Text

Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1986
	ML100290726
Person / Time
Site:	Indian Point
Issue date:	12/31/1986
From:	; Power Authority of the State of New York
To:	;
Shared Package
ML100290727	List: ML100290726; ML100290728;
References
	NUDOCS 8703050207
	Download: ML100290726 (38)
	v • d • e

Effluent and Waste Disposal Semi-Annual Report July 1 -

December 31, 1986 Facility Indian Point 3 Licensee New York Power Authority This information is provided in accordance with the requirements of Regulatory Guide 1.21.

The numbered sections of this report reference corresponding sections of the subject Regulatory Guide, pages 1.21-10 to 12.

A.

Supplemental Information

1.

Regulatory Limits Indian Point 3 is presently subject to limits on radioactive waste releases that are set forth in sections 2.3.1, 2.3.2, 2.3.3, 2.4.1, 2.4.2, 2.4.3 and 2.4.4 of Appendix B to Docket #50-286 entitled "Environmental Technical Specification Requirements Part II Radiological Environmental". The percentages of the technical specification limits reported in Tables 1A and 2A are the percent of the quarterly limits specified in the ETSR. If more than one limit applies to the release the most restrictive limit is applied.

2.

Maximum Permissible Concentration

a.

Fission and Activation Gases The quarterly dose resulting from release of fission and activation gases is calculated in accordance with the methodology stated in the Off Site Dose Calculation Manual (ODCM). The specific isotopes listed in Table IC are used to determine the effective dose factors for the time period.

b&c. Iodines, Tritium and Particulates The quarterly organ dose limit for Iodine 131, tritium and particulates with half-lives greater than eight days is calculated in accordance with the methodology stated in the ODCM.

d.

Liquid Effluents The quarterly dose limit for liquid isotopic releases is calculated in accordance with the methodology stated in the ODCM. The instantaneous concentration limit for noble gases dissolved in liquid releases is calculated based upon a maximum permissible concentration of 2.00E-4 as required by section 2.3.1.A of the ETSR.

8703050207 B70227 PDR ADOCK 05000286 R

PDR

3.

Average Energy The average energies (E) of the radionuclide mixture in releases of fission and activation gases were as follows:

3rd Quarter E

= 1.44E-01 MeV/dis E

= 5.58E-02 MeV/dis 4th Quarter E

= 1.63E-01 MeV/dis E

7.72E-02 MeV/dis

4.

Measurements and Approximations of Total Radioactivity

a.

Fission and Activation Gases Analysis of effluent gases has been performed in compliance with the requirements of Table 3.4-1 of the ETSR. In the case of isolated tanks (batch release) the total activity discharged is based on an isotopic analysis of each batch with the volume of gas in the batch corrected to standard temperature and pressure.

Vapor containment purge discharges have been treated as batch releases and pressure relief discharges have been treated as continuous releases (> 500 hrs/year as defined in NUREG 0133).

At least one complete isotopic concentration analysis of containment air is performed monthly. This analysis is used in conjunction with a process monitor to obtain the isotopic mixture and quantification of each pressure relief.

Isotopic analyses for each vapor containment purge are taken prior to and during the purge. This information is combined with the volume of air in each discharge to calculate the quantity of activity,, from thEse discharges.

The continuous building discharges are based on weekly samples of ventilation air for isotopic content. This information is combined with total air volume discharged and the process radiation monitor readings to determine the quantity of activity from continuous discharges.

Carbon 14 releases are estimated from the data provided in the New York State Department of Health study performed at IP3. These values are then prorated for the unit's annual power history.

b&c. Iodines and Particulates Iodine-131 and particulate releases are quantified by collecting a continuous sample of ventilation air on a TEDA impregnated activated charcoal cartridge and a glass-fiber filter paper. These samples are changed weekly as required in Table 3.4-1 of the ETSR and the concent ration of isotopes found by analysis of these samples is combined with the volume or air discharged during the sampling period to calculate the quantity of activity discharged.

For other iodine isotopes the concentration of each isotope is det ermined monthly on a 24-hour sample. The concentration of the isotopes found by analysis is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged.

d.

Liquid Effluents A sample of each batch discharge is taken and an isotopic analysis.

is performed in compliance with requirements specified in Table 3.3-1 of the ETSR. This isotopic concentration data is combined with information on volume discharged to determine the amount of each isotope discharged.

