Text

Effluent & Waste Disposal Annual Rept for 1995
	ML20101K185
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/31/1995
From:	Duffy J; VERMONT YANKEE NUCLEAR POWER CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	BVY-96-38, NUDOCS 9604020291
	Download: ML20101K185 (87)
	v • d • e

VERMONT YANKEE NUCLEAR POWER CORPORATION Ferry Road, Brattleboro, VT 05301-7002 w

\\

ENGINEERING OFFICE 580 MAIN STREET BOLTON. MA 01740 (508)779-6711 March 29,1996 BVY 96-38 United States Nuclear Regulatory Commission ATfN: Document Control Desk Washington, DC 20555

References:

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

Subject:

1995 Vermont Yankee Annual Effluent and Waste Disposal Report Pursuant to Vermont Yankee Technical Specification 6.7.C.1 and 10CFR50.36a(a)(2) enclosed is the subject report.

We trust that the information provided is acceptable; however, should you have any questions, please contact this office.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION tw.

James J. Duffy Licensing Engineer l

l l

l c: USNRC Region 1 Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager-VYNPS 0200G3 9604020291 951231 jd)

PDR ADOCK 05000271 ju j

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR 1995 f

f f

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Vermont Yankee Nuclear Power Station ain6e

TABLE 1A Vermont Yankee Effluent and Waste Disposal Annual Report First and Second Quarters. 1995 Gaseous Effluents - Summation of All Releases Est.

Quarter Quarter Total Unit 1

2 Error, %

4 Fission and Activation Gases

(.

1.

Total release C1 6.18E+00 1.32E+00 il.00E+02 2.

Average release rate for period pCi/sec 7.86E-01 1.68E-01

(

3.

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

Iodines 1.

Total Iodine-131 Ci 9.23E-04 3.81E-04 i5.00E+01 2.

Average release rate for period pC1/sec 1.17E-04 4.85E-05 3.

Percent of Tech. Spec. limit (1) 0.

Particulates 1.

Particulates with T-1/2 > 8 days Ci 2.96E-04 1.33E-04 i5.00E+01 2.

Average release rate for period pC1/sec 3.76E-05 1.69E-05 3.

. Percent of Tech. Spec. limit (1) 4.

Gross alpha radioactivity C1 1.43E-06 1.76E-06

~).

Tritium 1.

Total release Ci 7.40E+00 3.71E+00 2.

Average release rate for period pC1/sec 9.41E-01 4.71E-01 3.

Percent of Tech. Spec. limit (1)

(1)

Percent of Technical Specification limit will be provided in the Supplemental Effluent and Waste Disposal Report to be submitted per Technical Specification 6.7.C.1.

[

R12\\60 6

TABLE 1A (Continued)

Vermont Yankee Effluent and Waste Disposal Annual ReDort Third and Fourth Quarters. 1995 Gaseous Effluents - Summation of All Releases Est.

Quarter Quarter Total Unit 3

4 Error. %

A.

Fission and Activation Gases 1.

Total release C1 1.40E+00 9.74E-04

1.00E+02 2.

Average release rate for period pC1/sec 1.78E-01 1.24E-04 3.

Percent of Tech. Spec. limit (1)

B.

Iodines 1.

Total Itdine-131 C1 3.59E-04 2.42E-04 i5.00E+01 2.

Average release rate for period pC1/sec 4.57E-05 3.07E-05 3.

Percent of Tech. Spec. limit (1) b.

Particulates 1.

Particulates with T-1/2 > 8 days C1 8.43E-05 1.64E-04

5.00E+01 2.

Average. release rate for period pCi/sec 1.07E-05 2.09E 05 3.

Percent of Tech. Spec limit (1) 4.

Gross alpha radioactivity C1 3.05E-06 4.30E-06 D.

Tritium 1.

Total release Ci 6.27E+00 4.89E+00 2.

Average release rate for period pC1/sec 7.97E-01 6.22E-01 3.

Percent of Tech. Spec. limit (1) b(1)

Percent of Technical Specification limit will be provided in the Supplemental Effluent and Waste Disposal Report to be submitted per Technical Specification 6.7.C.1.

[

uruo '

E l

TABLE IB Vermont Yankee Effluent and Waste Disposal Annual Report l

First and Second Ouarters. 1995 Gaseous Effluents - Elevated Releases Continuous Mode Batch ModeU)

Quarter Quarter Quarter Quarter Nuclides Released Unit 1

2 1

2

1. Fission Gases Krypton-85 Ci ND ND krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-135 C1 6.18E+00 1.32E+00 Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for period Ci 6.18E+00 1.32E+00

2. Iodines Iodine-131 Ci 9.23F 04 3.81E-04 Iodine-133 C1 2.73E-03 1.03E-03 lodine-135 Ci ND ND Total for period C1 3.66E-03 1.41E-03

3. Particulates Strontium-89 C1 1.21E-04 2.62E-05 Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND 1.15E-05 Barium-lanthanum-140 C1 1.44E-04 ND Manganese 54 Ci 7.93E-06 3.72E-06 Chromium-51 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci 9.06E-06 7.63E-05 Cerium-141 Ci ND ND Zinc-65 Ci ND ND Total for D&iod Ci 2.82E-04 1.18E-04 (1) There were no batch mode gaseous releases for this reporting period.

ND -

Not detected at the plant stack.

mruo 1

l TABLE IB (Continued) i Vermont Yanked Effluent and Waste DisDosal Annual Report Third and Fourth Quarters. 1995 Gaseous Effluents - Elevated Releases Continuous Mode Batch Mo'de(l)

Quarter Quarter Quarter Quarter Nuclides Released Unit 3

4 3

4

1. Fission Gases Krvoton-85 Ci ND 4.24E-04 Krvoton-85m C1 ND ND Krvoton-87 Ci ND ND Krvoton-88 Ci ND ND 7

Xenon-133 Ci ND 5.50E-04 Xenon-135 Ci 1.40E+00 ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified C1 ND ND Total for period C1 1.40E+00 9.74E-04

2. Iodines Iodine-131 Ci 3.59E-04 2.42E-04 lodine-133 C1 1.97E-03 1.78E-03 Iodine-135 Ci ND ND Total for oeriod C1 2.33E-03 2.02E-03

3. Particulates Strontium-89 Ci 4.65E-05 4.87E-05 Strontium-90 Ci ND ND Cesium-134 C1 ND ND Cesium-137 C1 3.61E-06 5.77E-06 Barium-Lanthanum-140 Ci ND ND Manaanese-54 C1 3.22E-06 ND Chromium-51 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 C1 3.10E-05 3.61E-05 Cerium-141 Ci ND ND Zinc 65 Ci ND ND Total for period Ci 8.43E-05 9.06E-05 (1) There were no batch mode gaseous releases for this reporting period.

