ML19294C240

From kanterella
Jump to navigation Jump to search
Semiannual Monitoring Rept,Jul-Dec 1979
ML19294C240
Person / Time
Site: Point Beach  
Issue date: 12/31/1979
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19294C239 List:
References
NUDOCS 8003070359
Download: ML19294C240 (15)


Text

..

a hh B st T 2:

WISCONSIN ELECTRIC

.3 3e"

?

Semiannual

.e ;!

POWER COMPANY kI July 1,1979 through December 31,1979 l

t I i':

j' iN POINT BE ACH NUCLE AR P L ANT

[5..

  • i r-UNIT NOS.1 AND 2

..I?

]h p

t!'

O!

li

~ fI'

'P

, 'iji e4 j.;if'

~

p

!.??If

,{' !

U.S. Nuclear Regulatory Commission 6,

c d UthLky,D f,, N

f. '8

Docket Nos. 50-266 and 50-30I 73' b Facility Operating License Nos. 1 DPR-24 and DPR-27 k.f. 359 seav.en

TABLE OF COtiTENTS SECTION TITLE PAGE 1.0 RADIOACTIVE LIQUID RELEASES 1 2.0 RADIOACTIVE AIRBORNE RELEA3ES 4 3.0 RADIOACTIVE SOLID WASTE SilIPMENTS 8 4.0 NEW AND SPENT FUEL SIIIPMENTS AND RECEIPTS 8 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 9 6.0 NON-RADIOLOGICAL ENVIRONMENTAL MONITORING 10 7.0 NON-RADIOACTIVE CIIEMICAL RELEASES 11 8.0 CIRCULATING WATER SYSTEM OPERATIONS 12 9.0 LEAK TESTING OF RADIOACTIVE SOURCES 12

1.0 RADIOACTIVE LIQUID RELEASES Radioactive liquid releases via the circulating water discharge are summarized for total release and by individual source on a monthly basis in Table 1-1. An isotopic breakdown of the total radioactive liquid release is presented in Table 1-2. The total radioactive liquid release excluding tritium for this reporting period was 3.77E-1 Curies which included 2.60E-2 Curies of processed radioactive waste and primary coolant system letdown, 3.40E-1 Curies of Unit 1 steam generator blowdown, 1.10E-2 Curies of Unit 2 steam generator blowdown and 1. 83E-4 Curies of retention pond ef fluent. The total tritium release for Obis reporting period was 436 Curies, which included 428 Curies of processed radioactive waste and primary coolan t system let-down, 5.45 Curies of Unit 1 steam generator blowdown, 1.99 Curies of Unit 2 steam generator blowdown, and 1. 32 Curies of retention pond effluent. All radioactive liquid releases to Lake Michigan were made through the circulating water discharge. 1.1 Additions to Semiannual Monitoring Report January 1, 1979, through June 30, 1979 May J une Total Total Activity Released, Ci Gross Alpha <MDA 8.64E-7 1.50E-6 Average Diluted Discharge Concentration, PCi/cc Gross Alpha 1.32E-14 % MPC 4.42E-5 The following data which was not available at time of report preparation should be added to Table 1-2 of the Semiannual Monitoring Report January 1,1979, through June 30, 1979. May J un e To tal Sr-89 <MDA (MDA 3.75E-6 Sr-90 <MDA <MDA <MDA Alpha <MDA 8.64E-7 1.50E-6 TABLE l-1 RADIOACTIVE LIOUID CIRCULATING WATER RELEASE