Proportional composite samples of continuous discharges are taken and analyzed in compliance with Table 3.3-1 of the ETSR. This concentration data is combined with the volume discharged to calculate the total activity discharged. Carbon 14 releases are estimated from the data provided in the New York State Department of Health study performed at IP3.

These values are then prorated for the unit's annual power history.

5.

Batch Releases

a.

Liquid 1986 3rd Quarter 4th Quarter Number of Batch Releases 41 57 Total Time Period Batch Releases (Min.)

8135 9676 Maximum "

375 310 Average "

198 170 Minimum "

120 115 Average Stream Flow (cfs)

(not yet available)

b.

Gaseous Number of Batch Releases 4

(none)

Total Time Period Batch Releases (Min.)

3422 Maximum 2690 Average 855 Minimum 112

6.

Abnormal Releases

a.

Liquid None

b.

Gaseous None

7.0 Radiological Environmental Technical Specifications The Radiological Environmental Technical Specifications require reporting of prolonged outage of effluent monitoring equipment (Sections 2.1.C and 2.2.B) and significant changes in the land use census, Radiological Environmental Monitoring Program or exceeding the total curie content limitations in outdoor tanks.

(Sections 2.8.A, 2.8.B, 2.7.C and 2.3.4.B).

During this reporting period no reportable events occurred.

The RETS modified the content and format of the Semi-Annual Effluent Release Report (Section 5.3.3.1).

A Section G "Offsite Dose Calculation Manual Changes", has been included. The ODCM was retyped to put the entire document on one word processing system, and a complete copy of the ODCM, Rev.

4 is enclosed. During this reporting period there were several changes to the Offsite Dose Calculation Manual. There were no changes in the Process Control Program.

Indian Point 3.

EFFLUENT AND WASTE DISPOSAL~

SEMI -ANNUAL REPORT B. GASEOUS EFFLUENTS THIRD AND FOURTH QUARTER 1986

TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES UNIT QUARTER 3rd QUARTER EST. TOTAL 4th Error %

A.

Fission & Activation Gases Total release Average release rate Percent of technical limit.

Curies for period uCi/sec specification 7.83E+01 9.85E-00 9.22E-01 B. Iodines Total iodine - 131 Ci Average release rate for period uCi/sec Percent of technical specification limit.

3.86E-04 4.86E-05 4.15E-02 C. Particulates

1. Particulates with half-lives >8 days

2. Average release rate for period

3. Percent of technical specification limit.

4. Gross alpha radioactivity Ci 1.25E-04 3.21E-06 uCi/sec 1.57E-05 4.04E-07 4.15E-02 Ci

<3.45E-01 1.18E-01

<4.30E-01 D.

Tritium Total release Average release rate for period Percent of technical specification limit.

Ci uCi/sec 1.31E-00

1. 64E-01 4.15E-02 9.47E-01 1.19E-01

1. 18E-01 5.60E+02 7.05E+01 5.97E-o 2.50E+01 5.57E-04

7. 01E-05 1.18E-01 2.50E+01 2.50E+01 2.50E+01

Page 1 TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

GASEOUS EFFLUENTS-GROUND RELEASES CONTINUOUS MODE Nuclides Released

1. Fission Gases Krypton (Kr) 85m Krypton (Kr) 85 Krypton (Kr) 87 Krypton (Kr) 88 Xenon (Xe) 131m Xenon (Xe) 133m Xenon (Xe) 133 Xenon (Xe) 135m Xenon (Xe) 135 Xenon (Xe) 138 Argon (Ar) 41 Unidentified Unit 3rd Ouarter 8.72E-01 3.96E-01

3. 36E-03 2.94E-02 2.28E-01 6.62E-01 1.OOE+02 1.76E+01 4.48E-02 4th Quarter 2.65E-01 1.48E-00 2.05E-02 2.28E-01 3.55E-00 4.95E-00 5.24E+02 BATCH MODE 3rd Quarter 4th Quarter 4.98E-04

1. 45E+00 3.39E-01 5.81E-02 1.64E+01 2.52E+01 9.81E-04 1.07E-01 TOTAL FOR PERIOD Ci 1.20E+02 5.60E+02 1.82E+01

2. Iodines iodine (I) 131 Ci 3.86E-04 5.57E-04 iodine (I) 133 Ci 5.10E-05 iodine (I) 135 Ci TOTAL FOR PERIOD Ci 4.37E-04 5.57E-04

