Text

Semiannual Monitoring Rept Jul-Dec 1994
	ML20080K263
Person / Time
Site:	Point Beach
Issue date:	12/31/1994
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20080K256	List: ML20080K263; ML20080K267; NPL-95-0078, Forwards Semiannual Monitoring Rept Jul-Dec 1994, Containing Info Re Plant Releases,Solid Waste Shipments,New & Spent Fuel Shipments,Environ Monitoring,Cw Sys Operations & Leak Testing of Sources.Revised Environ Manual Also Encl;
References
	NUDOCS 9502280463
	Download: ML20080K263 (51)
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l WISCONSIN ELECTRIC SEMIANNUAL l

i MONITORING REPORT JULY 1994 through DECEMBER 1994 POWER COMPANY POINT BEACH NUCLEAR PLANT UNIT NOS.1 AND 2 1

I U.S. Nuclear Regulatory Commission Docket Nos. 50-266 and 50-301 Facility Operating License Nos.

DPR-24 and DPR-27 9502280463 950220 PDR ADOCK 05000266 l I

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4 PREFACE This Semiannual Monitoring Report for the period of July 1,1994, through December 31,1994, is submitted in accordance with Point Beach Nuclear Plant Unit Nos. I and 2 Technical Specification 15.7.8.4 and filed under Docket Nos. 50-266 and 50-301 for Facility Operation License Nos. DPR-24 and DPR-27, respectively.

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TABLE OF CONTENTS Section T3 Eagg 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 5 3.0 Radioactive Solid Waste Shipments 6 4.0 New and Spent Fuel Shipments 6 5.0 Radiological Emironmental Monitoring 9 6.0 Nonradioactive Chemical Releases 13 7.0 Circulating Water System Operation 13 8.0 Leak Testing of Radioactive Sources 13 9.0 Miscellancous Reporting Requirements 14 l

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SEMIANNUAL MONITORING REPORT July 1,1994 to December 31,1994 1.0 RADIOACTIVE LIOUID RELEASES The total radioactive liquid release, excluding tritium for this reporting period, was 6.46E-02 curies. This included 1.78E-03 curies in processed radioactive waste and primary coolant system letdown,5.31E-04 curies in Unit I steam generator blowdown,6.19E-02 curies in Unit 2 steam generator blowdown and 4.08E-04 curies in retention pond effluent.

The total tritium release for this tcporting period was 2.13E+02 curies. This included 2.12E+02 curies in processed radioactive waste and primary coolant system letdown,1.72E-02 curies in Unit I steam generator blowdown,1.29E+00 curies in Unit 2 steam generator blowdown and 1.56E-01 curies in retention pond emuent.

1.1 Circulatine Water Radionuclide Release Summary 1.1.1 Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summaiized by individual source and total curic released on a monthly basis and presented in Table 1-1. Table 1-1 also contains the comparison between the annual Appendix 1 dose limits for liquid emuent and the corresponding highest doses ;

calculated according to the ODCM using the semiannual and annual isotopic composition of the liquid discharge.

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 Semiannual Monitoring ;

Report for January 1,1994, through June 30,1994.

June 6-month Total i Total Activity Released [Ci]

Gross Alpha <MDA 2.89E-06 j Strontium 1.8E-07 3.32E-05 l Average Diluted Discharge l Concentration luCi/cc]

Gross Alpha <MDA Strontium 3.2E-15 1

Table I-1 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGE JULY 1,1994 THROUGH DECEMBER 31,1994 July A ugust Se ptem ber October N eeem ber D ecem ber Total T otal A ctivity R eleased lCl]

G amm a Sean 1. 8 9 E -0 2 2.01 E-0 2 1.0 4 E 0 2 1.7 0 E-0 3 7.3 9 E-0 3 6.10 E-0 3 6.4 6 E-0 2 Gross Alpha 4.7 0 E -0 3 0.00 E + 00 0.0 0E + 00 1.2 0 E -0 6 7.8 7 E-0 8 [1] l .3 3 E-0 6 T ritis m 3.0 6 E + 01 2.9 0 E + 01 6.6 7 E + 0 i 9.4 7E + 0 0 3.3 7E + 01 3.8 5 E + 0 3 2.13 E + 0 2 S tro ntiu m 4.0 0 E-0 7 9.4 9 E-0 7 1.0 4 E -0 5 1.2 0 E -0 6 3.5 4 E -0 7 ll] 1.3 3 E-0 5 Total V elem e Released [ gall Processed vv aste 6.2 6 E + 0 4 5.57E+04 2.5 0 E+ 0 5 9.3 9E +0 4 1.0 4 E + 0 5 5.5 5 E + 0 4 6.2 7 E + 0 5 U I Steam Generator Blow down 3.5 7 E + 0 6 3.5 5 E + 0 6 3.I I E + 06 3.5 7E + 06 3.4 6 E + 06 2.6 8 E + 06 1.99E+07 U 2 Steam G ener ator B low down 3.5 5 E + 06 3.5 5 E + 0 6 2.61 E + 0 6 2.9 4 E + 0 5 4.7 5 E + 0 6 2.6 7 E + 0 6 1.74E+07 R etention Pond 2.5 3 E + 0 6 2.9 0 E + 0 6 2.7 7 E + 0 5 2.19 E + 0 6 4.2 t E + 06 4.7 3 E + 06 1.93E+07 M is c ella n eo u s 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 0 E + 00 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 0 E + 00 0.0 0 E + 0 0 Total 9.71 E + 0 6 1.0 l E + 0 7 8.74E+06 6.15 E + 06 1.25E+07 1.01E+07 5.73E+07 Volume ef Dilutten W ater [eet 5.7 5 E + 13 5.75E+13 5.5 9 E + 13 5.91 E + 13 5.3 8 E + 13 3.3 t E + 13 3.3 7E + 14 A verage Diluted Discharge Cemeentration [uCI/cel Gamma Scan 3.2 9 E-10 3.5 0 E-10 1.8 6 E-10 2.ssE.Il 1.3 7 E-10 1.8 4 E-10 G ross Alpha 8.17 E -16 0.0 0 E + 0 0 0.0 0 E + 0 0 2.0 3 E-14 1.46E-15 [1]

T ritiu m 5.3 2E-0 7 5.0 4 E-0 7 1.19 E -0 6 1.6 0 E -0 7 7.19 E-0 7 1.16 E -0 6 S tro ntiu m 6.9 6 E -15 1.6 5 E-14 1.8 6 E -13 2.0 3 E-14 6.5 8 E-15 [Il M azie nne Discharge Coneentrattens luCl/cel Gross G amm a 6.5 3 E-10 4.9 9 E - 10 3.4 3 E-10 2.9 0 E-10 2.4 0 E-0 7 3.6 2 E-10 T ritiu m 3.8 0 E-0 5 2.5 9 E-0 5 2.6 6 E-0 5 5.10 E *0 6 4.2 2 E-0 5 3.6 8 E -0 5

[1) Information unavailable at time of report preparation Note: Dissolved noble gasses detected in liquid effluents are included in airborne release totals COMPARISON OF LIQUID EFFLUENT DOSES TO ANNUAL APPENDIX 1 DOSE LIMITS Annual Limit imreml January-June Highest Total Calculated Dose Imreml January-December Highest Total Calculated Dose Imreml 6 (uholebody) 1.97E-03 (infant) 3.64E-03 (infant) 20 (any organ) 2.59E-03 (infant thyroid) 3.84E-03 (infant th)Toid) 2 e

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Table 1-2 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGES JULY 1,1994 THROUGH DECEMBER 31,1994 July August September October November December Total Isotope [Cil [Ci] [Cil [Ci] [Cil [Ci] [Ci]

H-3 3.06E+01 2.90E+01 6.67E+01 9.47E+00 3.87E+01 3.85E+01 2.13E+02 1-131 6.73E-04 4.37E-05 6.88E-06 <MDA <MDA <MDA 7.24E-04 1-132 7.72E-04 2.23E-04 5.67E-04 1.73E-05 <MDA <MDA 1.58E-03 '

I-133 3.24E-03 3.19E-03 1.54E-03 3.02E-05 1.05E-03 5.57E-04 9.61E-03 1-135 2.64E-04 1.33E-03 <MDA <MDA <MDA <MDA 1.59E-03 F-18 1.26E-02 1.34E-02 7.87E-03 3.04E-04 5.61E-03 4.%E-03 4.47E-02 MN-56 2.12E-04 <MDA <MDA <MDA <MDA <MDA 2.12E-04 CO-58 3.19E-06 <MDA 8.56E-06 6.46E-05 1.13 E-05 1.42E-05 1.02E-04 CO-60 8.80E-05 1.70E-05 3.19E-05 3.81E-05 1.84E-05 8.72E-05 2.81E-04 Y-93 <MDA 1.33E-03 <MDA <MDA <MDA <MDA 1.33E-03 TC-99M <MDA <MDA 7.24E-05 <MDA <MDA <MDA 7.24E-05 AG-Il0M 6.01E-04 2.61E-05 1.31E-04 2.57E-04 5.%E-05 7.49E-05 1.15E-03 TE-131 1.62E-04 3.60E-04 <MDA <MDA <MDA <MDA 5.22E-04 CS-134 <MDA <MDA 7.12E-05 3.92E-04 1.77E-04 <MDA 6.40E-04 CS-137 1.72E-04 1.06E-04 1.22E-04 5.93E-04 4.68E-04 <MDA 1.46E-03 BA-140 <MDA <MDA 3.29E-06 <MDA <MDA <MDA- 3.29E-06 CE-141 <MDA <MDA <MDA <MDA <MDA 4.08E-04 4.08E-04 t

SR-89 <MDA <MDA 8.51E-06 <MDA <MDA [1] [1]

SR-90 4.00E-07 9.49E-07 1.89E-06 1.20E-06 3.54E-07 [1] [1]

[1] Information unavailable at time of report preparation Note: Dissolved noble gasses detected in liquid effluents are included in airborne release totals 3

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1 1.2 1sotopic Composition of Circulatine Water Discharces

.1.2.1 Releases During Current Reporting Period 1

The isotosc composition of circulating water discharges during the current reporting period is presented in Table 1-2.

1.2.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of report preparation and should be added to Table 1-2 of the Semiat.nual Monitoring Report for January 1,1994, through June 30,1994. ;

i Nuclidq Lung 6-Month Total SR-89 [Ci] <MDA <MDA SR-90 [Ci] 1.8E-07 3.32E-05 l

1.3 _ Subsoil Drain System Releases of Tritium 1.3.1 Releases During Current Reporting Period The releases of tritium via the subsoil drain system during the current reporting l period is presented in Table 1-3. l l

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'1 TABLE 1-3 -!

l SUBSOIL SYSTEM DRAINS - TRITIUM SUhatARY l July 1,1994 through December 31,1994 l l

Third Ouarter S-1 S-3 M S-10 Intal t l 113 [ Ci/cc] <MDA <MDA <MDA <MDA t Ave. Flow [gpd] 6.34E403 5.76E+03 1.36E+04 4.00E+02 Fourth Ouaner 113 [ Ci/cc] <MDA <MDA No Sample <MDA Ave. Flow [gpd] 2.96E+03 6.55E+02 No Flow 1.73E+04 1

Semiannual Totals Total Released [Ci] <MDA <MDA <MDA <MDA <MDA l Total Flow [ gall 8.56E+05 5.90E+05 1.25E+06 1.63E+06 4.32E+06 l l

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1.4 Land AnpliEatign of Sewace Sludae The Wisconsin Department of Natural Resources has approved the land-application of sewage sludges on various Wisconsin Electric Power Company properties surrounding the Point Beach Nuclear Plant. These sewage sludges, which may contain trace amounts of radionuclides, are applied in accordance with methodologies approved on January 13, 1988, pursuant to 10 CFR 20.302. The amounts discharged in the sewage during this reporting period are presented in Table 1-4.

TABLE 1-4 SEWAGE SLUDGE LAND APPLICATIONS July 1,1994 through December 31,1994 Date of Appliggign Q;1Ligns Si_tg Activity Relqugd1Cil September 15 13800 PB-02 <MDA October 4 7700 PB-02 <MDA November 30 8200 PB-02 <MDA 2.0 BA_DIOACTIVE AIRBORNE RELEASES The release paths contributing to radioactive airborne release totals during this reporting period were the auxiliary building vent stack, drumming area vent stack, gas stripper building vent stack, Unit I containment purge stack, Unit 2 containment purge stack, combined air ejector decay duct exhaust and turbine building ventilation exhaust.

There were three gas decay tank releases during this reporting period.

2.1 Radioactive Airbgrne Rqlgase Summary 2.1.1 Release During Current Reporting Period Radioactivity released in airborne efTluent for the current reporting period are summarized in Table 2-1. Table 2-1 also contains the comparison of the annual Appendix I dose limits for atmospheric effluents to the highest organ dose and the noble gas doses calculated using ODCM methodology and the isotopic composition of atmospheric releases identified in Table 2-2. ,

2.1.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of the last report preparation and should be added to Table 2-1 of the Semiannual Monitoring Report for January 1, IN through June 30,1994.

