Text

Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters,1987 Including Annual Radiological Impact on Man for 1987
	ML20196F227
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/31/1987
From:	Capstick R; VERMONT YANKEE NUCLEAR POWER CORP.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	FVY-88-13, NUDOCS 8803020099
	Download: ML20196F227 (103)
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EFFLUENT AND W).3TE DISPOSAL SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS, 1987 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN FOR 1987 E

Vermont Yankee Nuclear Power Station 4436P,'4. 243 5

l I

ERRATA In the Vermont Yankee Effluent and Waste Disposal Semiannual Report covering the first and second quarters of 1987, the following corrections should be made:

Table 3:

The curie total in Section A.1.c should be changed from 1.18E+01 to 1.16E+04 4436R/4.243

TABLE OF CONTENTS Page 11 ERRATA...........................................................

1.0 INTRODUCTION

1 1.0 MET EORO LOG I C AL DATA..............................................

2 3.0 DOSE ASSESSMENT..................................................

3 3.1 Doses From Liquid Effluents................................

3 3.2 Doses From Noble Cases.....................................

3 3.3 Doses from Iodine-131 Iodine-133 Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days................................................

3 3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation..................................................

5 REFERENCES.......................................................

8 TABLES...........................................................

9 APPENDIX A - SUPPLEMENTAL INFORMATION..................................

A-1 APPENDIX B - LIQUID HOLDUP TANKS.......................................

B-1 APPENDIX C - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION...........................................

C-1 APPENDIX D - RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION...........................................

D-1 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.............

E-1 AP P END IX F - LAND U S E C EN SU S...........................................

F-1 APPENDIX G - PROCESS CONTROL PR0 GRAM...................................

G-1 APP ENDIX H - 0FF-SITE DOSE C ALCU LATION MANUAL..........................

H-1 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS.........................................

I-1

-111-4436R/4.243

LIST OF TABLES Number Title Page 1A Gaseous Effluents - Summation Of All Releases 9

1B Gaseous Effluents - Elevated Releases 10 1C Caseous Effluents - Ground Level Releases 11 1D Gaseous Effluents - Nonroutine Releases 12 1A Liquid Effluents - Summation Of All Releases 13 2B Liquid Effluents - Nonroutine Releases 14 3

Solid k'aste and Irradiated Fuel Shipments 15 4

Maximum Off-Site Doses and Dose Commitments to Members of l

the Public 16-17 5A to 5H Annual Summary of Upper Level Joint Frequency Distribution 18-25 i

-iv-4436R/4.243

VERMONT YANKEE NUCLEAR POWER STATION SEMIANNUAL EFFLUENT RELEASE REPORT JULY - DECEMBER 1987

1.0 INTRODUCTION

Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste for the second six months of the year, with data summarized on a quarterly basis. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 1987. Tables 5A through 5H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 1987.

Radioactive effluents reported in the Semiannual Effluent Report covering the first six months of the year were used to determine the resulting doses for the first half of 1987.

1 As required by Technical Specification 6.7.C.1 dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the "Vermont Yankee Nuclear Power Station Of f-Site Dose Calculation Manual" (ODCM). These dose estimates were made using a "Method II" analysis as described in the ODCM. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 1) and actual measured meteorological data recorded during the reporting period.

As required by Technical Specification 6.7.C.1.b, this rs, ort shall also include an assessment of the radiation doses from radioactive effluents to member (s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period no recreational activities inside the site boundary were permitted, and, as a result, no dose assessments are required.

Assessment of radiation doses (including direct radiation) to the likely most exposed real member (s) of the public for the calendar year for the purposes of demonstrating conformance with 40CFR190, "Envircumental Radiation Protection Standards for Nuclest Fows.r Operations." are also required to be 4436R/4.243

included in this report if the conditions indicated in Technical Specification 3.8.M.1, "Total Dose," have been exceeded during the year.

Since the conditions indicated in the action statement under Technical Specification 3.8.M.2 were not entered into during the year, no additional radiation dose assessments are required.

All calculated dose estimates for this reporting period are well below the dose criteria of 10 CFR Part 50, Appendix I.

Appendices B through H indicate the status of reportable items per the requiremetts of Technical Specifications 6.7.C.1 and 6.14.A.

1 1 4436R/4.243

2.0 METEOROLOGICAL DATA Meteorological data was collected during this reporting period from the site's 300-foot met tower located approximately 2,200 feet northwest of the reactor building, and about 1.400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (94 meters) and is designed to meet the requ!.rements of Regulatory Guide 1.23 for meteorological monitoring.

i l

X/Q and D/Q values were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model.

All dispersion factors have been calculated employing appropriate source i

configuration considerations, as described in Regulatory Guide 1.111 (Reference 1).

A source depletion model as described in "Meteorology and Atomic Energy - 1968" (Reference 2) was used to generate deposition f actors, assuming a constant deposition velocity of 0.01 m/sec. Changes in terrain elevations in the site environment were also factored into the nieteorological models. 4436R/4.243

3.0 DOSE ASSESSMENT 3.1 Doses From Liquid Effluents There were no routine or accidental liquid rel(ases from Vermont Yankee during 1986. As a result, no receiving water exposure pathways could contribute to any whole body or organ doses to individuals in unrestricted areas.

3.2 Doses From Noble Gases Technical Specification 3.8.F.1 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I.

By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.8.F.1 assures that the releases of radioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."

Dose estimates due to the release of noble gases to che atmosphere are typically calculated at the site boundary, and nearest resident in each of the sixteen principle compass directions, as well as the point of highest off-site ground level air concentration of radioactive materials, and for each of the milk animal locations located within five miles of the plant. However, since no noble gases were reported as being above their lower limit of detectability (LLD) for this reporting period, no gamma and beta air doses were determined.

3.3 Doses From Iodine-131. Tritium and Radionuclides in Particulate Form With Half-Lives Creater Than 8 Days Technical Specification 3.8.G.1 limits the organ dose to a member of the public from iodine-131, iodine-133, tritium and radionuclides in 4436R/4.243

.~.

4 c ' T.. n 7.

particulate form with half-lives greater than 8 days (hereafter called iodines

'5D % '[.

. ;x

[

and particulates) in gaseous effluents released from the site to areas at and L

=

beyond the site boundary to those specified in 10 CFR Part 50, Appendix I

hjh, (7.5 mrem per quarter, and 15 mrem per year).

By implementing the j [,. ' *;j.

V>

F i,

b requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.8.G.1

m.... t.s,.y 4

-kY' assures that the releases of iodines and particulates in gaseous effluents 1

~*

will be kept "as low as is reasonably achievable."

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g.

j Exposure pathways that could exist as a result of the release of Ph lodines and particulates to the atmosphere include external irradiation from g y )Y fi ',

y e-... Q.

activity deposited onto the ground surface, inhalation, and ingestion of fi.f' i r

. m, y."..g vegetables, meat and milk. Dose estimates were made at the site boundary and 3

o

" 4.,,,. j,4 pri nearest resident in each of the sixteen principle compass directions, as well j

M as all milk animal locations within five miles of the plant. The nearest 3 '.

e., $p _

t 4

[

resident and milk animals in each sector were identified by the most recent f

Annual Land Use Census as required by Technical Specification 3.9.D.

. - > M "M..f u

r..g Conservatively, a vegetable garden was assumed to exist at each milk animal

'.:'1 l pig.?1%

y and nearest resident location. Furthermore, the meat pathway was assumed to h4.\\

esist at each milk animal location. Doses were also calculated at the point

~

u.

of maximum ground level air concentration of radioactive materials in gaseous t Q'f y

effluents and included the assumption that the inhalation, vegetable garden, N,

and ground plane exposure pathways exist for an individual with a 100 percent Th Y&ps~k[

occupancy factor.

It is assumed that milk and meat animals are free to graze on open

%.,.f.-

E pasture during the second and third quarters with no supplemental feeding.

hc u.

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{

This assumption is conservative since most of the milk animals inventoried in

(;.<. '.,

tz a

k[h

$y. <h the site vicinity are fed stored feed throughout the entire year with only 4

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E limited grazing allowed during the growing season.

It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in

, k. d..

y: 2.y elemental form (I ) and is available for uptake (see p. 26, Reference 4),

fffT'M.

(

2 During the first and fourth quarters, the milk animals are assumed to receive E

only stored feed.

m M

- 4436R/4.243 W.c

The resultant organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bone, liver, kidney, thyroid, inng and skin for adults, teenagers, children and infants. The maximum estimated quarterly and annual organ doses to any age group due to iodines and particulates at any of the off-site receptor locations are reported in Table 4.

These estimated organ doses are well below the 10 CFR Part 50 Appendix I dose criteria of Technical Specification 3.8.G.I.

3.4 Whole-Body Doses in Unrestricted Areas From Direct Radiation The major source of dose, consisting of direct radiation and sky shine, from the station is due to N-16 decay in the turbine building.

Because of the orientation of the turbine building on the site, and the shielding effects of the adjacent reactor building, only the seven westerly sectors (SSW to NNW) see any significant tirect rediation.

High Pressure Ionization Chamber (HPIC) measurements have been made in the plant area in order to estimate the direct radiation from the station.

The chamber was located at a point along the west site boundary which has been determined to receive the maximum direct radiation f rom the plant. Using measurements of dose rate made while the plant operated at different power levels, f rom shutdown to 100 percent, the total integrated dose from direct radiation over each three month period was determined by considering the quarterly gross megawatts generated. Field measurements of exposure, in units of Roentgen, were modified by multiplying by 0.6 to obtain whole-body dose equivalents, in units of rem, in accordance with recommendations of HASL Report 305 (Reference 5) for radiation fields resulting from N-16 photons.

Another source of dose, including direct radiation and sky shine, to the site boundary is from low level radioactive waste temporarily stored in the north warehouse. The annual dose is based on a dose per unit curie of waste stored in the north warehouse and determined at the same most restrictive site boundary dose location as that for N-16 shine from the Turbine Building. 4436R/4.243

The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed on Table 4 for each quarter. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any structure.

. 4436R/4.243

g REFERENCES 1.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", U.S. Nuclear Regulatory Commission, Office of Standards Development March 1976.

2.

Meteorology and Atomic Energy, 1968, Section 5-3.2.2, "Cloud Depletion",

pg. 204. U. S. Atomic Energy Commission, July 1968.

3.

C. A. Pelletier, and J. D. Zimbrick, "Kinetics of Environmental Radioiodine Transport Through the Milk-Food Chain", Environmental Surveillance in the Vicinity of Nuclear Facilities, Charles D. Thomas Publishers, Springfield, Illinois, 1970.

4.

Regulatory Guide 1.109, "Calculation o' Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50 Appendix I", U. S. Nuclear Regulatory Commission.

Office of Standards Development, Revision 1, October 1977.

5.

W. M. Lowder, P. D. Raf t, and G. dePlanque Burke, "Determination of N-16 Gamma Radiation Fields at BWR Nuclear Power Stations" Health and Safety Laboratory, Energy Research and Development Administration, Report No.

305, May 1976. 4436R/4.243

E'

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't Vermont Yankee i

i Effluent and Waste Dispossi Semiannual Report

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Third and Fourth Quarters 1987 h

Gaseous Effluents - Summation of All Releases F

k F

Unit Quarter Quarter Est. Total A. Fission and Activation Gases 45*

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1. Total release Ci ND ND s1.00E+02 fi [.l?

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2. Average release rate for period uCi/sec ND ND

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+; '

3. Percent of Tech. Spec. limit (1) 1 l

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g.

M i-b B. Iodines g

Y

1. Total Iodine-131 Ci 8.89E-03 7.29E-05 5.00E+01 I t

2. Average release rate for period uCi/see 1.13E-03 9.27E-06 L

3. Percent of Tech. Spec._ limit (2) 5.13E+00 6.87E-02 lt f

C. Particulates e

1. Particulates with T-1/2 > 3 days Ci 8.99E-04 8.93E-04 25.00E+01

2. Average release rate for period uCi/see 1.14E-04 1.14E-04

3. Percent of Tech. Spee limit (3)

(3)

[

4. Gross alpha radioactivity Ci ND ND L

h D. Tritium

_K

1. Total release Ci 2.37E+00 4.03E+00 25.00E+01

)

2. Average release rate for peried uCi/see 3.01E-01 5.12E-01 j[

3. Percent of Tech. Spec. limit 1

(3)

(3) e 17 (1) Technical Specification 3.8.F.1.a for gamma air dose.

Percent values for Technical Specification 3.8.F.1.a not applicable since no noble gases were detected.

(2) Technical Specification 3.8.G.1 for dose f rou I-131,1-133 Tritium, and radionuclides in particulate form.

(3) Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulates are included with I-131 above in Part B.

{

ND Not Detected.

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Caseous Effluents - Elevated Release er (1)

E Continuous Mode Batch Mode i

i Nuclides Released Unit Quarter Quarter Quarter Quarter

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Krypton-85 Ci ND ND C

NMd F

Krypton-85m Ci ND ND i

Krypton-87 Ci NT)

ND l'

Krypton-88 Ci ND ND Xenon-133 Ci ND ND b

Xenon-135 Ci ND ND

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h Xenon-135m Ci ND ND Xenon-138 Ci ND ND p

Ci f

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f Iodine-131 Ci 8.89E-03 7.29E-05 5

Iodine-133 Ci 1.05E-03 4.50E-04 N:

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Iodine-135 Ci ND ND

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Total for period Ci 9.94E-03 5.23E-04

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3. Particulates Strontium-89 Ci 6.62E-05 2.75E-05 E-Strontium-90 Ci 2.47E-07 5.84E-07 f

Cesium-134 Ci ND ND h

Cesium-137 Ci 5.64E-05 6.64E-06 I

Barium-Lanthanum-140 Ci ND ND Cobalt-60 Ci 5.94E-05 7.35E-04

.4 a

E Manganese-54 Ci 1.09E-04 9.76E-05

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m.

