ML20067C803

Semiannual Monitoring Rept Jul-Dec 1993 for Point Beach Nuclear Plant Units 1 & 2

ML20067C803
Person / Time
Site:	Point Beach
Issue date:	12/31/1993
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-94-015, CON-NRC-94-15 VPNPD-94-022, VPNPD-94-22, NUDOCS 9403040205
Download: ML20067C803 (18)

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Electnc POWER COMPANY 234 w ucrmnfo so,2cao NwoAee w 53201 204o W4)225 2345 VPNPD-94-022 NRC-94-015 February 22, 1994 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station F1-137 Washington, DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 SEMIANNUAL MONITORING REPQRT POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is the Semiannual Monitoring Report for Point Beach Nuclear Plant, Units 1 and 2, for the period July 1, 1993 through December 31, 1993. This report is submitted in accordance with Technical Specification 15.7.8.4.A and contains information regarding plant releases, solid waste shipments, new and spent fuel shipments, environmental monitoring, circulating water system operations, leak testing of sources, and other miscellaneous reportable items from this reporting period. Three copies of this report are provided for your convenience.

Sincerely,

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Bob Link Vice President Nuclear Power DAW /jg cc: NRC Regional Administrator, Region III NRC Resident Inspector l

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WISCONSIN ELECTRIC SEMIANNUAL MONITORING REPORT JULY 1993 through DECEMBER 1993 POWER COMPANY POINT BE ACH NUCLE AR PL ANT 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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PREFACE This Semiannual Monitorino Report for the period of July 1,1993, through December 31,1993, is submitted in accordance with Point Beach Nuclear Plant Unit Nos.1 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 SEti9H Ill!n Plan 1.0 Radioactive Liquid Releases 1 2.0 Radioactive Airborne Releases 5 3.0 Radioactive Solid Waste Shipments 8 4.0 New and Spent Fuel Shipments 9 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 14 9.0 Miscellaneous Reporting Requirements 14

SEMIANNU/J MONITORING REPORT July 1, 1993 te December 31, 1993 1.0 PADIQACTIVE LIOUID RELEASES The total radioactive liquid release, excluding tritium for this reporting period, was 9.20E-02 curies. This included 6.77E-3 curies in processed radioactive waste and primary coolant system letdown, 1.13E-04 curies in

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Unit 1 steam generator blowdown, 8.48E-02 curies in Unit 2 steam generator blowdown and 2.47E-04 curies in retention pond effluent.

The total tritium release for this reporting period was 2.55E+02 curies.

This included 2.53E+02 curies in processed radioactive waste and primary coolant system letdown, 4.71E-02 curies in Unit 1 steam generator blowdown, 1.76E+00 curies in Unit 2 steam generator blowdown and 8.10E-02 curies in retention pond effluent.

1.1 C_irculating Water Radionuclide Release Summary 1.1.1 Releases During Current Reporting Period Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curte released on a monthly basis and presented in Table 1-1. Table 1-1 also contains the comparison between the annual Appendix I 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 information was not available at the time of the previous report preparation and should be added to Table 1 of the Semiannual Monitoring Report for January 1, 1993, through June 30, 1993.

6-MONTH

^

LBX sHil! TOTAL

- Total Activity Released (Ci)

Gross Alpha 6.4E-08 <MDA 4.8E-06

_ Strontium 4.3E-06 1.6E-05 2.8E-05 Average Diluted Discharge Concentration (pCi/cc)

Gross Alpha 1.1E-15 <MDA Strontium 7.5E-14 2.8E-13 P

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TABLE 1-1 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGE JULY 1, 1993 THROUGH DECEMBER 31, 1993 JUL AUG SE2 OCT NOV DEC TOTAL Total Activity Released (Ci)

Gamma Scan 1.81E-02 1.76E-02 2.11E-02 7.87E-03 1.37E-02 1.36E-02 9.20E-02 Gross Alpha 1.7 E-07 6.6 E-08 2.0 E-07 2.0 E-07 (1) (1) (1)

Tritium 3.64E+01 6.25E+01 5.66E+01 2.58E+01 2.63E+01 4.74E+01 2.55E+02 Strontium 1.1 E-05 4.0 E-06 6.8 E-05 2.8 E-06 (1) (1) (1)

Total Volumes Released (Gal)