Page 2 TABLE IC

.EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

GASEOUS EFFLUENTS -

GROUND RELEASES Nuclides Released

3. Particulates Antimony (Sb) 125 Barium (Ba).133 Cadmium (Cd) 109 Cerium (Ce) 139 Cerium (Ce) 141 Cerium (Ce) 144 Cesium (Cs) 134 Cesium (Cs) 137 Cobalt (Co) 57 Cobalt (Co) 58 Cobalt (Co) 60 Chromium (Cr) 51 Iron (Fe) 55 Niobium_:

(Nb) 95 Strontium (Sr) 85 Strontium (Sr) 90 Tin (Sn) 113 CONTINUOUS MODE BATCH MODE Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter 1.20E-05

1. 76E-07

1. 61E-06 8.83E-07

1. 04E-04 5.86E-06

1. 09E-06 2.25E-06 9.61E-07 TOTAL Ci 1.26E-04 3.21E-06 0.00E-00 O.OOE-00 I.....

Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI -ANNUAL REPORT C. LIQUID EFFLUENTS THIRD AND FOURTH QUARTERS, 1986

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

LIQUID EFFLUENTS -SUMMATION oF ALL RELEASES UNIT QUARTER QUARTER EST.TOTAL 3rd 4th ERROR %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha)

2. Average diluted concentration during period

3. Percent of applicable limit B. Tritium

1. Total release

2. Average diluted concentration during period

3. Percent of applicable limit C. Dissolved and entrained gases

1. Total release

2. Average diluted concentration during period

3. Percent of applicable limit D. Gross alpha radioactivity

1. Total release E. Volume of waste released (prior to dilution)

F. Volume of dilution water used during period Ci uCi/xnl Ci uCi/mi Ci uci/ml 5.08E-02 1.64E-10

1. 99E-01 5.01E+01 1.62E-07 1.99E-01 5.79E-01 1.87E-09 1.99E-o Ci

<9.82E-05 2.55E-02 8.61E-1 8.90E-02

1. 44E+02 4.87E-07 8.90E-02

7. 59E-00

2. 56E-08 8.90E-02

<1.54E-04 2.50E+01 2.50E+01 2.50E+01 2.50E+01 liters 1.35E+06 1.93E+06 1.00E+01 2.96E+11 1.00E+01 liters 3.09E+11

LIQUID EFFLUENT AND TABLE 2B WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

Nuclides Released Antimony (Sb) 122 Antimony (Sb) 124 Antimony (Sb) 125 Barium (Ba) 140 Barium (Ba) 133 Cadmium (Cd) 109 Cerium (Ce) 139 Cerium (Ce) 141 Cerium (Ce) 144 Cesium (Cs) 134 Cesium (Cs) 137 Cesium (Cs) 138 Chromium (Cr) 51 Cobalt (Co) 57 Cobalt (Co) 58 Cobalt (Co) 60 Iodine (I) 131 Iodine (I) 133 Iodine (I) 134 Iodine (I) 135 Iron (Fe) 55 Iron (Fe) 59 Lanthanum(La) 140 Mercury (Hg) 203 CONTINUOUS MODE 3rd Ouarter 4th Ouarter BATCH MODE 3rd Ouarter 4th Ouarter 1.17E-04 1.82E-03 8.62E-04 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

1. 06E-03 1.55E-03 1.48E-04 5.73E-06 4.71E-03 5.24E-03 5.54E-04 2.21E-05 1.93E-04 2.58E-02 2.81E-04 2.68E-06 1.32E-05 1.23E-04 3.26E-05 2.37E-03 1.21E-03 1.84E-03 7.74E-05 1.55E-02 3.12E-05 Page 1 n

4.33E-06

Page 2 TABLE 2B LIQUID EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

Nuclides Manganese (Mn) 54 Molybdenum(Mo) 99 Nickel (Ni) 63 Copper (Cu) 64 Niobium (Nb) 94 Niobium (Nb) 95 Yttrium (Y) 88 Rubidium (Rb) 88 Ruthenium (Ru) 103 Ruthenium (Ru) 105 Ruthenium (Ru) 106 Silver (Ag)110m Sodium (Na) 24 Strontium (Sr) 85 Technetium(Tc) 99m Tin (Sn) 113 Tellurium (Te) 132 Tungsten (W) 187 Yttrium (Y) 91m Yttrium (Y) 92 Zinc (Zn) 65 Zirconium (Zr) 95 Jnit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci CONTINUOUS MODE 3rd Quarter 4th Quarter BATCH 3rd Quarter 5.57E-04 1.72E-03 MODE 4th Quarter 2.61E-05 3.31E-04 2.09E-03 1.90E-05 3.92E-04 7.85E-05 6.57E-03 1.72E-05 1.94E-05 1.40E-04 4.25E-05 3.89E-04 4.43E-05 5.12E-06 2.15E-04 TOTAL FOR PERIOD 5.09E-02 2.55E-02