Iron-55 Ci 2.18E-05 ND h

Zine-65 Ci 5.09E-05 2.60E-05 b

(1) There were no batch mode gaseous releases for this reporting period.

ND - Not detected at the plant stack.

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I TABl.E ID Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1987 Gaseous Effluents - Nonroutine Releases There were no nonroutine or accidental gaseous releases during the third or fourth quarters of 1987.

b 4436R/4.243

~

TABLE 2A Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1987 l

l Liquid Effluents - Nonroutine Releases i

I There were no liquid releases during the third or fourth quarters of 1987.

s 1 4436R/4.243

TABLE 2B Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1987 Liquid Effluents - Nonroutine Releases There were no nonroutine or accidental releases during the third or fourth quarters of 1987. 4436R/4.243

=

TABLE 3 Q

Vermont Yankee Effluent and Waste Disposal Semiannual Report

~~

Third and Fourth Quarters. 1987 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

,e i

Unit 6-Month Est. Total Period Error. %

1. Type of Waste

a. Spent resins, filter sludges, evaporator mJ 3.82E+01 bottoms, etc.

Ci 2.14E+02 27.50E+01 s.

b. Dry compressible waste, contaminated m3 1.11E+02 equipment, etc.

Ci 8.77E+00 27.50E+01

c. Irradiated components, control rods, mJ Ci etc.

2. Estimate of Major Nuclide Composition (By Type of Waste) i

a. Zine-65 1 3.00E+01

a. (Cont 'd) Hydrogen-3

% 1.05E-01 Cesium-137

% 1.97E+01 Iodine-127

% 7.00E-03 Cobalt-60

% 1.39E+01 Plutonium-241 % 3.00E-03 Cesium-134

% 1.35E+01 Trancort sics % 1.00E-03 Iron-55

% 1.01E+01 b.

Cobalt-60

% 5.28E+01 Manganese-54

% 6.75E+00 Iron-55

% 3.39E+01

?

Nickel-63

% 1.38E+00 Cesium-137

% 6.69E+00 Cobalt-58

% 1.25E+00 Manganese-54 % 2.31E-00 ~

7' Iron-59

% 8.93E-01 Hydrogen-3

% 2.94E-01 Nio)ium-95

% 6.18E-01 Cesium-134

% 2.59E-01 Technetium-99

% 4.73E-01 Cobalt-58

% 1.18E-01 Iodine-131

% 3.84E-01 Plutonium-241 % 6.00E-02 i

Zirconium-95

% 2.27E-01 Technetium-99 % 2.00E-02 e

Carbon-14

% 1.92E-01 Carbon _14

% 4.00E-03 Cesium-136

% 1.75E-01 Iodine-129

% 1.00E-03 Strontium-90

% 1.75E-01 Curium-242

% 1.00E-03

3. Solid Waste Disposition y

Number of Shipments Mode of Transportation Destination r

13 Truck Parnwell, SC r3 B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information

1) Class of solid waste containers shipped:

1A, 6B 1C, 5A (unstable)

2) Types of containers used: 8 Type A, 1 Type B 4 Strong-tight-container

3) Solidif ? cation agent or absorbent: %ne 4436R/4.243

\\

u

TABLE 4 Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1987 Maximum

Off-Site Doses and Dose Commitments to Members of the Publi.e Dose (mres)***

1st 2nd 3rd 4th Source Quarter Quarter Quarter Quarter Year **

Liquid Effluents (a)

Airborne Ef fluents Iodines and Particulates 2.50E-03 3.80E-02 3.85E-01 5.15E-03 4.31E-01 (1)

(2)

(3)

(4)

Noble Gases Beta Air (mrad) (b)

Gamma Air (mrad) (b)

Whole Body Dose from Facility Direct Radiation (arem) 6.64E+00 5.27E+00 1.79E+00 3.99E+00 1.77E+01 4

"Maximum" means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.

C*"Maximum" dose for the year is the sum of the maximum doses for each quarter.

This results in a conservative yearly dose estimate, but still well within the limits of 10CFR50.

C**The numbered footnotes indicate the location of the dose receptor, age group, and organ, where appropriate.

(1) Teen /GI-III, S-4000 meters.

(2) Infant / Thyroid, NW-4700 meters.

(3) Infant / Thyroid, NW-4700 meters.

(4) Teen /CI-III. NW-2900 meters. 4436R/4.243

TABLE 4 (Continued)

(c) There were no liquid releases during this reporting period.

(b) There were no detectable noble gases above the lower limit of detection for effluents released from the site during this reporting period.

I

-u-4436R/4.243

i l:

f.

i TABLE SA i

i I

W ONT YA* EE JAN37-IEC87 METE (RCLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS A CLASS FREQlENCY (PERCENT) =

.31 WIND DIRECTION FRCet L

SPEED (T14)

N PNE E ENE E ESE SE SSE S SW EM iG W

n' NW NNW M L TOTti C/U(

0 0

i (1)

.00

.Cc.Cc

.00

.Co f

(2)

.00

.CC

.($

.00

.00 j

i if 4.5k.0h 9.0h.0h.0h.0h.0h.0h.0h.0h.0h

.0

.0h 4.5h.0h.0h.

18.lb (2)

.01

.00

.03

.00

.01

.00

.0?

i t 7

'O O

0 2

0 0

1 0

0 0

0 3

(1)

.00

.00 9.09

.00

.00 4.55

.00 60

.00

.00 13.64 l

(2)

.00

.03

.00. 00

.01

.00

.(C

.00

.(c

.00

.04 ilf 4.5h.0h.0b.0h.0h 4.5h 4.5k 18.18 4.5h.0h.0h.0h.

.0h.0h.0h. $ 36.3f I

i (21

.01

.00

.01

.06

.01

.00

.00 00

.11

{

1 0

0 0

0 j

0 0

0 O

4 13-(18 4.55.00

.00

.00 4. 0

.00

.M 9.0)

.00 18.16 1)

(2)

.01

.00

.01

.00

.03

.00

.66 iff

.0h.0h.0h.0h.0h

.00 4.55.0h.0h.0h.0h.0h.0$.0h.0h 9.0f.0h 13 (2)

.00

.01

.00

.00 00

.00

.03

.($

.04 GT 24 0

_Q 0

0 0

0 (1)

.00

.00 (2)

.00

.C0 5

0 1

3 1

0 0

1 0

4 0

ALL SPEEDS 3

0 2

(1) 13.64

.00 9.09 9.0%

.00 4.55 13.64 22.7$ 4.55.00

.00

.00 4.55

.00 18.18

.00 100 M (2)

.04

.00

.03

.00

.01

.04

.07

.01

.00

.01

.00

.06

.00

.31 i

i1 00 C= CALM (WIND SPEED LESS THAN OR E@#L TO.M Ft0 I

i i

l i

_-,.-_.J

- ~ -

f TABLE 5B VEMONT YAWEE JANB7-DEC87 lETECRCLOGICAL DATA JOINT FREQUDCY DISTRIBUTION 297.0 FT WIM) DATA STABILITY CLASS B CLASS FREQlENCY (PERCST) =

.61 WIKD DIRECTION FR91 SPEED (FH)

N WE NE ENE E ESE SE $$E S SSW Sl WSW W M W N Wt T0141 CALM 0

0 0

0 0'

0 0

(

f1)

.00

.00 (2)

.00

.(c

.00

.Co C-3 0-1 0

0 0

1 0

0 1

0 0

3

.(1)

.00 1,72

.00

.00 1.72

.00

.00 1.72

.00

.00 5.17

-(2)

.00

.01

.00

.0)

.00

.01

.00

.01

.00

.(C

.(c

.04 0

0 4

0 1

0 0

0

.00 1.7h

.CA II) 1.72

.00

.00 3.4! 1,72

.0) 1.7h 1.7h

.00

'. 01 4-7 1

0 0

-0 0

6.90

.0) 13.97

.00

.01

.00

.01

.00

.06

.09

.15 (2) '.01

.00

.03 0

7

.00. 29.}31 8-12 4

1 0

0 1

1 0

2 0

0 0

0 6

(1) 6.90 1.72

.00

.00 1.72 1.72

.00 3.4$ 3.45

.00

.00 10.34 (2)

.06

.01

.00

.01

.00

.03

.00

.06

.00

.24 ib 1.7h 1.7h.0h.0h.0h.0$.0h.0h.0h 1.7h.0h.0h.0h 5.lf 1.7h 8.6!.0h 20.

(2)

.01

.00

.01

.00

.(0

.00

.04

.01

.07

.00

.!?

i f 1.7h.0h.0h.0h.0h.0h 1.7h.0h 1.7h.0h.0h.0h.0h 5.th 3.4h 12.0

.0h 25.h (2)

.01

.00

.01

.00

.01

.00

.04

.03

.10

.00

.21 GT 24 0

0 0

0 (1)

.00

.(0

.00

.(0 (2)

.00

.00.00

.00

.00 ALL SPEEDS 7

3 0

0 1

9 2

2 4

3 0

0 1

7 3

22 0

5?

(1) 12.07 5.17

.00

.00 1.72 5.1) 3.45 3.45 6.90 5.17

.00

.00 1.72 12.07 5.17 37.93

.00 1 E 00 (2)

.10

.04

.00

.01

.04

.03

.06

.04

.00

.01

.10

.04

.3!

.00

.61 (h

OD C= CALM (WIND SFEED LESS THAN CR E7.*L TO.60 PfW R. ;

TABLE Oq VEMONT YAEEE JAN87-DEC87 ETEm0 LOGICAL DATA J0!hT FREOLENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS C CLASS FREEENCY (FERCENT) = 2.19 WIND DIRECTION FRCM SPEED (FPH)

N mE NE ET E ESE SE SSE S SSW. Sl G W M NL' NW WR 10TE CALM

,Q 0

0 0

0' 0

0 0

0 6

0 0

(1)

.w

.00

.0)

.00

.00 (2)

.00

. 0).00

.0)

.00

.05 0

1 0

1 1

1 0

t 0

0 0

1.). !.00

.e4

.00

.64

.00

.64

.00

.CC

.00 00 00 5.13 C-3 1

(1)

.64 (2)

.01

.03 '.00

.01

.00

.01

.00

.01

.00

.(C

.11

.6k.0b.6k 1.2 2.5f 1.9$.6k.0h.0h.6k

.0

.0h 1.h 4.4

.0h 14.h 1.

1.2 (2)

.03

.01

.00

.01

.03

.06

.04

.01

.00

.01

.00

.03

.16

.06

.36 3

4 8

0 0

1 3

1 17 0

4 1.9}2 1.92 2.56 5.13 1.9}00

.00

.64 1.92

.64 10.00~.0) 34.62 8-12 8

1 1

1 0

(1) 5.13

.64

.00 (2)

.01

.00

.04

.06

.11

.04

.00

.0!

.04

.01

.24

.0)

.76 13-18 9

1 1

0 0

1 4

0 1

1 3

4 1

12 0

33 (1) 5.77

.64

.00

.0)

.00

.64 2.56

.00

.64

.64 1.92 2.56

.64 7.49

.00 24.36 (2)

.13

.01

.00

.C$

.00

.01

.00

.01

.04

.06

.01

.17

.00

.53 19-24 4

0 0

0 1

1 0

0 1

5 2

7 0

1 (1) 2.56

.00

.0)

.00

.64

.00

.64 3.21 1.28 4.49

.00 13.46 (2)

.06

.00

.01

.00

.01

.07

.03

.10

.CC

.29 GT 24 0

0 0

0 Q

i 2

5 0

9 (1)

.00

.0)

.00

.00 1. N 1.?8 3.21

.C0 5.77 (2)

.00

.09

.00

.(C

.00

.03

.07

.(4

.13

15. N 3.8h 1.9$ 1.2h.6k 3.8k 5.th 5.7$ 8 )$ 3.2!.6k 1.2h 3.2f 8 (2)

.34

.08

.04

.03

.01

.08

.11

.13

.20

.07

.01

.03

.07

.20

.67

.00 2.!'

h h

kPE0D C= CALM (WIND WEED LESS THAN @ ERCL TO.M Nm

-!p E

TABLE 5D VERMONT YASEE JANS7-DEC87 ETEOROLOO! CAL DATA JOINT FREQlENCY DISTRIBitTION 29700 FT WI W DATA STABILITY C1. ASS D CLASS FRERENCY (PDCENT) = 44.44 WIND DIRECTION FROM SPEED (fFH)

N l#E E EE E ESE

!E SSE S S93 93 IGl W WW W W WF 10 %

CALM 0

0 0

0 J

0 0

e

' (1)

.00

.00.00

.00

.(0

.00

.w 00

.00

-(2)

.00

.00-.00

.00

.(0

.C-3 38 22 28 22 18 27 45 21 21 5

3 7

14 9

16 28 0

3:4 (1) - 1.20

.69

.88

.69

.57

.85 1,42

.66

.16

.09

.22 44

.28

.51

.81

.(0 10.23-(2)

.53

.31

.39

.31

.25

.38

.63

.29

.07

.04

.10

.20

.13

.22

.39

.00

4. M 4-7 125 37 30 - 15 16 19 89 60 78 18 16 8

10 12 25 130 0

710

(!) 3.95 1.17

.95

.47

.57 1.13 2.81 1.97 2.46

.57

.51

.25

.32

.M

.79 4.10

.00 22.42 (2) 1.75.52

.42

.21

.25.55 1.25.64 1.09

.25.22.!!