Processed Waste 5.54E+04 8.69E+04 1.05E+05 1.76E+05 9.44E+04 5.72E+04 5.75E+05 (U1) Steam Generator Blowdown 3.53E+06 3.56E+06 3.37E+06 3.52E+06 3.18E+06 3.54E+06 2.07E+07 (U2) Steam Generator Blowdown 3.56E+06 3.56E+06 2.88E+06 3.97E+05 4.17E+06 3.59E+06 1.81E+07 Retention Pond 2.92E+06 2.90E+06 2.82E+06 2.51E+06 3.00E+06 2.71E+06 1.69E+07 Total 1.01E+07 1.01E+07 9.18E+06 6.60E+06 1.04E+07 9.90E+06 5.63E+07 Volume of Dilution Water (Gal) 1.51E+10 1.52E+10 1.47E+10 1.56E+10 1.43E+10 1.34E+10 8.83E+10 Average Diluted Discharge Concentration (pCi/cc)

Gross Gamma 3.20E-10 3.06E-10 3.79E-10 1.33E-10 2.52E-10 2.68E-10 Gross Alpha 3.0 E-15 1.1 E-15 3.4 E-15 3.4 E-15 (1) (1)

Tritium 6.39E-07 1.09E-06 1.01E-06 4.37E-07 4.85E-07 9.33E-07 Strontium 2.0 E-13 6.9 E-14 1.0 E-12 4.8 E-14 (1) (1)

Maximum Discharge Concentration During Release Period (pCi/cc)

Gross Gamma 4.60E-09 1.50E-09 2.89E-09 1.68E-09 4.47E-10 4.98E-10 Tritium 4.39E-05 4.27E-05 3.16E-05 2.60E-05 2.09E-05 4.16E-05 Comparison of liquid effluent January-June January-December doses to annual Appendix I Highest Total Highest Total ,

dose limits Annual Limit Calculated Dose Calculated Dose (mrem) (mrem) (mrem) 6 (whole body) 7.61E-03 (adult) 1.74E-02 (adult) 20 (any organ) 1.01E-02 (teen liver) 2.30E-02 (teen liver)

(1) Information unavailable at time of report preparation.

Note: Dissolved noble gases detected in liquid effluents are included in airborne release totals 2

a o rm n r, m m m rm TABLE 1-2 ISOTOPIC COMPOSITION OF CIRCULATING WATER DISCHARGES JULY 1, 1993 THROUGH DECEMBER 31, 1993 EUCLIDES JUL AUG SEP OCT NOV DEC TOTAL RELEASED (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies)

Tritium 3.64E+01 6.25E+01 5.66E+01 2.58E+01 2.63E+01 4.74E+01 2.55E+02 I-131 8.71E-05 9.99E-05 7.90E-04 2.27E-04 <1CA 1.84E-04 1.38E-03 I-132 8.35E-04 8.66E-04 1.39E-03 (MDA <MDA <MDA 3.09E-03 I-133 3.54E-03 3.36E-03 3.17E-03 <MDA 1.54E-03 2.81E-03 1.44E-02 I-134 6.63E-05 2.41E-04 1.98E-04 <MDA <MDA <MDA 5.05E-04 I-135 <MDA 1.11E-03 1.74E-03 <MDA (MDA <MDA 2.85E-03 ,

l F-18 8.55E-03 7.57E-03 5.75E-03 <MDA 9.38E-03 1.04E-02 4.17E-02 l Ea-24 <MDA 1.20E-05 <MDA <MDA <MDA <MDA 1.20E-05 MN-56 1.60E-04 <MDA <MDA <MDA <MDA <MDA 1.60E-04 Co-58 2.48E-05 <MDA 8.38E-06 4.53E-05 3.72E-05 2.62E-05 1.42E-04 i Co-60 3.15E-04 2.84E-05 4.73E-05 1.21E-04 6.22E-05 2.73E-05 6.01E-04 Eb-97 1.99E-05 <MDA <MDA 1.44E-05 <MDA <MDA 3.43E-05 Zr-97 8.77E-05 <MDA 1.30E-05 1.32E-05 5.92E-06 <MDA 1.20E-04 Tc-99m <MDA <MDA <MDA <MDA 1.21E-04 <MDA 1.21E-04 Ru-103 <MDA <MDA (MDA 3.47E-06 <MDA <MDA 3.47E-06 Ag-110m 2.52E-03 4.49E-04 5.85E-04 7.33E-04 3.05E-04 1.49E-04 4.74E-03 Sb-125 <MDA <MDA 1.27E-05 6.93E-06 8.73E-06 9.54E-06 3.79E-05 Cs-134 8.71E-04 1.14E-03 3.68E-03 3.27E-03 1.04E-03 (MDA 1.00E-02 Cs-137 1.11E-03 2.00E-03 3.37E-03 3.44E-03 1.18E-03 1.33E-05 1.11E-02 Ba-139 4.52E-05 7.20E-04 <MDA <MDA <MDA <MDA 7.65E-04 Sr-89 <MDA 3.1 E-06 <MDA 2.1 E-06 (1) (1) (1)