Iptal Particulates Aprtl May LLn.e 6-Month Total Strontium [Ci] <MDA <MDA <MDA <MDA 5

2.2 1sotopic Airborne Rels;Lsg 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 Semiannual Monitoring Report The following information was not available at the time of previous report preparation and should be added to Table 2-2 of the Semiannual Monitoring Report, covering the period January 1,1994, through June 30,1994 Euglids Apfil May n hLns 6-Month Total SR-89 [Ci] <MDA <MDA <MDA <MDA SR-90 [Ci] <MDA <MDA <MDA <MDA 2.2.3 Corrections to previous Semiannual Monitoring Report The Table 2.2 April value for Tritium was incorrectly reported as 1.02E+00 Cl.

The correct value is 1.02E+01 Ci. The reported Tritium total is correct. ,

3.0 BADIOACTIVE SOLID WASTE SHIPMENTS l There were no solid waste shipments for burial or on-site storage during the period from July 1, 1994 to December 31,1994, 4.0 NEW AND SPENT FUEL SHIPMENTS AND RECEIPTS During this reporting period, a total of 29 new fuel assemblics were received from Westinghouse Electric Corporation for Unit 2. The new fuel assemblies received for Unit 2 were used for the ,

Fall 1994 refueling.

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

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1 TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE

SUMMARY

JULY 1,1994 THROUGH DECEMBER 31,1994 July August September October November December Total Total Noble Gasses ICi] [1] 3.73E-01 3.30E-01 3.12E+00 2.39E+00 1.47E-01 6.03E-01 6.96E+00 Total Radioiodines [Cil 1.01E-05 5.21E-10 3.17E-06 7.91E-10 1.l lE-08 2.20E-08 1.33E-05 Total Particulates [Ci] 8.35E-05 4.01E45 1.66E-04 1.27E-03 7.47E-05 8.14E-05 1.72E-03 Alpha [Ci] 6.08E-05 4.01E-05 1.51E-04 1.12E-04 6.31E-05 8.14E-05 5.08E-04 Strontium [Ci] <MDA <MDA <MDA [2] [2] [2] [2]

All Others [Ci] 2.27E-05 0.00E+00 1.50E-05 1.16E-03 1.16E-05 0.00E+00 1.21E-03 Total Tritium [Ci] 4.19E+00 2.81E+00 3.85E400 1.63E+01 3.99E+00 3.52E+00 3.47E+01 Max IIourly Ave Release Rate [Ci/sec) 1.33E-06 1.28E-06 2.87E-06 2.54E-06 2.54E-06 5.53E-07

[1] Includes noble gas contribution from liquid releases.

[2] Information unavailable at time of report preparation, but values typically do not alter monthly totals.

COMPARISON OF EFFLUENT DOSES TO APPENDIX I LLMITS Cateeory Annual Dose Limit January-June Calculated Dose Imreml January-December Calculated Dose Imreml Particulate 30 mrem / organ 6.21E-03 4.48E-02 Noble Gas 40 mrad (p air) 3.77E-04 1.56E-03 Noble Gas 20 mrad (y air) 7.84E-04 3.27E-03 Noble Gas 30 mrem (skin) 5.22E-04 2.18E-03 Noble Gas 10 mrem (whole body) 9.10E-04 3.84E-03 7

TABLE 22 RADIOACTIVE AIRBORNE RELEASE

SUMMARY

JULY 1,1994 THROUGH DECEMBER 31,1994 N acil4 e J u ly A u 8ust Septem ber O ctober N esem ber D ecem ber T otal IV il ICll 1C 11 tCil 1C 11 ICII ICil 11 - 3 4.19 E + 0 0 2.8 t E + 0 0 3.8 5 E + 0 0 1.6 3 E + 0 ! 3.9 9 E + 0 0 3.5 2 E + 0 0 3.47E + 01 i

A R -41 1.3 5 E 01 1.5 5 E -01 1.31E+00 7.9 9 E -01 8.95E-02 2.6 5 E 2.7 5 E + 0 0 K R -85 7.4 7 E-0 2 6.9 9 E -0 2 5.4 7 E -0 2 <MDA <MDA <M D A 1.9 9 E -01 '

K R-85 M 5.5 7 E-03 3.9 8 E -0 3 7.0 4 E -0 2 6.5 2 E -0 2 I .9 0 E -0 3 1.2 8 E -0 2 I .6 0 E -01 K R-87 1.2 2 E -0 2 8.9 4 E -0 3 1.6 2 E -01 1.4 8 E -01 4.4 6 E -0 3 3.0 8 E -0 2 3.6 6 E -01 K R-88 1.3 5 E-0 2 9.9 0 E -03 1.7 4 E -01 I .6 l E-01 4.7 5 E -0 3 3.2 8 E -0 2 3.9 6 E -01 X E 13 3 2.9 8 E-0 2 6.4 5 E -0 3 - 3.7 3 E -0 2 5.7 8 E -0 2 7.6 3 E -0 3 1.6 6 E -0 2 1.5 6 E -01 X E-133 M I .9 8 E-03 1.4 9 E -0 4 5.19 E -0 3 6.0 7 E -0 3 5.0 6 E -0 5 <M D A l .3 4 E -0 2 l X E-13 5 2.7 0 E -0 2 4 .7 9 E -0 2 3.2 6 E -01 3.3 0 E-01 9.9 6 E -0 3 6.12 E -0 2 7.7 2 E 01 X E -13 5 M I .7 7 E -0 2 1.4 7 E -0 2 2.4 3 E -01 2.0 0 E -01 6.6 7 E -0 3 4.2 4 E -0 2 5.2 4 E -01 X E-13 8 5.6 2 E -0 2 4.31 E -0 2 7.3 6 E -01 6.2 3 E -01 2.16 E -0 2 1.4 2 E -01 1.6 2 E + 0 0 1-131 8.51 E -0 7 5.2 t E -10 1.5 3 E -0 6 <M D A 1.6 5 E -09 4.3 0 E -0 9 2.3 9 E -0 6 l-132 <MDA <MDA <MDA <MDA 4.2 4 E -0 9 <MDA 4.2 4 E -09 l-133 2.7 t E -06 <MDA 1.6 4 E -0 6 7.91 E -10 5.2 2 E-09 1.7 7 E -0 8 4.3 7 E -06 l-135 6.5 I E -06 <MDA- <MDA <M D A <MDA -<MDA- 6.5tE-06 F-18 2.2 4 E -0 5 <MDA 1.4 6 E -0 6 <MDA <MDA <MDA 2.3 9 E -0 5 CO 57 1.4 6 E -0 8 <MDA <MDA <MDA <MDA <M D A 1.4 6 E -0 8 C O -5 8 <MDA <MDA 6.3 2 E -0 7 5.3 9 E -0 7 <MDA <MDA 1. I 7 E -0 6 C O -60 <MDA <MDA <MDA 1.81E-06 1.12 E -0 5 <MDA 1.3 0 E -0 5 HR-82 1.4 3 E -09 I .9 I E -0 9 <MDA l .2 3 E -09 6.6 0 E - 10 1.2 3 E -09 6.4 6 E -0 9 C S-13 4 <MDA <MDA 5.2 S E -0 6 1.2 8 E -0 4 5.2 7 E -0 8 <MDA- 1.3 3 E -0 4 C 3-13 4 M <MDA <M D A 1.4 4 E -0 9 <MDA <MDA -<MDA 1.4 4 E -0 9 C S-13 7 2.69 E -07 <MDA 8.12 E -0 6 7.9 7 E -0 4 1.3 9 E -0 7 <MDA 8.0 6 E -0 4 C S-13 8 <M D A <M D A <MDA 2.31 E -0 4 2.18 E -0 7 <MDA 2.3 t E-04 A I, P il A 6.0 8 E -0 5 4.0lE-05 1.51E-04 1.12 E -0 4 6.31 E -0 5 8.14 E -0 5 5.0 8 E -0 4 S R-89 <MDA <M D A <MDA Ill [1] [Il [1]

S R -90 <MDA <MDA <MDA [Il ll] [Il [l]

[1] Information unavailable at time of report preparation, but values typically do not alter monthly totals reported in Table 2-1.

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I 5.0 MDIOLOGICAL, ENVIRONMENTAL MONITORING l 5.1 Introduction )

l The results in this Semiannual Report are presented in the new format which was initiated with the January - June 1992 Report. Results are reported directly as measured, )

including negative and zero values. This climinates the distortion of the results and long-term trends which occurs when the LLD is used to censor results that are below the LLD. This reporting convention follows that recommended in Health Physics Society Committee Report HPSR-1 (1980) released as document EPA 520/1-80-012.

The REMP results are presented in Table 5.1. The table contains the following information:

Sample: the type of the sample medium

Description:

the type of measurement LLD: the a priorilower limit of detection N: the number of samples analyzed Low: the lowest measured value

its associated 2s counting error Average: the average value i the standard deviation of N samples High: the highest measured value

its associated 2s counting error Units: the units of measurement Additional information also is presented in Table 5.1. Not all of the results in Table 5.1 are required by the PBNP radiological efIluent technical specifications (RETS). Non-RETS items and values are noted by an asterisk (*). For certain analyses, an LLD which is lower than that required by RETS is used. For these analyses, both LLDs are listed with the RETS LLD given in parentheses. Occasionally, anomalous results are obtained which lie well outside of the range of expected values. These results will be investigated and discussed in the narrative portion of this section. Blank values have not been subtracted from the results presented in Table 5.1.

5.2 Discussion Radiological environmental monitoring conducted at the Point Beach Nuclear Plant from July 1,1994 through December 31,1994 consisted of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs.

All TLD results for the reporting period were within the normal range. Site E-12, located on the discharge fiume pier continues to exhibit some of the lowest values whereas E-32, approximately 1 mile west of the plant, continues to exhibit the highest.

The higher values at E-32 have been noted since TLDs were first located at this site.

The reason for this result is not known and continues to be tracked. Note that TLD results from sites E-3 and E-31, located about 1200 feet north of E-32 at about the same distance from the plant, typically are 0.1 - 0.4 mR/ week lower than E-32 and continue to be so for this reporting period.

The analyses for individual radionuclides reveals that Sr-90 and Cs.137 continue to occur in emironmental samples. Sr-90 continues to pctsist in milk and water. Cs-137 occurs in sediment, fish, algae, vegetation, and soil. These radionuclides routinely occur in emironmental samples collected around the world and are attributable to the large scale atmospheric weapons tests of the 1960's, less frequent testing in the 70's and 80's, and to the Chernobyl accident.

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. i Tritium concentrations continue to be low. Three of the ten H-3 results for lake water j

, - were statistically equal to zero and two other results were within the range of results . .i obtained from blanks (-74.6

80.5 to 148

101 pCi/l). Both well water H-3 results ';

are not statistically different from zero. Tritium, in addition to being produced by - j' water-cooled reactors such as PBNP, also is a naturally occurring radionuclide.

Measured concentrations of RETS specified radionuclides occur as positive and -l Jnegative values scattered around zero. Although the positive values are usually smaller - !

- than their associated error, small, non-zero values (below the associated LLDs) whose - '!

2s error does not overlap zero occur for several radionuclides.

Most of the " positive" results occur for water samples. Of the thirty (30) analyses of lake water for radionuclides other than ones specified in RETS, two (2) results obtained in October are statistically greater than zero. The "other" radionuclide in this instance . ;i is Ru-103. Measured concentrations were four standard desiations greater than zero,1.5 .

t 0.7 pCi/l at E-06 and 1.6 t o.7 pCi/l at E-33. These sites are 1.5 and 4 miles north of :j PBNP, respectively. ' Note that Ru-103 also was detected at low levels (0.0061 1 0.0030 l and 0.001910.0017 pCi/g)in two of seven fish analyzed during October. Other positive lake water results occurred at E-05 in July (Mn-54: 3.4 i 2.4 pCi/1; Co-60: 4.1- ;

i 2.7 pCi/l), at E-05 in August (Co-60: 3.1 i 1.5 pCi/l), and at E-06 in November (Co- ;

60: 2.7 i 2.2 pCi/l). Finally, positive cobalt results were obtained for algae from E 05

and E-12: Co-58 in August and September (0.137 i o.024 and 0.068 i 0.020 pCi/g, ;

respectively) and Co-60 in August (0.02010.012 pCi/g) at E-05 and Co-58 (0.024 i 0.013 pCi/g) at E-12. j All of these small, positive values are lower than the LLDs and therefore lower than - {

25% of the notification values which would require a summation of fractions when more .

than one radionuclide is identified in an emironmental sample. Furthermore, these , .

positive values do not have the results for blank analyses subtracted. For example, the November lake water Co-60 concentration at E-06,2.712.2 pCi/l, is in the range of j blank values for the last two years, -3.09 i 3.52 to 2.9

2.1 pCi/1. Hence, subtraction of blank values would result in many of the positive values being statistically i indistinguishable from zero. However, the positive resuhs for Co-60, Co-58, Mn-54, and !