.14

.17

.35 1,82.00

9. %

66 4

133 30 30 l'

48 78 58 189 0

10:7 41

.76 2.% 1.5}' 4.f6.h

.9$.3$ !.52 2.46 1.83 5.M

.f0 3A?7

'9 9

IS "4

(1) 6.28 1.86.b.23 8-12 199 (2) 2.79

.83

.36

.13

.18

.34

.Y3

.67 1.87

.42

.17

.67 1.0/

.61 2.65

.C0 14.54

'8 11; 87 20s 0

7= 1 18 201 16 2

2 6

5 7

2 50 12 7

131) 6.35

.51

.06

.19

.16

.22

.06 1,58.36

.22.15.68 3.57 2.75 6.57 00 23.7:

((2) 2.82

.22

.03

.08

.07

.10

.03

.70

.17

.10

.07

.39 1.59 1.22 2.92

.00

10. 52

1. h.0!.0b.0b.0b.0h

.0

.0b.h.0h.0h.0h.th 1.h.b 3

.0b (2)

.64

.03

.00

.01

.03

.00

.24

.01

.08

.51

.32 1.77

.00 3.37 9

46 0

44 GT24

'4 0

0 0

1 0

2 0

0 0

0

(!)

.76

.00

.03

.00

.04

.00

.;0

.00

.00.04}

.28 1.45 00 2.65 (2)

.34

.00

.01

.00

.04

.00

.01

.13

.65

.00 1.15

'ALL SPEEDS 647 136 66 49 55 9A 210 131 302 66 57 33 106 249 218 727 0

9167 (1) 20.43 4.29 2.72 1.52 1.74 3.03 6.63 4.14 9.54 2.08 1.80 1.04 3.35 7. % 6.89 22.96

. 0i K4.F (2) 9.08 1.91 1.21

.67

.77 1.35 2.95 1.64 4.24

.93

.00

.44 1.49 3.49 3.06 10.20

.00 44.44 Th OD C* CALM (WIND SPEED LESS THW OR ECUAL TO.60 r'N

. t i

k

TABLE SE VEMONT VMEE JAN87-DEC87 ETEOROLOGICAL DATA JOINT F1tERENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS E C1. ASS FREEENCY (PERCENT) = 36.!!

WIND DIRECTION FROM

- SPEED (WH) -

N ME NE ENE E ESE SE SSE S SW W WW W. WNW NW NW WL T01AL CALM 0

0 0

o-0 0

(1)

.00

.M

.00

.00. 00

.00 (2)

.0)

.00

.00. 00

.00

.Co C-3 71 45 12 Yr 48 44 38 25 23 16 7

11 - 11 91 48 0

519

-(1) 2.76 1.75 1.34 1.SO 1.32 1,67 1.71 1.48

.97

.M

.62

.27 43 43 1.30 1.87

.00 20.17 17 (2) 1.00

.63

.45 42

.55

.67

.62

.53

.35

.32.22

.10

.15

.44

.67

.00 7.2?

17 19 7

19 29 190 0

Bos

. J'.

4-7 196 r2 11 7

15 128 107 M

2

.66 74

.27 70 1.13 7.38

.(0 34.41 (1) 7.4.2 1.34 43

.27

.$8 1.M 4.47 4.16 2.57 (2) 2.75 45.15

.10

.21

.39 1.80 1.50

.93

.21

.24

.27

.10

.25

.41 2.67

.(6 12.42 I

5 h!.h.Ok

.0k

.1

.3!1.b 1.k 2.bh1.b.N.hh1.b 1.b 1.f 9b bh.0h 28 51 (2) 2.13

.28

.01

.M

.11 41

.51

.86

.38

.20

.29

.55

.53

.63 3.33.00 10.31 I

2.b

.0

.0h.0k.0h.0h.0h.kh 1. h.hh.0k.th.h2

.h 4 k 13N 1.

(2)

.97

.03

.00

.01

.03

.00

.03

.17

.38

.25

.0!

.07

.29

.60

.32 !.60

.00 4.81

.19-24 19 0

0 0

5 1

0 6

5 1

0 0

4 3

7 27 0

76 (1)

.74

.00

.19

.04

.00

.23

.19

.04

.00

.16

.12

.27 1.05

.0)

?.03 (2)

.27

.00

.07

.01

.00

. 03

.07

.01

.9)

.00

.06

.04

.10

.38

.(0 1.M GT 24 0

0 0

0 1

0 0

1 4

0 0

1 0

0 1

3 0

j3 (1)

.00

.04

.00

.(0

.1)

.16

.(0

.00

.04

.00

.04

.12

.00

. ;l (2)

.00

.01

.00

.04

.06

.00

.01

.0)

.00

.01

.04

.0)

.16 8'

l 134 623 0

5 73 3.16 4.j3 5.ft24.21

.00 Ik.(n 202 1 87 48 53

' (11 19.70 3.85 1.71 1.!2 2.57 3. % 7.89 7.85 7.88 3.33 1.87 2.06 ALL SFTED$

507 99 44 29 66 85 203 49 31 (2) 7.11 1.39

.62

.55

.93 1.19 2.85 2.83 2.64 1.22

.67

.74 1.15 1.59 1.88 8.74

.00 36.!!

fhf fk b h!h OD C= CALM (WIND SEED 1.ESS TidN CR EGA TO.60 WH)

TABLE 5F YENO(T YA*EE JIN87-DEC87 ETEORCLOGICAL DATA JOINT FREQVENCY DISTRIRITION 297.0 FT WI C DATA STABILITY CLASS F (LASS FRERENCY (PERCDIT) = 13.09 WIND DIRECTION FROM SPEED (fFH)

N ME E EE E ESE SE SSE

$ SSW SW WSW W IMW NW PE Wit 70f4 CALM 0

0 0

0 (1)

.00

.00.00

.00

.00.00

.00

.0)

.00 (2)

.00

.00 00

.00 5

3.h7 3 k 2.k 2.b 2.b 2.h 2.b 3.b 1.h 1.h 1.N.2f 1.bh 1.h 1.kf 3.h.$ 3b (2)

.52.39

.31

.32.29

.29

.34 41

.18

.!?

.03

.!4

.17

.21

. 39

.00 4.54 f

.8

.7f.6k 1.h 1.b2 5.h 5. k 3.$2 1.N 1.!b 1.0h.5k 1.h 2.b 8.fk.0b 44 5

7 (2) 1.00

.11

.10

.03

.17

.24

.73

.67

.44

.25

.15

.14

.07

.17

.32 1.14 00 5.76 I!

3.h

.08.08.08.0h.081.b 1.!k.5k

.7

.9$

.5

.75 1.h

.2$ 8. b.0h 20 $

(2)

.52

.00

.25

.15

.07

.10

.13

.07

.!O

.14

.0) 1.15

.00

.71 13-18 4

0 0

0 1

0 0

1 0

0 2

2 0

9 0

19 (1)

.43

.00

.00.00

.00

.00.11

.00

.21

.00

.96

. 0) 2.04 (2)

.06

.00

.01

.00

.01

.00

.03

,00

.13

.00

.27 l>24 0

0 0

0' 0

0 0

0 (1)

.00

.00.00

.00

.00 i

(2)

.00

.00 8' fi

.4.4.4.4.4.4.4.08.08.4.4.08.08.4.4.08.08

.e

(

(2)

.00

.0)

.00

.0)

.00

.00 l

ALL SFfEDS 149 36 29 29 33 27 95 88 49 39 32 17 24 36 40 200 0

933 (1) 15.97 3.86 3.11 3.11 3.54 3.I7 10.18 9.43 5.25 4.18 3.43 1.92 2.57 3.86 4.2921.44

.00 100. (<'

(2) 2.09

.51

.41

.41 46.52 1.33 1.23

.69

.55 45

.24

.34

.51

.56 2.81

.00

!?.0?

hl hb vlC FhTkhFEkiOD C= CJLM (WIND SFEED LESS TIM OF: EQUAL TO.60 MN

. i i

P

f:

n TABLE 5G VERMONT YAREE JANB7-DEC87 ETEOROLO)lCAL DATA JOINT FREQl.OCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS 0 CLASS FREQUENCY (PERCENT) = 3.05 WIND DIRECTION FRCH

-SPEED 0FH)

N NNE E ENE E ESE E SSE S S$W - W WW W IMI NW fM WFL

'OR.

CALM

'O O

O 0

0 0

r (1)

.00

.0)

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TABLE 5H VERMONT YAW EE JAN87-DEC87 ETEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTim

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.6 100 E R PAGE

'ATfm3 FOR THfI PERIOD C= CALM (WIND SFEED LESS THAN OR E0 VAL TO.60 r.%

bENTOFALL0000

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'AT 0NS FOR TH T CF ALL 0 0 0

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APPENDIX A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Third and Fourth Quarters, 1987 Fccility Vermont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporat. ion 1A.

Technical Specification Limits - Dose and Dose kate Technical Specification and Category Limit a.

Noble Gases 3.8.E.1 Total body dose rate 500 mrem /yr 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Gamma air dose 5 mrad in a quarter 3.8.F.1 Gaara air dose 10 mrad in a year 3.8.F.1 Beta air dose 10 mrad in a quarter 3.8.F.1 Beta air dose 20 mrad in a year b.

Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a year c.

Liquids 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 arem in a year 3.8.B.1 Organ dose 5 mrem in a quarter

(

3.8.B.1 Organ dose 10 mrem in a year A-1 4436R/4.243

2A.

Technical Specification Limits - Concentration

~

L l

Technical Specification and Catenory Limit a.

Noble Cases No MPC limits b.

Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days:

No MPC limits c.

Liquids 3.8.A.1 Total fraction of MFC excluding noble gases l

(10CFR20. Appendix B, 10 1

i Table II, Column 2):

3.8.A.1 Total noble gas concentration: 12E-04 uCi/cc I-i 3.

Average Energy l

Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.

a.

Average gama energy:

3rd Quarter 3.54E-01 MeV/ dis 4th Quarter 1.08E+00 MeV/ dis b.

Average beta energy:

Not Applicable 4.

Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or appreximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

A-2 4436R/4.243

I:

l~

L a.

Fission and Activation Cases Daily samples are drawn at the discharge of the air ejector.

Isotopic breakdown of the releases are determined from these samples. A logarithmic chart of the stack gas monitor is read daily to determine the gross release rate. At the very low release rates normally encountered during operation with the augmented off-gas system the error of release rates may be approximately 1100 percent.

b.

Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridge are removed weekly (if releases are less than 4 percent of the Tech Spec limit), or daily (if they are greater than 4 percent of the limit), and are analyzed for radioiodine 131, 132, 133, 134, and 135. The iodines found on the filter are added to those on the charcoal cartridge. The error involved in these steps may be approximately !50 percent.

c.

Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately 150 percent.

d.

Liquid Effluents Radicactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liquid effluents released.

For each batch, station records are retained of the total activity (mci) released, concentration (uci/ml) of gross A-3 4436R/4.243

p radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River Each batch of radioactive liquid effluent released is analyzed for gross gasuna and gansna isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is also analyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition to gamma spectroscopy.

There were no liquid releases during the reporting period.

5.

Batch Releases a.

Liquid There were no routine liquid batch releases during the reporting

period, b.

Gaseous There were no routine gaseous batch releases during the reporting period.

6.

Abnormal Releases a.

Liquid There were no nonroutine liquid releases during the reporting period.

b.

Gaseous l

There were no nonroutine gaseous releases during the reporting period.

l A-4 4436R/4.243 l

1 _

APPENDIX B LIQUID HOLDUP TANKS Requirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report per Technical Specification 6.7.C.1.

Res ponse t The limits of Technical Specification 3.8.D.1 were not exceeded l

during this reporting period.

l l

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APPENDIX C i

RADIOACTIVE LIQUID EFFLUENT NONITORING INSTRUMENTATION Requirement Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1.

If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3.9.1, an explanation in the next Semiannual Effluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7.C.1.

Risponse:

Since the requirements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, I

no response is required.

i 1

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C-1 j

4436R/4.243 i

r

APPENDIX D RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.2.

If inoperable gaseous ef fluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Semiannual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.1.

Response

Since the requirements of Technical Specification Table 3.9.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, t

no response is required.

1 I

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+

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APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.9.C.

With milk samples no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3, Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Reports (1) identify the cause(s) of the sample (s) no longer being available. (2) identify the new location (s) for obtaining available replacement samples and (3) include revised ODCM figure (s) and table (s) reflecting the new location (s).

R sponse:

All required milk samples were available during this reporting period.

E-1 4436R/4.243 l

- ~.

APPENDIX F LAND USE CENSUS Requirement: A land use census is conducted in accordance with Technical Specification 3.9.D.

With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report.

Rosponses No locations were identified by the 1987 land use census that would yield at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to Technical Specification 4.8.G.I.

j l

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l F-1 4436R/4.243 l

APPENDIX G PROCESS CONTROL PROGRAM Requirement: Technical Specification 6.12.A.1 requires that licensee initiated changes to the Process Control Program (PCP) be' submitted to the Consoission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.

Response

There was no licensee initiated change (s) to the Process Control Program during this reporting period.

I d

a T

9 G-1 4436R/4.243 i

x7- _ - - _ -

APPENDIX H OFF-SITE DOSE CALCU1ATION MANUAL Requirements. Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.

Response

There was one licensee initiated revision to the Off-Site Dose Calculation Manual during this reporting period which consisted of the following:

1. Section 4.0 (Environmental Monitoring) of the ODCM was revised in Revision 4 to reflect the following changes

a. The Turbine Building is now used as the reference point for the direct radiation monitoring (TLD) stations, aince, for 4

site boundary monitoring locations the greatest potential I

contribution of exposure that the TLDs may record during routine operation is due to direct or scattered radiation from N-16 decay in the turbine.