Sr-90 1.5 E-06 8.6 E-07 6.8 E-05 7.3 E-07 (1) (1) (1)

(1) Information unavailable at time of report preparation.

Note: Dissolved noble gases detected in liquid effluents are included in airborne release totals.

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I 1.2 13otoolc Composition of Circulplina Water DischarG2a 1.2.1 Releases During Current Reporting Period The irotopic 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 3 of the Semiannual Monitoring Report for January 1, 1993, through June 30, 1993.

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6-MONTH digi TOTAL _ W 1%X Sr-89 (Ci) 2.2E 06 <MDA 6.5E-06 Sr 90 (Ci) 2.1E-06 1.6E-05 2.2E-05 1.3 Subsoil Drain System Releases of Tritium 1.3.1 Releases During Current Reporting Period WE The releases of tritium via the subsoil drain system during the current reporting period is presented in l m

Table 1-3.

TABLE 1-3 SUBSOIL SYSTEM DRAINS - TRITIUM

SUMMARY

July 1, 1993 through December 31, 1993

, Third Ouarter E,1 M M S-10 Totala H3 (pCi/cc) <MDA <MDA <MDA <MDA Ave. Flow (gpd) 4.82E+03 2.74E+03 7.08E+01 1.97E+04 Fourth Ouarter H-3 (pCi/cc) <MDA <MDA No Sample <MDA Ave. Flow (gpd) 2.39E+03 1.25E+03 No Flow 1.45E+04 gemiannual Totals Total Released (Ci) <MDA <MDA <MDA <MDA <MDA Total Flow (gale) 6.63E+05 3.67E+05 6.51E+03 3.14E+06 4.18E+06 I

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1.4 Land Anolication of Sewaae Sludoe 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. Thero sewage sludges, which may contain trace amounts of l radionuclidas, 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 APPLICATICNS July 1, 1993 through December 31, 1993 pate g LApm u n.'90 Gallons Site Activity Released (Ci)

July 13, 1993 14,100 PB 02 <MDA November 30, 1993 5,800 PB 02 <MDA 2.0 RADIOACTIVE AIRBORNE RELEASEJ 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 1 containment purge stack, Unit 2 containment purge stack, combined air ejector decay duct exhaust and turbine building ventilation exhaust.

There were two gas decay tank released during this reporting period.

2.1 Badippetive Airborne Release Summary 2.1.1 Rel'*e aa 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 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, 1993 through June 30, 1993.

6-MONTH

[. AEB IEX JUll TOTAL Strontium (Ci) 4.38E-08 4.53E-08 4.38E-08 1.33E-07 2.2 Isotocic Airborne 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.

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TABLE 2-1 RADIOACTIVE AIRBORNE RELEASE SUdMRY JULY 1, 1993 THROUGH DECEMBER 31, 1993 JUL AUG SEP M NOV DEC 'IOTAL Total Noble Gases (Ci) : (1) 5.67E-01 5.49E-01 1.49E+00 2.17E-01 2.16E-01 1.87E-01 3.23E+00 Total Radiciodines (Ci) : 1.32E-09 5.51E-06 2.43E-05 9.38E-05 7.79E-06 2.17E-06 1.34E-04 Total Particulates (Ci) : 3.08E-07 1.23E-05 8.81E-05 1.45E-02 3.32E-05 4.38E-05 1.47E-02 Alpha (Ci) : 3.08E-07 <MDA 4.88E-07 1.11E-06 4.67E-07 3.31E-05 3.55E-05 Strontium (Ci) : <m <MDA <MDA (2) (2) (2) (2)