Page 3 TABLE 2B LIQUID EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

CONTINUOUS'MODE 3rd Quarter 4th Quarter BATCH 3rd Quarter 3.74E-05 2.94E-03 5.53E-01 1.11E-02 1.20E-02 1.88E-04 MODE 4th Quarter 5.50E-02 7.38E-00 1.09E-01 4.17E-02 6.81E-04 9.69E-03 1.06E-05 TOTAL DISSOLVED AND ENTRAINED GASES Ci 5.79E-01 7.56E-00 Nuclides Argon Xenon Xenon Xenon Xenon Krypton Krypton Krypton (Ar)

(Xe)

(Kr)

Unit Ci Ci Ci Ci Ci Ci Ci Ci 41 13 lm 133 133m 135 85m 85 88

Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT D. SOLID WASTE THIRD AND FOURTH QUARTERS, 1986

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July 1 -

December 31, 1986 SOLID WASTE SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

Unit 6 Month Period Est. Total

1.

Type of Waste Class A Class B Error, %

3

a. Spent resins, filter m

0 4.81E+O 5.0E+1 sludges, etc.

Ci 0

1.70E+1 3

b. Dry compressible, contam.

m 2.97E+O 0

5.0E+1 equipment for burial Ci 1.76E+O 0

3

c. Irradiated Components m

0 0

N/A Ci 0

0 3

d. Other:

Dry compressible, m

7.03E+1 0

5.0E+1 contaminated equip. for Ci 8.94E-1 0

volume reduction at offsite facility

2.

Estimate of major nuclide composition (by type of waste)

a. Resin CL:A& i.,.

15 32 22 7

b. Dry-Burial CLASS A 33 19 32 6

d. Dry-Vol. Reduction CLASS A 25 12 46 5

6 0

6

3.

Solid Waste Disposition Number of Shipments 2

3 Mode of Transport Truck Truck Destination Barnwell, SC SEG, Oak Ridge, Tenn.

for Volume Reduction

4.

Containers Shipped Class A Class B Container Number Solid. Media Number Solia. Medla For Burial:

Drums 14 none N/A N/A Poly HIC N/A N/A 1

none For Volume Reduction:

Drums 174 none N/A N/A Crates 12 none N/A N/A UNIT NUCLIDE Fe-55 Co-58 Co-60 Ni-63 Sb-125 Cs-134 Cs-137 a

Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT E.

RADIOLOGICAL IMPACT N MAN January -

December 1986

RADIOLOGICAL IMPACT ON MAN The radiological impact on man is determined by conservatively calculating doses to a hypothetically maximum individual offsite based on plant effluents.

These calculations are divided into 3 categories:

Noble Gases Particulates and Iodine Liquid Releases (fish and invertebrate consumption)

An annual average dispersion factor is used in the calculations, the details of which are presented in the Offsite Dose Calculation Manual.

The computer code used to perform dose calculations incorporates the models and parameters presented in the Indian Point 3 ODCM which utilizes the assumptions in Regulatory Guide 1.109 and NUREG 0133.

Carbon 14 release concentrations and resulting dose is estimated using data generated at Indian Point 3 by the New York State Department of Health. These estimates are consistent with the estimates in NUREG 0017, rev. 1.

Dose calculations from liquid pathways to individuals for the fish and invertebrate consumption pathways are computed using the methodology and parameters in the Indian Point 3 ODCM which incorporates the calculational models that are present in Regulatory Guide 1.109 and NUREG 0133.

Indian Point 3 Radiological Impact on Man January - December 1986

(

Reference:

Indian Point 3 RETS, Section 5.3.3)

Maximum Exposed individual Doses in mrem Total Body Skin Bone Liver Thyroid Kidn~v Tiinn (T-T.T.T A. Gaseous Pathway A.1 Noble Gases A.2 Radioiodines, Particulates, and Tritium A

A.3 Carbon-14 B.