ND -' Not detected at the plant stack.

nruo ;

l

TABLE IC Vermont Yankee Effluent and Waste Disposal Annual Report First and Second Ouarters 1995 Gaseous Effluents - Ground level Releases (2)

Continuous Mode Batch Mode (I)

Quarter Quarter Quarter Quarter Nuclides Released Unit 1

2 1

2

1. Fission Gases Krvoton-85 Ci ND ND krvoton-85m Ci ND ND KrvDton-87 Ci ND ND Krypton-88 C1 ND ND Xenon-133 Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Xenon-131m Ci ND ND Total for period Ci 0.00E+00 0.00E+00

2. Iodines (2)

Iodine-131 Ci ND ND lodine-133 Ci ND ND Iodine-135 Ci ND ND Total for period Ci 0.00E+00 0.00E+00

3. Particulates(2)

Strontium 89 Ci ND ND Strontium-90 C1 2.52E-1.05E-07 Cesium-134 Ci 1.10E-6.16E-08 Cesium-137 Ci 7.77E-06 3.86E 06 Barium-Lanthanum-140 Ci ND ND Mancanese-54 Ci 3.25E-09 2.14E 06 Chromium-51 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci 5.46E-06 8.77E-06 Cerium-141 Ci ND ND Zinc-65 Ci ND.

ND Iron-SL Ci ND 6.12E-07 Total for period C1 1.36E-05 1.55E-05 (1) There were no batch mode gaseous releases f'or this reporting period.

(2) Use of the North Warehouse stack as a ground level release point was initiated at the beginning of the fourth quarter of 1994.

ND - Not detected in the waste oil sample.

a m 6a TABLE IC (Continued)

Vermont Yankee Effluent and Waste Disoosal Annual Report Third and Fourth Quarters 1995 Gaseous Effluents - Ground Level Releases (2)

Continuous Mode Batch ModeU)

Quarter"#

Ouarter Quarter Quarter Nuclides Released Unit 3

4 3

4

1. Fission Gases Krvoton 85 Ci ND ND

__ Krvoton 85m Ci ND ND Krvoton-87 Ci ND ND Krvoton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-135 Ci ND ND

-Xenon-135m Ci ND ND Xenon-138 Ci ND ND Xenon-131m Ci ND ND Total for oeriod Ci 0.00E+00 0.00E+00

2. Iodines (2)

Iodine-131 Ci ND ND Iodine-133 Ci ND ND Iodine-135 Ci ND ND Total for oeriod C1 0.00E+00 0.00E+00

3. Particulates(2)

Strontium 89 Ci ND ND Strontium 90 Ci ND 8.19E-08 Cesium-134 Ci ND 8.62E-08 Cesium-137 Ci ND 2.02E-06 Barium Lanthanum 140 Ci ND ND Manaanese-54 Ci ND 1.98E-05 Chromium-51 Ci ND ND Cobalt-58 Ci ND-2.47E-06 Cobalt-60 Ci ND-3.03E-05 Cerium-141 Ci ND ND Zinc-65 Ci ND 1.90E-05 Iron-55 C1 ND 1.59E-06 Total for Deriod Ci 0.00E+00 7.52E-05 (1) There were no batch mode gaseous releases for this reporting period.

(2) Use of the North Warehouse stack as a ground.. level release point was initiated at the beginning of the fourth quarter of 1994.

ND - Not detected in the waste' oil sample, ni m o TABLE 10 Vermont Yankee Ef fluent and Waste Disposal Annual Report for 1995 Gaseous Effluents - Nonroutine Releases There were no nonroutine or accidental gaseous releases during this reporting period.

r airuo '

l l

TABLE 2A Vermont Yankee Effluent and Waste Disoosal-Annual Report for 1995 Liauid Effluents - Summation of All Releases There were no liquid releases during this reporting period.

am6o.

TABLE 2B Vermont Yankee Effluent and Waste Disposal Annual Report for 1995 Liauid Ef fluents - Nonroutine Releases There were no liquid releases during this reporting period.

airwo _ - _ _ _ _ _ _ _ _ _ _ _ _ _

TABLE 3 Vermont Yankee Effluent and Waste DisDosal Annual ReDort First and Second Guarters. 1995 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel):

Unit 6-Month Est. Total

1. Type of Waste Period Error. %

a. Spent resins, filter sludges, evaporator m'

bottoms. etc.

Ci t7.50E+01

b. Dry compressible waste, contaminated m'

ecuipment. etc.

Ci 7.50E+01

c. Irradiated components, control rods, m'

etc.

Ci

+7.50E+01

2. Estimate of M'ajor Nuclide Composition (By Type of Waste):

a.

Zinc-65 b.

Iron-55 Cesium-137 Zinc-65 I

Cobalt-60 Cobalt-60 Cesium-134 Mancanese-54 %

Manaanese-54 %

Ceslum-137

3. Solid Waste Disposition:

Number of Shipments Mode of Transportation Destination i

"No solid waste was disposed during this period."

B. Irradiated Fuel Shipments (Disposition):

None C. Supplemental information

1) Class of solid waste containers shipped:

2) Types of containers used:

1

3) Solidification agent or absorbent:

None l

I q muo

)

_.~

i TABLE 3 (Continued)

Vermont Yank (?

Effluent and Waste DisDosal Annual ReDort Third and Fourth Quarters. 1995 Solid Waste and Irradiated Fuel Shipments i

o

. A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel):

Unit 6-Month Est. Total

1. Type of Waste Period Error. %

a. Spent resins, filter sludges, evaporator m'

3.41E+00 bottoms, etc.

C1 1.35E+02

+7 50E+01 i

b. Dry compressible waste, contaminated m'

O.00E+00 eauiDment. etc.

Ci 0.00E+00 t7.50E+01

c. Irradiated components, control rods.

m' O.00E+00 etc.

Ci 0.00EA00 t7.50E+01 t

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

l a.

Zinc-65

% 2.00E+01 b.

Iron %

Cesium 137

% 1.60E+00 Zinc-65 Cobalt-60

% 2.70E+01 Cobalt-60 Mancanese-54 % 8.40E+00 Manaanese-54 %

Nickel-63

% 1.12E+01 Cesium 137 fron-55

% 3.02E+01

- 3. Solid Waste Disposition:

Number of Shioments Mode of TransDortation Destination i

1 Truck Barnwell, SC B. Irradiated fuel Shipments (Disposition):

None C. Supplemental information

1) Class of solid waste containers shipped:

IB

2) Types of containers'used:

1 Type A

3) Solidification agent or absorbent:

None I

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TABLE 5A j

VENdOIrf YANKEE JAN 95 - DEC 95 NET 30k0 LOGICAL DATA JOIlf? FREQUENCY DISTRIBt7FION 297.0 FT WIND DATA STABILITY CIASS A CLASS FREQUENCY (PERCENT)

=

3.02

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WIND DIRECTION FRON 4

CPEED(MPH)

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CAIJE 0

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(2)

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2 0

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3 1

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4 0

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13 5

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64 (1) 1.64

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0 0

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19 (1) 1.64

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0 0

3 3

12 0

18 (1)

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.00 1.38 (2)

.00

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.22 ALL SPEEDS 23 8

0 1

2 17 8

22 26 12 3

2 14 24 11 11 0

244 (1) 9.43 3.28

.00

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.82 5.74 9.84 4.51 29.10

.00 100.00 (2)

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.27

.32

.15

.04

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.17

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.00 3.02 (1)rPERCENT OF ALL 000D OBSERVATIONS FOR THIS PAGE (21sPERCEIFF OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 NPH) l l