All Others (Ci) - <MDA 1.23E-05 8.76E-05 1.45E-02 3.27E-05 1.07E-05 1.47E-02 Total Tritium (Ci): 4.68E+00 1.78E+01 7.45E+00 1.69E+01 1.01E+01 9.39E+00 6.63E+01 Maximum Hourly Average Release Rate (Curies /Second) 5.73E-07 5.55E-07 9.01E-05 2.06E-05 2.12E-06 1.02E-07 Comparison of effluent doses to Appendix I limits January-June January-Decerber Catecory Annual Dose Limit Calculated Dose Calculated Dose particulate 30 mrem / organ 1.63E-02 (child liver) 5.35E-01 (child liver) noble gas 40 mrad ( air) 8.74E-04 1.22E-03 noble gas 20 mrad (y air dose) 1.66E-03 2.25E-03 noble gas 30 mrem (skin) 1.10E-03 1.49E-03 noble gas 10 mrem (whole body) 1.96E-03 2.67E-03 (1) Includes noble gas contribution from liquid releases.

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

6 M M M M M M m M M e m m m m m m m a e

TABLE 2-2 RADIOACTIVE AIRBORNE RELEASE

SUMMARY

JULY 1, 1993 THROUGH DECEMBER 31, 1993 NUCLIDES JUL AUG SEP OCT NOV DEC TOTAL RELEASED (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curie s)

Tritium 4.68E+00 1.78E+01 7.45E+00 1.69E+01 1.01E+01 9.39E+00 6.63E+01

, Xe-133 1.86E-01 1.57E-01 8.33E-01 1.03E-01 5.78E-02 2.32E-02 1.36E+00 l

Kr-85m 5.09E-03 7.18E-03 1.50E-02 4.07E-06 2.13E-03 1.52E-03 3.09E-02 Kr-88 1.18E-02 1.64E-02 3.47E-02 1.08E-05 5.41E-03 3.27E-03 7.16E-02 Xe-133m 3.85E-04 2.93E-04 4.72E-03 <MDA 7.2SE-05 2.37E-03 7.84E-03 Xe-135 3.42E-02 4.39E-02 8.43E-02 2.03E-05 1.13E-02 6.91E-03 1.81E-01 Xe-138 3.71E-02 4.61E-02 9.28E-02 4.79E-05 2.30E-02 1.33E-02 2.12E-01 Kr-87 9.18E-03 1.30E-02 2.66E-02 1.02E-05 5.47E-03 3.00E-03 5.73E-02 Xe-135m 1.18E-02 1.57E-02 2.89E-02 1.63E-05 8.03E-03 4.48E-03 6.89E-02 Ar-41 1.35E-01 1.88E-01 1.82E-01 1.14E-01 1.03E-01 1.29E-01 8.51E-01 Kr-85 1.36E-01 6.12E-02 1.83E-01 <MDA <MDA <MDA 3.80E-01 Xe-131m 6A <MDA 1.11E-03 <MDA <MDA <MDA 1.11E-03 I-131 1.32E-09 4.73E-07 1.06E-05 9.38E-05 2.11E-06 4.51E-07 1.07E-04 I-132 6A 7.76E-07 2.21E-06 <MDA <MDA 4.26E-07 3.41E-06 I-133 <MDA 2.11E-06 6.71E-06 <MDA 5.68E-06 1.30E-06 1.58E-05 I-134 <MDA 6.13E-07 <MDA <MDA <MDA <MDA 6.13E-07 I-135 6A 1.54E-06 4.75E-06 (MDA <MDA <MDA 6.29E-06 F-18 <MDA 2.78E-06 3.77E-06 <MDA 1.71E-05 1.06E-05 3.43E-05  ;

Na-24 <MDA <MDA <MDA 6A 2.01E-06 <MDA 2.01E-06 l Co-58 <MDA (MDA <MDA 3.74E-04 <MDA sMDA 3.74E-04 i Co-60 <MDA <MDA 1.20E-06 5.92E-04 3.13E-11 <MDA 5.93E-04 l Rb-88 <MDA 8.09E-06 1.32E-06 <MDA <MDA <MDA -9.41E-06 Cs-134 <MDA 7.38E-07 3.89E-05 6.74E-03 6.66E-06 <MDr 6.79E-03 Cs-137 <MDA 6.55E-07 4.05E-05 6.75E-03 6.93E-06 <MDA 6.80E-03 Cs-138 <MDA <MDA 1.94E-06 <MDA 9.17E-08 1.12E-07 2.14E-06 Sr-89 <MDA <MDA <MDA (1) (1) (1) (1)

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

Alpha 3.08E-07 <MDA 4.88E-07 1.11E-06 4.67E-07 3.31E-05 3.55E-05 (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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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, 1993, through June 30, 1993.

