ML20148P383

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Effluent & Waste Disposal Semi-Annual Rept 890101-0630
ML20148P383
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 06/30/1985
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20148P290 List:
References
FOIA-97-207 NUDOCS 9707020215
Download: ML20148P383 (31)
v • d • e


Text

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Effluent and Waste Disposal Semi-Annual Report i

January 1 - June 30, 1985 Facility Indian Point 3 i

Licensee New York Power Authority l

1 This information is provided in accordance with the requirements of Regulatory Guide 1.21.

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

A.

Supplemental Information

'l 1.

Reculatory Limits Indian point J is presently subject to limits on radioactive waste reieases 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

'Iachnical Specification Requirements part II Raciological Environmental".

The percentages of the technicai specification liniits 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 methodoiogy stated in the off Site Dose Calculation Manual (ODCM).

The specific isotopes listed in Table 1C l

are used to determine the effective dose tactors for the time perloo.

b&c. :odines, Tritium and Particulates The quarterly organ dose limit for Iodine 131, tritium and particulates with half-lives greater than eight days is calculated in j

accordance with the methodology stated in the UDCM.

d.

Liquid Effluents The quarterly dose limit for liquid isotopic releases is calculated in accordance with the methodology stated in tne ODCM.

The iimit 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.

9707020215 970626 PER FOIA ELLIS97-207 PDR s

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t 3.

Averace Enercy 1

The average _ energies (E) of the racionuclide mixture in releases of fission ano activation gases were as follows:

ist Quarter 1.72E-1 MeV/ dis E = 7.24E-2 MeV/ dis E

=

T 2nd Quarter E{=s.94E-2McV/ dis 1.62E-1 MeV/ dis E

=

Y 4.

Measurements and Acoroximations 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 (baten release) the total activity dischargec is based on an j

isotopic analysis of each batch with tne 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 ar.alysis of containment air is i

performec monthly.

This analysis is used in conjunction with a process i

monitor to obtain the isotopic mixture and quantification j

of eacn pressure relief.

Isotopic analyses for eacn vapor containment purge are taken prior to and during tne purge.

This information is combined with the volume of air in each discharge to calculate the quantity of activity, from these disenarges.

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 tne process radiation monitor reacings to determine the quantity of activity from continuous discharges.

b&c. Iodines and Particulates 1

Iodine-131 and particulate releases are quantified by collecting a continuous sample at ventilation air on a TEDA impregnated activated charcoal cartridge and a glass-tiber tilter 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 cisenarged during the sampling period to calculate the quantity of activity disenarged.

For other iodine isotopes the concentration or eacn isotope is uet-ermined monthly on a 24-hour sample.

The concentration of tne isotopes found oy analysis is comoined with the volume of air discharged during the sampling period to calculate the quantity or activity discharged.

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Liquid Effluents

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i 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 comnined j

with information on volume discharged to determine the amount j

of each 1sotope discharged.

A 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.

5.

Batch Releases a.

Liquid

)

1985 ist Quarter 2nd Quarter Number of Batch Releases 44 62 i

Total Time Perioc Batch Releases (Min.)

11715 21483 Maximum "

640 520 Average "

266 262 Minimum "

105 160 l

Average Stream Flow (cis)

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Gaseous Numoer of Bate.1 Releases 7

la Total Time Feriod Batch Release (Min.)

787 9392 Maximum 305 6620 Average 112 645 Minimum 12 15 6.

Abnormal Releases i

a.

Liquid None b.

Gaseous None l

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7.0 Radiolocical Environmental Technical Soecitications 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 i

limitations in outdoor tanks.

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

Durir; 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).

In accordance with this requirement, Section E " Radiological Impact On Man" and Section F " Meteorological Data" will be submitted for the calendar year in the second semi-annual L

effluent release report of the year. Additionally, a new section,

?

Section G "Off Site Dose Calculation Manual Changes" has been included.

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i EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT B. GASEOUS EFFLUENTS j

FIRST AND SECOND QUARTER, 1985 1

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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTI > EST. TOTAL 1st 2~

ERROR %

A.

Fission & Activation Gases

1. Total release Ci 9.42E+2 3.78E+2 2.50E+1
2. Average release rate for period uCi/sec 1.21E+2 4.88E+1
3. Percent of techr.ical specification 1.12E+1 8.43E+0

{

ilmit.

B.