(

TABLE 5B VERM0erf YANKEE JAN 95 - DEC 95 NETEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS S CIASS FREQUENCY (PERCENT)

=

2.80 WIND DIRECTICBI FRON I

I SPEED (NPH)

N ISfE NE ENE E ESE SE SSE S

SSW SW WSW W tent NW WW VRAL TOTAL f

CALM o

0 0

0 (1)

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C-3 2

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0 0

1 0

0 0

1 0

6 l

(1)

.88

.00

.88

.00

.44

.00

.44

.00 2.45 1

(2)

.02

.00

.02

.00

.01

.00

.01

.00

. 0."

l 4-1 2

1 4

2 3

2 8

8 5

3 1

0 0

1 1

9 0

50 i

(1)

.88

.44 1.77

.88 1.33

.88 3.54 3.54 2.21 1.33

.44

.00

.44

.44 3.98

.00 22.12

)

(2)

.02

.01

.05

.02

.04

.02

.10

.06

.04

.01

.00

.01

.11

.00

.62 8-12 9

1 0

0 0

2 4

10 13 8

1 2

6 3

1 13 0

73 (1) 3.98

.44

.00

.88 1.77 4.42 5.75 3.54

.44

.88 2.65 ~ 1.33

.44 5.75

.00 32.30 (2)

.11

.01

.00

.02

.05

.12

.16

.10

.01

.02

.07

.04

.01

.16

,00

.90 13-18 7

0 0

0 2

1 1

0 13 3

4 1

4 11 1

21 0

69 (1) 3.10

.00

.88

.44

.00 5.75 1.33 1,77

.44 1.77 4.87

.44 9.29 00 30.53 (2)

.09

.00

.02

.01

.00

.16

.04

.05

.01

.05

.14

.01

.26

.00

.85 19-24 1

0 0

0 3

0 0

0 1

4 3

0 0

20 (1)

.44

.00

.00 1.33

.00

.44 1.77 1.33 3.54

.00 8.85 (2)

.01

.00

.04

.00

.01

.05

.04

.10

.00

.25 0T 24 0

0 0

3 1

4 0

8 l

(1)

.00

.00 1.33

.44 1.77

.00 3.54 i

(2)

.00

.04

.01

.05

.00

.10 ALL SPEEDS 21 2

6 2

5 5

13 19 34 14 6

3 11 22 7

56 0

226 (1) 9.29

.88 2.65

.88 2.21 2.21 5.75 8.41 15.04 6.19 2.65 1.33 4.87 9.73 3.10 24.78

.00 100.00 (2)

.26

.02

.07

.02

.06

.16

.24

.42

.17

.07

.04

.14

.27

.09

.69

.00 2.80 (1)aPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAIE (2)aPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PE LIOD C3 CA1AI (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) l l

I I

= ~ _ _

l i

i TABLE SC l

VERNONT YAMLEE JAN 95 - DEC 95 NETSOR0 LOGICAL DATA J01WF FREQUSMCY DISTRIBUTION

(

297.0 PT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT)

=

3.91 WIND DIRECTION FROM i

l SPEED (NPH)

N 30fE NE ENE E ESE SE SSE S

SSW SW WSW W

WNW NW MRf VRBL TOTAL CAIJE O

0 0

0 (1) 00

.00

.00 (2)

.00

.00 C-3 1

0 1

2 0

1 3

1 0

0 0

1 0

12 t

(1)

.32

.00

.32

.63

.00

.32

.95

.32

.00

.32

.00

.32

.00

.32

.00 3.80 (2)

.01

.00

.01

.02

.00

.01

.04

.01

.00

.01

.00

.01

.00

.01

.00

.15 4-7 5

1 3

2 2

6 6

11 6

1 1

0 1

9 0

56 (1) 1.58

.32

.95

.63

.63 1.90 1.90 3.48 1.90

.32

.00

.32 2.85

.00 17.72 (2)

.06

.01

.04

.02

.07

.14

.07

.01

.00

.01

.11

.00

.69 8-12 11 1

0 0

3 8

5 7

16 6

1 2

10 9

6 24 0

109 (1) 3.48

.32

.00

.95 2.53 1.58 2.22 5.06 1.90

.32

.63 3.16 2.85 1.90 7.59

.00 34.49 (2)

.14

.01

.00

.04

.10

.06

.09

.20

.07

.01

.02

.12

.11

.07

.30

.00 1.35 13-18 10 1

1 0

0 0

0 3

10 4

2 1

7 16 9

29 0

93 (1) 3.16

.32

.00

.95 3.16 1.27

.63

.32 2.22 5.06 2.25 9.18

.00 29.43 (2)

.12

.01

.00

.04

.12

.05

.02

.01

.09

.20

.11

.36

.00 1.15 l

19-24 4

0 0

0 1

0 3

8 4

14 0

35 l

(1) 1.27

.00

.32

.00

.32

.00

.95 2.53 1.27 4.43

.00 11.08 (2)

.05

.00

.01

.00

.01

.00

.04

.10

.05

.17

.00

.43

?

GT 24 2

0 0

3 2

4 0

11 (1)

.63

.00

.00 00

.00

.95

.63 1.27

.00 3.48 (2)

.02

.00

.04

.02

.05

.00

.14 ALL SPEEDS 33 3

5 4

5 15 14 22 33 12 5

4 21 37 22 81 0

316 l

(1) 10.44

.95 1.58 1.27 1.58 4.75 4.43 6.96 10.44 3.80 1.58 1.27 6.65 11.71 6.96 25.63

.00 100.00 l

(2)

.41

.04

.06

.05

.06

.19

.17

.27

.41

.15

.06

.05

.26

.46

.27 1.00

.00 3.91 i

l (1)ePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PACE l

(2)aPERCENT OF ALL 000D OBSERVATIONS FOR THIS PERIOD l

Ca CAIJE (WIND SPEED LESS THAN OR EQUAL TO.95 MPH)

{

l 4 1

~..

m l

l 1

l l

TABLE SD VERHONT YAF.KEE JN4 95 - DEC 95 METEOROLOGICAL DATA JOINT PREQUENCY DISTRIBUTION 297.0 FT WIND DAfA STABILITY CLASS D CLASS FREQUENCY (PERCErf) = 43.75 WIND DIRECTION FROM SPEED (MPH)

N SSIE NE ENE E ESE SE SSE S

SSW SW WSW W telW NW BelW VRSL TOTAL CAIJi 0

1 0

0 0

1 1

0 0

3 (1)

.00

.03

.00

.03

.00

.08 (2)

.00

.01

.00

.01

.00

.04 C-3 45 25 21 18 24 32 47 40 23 18 11 14 14 18 24 29 0

403 (1) 1.27

.71

.59

.51

.68

.91 1.33 1.13

.65

.51

.31

.40

.51

.68

.82

.00 11.40 (2)