Liquid Pathway B.1 All Releases (w/o C-14)

B.2 Carbon-14 2.30E-1 4.92E-4 3.84E-1

8. 35E-3 2.81E-3 1.08E-O 1.97E-4 6.OOE-4 6.22E-2 6.29E-4 4.11E-4 4.17E-4 1.92E-0 3.84E-1 3.84E-1 3.84E-1 3.84E-1 3.84E-1 3.05E-2 2.1OE-2 2.22E-2 2.56E-3 1.08E-2 3.92E-2 1.40E-2 2.81E-3 2.81E-3 2.81E-3 2.81E-3 2.81E-3 1.08E-0 1.96E-0 4.08E-1 4.71E-1 3.90E-1 3.98E-1 4.26E-1 Site Boundary, 350 meters, SW sector Infant, 8.1 km, SSW sector Child, 1.3 km, S sector Adult, 1.4 km, SW sector TOTALS 6.26E-1 Bone Liver Thvroid Kidne Lun GI-LLI

Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT F. METEROROLOGICAL DATA January - December 1986

- - - - I-.RC FORMAT FOR NUREG 1.21**i INDIAN POINT JULY-SEPT 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS A WINO DIRECTION WIND SPEED (MPH)

N NE NE ESE E

ESE SE SSE S

SS14 SW NW 01-03

4.

1.

2.

0.

1.

5.

11.

19.

7.

3.

1.

6.

2.

5.

04-07

67.

9.

4.

1.

0.

2.

14.

72.

25.

13.

7.

16.

5.

16.

26.

08-12

6.

1.

2.

0.

3.

8.

0.

4.

6.

13-18

0.

19-24

0.

>24

0.

TOTAL

70.

277.

30.

O.

0.

CALM a.

TOTAL

77.

11.

7.

3.

0.

1.

7.

25.

94.

40.

16.

8.

22.

'I.

22.

37.

*NRC FORMAT FOR ?IJRE6 1.2 INDIAN POINT JULY-SEPT 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS B WIND DIRECTION 01-03

4.

3.

0.

1.

8.

2.

1.

3.

1.

2.

1.

04-07

18.

9.

1.

0.

1.

18.

4.

5.

1.

2.

0.

08-12

1.

0.

1.

0.

WIND SPEED (MPH) 13-18

0.

19-24

0.

-0.

0.

TOTAL

31.

61.

3.

0.

CAU 0.

TOTAL

23.

13.

1.

2.

27.

6.

2.

5.

3.

2.

1.

W*******NC FORMAT FOR NUREG 1.21***

INDIAN POINT JULY-SEPT 1986 10 METER WIND SPEED & DIR.

WITH 61-10 METER DELTA T PASQUILL CLASS C WIND DIRECTION WIND SPEED (MPH) 01-03 04-07 08-12 13-18 19-24

>24 TOTAL N

3.

21.

0.

24.

N NE

2.

0.

4.

NE

4.

1.

0.

9.

ENE

1.

0.

1.

E

1.

0.

2.

ESE

?.

0.

2.

SE

2.

0.

2.

SSE

3.

0.

6.

S

9.

15.

0.

24.

SSIW

3.

4.

1.

0.

8.

S

1.

0.

2.

WSW

0.

1.

0.

O.

0.

W

3.

4.

0.

7.

0.

1N4

0.

2.

0.

2.

NNW

4.

3.

0.

7.

TOTAL

38.

61.

2.

0.

101.

CALM

0.

I,e

- - - - NRC FORMAT FOR HUREG 1.21******

INDIAN POINT JULY-SEPT 1986 10 METER MIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS 0 DIRECTION N

NNE NE ENE E

ESE SE SSE S

SSW SW NW III 01-03

11.

21.

34.

20.

5.

22.

13.

43.

15.

11.

12.

6.

2.

5.

04-07

77.

36.

22.

5.

6.

2.

0.

4.

86.

39.

3.

2.

8.

3.

8.

13.

08-12

7.

2.

0.

5.

4.

0.

1.

WIND SPEED (MPH) 13-18

0.

19-24

0.

>24

0.

TOTAL 256.

314.

21.

0.

CALIM 0.

TOTAL

95.

59.

56.

39.

26.

7.

22.

17.

134.

58.

14.

6.

11.

19.

591.

N*m*m***C FORMAT FOR NUREG 1.21*****

INDIAN POINT JULY-SEPT 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS E MIND DIRECTION 01-03

31.

52.

56.

26.

23.

19.

36.

31.

76.

55.

18.

9.

11.

10

19.

14.

04-07

41.

49.

38.

3.

2.

0.

2.,

95.

42.

3.

4.

6.

18.

08-12

0.

2.

1.

0.

WIND SPEED (MPH) 13-18

0.

19-24

0.

>24

0.

TOTAL 486.

310.

5.

0.