6-MOZITH APRIL E_Y JUNE TOTALS =

Sr-89 (Ci) <MDA <MDA <MDA <MDA Sr-90 (Ci) 4.38E-08 4.53E-08 4.38E-08 1.33E-07 2.2.3 Corrections to previous Semiannual Monitoring Report Total airborne I-133 was incorrectly reported as 3.36E-01 curies. The correct total is 3.36E-05 curies.

3.0 RADIOACTIVE SOLID WASTE SHIPMENTS Solid wastes shipped for burial during this reporting period were as follows: l DATE OF SHIPMENT VOLUME TOTAL ACTIVITY TO BURIAL (CUBIC FEET) (Curies) BURIAL SITE 7/02/93 6.54 (1) 7.00E-04 Barnwell, SC 7/15/93 26.97 (1) 1.74E-02 Ba rnwell, SC 7/19/93 3.00 (1)

• 67E-02 Barnwell, SC  ;

8/02/93 4.47 (1) 4.00E-04 Ba rnwell, SC 8/02/93 7.50 (1,2) 1.92E-02 Barnwell, SC 8/12/93 102.08 (1,2) 8.00E-04 Barnwell, SC 10/06/93 97.50 (3) 3.22E+00 Barnwell, SC )

10/13/93 36.21 (1,2) 5.00E-03 Barnwell, SC i 10/15/93 38.30 (3) 1.18E+00 Barnwell, SC l 10/28/93 81.12 (1,2) 1.89E-02 Barnwell, SC l 11/02/93 120. (4) 2.37E+02 Barnwell, SC i 11/12/93 7.50 (1,2) 7.00E-04 Barnwell, SC J 11/22/93 9.00 (1,2) 0.00E+00 Barnwell, SC l 11/22/93 15.00 (1,2) 3.00E-04 Barnwell, SC l 11/29/93 18.20 (1) 1.03E-02 Barnwell, SC 11/30/93 70.00 (1) 3.51E-02 Barnwell, SC 12/03/93 31.30 (1) 1.59E-02 Barnwell, SC l 12/06/93 7.50 (1,2) 2.00E-04 Barnwell, SC E 12/07/93 22.50 (1,2) 1.80E-03 Barnwell, SC 12/09/93 113.37 (1,2) 9.60E 03 Barnwell, SC 12/10/93 7.50 (1,2) 2.00E-04 Barnwell, SC 12/10/93 15.00 (1,2) 3.30E-05 Barnwell, SC W 12/15/93 31.40 (1) 1.72E-02 Barnwell, SC 12/18/93 97.18 (1, 2 ) 5.63E-02 Barnwell, SC 12/21/93 132.50 (1,2) 7.90E-03 Barnwell, SC l 12/21/93 31.50 (1,2) 1.40E-03 Barnwell, SC E 12/21/93 19.10 (1,2) 1.00E-03 Barnwell, SC 12/29/93 28.42 (1,2) 1.45E-01 Barnwell, SC TOTAL 1181.16 241.78 (1) Dry Active Waste (2) Scrap Metal (3) Evaporator Concentrates l W

(4) Bead Resin I

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4.0 NEW AND SPENT FUEL SHIPMENTS AND RECEIPTS During this reporting period, a total of 28 new fuel assemblies were received f rom Westinghouse Electric Corporation for Unit 2. The new fuel assemblies received for Unit 2 were used for the Fall 1993 refueling.

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

5.0 PADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Introduction 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 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. This table contains the following information:

Sample: the type of the sample medium

Description:

the type of measurement LLD: the a oriori lower limit of detection N: the number of samples analyzed Low: the lowest measured value t its associated 20 counting error Average: the average value i the standard deviation of N samples High: the highest measured value t its associated 20 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 with the RETS LLD given in parentheses. Occasionally, anomalous results are obtained which lie well outside of the range of expected values. If, upon investigation, these values are found not to be the result of PBNP operations they will not be listed in the table. In this case, the highest reported value will be footnoted and the omitted value 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, 1993 through December 31, 1993 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 flume pier continues to exhibit some of the lowest values.