SUMMARY

PERTOD JULY 1 TO DECEMBER 31, 1974 July August Sentember October November December Total Total Activity Released, Ci Beta-Gamma (1) 1.90E-02 1.67E-01 5.28E-02 6.33E-02 3.67E-02 3.82E-02 3.77E-01 Gross Alpha 5 90E-07 7.lCE-07 1.17E-07 6.81E-07 ( 3) 3.51E-07 (3) Tritium 3.20E+01 9.67E+01 1.06E+02 1.04E+02 3.73E+01 6.00E+01 4.36E+02 Total Volums Released, Gal: Processed Waste 6.62E+04 3.74E+05 1.54E+05 1.80E+05 2.65E+05 1.85E+05 1.22E+06 Steam Generator Blowdown, Unit 1 2.57E+06 1.02E+06 2.89E+06 4.5CE+05 8.21E+05 1.89E+06 9.64E+06 Steam Generator Blowdown, Unit 2 1.09E+06 2.94E+06 2.78E+C6 3.00E+06 2.80E+06 2.74E+06 1.54E+07 Retention Pond 1.73E+06 2.53E+06 1.65E+06 1.37E+06 1.70E+06 2.63E+06 1.16E+07 0y Total 5.46E+06 6.86E+06 7.47E+06 5.00E+06 5.59E+06 7.44E+06 3.78E+07 volume of Dilution Water, ml 4.87E+13 3.84E+13 6.84E+13 2.29E+13 1.13E+13 3.35E+13 2.23E+14 Average Diluted Discharge Concentration, uCi/cc Gross Beta-Gamma 3.90E-10

4. 3 3E-09 7.70E-09 2.77E-09 3.24E-09 1.14E-09 1.14E-09

% MPC 2.30E-02 1.40E-01 7.54E-02 3.56E-01 3.39E-02 6.08E-02 Gross Alpha 1.01C-14 1.85E-14 1.71E-15 2.97E-14 ( 3) 1.05E-14 s MPC 3.42E-05 6.16E-05 5.69E-06 9.91E-05 (3) 3.49E-05 TriLium 6.57E-07 2.52E-06 1.55E-06 4.54E-06 3.30E-06 1.79E-06 s MPC 2.19E-02 8.33E-02 5.17E-02 1.51E-01 1.10E-01 5.97E-02 Maximum Discharge Concentration During Release Period, LCi/cc Gross Beta-Gamma (1) 9.68E-10 3.52E-07 1.12C-08 2.27E-08 5.OnE-09 1.05E-07 Tritium 4.47E-05 6.59E-05 5.62E-05 5.82E-05 6.12E-05 1.02E-04 NOTES: (1) Not including Strontium results which cenerally have a negligible e f fect. (2) Summation of the individual isotopic 10 CFR 20, Appendix B Table II FTC's. ( 3) Data unavailable at time of report writing.

TABLE l-2 ISOTOPIC COMPOSITION OF CIRCULAT!NG WATER DISCHARGES PERIOD JULY I TO DECEMBER 31, 1979 Nuclides July August September October Novembe r December Total Released (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) H-3 3.20E+01

9. 6 7E + 01 1.06E+02 1.04E+02 3.37E+01 6.00E+01 4.36E+02 F-18 2.36E-04 1.92E-03 8.70E-04 1.38E-03 7.03E-04 3.30E-03 8.41E-03 Cr-51

<MDA <MDA 2.llE-04 <MDA <MDA 3.24E-04 5.35E-04 Mn-54 5.75E-05 3.79E-03 <MDA 7.99E-07 1.40E-03 1.60E-03 6.85E-03 Co-57 'MDA <MDa <MDA <MDA <MDA 3.16E -05 3.16E-05 Co-58 <MDA 3.02E-02 1.93E-03 1.85E-04 1.18E-03 7.25E-03 4.07E-02 Co-60 5.09E-04 6.54E-03 3.88E-04 2.04E-04 8.92E-04 4.58E-03 1.31E-02 Fe-59 <MDA 9.17E-05 <MDA <MDA <MDA <MDA 9.17E-05 Kr-85m <MDA <MDA <MDA <MDA <MDA 4.70E-05 4.70E-05 Rb-88 <MDA <MDA 2.18E-02 <MDA <MDs 1.30E-04 2.19E-02 Sr-89 <MDA 1.56E-05 <MDA a.47E-05 1.50E-05 <MDA 6.53E-05 Sr-90 <MDA <MDA 1.llE-06 8.85E-06 6.90E-06 <MDA 1.69E-05 Zr-95 <MDA 1.30E-03 <MDA <MDA 1.03E-04 9.26E-05

