 1 j

1. new identification numbers of forms used for sample collection and scheduling .

~ based upon the new PBNP form numbering system, I

2. wording added to clarify instructions for sample collection and handling, .

I 3. chang in the radioanalytical vendor's telephone number to reflect new Chicago

suburb area code.

The two revisions to the ODCM consist of the following: }

1. Rev. 4, March 1990 (Appendix A.2) reflects the new Point Beach Nuclear Plant's'

Wisconsin Pollutant Discharge Elimination System permit which allows the Ll u

characterization of non-radiological chemical and physical properties of sewage *

B sludge for land application to be made on an annual basis as compared to the 1 previous per application basis,

2. Rev 5, June 1990 (pages 3-2 through 3-5) reflects changes to the liquid n release alarm setpoint methodology. Our analysis of the previous setpoint 1~

methodology based on the Coe MPC revealed the potential for a non-conservative result for certain radionuclides. This potential is 9 e= corrected in the methodology in which the liquid release alarm setpoints

[ls i

are based on the PBNP historical (19851989) 5 year weighted a.verage circulating water radionuclide concentration scaled to equal a weighted average MPC in the circ water system under maximum flow.

The changes to the ODCM and PCP increase the overall effectiveness of these

[

programs.

Intertaboratory Comoarlson Prooram

~

. 9.2 L'

The analyticallaboratory contracted to perform the radioanalyses of the PBNP L environmental samples participated in the EPA Intertaboratory Comparison Program during this reporting period.

l 9.3 Deviations from Soecified Environmental Samole Tvoes. Locations. and Frecuencies Sample types, sampling locations, and collection frequencies complied with Technical Specification 15.7.7.A during this reporting period.

L L$ W  !

14

r..

i, j.

o.. ,

'I s 95- Suinmarv of Unachievable Soecified Environmental LLDs

' All LLDs listed in Table 15.7,7 22 of the PBNP Technical Specifications were during this -

I sampling period..

~

f q 9.5 Soecial Circumstances No special circumstances report regarding operation 'of the explosive gas monitor for the waste gas. holdup system was needed during this reporting period.- ,

e .

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I I 15