2. The ODCM was also revised in Revision 4 to reflect additional 3

changes in the gaseous dose and dose rate calculations. These changes are identified as follows:

4 l

a. The noble gas dose equations, dose conversion f actors for individual iodine, tritium, and particulate radionuclides.

1 description of bases for equations, effluent monitor setpoint i

equations, and example problem calculations were a:Nised for j

a more recent five year (1981-1985) period than originally l

developed for the CDCM.

i B-1 4436R/4.243

i l

b. The dose rate factors for iodine and particulate 3

l l

I radionuclides were also revised to change'the shielding I

factor from exposure to the ground plane from 0.7 to 1.0 to f

be consistent with the application of shielding factors for noble gas dose rate factors currently incorporated in the-ODCM.

c. The ground deposition factors (D/Q values) which are factored into the critical organ dose, and dose rate factors were i

revised to reflect a deposition velocity of 1 en/sec which

[

has become a "representative" value generally adopted by the

(

industry in recent years.

I

3. Page 5-22 of Revision 3, which was inadvertantly omitted from j

the Revision 3 package, is included in this report.

l 6

None of the above changes will reduce the accuracy or i

reliability of dose calculations or setpoint determinations.

The above changes have been reviewed by PORC and approved by the f

Manager of Operations. Revised ODCM pages reflecting the above changes are included as part of this appendix.

t

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1 i

t VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REV. sd i

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i T%e. Ac :.m w, 4e 5,..%

/h p t w,,, e e,

p fd ta '., M /

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Plant Oper*dtional Review Date i

Committee i

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Approved $v2 L-A 3 AAMs/ Jaloslgt

@antMSu5ger Oate t

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LIST - OF AFF ECTED P AGES PAGE REVISION-DA1E

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i v =

0 03/01/84 vi-vil 3

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1. P - 1. S O

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LIST OF AFFECTED PAGES (cont.)

PAGE REVISION DATE 5.10-5 to 4

12/30/87 5.15-5.16 3

12/09/86 5.17-5.13 4

12/30/87 5.19-5.22 3

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i Table 1.1-4 Summary of Methods to Calculate Dose Rates t

i Equation Reference Number Category Ecuation Section t

3-5 Total Body Dose Rate j

gmrem) = 0.70 h

DF8 3I i

i from Noble Gales tb yr g

Imrem' " [0

.5T 3.5.1 3-7 Skin Dose Rate DF, 1

g from Noble Gases skin yr g

.STP 3.6.1 3-16 Critical Organ Dose t

Rate from Iodines, R,(* 'r 3"L0

DFGlg, t

g 1

Tritium 1

and Particulates with l

T 1/2 Greater Than Eight Days 5

t o

i e

4 Revision 1 Date11/-e[37 Approved By D 4MA 1-8 5713R/20.74

i Table 1.1-5 Sumary of Methods to Calculate Doses to Air from Noble Gases Equation R2ference Number Category

[quation Section 3-21 Gama Dose to Air air (mrao. 0.022 Q

OFY 3*7'I ST Y

D from Noble Gases i

1 g

3-23 Beta Dose to Air 6

ST 0

3'8*I Dair (mrad) 0.019 Q

OF from Noble Gases i

1 g

l 4

l I

a

!*MN Revision H Date 1 f st?

Approved By i.,

5713R/20.74 1

Table 1.1-7 Summary of Methods for Setpoint Determinations Ecuation Reference Number Category Ecuation Section 5-1 Liquid iffluents:

Liquid Radwaste L

OF 5.1.1.1 R

I C

Discharge Monitor spt (CE8'

M

.,n l I

,g 3

(17/350)

Gaseous Effluents:

Plant Stack (RR-108-1A, RR-108-18) and A0G Offgas c;, stem (3127, 312 0 Loble Gas Activity Monitors tb 5.2.1.1 5-9 Total Body g

(com) = 716 59y p

5.2.1.1 5-10 Skin n (<pm) = 3000 Sg y 1

5.2.2.1 5-21 SJAE Noble Gas "SJAE (com) 1.6E+05 5 Activity Monitors spt 9y

i (17/150A, 17/1506)

Approved sy. M ' C \\ L h / -

Reeision a case 3

.n x

1-11 5713R/20.74

Table 1.1-10 Dose Factors Specific for Vermont Yankee for Noble Gas Releases Gamma Total Body Beta Skin.

Combined Skin Beta Air Gamra L'-

Dose Factor Dose Factor Dose Factor Dose Factor Dose Ta:::

3 3

3 DF0 (mrad-m ) DFJ(ma:

Radionuclide DFB, (mrem-m ) DFSg (mrem-m ' Ub (mrem-sec)

DCi-yr DCi-yr uCl-yr g

DCl-yr pCi-v Ar-41 8.84E-03*

2.69E-03 8.81E-03 3.28E-03 9.30E *3 Kr-83m 7.56E-08 1.49E-05 2.88E-04 1.93E-:E K ?-Tc 1.17E-03 1 16E-03 1.83E-03 1.97E-03 1.23E-:3 Kr-85 1.61E-05 1.34E-03 8.16E-04 1.95E-03 1.72E-:5 Kr-87 5.92E-03 9.73E-03 1.06E-02 1.03E-02 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.32E-02 2.93E-03 1.52E-::

Kr-89 1.66E-02 1.01E-02 1.94E-02 1.06E-02 1.73E-2 Kr-90 1.56E-02 7.29E-03 1.70E-02 7.83E-03 1.63E-0:

Xe-131m 9.15E-05 4.76E-04 4.06E-04 1.11E-03 1.56E-04 Xe-133m.

2.51E-04 9.94E-04 8.49E-04 1.48E-03 3.27E-:'

Xe-133 2.94E-04 3.06E-04 4.57E-04 1.05E-03 3.53E-0; Xe-135m 3.12E-03 7.11E-04 3.03E-03 7.39E-04 3.36E-?3 Xe-135 1.81E-03 1.86E-03 2.60E-03 2.46E-03 1.92E-:3 Xe-137 1.42E-03 1.22E-02 8.48E-03 1.27E-02 1.51E-03 Xe-138 8.83E-03 4.13E-03 9.60E-03 4.75E-03 9.2iE-03 1

8.84E 8.84 x 10-3 v bik Revision 4 Date it,Ae/c 7 Approved By h k i

/

G 1-18 5713R/20.74

Table 1.1-12 Dose and Dose Rate Factors Specific for Vermont Yankee for Iodines, Tritium and Particulate Releases Critical Organ Critical Organ Dose Factor Dose Rate Factor ico (*Ci )

DFG ' co (*yr*-uCi

~5' DFG i

Radlonuclide H-?

1.81E-04 5.70E-03 C-14 1.10E-01 3.47E+00 Cr-51 3.80E-03 1.32E-01 Mn-54 4.36E-01 1.72E+01 Fe-59 4.35E-01 1.44E+01 Co-58 2.26E-01 8.07E+00 Co-60 4.76E+00 2.12E+02 Zn-65 2.32E+00 7.51E+01 Sr-89 7.08E+00 2.23E+02 Sr-90 2.69E+02 8.48E+03 Zr-95 4.31E-01 1.42E+01 Sb-124 7.86E-01 2.63E+01 I-131 4.80E+01 1.51E+03 I-133 5.12E-01 1.61E+01 Cs-134 9.88E+00 3.28E+02 Cs-137 1.01E+01 3.44E+02 Ba-140 7.02E-02 3.27E+00 Ce-141 1.06E-01 3.37E+00 Ce-144 2.40E+00 7.60E+01 i

Approved By:hl L b J, 6 k-)u Revision 4 Date r /r /<: 7 1-20 5713R/20.74 l

r 5

factors, summing all the products together, and then multiplying this total by a conversion constant (0.70), as seen in the following Equation 3-5 (an example calculation is provided in Appendix A):

hf DFB (3-5) 0.70 R

9 tb i

3 gmrem)

(DCl-sec)

(g) (mrem-m )

3 sec pC1-yr yr C1-m where:

hf In the case of noble gases, the release rate from the plant stack (pC1/sec) for each radionuclide, "i", identified.

The release rate at the plant stack is based on the measured radionuclide distribution in the off-gas at the Steam Jet Air Ejector (SJAE) during plant operation when the activity at the stack is below detectable levels, and the recorded total gas effluent count rate from the Stack Gas Monitor I or II.

The release rate at the stack can also be stated as follows:

'SJAE S

L F

(3-28) hST g

39 I

{g5JAE i

(cpm) (pCi/cc) W sec cpm see Plant Stack Gas Monitor I or II count rate (cpm).

M

=

Appropriate or conservative plant stack monitor S

=

g detector counting efficiency for the given nuclide mix (cpm /(pC1/cc)).

Stack flow rate (cc/sec).

F

=

hyJAE The last measured release rate at the steam jet air ejector of noble gas 1 (pCi/sec).

Total body gamma dose factor (see Table 1.1-10).

OFBt l

!/

0 Revision l

Date, /

._-c Approved By e

/

3-15 5713R/20.74

Method I was derived from Regulatory Guide 1.109 as follows:

k E+06 5

[X/Q)Y h

DFB (3-6)

=

tb 7

3 1

3 (sec) gg) gmrem-m )

g e

(mremy g

yr pC1)

( )

,3 sec pC1-yr where:

Shielding factor = 1.0 for dose iate determination.

S p

Maximum annual average gamma atmospheric dispersion factor

[X/Q)Y

=

3 6.98E-07 (sec/m )

=

Qf Release rate from the plant stack of noble gas "1" (pC1/sec).

=

Gamma total body dose factor, (

).

See Table 1.i-10.

DFB,

=

y l

Equation 3-6 reduces to:

hf DFB k

0.70 I

(3-5)

=

tb 1

3 (mrem)

(DC1-sec)

(g) (mrem-m 3

sec pCi-yr yr Cl-m The selection of critical receptor, outlined in Section 3.10, is inherent in Method I, as are the maximum expected off-site annual or long-term average atmospheric dispersion factors.

Due to the holdup and decay of gases allowed in the A0G, off-gas concentrations at the plant stack during routine plant eperations are usually too low for determination of the radionuclide mix at the plant stack.

It is then conservatively assumed that most of the noble gas activity at the plant stack is the result of in-plant steam leaks which are removed to the plant stack by building vontilation air flow, and that this air fice has an isotopic distribution consistent witn that routinely measured at the SJAE.

Revision ;f Date

/. /4 7 Approved By b

\\,

Ni i

I 3-17 1

5713R/20.74

reduce to a value of 1, and the combined skin dose factor DF'g for Xe-133 (4.57 E-04 mrem-sec/pCl-year) is used in Equation 3-7.

Alternately, a relative radionuclide "1" mix fraction (f ) may be taken from Table 5.2-1 as g

a function of time after shutdown, and substituted in place of the ratto of eachh5AE tothesumofallhSJAE in Equation 3-28 above to determine the relative fraction of each noble gas potentially available for release to the total (example calculations can be found in Appendix A).

Just prior to plant s9artup before a SJAE sample can be taken and analyzed, the monitor alarm setpoints should be based on Xe-138 as representing the most prevalent high dose factor noble gas expected to be present shortly after the plant returns to power. Monitor alarm setpoints which have been determined to be conservative under any plant conditions may be utilized at any time in lieu of

(

the above assumptions.

Equation 3-7 can be applied under the following conditions (otherwise, l

justify Method I or consider Method II):

l 1.

Normal operations (not emergency event), and l

2.

Noble gas releases via the plant stack to the atmosphere.

3.5.2 Basis For Method I Tile methods to calculate skin dose rate parallel the total body dose i

ra9e methods in Section 3.4.3.

Only the differences are presented here.

Method I may be used to show that the Technical Specification which limits skin dose rate from noble gases released to the atmosphere (Technical l

Specification 3.8.E.1) has been met for the peak noble gas release rate.

Method I was derived from Regulatory Guide 1.109 as follows:

S D

l.11 S D

+ 3.17E+04 Og (X/03 DFS (3-8)

F tr g

Approvee8hADsA<>w Revision 9 Date :

7 r

3.,,

5713R/20.74

3 (aremy g) ( ) gmrad)

(Ci-sec)

CJ g DCi-yr g

mrem-m )

,3 ) gpC1-yr yr yr yr where:

Average ratio of tissue to air absorption coefficients will 1.11 convert mrad in air to mrem in tissue.

3.17E+04

'Q-(X/Q)

DF Y (3_g)

D

=

g tr g

i 3

gerad) gCi-see)

(C1) g pC1-yr g mrad-m

,3 ) pCi-yr yr yr D

(X/Q)Y (X/Q)

(3-10)

/

noa Dfinite =

air 3

Imrad' Imrad} I iec' see m

yr yr

,3 31.54 hST (3-11) and O

=

g (C_1 ) gCi-sec) gg) yr pCi-yr sec it I*II I 1E+06 (X/0)Y h

DF{

(3-12) so skin F

1 3

( )

( ) (b) (E)

($) (mrad-m )

( *yr *)

pCi

,3 sec PCi-yr 1E+06 X/Q hf

DFS,

+

1 3

see uC1 mrem-m )

gg) g C1

,3 sec pCi-yr substituting L

6.98E-07 sec/m3 CX/Q]Y

=

5.99E-07 sec/m3 X/Q

=

[ bt i N N

l 1

Revision N Date~1/i<;/57 ApprovedBy:b

//6 v

3-22 5713R/20.74

Shielding factor 1.0 for dose rate determinations SF hfT hfT DF{

DFS (3-13) 0.60 0.77 gives R

+

g skin i

i 3

3 g

y (DCi-sec-mremygg) gmrem-m )

goci-sec)(fi,) gmrem-m )

mrem l

3 sec pC1-yr 3

sec pCi-yr Cl-m yr Ci-m -mrad hf(0.77DF{+0.60DFS)

(3-14) g i

define DFj-0.77DF{+0.60DFS (3-15) g DF (3-7) then R

skin g

1 (mrem) gg) gmrem-sec) yr see pCi-yr The selection of critical receptor, as outlined in Section 3.10 is inherent in Method I, as it determined the maximum expected off-site atmospheric dispersion factors based on past long-term site-specific meteorology.