1. 50E-0 3 Nb-95 (MDA 5.38E-04

<MDA <MDA 8.31E-05 4.49E-04 1.07E-03 Mo-99 <MDA 1.17E-04 <MDA 1.05E-04 <MDA 5.69E-04 7.91E-04 Ru-103 <MDA 1.75E-03 <MDA 3.89E-05 1.77E-05 1.88E-04 1.99E-03 Sn-ll3 <MDA <MDA <MDA <MDA 2.94E-OS 4.85E-05 7.79E-05 w Sb-124 <MDA 1.78E-04 (MDA <MDA <MDA 5.14E-05 2.29E-04 Sb-125 <MDA (MDA <MDA 3.81E-05 <MDA 4.18E-04 4.56E-04 I-131

9. 8 8E-04 9.81E-03 1.12E-02 1.58E-02 3.39E-04 4.38E-03 4.25E-02 I-132 9.36E-04 3.24E-02 7.87E-04 6.54E-03

<MDA 6.65E-04 4.13E-02 I-133 6.06E-03 9.20E-03 4.66E-03 2.49E-02 7.89E-04 3.30E-03 4.89E-02 I-134 2.27E-03 9.58E-04 <MDA

9. 4 4E- 0 5

<MDA 8.39E-04 4.16E-03 I-135 3.19E-03 3.72E-03 <MDA 9.24E-03 (MDA 1.14E-03 1.73E-02 Te-132 <MDA 4.88E-05 <MDA 2.04E-05 <MDA <MDA 6.92E-05 Xe-131m <MDA <MDA <MDA <MDA <MDA 3.10E-04 3.10E-04 Xe-133 4.22E-04 3.20E-03 2.21E-03 6.44E-04 <MDA 2.51E-03 8.99E-03 Xe-135 1.68E-05 1.42E-03 1.24E-04 3.13E-04 <MDA 4.72E-04 2.35E-03 Cs-134 6.98E-04 2.56E-03 6.51E-04 5.73E-04 4.96E-03 4.55E-04 9.90E-03 Cs-137 2.23E-03 5.42E-03 3.02E-03 2.28E-03 2.61E-02

3. 21E-0 3 4.23E-02 Cs-138
1. 4 3E-0 3 5.84E-03
3. 2 3E-0 3 9.69E-04

<MDA 1.09E-03 1.26E-02 Ce-139 <MDA <MDA 1.58E-04 <MDA <MDA <MDA 1.5EE-04 Ce-144 <MDA <MDA <MDA <MDA <MDA 1.21E-05 1.21E-05 Ba-140 <MDA 2.70E-02 1.21E-03 <MDA <MDA 4.04E-04 2.86E-02 La-140 <MDA

1. 8 4E- 02 1.80E-04

<MDA <MDA 2.8CE-04 1.89E-02 Alpha 5.00E-07 7.10E-07 1.17E-07 6.81E-07 (1) 3.51E-07 (1) ~~~~~~~~ TOTAL ~ ~ NOTES: <MDA - Less than minimum detectable activity. (1) - Data unavailable at report time. (2) - Total does not include tritium, or alpha.

2.0 RADIOACTIVE AIRBORNE RELEASES Radioactive airborne releases during normal plant operation are reported by total release in Table 2-1, and summarized by isotope in Table 2-2. The release paths contributing to radioactive airborne releases during this reporting period were the auxiliary building vent stack, Unit 1

ontainment purge stack, Unit 2 containment purge stack, drumming area vent stack, gas stripper building ventilation exhaust, combined air ejector decay duct exhaust and turbine building ventilation exhaust.

There were five gas decay tank releases during this report period. 2.1 Additions to the Semiannual Monitoring Report, January 1,

1979, through June 30, 1979 The following data which was not available at the time of the report preparation should be added to Table 2-2 in Section 2.0 of the Semiannual Monitoring Report covering the period January 1, 1979, through June 30, 1979.

April M June Total, Ci Sr-89

3. ole-08 2.03E-08 2.01E-08 6.52E-07 S r-90 9.38E-08 8.88E-08 8.62E-08 3.llE-07 2.2 Corrections to the Semiannual Monitoring Report, January 1,
1979, through June 30, 1979 The following corrections should be made +o Table 2-2 in Section 2.0 of the Semiannual Monitoring Report coverlag the period January 1, 1979, Chrough June 30, 1979.