Ru-103 from lake water and algae obtained at E-05 during the months of July, August,- l and September together with the positive Ru 103 results for two of the seven fish samples for the same time period suggest a related source. j While there are not enough statistically significant results to draw any definite -

conclusions as to the source, the results do not appear to be related to PBNP effluent. ,

First, seven of the ten positive results are at E-05 and E-33 which are north of PBNP in j an area where the predominant current is from north to south. Second, no positive ,

results for any of these radionuclides was found in the weekly composited water samples l from the effluent channel. Finally, Ru 103, was not detected in the PBNP cfiluents {

during 1994. Therefore, it is unlikely that the positive results in the environmental - ,

samples are the result of PBNP discharges. ,

5.3 Land Use Census .l l

In accordance with the requirements of Technical Specification 15.7.7.D, a Sisual verification of animals grazing in the vicinity of the Point Beach Nuclear Plant site -

boundary was completed in . August of 1994 to ensure that the milk sampling locations ' l remain as conservative as practicable. No significant change in the use of pasture lands !

was noted. Therefore, the existing milk sampling program continues to be acceptable. ;

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TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS sample Description I.LD H Low Average High Units TLD Environrnental Radiation (*) 53 0.70 1 0.03 0.87 i 0.13 1.29 i 0.03 mR/7 days Air Gross beta 0.01 154 0.000 1 0.002 0.021 i 0.010 0.065 1 0.004 pCi/m' Cs-137 0.01(0.06) 12 -0.0000 0.0009 0.0001t0.0005 0.000910.0011 pCi/m' Cs-134 0.05 12 -0.000910.0010 0.000110.0005 0.0000t0.0009 pC1/m' I-131 0.03(0.07) 154 -0.020 1 0.017 -0.001 1 0.007 0.011 1 0.014 pCi/m' other gamma emitters (*) 0.1(*) 12 -0.001210.0011 -0.000110.0005 0.0005i0.0004 pC1/ m' Milk I-131 0.5 18 -0.0510.16 0.09 1 0.08 0.23 i 0.27 pCi/1 - >

Sr-89(*) 5(*) 18 -0.9 i 0.9 0.0 1 0.5 0.7 i 0.8 pCi/1 Sr-90(*) 1(*) 18 0.8 i 0.4 1.3 i 0.3 1.7 i 0.4 pCi/1 Cs-134 5(15) 18 -1.9 i 2.5 -0.3 1 0.8 1.1 i 1.3 pC1/1 Cs-137 5(18) 18 -0.8 t 2.5 0.8 1 0.9 2.2 1 2.4 pC1/1 Ba-La-140 5(15) 18 -3.2 1 2.8 -0.1 i 1.3 1.4 1 3.4 pC1/1 Other gamma emitters (*) 15t*) 18 -2.5 i 2.7 0.1 1 1.3 1.8 1 3.3 pC1/1 Lake water Gross beta 4 30 1.2 1 0.4 2.7 i 1.0 5.6 i 2.8 pC1/1 I-131 0.5(2) 30 -0.1210.17 0.05 1 0.10 0.25 i 0.27 pC1/1 Mn-54 10(15) 30 -1.8 i 2.9 0.2 i 1.0 3.4 i 4.2 pCi/1 Fe-59 30 30 -7.3 i 6.2 -0.1 1 2.7 4.8 1 6.6 pC1/1 Co-58 10 30 1.5 i 3.0 -0.0 1 1.0 2.2 1 3.1 pCi/1 Co-60 10 30 -2.2 1 2.2 1.1 i 1.6 4.1 1 2.7 pC1/1 Zn-65 30 30 -5.0 1 3.9 -0.5 1 2.1 4.7 2 5.7 -pci/1 Zr-Nb-95 15 30 -2.3 1 5.3 -0.2 i 1.2 3.1 1 10.0 pCi/1 Cs-134 10(15) 30 -2.2 i 3.5 0.6 i 1.1 2.7 i 3.3 pCi/1 Cs-137 10(18) 30 -1.9 1 2.3 0.2 i 0.9 2.2 i 3.2 pCi/1 Ba-La-140 15 30 -9.1 1 11.4 -2.2 i 3.3 3.6 i 4.1 pCi/1 Other gamma emitters (*) 30(*) 30 -3.4 i 3.6 -0.4 1 2.1 7.0 1 24.1 pC1/1 H-3 500(3000) 10 -27 1 72 126 i 73.7 223 i 83 pC1/1-Sr-89(*) S(*) 10 -0.8 i 0.8 -0.0 1 0.5 0.6 0.9 pC1/1 Sr-90(*) 1 (* ) 10 0.3 1 0.3 0.6 1 0.4 1.6 1 0.5 pC1/1 4

Algae Gross beta 0.25 4 2.01-1 0.25 2.84 1 0.71 3.55 1 0.39 pCi/g Co-58 0.25 4 0.00410.015 0.058.i 0.059 0.137 i 0.024 pCi/g Co-60 0.25 4 0.00210.009 0.010 1 0.000 0.020 2 0.012 pC1/g Cs-134 0.25 4 -0.01410.017 0.001 1 0.011 0.012 1 0.012 pCi/g Cs-137 0.25 4 0.01810.011 0.034 1 0.024 0.069 i 0.025 pC1/g t

11

_ _ , _ . . __ . . - - . _ ._ - . . . _ _ . .- . . . _ _ . . -- ~ . - __. .__ _ _ _ _ _ - __

i sample Description I.LD N Low Average High Units j Fish Gross beta (*) 0.5(*) B 2.36 1 0.05 3.29 i 0.47 4.00 1 0.11 pC1/g Mn-54 0.13 8 -0.001t0.006 0.00010.004 0.00410.005 pCi/g Fe-59 0.26 8 -0.03010.020 -0 00410.072 0.02310.072 pCi/g Co-58 0.13 0 -0.00210.007 0.00110.003 0.00310.007 pCi/g Co-60 0.13 8 -0.00610.004 0.00310.005 0.01210.117 pC1/g 2n-65 0.26 8 -0.00910.016 0.00410.000 0.01010.012 pCi/g pC1/g .

Cs-134 0.13 8 -0.004t0.027 -0.00110.002 0.00310.003 Cs-137 0.15 8 0.03410.012 0.05410.014 0.06010.015 pC1/g other gamma emitters (*) 0.5(*) 8 -0.005i0.045 0.00110.005 0.00710.014 pC1/g Well water Gross beta 4 2 1.7 1 1.3 2.6 i 1.3 3.5 A 1.3 pC1/1 I-131 0.5(2) 2 0.04 0.18 0.11 1 0.10 0.18 i 0.18 pC1/1 Mn-54 10(15) 2 -1.0 1 2.3 -0.2 1 1.1 0.6 i 2.5 pC1/1 Fe-59 30 2 -1.7 i 6.6 0.4 1 2.9 2.4 i 6.8 pC1/1 Co-58 10 2 0.5 1 2.9 0.9 i 0.8 1.0 1 2.8 pC1/1 Co-60 10 2 1.1 1 2.6 2.2 1 1.6 3.3 1 2.0 pC1/1 Zn-65 30 2 0.3 1 5.0 1.2 1 1.2 2.0 i 5.4 pC1/1 Zr-Nb-95 15 2 -0.2 5.0 0.3 1 0.6 0.7 1 2.9 pC1/1 Cs-134 10(15) 2 -3.6 i 9.1 -1.6 i 2.8 0.4 i 3.0 pC1/1 Cs-137 10(18) 2 -0.6 i 2.9 -0.1 1 0.8 0.5 i 3.1 pCi/1 Ba-La-140 15 2 -3.0 t 8.3 ~2.6 1 0.6 -2.1 i 1.1 pC1/1 other gamma emitters (*) 30(*) 2 -0.1 i O.1 0.8 i 1.2 1.6 i 3.8 pC1/1 H-3 500 2 -27.3 i 72.6 19.4 i 66.0 66.0 1 82.2 pCi/1 Sr-89(*) 5(*) 2 -0.35 1 0.44 0.06 1 0.57 0.46 i 0.48 pC1/1 Sr-90(*) 1(*) 2 0.10 1 0.16 0.11 1 0.30 0.32 i 0.21 pCi/1 Soil (*) Gross beta 2 8 6.5 I 1.9 18.0 1 7.5 27.8 i 3.0 pCi/g Cs-137 0.15 8 0.009 i 0.014 0.286 i 0.224 0.63 1 0.06 pC1/g Shoreline Gross beta 2 5 3.5 1 1.5 6.0 i 1.6 7.7 i 1.3 pC1/g sediment ( * ) Cs-137 0 15 5- 0.019 i 0.032 0.036 1 0.020 0.064 t 0.026 pC1/g Vegetation Gross beta (*) 0.25(*) 16 4.3 0.2 6.3 1 1.7 10.3 1 0.4 pC1/g Cs-134 0.06 16 -0.00410.012 0.003 0.004 0.008 i 0.013 pC1/g Cs-137 0.08 16 0.01910.017 0.007 1 0.009 0.019 i 0.017 pCi/g I-131 0.06 16 -0.00910.019 0.001 1 0.005 0.010 1 0.024 pCi/g 12

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t 6.0 NONRADIOACrlVE CHEMICAL RELEASES 6.1 Scheduled Chemical Waste Relt agg Scheduled chemical waste releases to the circulating water system from July 1,1994, to December 31,1994, included 4.93E+06 gallons of neutralized wastewater. The wastewater contained 6.32E+02 pounds of suspended solids and 3.85E+05 pounds of dissolved solids.

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

6.2 Miscellaneous Chemical Waste Releases 7

Miscellaneous chemical waste releases from the retention pond (based on effluent analyses) to the circulating water for July 1,1994, to December 31,1994, included 1.93E+07 gallons of clarified wastewater, .The wastewater contained 2.12E+03 pounds of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1,1994, to December 31,1994, included 1.80E+05 . .

pounds of sodium bisulfite and 5.00E+04 pounds of sodium hypochlorite.-

7.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 7-1.

t TABLE 7-1 CIRCULATING WATER SYSTEM OPERATION July 1,1994 to December 31,1994 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling i 489.6 489.6 492.2 503.5 473.0 282.2 Water Discharge IMgal/ day] 2 489.6 489.2 477.7* 256.7* 406.2 282.2 Average Cooling Water 1 56 57 58 49 44 38 ,

Intake Temperature [*Fl 2 56 57 58* 43' 43 38 Average Cooling Water 1 74 76 77 67 63 69 l Discharge Temperature 1"F] 2 76 76 77* 45' 63 69 Average Ambient Lake 53 56 56 47 42 37 Temperature l'Fl

' Unit 2 refueling shutdown from September 24,1994 to October 30,1994

- For days with cooling water discharge flow 8.0 L.EAK TESTING OF RADIOACTIVE SOURCES During this reporting period, all applicable scaled radioactive sources were leak tested in ;

accordance with Technical Specification 15.4.12. Leak test results were all <0.005 Ci. !

i 13 1

9.0 : MISCELLANEOUS REPORTTNG REOUIREMENTS 9.1 Revisions to the PBNP Office Dose Calgilation Manual (ODCM) and Process Control Elogram (PCP)-

The Environmental Manual was revised during this reporting period. Resisions were made to reflect administrative name changes and to indicate the location of a new

i sampling site. The new site E-33, was added for lake water samples because access to~

Lake Michigan via the steep bluff at E-09 was dangerous during the winter months and during times ofinclement weather. .;

9.2 Interlaboratory Comparison Prograan 4

The analytical laboratory contracted to perform the radionnalyses of the PBNP '

environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period.

9.3 Deviations from Specirgd a Environmental Sample Tvoes. Locations. and Freauencies

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, During thisuporting period, a deviation from the sampling frequency specified in Table 15.7.7-1 of the Technical Specifications occurred at sites E-04 and E-09. A mechanical failure of the air sampling pump at E-04 prevented an air particulate and an iodine

. sample from being colixted the week ending September 13,1994. The TLD at E-09 was lost in the field for the 4th quarter of 1994. ,

t 9.4 Sj;mmary of Unachievable Specific.d_ffgironmental I.LDs All LLDs listed in Table 15.7,7-2 of the PBNP Technical Specifications were achieved during this sampling period.

9.5 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during this reporting period.

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l WISCONSIN ELECTRIC SEMIANNUAL MONITORING REPORT JULY 1994 through DECEMBER 1994 POWER COMPANY !

POINT BEACH NUCLEAR PLANT l

UNIT NOS.1 AND 2 l

U.S. Nuclear Regulatory Commission Docket Nos. 50-266 and 50-301 Facility Operating License Nos.

DPR-24 and DPR-27 l

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PREFACE This Semiannual Monitoring Report for the period of July 1,1994, through December 31,1994, is submitted in accordance with Point Beach Nuclear Plant Unit Nos. I and 2 Technical Specification 15.7.8.4 and filed under Docket Nos. 50-266 and 50-301 for Facility Operation License Nos. DPR-24 and DPR 27, respectively.

TABLE OF CONTENTS Eqction Tit]g Eagg 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 5 3.0 Radioactive Solid Waste Shipments 6 4.0 New and Spent Fuel Shipments 6 5.0 Radiological Environmental Monitoring 9 6.0 Nonradioactive Chemical Releases 13 7.0 Circulating Water System Operation 13 8.0 Leak Testing of Radioactive Sources 13 9.0 Miscellaneous Reporting Requirements 14

SEMIANNUAL MONITORING REPORT July 1,1994 to December 31,1994 1.0 RADIOACTIVE LIOUID REl&6SfiS The total radioactive liquid release, excluding tritium for this reporting period, was 6.46E-02 curies. This included 1.78E-03 curies in processed radioactive waste and primary coolant system letdown,5.31E-04 curies in Unit I steam generator blowdown,6.19E-02 curies in Unit 2 steam generator blowdown and 4.08E-04 curies in retention pond emuent.