Iodines

1. Total lodine - 131 Ci 1.13E-5 8.66E-4 2.50E+1
2. Average release rate for period uCi/sec 1.45E-5 1.12E-4
3. Percent of technical specification 2.60E-2 1.84E-1 limit.

C.

Particulates i

1. Particulates with half-lives 28 days Ci 3.07E-5 4.1SE-5 2.50E+1
2. Average release rate for period uCi/sec 3.95E-6 5.31E-6
3. Percent of technical specification limit.

2.60E-2 1.84E-1

4. Gross alpna radioactivity Ci (4.03E-1

<4.40E-1 D.

Tritium

1. Total release C1 3.67E-1 4.74E-1 2.50E+1
2. Average release rate for period uC1/sec 4.72E-2 6.11E-2
3. Percent of technical specification 4

2.60E-2 1.84E-1 limit.

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Page 1 TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

GASEOUS EFFLUENTS-GROUND RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter

1. Fission Gases Krypton (Kr) 85 C1 6.36E-1 1.05E+0 1.81E-2 3.72E-1 Krypton (Kr) 85m C1 1.70E+1 1.26E+0 3.65E-3 Krypton (Kr) 87 C1 2.50E-3 1.69E-2 1.19E-3 4.84E-4 Krypton (Kr) 88 Ci 1.51E-2 9.11E-2 3.97E-3 Xenon (Xe) 133 C1 B.02E+2 1.61E+2 1.47E+0 1.82E+2 Xenon (Xe) 133m C1 1.11E+0 2.00E+0 2.64E-2 2.64E+0 Xenon (Xe) 135 C1 1.18E+2 2.27E+1 4.84E-2 1.75E+0 Xenon (Xe) 135m Ci Xenon (Xe) 138 Ci Xenon (Xe) 131m Ci 1.44E+0 1.08E+0 3.17E-2 2.83E+0 Argon (Ar) 41 Ci 1.01E-1 5.85E-2 Unidentified Ci TOTAL FOR PERIOD Ci 9.40E+2 1.89E+2 1.60E+0 1.89E+2 2.

Iodines iodine (I) 131 Ci 1.13E-4 S.66E-4 iodine (I) 133 Ci 7.27E-5 iodine (I) 135 Ci TOTAL FOR PERIOD Ci 1.13E-4 9.39E-4

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TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

GASEOUS EFFLUENTS - GROUND RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter 3 Particulates Antimony (Sb) 125 C1 1.30E-8 Cadmium (Cd) 109 C1 1.28E-7 5.71E-6 Cerium (Ce) 139 Ci 6.31E-7 Cerium (Ce) 141 C1 1.76E-7 l

Cerium (Ce) 144 C1 1.59E-6 5.71E-7 Cesium (Cs) 134 C1 2.25E-7 Cesium (Cs) 137 Ci 3.57E-6 6.23E-6 Cobalt

( 3) 57 Ci 9.70E-9 3.18E-8 Cobalt (Co) 58 Ci 7.81E-7 3.62E-6 Cobalt (Co) 60 C1 2.37E-5 2.42E-5 Iron (Fe) 55 C1 1.01E-7 3.14E-7 Niobium (Nb) 95 C1 7.49E-8 Ruthenium (Ru) 103 Ci 2.12E-7 i

Strontium LSr) 90 Ci 2.65E-8 Tin (Sn) 113 Ci 3.47E-7 I

TOTAL Ci 3.08E-5 4.15E-5

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Indian Point 3 1

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT C. LIQUID EFFLUENTS FIRST AND SECOND QUARTERS, 1985 1

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985) l LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 1st 2nd ERROR %

i A. Fission and activation products

1. Total release (not including tritium.

gases, alpha)

Ci 8.90E-2 9.92E-2 2.50E+1

2. Average diluted concentration during period uC1/ml 1.75E-10 1.84E-10 l
3. Percent of applicable limit 1.10E-1 2.18E-1 B. Tritium 1
1. Total release ci 8.66E+1 1.34E+2 2.50E+1 l
2. Average diluted concentration during period uCi/ml 1.70E-7 2.48E-7
3. Percent of applicable limit t

1.10E-1 2.18E-1 C. Dissolved and entrained gases

1. Total release ci 5.56E0 2.11E0 2.50E+1
2. Average diluted concentration during period uCi/ml 1.09E-8 3.91E-9
3. Percent of applicable limit 5.4SE-3 1.9EE-3 l