January Februa ry March S r-90 1.27E-08 1.15E-08 1.82E-08 2.3 Cor re ctions to the Semiannual Monitoring Reports for Calendar Year 1978 2.3.1 Corrections to the Semiannual Monitoring Report, January 1, 1978, through June 30, 1978 The following corrections should be made to Table 2-2 in Section 2.0 of the Semiannual Monitoring Report covering the period January 1, 1978, through June 30, 1978. April Mg June Total Sr-89 1.02E-07 9.40E-08 9.10E-08 6.93E-07 Sr-90 2.43E-08 1.92E-08 1.43E-08

5. 7 8E-08 2.3.2 Corrections to the Semiannual Monitoring Report, July 1, 1978, through Deceraber 31, 1978 The following corrections should be made to Table 2.2 in Section 2.0 of the Semiannual Monitoring Report covering the period July 1,1978, through December 31, 1978.

July August September October S r-89

7. 87E-0 8 7.87E-08
7. 6 3F.-0 8 4.13E-07 Novembe r December Total S r-89 4.00E-07 4.13E-07 1.46E-06 July August September October S r-90 1.57E-08 1.57E-08 1.53E-08

<MDA November December Total S r-90 <MDA <MDA 4.67E-08 o TABLE 2-1 RADIOACTIVE AIRBOR'IE RELEASE

SUMMARY

PERIOD JULY l TO DECEMBER 31, 1979 July August September October November December Total Total Curies Released (Excluding Tritium) 8.61E+01 2.51E+02 1.10E+02 1.91E+01 1.46E+01 2.64E+02 7.45E+02 Total Xe-133 Equivalent l Curies Released 6.34E+02 2.80E+03

1. 2 7E+0 3 3.30E+02 1.08E+02 6.38E+02 5.78E+03 Average Release Rate (Ceries/Second) 2 2.36E-04 1.04E-03 4.89E-04 1.23E-04 4.2E-05 2.38E-04 Percent of Annuci Tech-i nical Specification Limits 3 1.18E-01 5.22E-Ol 2.44E-01 6.16E-02 2.08E-02 1.19E-01 Maximum Hourly Average Release Rate (Curies /Se cond) 4 1.28E-03 1.24E-02 1.23E-02 1.33E-03 4.61E-05 7.58E-03 Monthly Average Site Boundary Ccncentration (pCi/cc)2 3.55E-10 1.56E-09 7.33E-10 1.85E-10 6.25E-ll 3.57E-10 1 All gaseous and particulate releases are converted to "13 3Xe equivalent" for calculational purposes using the ratio MPCXe-133/MPCi.

MPC's for isotopes of iodine and particulate with half-lives longer than eight days are reduced by a factor of 700. 2 Averaged over one month and based on Xe-133 equivalent. 3 Annual average Technical Specification limits are 0.2 Ci/sec Xe-133 based on X/Q - 1.5 X 10-6 sec/m, 3 3 Maximum Technical Specification limits are 2.0 Ci/sec Xe-133 based on X/Q - 1.5 x 10-6 sec/m, 4 Expressed as Xe-133 equivalent.

TABLE 2-2 PADIOACTIVE AIRBORNE RELEASE

SUMMARY

PERIOD JULY l TO DECEMBER 31, 1979 July Aug us t Septembe r October November December Total (Curies) (Curies) (Curies) (Curies? (Curies) (Curies) (Curies) Tritium 7.57E+01 6.71E+01 1.04E+01 7.66E+01 1.13E+02 1.22E+02 4.65E+02 Noble Gases Ar-41 1.28E+01 1.76E+01 5.92E+00

3. 0 3E + 00 3.07E+00 2.78E+00 4.52E+01 Kr-85 4.96E-01 6.07E+00 1.01E+00 3.20E-01 1.01E+00 1.51E+01 2.40E+01 Kr-85m 8.53E+00 2.28E+01 6.94E+00 1.24E+00 2.12E-01 2.34E+00 4.21E+01 Kr-87 3.44E+00
1. 0 3E +01 5.05E+00 8.75E-01 2.40E-01 1.72E+00 2.16E+01 Kr-88 1.16E+01 3.97E+01 1.26E+01 2.06E+00 3.43E-01 3.29E+00 6.96E+01 Xe-133 5.57E+00 3.llE+01 2.51E+01 2.53E+00
7. 4 3E +00 1.95E+02 2.67E+02 Xe-133m
1. 8 7E- 01 2.82E-01 1.23E+00 2.18E-02 6.66E-02 3.68E-01 2.16E+00 Xe-135
3. 7 8E+01 1.15E+02 4.38E+01 5.56E+00 9.99E-01 4.18E+01 2.45E+02 Xe-135m 2.56E+00 3.13E+00 2.86E+00 1.53E+00 4.65E-01 8.24E-01 1.14E+01 Xe-138 3.15E+00 5.41E+00 4.96E+00 1.92E+00 7.26E-01 1.08E+00 1.72E+01 Particulates with Half Lives less Than Eight Days F-18