The total tritium release for this reponing period was 2.13E+02 curies. This included 2.12E+02 curies in processed radioactive waste and primary coolant system letdown,1.72E-02 curies in Unit I steam generator blowdown,1.29E+00 curies in Unit 2 steam generator blowdown and 1.56E-01 curies in retention pond emuent.

1.1 GID!latiDEli'Digt Radio.nuclLddskass_,S.Juulua[I 1.1.1 Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curic released on a monthly basis and presented in Table 1-1. Table 1-1 also contains the comparison between the annual Appendix ! dose limits for liquid emuent and the corresponding highest doses calculated according to the ODCM using the semiannual and annual isotopic composition of the liquid discharge.

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 Semiannual Monitoring Report for January 1,1994, through June 30,1994.

June 6-month Total Total Activity Released [Ci]

Gross Alpha <MDA 2.89E-06 Strontium 1.8E-07 3.32E-05 Average Ililuted Discharge Concentration luCi/ccl Gross Alpha <MDA Strontium 3.2E-15

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Table 1-1 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGE JULY 1,1994 THROUGH DECEMBER 31,1994 J aly A u g ust Se p tens be r Deteber N evese b er D e ce su b e r Total Total A ctivity Released lCil .

Gamm a Sean 1.89E-02 2.e l E-0 2 1.0 4 E -0 2 1.7 0 E -0 3 7.3 9 E-0 3 6.10 E-0 3 6.4 6 E-0 2 Gross Alpha 4.7 0 E-0 8 0.0 0 E + 0 0 0.0 0 E + 0 0 1.2 0 E-0 6 - 7.8 7 E-0 8 ll) 1.3 3 E-0 6 F ritiu m 3.0 6 E + 01 2.9 0 E + 01 6.6 7 E + 01 9.4 7E + 0 0 3.8 7 E + 01 3.8 5 E + 01 2.13 E + 0 2 S tro ntiu m 4.0 0 E-0 7 9.4 9 E -0 7 1.0 4 E-0 5 1.2 0 E-0 6 3.5 4 E-0 7 l11 1.3 3 E -0 5

Teen' Volunie Released l gall Processed Y( aste 6.2 6 E + 0 4 5.57E+04 2.5 0 E + 0 5 9.8 9 E + 0 4 1.04E+05 5.55E+04 6.2 7 E + 0 5 U I Steam Generator Blowdows 3.5 7 E + 0 6 3.5 3 E + 06 3.I I E + 06 3.5 7 E + 0 6 3.4 6 E + 0 6 2.6 8 E + 0 6 1.99E+07 U 2 Steam Generator Blowdown 3.5 5 E +06 3.5 5 E+ 06 2.61 E + 0 6 2.9 4 E + 0 5 4.7 5 E + 06 - 2.6 7 E + 0 6 l74E+07 Retention Pond 2.5 3 E + 0 6 2.9 0 E + 0 6 2.7 7 E + 0 6 2.19 E + 0 6 4.2 t E+ 06 4.7 3 E + 06 1.93E+07 M is c ella n eo u s 0.00E+00 0.0 0 E + 0 0 0.0 0 E + 00 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 S E + 0 0 0.0 0 E + 0 0 rotal 9.7 t E + 0 6 1.0lE+07 8.74E+06 6.15 E + 0 6 1.25E+07 1.0lE+07 5.73E+07 Vetusse e er Dilutlen W ater leel 5.7 5 E + 13 5.7 5 E + 13 5.5 9 E + 13 5.9tE+13 5.38E+13 3.3 t E + 13 3.17E + 14 Average Diluted Discharge Cemeentration luCIIrel G am m a Scan 3.2 9 E -10 3.5 0 E -10 1.8 6 E-10 2.88E-11 ' l .3 7E-10 1.8 4 E Gross Alpha 8.17E-16 0.0 0 E + 0 0 0.0 0 E + 0 0 2.0 3 E-14 1.46E-15 lIl I T ritiu m 5.3 2 E -0 7 5.0 4 E-0 7 1.19 E -0 6 1.6 0 E -0 7 7.19 E-0 7 1.16 E -0 6

' S t ro n tiu m ,

6.9 6 E-15 1.6 5 E-14 1.86E-13 2.0 3 E-14 6.58 E-15 lIl M azim une Discharge Concentrations luCE/cel G ross G am m a 6.5 3 E -10 4.9 9 E-10 3.4 3 E-10 2.9 0 E -10 2.4 0 E-0 7 3.6 2 E-10 T ritiu m 3.8 0 E -0 5 2.5 9 E -0 5 2.6 6 E-0 5 5.10 E-0 6 4.2 2 E-0 5 3.6 8 E-0 5 [

[1] Information unavailable at time of repolt preparation Note: Dissolved noble gasses detected in liquid effluents are included in airborne release totals COMPARISON OF LIQUID EFFLUENT DOSES TO ANNUAL APPENDIX I DOSE LIMITS r

Annual Limit Imreml January-June Highest Total Calculated Dose Imreml January-December Highest Total Calculated Dose Imremi .

6 (wholebody) 1.97E-03 (infant) 3.64E-03 (infant) 20 (any organ) 2.59E-03 (infant thyroid) 3.84E-03 (infant thyroid) 2.

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9 Table 1-2 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGES JULY I,1994 THROUGH DECEMBER 31,1994 July August September October November December Total Isotope (Ci] [Ci] [Ci] [Cil (Ci] [Ci] [Ci]

H-3 3.06E+01 2.90E+01 6.67E+01 9.47E+00 3.87E+01 3.85E+01 2.13E+02 I-13 I 6.73E-04 4.37E-05 6.88E-06 <MDA 4fDA <MDA 7.24E-04 I-132 7.72E-04 2.23E-04 5.67E-04 1.73E-05 <MDA <MDA 1.58E-03 I-133 3.24E-03 3.19E-03 1.54E-03 3.02E-05 1.05E-03 5.57E-04 9.61E-03 I-135 2.64E-04 1.33E-03 <MDA <MDA 4fDA <MDA 1.59E-03 F-18 1.26E-02 1.34E-02 7.87E-03 3.04E-04 5.61E-03 4.96E-03 4.47E-02 MN-56 2.12E-04 GIDA <MDA 4fDA <MDA <MDA 2.12E-04 CO-58 3.19E-06 <MDA 8.56E-06 6.46E-05 1.13E-05 1.42E-05 1.02E-04 CO-60 8.80E-05 1.70E-05 3.19E-05 3.81E-05 1.84E-05 8.72E-05 2.81E-04 Y-93 4fDA 1.33 E-03 <MDA <MDA <MDA <MDA 1.33E-03 TC-99M <MDA <MDA 7.24E-05 <MDA <MDA <MDA 7.24E-05 AG-Il0M 6.01E-04 2.61E-05 1.31E-04 2.57E-04 5.96E-05 7.49E-05 1.15E-03 TE-l31 1.62E-04 3.60E-04 <MDA <MDA <MDA <MDA 5.22E-04 CS-134 41DA <MDA 7.12E-05 3.92E-04 1.77E-04 <MDA 6.40E-04 CS-137 1.72E-04 1.06E-04 1.22E-04 5.93E-04 4.68E-04 <MDA 1.46E-03 BA-140 41DA <MDA 3.29E-06 <MDA <MDA <MDA 3.29E-06 CE-141 <MDA <MDA <MDA <MDA <MDA 4.08E-04 4.08E-04 SR-89 <MDA 4fDA 8.51E-06 <MDA <MDA [1] [1]

SR-90 4.00E-07 9.49E-07 1.89E-06 1.20E-06 3.54E-07 , []l [lJ

[1] Information unavailable at time of report preparation Note: Dissolved noble gasses detected in liquid efIluents are included in airborne release totals 3

l.2 h9 topic Compositiqn of Circulati_nc Water Discharces 1.2.1 Releases During Current Reporting Period The isotopic composition of circulating water discharges during the current reporting period is presented in Table 1 2.

1.2.2 Additions to Presious Semiannual Monitoring Report The following information was not available at the time of report preparation and should be added to Table 1-2 of the Semiannual Monitoring Report for January 1,1994, through June 30,1994.

Nuclide hutg 6-Month Total SR-89 [Ci] <MDA <MDA SR-90 [ Cal 1.8E-07 3.32E-05 1.3 Subsoil Drain System Releases of Tritium 1.3.1 Releases During Current Reporting Period The releases of tritium via the subsoil drain system during the current reporting period is presented in Table 1-3.

TAllLE l 3 SUBSOIL SYSTEM DRAINS - TRITIUM

SUMMARY

July 1,1994 through December 31,1994 Third Ouartst El S-3 S-9 E-10 Total 11-3 [ Ci/cc] <MDA <MDA <MDA <MDA Ave. Flow [gpdj 6.34E+03 5.76E+03 1.36E+04 4.00E+02 Fourth Ouar_tcl l 11-3 [ Ci/cc] <MDA <MDA No Sample <MDA i Ave. Flow [gpdj 2.96E+ 03 6.55E+02 No Flow 1.73 E+04 i E9miannual Tota.lj Total Released [Cil <MDA <MDA <MDA <MDA <MDA Total Flow [ gall S.56E+05 5.90E+05 1.25E+06 1.63 E+06 4.32E+06 l

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1.4 Lggi Application of Sewane Sludce The Wisconsin Department of Natural Resources has approved the land-appication of sewage sludges on various Wisconsin Electric Power Company properties surrounding the Point Beach Nuclear Plant. These sewage sludges, which may contain trace amounts of radionuclides, are applied in accordance with methodologies approved on January 13, 1988, pursuant to 10 CFR 20.302. The amounts discharged in the sewage during this reporting period are presented in Table 1-4.

TABLE l-4 SEWAGE SLUDGE LAND APPLICATIONS July 1,1994 through December 31,1994 Date of A_pplication Gallons Sig Activity Released ICil September 15 13800 PB-02 <MDA October 4 7700 PB-02 <MDA November 30 8200 PB-02 <MDA 2.0 RADIOACTIVE AIRBORNE RELEASES The release paths contributing to radioactive airborne release totals during this reporting period were the auxiliary building vent stack, drumming area vent stack, gas stripper building vent stack, Unit I containment purge stack, Unit 2 containment purge stack, combined air ejector decay duct exhaust and turbine building ventilation eshaust.

There were three gas decay tank releases during this reporting period.

2.1 Radioactive Airborne Release Summary 2.1.1 Release During Current Reporting Period Radioactivity released in airborne effluent for the current reporting period are summarized in Table 2-1. Table 2-1 also contains the comparison of the annual Appendix 1 dose limits for atmospheric eflluents to the highest organ dose and the noble gas doses calculated using ODCM methodology and the isotopic composition of atmospheric releases identified in Table 2-2.

2.1.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of the last report preparation and should be added to Table 2 1 of the Semiannual Monitoring Report for January 1,1994 through June 30,1994.

Total Particulates r Ap_ril Mal June 6-Month Total Strontium lCi] <MDA <MDA <MDA <MDA 5

.- l 2.2 h91onic Airborne Rsisasi 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 Semiannual Monitoring Report ;

The following information was not availab!c at the time of previous report preparation and should be added to Table 2 2 of the Semiannual Monitoring Report, covering the period January 1,1994, through June 30,1994.

Nuclids optil Mu htns 89 nth Total SR-89 lCij <MDA <MDA <MDA <MDA SR-90 [Cil <MDA <MDA <MDA <MDA 2.2.3 Corrections to previous Semiannual Monitoring Report The Table 2.2 April value for Tritium was incorrectly reported as 102E+00 Ci.

The correct value is 1.02E+0! Ci. The reported Tritium total is correct.

3.0 BAD 10ACTiyJi1QLip WASTFJ11[PBf]HS There were no solid wa te shipments for burial or on-site storage during the period from July 1, 1994 to December 31,1994.

4.0 MiliY_AND_SITitHJ3EldilllB' E1HS AND RECEll1$ :

During this reporting period. a total of 29 new fuel assemblics were received from Westinghouse Electric Corporation for Unit 2. The new fuel assemblics received for Unit 2 were used for the Fall 1994 refueling.

There were no spent fuel shipments made from Point Beach Nuc! car Plant during this reporting perkxl 6

9 TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE SL%LNIARY JULY 1,1994 THROUGH DECEhfBER 31,1994 July August September October November December Total Total Noble Gasses lCi] [1] 3.73E-01 3.30E-01 3.12E+00 2.39E+00 1.47E-01 6.03 E-01 6.%E+00 Total Radioiod!nes [Ci] 1.01 E-05 5.21E-10 3.17E-06 7.91E-10 1. I IE-08 2.20E-08 1.33E-05 Total Particulates [Cil S.35E-05 4.01E-05 1.66E-04 1.27E-03 7.47E-05 8.14E-05 1.72E-03 Alpha [Ci] ' 6.08E-05 4.01E-05 1.51E-04 1.12E-04 6.31E-05 8.14E-05 5.08E-04 Strontium [Ci] <hiDA <h1DA <hlDA [2] [2] [2] [2]

All Others [Ci] 2.27E-05 0.00E+00 1.50E-05 1.16E-03 1.16E-05 0.00E+00 1.21E-03 Total Tritium [Ci] 4.19E+00 2.81E+00 3.85E+00 1.63E+01 3.99E+00 3.52E+00 3.47E+01 Slas llourly Are Release Rate {Ci/sec] 1.33 E-06 1.28E-06 2.87E-06 l 2.54E-06 2.54E-06 5.53E-07

[1] Includes noble gas contribution from liquid releases.