.56

.31

.26

.22

.30

.40

.58

.50

.28

.22

.14

.17

.11

.22

.30

.36

.00 4.99

(

4-7 119 48 21 15 42 67 93 105 102 23 10 12 10 21 32 177 0

897 (1) 3.37 1.36

.59

.42 1.19 1.90 2.63 2.97 2.89

.65

.28

.34

.28

.59

.91 5.01

.00 25.37 i

(2) 1.47

.59

.26

.19

.52

.83 1.15 1.30 1.26

.28

.12

.15

.12

.26

.40 2.19

.00 11.10 8-12 169 33 8

8 24 35 35 129 182 50 29 21 46 83 60 217 0

1129 l

(1) 4.78

.93

.23

.68

.99

.99 3.65 5.15 1.41

.82

.59 1.30 2.35 1.10 6.14

.00 31.94 (2) 2.09

.41

.10

.30

.43

.43 1.60 2.25

.62

.36

.26

.57 1.03 74 2.69

.00 13.97 13-18 112 13 0

2 4

0 9

21 90 30 9

17 46 107 119 223 0

802 (1) 3.17

.37

.00

.06

.11

.00

.25

.59 2.55

.85

.25

.48 1.30 3.03 3.37 6.31

.00 22.69 (2) 1.39

.26

.00

.02

.05

.00

.11

.26 1.11

.37

.11

.21

.57 1.32 1.47 2.76

.00 9.93 19-24 18 1

0 1

0 0

1 7

24 10 2

0 8

40 40 102 0

254 (1)

.51

.03

.00

.03

.00

.03

.20

.68

.28

.06

.00

.23 1.13 1.13 2.89

.00 7.19 l

(2)

.22

.01

.00

.01

.00

.01

.09

.30

.12

.02

.00

.10

.50

.50 1.26

.00 3.14 i

GT 24 1

0 0

1 3

1 1

0 1

14 2

23 0

47 i

l (1)

.03

.00

.03

.08

.03

.00

.03

.40

.06

.65

.00 1.33 I

(2)

.01

.00

.01

.04

.01

.00

.01

.17

.02

.28

.00

.58 ALL SPEEDS 464 121 50 44 94 134 185 303 424 132 62 64 125 284 278 771 0

3535 (1) 13.13 3.42 1.41 1.24 2.66 3.79 5.23 8.57 11.99 3.73 1.75 1.81 3.54 8.03 7.86 21.81

.00 100.00 (2) 5.74 1.50

.62

.54 1.16 1.66 2.29 3.75 5.25 1.63

.77 19 1.55 3.51 3.44 9.54

.00 43.75 (11sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2'sPERCErr OF ALL GOOD OSSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 NPH)

I f

4.

r,

__m i

i TABLE SE VERPONT YANREE JAN 95 - DEC 95 NETEOR01401 CAL DATA JOINT FREQUdNCY D187RIBt7f!ON 297.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) a 31.13 WIND DIRECTION FRON SPEED (MPH)

N NNE NE ONE E ESE SE SSE S

SSW SW WSW W

WIW NW BBlW VRSL TOTAL CAIJE 2

1 0

1 1

0 1

0 2

0 1

2 0

1 0

13 (1)

.08

.04

.00

.04

.00

.04

.00

.04

.00

.08

.00

.04

.08

.00

.04

.00

.52 (2)

.02

.01

.00

.01

.00

.01

.00

.01

.00

.02

.00

.01

.02

.00

.01

.00

.16 C-3 85 56 47 40 48 53 54 60 38 17 16 13 19 27 48 58 0

679 i

(1) 3.38 2.23 1.87 1.59 1.91 2.11 2.15 2.39 1.51

.68

.64

.52

.76 1.07 1.91 2.31

.00 27.00 (2) 1.05

.69

.58

.50

.59

.66

.67

.74

.47

.21

.20

.16

.24

.33

.59

.72

.00 8.40 4-7 148 25 14 15 16 30 99 102 76' 18 15 16 20 23 66 201 0

884 (1) 5.88

.99

.56

.60

.64 1.19 3.94 4.06 3.02

.72

.60

.64

.80

.91 2.62 7.99

.00 35.15 (2) 1.83

.31

.17

.19

.20

.37 1.23 1.26

.94

.22

.19

.20

.25

.28

.82 2.49

.00 10.94 8-12 OS 8

0 0

1 8

13 72 64 30 8

13 37 45 59 203 0

649 (1) 3.50

.32

.00

.04

.32

.52 2.86 2.54 1.19

.32

.52 1.47 1.79 2.35 8.07

.00 25.81 (2) 1.09

.10

.00

.01

.10

.16

.89

,79

.37

.10

.16

.46

.56

.73 2.51

.00 8.03 13-18 21 2

0 0

0 1

4 12 41 18 4

2 15 30 23 80 0

253 (1)

.83

.08

.00

.04

.16

.48 1.63

.72

.16

.08

.60 1.19

.91 3.18

.00 10.06 (2)

.26

.02

.00

.01

.05

.25

.51

.22

.05

.02

.19

.37

.28

.99

.00 3.13 19-24 4

0 0

1 9

1 0

0 0

4 4

9 0

32 (1)

.16

.00

.04

.36

.04

.00

.16

.36

.00 1.27 (2)

.05

.00

.00'

.00

.01

.11

.01

.00

.05

.11

.00

.40 GT 24 2

0 0

2 1

0 0

5 (1)

.08

.00

.08

.04

.00

.20 (2)

.02

.00

.02

.01

.00

.06 ALL SPEEDS 350 92 61 56 65 93 171 249 230 84 45 44 92 131 200 552 0

2515 (1) 13.92 3.66 2.43 2.23 2.58 3.70 6.80 9.90 9.15 3.34 1.79 1.75 3.66 5.21 7.95 21.95

.00 100.00 (2) 4.33 1.14

.75

.69

.80 1.15 2.12 3.08 2.85 1.04

.56

.54 1.14 1.62 2.48 6.83

.00 31.13 (1)aPERCEDrf 0F ALL GOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OSSERVATIONS FOR THIS PERIOD Co CAIJE (WIND SPEED LESS THAN OR EQUAL 70

.95 MPH) i 1

- - - ~ -.

~ ~ -

1 l

l i

TABLE 5F l

VERMONT YANKEE JAN 95 - DEC 95 NETEOROLCCICAL DATA JOINT FREQUENCY DISTRIBtPFION 1

297.0 FT WIND DATA STSBILITY CLASS F CIASS FREQUENCY (PERCENT) = 13.42 WIND DIRECTION FRON I

I I

l SPEED (MPH)

N MNE NE ENE E

ESE SE SSE S

SSW SW WSW W

MMW NW SSIW VR3L TOTAL j

l CAlat 0

1 2

0 0

0 1

0 0

1 0

0 0

5 l

(1)

.00

.09

.18

.00

.09

.00 00

.09

.00

.46 i

(2)

.00

.01

.02

.00

.01

.00

.01

.00

.06 I

t C-3 53 36 32 32 23 31 53 32 29 12 20 10 14 9

17 26 0

429 I

(1) 4.89 3.32 2.95 2.95 2.12 2.86 4.89 2.95 2.68 1.11 1.85

.92 1.29

.83 1.57 2.40

.00 39.58 (2)

.66

.45

.40

.28

.38

.66

.40

.36

.15

.25

.12

.17

.11

.21

.32

.00 5.31 4-7 60 10 1

6 19 22 52 49 23 9

13 13 17 17 24 95 0

430 i

(1) 5.54

.92

.09

.55 1.75 2.03 4.80 4.52 2.12

.83 1.20 1.20 1.57 1.57 2.21 8.76

.00 39.67 (2)

.74

.12

.01

.07

.24

.27

.64

.61

.28

.11

.16

.21

.30 1.18

.00 5.32

(.