D. Gross alpha radioactivity 1

1. Total release Ci 44.70E-4

<1.58E-4 2.50E+1 i

E. Volume of waste release (prior to dilution) liters 8.00E+6 2.82E+6 1.00E+1 F. Volame of dilution water used during period liters 5.1CE+11 5.38E+11 1.00E+1 l

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Page 1 TABLE 2B LIQUID EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT CONTINU0tlS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter ist Quarter 2nd Quarter Antimony (Sb) 122 Ci 5.46E-5 1.17E-4 Antimony (Sb) 124 C1 4.86E-4 2.39E-4 Antimony (SD) 125 C1 2.72E-3 4.11E-3 Barium / Lanthanum 140 Ci 6.07E-5 Barium (Ba) 133 Ci 3.98E-6 5.36E-5 Cadmium (Cd) 109 C1 2.53E-4 Cerium (Ce) 139 Ci 7.63E-4 4.69E-4 Cer.um (Ce) 141 Ci 6.76E-6 Cerium (Ce) 144 Ci 1.04E-4 2.13E-4 Cesium

( L.- ) 134 C1 4.97E-4 1.06E-3 Cesium (Cs) 13C Ci 1.01E-5 Cesium (Cs) 137 Ci 1.99E-6 9.67E-4 3.38E-3 l

Chromium (Cr) 51 Ci 6.09E-4 3.49E-3 Cobalt (Co) 57 C1 1.85E-5 2.08E-5 7.26E-5 l

Cobalt (Co) 58 Ci 3.33E-4 3.57E-2 3.92E-2 Cobalt (Co) 60 Ci 6.19E-4 7.94E-6 7.16E-3 2.44E-2 l

l Iodine (I) 131 Ci 4.19E-4 2.27E-6 1.29E-3 4.72E-3 l

Iodine (I) 133 C1 2.69E-5 9.06E-5 5.96E-4 Iodine (I) 134 Ci 3.02E-4 2.90E-4 Iodine (I) 135 C1 2.23E-5 Iron (Fe) 55 Ci 2.91E-2 1.65E-2 Iron (Fe) 59 Ci 3.05E-4 4.11E-4 i

Mercury (Hg) 203 C1 2.36E-5 3.12E-6 1.04E-5

Page 2 TABLE 2B CONTINUOUS MODE BATCH MODE Nuclides Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Manganese (Mn) 54 Ci 3.39E-4 2.18E-3 Manganese (Mn) 56 C1 2.34E-6 1.42E-5 Molybdenum (Mo)99 Ci 5.05E-5 Nickel (N1) 63 C1 4.61E-3 2.64E-3 Copper (Cu) 64 Ci 4.45E-4 Lanthanum (La) 142 Ci 5.43E-6 Niobium

( 'b ) 95 Ci 8.78E-5 5.87E-4 Yttrium (Y) 88 C1 1.13E-4 Rubidium (Rb) 88 C1 1.43E-3 Ruthenium (Ru) 103 Ci 2.02E-5 Ruthenium (Ru) 105 Ci 2.27E-5 7.88E-5 Silver (Ag)110m Ci 2.75E-4 2.42E-3 Sodium

$Na) 24 Ci 1.34E-6 2.01E-5 Strontium (Sr) 85 C1 1.04E-5 1.59E-5

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Technetium (Tc)99m Ci 9.40E-6 2.92E-5 2.13E-4 Tin (Sn) 113 Ci S.42E-5 1.77E-5 Yttrium (Y) 91m Ci 1.57E-5 3.21E-6 1.20E-5 Zine (Zn) 65 C1 Zirconium (Zr) 9' Ci 2.31E-6 2.38E-6 t

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Page 3 TABLE 2B i

CONTINUOUS MODE BATCH MODE f

Nuclides Unit ist Quarter 2nd Quarter 1st Quarter 2nd Quarter Ruthenium (Ru) 106 Ci 9.59E-5 Tellurium (Te) 132 C1 2.75E-4 i

TOTAL FOR PERIOD 1.52E-3 1.22E-5 8.75E-2 9,66E-2' Xenon (Xe) 133 Ci 3.26E-3 5.54E0 2.0tE0 Xenon (Xe) 135 C1 2.07E-2 4. 541:- 2 l

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f EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT l

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FIRST FND SECOND i

QUARTERS, 1985 i

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1985 y SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

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

Unit 6 Month Period Est. Total 1.

Tvoe of Waste Class A Class B Error, %

j

a. Spent Resins, filter m

25.5 4.3 5.0E+1 sludaes, etc.