[2] Information unavailable at time of report preparation, but values typically do not alter monthly totals.

COhiPARISON OF EFFLUENT DOSES TO APPENDIX 1 LIhilTS Category Annual Dose Limit Jamnry-June Calculated Dose Imreml Januan-December Calculated Dose Imreml Paniculate 30 mrem / organ 6.21E-03 4.48E-02 Noble Gas 40 mrad ( air) 3.77E-04 1.56E-03 Noble Gas 20 mrad (y air) 7.84E-04 3.27E-03 Noble Gas 30 mrem (skin) 5.22E-04 2.18E-03 Noble Gas 10 mrem (uhole body) 9.10E-04 3.84E-03 7

L TABLE 22 RADIOACTIVE AIRBORNE RELEASE

SUMMARY

JULY 1,1994 THROUGH DECEMBER 31,1994 N actl4 e J u ly A ugust Septem ber October N ovem ber D ecem ber T otal i ICII [Cil ICal ICal ICII Ital ICil 11 - 3 4.19 E + 00 2.81 E + 0 0 3.8 5 E + 0 0 1.6 3 E + 0 ! 3.99 E + 00 3.5 2 E + 0 0 3.4 7 E + 0 I l

A R -41 1.3 5 E -01 1.5 5 E -01 1.31E+00 7.9 9 E -01 8.9 5 E -0 2 2.6 5 E -01 2.7 5 E + 0 0 K R-85 7.4 7 E -0 2 6.9 9 E-0 2 5.4 7 E -0 2 <MDA <MDA <MDA I .9 9 E -01 i K R-85M 5.5 7 E -0 3 3.9 8 E-03 7.0 4 E -0 2 6.5 2 E-0 2 1.9 0 E -0 3 1.2 8 E -0 2 1.6 0 E -01 K R-87 1.2 2 E -0 2 8.9 4 E -0 3 1.6 2 E -01 1.4 8 E -01 4.4 6 E -0 3 3.0 8 E -0 2 3.6 6 E -01 K R-8 8 1.3 5 E -0 2 9.9 0 E-03 1.7 4 E -01 1.6 I E -01 4.7 5 E -0 3 3.2 8 E -0 2 3.9 6 E -01 X E -13 3 2.9 8 E -0 2 6.4 5 E -0 3 3.7 3 E -0 2 5.7 8 E -0 2 7.6 3 E -0 3 1.6 6 E -0 2 1.5 6 E -01 X E -13 3 M I .9 8 E -03 1.4 9 E -0 4 5.19 E -0 3 6.0 7 E -0 3 5.0 6 E -0 5 <MDA 1.3 4 E -0 2 X E-13 5 2.7 0 E -0 2 1.7 9 E -0 2 3.2 6 E -01 3.3 0 E -01 9.9 6 E -0 3 6.I 2 E -0 2 7.7 2 E -01 X E -13 5 M 1.7 7 E -0 2 1.4 7 E -0 2 2.4 3 E-01 2.0 0 E -01 6.6 7 E -0 3 4.2 4 E -0 2 5.2 4 E -O i X E-13 8 5.6 2 E -0 2 4.3 t E-0 2 7.3 6 E -01 6.2 3 E -01 2.16 E -0 2 1.4 2 E -01 1.6 2 E + 0 0 I-131 8.51E-07 5.21 E - 10 1.5 3 E -0 6 <MDA I .6 5 E -0 9 4.3 0 E -09 2.3 9 E -0 6 I-132 <MDA <MDA <MDA <MDA 4.2 4 E -09 <MDA 4.2 4 E -09 I-133 2.7 t E-06 <MDA I .6 4 E -0 6 7.9t E-10 5.2 2 E-09 1.7 7 E -0 8 4.3 7 E -0 6 1-135 6.51 E-06 <MDA <MDA <MDA <MDA <MDA 6.5IE-06 F-18 2.2 4 E -0 5 <MDA 1.4 6 E -0 6 <MDA_ <MDA <MDA 2.3 9 E-0 5 C O -5 7 1.4 6 E -0 8 <MDA <MDA <M D A <MDA <MDA 1.4 6 E -0 8 j C O-58 <MDA <MDA 6.3 2 E -0 7 5.3 9 E-07 <MDA <MDA 1.17 E -0 6 C O -60 <MDA <MDA <MDA 1.8tE-06 1.12 E -0 5 <M D A l .3 0 E -0 5 B R-82 1.4 3 E -09 1.9 t E -09 <MDA 1.2 3 E -0 9 6.6 0 E - 10 1.2 3 E -09 6.4 6 E -09 C S-13 4 <MDA <MDA 5.2 S E-06 1.2 8 E -0 4 5.2 7 E-0 8 <MDA l .3 3 E -0 4 C S-13 4 M <MDA <MDA 1.4 4 E -0 9 <MDA <MDA <MDA I .4 4 E-09 C S -13 7 2.69 E 07 <MDA 8.12 E -0 6 7.9 7 E -0 4 1.3 9 E -0 7 <MDA 8.0 6 E -0 4 C S-13 8 <MDA <MDA <MDA 2.3 I E-04 2.18 E -0 7 <MDA 2.3 l E-0 4 A L P II A 6.0 8 E -0 5 4.01 E -0 5 1.5tE-04 1.12 E -04 6.31 E -0 5 8.14 E -0 5 5.0 8 E -0 4 SR 89 <MDA <MDA <MDA II] [1] [1] [1]

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[1] Information unavailable at time of report preparation, but values typically do not alter monthly totals reported in Table 2-1.

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5,0 BADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Introduction The results in this Semianmaal Report are presentcJ in the new format which was initiated with the January - June 1992 Report. Results are reported directly as measured, including negative and zero values. This climinates the distortion of the results and long-term trends which occurs when the LLD is used to censor results that are below the LLD. This reporting convention follows that recommended in Health Physics Society Committee Report IIPSR 1 (1980) released as document EPA $20/180-012.

The REMP results are presented in Table 5.1. The table contains the following information:

Sample: the type of the sample medium

Description:

the type of measurement LLD: the gwderd lower limit of detection N: the number of samples analyzed Low: the lowest measured value i its associated 2s counting error Average: the average value i the standard deviation of N samples liigh: the highest measured value i its associated 2s counting error Units: Ihe units of measurement Additional information also is presented in Table 5.1. Not all of the results in Tabic 5.1 are required by the PBNP radiological effluent technical specifications (RETS). Non-RETS items and values are noted by an asterisk (*). For certain analyses, an LLD which is lower than that required by RETS is used. For these analyses, both LLDs are listed with the RETS LLD given in parentheses. Occasionally, anomalous results are obtained w hich lie well outside of the range of expected values. These results will be investigated and discussed in the narrative portion of this section. Blank values have not been subtracted from the results presented in Tab!: 5.1.

5.2 Discussion Radiological environmental monitoring conducted at the Point Beach Nuclear Plant from July 1,1994 through December 31,1994 consisted of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs.

All TLD results for the reporting period were within the normal range. Site E-12, located on the discharge fiume pier continues to exhibit some of the lowest values u hereas E 32, approximately I mile west of the plant, continues to exhibit the highest.

The higher values at E-32 have been noted since TLDs were first located at this site.

The reason for this result is not known and continues to be tracked. Note that TLD results from sites E-3 and E-31, located about 1200 fwt north of E-32 at about the same distance from the plant, typically are 0.1 - 0.4 mR/ weck lower than E-32 and continue to be so for this reporting period.

The analyses for individual radionuclides reveals that Sr-90 and Cs-137 continue to occur in environmental samples. St-90 continues to persist in milk and water. Cs-137 occurs in sediment, fish, algae, vegetation, and soil These radionuclides routinely occur in environmental samples collected around the world and are attributab!c to the large scale atmospheric weapons tests of the 1960's, less frequent testing in the 70's and 80's, and to the Chernobyl accident.

9

Tritium concentrations continue to be low. Three of the ten H 3 results for lake water were statistically equal to zero and two other results were within the range of results obtained from blanks (-74.6

80.5 to 148

101 pCi/l). Both well water H-3 results are not statistically difTerent from zero. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide.

Measured concentretions of RETS specified radioauclides occur as positive and negative values scattered around zero. Although the positive values are usually smaller ,

than their associated error, small, non-zero values (below the associated 11Ds) whose !

2s error does not overlap zero occur for several radionuclides. j Most of the " positive" results occur for water samples. Of the thirty (30) analyses of lake water for radionuclides other than ones specified in RETS, two (2) results obtained in October are statistically greater than zero. The "other" radionuclide in this instance is Ru-103. Measured concentrations were four standard deviations greater than zero,1.5 i 0.7 pCi/l at E-06 and 1.6 i 0.7 pCi/l at E-33. These sites are 1.5 and 4 miles north of PBNP, respectively. Note that Ru-103 also was detected at low levels (0.00611 0.0030 and 0.001910.0017 pCi/g) in two of seven fish analyzed during October. Other positive lake water results occurred at E-05 in July (Mn-54: 3.4 i 2.4 pCi/l; Co-60: 4.1 i 2.7 pCi/l), at E-05 in August (Co-60: 3.1 i 1.5 pCi/l), and at E-06 in November (Co-

60. 2.7 i 2.2 pCi/l). Finally, positive cobalt results were obtained for algae from E-05 and E-12: Co-58 in August and September (0.13710.024 and 0.068 t 0.020 pCi/g, respectively) and Co-60 in August (0.02010.012 pCi/g) at E-05 and Co-58 (0.024 i 0.013 pCi/g) at E-12.

All of these small, positive values are lower than the LLDs and therefore lower than 25% of the notification values which would require a summation of fractions when more than one radionuclide is identified in an environmental sample. Furthermore, these positive values do not have the results for blank analyses subtracted. For example, the November lake water Co-60 concentration at E-06, 2.7 i 2.2 pCi/1, is in the range of blank values for the last two years, -3.0913.52 to 2.9

2.1 pCi/1. Hence, subtraction of blank values would result in many of the positive values being statistically indistinguishable from zero. However, the positive results for Co-60, Co-58, Mn-54, and Ru-103 from lake water and algae obtained at E-05 during the months of July, August, and September together with the positive Ru-103 results for two of the seven fish samples for the same time period suggest a related source.

While there are not enough statistically significant results to draw any definite conclusions as to the souice, the resuhs do not appear to be related to PBNP cffluent.

First, seven of the ten positive results are at E-05 and E-33 which are north of PBNP in an area where the predominant current is from nonh to south. Second, no positive results for any of these radionuclides was found in the weekly composited water samples from the effluent channel. Finally, Ru-103, was not detected in the PBNP effluents during 1994. Therefore, it is unlikely that the positive results in the emironmental samples are the result of PBNP discharges.

5.3 Land Use Census in accordance with the requirements of Technical Specification 15.7.7.D, a visual verification of animals grazing in the vicinity of the Point Beach Nuclear Plant site boundary was completed in August of 1994 to ensure that the milk sampling locations remain as conservative as practicable. No significant change in the use of pasture lands was noted. Therefore, the existing milk sampling program continues to be acceptable.

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6.0 NONRADIOACTIE CIIEMICAL RELEASES 6.1 Scheduled Chemical Waste Releases ;

Scheduled chemical waste releases to the circulathg water system from July 1,1994, to December 31,1994, included 4.93E+06 gallons of neutralized wastewater. The wastewater contained 6.32E+02 pounds of suspended solids and 3.85E+05 pounds of dissolved solids.

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

6.2 hiisspil gneous i Chemical Waste R.cip.;uigi Miscellaneous chemical waste releases from the retention pond (based on efiluent analyses) to the circulating water for July 1,1994, to December 31,1994, included 1.93E+07 gallons of clarified wastewater. The wastewater contained 2.12E+03 pounds of suspended solids.

Miscellanec,us chemical waste released directly to the circulating water, based on amount of chemicals used from July 1.1994, to December 31,1994, included 1.80E+05 pounds of sodium bisulfite and 5.00E+04 pounds of sodium hypochlorite.

7.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 7-1. l TABLE 7-1 CIRCULATING WATER SYSTEM OPERATION July 1,1994 to December 31,1994 l UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling 1 489.6 489.6 492.2 503.5 473.0 282.2 Water Discharge [Mgal/ day) 2 489.6 489.2 477.7* 256.7* 406.2 282.2 l Average Cooling Water 1 56 57 58 N 44 38 ;

Intake Temperature l'F] 2 56 57 58' 43 38 Average Cooling Water 1 74 76 77 63 69 Discharge Temperaturc [*F1 2 76 76 77* .i

63 69 Average Ambient Lake 53 56 56 47 42 37 Temperature [*F)

' Unit 2 refueling shutdown from September 24,1994 to October 30,1994

- For days with cooling water discharge flow 8.0 LEAK TESTING OF RADIOACTIVE SOURCE.S During this reporting period all applicable scaled radioactive sources were leak tested in accordance with Technical Specification 15.4.12. Leak test results were all <0.005 Ci.

l 13 1 I

9.0 MISCELLANEOUS REPORTING REOUIREMENTS 9.1 Revisions to the PBNP Offigspose Calquiation Manual (ODCM) and Process Control Program tPCP)

The Environmental Manual was revised during this reporting period. Revisions were made to relicct administrative name changes and to indicate the heation of a new sampling site, The new site , E-33, was added for lake water samples because access to Lake Michigan via the steep bluff at E-09 was dangerous during the winter months and during times ofinclement weather.