CALM 14.

TOTAL

72.

101.

94.

29.

25.

19.

36.

33.

173.

99.

22.

12.

15.

14.

25.

32.

S801.

- - - NRC FORMAT FOR NUREG 1.21 INDIAN POINT JULY-SEPT 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS F

.WIND DIRECTION 01-03 N

21.

NNE

32.

NE

43.

ENE

15.

E

17.

ESE

6.

SE

8.

SSE

12.

S

6.

SSW

4.

Sw

2.

NS

1.

W

2.

WNW

2.

I1

5.

1*1 2.

WIND SPEED (MPH) 04-07

2.

6.

24.

0.

1.

0.

TOTAL 178.

33.

08-12

0.

1.

0.

13-18

0.

19-24

0.

.0.

0.

1.

0.

CALM 4.

TOTAL

23.

38.

68.

15.

17.

6.

8.

12.

7.

4.

2.

1.

2.

5.

2.

212.

- - - - t#RC FORMAT FOR NUREG 1.21*****

INDIAN POINT JULY-SEPT 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS G WIND DIRECTION WIND SPEED (MPH) 01-03 04-07 08-12 13-18 19-24

>24 TOTAL N

2.

0.

2.

NNE

1.

0.

1.

NE

3.

0.

6.

ENE

1.

0.

1.

E

0.

ESE

1.

0.

1.

SE

0.

SSE

0.

S

2.

0.

2.

SSM

0.

SW

0.

WSW

0.

i

0.

WNW

0.

O

0.

I4

0.

TOTAL

10.

3.

0.

13.

CALM 0.

- - - - -NRC FCqMAT FOR NUREG 1.21-**

INDIAN POINT OCT-DEC 1986 10 METER WIND SPEED & DIR.

WITH 61-10 METER DELTA T PASQUILL CLASS A MIND DIRECTION WIND SPEED (MPH)

N NNE NE ENE E

ESE

.SE SSE S

SSW SW WSW NW H'A 01-03

1.

0.

3.

6.

1.

0.

1.

0.

1.

04-07

22.

0.

1.

0.

9.

16.

4.

8.

1.;

6.

11.

16.

12.

08-12

6.

0.

4.

5.

0.

1.

6.

2.

13-18

0.

19-24

0.

>24

0.

TOTAL

13.

106.

25.

0.

CALIM 0.

TOTAL

29.

0.

1.

0.

12.

26.

10.

8.

1.

8.

12.

22.

15.

144.

- - - - RC FORMAT FOR NUREG 1.21******

INDIAN POINT OCT-DEC 1936 10 METER WIND SPEED & DIR.

WITH 61-10 METER DELTA T PASqUILL CLASS B WI!D DIRECTION 01-03

0.

1.

4.

2.

0.

2.

0.

1.

2.

04-07

16.

1.

0.

1.

0.

2.

0.

2.

10.

2.

1.

0.

3.

4.

08-12

6.

1.

0.

1.

0.

5.

WIN"D SPEED (MPH) 13-18

0.

1.

0.

19-24

0.

TOTAL

14.

50.

19.

1.

0.

CALI 0.

TOTAL

22.

2.

0.

1.

0.

1.

3.

15.

5.

1.

2.

0.

4.

11.

15.

- - - - NRC FORMAT FOR NUREG 1.

INDIAN POINT OCT-DEC 1986 10 METER HIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS C WIND SPEED (MPH) 04-07 08-12 13-18 19-24

14.

6.

1.

0.

4.

0.

1.

0.

1.

0.

1.

0.

0..

0.

1.

0.

3.

0.

3.

1.

0.

1.

1,

0.

2.

3.

0.

2.

3.

0.

7.

5.

0.

TOTAL

28.

40.

19.

>24

0.

1.

0.

/

CAJ 0.

WIND DIRECTION 01-03 TOTAL

24.

5.

1.

2.

1.

0.

3.

8.

11.

1.

0.

3.

6.

16.

88.

- - - - NRC FORMAT FOR NUREG 1.21 INDIAN POINT OCT-DEC 1986 10 METER MIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS 0 WIN DIRECTION 01-03

45.

29.

19.

16.

8.

9.

i0.

14.

33.

28.

13.

8.

10.

4.

7.

14.

04-07 127.

91.

32.

13.

2.

0.

3.

2.

48.

13.

1.

4.

15.

21.

46.

47.

08-12

41.

26.

2.

0.

1.

0.

1.

5.

7.

28.

WIND SPEED (MPH) 13-18

8.