C1 28.7 9.6

b. Dry Compressible, m

0 0

N/A contaminated eauip. etc.

Ci 0

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c. Irradiated Components m

0 0

N/A I

Ci 0

0 j

d. Other m

0 0

N/A Ci 0

0 2.

Estimate of major nuclide composition (by type of war,te)

NUCLIDE UNIT CLASS A CLASS B j

a.

Mn-54 1.4 0

Fe-55 9.4 2.2 Co-58 S2.6 13.1 Co-60 20.9 7.6 Ni-63 S.2 2.9 Cs-134 3.5 26.2 Cs-137 7.0 48.0 1

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Solid Waste Disposition i

l Number of Shipments Mode of Transcort Destination l

5 Truck Barnwell, So. Carolina l

3 Truck Richland, Washington 4.

Centainers Shipped Class A Class B Container Number Solid. Mea g Number Solid. Media Pressure Vessel 23 none O

N/A High Integrity i

none 1

none Container Steel Liner 1

cement 0

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EFFLUENT AND WASTE DISPOSAL

[

SEMI-ANNUAL REPORT i

. E. RADIOLOGICAL IMPACT ON MAN FIRST AND SECOND QUARTERS, 1985 i

(To be submitted in next semi-annual report) l i

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Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT F. METEROROLOGICAL DATA FIRST AND SECOND QUARTERS, 1985 l

(To be submitted in next semi-annual report)

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-EFFLUENT AND naSTE DISPOSAL i

1 SEMI-ANNUAL REPORT 4

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G. OFFSITE DOSE CALCULATION MANUAL CHANGES f

FIRST AND SECOND j

-QUARTERS, 1985 i

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I Cffsite Dose Calculation Manual (ODCM) Chances Changes have been made to the ODCM since our last submittal.

Each change is described and justified separately.

These changes have been reviewed by the plant Operating Review Committee as required by Section 6.5 of Appendix A to the facility operating license. These changes have been effective since January 1, 1985.

i 1.

Description of Change:

With the enhanced capabilities afforded by computerization of dose assessments, the identified operational methodologies for both liquid and gaseous releases have been replaced with nuclide and organ specific dose calculations.

The previous methodology is maintained as a backup hand calculation method.

i The previously defined theoretical dose mennodology, enhanced to allow organ specific dose calculations, becomes the operational dose methodology. These sections are entitled " Dose Methodology (Computer Calculation)."

l The effects of the change are reflected in title changes to sections 2.4, 2.5, 3.3 and 3.4.

Tables 2-1, 3-1 and 3-3 were l

altered to include organ specific dose factors. Tables 3-1 and f

3-3 also replace table 3-11, 3-12, 3-13, 3-14, 3-15 and 3-16 t

which are deleted. To maintain sequential numocring, table 3-18 becomes 3-11.

l Justification for Change:

l The change allows a more complete and accurate dose cal-culation to be performed with less effort. The use of the computer j

should also reduce the number of errors in dose calculations.

i Impact of Change on Dose Assessments and Set point Determinations:

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Improved accuracy and reliability are the major results of this change. By determining the total dose for eacn organ, re-

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ported critical organ coses will be reduced.

previously tne critical organ doses cue to each nuclide were summed and reported.

Because the permissible discharge rates for gaseous releases are i

set through the use of the hand calculation technique, this change i

will have no impact.

For liquid releases, this change will have no impact on setpoint determinations.

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2.

Description of Change:

The finite cloud model which is weighted by the annual average percent occurrence of Pasquill categories is used for the cal-culation of air and whole body dose rates due to gamma emitting noble gas releases. Also effected is the splitting of site dose between Indian Point Units 2 and 3 for instantaneous release.

This change is addressed in the revision at attachment 4-1 of the ODCM which nas been re-numbered at Appendix 3-A and in section 3.6.

Sections 1.2.1, 3.3.1, 3.3.3, 3.4.1 and 3.4.3 and tables 3-4, 3-6, 3-8, 3-9 and 3-10 are effected by the change.

t Justification for Change:

The use of a semi-infinite cloud model overestimates the dose frot. or in a small plume, Because the site boundary is unusually short for the' Indian Point-3 reactor, the overestimate is particularly burdensome to plant operations.

Impact of Change on Dose Assessments and Set Point Determinations:

Permissible discharge rates for instantaneous noble gas re-leases are increased by approximately a factor of 2.