9.2 Interlaboratory Congarison Procram The analytical laboratory contracted to perform the radioanalyses of the PBNP environmental sampics participated in the EPA Interlaboratory Comparison Program during this reporting period. ;

9.3 Deviations from S.pecified Environrnqntal Samnle Types. Locationund Freauencin During this reporting period, a deviation from the sampling frequency specified in Table 15.7.71 of the Technical Specifications occurred at sites E-04 and E-09. A mechanical failure of the air sampling pump at E-04 prevented an air particulate and an iodine sample from being collected the week ending September 13,1994. The TLD at E-09 was lost in the field for the 4th quarter of 1994 9.4 Sammary of Unachievable SpspjDed Environnjqntal LLDs All LLDs listed in Table 15.7.7-2 of the PBNP Technical Specifications were achieved during this sampling period.

9.5 Snecial Circumstanc_g No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during this reporting period. '

14

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WISCONSIN ELECTRIC SEMIANNUAL MONITORING REPORT JULY 1994 through DECEMBER 1994 POWER COMPANY POINT BEACH NUCLEAR PLANT l UNIT NOS.1 AND 2 l

U.S. Nuclear Regulatory Commission Docket Nos. 50-266 and 50-301 Facility Operating License Nos.

DPR-24 and DPR-27

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This Semiannual Monitoring Report for the period of July 1,1994, through December 31,1994, is submitted in accordance with Point Beach Nuclear Plant Unit Nos. I and 2 Technical Specification 15.7.8.4 and filed under Docket Nos. 50-266 and 50-301 for Facility Operation License Nos. DPR-24 and DPR-27, respectively.

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4 TABLE OF CONTENTS Section Title Eagg 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 5 3.0 Radioactive Solid Waste Shipments 6 4.0 New and Spent Fuel Shipments 6 5.0 Radiological Environmental Monitoring 9 6.0 Nonradioactive Chemical heleases 13 7.0 Circulating Water System Operation 13 8.0 Leak Testing of Radioactive Sources 13 9.0 Miscellaneous Reporting Requirements 14 1

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SEMIANNUAL MONITORING REPORT July 1,1994 to December 31,1994 1.0 R.ADIOACTIVE LIOUID RELEASES The total radioactive liquid release, excluding tritium for this reporting period, was 6.46E-02 curies. This included 1.78E-03 curies in processed radioactive waste and primary coolant system letdown,5.31E-04 curies in Unit I steam generator blowdown,6.19E-02 curies in Unit 2 steam generator blowdown and 4.08E-04 curies in retention pond effluent.

The total tritium release for this reporting period was 2.13E+02 curies. This included 2.12E+02 curies in processed radioactive waste and primary coolant system letdown,1.72E-02 curies in Unit I steam generator blowdown,1.29E+00 curies in Unit 2 steam generator blowdown and 1.56E-01 curies in retention pond efiluent.

1.1 Circulatine Water Radionuclide Release Summan 1.1.1 Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summarized by individual source and total cune released on a monthly basis and presented in Table 1-1. Table 1-1 also contains the comparison between the annual Appendix 1 dose limits for liquid effluent and the corresponding highest doses calculated according to the ODCM using the semiannual and annual isotopic composition of the liquid discharge.

1.1.2 Additions to Previous Semiannual Monitoring Report The following infonnation was not available at the time of the previous report ;

preparation and should be added to Table 1-1 of the Semiannual Monitoring i Report for January 1,1994, through June 30,1994.

i June 6-month Total i Total Activity Released ICil l

Gross Alpha <MDA 2.89E-06 i Strontium 1.8E-07 3.32E-05 )

Ascrage Diluted Discharge l Concentration [uCi/tel j Gross Alpha <MDA i Strontium 3.2E-15 l

1

Table 1-1 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGE JULY 1,1994 THROUGH DECEMBER 31,1994 J u ly A ugust Se pte ns be r Orteber N evens be r D e ce ne b e r Total r etal A ettsity R eleased [Cil G am nia Scan 1.8 9 E -0 2 2.01 E -0 2 1.0 4 E -0 2 1.7 0 E-0 3 7.3 9 E -0 3 6.10 E-0 3 6.4 6 E-0 2 G ro ss Alpha 4.7 0 E -0 8 0.0 0 E + 0 0 0.00 E + 00 1.2 0 E -0 6 7.8 7 E-0 8 [1] 1.3 3 E-0 6 T ritiu m 3.0 6 E + 0 ! 2.9 0 E + 01 6.6 7 E + 01 9.4 7 E + 0 0 3.87E+01 3.8 5 E + 01 2.13 E + 0 2 S tro n tiu m 4.0 0 E-0 7 9.4 9 E-0 7 1.0 4 E-0 5 1.2 0 E-0 6 3.5 4 E-0 7 Ill 1.3 3 E-0 5 Total Volum e Released l gall Processed W aste 6.2 6 E + 0 4 5.57E+04 2.5 0 E + 0 5 9.89E+04 1.04E+05 5.55E+04 6.2 7 E + 0 5 U I Steam Generator Blowdown 3.5 7E + 06 3.5 5 E + 0 6 3.1 1 E + 0 6 3.5 7E + 0 6 3.4 6 E + 0 6 2.6 8 E + 0 6 1.99E+07 U 2 Steam Generator Blowdown 3.5 3 E + 0 6 3.5 5 E + 06 2.6 t E + 06 2.9 4 E + 0 5 4.7 5 E + 0 6 2.6 7 E + 0 6 1.74E+07 R etention Pond 2.5 3 E + 0 6 2.9 0 E + 0 6 2.7 7E + 0 6 2.19 E + 0 6 4.2 t E + 06 4.73E+06 1.93E+07 Nt is c ella n e o u s 0.00E+00 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 0 E + 0 0 0.0 0 E + 0 0 Total 9.71 E + 0 6 1.0 l E + 0 7 8.7 4 E + 0 6 6.15 E + 0 6 1.2 S E + 0 7 1.01 E + 0 7 5.7 3 E + 0 7 Volum e er Dilutlen W ater leel 5.7 5 E + 13 5.7 5 E + 13 5.5 9E + 13 5.91 E + 13 5.38E+13 3.3 t E + 13 3.17E + 14 A verage Diluted Discharge Concentration [uCi/ce]

) Gamma Scan 3.2 9 E-10 3.5 0 E-10 1.8 6 E -10 2.8 8 E-11 1.3 7 E -10 1.8 4 E-10 Gross Alpha 8.17 E - 16 0.0 0 E + 0 0 0.0 0 E + 0 0 2.0 3 E -14 1.4 6 E -15 (1]

r ritiu m 5.3 2 E-0 7 5.0 4 E-0 7 1.19 E-0 6 1.6 0 E -0 7 7.19 E-0 7 1.16 E -0 6 S t-o n tiu m 6.9 6 E -15 1.6 5 E-14 1.86E-13 2.0 3 E-14 6.5 8 E-15 (l]

M asim une Discharge Ceneentrations luCi/ce]

Gross O sam a 6.5 3 E -10 4.9 9 E-10 3.4 3 E-10 2.9 0 E -10 2.4 0 E -0 7 3.6 2 E-10 T ritiu m 3.8 0E-0 5 2.5 9 E -0 5 2.6 6 E-0 5 5.10 E -0 6 4.2 2 E -0 5 3.6 8 E-0 5

[1] Information unavailable at time of report preparation Note: Dissoh ed noble gasses detected in liquid effluents are included in airborne release totals COMPARISON OF LIQUID EFFLUENT DOSES TO ANNUAL APPENDIX I DOSE LIMITS Anmlal Limit Imreml Janualv-June Hichest Total Calculated Dose Imreml Jamtary-December Hichest Total Calculated Dose Imren. 6 (wholebody) 1.97E-03 (infant) 3.64E-03 (infant) 20 (any organ) 2.59E-03 (infant thyroid) 3.84E-03 (infant thyroid) 2 4 b _____.m_. -___-._ _ _ _ . . . _ _ . . . . . . . - . - , . , . . - , _ _ - , . , ,

                                                                                                                        -      e,.-.-w.,         , .-,         ,              m       ,  ,4   ,m,,.-..  . , ,wm. . . .       ,. - . , , _ , , _ , .         _ ,, ,,

z . . Tahic l-2 ISOTOPIC COMPOSITION OF CIRCULATING WA711R DISCHARGES 1 JULY 1,1994 THROUGH DECEMBER 31,1994 July August September October Nosember December Total isotope [Ci] [Cil [Cil [Ci] [Cil [Ci] [Ci] H-3 3.06E+01 2.90E+01 6.67E+01 9.47E+00 3.87E+01 3.85E+01 2.13E+02 I-!31 6.73E-04 4.37E-05 6.88E-06 <MDA 4tDA <MDA 7.24E-04 I-l32 7.72E-04 2.23E-04 5.67E-04 1.73E-05 <MDA <MDA 1.58E-03 1-133 3.24E-03 3.19E-03 1.54E-03 3.02E-05 1.05E-03 5.57E-04 9.61E-03 I-I35 2.64E-04 1.33E-03 41DA <MDA <MDA <MDA 1.59E-03 F-18 1.26E-02 1.34E-02 7.87E-03 3.04E-04 5.61E-03 4.%E-03 4.47E-02 MN-56 2.12E-04 <MDA <MDA <MDA <MDA <MDA 2.12E-04 CO-58 3.19E-06 CIDA 8.56E-06 6.46E-05 1.13E-05 1.42E-05 1.02E-04 CO-60 8.80E-05 1.70E-05 3.19E-05 3.81E-05 1.84E-05 8.72E-05 2.81E-04 Y-93 4fDA 1.33E-03 <MDA 4fDA CIDA 4tDA 1.33E-03 TC-99M 4fDA <MDA 7.24E-05 4fDA CIDA <MDA 7.24E-05 AG-Il0M 6.01E-04 2.61E-05 1.31E-04 2.57E-04 5.%E-05 7.49E-05 1.15E-03 TE-131 1.62E-04 3.60E-04 4fDA 4fDA 41DA <MDA 5.22E-04 CS-134 <MDA 4fDA 7.12E-05 3.92E-04 1.77E-04 <MDA 6.40E-04 CS-137 1.72E-04 1.06E-04 1.22E-04 5.93E-04 4.68E-04 41DA 1.46E-03 BA-140 <MDA <MDA 3.29E-06 <MDA <MDA <MDA 3.29E-06 CE-141 <MDA <MDA -<MDA <MDA <MDA 4.08E-04 4.08E-04 . SR-89 <MDA <MDA 8.51E-06 <MDA <MDA [1] [1] , SR-90 4 00E-07 9.49E-07 1.89E-06 1.20E-06 3.54E-07 [1] [1] , [ll Infonnation unavailable at time of report preparation Note: Dissolved noble gasses detected in liquid effluents are included in airborne release totals 3 F

                                 .      - . . , _ , . , . _                   _ .       ,    . . . . . . - . . . .. . .,._ - _._       ..m.

1.2 hdspic Composition of Circulatine Wster Dischaigts i 1.2.1 Releases During Current Reporting Period f l The isotopic cornposition of circulating water discharges during the current reporting period is presented in Table 1-2. 1.2.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of report preparation and should be added to Table 12 of the Semianmtal Monitoring Report for January 1,1994, through June 30,1994, 1 Nuclidg lung 6-Month Total j SR-89 [Ci] <MDA <MDA l SR-90 [Cij 1.8E4)7 3.32E-05 J 1.3 Sullspjijplain Ssstem RglgasstpErilinig 1.3.1 Releases During Current Reponing Period The releases of tritium via the subsoil drain system during the current reporting period is presented in Table 1-3. TABLE l-3 SUBSOIL SYSTEM DRAINS -TRITIUM