<MDA <MDA <MDA 1.3BE-07 <MDA 1.42E-03 1.42E-03 Mn-56 5.74E-06 <MDA 'MDA <MDA <MDA <MDA 5.74E-06 Rb-88

5. 3 3E -0 2 1.37E-03 2.81E-03 7.48E-05

'MDA 1.76E-05 5.76E-02 S r-91 <MDA <MDA (MDA (MDA MDA 1.66E-06 1.66E-06 Mo-99 <MDA 6.20E-06 <MDA <MDA <MDA 1.34E-06 7.54E-06 Te-132

2. 2 8E-06 9.78E-07 8.77E-07

<MDA (MDA 1.39E-06 5.53E-06 Cs-136 <MDA <MDA 4.06E-06 (MDA <MDA

  1. MDA 4.06E-06 Cs-138 9.26E-03 7.00E-04 1.13E-03 1.27E-05 3.37E-06 4.54E-05 1.12E-02 La-140

<MDA 7.36E-05

6. 5 3E-0 7

<MDA <MDA 4.58E-09

7. 4 3E-0 5 Particulates with Half Lives Greater Than Eight Days and Iodines Cr-51

<MDA 6.41E-04 'MDA (MDA <MDA 2.22E-08 6.41E-04 Mn-54 <MDA

2. 6 5E-0 5 4.49E-07

<MDA (MDA 5.76E-09 2.10E-05 Co-57 <MDA 2.61E-05 <MDA <MDA <MDA 9.00E-10 2.61E-05 Co-58 8.50E-04 1.llE-03 8.44E-06 1.5GE-05 2.00E-05 4.16E-06 2.00E-03 Co-60 6.05E-04 8.04E-04 1.48E-05 2.82E-05 8.04E-06 5.86E-06

1. 47E-0 3 Sr-89 4.70E-07 4.81E-07 4.55E-07 (1)

(1) (1) (1) S r-90 8.54E-08 8.llE-08

8. 7 3E-08 (1)

(1) (1) (1) Nb-95 <MDA 2.62E-04 8.81E-08 <MDA 1.23E-06 3.00E-06 2.66E-04 Zr-95 <MDA 5.60E-05 5.15E-10 'MDA 1.36E-06 1.56E-06 5.90E-05 Ru-lO3 < MDA 4.27E-04 <M DA 2.44E-08 1.83E-06 2.092-06 4.31E-04 Cd-109 6.95E-04 'MDA 1.42E-06 <MDA 'MDA 3.21E-04 1.02E-03 Sn-113 <MDA 6.88E-07 (MOA 'MDA <MDA <MDA 6.89E-07 Sb-125 <MDA (MDA <MDA <MDA (MDA 5.61E-09 5.61E-09 I-131 2.95E-03 2.07E-04 2.60E-04 7.99E-05 1.89E-05 4.10E-05 3.56E-03 1-132 (MDA 1.59E-03 1.07E-03 1.10E-04 1.45E-05 4.04E-04 3.19E -0 3 Ba-l'3

2. 30E-04

'MDA <MDA <MDA <MDA <MDA 2.30E-04 .33 6.27E-03 1.19E-04 1.14E-04 1.29E-05 1.03E-07 1.90E-05 6.53E-03 Cs-134 2.74E-04 4.13E-06 4. 6 3E-06 4.62E-07 8.72E-07 2.13E-06 2.66E-04 I-134 <MDA 6.31E-07 <MDA 2.29E-08 <MDA 1.15E-05 1.22E-05 I-135 (MDA 1.21E-05 <MDA 4.93E-06 <MDA 1.16E-05 2.86E-05 Cs-137 5.52E-04 7.67E-06 1.27E-05 1.21d-06 4.68E-06 3.10E-05 6.09E-04 Ce-139 9.15E-09 <MDA (MDA 1.54E-09 <MDA (MDA 1.07E-08 Ba-140 <MDA 5.71E-07 5.90E-08 'MDA (MDA