1.

0.

o.

4.

2.

4.

19-24

0.

>24

0.

TOTAL 267.

465.

139.

17.

0.

CALM-0.

TOTAL 221.

147.

53.

29.

10.

9.

13.

16.

81.

42.

14.

13.

30.

34.

83.

93.

888.

- - - - NRC FORMAT FOR NUREG 1.21******

INDIAN POINT OCT-DEC 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS E WIND DIRECTION N

NNE NE ENE E

ESE SE SSE s

SSW S14 WSW W

NW Nw NN 01-03

41.

59.

58.

17.

13.

22.

33.

60.

30.

23.

22.

18.

16.

14.

20.

04-07

26.

37.

28.

4.

1.

0.

2.

55.

17.

10.

4.

32.

19.

10.

08-12

0.

2.

o'

0.

1.

0.

1.

0.

4.

WIND SPEED (MPH) 13-18

0.

19-24

0.

0:

0.

TOTAL 463.

265.

15.

0.

CALM 0.

TOTAL

67.

98.

86.

22.

18.

14.

22.

31%

117.

47.

33.

27.

51.

35.

37.

34.

- - - - 14RC FORMAT FOR NUREG 1.21******

INDIAN POINT OCT-DEC 1936 10 METER WIND SPEED & DIR.

WITH 61-10 METER DELTA T PASQUILL CLASS F WIND DIRECTION 01-03

25.

47.

46.

13.

9.

0.

5.

6.

10.

6.

3.

6.

3.

2.

4.

11.

04-07

2.

4.

30.

2.

0.

2.

0.

08-12

0.

WIND SPEED (MPH) 19-24

0.

13-18

0.

.0.

>24

0.

TOTAL 196.

40.

0.

CALM 0.

TOTAL

27.

51.

76.

15.

9.

0.

5.

6.

12.

6.

3.

6.

3.

2.

4.

11.

236.

- - - - NRC FORMAT FOR t'.UEG 1.2***

INDIAN POINT OCT-DEC 1986 10 METER WIND SPEED & DIR. WITH 61-10 METER DELTA T PASQUILL CLASS G WIND DIRECTION 01-03

6.

3.

4.

1.

0.

1.

0.

1.

0.

1.

0.

2.

04-07

0.

1.

5.

0.

O.

08-12

0.

WIND SPEED (MPH) 13-18

0.

19-24

0.

TOTAL

19.

6.

0.

TOTAL

6.

4.

9.

1.

0.

1.

0.

1.

0.

1.

0.

2.

25.

CALM 0.

Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT G. OFFSITE DOSE CALCULATICN ',ANUAL CHANGES THIRD AND FOUR h QUARTERS, 1986

4 ODCM CHANGES SINCE JUNE 1986 NOTE:

"NO IMPACT" is to be interpreted as meaning no impact relative to offsite dose assessment or setpoint determination.

1.

==

Description:==

This fourth revision to the ODCM is a completely retyped version.

The overall format and content remains the same with the exception of the changes noted below and the equations in Chapters 3 and 4.

The equations in the body of the document are mathematically equivalent to those in the previous submittal, but the algebraic variables now employ the standard english alphabet as opposed to the many Greek symbols and subscripted references previously employed.

Justification: The purpose of this change was to increase readability and add administrative efficiency to reviewing and or future editing of the document.

The text was retyped so that the major sections could all be accessed utilizing one word processing system.

Impact:

No impact relative to offsite dose assessment.

2.

==

Description:==

Table 1-1 was updated to Indicate t hat the Gas Disposal System Monitor does have a setpoint which is used to ensure that the gas decay tank activity limit is not exceeded.

Justification:

Impact:

3.

==

Description:==

Justification:

Impact:

4.

==

Description:==

Justification:

This change is a correction to the previously submitted table.

Results in a more accurate summary of our effluent monitors.

There Is no impact on dose assessments or setpoInt determination.

The reference to continuous releases in Section 2.1.6 which appears in the last ODCM submittal is removed from this current revision.

This is a clarification which makes Section 2.1.6 more in agreement with the intent of 2.1.2 which refers to any radioactive waste.

No Impact.

The Service Water Radiation Monitor, R-16, is added to Section 2.1.13.

This change addresses the redundant monitoring capability for this system.

No impact.

Impact:

5.

==

Description:==

Justification:

Impact:

6.

==

Description:==

Justification:

Impact:

7.

==

Description:==

Justif ication:

Impact:

8.