SUMMARY

July 1,1994 through December 31,1994 1Nrd_Q91rl.c1 S,1 S-l $;9 SdQ Istal 11-3 [ Ci/cc] (MDA <MDA <MDA <MDA Ave. Flow [gpd] 6.34E+03 5.76E+03 1.36E+04 4.00E+02 Eggrth Ou:LrisI 11-3 [ Ci/cc] <MDA <MDA No Sample <MDA Atc. Flow [gpdl 2.96E+03 6.55E402 No Flow 1.73E+04 Sil!N4Dimal_ Teal.s Total Released [Ci) <MDA <MDA <MDA <MDA <MDA Total Flow [ gall 8.56E+05 5.90E+05 1.25E+06 1.63E+06 4.32E+06 4

s- l , i 1.4 Land Apolication of Segre Studgg The Wisconsin Depanment of Natural Resources has approved the land-application of sewage sludges on various Wisconsin Electric Power Company properties surrounding the Point Beach Nuclear Plant. These sewage sludges, which may contain trace amounts of radionuclides, are applied in accordance with methodologies approved on January 13,- 1988, pursuant to 10 CFR 20.302. The amounts discharged in the sewage during this reporting period are presented in Table 1-4. TABLE l-4 SEWAGE SLUDGE LAND APPLICATIONS July 1,1994 through December 31,1994 , pate of Application Gallons Sitg Activity Released ICil September 15 13800 PB-02 <MDA October 4 7700 PB-02 <MDA November 30 8200 PB-02 <MDA 2.0 B_ADIOACTIVE AIRBORNE RELEASE.S The release paths contributing to radioactive airborne release totals during this reporting period wcre the auxiliary building vent stack, drumming area vent stack, gas stripper building vent stack, Unit I containment purge stack, Unit 2 containment purge stack, combined air ejector decay duct exhaust and turbine building ventilation exhaust. There were three gas decay tank releases during this reporting period. 2.1 Radioactive Airborne Release Summary 2.1.1 Release During Current Reporting Period Radioactivity released in airborne effluent for the current reporting period are summarized in Table 2-1. Table 21 also contains the comparison of the annual Appendix I dose limits for atmospheric ellluents to the highest organ dose and the noble gas doses calculated using ODCM methodology and the isotopic composition of atmospheric reicases identified in Table 2-2, 2.1.2 Additions to Previous Semiannual Monitoring Report The foll wing information was not available at the time of the last report preparation and should be added to Table 2-1 of the Semiannual Monitoring Report for January 1,1994 through June 30,1994. Total Partigulates April May Jgng 6-Month Total Strontium [Cil <MDA <MDA <MDA <MDA

2.2 Isotopic Airborn_q Relecseg 2.2.1 Releases During Cunent Reporting Period The monthly isotopic airborne releases for the current reporting period are presented in Table 2-2. 2.2.2 Additions to Previous Semiannual Monitoring Report The following information was not available at the time of previous report preparation and should be added to Table 2 2 of the Semiannual Monitoring Report, covering the period January 1,1994, through June 30,1994. l Eqql.isig r Annil May June 6-Month Total SR 89 [Cil <MDA <MDA <MDA <MDA SR-90 [Ci] <MDA <MDA <MDA <MDA 2.2.3 Corrections to previous Semiannual Monitoring Report The Table 2.2 April value for Tritium was incorrectly reported as 1.02E+00 Ci. The correct value is 1.02E+01 Ci. The reported Tritium total is correct. 3.0 RADIOACTIVE SOLID WASTE SHIPMENTS There were no solid waste shipments for burial or on-site storage during the period from July 1, 1994 to December 31,1994. 4.0 NEW AND SPENT FUEL SIIIPMENTS AND RECEIFrTS During this reporting period, a total of 29 new fuct assemblies were received from Westinghouse Electric Corporation for Unit 2. The new fuel assemblies received for Unit 2 were used for the Fall 1994 refueling. There were no spent fuel shipments made from Point Beach Nuclear Plant during this reporting period. 6

5 k TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE SUNL\lARY JULY 1,1994 THROUGH DECEMBER 31,1994 July ~ . August September October November December Total Total Noble Gasses [Cil [IJ 3.73E-01 3.30E-01 3.12E+00 2.39E+00 1.47E-01 6.03E-01 6 96E+00 'I 1.01E-05 5.21E-10 3.17E-06 1.l lE-08 Total Radiciodines [Ci] 7.91E-10 2.20E-08 1.33E-05 Total Particulates [Cil 8.35E-05 4.01E-05 1.66E-04 1.27E-03 7.47E45 8.14E-05 1.72E-03 Alpha [Ci] 6.08E-05 4.01E-05 1.51E-04 1.12E-04 6.31E-05 8.14E-05 5.08E-04 ; Strontium [Ci] <MDA <MDA <MDA [2] [2]- [2] [2] All Others [Ci] - 2.27E-05 0.00E+00 1.50E45 1.16E-03 1.16E-05 0.00E+00 1.21E-03 Total Tritium [Ci] 4.19E+00 2.81E+00 3.85E+00 1.63E+01 3.99E+00 3.52E+00 3.47E+01 .l ' Max Hourly Are Release Rate [Ci/sec) 1.33E-06 1.28E-06 2.87E-06 2.54E-06 2.54E-06 5.53E-07 . [1] Includes noble gas contribution from liquid releases. [2] Information unavailable at time of report preparation, but values typically do not alter monthly totals. COMPARISON OF EFFLUENT DOSES TO APPENDIX 1 LL\flTS , l Category Annual Dose Limit January-June Calculated Dose Imreml Januarv-December Calculated Dose Imreml t i Particulate 30 mrem / organ 6.21E-03 4.48E-02 Noble Gas 40 mrad ( air) 3.77E-04 1.56E-03 . ; Noble Gas 20 mrad (y air) 7.84E-04 3.27E Noble Gas 30 mrem (skin) 5.22E-04 2.18E-03 Noble Gas 10 mrem (nhole body) 9.10E-04 3.84E-03

-]

i i i 7 , s

                                                                                                         ,           .           e      ,              ,     ir s            ,

i TABLE 2 2 RADIOACTIVE AIRBORNE RELEASE

SUMMARY

JULY 1,1994 TIIROUGH DECEMBER 31,1994 N uclid e J u ly A ugust Septem ber O ctober N ovem ber D ecem ber T otal Ic ti IcIl ICII Ic ti Icti lcIl Icli 11 - 3 4.19 E + 0 0 2.81 E + 00 3.8 5 E + 0 0 1.6 3 E + 01 3.9 9 E + 0 0 3.5 2 E +00 3.4 7 E + 0 ! A R -41 1.3 5 E -01 1.5 5 E -01 1.31E+00 7.9 9 E -01 8.9 5 E -0 2 2.6 5 E -01 2.7 5 E + 00 K R-8 5 7.4 7 E -0 2 6.9 9 E-02 5.4 7 E -0 2 <MDA <MDA <MDA 1.9 9 E -01 K R-85 M 5.5 7 E-0 3 3.9 8 E -0 3 7.0 4 E -0 2 6.5 2 E -0 2 1.9 0 E -0 3 1.2 8 E -0 2 1.6 0 E -01 K R-8 7 1.2 2 E -0 2 8.9 4 E -0 3 1.6 2 E -01 1.4 8 E -01 4.4 6 E -0 3 3.0 8 E-0 2 3.6 6 E -01 K R-8 8 l .3 5 E -0 2 9.9 0 E -0 3 1.7 4 E -01 1.6 t E -01 4.7 5 E -0 3 3.2 8 E-0 2 3.9 6 E -01 X E -13 3 2.9 8 E -0 2 6.4 5 E -03 3.7 3 E -0 2 5.7 8 E -0 2 7.6 3 E -0 3 1.6 6 E -0 2 1.5 6 E -01 X E -13 3 M I .9 8 E -0 3 1.4 9 E -0 4 5.19 E -0 3 6.0 7 E -0 3 5.0 6 E -0 5 <MDA 1.3 4 E -0 2 X E -13 5 2.7 0 E -0 2 1.7 9 E -0 2 3.2 6 E -01 3.3 0 E -01 9.9 6 E -0 3 6.12 E -0 2 7.7 2 E -01 X E-13 5 M l .7 7 E -0 2 1.4 7 E -0 2 2.4 3 E -01 2.0 0 E -01 6.6 7 E -0 3 4.2 4 E-0 2 5.2 4 E -01 X E - 13 8 5.6 2 E -0 2 4.3 t E -0 2 7.3 6 E -0 I 6.2 3 E -01 2.16 E -0 2 1.4 2 E -01 1.62E+00 1-131 8.51 E-07 5.21 E - 10 1.5 3 E -0 6 <MDA 1.6 5 E -0 9 4.3 0 E -0 9 2.3 9 E -0 6 l-132 <MDA <MDA <MDA <MDA 4.2 4 E -09 <MDA 4.2 4 E -0 9 I-133 2.7 t E-06 <MDA 1.6 4 E -0 6 7.9 t E -10 5.2 2 E -09 1.7 7 E -0 8 4.3 7 E -0 6 1-135 6.5!E-06 <MDA <MDA <MDA <MDA <MDA 6.5 I E -06 F-18 2.2 4 E -0 5 <MDA 1.4 6 E -0 6 <MDA <MDA <MDA 2.3 9 E -0 5 C O-5 7 1.4 6 E -0 8 <MDA <MDA <MDA <MDA <MDA 1.4 6 E -0 8 C0-58 <MDA <MDA 6.3 2 E -07 5.3 9 E -0 7 <MDA <MDA 1.17 E -0 6 CO-60 <MDA <MDA <MDA 1.81 E -0 6 1.12 E -0 5 <MDA 1.3 0 E -0 5 B R-8 2 1.4 3 E -0 9 I .9 I E -0 9 <MDA 1.2 3 E -79 6.6 0 E - 10 1.2 3 E -0 9 6.4 6 E -0 9 C S-13 4 <MDA <MDA 5.2 5 E -06 1.2 8 E -0 4 5.2 7 E -0 8 <MDA 1.3 3 E -04 C S-13 4 M <MDA <MDA 1.4 4 E -0 9 <MDA <MDA <MDA l .4 4 E -0 9 C S-13 7 2.6 9 E -0 7 <MDA 8.12 E -0 6 7.9 7 E -0 4 1.3 9 E -0 7 <MDA 8.0 6 E -0 4 C S -13 8 <MDA <MDA <MDA 2.31 E -0 4 2.18 E -0 7 <MDA 2.3 t E -0 4 A L P il A 6.0 8 E -0 5 4.0tE-05 1.51 E -0 4 1.12 E -0 4 6.31 E -0 5 8.14 E -0 5 5.0 8 E -0 4 S R -8 9 <MDA <MDA <MDA [11 [Il [1] [Il S R-90 <MDA <MDA <MDA [1] [Il [11 lIl [1] Information unavailable at time of report preparation, but values typically do not alter monthly totals repolted in Table 2-1. 8 ? - t

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Introduction The results in this Semiannual Report are presented in the new format which was initiated with the Jamiary - June 1992 Report. Results are reported directly as measured, including negative and zero values. This eliminates the distortion of the results and long-term trends which occurs when the LLD is used to censor results that are below the LLD. This reporting convention follows that recommended in Health Physics Society Committee Report HPSR-1 (1980) released as document EPA 520/1-80-012. The REMP results are presented in Table 5.1. The table contains the following information: Samp!c: the type of the sample medium

Description:

the type of measurement LLD: the a oriorilower limit of detection N: the number of samples analyzed Low: the lowest measured value

its associated 2s counting error Average: the average value
the standard deviation of N samples High: the highest measured value
its associated 2s counting error Units: the units of measurement Additional information also is presented in Table 5.1. Not all of the results in Table 5.1 are required by the PBNP radiological effluent technical specifications (RETS). Non-RETS items and values are noted by an asterisk (*). For certain analyses, an LLD which is lower than that required by RETS is used. For these analyses, both LLDs are listed whh the RETS LLD given in parentheses. Occasionally, anomalous results are obtained which lie well outside of the range of expected values. These results will be investigated and discussed in the narrative portion of this section. Blank values have not been subtracted from the results presented in Table 5.1.

5.2 Discussion , 1 Radiological environmental monitoring conducted at the Point Beach Nuclear Plant -) from July 1,1994 through December 31,1994 consisted of air filters, milk, lake water, ! well water, soil, fish, shoreline sediments, algae, vegetation, and TLDs. All TLD results for the reporting period were within the normal range. Site E-12, I located on the discharge flume pier continues to exhibit some of the lowest values whereas E-32, approximately 1 mile west of the plant, continues to exhibit the highest. The higher values at E-32 have been noted since TLDs were first located at this site. The reason for this result is not known and continues to be tracked. Note that TLD results from sites E-3 and E-31, located about 1200 feet north of E-32 at about the same

                                                                                                             -l distance from the plant, typically are 0.1 - 0.4 mR/ week lower than E-32 and continue to    ;

be so for this reporting period. ! The analyses for individual radionuclides reveals that Sr-90 and Cs-137 continue to occur in environmental samples. Sr-90 continues to persist in milk and water. Cs-137 occurs in sediment, fish, algae, vegetation, and soil. These radionuclides routinely occur in emironmental samples collected around the world and are attributable to the large scale atmospheric weapons tests of the 1960's, less frequeni testing in the 70's and 80's, and to the Chernobyl accident. 9

t Tritium concentrations continue to be low. Three of the ten H-3 results for lake water were statistically equal to zero and two other results were within the range of results obtained from blanks (-74.6

80.5 to 148
101 pCi/l). Both well water H-3 results are not statistically different from zero. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide.

Measured concentrations of RETS specified radionuclides occur at positive and negative values scattered around zero. Although the positive VAics are usually smaller than their associated error, small, non-zero values (below the associated LLDs) whose

      *2s error does not overlap zero occur for several racitonuclides.