7. 9 8E-09 6.38E-07 Ce-141
1. 34E-07 2.03E-04

<MDA <MDA 1.36E-06 3.39E-06

2. 0 8E-04 Ce-144

<MDA <MDA <MDA <MDA 6.92E-07 <MDA 6.92E-07 Alpha <MDA 4.58E-07 <MDA (MDA 'MDA 2.44E-08 4.82E-07 NOTES: <MDA - Less than minimum detectable activity. (1) - Data unavailable at report time.

3. 0 RADIOACTIVE SOLID WASTE SilIPMENTS Shipments of fsite of soliu waste for burial during this reporting period were as follows:

Date Volume (Pt. 3) Total Activity (Ci) 07-18-79 126 657 07-18-79 58 25.8 08-07-79 569.5 0.389 09-12-79 774.7 0.38 09-20-79 60 0.939 09-25-79 60 0.914 11-08-79 562.5 0.492 11-15-79 60 1.65 12-11-79 585 0.813 12-12-79 60 7.78 2,916 696 (1) Involved spent resin 4.0 NEW AND SPENT FUEL SilIPMENTS AND RECEIPTS During this reporting period, a total of 28 new fuel assemblies were received from Westinghouse Electric Corporation for Unit 1. No new fuel assemblies were received for Unit 2. No spent assemblies were shipped from Unit 1 or 2. _g.

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological environmental monitoring conducted by Point Beach Nuclear Plant for the period from July 1, 1979, through December 31, 1979, consisted of air filters, gamma dose, vegetation, lake water, well water, milk, shoreline silt, soil, algae, and fish samples collected and analyzed in accordance with Technical Specification 15.4.10 All measurements obtained this period are well within the normal range, and no ur. usual results or significant departures from normal were noted. No. Sample Type Low Average

  • High Units TLDs 32 Quarterly 0.20 0.83 + 0.54 1.34 mR/wk Air Filters 150 Gross Beta

<0.01 0.043 + 0.057 0.28 pCi/m3 150 Radiciodine all <0.03 PCi/m3 12 Gamma Scan Ce-144 all <0.01 pCi/m3 Cs-137 <0.001 <0.002 + 0.002 0.004 pCi/m3 Others all <0.001 pCi/m3 Milk 18 Radiciodine all <0.5 pCi/1 18 Sr-89 all <5 pCi/l 18 Sr-90 1 413 7 pCi/l 18 Gamma Scan all <5 pCi/l Lake Water 30 Gross Beta <1 4 +5 8 pCi/1 30 Gamma Scan al1 <10 pCi/1 10 Tritium <0.5 0.5 + 0.3 0.8 pCi/ml 10 Sr-89 <5 <5 <6 pCi/l 10 Sr-90 <1 <2 +4 <6 pCi/l Well Water 2 Gross Beta <1 <l.5 2 pCi/l 2 Gamma Scan both <10 pCi/l 2 Tritium both <0.5 pCi/ml 2 Sr-89 both <5 pCi/1 2 Sr-90 both <1 pCi/l Vegetation 16 Gross Beta 2 7+7 15 pCi/g (we t ) 16 Gamma Scan all <1 pCi/g (wet) _9-