For in-ternally set discharge limits which are based on quarterly and annual dose limits, the increase in release limits is more often offset by another change to the ODCM (see changes #3 and #12).

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Description of Change:

The locations where time averaged doses are calculated for l

noble gas releases is changed from the nearest resident to the site boundary. The change effects sections 1.2.1, 3.3.3 and 3.4.3.

Tables 3-10a and 3-19, which contained nearest resident dose l

l factors,.are deleted.

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l Justification for Change:

1 A review of the Indian point-3 technical specifications j

identified an inconsistency in the ODCM approach to calculating j

l air dose rates at the nearest resident. The described change was necessary to rectify this inconsistency.

1 Impact of Change on Dose Assessmente and Set point Determinations:

Because of the increase in the X/Q resulting from moving'from the nearest resident to the site boundary, permissible discharge 1

rates calculated for quarterly and annual doses are decreased by approximate)y an order of magnitude.

Likewise, dose estimates for time averaged calculations are increased.

For instantaneous dose and set point calculations, there will be no impact from this change.

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4.

Description of change:

A bioaccumulation factor of 150 for cesium in invertebrates is assumed. The change occurs in sections 2.4.3 and 2.5.

Table 2-1 (Alt) values also includes this change.

Justification Ior Change:

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Previously, fresn water bicaccumulation factors for invertebrates were listed, however, as discussed in Section 2.4.1 of the ODCM, the Hudson River near IP-3 is brackish.

In addition, as outlined in our last ODCM submittal, a fish bioaccumulation factor of 150 is used which was based on site specific data for cesium bioaccumulation in fish.

Regulatory Guide 1.109 in Table A-1 lists an invertebrate bicaccumulation factor that is less than the value for fish in both the fresh and saltwater cases.

Therefore, there is no just1I1 cation for using an invertebrate value that exceeds the value for fish.

I Impact of Change On Dose Assessment ar.d Set Point Determinations:

Doses will be calculated on site specific data for cesium which should yield more representation doses. The net effect will be to lower the estimated doses relative to the last ODCM sub-mittal. Set points are calculated based on the MPCw and are not affected by this change.

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Description of Change:

With the exception of cesium (where site specific data exists), all invertebrate bioaccumulation factors have been changed 3

from fresh water to salt water factors, from Regulatory Guide 1.109.

Justification for Change:

Since the water near IP-3 is brackish, not fresh, we chose to select saltwater bioaccumulation factors for the invertebrates.

This is a conservative assumption for the radionuclides that are released most frequently and abundantly.

Impact of Change on Dose Assessment and Set Point Determination:

Calculated doses will be somewhat higher based on typical nuclide mix (e.g. Co-60, Co-58, Cr-51), out for some nuclides However,. based (e.g. Mn-54) doses will be lower with this change..

on typical nuclides discharged this will yield slightly higher doses.

Set points are not effected by this change because they are calculated based on MPCw.

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. Description of Change:

I Silver bioaccumulation factors were changed from 1.0 for fish and invertebrates to 2.3 and 3300 respectively.

Justification of Change:

No bioaccwmulation factor for silver is listed in Rev. 1 of f

Reg. Guide 1.109, Table A-1.

A value of 1.0 was listed in the The previous submittal because of lack of better information.

1 values listed above were obtained from ERDA publication 660 (March 1976), Oak 13dge National Laboratories and are included.in the most

)

recent ODCM revision in the interest of increased accuracy-since Ag110m is a potential component of IP-3 liquid releases.

Impact cf Change on Dose Assassment and Set Point Determinations:

This change increases the accuracy of the dose calculations for liquid releases and increases the calculated doses.

Se' point determination is not effected by this change.

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I 7.

Description of Change:

J What was the Operational Dose Methodology for liquids, is now the Backup Dose Methodology (Section 2.5).and was enhanced to in-l clude the invertebrate pathway as well as the fish pathway.

1 Justification for Change:

For more completeness, this pathway is included, even in the simplified calculations.

Impact of Change of Dose Assessments and Set Point Determinations:

Under normal operation, the hand calculations will not be used. However, when the need arises, dose estimates will be both higher and more accurate due to this change.

Set point de-i terminations are not effected.

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8.

Description of Change:

A correction factor of 1/0.9 is included in the equation for the simplified dose methodology.

This change is found in section 2.5.

i Justification for Change:

The correction factor accounts for dose which is caused by nuclides which are not considered in the calculation.

i Impact of Change on Dose Assessments and Set Point Determinations:

Under normal operation, tha h=nd calculations will not be

)

used.