8-12 18 1

0 0

0 2

7 11 7

7 8

8 14 12 12 92 0

199 (1) 1.66

.09

.00

.18

.65 1.01

.65

.74

.74 1.29 1.11 1.11 8.49

.00 18.36 (2)

.22

.01

.00

.02

.09

.14

.09

.10

.17

.15

.15 1.14

.00 2.46 13-18 2

0 0

3 0

0 0

0 2

2 2

9 0

20 (1)

.18

.00

.28

.00

.18

.83

.00 4.85 (2)

.02

.00

-. 0 0

.00

.04

.00

.02

.11

.00

.25 19-24 0

0 0

1 0

0 0

1 l

(1)

.00

.09

.00

.09 l

(2)

.00

.01 00

.00

.01 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

' ALL SPEEDS 133 48 35 38 42 55 112 95 59 28 42 31 47 42 55 222 0

1084 l

(1) 12.27 4.43 3.23 3.51 3.87 5.07 10.33 8.76 5.44 2.58 3.87 2.06 4.34 3.87 5.07 20.48

.00 100.00 (2) 1.65

.59

.43

.47

.52

.68 1.39 1.18

.73

.35

.52

.38

.58

.52

.68 2.75

.00 13.42 l

f (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE j

(21sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Cs CAIJE (WIND SPEED LESS THAN OR EQUAL To

.95 NPH) l i - - - -

I I

i l

l I

TABLE SG l

l VERaGrf YANKEE JAN 95 - DEC 95 NETEORO14GICAL DATA JOINT FREQUENCY DISTRISLTf!ON l

297.0 PT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT)

=

1.98 i

WIND DIRECTION FROM I

l' fPBED(NPH)

N mfE NE ENE E

ESE SE SSE S

SSW SW WSW W

NNN NW NNW VERL TOTAL CAIJi 0

0 0

0 (1)

.00

.00 l

(2)

.00

.00 C-3 2

2 1

1 2

2 7

4 2

2 3

1 2

4 4

3 0

42 (1) 1.25 1.25

.63

.63 1.25 1.25 4.38 2.50 1.25 1.25 1.88

.63 1.25 2.50 2.50 1.88

.00 26.25 (2)

.02

.01

.02

.09

.05

.02

.04

.01

.02

.05

.04

.00

.52 4-7 6

0 0

1 0

2 9

10 8

1 7

3 8

4 4

5 0

68 (1) 3.75

.00

.63

.00 1.25 5.63 6.25 5.00

.63 4.38 1.88 5.00 2.50 2.50 3.13

.00 42.50 (2)

.07

.00

.01

.00

.02

.11

.12

.10

.01

.09

.04

.10

.05

.06

.00

.84 8 12 '

1 0

0 0

0 1

1 4

3 1

2 1

8 4

1 17 0

44 (2 )

.63

.00

.63

.63 2.50 1.88

.63 1.25

.63 5.00 2.50 63 10.63

.00 27.50 (2)

.01

.00

.01

.05

.04

.01

.02

.01

.10

.05

.01

.21

.00

.54 I

13-18 0

0 0

0 2

1 0

0 1

1 0

6 (1)

.00

.00 1.25

.63

.00

.63

.00

.63

.00 3.75 l

(2)

.00

.02

.01

.00

.01

.00

.01

.00

.07 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 i

GT 24 0

0 0

0 (1)

.00

.C0

.00

.00 (2)

.00

.00 l

l ALL SPEEDS 9

2 1

2 2

5 17 18 15 5

12 5

19 13 9

26 0

160 (1) 5.63 1.25

.63 1.25 1.25 3.13 10.63 11.25 9.38 3.13 7.50 3.13 11.88 8.13 5.63 16.25

.00 100.00 (2)

.11

.02

.01

.02

.06

.21

.22

.19

-. 0 6

.15

.06

.24

.16

.11

.32

.00 1.98 I

i (1)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)rPERCE3rr OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C2 CAIJE (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) l l

l 4

I

TABLE SH v

VERNOBFF YANKEE JAN 95 - DEC 95 NETBOROLOGICAL DATA JOI3rr FREQUENCY DISTRIBt7FION 297.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 NIND DIRECTION FRON (PEED (NPH)

N ISfE NE ENI.

E ESE SE SSE S

SSF SN NSN N

ISIN NN lebt VRBL TOTAL CAIJi 2

3 2

1 0

1 1

0 1

0 3

0 1

4 1

1 0'

21 (1)

.02

.04

.02

.01

.00

.01

.00

.01

.00

.04

.00

.01

.05

.01

.00

.26 (2)

.02

.04

.02

.01

.00

.01

.00

.01

.00

.04

.00

.01

.05

.01

.00

.26 C-3 188 120 104 94 98 122 164 141 92 51 50 38 49 59 93 110

-0 1581

' (1) 2.33 1.49 1.29 1.16 1.21 1.51 2.03 1.75 1.14

.63

.62

.47

.61

.73 1.15 1.46

.00 19.57 (2) 2.33 1.49 1.29 1.16 1.21 1.51 2.03 1.75 1.14

.63

.62

.47

.61

.73 1.15 1.46

.00 19.57 4-7 245 90 43 41 83 136 271 294 226 58 48 47 58 69 129 509 0

2447 (1) 4.27 1.11

.53

.51 1.03 1.68 3.35 3.64 2.80

.72

.59

.58

.72

.85 1.60 6.30

.00 30.28 (2) 4.27 1.11

.53

.51 1.03 1.68 3.35 3.64 2.80

.72

.59

.58 72

.85 1.60 6.30

.00 30.28 8-12 306 44 8

8 28 60 68 241 297 106 51 47 126 158 141 585 0

2274 (1) 3.79

.54

.10

.35

.74

.84 2.98 3.68 1.31

.63

.58 1.56 1.96 1.75 7.24

.00 28.14 (2) 3.79

.54

.10

.35

.74

.84 2.98 3.68 1.31

.63

.58 1.56 1.96 1.75 7.24

.00 28.14

(

13-18 156 le 1

2 6

5 15 41 163 60 19 21 79 180 159 382 0

1307 (1) 1.93

.22

.01

.02

.07

.06

.19

.51 2.02 74

.24

.26

.98 2.23 1.97 4.73

.00 16.18 (2) 1.93

.22

.01

.02

.07

.06

.19

.51 2.02

.74

.24

.26

.98 2.23 1.97 4.73

.00 16.18 19-24 31 1

0 1

0 0

1 8

38 11 3

0 15 60 51 141 0

361 (1)

.30

.01

.00

.01

.00

.01

.30

.47

.14

.04

.00

.19

.74

.63 '1.75

.00 4.47 (2)

.30

.01

.00

.01

.00

.01

.10

.47

.14

.04

.00

.19

.74

.63 1.75

.00 4.47 GT 24 5

0 0

'O 0

3 4

1 1

0 1

23 8

43 0

89 (1)