No. Sample Type Low Average

  • High Units Soil 9

Gross Beta 2 3 f; 2 4 pCi/g (dry) 9 Gamma Scan all <1 pCi/g (dry) Algae 4 Gross Beta <1 2 j; 3 3 pCi/g (wet) 4 Gamma Scan all <1 pCi/g (wet) Fish 6 Gross Beta 1 2 f; 2 3 pCi/g (wet) 6 Gamma Scan all <1 pCi/g (wet) Shoreline Silt 5 Gross Beta 1 2 f; 2 2 pCi/g (wet) 5 Gamma Scan all <1 pCi/g (wet) 6.0 NON-RADIOLOGICAL EtNIRONMENTAL MONITORING PROGRAM In accordance with Amendment numbers 29 and 33 to Facility Operating Licenses DPR-24 and DPR-27 respectively, dated November 4, 1977, the Environmental Technical Specifications for the Point Beach Nuclear Plant Units 1 and 2 were modified to allow temporary suspension of the non-radiological environmental monitoring program pending NRC review of the summary report of the five years of monitoring. As a result, the semiannual report specified by item 16.6.2.a of the Technical Specification is not applicable. 9 7.0 NON-RADIOACTIVE CHEMICAL RELEASES 7.1 Scheduled Chemical Waste Releases Scheduled chemical waste 1 leases to the circulating water system for the period of 07-01-79 to 12-31-79 included 3,217,292 gallons of neutralized clear water waste. The waste water contained 638 pounds of suspended solids and 183,123 pounds of dissolved solids.* When averaged over the reporting period, these discharges represented 37.79% of the Technical Specification limit for dissolved solids and .277% of the Technical Specification limit for suspended solids.** The concentration increases of daemical waste in the circulating water system during the period of chemical releases ranged from 4.89 to 7.89 ppm dissolved solids and from 3.14E-04 to 8.45E-02 ppm suspended solids.** Plant chemical records indicated that the following amounts of chemicals were released in the form of neutralized waste: Sodium 48,211 pounds Sulfate 109,536 pounds

  • Chemical releases calculated are based upon neutralized tank analysis prior to discharge.
    • Based on calculations during times of actual discharges.

7.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases to the circulating water system from the retention pond for the period of 07-01-79 to 12-31-79 included 11,600,000 gallons of clear water waste. The waste water contained 1,680 pounds of suspended solids and 84,200 pounds of dissolved solids.* When averaged over the reporting period, these discharges were 2.49% of the Technical Specification limit for dissolved solids and 0.089% of the limit for suspended solids. Retention pond analysis and plant chemical records indicate that the following daemicals were released in the form of clear water waste from the retention pond. Sodium 7,689 pounds Chloride 11,866 pounds Phosphate 130 pounds The balance of the dissolved solids were in the form of soluble calcium and magnesium compounds resulting from the plant makeup water cold lime softening process.

  • Chemical release calculations are based on retention pond analyses during the period 07-01-79 to 12-31-79.

8.0 CIRCULATING WATER SYSTEM OPERATIONS The circulating water system operation during this reporting period for periods of plant operation is described in Table 8-1. d 9.0 LEAK TESTING OF RADIOACTIVE SOURCES During the reporting period, all applicable scaled radioactive sources were leak tested according to Technical Specification requirement 15.4.12. Results of the leak testing showed no removable contamination greater than 0.005 micro-Curies from sealed radioactive sources. p TABLE 8-1 CIRCULATING WATER SYSTEM OPERATION July August Sentember October November Dece mbe r Average Volune Cooling UNIT 1 598.1 505.9 579.8 51.'. 2 270.9 327.9 Water Discharge, Million Gal / Day UNIT 2 474. 3 596.7 593.1 634.9 633.4 434.2 Average Cooling Water UNIT 1 55.6 57.2 55.3 53.1 41.6 37.9 Intake Temperature 4) Degrees F UNIT 2 55.4 58.1 54.9 52.3 43.3 39.0 Average Cooling Water UNIT 1 71.9 69.2 71.4 64.4 43.3 53.7 Discharge Temperature 4) Degrees F UNIT 2 67.9 74.0 70.6 67.7 58.1 61.5 Average Ambient UNIT 1 52.4 55.3 52.5 50.6 41.7 35.7 Temperature Degrees F UNIT 2 (3) ( 3) (3) ( 3) ( 3) ( 3) (1) Unit 1 was shut down for refueling from October 8, 1979, to November 22, 1979. (2) Unit 1 was shut down for steam generator maintenance from August 7, 1979, to August 19, 1979, and December 17, 1979, to December 21, 1979. ( 3) Instrumentation out-of-service. (4) Unit 2 was shut down for maiatenance from July 7, 1979, to July 19, 1979.}}