3.5.3 Method II If Method I cannot be applied, or if the Method I dose exceeds the limit, then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable.

The base case analysis, documented above, is a good example of the use of Method II.

It is an acceptable starting point for a Method II analysis.

Analyses requiring Method II calculations should be referred to YNSD to be performed and documented.

J f

3-23 5713R/20.74

5 Sec21or. 3.9 as follows:

k Q DFG (3-17)

=

eo g

igo

( *]*)

(mrem)

(C1) applying the conversion factor 31.54 (Ci-sec/pCl-yr) and converting Q to h in pCl/sec as it applies to the plant stack yields:

k 31.54 hSTP DFG (3-18) en jeg i

(p_C1 ) (mrem) l gmrem)

(Cl-sec)

C yr pCl-yr sec C1 l

Eq. 3-18 1s rewritten in the form:

k, h

DFGjg, (3-W g

(pC1) (mrem-sec)

C gmrem) yr sec pCi-yr OFG'gg, incorporates the conversion constant of 31.54 and has assumed that the shielding factor (S ) applied to the direct exposure pathway from p

radionuclides deposited on the ground plane is equal to 1.0 in place of the 5 value.of 0.7 assemed in the determination of DFG for integrated 7

gen doses over time.

The selection of a critical receptor (based on the combination of exposure pathways which include direct dose from the ground plane, inhalation, and ingestion of vegetables, meat, and milk) which is outlined in Section 3.10 is inherent in Method I, as are the maximum expected off-site atmospheric dispersion factors based on past long-term site-specific meteorology.

Should Method II be needed, the analysis for critical receptor critical pathway (s) and atmospheric dispersion factors may be performed with actual meteorologic and latest land use census data to identify the location of those pathways which are most impacted by these type of releases.

Revision ~!

Date :. /

-c. n -

Approved B b.

l 3-26 1

5713R/20.74

3.7 Method to Calculate the Gamma Air Dose from Noble Gases Technical Specification 3.8.F.1 limits the gamma dose to air from noble gases at any location at or beyond the site boundary to 5 mrad in any quarter and 10 mrad in any year.

Dose evaluation is required at least once per month.

Use Method I first to calculate the gamma air dose for the plant stack releases during the period.

Method I applies at all dose levels.

Use Method II if a more accurate calculation is needed.

3.7.1 Method I The gamma air dose from plant stack releases is:

T 0,Jr=0.022 4._

Q 0FJ (3-21) g 1

(mrad) (pCi-yr)

(C1) (*#8d-* )

3 Ci-m pCl-yr where:

total noble gas activity (Curies) released to the atmosphere via O

=

g the plant stack of each radionuclide "i" during the period of interest.

DF{=gammadosefactortoairforradionuclide"1".

See Table 1.1-10 Equation 3-21 can be applied under the following conditions (otherwise justify Method I or consider Method II):

1.

Normal operations (not emergency event), and 2.

Noble gas releases via the plant stack to the atmosphere.

7 g,,

Revision 4 Date i.

.. /c 3 Approved By: y O S re(M j' 3-28 5713R/20.74 l

l

3.7.2 Basis for Method I Method I may be used to show that the Technical Specification which limits off-site gama air dose from gaseous effluents (3.8.F.1) has been met for releases over appropriate periods.

This Technical Specification is based on the Objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated annual gama air dose at unrestricted area locations.

Exceeding the Objective does not imediately limit plant operation but requires a report to the NRC.

For any noble gas release, in any period, the dose.is taken from Equations B-4 and B-5 of Regulatory Guide 1.109 with the added assumption that Ofinite = 09 X/0)Y (X/Q):

/

D

= 3.17E+04 [X/Q)Y Q

DF{

(3-22) ar g

1 (f

3

) (sec/m )

(Ci) (*'

}

(mrad) r-chere:

(X/Q)Y = maximum annual average gama atmospheric dispersion factor 3

~

= 6.98E-07 (sec/m )

O

- number of curies of noble gas "1" released g

chich leads to:

0.022 Qg DF{

(3-21)

D

=

ar 1

(mrad)

(DC1-

)

(C1) (

)

Ci-m The main difference between Method I and Method II is that Method II could allow the use of actual meteorology to determine (X/Q)Y rather than use the maximum long-term average value obtained for the years 1981 to 1985.

1 Approved By 1 @ -\\ !'blu (

Revision M Date - -;

7 e

3-29 5713R/20.74

l 3.8 Method to Calculate the Beta Air Oose from Noble Gases Technical Specification 3.8.F.1 limits the beta dose to air from noble gases at any location at or beyond the site boundary to 10 mrad in any quarter and 20 mrad in any year.

Oose evaluation is required at least once per month.

Use Methoc4 I first to calculate the beta air dose for the plant stack releases during the period.

Method I applies at all dose levels.

Use Method II if a more accurate calculation is needed or if Method I l

cannot be applied.

l 3.8.1 Method I The beta air dose from plant vent stack releases is:

0.019 Qg Off Ofir (3-23)

=

1 (C1) (*

)

[)

~

(mrad)

(

there:

OF. beta dose factor to air for radionuclide "i".

See Table 1.1-10.

Q

= tcital noble gas activity (Curies) released to the atmosphere via g

the plant stack of each radionuclide "1" during the period of interest.

Equation 3-23 can be applied under the following conditions (otherwise justify Method I or consider Method II):

1.

Normal operations (not emergency event), and 2.

Noble gas releases via the plant stack to the atmosphere.

\\f m

A Revision 'l Date : '.

/e ?

Approved By: d b k V ht

/*

3-31 5713R/20.74

3.8.2 Basis for Method I This section serves three purposes:

(1) to document that Method I compiles with appropriate NRC regulations, (2) to provide background and training information to Method I users, and (3) to provide an introductory user's guide to Method II.

The methods to calculate beta air dose parallel the gamma air dose methods in Section 3.7.3.

Only the differences are presented here.

Method I may be used to show that the Technical Specification which limits off-site beta air dose from gaseous effluents (3.8.A.1) has been met for releases over appropriate periods.

This Technical Specification is based on the Objartive in 10CFR50, Appendix I, Subsection B.1, which limits the estimated annual teta air dose at unrestricted area locations.

Exceeding the Objective does not immediately limit plant operation but requires a report to the NRC within 30 days.

For any noble gas release, in any period, the dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109:

DFf (3-24)

D

= 3.17E+04 X/Q /_,

0 r

9 1

3 (mrad)

(Cl-sec) (m)

(gg) (mrad-m )

DCi-n 3

pCi-yr m

substituting X/Q. Maximum annual average undepleted atmospheric dispersion factor.

3 5.99E-07 sec/m

!/o k

.Ls b

1.-

Revision li Date ; ; e.- /.J 7 Approved By 3-32 5713R/20.74

E We have 0.019 Qg DFf (3-23)

D tr 1

d

[)

(C1) (

)

(mrad)

(

3.8.3 Method II If Method I cannot be applied, or if the Method I dose determination indicates that the Technical Specification limit may be exceeded, or if a more exact calculation is required, then Method II may be applied. Method II c@nsists of the models, input data and assumptions in Regulatory Guide 1.109, Ree. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented.

j 3-33 i

5713R/20.74

1 the conservative margin to the calculation of critical organ dose in Method I.

Method II allows that actual individuals, with real behaviors, be taken into account for any given release.

In fact, Method I was based on a Method II analysis of the critical receptor for the annual average conditions. For purposes of complying with the Technical Specifications 3.8.G.2 maximum long term (five years) average atmospheric dispersion factors are appropriate for batch and continuous releases.

That analysis was called the "base case"; it cas then reduced to form Method I.

The base case, the method of reduction, and the assumptions and data used are presented below.

The steps performed in the Method I derivation follow.

First, in the ba:e case, the dose impact to the critical receptor in the form of dose factors (mrem /C1) cd I curie release of each I+P radionuclide to gaseous l

effluents was derived.

Then Method I was determined using simplifying and further conservative assumptions.

The base case analysis uses the methods, data and assumptions in Regulatory Guide 1.109 (Equations C-2, C-4 and C-13 in Reference A).

Tables 3.9-1 and 3.9-2 outline human consumption and environmental parameters used in the analysis.

It is conservatively assumed that the critical receptor lives at the "maximum off-site atmospheric dispersion factor location" as defined in Section 3.10.

However, he is exposed, conservatively, to all pathways (see Section 3.10).

The resulting site-specific dose factors are for the maximum organ and the age group with the highest dose factor for that organ.

These critical organ, critical age dose factors are given in Table 1.1-12.

For any gas release, during any period, the increment in annual average dose from radionuclide "1" is:

ADggo = Qg DFG (3-2O gen there DFG is the critical dose factor for radionuclide "1" and Q is 3o g

the activity of radionuclide "1" released in curies.

d]

wk Revision -i Date 1 / :- k7 Approved By

~

i l

3-36 5713R/20.74

Environmental Parameters for Gaseous Effluents at V;.rmont Yankm (Deriv:d from Refcrcnco A)

Vegetables Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored 2

YV Agricultural (Kg/M )

2.

0.70 2.

l Producttvity 2

P Soll Surface (KG/M )

240.

Density T

Transport Time (HRS) 48.

48.

480.

to User TB Soll Exposure (HRS) 131400.

131400.

Time l

TF Crop Exposure (HRS) 1440.

1440.

720.

1440.

720.

1440.

720.

1440.

Time to Plume TH Holdup After (HRS) 1440.

24.

O.

2160.

O.

2160.

O.

2160.

Harvest QF Animals Daily (KG/ DAY) 50.

50.

6.

50.

Feed FP Fraction of Year 0.50 0.50 0.50 on Pasture FS Fraction Pasture 1.

1.

when on Pasture FG Fraction of Stored 0.76 Veg. Grown in Garden FL Fraction of Leafy 0.50 Veg. Grown in Garden FI Fraction Elemental Iodine - 0.5 3

H Absolute Humidity = 5.6 (qm/M )

k gv[v L s Revision Date l

'7,., f

/

I

.t R Apl i oveil l>'

.t g

5/I3R/.'o.74

l 3.10 Receptor Points and Annual Average Atmospheric Dispersion Factors for Important Exposure Pathways The gaseous effluent dose methods have been simplified by assuming an individual whose behavior and living habits inevitably lead to a higher dose than anyone else.

The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:

1.

Direct exposure to contaminated air; 2.

Direct exposure to contaminated ground; 3.

Inhalation of air; 4.

Ingestion of vegetables; 5.

Ingestion of cow's milk; and 6.

Ingestion of meat.

Section 3.10.1 details the selection of important off-site locations and reeeptors.

Section 3.10.2 describes the atmospheric model used to convert me%eorologic data into atmospheric dispersion factors.

Section 3.10.3 presents the maximum atmospheric dispersion factors calculated at each of the off-site receptor locations.

3.10.1 Receptor Locations Three important receptor locations are considered in the dose and dose rate equations for gaseous radioactive effluents.

They are:

1.

The point of maximum gamma exposure from an over5ead noble gas cloud; Approved By b h

\\ [a h Revision i

Oate t;/; -/c /

/

(

3-40 5713R/20.74 1

2.

The point of maximum ground level air concentration and deposition of radionuclides.

The point of maximum gamma exposure (S sector, 400 meters) was determined by finding the maximum five-year average gamma X/Q at any off-site location.

The location of the maximum ground level air concentration and deposition of radionuclides (NH sector, 2900 meters) was determined by finding the maximum five-year average depleted X/Q and D/Q at any off-site location.

For the purposes of det2rmining the Method I dose factors for iodines, 1

tritium, and particulates, a milk animal was assumed to exist at the location Cf highest calculated ground level air concentration and deposition as noted above. This location then conservatively bourds the deposition of l

radionuclides at all real milk animal 'ocations.

1 3.10.2 Vermont Yankee Atmospheric Dispersion Model The annual average atmospheric dispersion factors are computed for routine (long-term) releases using Yankee Atomic Electric Company's (YAEC)

AEOLUS Computer Code (Reference B).

AEOLUS is based, in part, on the straight-line airflow model discussed in Regulatory Guide 1.111 (Reference C).

The valley in which the plant is located is considered by the model.

AEOLUS produces the following annual average atmospheric dispersion fac% ors for each location:

l 1.

Undepleted X/Q dispersion factors for evaluating ground level l

concentrations; 2.

Depleted X/Q dispersion factors for evaluating ground level concentrations;

^

\\ l' l/ vb Revision 1'

Da t e - / : < q, ?

Approved By:

M

. }

3-41 5713R/20.74

w 3.

Gama X/Q dispersion factors for evaluating gama dose rates from a sector averaged finite cloud (multiple energy undepleted source);

and 4.

D/Q deposition factors for evaluating dry deposition of elemental radiolodines and other particulates.

The deposition velocity concept presented in "Meteorology and Atomic Energy - 1968" (Reference E Section S-3.2) is used to determine the depleted X/Q and 0/Q factors, assuming a constant deposition velocity of I cm/sec.

Gama dose rate is calculated throughout this 00CM using the finite cloud model presented in "Meteorology and Atomic Energy - 1968" (Reference E.

Section 7-5.2.5).