Most of the " positive" results occur for water samples. Of the thirty (30) analyses of lake water for radionuclides other than ones specified in RETS, two (2) results obtained in October are statistically greater than zero. The "other" radionuclide in this instance is Ru-103. Measured concentrations were four standard deviations greater than zero,1.5 10.7 pCi/l at E-06 and 1.6 i 0.7 pCi/l at E-33. These sites are 1.5 and 4 miles north of PBNP, respectively. Note that Ru-103 also was detected at low levels (0.0061 i 0.0030 and 0.0019 i 0.0017 pCi/g) in two of seven fish analyzed during October. Other ! positive lake water results occurred at E-05 in July (Mn-54: 3.412.4 pCi/l; Co-60; 4.1 i 2.7 pCi/l), at E-05 in August (Co-60; 3.1 i 1.5 pCi/l), and at E-06 in November (Co-60: 2.7 i 2.2 pCi/l). Finally, positive cobalt results were obtained for algae from E-05 and E 12: Co-58 in August and September (0.137 i 0.024 and 0.068 i 0.020 pCi/g, respectively) and Co-60 in August (0.020 i 0.012 pCi/g) at E-05 and Co-58 (0.024 i O.013 pCi/g) at E-12. All of these small, positive values are lower than the LLDs and therefore lower than 25% of the notification values which would require a summation of fractions u hen more than one radionuclide is identified in an environmental sample. Furthermore, these positive values do not have the results for blank analyses subtracted. For example, the November lake water Co-60 concentration at E-06,2.712.2 pCi/1, is in the range of blank values for the last two years, -3.09 3.52 to 2.9

2.1 pCi/1. Hence, subtraction of blank values would result in many of the positive values being statistically indistinguishable from zero. However, the positive results for Co-60, Co-58, Mn-54, and Ru-103 from lake water and algae obtained at E-05 during the months of July, August, and September together with the positive Ru-103 results for two of the seven fish l samples for the same time period suggest a related source.

While there are not enough statistically significant results to draw any definite conclusions as to the source, the results do not appear to be related to PBNP effluent. First, seven of the ten positive results are at E-05 and E-33 which are north of PBNP in an area where the predominant current is from north to south. Second, no positive results for any of these radionuclides was found in the weekly composited water samples from the effluent channel. Finally, Ru-103, was not detected in the PBNP cffluents during 1994. Therefore, it is unlikely that the positive results in the environmental samples are the result of PBNP discharges. 5.3 Land Use Census in accordance with the requirements of Technical Specification 15.7.7.D, a visual verification of animals grazing in the vicinity of the Point Beach Nuclear Plant site boundary was completed in August of 1994 to ensure that the milk sampling locations remain as conservative as practicable. No significant change in the use of pasture lands was noted. Therefore, the existing milk sampling program continues to be acceptable. 10

i TABLE 5.1 i RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS i Sanple Description LLD N Low Average High Units TLD Environmental Radiation (*) 53 0.70 1 0.03 0.87 i 0.13 1.29 i 0.03 mR/7 days ? Air Gross beta 0.01 154 0.008 i 0.002 0.021 1 0.010 0.065 1 0.004 pC1/ m' Cs-137 0.01(0.06) 12 -0.000810.0009 0.000110.0005 0.000810.0011 pC1/ m' Cs-134 0.05 12 -0.0009io.0010 0.000110.0005 0.0008t0.0009 pCi/m' I-131 0.03(0.07) 154 -0.020 i 0.017 -0.001 1 0.007 0.011 1 0.014 pCi/m' Other gamma emitters (*) 0.1(*) 12 -0.001210.0011 -0.000110.0005 0.000510.0004 pCi/m' Milk I-131 0.5 18 -0.05io.16 0.09 1 0.08 0.23 1 0.27 pC1/1 Sr-89(*) 5(*) 18 -0.9 1 0.9 0.0 1 0.5 0.7 i 0.8 pC1/1 SI-90(*) 1(*) 18 0.8 i 0.4 1.3 1 0.3 1.7 0.4 pC1/1 Cs-134 5(15) 18 -1.9 1 2.5 -0.3 1 0.8 1.1 i 1.3 pCi/1 Cs- 137 5(18) 18 -0.8 1 2.5 0.8 i 0.9 2.2 2.4 pC1/1 Ba-La 140 5(15) 18 -3.2 i 2.8 -0.1 1 1.3 1.4 1 3.4 pCi/1 Other gaiM. itters(*) 15(*) 18 -2.5 1 2.7 0.1 1.3 1.8 i 3.3 pC1/1 Lake water Gross bsca 4 30 1.2 1 0.4 2.7 i 1.0 5.6 1 2.8 pCi/1 I-131 0.5(2) 30 ~-0.12ic.17 0.05 i 0.10 0.25 i 0.27 pC1/1 Mn-54 10(15) 30 -1.0 i 2.9 0.2 i 1.0 3.4 i 4.2 pCi/1 Fe-59 30 30 -7.3 1 6.2 -0.1 1 2.7 4.0 i 6.6 pCi/1 Co-58 10 30 1.5 i 3.0 -0.0 i 1.0 2.2 i 3.1 pC1/1 Co-60 10 30 -2.2 1 2.2 1.1 1 1.6 4.1 1 2.7 pCi/1 Zn-65 30 30 -5.0 1 3.9 -0.5 t 2.1 4.7 i 5.7 pC1/1 Zr-Nb-95 15 30 -2.3 t 5.3 -0.2 1 1.2 3.1 1 10.0. pC1/1 Cs-134 10(15) 30 -2.2 i 3.5 0.6 1.1 2.7 1 3.3 pC1/1 Cs-137 10(10) 30 -1.9 i 2.3 0.2 i 0.9 2.2 1 3.2 pCi/1 Ba-La-140 15 30 -9.1 i 11.4 -2.2 1 3.3 3.6 i 4.1 pC1/1 Other garrma emitters (* ) 30(*) 30 -3.4 1 3.6 -0.4 1 2.1 7.0 1 24.1 pCi/1 H-3 500(3000) 10 -27 i 72 126 1 73.7 223 i 83 .pC1/1 Sr-89(*) 5(*) 10 -0.8 1 0.8 -0.0 1 0.5 0.6 1 0.9 pCi/1 Sr-90(*) 1(*) 10 0.3 1 0.3 0.6 1 0.4 1.6 1 0.5 pCi/1 Algae Gross beta 0.25 4 2.01 1 0.25 2.84 1 0.71 3.55 1 0.39 pCi/g Co-58 0.25 4 0.00410.015 0.059 1 0.059 0.137 i 0.024 pCi/g Co-60 0.25 4 0.00210.009 0.010 1 0.000 0.020 1 0.012 pCi/g Cs-134 0.25 4 -0.01410.011 0.001 i 0.011 0.012 i 0.012 pCi/g i Cs-137 0.25 4 0.01810.011 0.034 i 0.024 0.069 i 0.025 pC1/g d 11

sample Description I.ID N Low Average Eigh t? nits Fish Gross beta (*) 0.5(*) 8 2.36 1 0.05 3.29 ! 0.47 4.00 1 0.11 pC1/g Mn-54 0.13 0 -0.00110.006 0.000t0.004 0.00410.005 pCi/g Fe-5 9 0.26 8 -0.03010.020 -0.00410.072 0.023t0.072 pCi/q co-58 0.13 8 -0.002 0.007 0.00110.003 0.00310.007 pci/g Co-60 0.13 8 -0.006t0.004 0.00310.005 0.01210.117 pCi/g Zn-65 0.26 8 -0.00810.016 0.004t0.008 0.01010.012 pCi/g Cs-134 0.13 8 -0.00410.027 -0.00110.002 0.00310.003 pC1/g Cs-137 0.15 8 0.034t0.012 0.054t0.014 0.06010.015 pC1/g other gamma emitters (* ) 0.5(*) 8 -0.00510.045 0.00110.005 0.00710.014 pC1/g Well water Gross beta 4 2 1.7 i 1.3 2.6 i 1.3 3.5 t 1.3 pC1/1 I-131 0.5(2) 2 0.04 i O.18 0.11 1 0.10 0.18 i 0.18 pC1/1 ; Mn-54 10(15) 2 -1.0 i 2.3 -0.2 i 1.1 0.6 i 2.5 pCi/1 i Fe-59 30 2 -1.7 i 6.6 0.4 1 2.9 2.4 i 6.8 pCi/1 Co-58 10 2 0.5 1 2.9 0.8 i 0.8 1.0 1 2.8 pC1/1 - Co-60 10 2 1.1 2.6 2.2 i 1.6 3.3 i 2.0 pCi/1 l Zn-65 30 2 0.3 i 5.0 1.2 t 1.2 2.0 5.4 pC1/1 Zr-Nb-95 15 2 -0.2 i 5.0 0.3 1 0.6 0.7 1 2.9 pC1/1 Cs-134 10(15) 2 -3.6 i 9.1 -1.6 i 2.8 0.4 t 3.0 pC1/1 Cs-137 10(18) 2 -0.6 i 2.9 -0.1 t 0.8 0.5 i 3.1 pC1/1 Ba-La-140 15 2 -3.0 i 8.3 -2.6 0.6 -2.1 1 1.1 pCi/1 Other gamma emitters (*) 30(*) 2 -0.1 1 0.1 0.8 1 1.2 1.6 i 3.8 oC1/1 H-3 500 2 -27.3 i 72.6 19.4 i 66.0 66.0 1 82.2 pC1/1 Sr-89(*) 5(*) 2 -0.35 i 0.44 0.06 i 0.57 0.46 1 0.48 pC1/1 Sr-90(*) 1(*) 2 0.10 1 0.16 0.11 1 0.30 0.32 1 0.21 pCi/1 Soil (*) Gross beta 2 8 6.5 t 1.9 18.0 1 7.5 27.8 i 3.0 pCi/g Cs-137 0.15 8 0.009 0.014 0.286 i 0.224 0.63 1 0.06 pC1/g Shorelir.e Gross beta 2 5 3.5.1 1.5 6.0 t 1.6 7.7 1 1.3 pC1/g sediment (*) Cs-137 0.15 5- 0.019 i 0.032 0.036 1 0.020 0.064 i 0.026 pCi/g Vegetation Gross beta (*) 0.25t*) 16 4.3 0.2 6.3 i 1.7 10.3 1 0.4 pCi/g Cs-134 0.06 16 -0.004to.012 0.003 i 0.004 0.000 i .013 pC1/g Cs-137 0.08 16 0.019to.017 0.007 i 0.009 0.019 i 0.017 pCi/g I-131 0.06 16 -0.00910.019 0.001 i 0.005 0.010 1 0.024 pCi/g i l 12 _ _ _ _ . _ _ _ _ _ _ _ _ _ ______________n___._____u __. _ _ _ - _ _ _ - _ _

a e i 6.0 NONRADIOACTIVE CliEMICAL RELEASES 6.1 Scheduled Chemical Waste Releases

                            . Scheduled chemical waste releases to the circulating water system from July 1.1994, to December 31,1994, included 4.93E+06 gallons of neutralized wastewater. The wastewater contained 6.32E+02 pounds of suspended solids and 3.85E+05 pounds of dissolved solids.

Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralizing tanks. 6.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases from the retention pond (based on efl1uent analyses) to the circulating water for July 1,1994, to December 31,1994, included 1.93E+07 gallons of clarified wastewater. The wastewater contained 2.12E+03 pounds of suspended solids. Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1,1994, to December 31,1994, included 1.80E+05 pounds of sodium bisulfite and 5.00E+04 pounds of sodium hypochlorite. 7.0 CIRCULATING WATER SYSTEM OPEPATION , The circulating water system operation during this reporting period for periods of plant operation is described in Table 7-1. TABLE 7-1 CIRCULATING WATER SYSTEM OPERATION July 1,1994 to December 31,1994 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling 1 489.6 489.6 492.2 503.5 473.0 282.2 Water Discharge [Mgal/ day 1 2 489.6 489.2 477.7* 256.7* 406.2 282.2 Average Cooling Water 1 56 57 58 49 44 38 l Intake Temperature [*F] 2 56 57 58* 43* 43 38 Average Cooling Water 1 74 76 77 67 63 69 Discharge Temperature l'F1 2 76 76 77* 45' 63 69 Average Ambient Lake 53 56 56 47 42 37 Temperature l'Fl

Unit 2 refueling shutdown from September 24,1994 to October 30,1994

         **For days with cooling water discharge flow 8.0       LEAK TESTING OF RADIOACTIVE SOURCES During this reporting period, all applicable scaled radioactive sources were leak tested in accordance with Technical Specification 15.4.12. Leak test results were all <0.005 Ci.

13

l l

                                                                                                                                    *    \

9.0 MISCELLANEOUS REPORTING REOUIREMENTS 9.1 Resisions to the PBNP Office Dose Calculation Manual (ODCM) and Process Control Procram fPCP) I The Environmental Manual was resised during this reporting period. Resisions were made to reflect administrative name changes and to indicate the location of a new sampling site. The new site , E-33, was added for lake water samples because access to Lake Michigan via the steep blufrat E-09 was dangerous during the winter months and dming times ofinclement weather. 9,2 Interlaboratory Comparison Program The analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period. 9.3 Desiations from Specified Emironmental Sample Tvoes. Locations, and Freauencies During this reporting period, a desiation from the sampling frequency specified in Table 15.7.7-1 of the Technical Specifications occurred at sites E-04 and E-09. A mechanical failure of the air sampling pump at E-04 prevented an air particulate and an iodine sample from being collected the week ending September 13,1994. The TLD at E49 was lost in the field for the 4th quarter of 1994. 9.4 Stimmary of Unachievable Specified Emironmental LLDs All LLDs listed in Table 15.7.7-2 of the PBNP Technical Specifications were achieved during this sampling period. 9.5 Special Ciretmistances No special circumstances report regarding operation of the :xplosive gas monitor for the waste gas holdup system was needed during this reporting period. 14 _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}

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