.06

.00

.04

.05

.01

.00

.01

.28

.10

.53

.00 1.10 (2)

.06

.00

.04

.05

.01

.00

.01

.28

.10

.53

.00 1.10 ALL SPEEDS 1033 276 158 147 215 324 520 728 821 287 175 153 329 553 582 1779 0

8080 (1) 12.78 3.42 1.96 1.82 2.46 4.01 6.44 9.01 10.16 3.55 2.17 1.89 4.07 6.84 7.20 22.02

.00 100.00 (2) 12.78 3.42 1.96 1.82 2.66 4.01 6.44 9.01 10.16 3.55 2.17 1.89 4.07 6.84 7.20 22.02

.00 100.00 (1)sPERCENT OF ALL OOOD ORSERVATIONS FOR THIS PAGE (2)sPERCENT OF ALL GOOD OdSERVATIONS FOR THIS PERIOD Cs CAIJE (NIND SPEED LESS THAN OR SQUAL TO

.95 NPH) ___

l 1

i 1

i I

1 TABLF 6A l

VERNONf YANKEE JAN 95 - DEC 95 NETEOROLOGICAL DATA JOINF FREQUENCY DISTRIBUTION l

35.0 FT WIND DATA STABILITY CIASS A CIASS FREQUENCY (PERCENT)

=

4.18 l

WIND DIRECTION FRON I

! srEED(NrH) u NNE wE ENE E EsE sE ssE s ssw sN wsw w uNN NN mw vRn1.

ToTAI.

CArm 0

0 0

0 (1)

.00

.00 t

(2)

.00

.00 C-3 3

7 4

5 6

5 4

4 1

1 2

0 0

0 1

1 0

44.

l (1)

.87 2.03 1.16 1.45 1.74 1.45 1.16 1.16

.2)

.29

.58

.00

.29

.00 12.75 i

(2)

.04

.08

.05

.06

.07

.06

.05

.0L

.01

.02

.00

.01

.00

.53 1

l 4-1 15 8

3 13 11 11 10 16 17 9

2 4

4 7

11 31 0

172 (1) 4.35 2.32

.87 3.77 3.19 3.19 2.90 4.64 4.93 2.61

.58 1.16 1.16 2.03 3.19 8.99

.00 49.86 (2)

.18

.10

.04

.16

.13

.12

.19

.21

.11

.02

.05

.08

.13

.38

.00 2.08 8-12 17 2

0 0

0 5

9 4

0 1

0 15 8

28 0

102 (1) 4.93

.58

.00

.00 1.45

.00 1.45 2.61 1.16

.00

.29 2.32 4.35 2.32 8.12

.00 29.57 (2)

.21

.02

.00

.06

.00

.06

.11

.05

.00

.01

.10

.18

.10

.34

.00 1.24 13-18 5

0 0

0 3

7 2

6 0

23 (1) 1.45

.00

.87 2.03

.58 1.74

.00 6.67 (2)

.06

.00

.04

.08

.02

.07

.00

.28 19-24 2

0 0

1 1

0 0

4 (1)

.58

.00

.29

.00

.00 1.16 l

(2)

.02

.00

.01

.00

.05 GT 24 0

0 0

0 l

(1)

.00

.00 l

(2)

.00

.00 1

l ALL SPEEDS 42 17 7

18 17 21 14 25 27 14 4

5 15 30 23 66 0

345 (1) 12.17 4.93 2.03 5.22 4.93 6.03 4.06 7.25 7.83 4.06 1.16 1.45 4.35 8.70 6.67 19.13

.00 100.00 (2)

.51

.21

.08

.22

.21

.25

.17

.30

.33

.17

.05

.06

.18

.36

.28

.80

.00 4.18 i

(1)sPERCENT OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2)mPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ca CAIM (WIND SPEED LESS THAN OR EQUAL TO

.95 NPH) l l

i i l

1

(

{

(

TABLE 6B VERN0Brr YANKEE JAN 95 - DEC 95 NETEOR0 LOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CIA 88 8 CIASS FREQUENCY (PERCENT) e 2.73 WIND DIRSCTION FROM SPEED (NPH)

N BerE NE ENE E ESE SE SSE S

SSW SN WSW W

Mai NW BBAf VRSL TOTAL CAIJI O

O O

O 0

0 0

0 (1)

.00

.00 (2)

.00

.00 C-3 1

1 2

2 3

2 1

1 1

2 1

0 0

1 0

18 (1)

.44

.89 89 1.33

.89

.44

.89

.44

.00

.44

.00 8.00 (2)

.01

.02

.04

.02

.01

.02

.01

.00

.01

.00

.22 4-7 18 4

3 5

3 10 4

6 5

4 0

3 4

2

.6 16 0

93 (1) 8.00 1.78 1.33 2.22 1.33 4.44 1.78 2.67 2.22 1.78

.00 1.33 1.78

.89 2.67 7.11

.00 41.33 (2)

.22

.05

.04

.06

.04

.22

.05

.07

.06

.05

.00

.04

.05

.02

.07

.19

.00 1.13 8-12 19 3

0 0

0 3

1 1

14 6

0 2

4 16 4

13 0

86 (1) 8.44 1.33

.00

.00 1.33

.44

.44 6.22 2.67

. 00

.89 1.78 7.11 1.75 5.78

.00 38.22 (2)

.23

.04

.00

.04

.01

.17

.07

.00

.02

.05

.19

.05

.16

.00 1.04 13-18 3

2 0

0 0

0 3

1 0

0 1

6 2

4 0

22 (1) 1.33

.89

.00

.00 1.33

.44

.00

.44 2.67

.89 1.78

.00 9.78 (2)

.04

.02

.00

.04

.01

.00

.01

.07

.02

.05

.00

.27 19-24 0

0 0

2 3

0 0

5 (1)

.00

.89 1.33

.00

.00 2.22 (2)

.00

.02

.04

.00

.06 07 24 0

0 0

0 1

0 0

1 (1)

.00

.44

.00

.44 (2)

.00

. 00

.00

.01

.00

.01 ALL SPEEDS 41 10 5

7 6

15 6

8 23 13 1

5 9

26 16 34 0

225 (1) 18.22 4.44 2.22' 3.11 2.67 6.67 2.67 3.56 10.22 5.18

.44 2.22 4.00 11.56 7.11 15.11

.00 100.00 (2)

.50

.12

.06

.08

.07

.18

.07

.10

.28

.16

.01

.06

.11

.32

.19

.41

.00 2.73 (lisPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (21sPERCENT OF ALL GOOD OSSERVATIONS FOR THIS PERIOD Ce CAIJi (WIND SPEED LESS THAN OR EQUAL TO

.95 NPH)

{

{ L F

i

l l

l TABLE 6C VERMONT YANKEE JAN 95 - DEC 95 NETEOROLOGICAL DATA JOINT FREQUENCY DISTRIBiff!ON 35.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCDrr) 3.59

=

WIND DIRECTION FRON l

f SPEED (NPH)

N NNE NE ENE E

ESE SE W.