That model is implemented through the definition of an Y

effective gama atmospheric dispersion factor, (X/Q ) (Reference B. Section 6), and the replacement of X/Q in infinite cloud dose equations by the Y

[X/Q ),

3.10.3 Annual Average Atmospheric Dispersion Factors for Receptors Actual measured meteorological data for the five-year period, 1978 through 1982, were analyzed to determine all the values and locations of the maximum off-site annual average atmospheric dispersion factors.

Each dose and dose rate calculation incorporates the maximum applicable off-site annual average atmospheric dispersion factor.

The values used and their locations are sumarized in Table 3.10-1.

Table 3.10-1 also indicates which atmosoneric dispersion factors are used to calculate the various doses or dose rates of interest.

l Revision H Date -

/7 Approved By D S$

k$ 0 &

3-42 5713R/20.74 l

Trbio 3.10-1 Vermont Yankee Dilution Factors Dose Rate to Individual Dose to Air Total Body _

_ Skin Critical Organ Gamma Beta 2)

X/0 depleted (

)

5.85E-07 X/O undepleted (5'3) 5.99E-07(2' 5.99E-07(2) m D/0 (h) 5.85E-09(2) m II' II' 6.98E-07(I' 6.98E-07 6.98E-07 X/QY(

)

m (1) Maximum gamma exposure point: S sector, 400 meters (0.25 miles).

(2) Maximum ground level concentration: NW sector, 2900 meters (1.80 miles).

3-43 Approved y 6Uk Datef;/ __/ g 7 3,/

R2 vision

/

5713R/20.14

,.c-c

-J

The Connecticut River Valley in the vicinity of the Vermont Yankee plan 2 has a pronounced up-and down-valley wind flow. Based on five years of me%eorological data, wind blows into the 3 "up-valley" sectors (N, NNW, and NH) 27 percent of the time, and the 4 "down-valley" sectors (5, SSE, SE, and ESE) 40 percent of the time, for a total "in-valley" time of 76 percent.

Station AP/CF-12 (NNW, 3.6 km) in North Hinsdale, New Hampshire, monitors the up-valley sectors.

It is located in the sector that ranks fourth overall in terms of wind frequency (i.e., in terms of how often the wind blows into that sector), and is approximately 0.5 miles from the location of the calculated maximum ground level D/Q (i.e., for any location in any sector, for the entire Vermont Yankee environs).

This station provides a second function by its location in that it also monitors North Hinsdale, New Hampshire, the community 01th the second hig9est gr end level D/Q for surrounding communities, and it has been in operation since the preoperational period.

The down-valley direction is monitored by two stations - at River Station Numper 3.3 (AP/CF-11, SSE, 1.9 km) and at Northfield, Massachusetts (AP/CF-14, SSE, 11.3 km).

They both reside in the sector with the maximum aind frequency and they bound the down-valley point of calculated maximum ground level 0/Q (the second highest overall ground level 0/0 for any location in any sector). Station AP/CF-Il is approximately one mile from this point, betaeen it and the plant.

Station AP/CF-14 also serves as a community monitor for Northfleld, Massachusetts.

Both stations have been in operation since the preoperational period.

In addition to the up-and down-valley 'ocations, two communities have been ehosen for community sampling locations.

The four nearest population groups with the highest long-term average 0/Q values, in decreasing order, are Nor%hfield, Massachusetts, North Hinsdale, New Hampshire, Brattleboro, Vermont, and Hinsdale, New Hampshire.

The community sampler for Northfield is at Sta91on AP/CF-14 (mentioned above).

North Hinsdale is already monitored by the up-valley station (AP/CF-12, NNW, 3.6 km), which also indirectly monitors 1

/.

Reeision -

Date ' : /,/~ '

Approved By ( kM l'ir [t M

/

~

4-IA 5713R/20.74

the city of Brattleboro, located further out in the same sector.

The second sa:pler specifically designated for a community is at Hinsdale Substation (AP/CF-13. E, 3.1 km) in Hinsdale.

The control air sampler was located at Spofford Lake (AP/CF-21, NNE, 16.1 km) due to its distance from the plant and the low frequency for cind blowing in that direction based on the long-term (five-year) meteorolod cal history.

Sectors in the general west to southwest direction, which would otherwise have been preferable due to lower wind frequencies, were not chosen since they approached the region surrounding the Yankee Atomic plant in Rowe, Massachusetts.

An additic9al air sampler is maintained at the Tyler Hill site (AP/CF-15, WNW, 3.4 km), which is along the western side of the valley in general proximity of historical dairy operations.

(The sixth location is not a specific Technical Specification requirement.)

4.3 Distances and Directions to Monitoring Stations It should be noted that the distances and directions for direct radiation monitoring locations in Table 4.1, as well as the sectors shown in Figures 4.5 and 4.6, are keyed to the center of the Turbine Building due to the critical nature of the Turbine Building-to-TLD distance for close-in stations.

For simplicity, all other radiological environmental sampling locations use the plant stack as the origin.

These distances and directions are also used in the semiannual reports.

Technical Specification 6.7 in the fifth paragraph, specifies that in the Annual Radiological Environmental Surveillance Report, the reactor shall be used as the origin for 411 distances and directions to sampling locations.

Vermont Yankee interprets "the reactor" to mean the reactor site which includes the plant stack and the Turbine Building.

The distances to the plant stack and Turbine Building will, therefore, be used in the Annual Radiological Environmental Surveillance Reports for the sampling and TLD monitoring stations, respectively.

b nL @

Revision 1i, Date h /,/f 7 Approved By: i l

l 4-1B 5713R/20.74

Table 4.1 (continued)

Radiological Environmental Monitoring Stations

Distance From Direction From Center of the Center of the Exposure Pathway Sample Location Turbine Turbine and/or Sample and Designated Code Bui ldi ng(km)

Building 4.

DIRECT RADIATION i

DR-1 River Station 1.6 SSE l

No. 3.3 OR-2 N. Hinsdale, NH 3.9 NNW OR-3 Hinsdale Substation 3.0 E

OR-4 Northfield, MA 11.0 SSE OR-5 Spofford Lake 16.3 NNE OR-6 Vernon School 0.46 WSW OR-7

. Site Boundary 0.27 W

sW OR-8

~ Site Boundary 0.25 N

l OR-9 Inner Ring 2.1 j

OR-10 Outer Ring 4.6 N

i DR-1!

Inner Ring 2.0 NNE OR-12 Outer Ring 3.6 NNE OR-13 Inner Ring 1.4 NE OR-14 Outer Ring 4.3 NE OR-15 Inner Ring 1.4 ENE OR-16 Outer Ring 2.9 ENE OR-17 Inner Ring 1.2 E

OR-18 Outer Ring 3.0 E

OR-19 Inner Ring 3.5 ESE OR-20 Outer Ring 5.3 ESE OR-21 Inner Ring 1.8 SE OR-22 Outer Ring 3.2 SE OR-23 Inner Ring 1.8 SSE OR-24 Outer Ring 3.9 SSE OR-25 Inner Ring 2.0 S

OR-26 Outer Ring 3.7 5

DR-27 Inner Ring 1.0 SSW OR-28 Outer Ring 2.2 SSW OR-29 Inner Ring 0.7 WSW OR-30 Outer Ring 2.3 SW OR-31 Inner Ring 0.8 W

OR-32 Outer Ring 5.0 WSW OR-33 Inner Ring 0.9 WW OR-34 Outer Ring 4.9 W

OR-35 Inner Ring 1.4 WNW OR-36 Outer Ring 4.7 WNW DR-37 Inner Ring 3.0 NW OR-38 Outer Ring 7.7 NW OR-39 Inner Ring 3.2 NNW DR-40 Outer Ring 5.8 NNW

Sample locations are shown on Figures 4.1 to 4.6.

- Station IXs are indicator stations and Station 2Xs are control stations (for all but the Direct Radiation stations).

"'To be sampled and analyzed semi-annually.

4-3 m

Approved By:(_i\\ Q2~h 3 kl.*

Revision N Date.; / __

-7 I

5713R/20.74

l

(

1.'

!!!iE N

1 rn to

)

\\

DR-10 IIW DE-12

/

'" 9

R-2 p

8 H!!iSDALE fl.H.\\--

mz.1.

DP-37 IB-9 OR-11 0

0 'e 4

\\ r?-36 c,,4 DR-13 0?-15 W!!W g;;;

M

~~~

~~~~

\\

?-3 5 /* 8 tE-15

?.3 PLAQ

p-i-E W

[

i L

3

/

tvunts II=PC 8

VERl C CAM

.. [.

!?-1; kr3-21

?-32 gg,gg

[

\\t3-23 eee nSW VERtt0!i, V.T.

~ ~ ~ '

g p..

\\.7R-25 OR-30

\\ =>-22 N EP-26 DR-2k

/

0 1

2 3

llLV PCW e

K!LCF!TERS

~

Figure 4-5 TLD Locations Within $k.:n of Plant g

R^ vision I

Date:_/.

' 7 4-8 Approved By S, ' t s' - "

/

5.2 Gaseous Effluent Instrumentation Setpoints Technical Specification 3.9.B.1 requires that the radioactive gaseous effluent instrumentation in Table 3.9.2 of the Technical Specifications have their alarm setpoints set to insure that Technical Specifications 3.8.E.1 and 3.8.K.1 are not exceeded.

Technical Specification 3.8.E.1.a limits the activity concentration in off-site gaseous effluents to well below the appropriate HPCs in 10CFR20 by limiting the whole body and skin dose rates to areas at or beyond the site boundary. Technical Specification 3.8.K.1 limits the gross radioactivity release rate at the steam jet air ejector (SJAE) to 0.16 C1/sec.

5.2.1 Plant Stack Noble Gas Act'vity Monitors (RR-108 1A and RR-108-18) and Augmented Off-Gas System Noble Gas Activity Monitors (3127 and 3128)

The plant stack and A0G noble gas activity monitors are shown on Figure 6-2.

5.2.1.1 Method to Determine the Setpoint of the Plant Stack Noble Gas Activity Monitors (RR-108-1A and RR-108-18) and the Augmented Off-Gas System Noble Gas Activity Monitors (3127 and 3128)

The setpoints of the plant stack and A0G system noble gas activity monitors are determined in the same manner.

The plant stack or A0G system noble gas activity monitor response in counts per minute at the limiting off-site noble gas dose rate to the total body or to the skin is the setpoint, denoted R N

is the lesser of:

spt*

spt f

h (5-9) 716 S

R DFB t=

g g

3 3

see DCi-yr ICP*I (mrem-uCi-m ' (com-cm '

yr-pC1-sec pCi 3

mrem-m n

\\:

Revision

! Date-v/c 1 Approved By: L La R j y a l W k

/

/'

5-9 5713R/20.74

.,1 and:

h (5-10)

R

= 3,000 5

D 9

3 ICP"}

Imrem) <com-tm } I T I pCi-yr '

sec yr pCi mrem-sec cm I

there:

R

- Response of the monitor at the limiting total body dose l

t rate (com) 3 cmrem-uC1 m )

500 716 yr-pci-sec l

l (1E+06)

(6.98E-07) 500

- Limiting total body dose rate (mrem /yr)

I 1E+06 Number of pCl per pC1 (pC1/pC1)

.[X/QF,maximumfive-yeag)averagegammaatmospheric 6.98E-07 dispersion factor (sec/m S

. Appropriate (plant stack or A0G system) detector g

counting efficiency from the most recent calibration (cpm /(pC1/cc))

3 F

Appropriate (plant stack or A0G system) flow rate (cm /sec) 3 DFB

= Composite total body dose factor (mram-m /pCi-yr) e Qg 0FB g (5-11)

=

L. Os 4 [6 %

Approved By i Revision 4 Date t/. /,17

--U.LL_

5-10 l

l 5713R/20.74

gas.

The nominal plant stack flow is 7.5E+07 cc/sec ((160,000 cfm x 28.300 3

cc/ft )/60 set / min).

When monitor responses indicate that activity levels are below the LLDs at the stack (or A0G) monitors, the relative contribution of each noble gas radionuclide can conservatively be approximated by analysis of a sample of off-gas obtained during plant operations at the steam jet air ejector (SJAE). This setpoint example is based on the following data (see Table 1.1-10 for DFB9 andDFj):

hf^

OFB 0Fj i

3 guCi) gmrem-m )

gmrem-sec) i see DCi-yr uCi-yr Xe-138 1.03E+04 8.83E-03 9.60E-03 Kr-87 4.73E+02 5.92E-03 1.06E-02 Kr-88 2.57E+02 1.47E-02 1.32E-02 Kr-85m 1.20E+02 1.17E-03 1.83E-03 Xe-135 3.70E:02 1.81E-03 2.60E-03 Xe-133 1.97E+01 2.94E-04 4.57E-04 7.SJAE Q, DFBg 0FB (5-11) c r'

.SJAE L

Q 1 i

r.SJAE

/

O 0FB, - (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E-03) g i

+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)

+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04)

I 3

9.83E+01 (pC1-mrem-m /sec-pC1-yr)

Date. '.'. Q -7 Approved By: M

.\\ Ivbl(W Revision 4 5-12 5713R/20.74 f

r--

SJAE Q

- 1.03E+04 + 4.73E+02 + 2.57E+02 u

i i

l

+ 1.20E+02 + 3.70E+02 + 1.97E+01

- 1.15E+04 pC1/sec.

9.83E+01 0FB g

= 1.15E+04 3

- 8.52E-03 (mrem-m /pC1-yr)

R t' III I g

0FB g 1

1

- (716) (IE+08) (7.5E+07)

(8.52E-03) l 112,050 com Nert:

T.SJAE LQ 0F{

g 1

(5-12)

OF'.