==

Description:==

Justification:

Impact:

The definition of dilution flow in the discharge canal eliminates the statement "Unit 3 circulators only" In Section 2.2.5.

This change was necessary to make 2.2.5 consistent with 2.1.8 which discusses partitioning of full site dilution flow.

No impact.

Section 2.5.2 has been revised to indicate that 95% of the doses from liquid releases will be accounted for by using the backup dose methodology.

As a consequence the correction factor to account for the remainder of the dose is changed from 1.2 to I.I.

Thils method provides a more accurate hand calculation methodology which is still manageable without a

computer.

This change increases the accuracy of offsite dose calculations using the manual method for liquid releases.

Setpoint determination is unaffected.

Section 2.5.3 is corrected to include the silver bioaccummulation factors as indicated as well as a discussion of these factors.

(NOTE: This change was discussed in the 1984 ODCM Rev. 2 change package, Item No. 6.)

The Indicated text was inadvertently left out of the last revision.

This change is a

typographical correction.

Increased dose assessment accuracy, setpolnts are unaffected.

Sections 2.4.3 and 2.5.3 now include more reasonable bloaccumulation factors for Niobium.

The values are now 300 and 100 for fresh water fish and marine invertebrates respectively.

Table 2-1 Is also effected.

International Atomic Energy Agency Report No. 57 provides more recent data then that presented In Regulatory Guide 1.109 which was the original source of data for the bloaccumulation factors. A review of this document indicates that the R.G. 1.109 values are substantially over conservative and therefore the more recent IAEA information Is incorporated in this ODCM revision.

More accurate (ose assessment for liquid effluents with no impact on setpoints.

t

9.

==

Description:==

Justification:

Impact:

10.

==

Description:==

Justification:

Impact:

I].

Description:

Justification:

Impact:

12.

==

Description:==

Justification:

The previous gas activity value of 430 uCi/cc has been changed to 300 uCi/cc to ensure the maintenance of the 50,000 Ci limit'in the gas storage tank.

This affects Section 3.1.12.

This change considers the pressure relief valve which would allow pressurization of the tank.

Since a sample would be at atmospheric

pressure, the activity concentration is corrected for the maximum allowable pressure (valve release point).

This change eliminates the potential for under estimating total activity In the storage tank.

Section 3.3.13 is changed to include the proper design flow rate for ventillation of the Radioactive Machine Shop, 24,750 cfm.

Another set of fans (weld station fans at 3000 cfm each) are not routinely operated and the previous flow rate listed at 33,750 cfm included these fans.

Therefore, the correct flow rates to use are now indicated, normally 24,750 cfm without the weld station fans and 33,750 cfm if they are all operating.

This will increase the accuracy of any required offsite dose assessments should this release path become important.

This change will increase the associated setpoint.

Appendix B has been added to the ODCM to Include a discussion of detection limit application at Indian Point No. 3.

It includes both the critical level and lower limit of detection concepts.

The'RETS refers to lower limits of detection as defined in the ODCM.

This change incorporates the required section.

(Ref:

NUREG/CR-4007, "Lower Limit of Detection:

Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements".)

No impact.

The control function previously listed in Table 1-1 for component cooling monitors, R-17A and B, has been removed from the table.

The isolation of the surge tank vents from the atmosphere is not a RETS requirement and this function no longer applies to these monitors.

No impact.

I Impact:

13.

==

Description:==

Justification:

Impa ct:

14.

==

Description:==

Justification:

Impact:

15.

==

Description:==

Justification:

Impact:

16.

Descrip tion:

Justification:

The procedural information (in 2.3.4.2.a) relatIve-to recording tank information such as volume, times, etc.

has been deleted.

This Information is covered by plant procedure and is Inappropriate for inclusion In the ODCM.

No impact.

The Hot Lab tanks in the Administrat on Building have been deleted from Figure 2-1 and the component cooling system has been added.

Figure 2-1 is updated to properly reflect the release points identified in RETS Table 2.1-1.

No Impact.

Figure 3-1 was changed to correct the radiation monitor designations for the Radioactive Machine Shop and the Administration Building.

The proper designations for these monitors are RE 59 and RE 46 as indicated.

This represents a

typographical correction.

No impact.

The blowdown flash tank and condenser air ejector are removed from the description of release points in the last paragraph of Section 1.2.1.

This change clarifies the statement that the total discharge rate for all release points must remain less than the permissible discharge ra-te.

No impact, clarification only.

-Impact:

ML100290726

Text

Reference:

Description:

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