The analyses for individual radionuclides in environmental samples does not reveal any unexpected results. Sr-90 continues to persist in milk and water. Cs-137 continues to persist in 9

milk, sediment, fish, algae, vegetation, and soil. These radionuclides routinely occur in environmental samples collected around the world. The occurrence of these radionuclides in the environment is attributable to the large scale atmospheric weapons tests of the 1960's, lesu frequent testing it. the 70's and 80's, and to the Chernobyl accident. Tritium concentrations continue to be low with four of the ten H-3 results being either less than the typical blank results of 72.9 i 99.1 pCi/l or otherwise not statistically different from zero. Tritium, in addition to being a naturally occurring radionuclide also is produced by water-cooled reactors such as PBNP.

Measured concentrations of other radionuclides 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 LLDs) whose 12e error does E not overlap zero occur for several radionuclides, g Most of the " positive" results occur for water samples. Of the thirty (30) measurements of Co-58 concentrations in lako water, two (2) results obtained in August are statistically greater than zero. Howerver, no detectible Co-58 was released from PBNP during the months of July, August, and September. Therefore, these positive results appear to be statistical artitfacts. Two (2) of thirty (30) Co 60 results (1.2 1 0.9 and 2.9 1 2.1) were greater than zero. However, the subtraction of values obtained from " blanks" (1.2 t 2.3) would make these results statistically equivalent to zero (0) . Zr-Nb 95 (5.7 i 4.5) also has a positive result in lake water. However, there was no detectible Zr Nb-95 l in PBNP effluent during this reporting period. Furthermore, the a subtraction of blank values (2.4 i 5.0 and 1.5 t 3.2 pCi/1) would make the results statistically equivalent to zero. Therefore, positive results for Co 60 and Zr-Nb-95 appear to be statistical artifacts.

In milk, one of eighteen results was positive for I-131 (0.17 1 0.15). However, subtraction of the typical blank value (0.1 1 0.1) would make this result statistically equal to zero.

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 E completed in August of 1993 to ensure that the milk sampling locations remain as conservative as practicable. No significant E

change in the use of pasture lands was noted. Therefore, the existing milk sampling program continues to be acceptable.

5.4 Correction to Previous Report The average Co-137 concentration in soil was incorrectly reported as 0.038 1 0.158 in Table 5.1 in the previous report. The correct value is 0.238 i 0.158 pCi/g.

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TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING RESULTS Description LLD N Low Average High Units Sample

(*) 1.29 i O.03 mR/7 days TLD Environmental Radiation 54 0.58 1 0.03 0.90 0.13 Air Gross beta 0.01 155 0.010 1 0.002 0.023 1 0.008 0.049 1 0.004 pCi/m' Cs-137 0.01(0.06) 12 -0.000510.0008 -0.000010.0003 0.0005 0.0008 pCi/m' Cs-134 0.05 12 -O 000410.0007 -0.000010.0002 0.0003 0.0004 pCi/m' I-131 0.03(0.07) 155 -n.ul6 1 0.017 -0.001 0.007 0.017 0.017 pCi/m' Other gamma emitters (*) 0 .1 ( * ) 12 -l J00810.0009 0.0001 0.0004 0.0006 0.0005 pCi/m' Milk I-131 0.5 18 -0.2010.22 0.03 1 0.10 0.19 1 0.23 pCi/1 Sr-89 (*) 5 (*) 18 -1.8 1.4 -0.2 i 0.9 1.5 1.5 pCi/1 Sr-90 (*) 1(*) 18 0.S i 0.3 1.5 0.4 2.1 1 0.5 pCi/1 Cs-134 5(15) 18 -3.0 2.2 -1.2 1.0 0.6 2.6 pCi/1 Cs-137 5(18) 18 -3.2 t 2.3 0.4 i 1.4 2.4 1 2.2 pCi/1 Ba-La-140 5(15) 18 -2.0 1 3.1 -0.3 1 1.2 2.0 2.6 pCi/1 Other gamma emitters (*) 15 ( * ) 18 -1,2 2.7 0.6 i 1.2 2.4 3.0 pCi/1 Lake water Gross beta 4 30 1.6 0.5 2.7 0.9 5.6 t 1.0 pCi/1 I-131 0.5 (2) 30 -0.10 0.20 0.10 0.12 0.32 1 0.33 pCi/1 Mn-54 10(15) 30 -1,6 2.3 0.2 1.1 2,4 2.7 pCi/1 Fe-59 30 30 -3.3 i 7.0 0.1 1 2.3 5.3 1 5.5 pCi/1 Co-58 10 30 -3.2 2.1 0.1 1.7 4.9 4.3 pCi/1 Co-60 10 30 -2.3 i 7.7 0.4 1 1.2 2.9 i 2.1 pCi/1 Zn-65 30 30 -6.4 5.3 -1.3 2.9 4.2 5.8 pCi/1 Zr-Nb-95 15 30 -3.8 i 4.5 0.1 1.9 5.7 4.5 pCi/1 Cs-134 10(15) 30 -5.5 2.7 -1.2 1.6 1.2 2.4 pCi/1 Cs-137 10(18) 30 -3.1 1 3.6 0.4 i 1.1 1.9 t 2.2 pCi/1 Ba-La-140 15 30 -11.2 i 11.4 -1.4 3.5 5.6 i 7.4 pCi/1 Other gamma emitters (*) 30 (*) 30 -2.8 8.8 -0.6 i 1.0 1.6 16.2 pCi/1 H-3 500(3000) 10 26 91 106 70' 277 105- pCi/1 Sr-89 (*) 5 (*) 10 -1.5 1.6 -0.3 1 0.3 1.5 1.6 pCi/1 Sr-90 (*) 1(*) 10 0.3 t 0.4 0.9 i 0.4 1.5 t 0.5 pCi/1 Algae Gross beta 0.25 4 0.85 0.12 3.06 i 1.49 4.04 1 0.23 pCi/g Co-58 0.25 4 -0.02410.037 -0.004 1 0.017 0.017 1 0.022 pCi/g Co-60 0.25 4 0.003 0.013 0.012 1 0.008 0.022 0.028 pCi/g Cs-134 0.25 4 -0.03710.009 -0.018 i 0.015 -0.002 1 0.009 pCi/g Cs-137 0.25 4 0.031 0.022 0.045 1 0.011 0.054 1 0.032 pCi/g 11