7

,33 '

L 0 ^,

1 V.5]/ E L_ O 0Fj-(1.03E+04)(9.60E-03) + (4.73E+02)(1.06E-03) g 1

(2.57E+02)(1.32E-02) + (1.20E+02)(1.83E-03)

+

+ (3.70E+02)(2.60E-03) + (1.97E+01)(4.57E-04) 1.04E+02 (pCi-mrem-sec/sec-pCi-yr)

=

0F, 1.04E+02 c

1.15E+04 1

Revision '1 Date i; /-c/' 7 Approved By: WLL'i ID M M i

s 5-13 5713R/20.74

?*

_T h

9.04E-03 (mrem-sec/ Ci-yr) gh (5-10) 5 "

R

- 3,000 S st 1

1

- (3,000) (IE+08)

(7.5E+07)

(9.04E-03) 7

- 442,478 cpm i

3 "

and R The setpoint, Rspt, is the lesser of R t

st' is less than For the noble gas mixture in this example Rspt L_

R

", indicating that the total body dose rate is more restrictive.

Therefore, in this example the "Stack Gas I" and "Stack Gas II" notte gas f

activity monitors should each be set at 112.050 com above background or at some conservative value below this (such as that which might be based on controlling release rates from the plant in order to maintain off-site air concentrations below 2 x HPC when averaged over an hour).

E_

5.2.1.3 Basis for the Plant Stack and A0G System Noble Gas Activity Monitor Setpoints The setpoints of the plant Stack and A0G system noble gas activity J

i monitors'must ensure that Technical Specification 3.8.E.1.a is not exceeded.

Sections 3.4 and 3.5 shev hat Fouations 3-5 and 3-7 are acceptable methods for determining Compliance with that Technical Specification.

Which equation (i.e., dose 5., total body or skin) is more limiting depends on the noble gas

- ly mixture. Therefore, each equation must be considered separately.

The "i

derivations of Ecuations 5-9 and 5-10 begin with the general equation for the response R of a radiation monitor:

5 C

(5-13) j R

=

93 g

ll!

(c-c='> (e NW (cpm >

pC) e,3

_f1 f

1

/

7v

%3.Y Approved By: L U A _\\l'j. -

a k.W Revision 4 Date t /. k7 5-14

- e ' -

?

5713R/20.74 e

d e

- - - - - - - ~ _ - - _ _ _ _ _ _ -. _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _

1 h

hg (5-16)

S R

=

g (cpm)

(CDm-cm

( ~s e t '

(fCl,'

C1 3

sec Cm The total body dose rate due to noble gases is determined with Equation 3-5:

hg 0FB (3-5) 0.70 R

=

g tb i

3 g

y (DCl-secy guci) gmrem-m )

mrem 3

sec p 1-yr yr C1-m where:

k

= total body dose rate (mrem /yr) tb 3

0.70

- (1.0E+06) x (6.98E-07) (pCl-sec/pCi-m )

lE + 06

- number of pCi per pCi (pCl/pCl) 6s98E-07-[X/QF,maximumannualaveragegammaatmospheric 3

dispersion factor (sec/m )

Qg

= the release rate of noble gas "1" in the mixture for each noble gas identified (pCi/sec) (Equivalent to

.ST Qg for noble gases released at the plant stack.)

DFB,

. total body dose factor (see Table 1.1-10) 3 (mrem-m /pCl-yr)

Reetston 2L Date it/2 e /5 7 Approved By: ( I A h _ f/ A i

N i

5-17 5713R/20.74

f A composite total body gamma dose factor, OFB, may be defined such that:

g T

T 6g DrB

<5-17)

DrB c

og =c g

e i

i 3

3 guC1) guCi) gmrem-m )

mrem-m pct-yr sec sec pCi-yr Solving Equation 5-23 for DFB yields:

e hg 0FB 3

I G-11) 0FB

=

e g,,

4O g

i Technical Specification 3.8.E.1.a licits the dose rate to the total body from noble gases at any location at or beyond the site boundary to 500 trem/yr.

By setting R equal to 500 mrem /yr and substituting 0FB for orb tb g

g in Equation 3-5, one may solve for L Qg at the limiting whole body noble gas I

dose rate:

T'.

pk (5-18)

/_., Qg =

716 i

c 3

gh) mrem-uCi-m ) (DCi-yr )

g see yr-pCi-sec 3

mrem-m Substituting this result for hg in Equation 5-16 yields R the response to of the monitor at the limiting noble gas total body dose rate:

h b

Rfpg=

G-D 716 5

9 mrem-uCl-m g,,,g,3 3

see DCi-yr ICP*)

Iyr-pct-Isf pCl 3

mrem-m n

j.

Revision M Date

'T'7 Approved By: b &.I/l M / b v

o 5-1B 5713R/20.74 b

.5]AE OFB Qg i

3 1

(uC1/sec)

(mrem-m /DCi-yr)

Xe-138 5.15 E+03 8.83 E-03 Kr-87 2.37 E+02 5.92 E-03 Kr-88 1.29 E+02 1.47 E-02 Xe-135 1.85 E+02 1.81 E-03 Calculation The dose rate is calculated from Equations (3-5) and (3-28):

(3-5) it 0.70 h

DFB tb -

g i

3 gerem) geCl-sec) gg)

(mrem-m )

3 sec pCi-yr yr UCi-m a... 'here the stack release rate is determined from:

.SJAE (3-28)

.ST 0 1

. Sa.:

W 0

guC1/cc)

(cc_)

1

' cpm) g cpm sec (b) sec

.k

First,determinethesum([)ofallQ

,d the fraction that each noble g

i gas i represents in the total gas mix.

.SJAE Q

- (5.15 E+03) + (2.37 E+02) + (1.29 E+02) + (1,85 E+04.

g

- 5.70 E+03 uC1/sec and the relative fraction of each noble gas:

b'D)1 Moil Revision H Date t/, / : /

Approved By:

~

i i

A-4 5713R/20.74 l

g.-

f h

/5.70 E+03 Relahy raction g

0.904 Xe-138 5.15 E+03/5.70 E+03 0.042 Kr-87 2.37 E+02/5.70 E+03 0.023 Kr-88 1.29 E+02/5.70 E+03 0.032 Xe-135 1.85 E+02/5.70 E+03

=

Next, the stack release rate of each noble gas I from Equation (3-28) can be substituted into Equation (3-5) to give the dose rate as:

1 F

f DFB Rtb = 0.70 M g 3

g g

1

= 0.70 80,000 1/IE+08 7.55 E+07 f

DFB g

g g

4.23 E+04 ((0.904)(8.83 E-03) + (0.042)(5.92 E-03) +

1 (0.023)(1.47 E-02) + (0.032)(1.81 E-03)) -

Anscer ktb = 365 mrem / year noble gas total body dose rate.

Revision h Date n / n/ei7 Approved By: L bt

,1 : L..*

3 i

i A-5 5713R/20.74

w fg (32 day)*

DF8 **

g g

Kr-85 0.152 1.61 E-05 Xe-131m 0.070 9.15 E-05 Xe-133 0.777 2.94 E-04

Fraction of nuclide in mix as function of time (see Table 5.2-1).

- Dose factors frcm Table 1.1-10.

Calculation The dose rate is calculated from Equations (3-5) and (3-28):

(3-5) k 0.70 h

DFB tb =

g i

3 g

ygoCi-sec)

( f_i. )

(mrem-m )

erem 3

sec PCI-yr yr uCl-m and where the stack release rate is determined from:

.SJAE (3-28)

.57 Q,

j-F 0

M 1

r.SJAE Sg LQ1 1

guC1/cc) guC1)

(cpm)

( c_c_)

c set cpm sec

.SJAE However, for a time (t) after shutdown, the ratio of Qg to the sum release rate of all noble gases can be replaced in Equation (3-28) by the relative fraction (f (t)) of each noble gas available in the system; g

therefore, Equation (3-28) can be written:

b

!/sf kl ;*

. Revision y Date 61/3 e/r7 Approved By

~

4

/

A-7 5713R/20.74

.ST 1

~

Q

= f (t)

M F

1 i

Sg Therefore, using the above data for a ti,me period 32 days after shutdown, the

' dose rate equation can also be written as:

1 ktb = 0.70 M F

f (t)

DFB gg g

g g

= 0.70 80,000 1/1E+08 7.55 E+07 C(0.152)(1.61 E-05) +

(0.070)(9.15 E-05) + (0.777)(2.94 E-04)) e Anster ktb = 10.0 mrem / year noble gas total body dose rates at 32 days after shutdown.

1 1

Revision

'l Date I c /4/5 7 Approved By:' th

, [4 '^

V i

i A-8 57f3R/20.74

.5]AE OFj 0 1 zmrem-sec) 1 (uC1/sec) uCl/ year Xe-138 5.15 E+03 9.60 E-03 Kr-87 2.37 E+02 1.06 E-02 Kr-88 1.29 E+02 1.32 E-02 Xe-135 1.85 E+02 2.60 E-03 Calculation The skin dose rate is calculated from Equations (3-7) and (3-28):

(3-7) k Q

DFj skin =

1 (mrem) guC_i,)

(mrem-sec) l yr sec uC1-yr and where the stack release rate is determined from:

.SJAE (3-28)

.ST Q,

j N

F 0

1 SJAE Sg 1

(cpm) guC1/cc)

( c.c_)

c g

Cpm sec (sec)

.SJAE First,determinethesum([)ofallQ and the fraction that each noble

(

g i

gas i represents in the total gas mix.

T

.SJAE i.

Qg

- (5.15 E+03) + (2.37 E+02) + (1.29 E+02) + (1.85 E+02)

L 1

- 5.70 E+03 uC1/sec.

and the relative fraction of each noble gas:

Revision LI. Date t /< /s 7 Approved By: Yl(I

/W N P w

l A-10 l

5713R/20.74 l

i

\\

f i

I SJAE 1

h

/5.70 E+03 Relative Fraction g

i of Total i

Xe-138 5.15 E+03/5.70 E+03 0.904

=

Kr-87 2.37 E+02/5.70 E+03 0.042

=

Kr-88 1.29 E+02/5.70 E+03 0.023

=

Xe-135 1.85 E+02/5.70 E+03 0.032

=

Next, the stack release rate of each noble gas i from Equation (3-28) can be substituted into Equation (3-5) to give the skin dose rate as:

1 M

F f

skin -

g g

g 0Fj

= 80,000 1/1E+08 7.55 E+07 ((0.904)(9.60 E-03) +

(0.042)(1.06 E-02) + (0.023)(1.32 E-02) + (0.032)(2.60 E-03))

= 6.04 E+04 (8.68 E-03 + 4.45 E-04 + 3.04 E-04 + 8.32 E-05)

= 6.04 E+04 (9.51 E-03)

Ansver Rskin - 574 mrem / year noble gas skin dose rate.

bbb Revision N. Date I / o/5 7 ApprovedBy:l b A

~

A-11 5713R/20.74

r i

DFj

"'*-5'C fg (t >5 days)

(*uC t -ye ar)__

g Xe-133 1.

4.57 E-04 Calculation The skin dose rate is calculated from Equations-(3-7) and (3-28):

.ST (3-7) 0 DFj Rskin "

1 g

g,C1) g y

u mrem-sec (mromy yr sec uCi-yr and, the stack release rate is determined from:

o

.SJAE (3-28)

.ST Qg N

F 0 1 O.SJAE Fg-L Q, t

However, for times greater than five days after shutdown, Xe-133 may be used as the referenced radionuclide alone. Therefore, in Equation (3-28) the ratio i

i

.SJAE

.SJAE of Qg

'to the sum of all Q can be replaced by a value of I which g

Indicates that all the contribution to the release is from Xe-133.

t Therefore:

.ST Q -133 1.0 x 120,000 x 1/IE+08 x 7.55 E+07 Xe guCi/cc)

(cc/sec)

(cpm) cpm 6,333 - 90,600 uCt/sec.

x t

N o.

Approved By: b hb/

Revision N

Date !r/ u /f ~7

/

A-13 i

5713R/20.74

5

.5T Therefore, replacing this value of Q, into Equation-(3-7) we find the skin dose rate as:

k

= 90,600 x

4.57 E-04 skin

.<cremy guC1) g y

erem-sec yr sec UCl-yr 4

Ansrer kskin. 41.4 mrem / year.

1 1

i i

!/t CVb Revision N Date Iqbe/; 7 Approved B a

/

A-14 5713R/20.74

EXAMPLE PROBLEM NO. 6 1D2 Critical Organ Dose Rate From Iodine, Tritium, and Particulates References a)

OOCH Section 3.6 (Method I).

b)

Technical Specification 3.8.E.1.b.

prob'em Calculate the critical organ dose rate due to measured effluent data taken from the plant stack for a seven-day sample collection period.

Plant Data a)

Stack particulate analysis for the seven-day period of interest.

(I'

.STP DFG' Activity Q1 mrem c

g yr-uCi )

_i (uCi/sec)

Sr-89*

1,42 E-04*

2.23 E+02 Sr-90*

3.50 E-03*

8.48 E+03 Co-60 4.89 E-02 2.12 E+02 Cs-137 3.90 E-03 3.44 E+02 Zn-65 1.01 E-02 7.51 E+01 Na-24**

2.76 E-03**

Mn-54+

<2.87 E-06+

1,72 E+01 (I)

DFG'co dose rate factor for each radionuclide is taken from Table 1.1-12.

q Revision 4 Date ~ /c. h 7 Approved By: b h,AlW6*

A-15 5713R/20.74 i

Notes

Fcr Sr-89/90, use the m it recent available measurement from quarters composite analysis.