S SSW SW WSW W

tefW NW ISfW VRBL TOTAL i

CAIR 0

0 0

0 (1)

.00

.00'

.00

.00 l

(2)

.00

.00 C-3 2

2 2

0 3

1 2

2 2

1 1

1 0

0 0

1 0

20 (1)

.68

.00 1.01

.34

.68

.34

.00

.34

.00 6.76 (2)

.02

.00

.04

.01

.02

.01

.00

.01

.00

.24 4-7 20 5

3 9

11 8

17 13 5

3 1

7 5

8 27 0

147 (1) 6.76 1.69 1.69 1.01 3.04 3.72 2.70 5.74 4.39 1,69 1.01

.34 2.36 1.69 2.70 9.12

.00 49.66 j

(2)

.24

.06

.04

.11

.13

.10

.21

.16

.06

.04

.01

.08

.06

.10

.33

.00 1.78 8-12 20 2

0 0

1 2

0 2

16 6

2 2

13 9

16 14 0

105 (1) 6.76

.68

.00

.34

.68

.00

.68 5.41 2.03

.68

.68 4.39 3.04 5.41 4.73

.00 35.47 (2)

.24

.02

.00

.01

.02

.00

.02

.19

.07

.02

.16

.11

.19

.17

.00 1.27 13-18 2

0 0

0 5

0 0

0 1

5 6

4 0

23 i

(1)

.68

.00

.00 1.69

.00

.34 1.69 2.03 1.35

.00 7.77 (2)

.02

.00

.06

.00

.01

.06

.07

.05

.00

.28 19-24 0

0 0

0 1

0 0

1 (1)

.00

.34

.00

.34 (2)

.00

.03

.01

.00

.01 GT 24 0

0 0

J 0

0 0

0 (1)

.00

.00 (2)

.00

.00 l

I ALL SPEEDS 44 9

7 3

13 14 10 21 36 12 6

4 21 19 31 46 0

296 i

(1) 14.86 3.04 2.36 1.01 4.39 4.73 3.38 7.09 12.16 4.05 2.03 1.35 7.09 6.42 10.47 15.54

.00 100.00 (2)

.53

.11

.08

.04

.16

.17

.12

.25

.44

.15

.07

.05

.25

.23

.38

.56

.00 3.59 (1)aPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE l

(2)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Cs CAIA (WIND SPEED LESS THAN OR EQUAL TO

.95 NPH) l f

i l l

l

{

TABLE 6D VEme0NT YANKEE JAN 95 - DEC 95 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY C1 ASS D CLASS FREQUENCY (PERCENT) = 35.82 WIND DIRECTION PRON SPEED (MPH)

N SSIE NE ENE E

ESE SE SSE S

SSW SW WSW W

DSM NW ISIW VRSL TOTAL CA!Je 0

0 0

0 1

0 0

1 (1) 00

.00

.03

.00

.03 (2)

.00

.00 00

.00

.01

.00

.01 C-3 88 44 47 39 46 44 35 50 35 25 22 19 31 24 48 104 0

701 (1) 2.98 1.49 1.59 1.32 1,56 1.49 1.18 1.69 1.18

.85 74

.64 1.05

.81 1.62 3.52

.00 23.72 (2) 1.07

.53 57

.47

.56

.53

.42

.61

.42

.30

.27

.23

.38

.29

.58 1.26

.00 8.50 4-7 226 60 19 24 59 64 60 153 150 32 34 29 42 67 81 254 0

1354 (1) 7.65 2.03 64

.81 2.00 2.17 2.03 5.18 5.08 1.08 1.15

.98 1.42 2.27 2.74 8.60

.00 45.82 (2) 2.74

.73

.23

.29

.72

.78

.73 1.85 1.82

.39

.41

.35

.51

.81

.98 3.08

.00 16.41 8-12 134 27 1

1 7

6 3

24 108 28 18 11 48 113 101 117 0

747 (1) 4.53

.91 03

.03

.24

.20

.10

.81 3.65

.95

.61

.37 1.62 3.82 3.42 3.96

.00 25.28 (2) 1.62

.33 01

.01

.08

.07

.04

.29 1.31

.34

.22

.13

.58 1.37 1.22 1.42

.00 9.05 13-18 15 1

0 0

0 1

0 2

18 4

1 0

8 48 37 9

0 144 (1)

.51

.03

.00

.03

.00

.07

. 61

.14

.03

.00

.27 -1.62 1.25

.30

.00 4.87 (2)

.18

.01

.00

.01

.00

.02

.22

.05

.01

.00

.10

.58

.45

.11

.00 1.75 19-24 0

0 0

0 1

0 0

5 2

0 0

8 (1)

.00

.00 00

.00

.03

.00

.17

.07

.00

.27 (2)

.00

.01

.00

.06

.02

.00

.00 10 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 463 132 67 64 112 115 98 229 312 89 76 59 129 257 269 404 0

2955 (1) 15.67 4.47 2.27 2.17 3.79 3.89 3.32 7.75 10.56 3.01 2.57 2.00 4.37 8.70 9.10 16.38

.00 100.00

[

(2) 5.61 1.60

.81

.78 1.36 1.39 1.19 2.78 3.78 1.08

.92

.72 1.56 3.12 3.26 5.87

.00 35.82

('.

(1)sPERCEbrT OF ALL 000D OBSERVATIONS FOR THIS PAGE l

(2taPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CAIJE (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) 1 f

(

( L i

.__.2.

I

{

TABI2E 6E VERMONT YANKEE JAN 95 - DEC 95 NETEOR0 LOGICAL DATA JOI M FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CIASS E CIASS FREQUENCY (PERCENT) = 33.73 WIND DIRECTION FROM CPEED(MPH)

N NNE NE ENE E ESE SE SSE S

SSW SW WSW W

NNW NW DefW VRBL TOTAL CAIJE O

0 0

1 1

0 0

0 2

1 2

0 0

2 0

11 (1)

.00

.04

.00

.07

.00

.07

.04

.07

.00

.07

.00

.40 (2)

.00

.01

.00

.02

.00

.02

.01

.02

.00

.02

.00

.13 C-3 90 43 35 32 30 33 47 81 96 106 169 131 142 119 122 182 0

1458 (1) 3.23 1,55 1.26 1.15 1.00 1.19 1,69 2.91 3.45 3.81 6.07 4.71 5.10 4.28 4.38 6.54

.00 52.39 (2) 1.09

.52

.42

.39

.36

.40

.57

.98 1.16 1.28 2.05 1.59 1.72 1.44 1.48 2.21

.00 17.67 4-7 93 19 7

5 10 29 36 134 96 36 22 34 77 79 123 204 0

1004 (1) 3.34

.68

.25

.18

.36 1.04 1.29 4.81 3.45 1.29 79 1.22 2.77 2.84 4.42 7.33

.00 36.08 (2) 1.13

.23

.08

.06

.12

.35

.44 1.62 1.16

.44

.27

.41

.93

.96 1.49 2.47

.00 12.17 8-12 19 1

0 0

1 1

4 19 59 6

2 5

15 54 49 37 0

272 (1)

.68

.04

.00

.04

.14

.68 2.12

.22

.07

.18

.54 1.94 1.76 1.33

.00 9.77 (2)

.23

.01

.00

.01

.05

.23 72

.07

.02

.06

.18

.65

.59

.45

.00 3.30 13-18 3

0 0

0 1

4 11 0

1 0

1 9

0 0

0 38 (1)