Sample Description LLD N Low Average High Units Fish Gross beta (*) 0.5 (*) 4 2.24 1 0.07 2.78 1 0.51 3.44 0.10 pCi/g Mn-54 0.13 4 -0.002 0.006 0.001 0.033 0.00410.006 pCi/g Fe-59 0.26 4 -0.00710.002 -0.001 0.005 0.004 0.002 pCi/g Co-58 0.13 4 -0.00410.008 -0.00110.002 0.00110.006 pCi/g Co-60 0.13 4 -0.00310.006 -0.00110.002 0.00210.008 pCi/g 2n-65 0.26 4 -0.00410.012 0.00110.006 0.00910.012 pCi/g Cs-134 0.13 4 -0.006 0.009 -0.00210.004 0.00210.015 pCi/g Cs-137 0.15 4 0.047 0.014 0.08410.028 0.11510.024 pCi/g Other gamma emitters (*) 0.5 ( *) 4 -0.00610.012 -0.001 0.004 0.003 0.006 pCi/g Well water Gross beta 4 2 1.7 2.7 2.3 1 0.8 2.9 i 2.1 pCi/1 I-131 0.5 (2) 2 0.16 0.19 0.17 1 0.01 0.17 0.27 pCi/1 Mn-54 10(15) 2 -0.2 1 2.6 0.2 0.6 0.6 1.0 pCi/1 Fe-59 30 2 -0.7 6.4 -0.7 0.1 -0.6 2.9 pCi/1 Co-58 10 2 -0.5 1 2.9 0.3 1 1.1 1.0 i 1.2 pCi/1 Co-60 10 2 0.3 2.9 0.4 1 0.1 0.5 0.9 pCi/1 Zn-65 30 2 -8.2 1 7.0 -5.2 1 4.2 -2.2 i 1.9 pCi/1 Zr-Nb-95 15 2 -0.1 1 4.3 0.1 0.2 0.2 1 2.0 pCi/1 Cs-134 10(15) 2 -8.4 t 3.3 -4.4 5.7 -0.3 0.8 pCi/1 Cs-137 10(18) 2 -0.3 0.9 -0.2 0.1 -0.0 0.9 pCi/1 Ba-La-140 15 2 -0.6 i 3.9 -0.2 1 1.1 1.0 i S.6 pCi/1 Other gamma emitters (*) 30 (*) 2 -1.2 1 1.7 -0.2 1 1.4 0.8 3.0 pCi/1 H-3 500 2 -57.6 9.5 -47.1 14.9 -36.5 90.2 pCi/1 Sr-89 (*) 5 (*) 2 -0.0 0.4 -0.2 1 0.2 0.3 0.9 pCi/1 Sr-90 (*) 1(*) 2 0.0 t 0.2 0.0 t 0.0 0.0 0.3 pCi/1 Soil (*) Gross beta 2 8 12.66 i 2.22 23.20 1 5.78 32.35 3.37 pCi/g Cs-137 0.15 8 0.11 t 0.03 0.42 0.25 0.87 1 0.04 pCi/g Shoreline Gross beta 2 5 3.8 i 1.2 6.7 2.8 9.9 i 2.2 pCi/g sediment ( *) Cs-137 0.15 5 0.032 0.010 0.043 i 0.009 0.053 i 0.014 pCi/g Vegetation Gross beta (*) 0.25 (*) 16 3.4 1 0.1 4.9 1.0 6.6 0.2 pCi/g Cs-134 0.06 16 -0.01410.012 -0.004 0.006 0.003 1 0.010 pCi/g Cs-137 0.08 16 -0.004 0.009 0.012 0.022 0.086 0.025 pCi/g I-131 0.06 16 -0.03410.038 0.001 1 0.011 0.013 i 0.020 pCi/g 12