However, when the need arises, dose estimates will be both higher and more accurate due to this change.

Set point deter-l minations are not effected.

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9.

Description of Changes:

For detemination of the instantaneous dose rates for rad-First, as ioiodines and particulates, two changes were made.

described in_the bases for the Indian point 3 RETS, only.the inhalation pathway will be considered.

Second, the child age

)

group (the critical age group for thyroid dose due to inhalation) will be assumed rather than the infant.

This change is found in As a result of the simplification the section is Section 3,3.2.

Information previously included in rearranged and shortened.

3.3.2.2, 3.3.2.b and 3.3.2.c is no longer useful and has

. sections been deleted.

Justification for Change:

A comparison of calculated doses indicated that even for a pure iodine release the dose to the infant due to inhalation, ground plane exposure and ingestion of cow milk from the nearest dairy is only slightly higher than the child dose due to Also, the bases for the RETS states, "These release rate limits also restrict, at all times, the corresponding thyroid J

inhalation.

dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year."

The change also greatly simplifies the calculations involved.

Impact of Change on Dose Assessments.and Set point Determinations:

The set point calculation for instantaneous releases is based Dose decreases by about 23% and the set points on I-131 only.

consequently increase by 23%.

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10.

Description of Change:

I In Section 3.4.4, which is the simplified method for time averaged dose at the nearest resident from iodines and par-ticulates.,.the' vegetation pathway is added, and the age group is changed to child.

(Change number 11 should also be consulted).

j Justification for Change:

Using the assumption of the ODCM regarding exposure points, doses to the child were calculated to exceed those to the infant. The basic reason for this is the zero usage factor for infant vegetation consumption.

Impact of Change on Dose Assessment and Set Point Determinations:

Higher and more accurate doses will be calculated using this methodology.

No change is expected to the set point determin-ations.

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11.

Description of Change:

Rather than add the time averaged iodine and particulate dose from cow milk taken at the nearest dairy to the calculated nearest resident dose; an imaginary secondary receptor is established at 5 miles in the worst meteorological sector. At this location, doses due to ecw-milk, inhalation, vegetation and ground plane deposition will be determined. 'The secondary receptor dose will be compared to the nearest resident dose and the largest value will be reported. This change effects sections 3.3.4 and 3.4.4.

Justification for Change:

This approach is more inline with NUREG 0133, page 30 which recommends the creation of an imaginary cow / receptor at 4.5-5 miles in the worst meteorological sector knen no real cow exists within 5 miles. Also, this methodology is more easily handled with the computerized dose assessment system that is being incorporated.

Impact of Change on Dose Assessments and Set point Determination:

This change will have no impact on set point determinations.

The impact on dose assessment will depend on the nuclide mix.

Assuming 1-131 to be the nuclide of concern, this will slightly increase the dose calculated compared to the previous methodology.

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' 12. Description of Change:

The X/Q meteorological dispersion parameter values have been increased by a factor of 2.2.

This effects the values of X/Q listed in chapter 3 of the ODCM; for example, the site boundary X/Q was 1.4E-5sm-3 and is now 3.0E-5sm-3.

This also effects the partitioning of allowable release rates between Indian Point 2 and 3 for instantaneous releases.

The ground plane deposition par-ameters were unaffected by this change.

Justification for Change:

An error in the computer run of the site meteorological data that generated the X/Q values for our previous ODCM submitted was detected and this prompted the above change. The error was significant enough to warrant re-calculation of allowable release rate limits based on the dose and dose rate limits specified in the RETS.

Impact of Change on Dose Assessment and Set Point Determinations:

i The net effect of this change is to cause calculated dose l

to be greater and associated set points to be lower due to the l

5 increase in X/Q values in this submittal over the previous submittal.

Refer to Section 1.2.1 for the allowable release rates.

Note that other factors have also been involved in changing these l

permissible limits.

(refer to ODCM changes 2, 3, 10, 11).

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13.

Description of Change:

The equation to convert annual dispersion or deposition parameters to short term parameters has been corrected, see Section 3.5.5.

Justification for Change:

The algebraic for.n of the equation was not correct due to a typographical error.

Impact of Change:

There was no impact because the numbers generated in the previous submittal were correct (i.e. the correct equation was employed).

Process Control Program (PCP) Chances There have been no revisions to the pCP since our last semi-annual report.

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