- Na-24 has a half life of less than 8-1/2 days, and therefore is not included in the dose analysis per requirements of Technical Specification 3.8.E.1.b even though it was detected.

eMn-54 is not included in the dose analysis since it was not detec'.ed as being present above the LLD.

b)

Stack todine (charcoal and particulate activities combined for the seven-day period of interest):

.STP DFG' Activity Q i mrem c

g yr-uCi )

i (uC1/sec) 1-131 1.16 E-03 1.51 E+03 1-133*

<6.35 E-05*

1.61 E+01 1-135**

7.21 E-03**

5.14 E-01 and H-3+

3.17 E-02 5.70 E-03 Notes

I-133 is not included in the dose analysis for this case since it was not detected is being present in the stack analysis.

- I-135 is not included in the dose analysis because it has a half life less than 8-1/2 for particulates, and is not included as a required iodine in Technical Specification 3.8.E.1.b.

oTritium value based as latest available stack grab sample.

!//$ (N IV Revision 4 DateI I:,./ < 7 Approved By

/

A-16 5713R/20.74

~

Calculation The dose rate is calculated from Equation (3-16):

(3-16) k,=g h

DFGjgg g

gerem) guC1) gmrem-sec) yr sec uC1-yr The dose rate factors (DFG'ggg) for each of the radionuclides detected in the plant stack charcoal and particulate filter sample (plus tritium) is taken from Table 1.1-12 of the 00CM.

Therefore:

k,= (1.42 E-04)(2.23 E+02) + (3.50 E-03)(8.48 E+03) + (4.89 E-02) g (2.12 E+02) + (3.90 E-03)(3.44 E+02) + (1.01 E-02)(7.51 E+01)

+ (1.16 E-03)(1.51 E+03) + (3.17 E-02)(5.70 E-03).

Anster R,= 33".6 mrem / year critical organ dose rate from iodine, tritium, and g

particulate.

b ih h

Revision El Date n /nel s 7 Approved By

( 'I" A-17 5713R/20.74

Calculation j

i The maximum gamma air dose off-site is calculated from Equation (3-21):

Qf DFf D{tr (3-21)

= 0.022 3

4 mrad-m )

(arad)- (DCl-r)

(Cl) pCi-yr C1-m Therefore:

Dfir = 0.022 ((3.55 E-01)(1.52 E-02) + (4.71 E+00)(1.23 E-03)

+ (2.75 E+00)(9.21 E-03) + (3.51 E+01)(1.92 E-03) +

(9.42 E+01)(3.52 E-04))

= 0.022 (5.40 E-03 + 5.79 E-03 + 2.53 E-02 + 6.74 E-02 +

3.31 E-02)

Answer Dfir = 3.01 E-03 mrad gamma air dose during the month.

Revision 4 Date e/:./S 7 Approved By Ib. L'\\ / ) bl/1" A-19 5713R/20.74

M l

Calculation The maximum beta air dose off-site is calculated from Equation (3-23):

DFf ST (3-23)

D

= 0.019 Q

alr 1

3 (mrad) ( Ci-r)

(Cl)

(mrad m )

pct-yr Cl-m l

Therefore:

l-D,9; = 0.019 ((3.55 E-01)(2.93 E-03) + (4.71 E+00)(1.97 E-03)

+-(2.75 E+00)(4.75 E-03) + (3.51 E+01)(2.46 E-03) +

(9.42 E+01)(1.05 E-03)]

0.019 (1.04 E-03 + 9.28 E-03 + 1.31 E-02 + 8.63 E-02 +

i l

9.89 E-02)

I

\\

Anster A

D

= 3.96 E-03 mrad beta air dose during the month.

air t

's 6

/

A-21 5713R/20.74 i

l EXAMPLE PROBLEM NO. 9 l

192 Critical Organ Dose From Iodine, Tritium, and Particulates References a) 00CM Section 3.9 (Method I).

b)

Technical Specification 3.8.G.I.

7toblem Calculate the critical organ dose due to the total activity recorded as being released from the plant stack during a calendar month.

Plant Data a)

From the combined stack analyses during the month, the following activity released is:

DFG gg, 0 1 Imrem}

(C1)

Ci Sr-89*

5.42 E-04*

7.08 E+00 Sr-90*

1.10 E-02*

2.69 E+02 Co-60 2.30 E-01 4.76 E+00 Cs-137 1.15 E-02 1.01 E+01 Zn-65 2.60 E-02 2.32 E+00 Na-24**

7.11 E-03*

Mn-54

<2.76 E-06+

4.36 E-01

\\b[t/h*

Revision 4 Date I / ',o/f 7 Approved By

/

1 A-22 5713R/20.74

l Notes for Plant Data a) Above (1) Crt ucal organ dose factor taken from Table 1.1-12.

CFor Sr-89/90, use the most recent available measurement from the quarterly composite analysis.

$$Na-24 has a half life of less than 8-1/2 days, and therefore is not included in accordance with Technical Specification 3.8.G.I.

<Mn-54 is not included in the dose analysis since it was not detected as being present above the required LLO.

b)

Total iodine release for the month based on the combined charcoal and particulate filter samples taken during the month:

DFG lco 0 1 (mrem}

I (Ci)

Ci I-131 4.30 E-03 4.80 E+01 l

I-133 1.12 E-04*

5.12 E-01 l

!-135**

2.01 E-02" and H-3+

0.15 1.81 E-04 Calculation The dose is calculated from Equation (3-25):

Qf 0FG (3-25)

D gg, gg (arem)

(C1)

(mrem /C1)

Revision El Date o lho /r,)

Approved By:

i M

~*

/

i A-23 5713R/20.74

Notes for Plant Data b) Above

In this case, I-133 was found in one of the weekly stack samples to be present, and therefore based on that value is included in the dose analysis.

- I-135 is not included in the dose analysis because it has a half life less than 8-1/2 days for particulates and is not included as a required iodine in Technical Specification 3.8.B.1.

+ Tritium value based on the monthly stack grab sample.

The dose factor (DFGggn) for each radionuclide detected in the plant stack charcoal and particulate filter sample (plus tritium) is taken from Table 1.1-12 of the 00CM.

Therefore:

D,- (5.42 E-04M7.08 E+00) + 0.10 E-02M2.69 E+02) +

g (2.30 E-01)(4.76 E+00) + (1,15 E-02)(1.01 E+01) +

(2.60 E-02)(2.32 E+00) + (4.30 E-03)(4.80 E+01) +

(1,12 E-04)(5.12 E-01) + (0.15)(1.81 E-04) -

Ansrer O,.

.o m,em ma m m,,.n dose for the o nth.

c I

6 1

Y A-24 l

5713R/20.74

EXAMPLE CALCULATION NO. 10 11Et Releases Limited to 2X MPC Average Over an Hour in Off-Site Air Concentrations References a) 10CFR50.72 b) 10CFR50.73 Problem Find the minimum stack gas monitor response which would require an assessment to determine if a four-hour notification to NRC is required per 10CFR50.72.

Assumptions a)

Maximum expected stack flow rate (F) 8.73 E+07 cc/sec (185,000 cfm x 4.72 E+02 #C/sec,

)

f b)

Plant stack monitor detector 1 E+08 counting efficiency (59) com per UC1/cc c)

Maximum off-site ground level 5.99 E-07 3

dispersion parameter (X/Q undepleted) sec/m (from ODCM Table 3.10-1) d)

Most restrictive MPC value for noble 2 E-08 gases (10CFR20, Appendix B, Table II, uCi/sec Column 1) for Kr-87)

Revision 'I Date,:l; /r'7 Approved By

~

Y I

J A-25 5713R/20.74

-=

l l

dalculation(Parti)

The setpoint R for the stack monitor which would correspond to an spt instantaneous off-site air concentration of 2 x MPC for the most restrictive noble gas can be calculated by:

Rspt = 2 MPC Sg h

1 E+06 f

com 3

gg)

LQi g

(cpm)

UCl/cc) (,3,g) g[cc) g]cc,)

cc l

= 2 x (2 E-08)(IE+08)(1/5.99 E-07)(1E +06)(1/8.73 E+07) spt = 76,500 cpm setpoint alarm value.

R Now if the monitor alarmed at a setpoint of 76,500 cpm, an additional evaluation would be necessary to determine if the 2 x MPC limit for the actual radionuclide gas mix would be exceeded when averaged over one hour. As an example, assure the following:

f Plant Data a)

Recorded stack flow rate during release (F) 7.55 E+07 cc/sec C

'C

)

(160,000 cfm x 4.72 E+02

=

b)

Duration of release spike.

50 minutes t

c)

Maximum recorded stack monitor 210,000 cpm count rate.

[L W Revision U Date i;he l%7 Approved By:

L A-26 5713R/20.74

l l

d)

Time trace of stack monitor response during release.

210.000 6

\\

epa

\\\\

--- sackground 1,000

=

time t.o t,t3g 3

Total counts area under trace Approximately 210,000 cpm x 50 minutes x 1/2 Approximately 5,250,000 counts.

count Total counts averaged over one hour 1.ho

- 87,500 cpm Since the average count rate over one hour still exceeds the instantaneous alarm setting of 76,500 cpm, we must now look at the l

individual radionuclide concentrations off-site and see if the sum of the ratios of each nuclide concentrations over its MPC value is less than 2.0 in order to determine if the 2 x MPC notification rule had been reached.

Therefore, the mix fractions (f ) that each noble gas represents the g

total release must be determined from a representative off-gas or stack release sample.

e)

Assume the following fractions were determined:

7 Approved By: bY T[tbb Revislon M Date i- / ;ch, A-27 5713R/20.74

O 8

)

t 0 1 MPC I

}

I 1

t (10CFR201 Accendix 8)

Xe-133 3.50 E-04 0.40 3 E-07 uCl/cc Xe-133m 2.98 E-04 0.34 3 E-07 Xe-135 1.23 E-04 0.14 1 E-07 Kr-88 1.04 E-04 0.12 2 E-08 Total 6.75 E-04 Calculation (Part !!)

)

The air concentration off-site of each noble gas i can be found from:

F X/Q 10'0 h

C,- f, M

g i_)

( Lee) 3 g st)

(cpm) guC1/cc) g u

cc cpm sec

,3 (h) g (87.500(1/1 E+08)(7.55 E+07)(5.99 E-07)(10-6)

=f C,

f, (3.96 E-08)

Therefore, using the f from the table above we find:

g C g 1

(uCt/cc)

Xe-133 1.58 E-08 Xe-133m 1.35 E-08 Xe-135 5.54 E-09 Kr-88 4.75 E-09 j

N[OA Revision N Date in //c/' 7 Approved 8y 2

j j

A-28 5713R/20.74 I

Finally, the sum of the ratto of concentrations to MPC can be found:

k*k*k*k Cr 1.58 i:-08 1.35 E-08 5.54 E-09 4.75 E-09

<2 3 E-07 3 E-07 1 E-07 2 E-08 0.053

+

0.045

+

0.055

+

0.238

= 0.39 <2 Answers Since the sum of the ratios of the time averaged individual radionuclides air concentrations over their MPC limits in less than 2, there is no reporting requirement under 10CFR50.72 or 10CFR50.73.

Revision 4 Date

7 Approved By

\\

w N*w A-29 5713R/20.74 l

Steam Jet Air Elector (S3AE) Noble Gas Activity Monitors (17/150A and 5.2.2 17/1508)

The steam jet air ejector noble gas activ.ity monitors are shown on Figure 6-2.

Method to Detemine the SetDoints of the Steam Jet Air E3ector Of fuas 5.2.2.1 Activity Monitors (17/150A and 17/1508)

I The SJAE noble gas activity monitor response in counts per minute at the limiting release rate is the setpoint, denoted RSJAE, and is p

determined as follows:

SJAE 1.6E+05 S

1 (5-21) l R

=

9 (m/hr)

(b)

(hr-pCi)

(E) sec c,c where:

SJAE

= Response of the monitor at the limiting release rate (mR/hr)

R

= Limiting release rate for the SJAE specified in Technical 1.6E+05 Specification 3.8.K.1 (uti/sec)

= Detector counting efficiency from the most recent S

9 calibration ((mR/hr)/(pti/cc))

F

= SJAE gaseous discharge flow (cc/sec) 5.2.2.2 Basis for the SJAE Noble Gas Activity Monitor SetDoint The SJAE noble gas activity monitor setpoint must ensure that Technical Specification 3.8.K.1 is not exceeded. The derivation of Equation 5-21 is straightforward. Simply taking equation 5-16 and substituting the limiting releaserateattheSJAEforhyieldsEquation5-21,thesetpointequationfor the SJAE noble gas activity monitor.

AporovedDy:['[/8"._

RevisiendDate 5-22 b

APPENDIX I RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREA1 MENT SYSTEMS Requirement: Technical Specification 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response t There were no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting period.

I-1 4436R/4.243

VEllMONT YANKEE NUCLEAll POWEll COllPOllATION RD 5. Box 169. Ferry Road Brattleboro, VT 0$301

,,,n ENGINEERING OFFICE A

1671 WORCESTER ROAD F RAMINGHAM, M ASS ACHUSETTS 01701 February 29, 1988 mamupw,ex FVY 88-13 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Reference:

(a) License No. DPR-28 (Docket No. 50-271)

Subject:

Vermont Yankee Semiannual Effluent Release Report

Dear Sir:

Enclosed herewith please find one copy of the Vermont Yankee Nuclear Power Corporation Semiannual Effluent Release Report. This report covers the period beginning July 1, 1987 and ending December 31, 1987 and is submitted in cecordance with our Technical Specifications 6.7.C.1.

We trust that the enclosed information is satisfactory; however, should you have any questions, please contact me.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION

'/

R. W. Capstick Licensing Engineer RWC/25.439 Enclosures cc: USERC Region I 475 Allendale Road King of Prussia, PA 19406 USNRC Resident Inspector, VYNPS 4.

_ ----_--___-__--;

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