4 6.0 NONRADIOACTIVE CHEMICAL RELEASES 6.1 Scheduled Chemical Waste Releases

• Scheduled chemical waste releases to the circulating water system from July 1, 1993, to December 31, 1993, included 5.95E+06 gallons of neutralized wastewater. The wastewater contained 5.82E+02 pounds of suspended solids and 4.28E+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 Miscellaueous Chemical Waste Releases

• Miscellaneous chemical waste releases from the retention pond (based on effluent analyses) to the circulating water for July 1, 1993, to December 31, 1993, included 1.69E+07 gallons of clarified wastewater. The wastewater contained 1.62E+03 pounds-of suspended solids.

• Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 1993, to December 31, 1993, included 9.93E+04 pounds of sodium bisulfite and 4.42E+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.

TABLE 7-1 CIRCULATING WATER SYSTEM OPERATION July 1, 1993 to December 31, 1993 37Ula AUG SEP QCI EQV E p_E_q Average Volume Cooling U1 489.7 489.6 491.1 503.4 476.6 432.8 Water Discharge (Million gal / day) ** U2 485.7 489.6 474.1* 267.8* 477.2 436.5 Average Cooling Water U1 55 60 54 48 42 39 Intake Temperature (Degrees F) U2 55 60 54* 44* 42 39 Average Cooling Water U1 74 79 72 66 61 60 Discharge Temperature (Degrees F) U2 76 81 74* 52* 61 61 l'

Average Ambient Lake Temperature (Degrees F) 52 57 51 46 41 37

(* Unit 2 refueling shutdown from September 25, 1993 to October 30, 1993i

(**For days with cooling water discharge flow)

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t 8.0 LEAK TESTING OF RADIOACTIVE SOURCES l

During this reporting period, all applicable sealed radioactive sources were leak tested in accordance with Technical Specifica*.lon 15.4.12.

Leak test results were all <0.005 pCi.

9.0 MISCELLANEOUS REPORTING REOUIPEMENTS 9.1 Revisions to the PBNP Office Dose Calculation Manusi (ODCM) and Process Control Procram (PCP) l No revisions were made to either the Environmental Ma.1ual, the ODCM, or the PCP during this reporting period.

9.2 Interlaboratory Comoarison Program The analytical laboratory contracted to perform the radicanalyses of the PBNP environmental samples participated in the EPA Interlaboratory Comparison Program during this reporting period.

9.3 Deviations from Specified Environmental Samole Tvoes, Locations, and Frecuencies During this reporting period, a deviation from the sampling frequency specified in Table 15.7.7-1 of the Technical Specifications occurred at site E-01 when power was lost to the air sampler at site E-01 for one week. Power was lost when trenching for the fiber optics cable cut the power cable to the site. As a result, no air particulate and radiciodine air samples were obtained during that time period. Deviations pursuant to equipment malfunctions are permitted pursuant to 15.7.7.A.2.

In order to prevent reoccurrence, the location of power lines to i the site have been updated on controlled drawings. Also, CHAMPS l j and the Master Data Book have been updated.

9.4 Summary of Unachievable Snecified Environmentpl LLDJ All LLDs listed in Table 15.7.7-2 of the PBNP Technical Specifications were achieved during this sampling period.

l 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.

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