.11

.00

.04

.14

.40

.00

.04

.00

.04

.32

.29

.00

.00 1.37 (2)

.04

.00

.01

.05

.13

.00

.01

.00

.01

.11

.10

.00

.46 f

19-24 0

0 0

0 t

(1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0

[

(1)

.00

(

(2)

.00

.40 ALL SPEEDS 205 63 42 38 42 63 88 238 264 148 196 171 237 261 302 425 0

2783 (1) 7.37 2.26 1.51 1.37 1.51 2.26 3.16 8.55 9.49 5.32 7.04 6.14 8.52 9.38 10,85 15.27

.00 100.00 (2) 3.48

.76

.51

.46

.51

.76 1.07 2.88 3.20 1.79 2.38 2.07 2.87 3.16 3.66 5.15

.00 33.73 I

(1)sPERCIbrf OF ALL 000D OBSERVATIONS FOR THIS PAGE (21sPERCEM OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO

.95 NPH) l

(

l f <

I r

[

TABLE 6F VERN0erf YANKEE JAN 95 - DEC 95 NETEOROLOGICAL DATA JODrf FREQUENCY DISTRIBL7FION 35.0 FT WIND DATA STABILITY CLASS F CIASS FREQUENCY (PERCENT) = 15.56 WIND DIRECTION FROM SPEED (NPM)

N

$3fB NE ENE E ESE SE SSE S SSW SW WSW W

tefW NW BBAf VRSL TOTAL CAIJi 0

0 0

1 0

0 2

0 0

3

~

(1)

.00

.16

.00

.23 (2)

.00

.01

. 00

.00

.02 00

.00

.04 C-3 28 14 14 12 8

16 15 30 39 116 228 196 174 110 89 52 0

1141

.(1) 2.18 1.09 1.09

.93

.62 1.25 1.17 2.34 3.04 9.03 17.76 15.26 13.55 8.57 6.93 4.05

.00 88.86 (2)

.34

.17

.15

.30

.19

.18

.36

.47 1.41 2.76 2.38 2.11 1.33 1.08

.63

.00 13.83 4-7 8

2 0

0 1

2 4

6 2

13 21 9

17 17 17 17 0

136 L

(1)

.62

.16

.00

.08

.16

.31

.47

.16 1.01 1.64

.70 1.32 1.32 1.32 1.32

.00 10.59 (2)

.10

.02

.00.

.00

.01

.02

.05

.07

.02

.16

.25

.11

.21

.00 1.65 8-12 0

0 0

0 1

1 0

0 0

3

(

(1)

.00

.08

.00

.08

.00

.23 (2)

.00

.00 00

.00

.01

.00

.01

.00

.04 13-18 0

0 0

1 0

0 0

1 (1)

.00

.08

.00

.08 (2)

.00

.01

.00

.01 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.C0

.00

.00 ALL SPEEDS 36 16 14 12 9

18 19 36 41 129 250 206 192 129 108 69 0

1284

['

(1) 2.80 1.25 1.09

.93

.70 1.40 1.48 2.80 3.19 10.05 19.47 16.04 14.95 10.05 8.41 5.37

.00 100.00 (2)

.44

.19

.17

.15

.11

.22

.23

.44

.50 1.56 3.03 2.50 2.33 1,56 1.31

.84

.00 15.f6 (1)sPERCE3FF OF ALL GOOD OBSERVATIONS FOR THIS PAGE (21sPERCEBrf OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Co CAIJE (WIND SPEED LESS THAN OR EQUAL 70

.95 NPH)

[

(

[ ?

l' L

l I

l l

TABLE 6G l

l VERNOW YANKEE JAN 95 - DEC 95 NETEOR01401 CAL DATA JOIDFF FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS O CLASS FREQUENCY (PERCENT) e 4.39 WIND DIRECTION FRON SPEED (NPN)

N DBfB NE ENE E ESE SE SSE S

SSN EN wSN w gent 3hi BEIN VRBL TOTAL l

CAIJE O

O 0

0 0

0 (1)

.00

.00 (2)

.00

. 00 '.00

.00

.00 C-3 9

7 9

5 8

5 4

15 26 38 60 49 29 23 11 13 0

311 (1) 2.49 1.93 2.49 1.38 2.21 1,38 1.10 4.14 7.18 10.50 16.57 13.54 8.01 6.35 3.04 3.59

.00 85.91 (2)

.11

.08

.11

.06

.10

.06

. 05 -

.18

.32

.46

.73 459

.35

.28

.13

.26

.00 3.77 I

4-7 3

1 1

1 0

3 3

3 14 3

2 4

4 7

0 50 (1)

.83

.28

.00

.28

.00

.83

.83 3.87

.83

.55 1.10 1.10 1.93

.00 13.81 (2)

.04

.01

.00

.01

.00

.04

.17

.04

.02

.05

.08

.00

.61 0 12 0

0 0

0 (1)

.00

.00 (2)

.00

.00 13-18 0

0 0

1 0

0 0

1 (1)

.00

.8

.00

.28 (2)

.00

.01

.00

.01 19-24 0

0 0

C 0

0 0

0 I

(1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 12 8

10 6

8 6

4 18 29 41 74 52 31 28 15 20 0

362 (1) 3.31 2.21 2.76 1.66 2.21 1.66 1.10 4.97 8.01 11.33 20.44 14.36 8.56 7.73 4.14 5.52

.00 100.00 (2)

.15

.10

.12

.07

.10

.07

.05

.22

.35

.50

.90

.63

.38

.34

.18

.24

.00 4.39 l

(1)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)rPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CA!Ji (NIND SPEED LESS THAN OR EQUAL TO.95 MPH) l l

i

' t i

TABLE 6H VERMONT YANKEE JAN 95 - DEC 95 NETEOROLOGICAL DATA JOINT FREQUENCY DISTRIBtFFION 35.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FRON SPEED (NPH)

N NNE WE ENE E ESE SE SSE S SSW SW WSW W

W NN BBRf VRSL TOTAL CALN 0

0 0

1 1

0 0

0 2

0 3

2 2

0 2

2 0

15 (1)

.00

.01

.00

.02

.00

.04

.02

.00

.02

.00

.18 (2)

.00

.01

.00

.02

.00

.04

.02

.00

.02

.00-

.18 C-3 221 118 113 95 104 106 108 183 200 289 483 396 376 276 271 354 0

3693 (1) 2.68 1.43 1.37 1.15 1.26 1.28 1.31 2.22 2.42 3.50 5.85 4.80 4.56 3.35 3.28 4.29

.00 44.76 (2) 2.68 1.43 1.37 1.15 1.26 1.28 1.31 2.22 2.42 3.50 5.85 4.80 4.56 3.35 3.28 4.29

.00 44.76 4-7 383 99 38 51 93 128 122 335 286 102 96 83 153 181 250 556 0

2956 (1) 4.64 1.20

.46

.62 1.13 1.55 1.48 4.06 3.47 1.24 1.16 '1.01 1.85 2.19 3.03 6.74

.00 35.83 (2) 4.64 1.20

.46

.62 1.13 1.55 1.48 4.06 3.47 1.24 1.16 1.01 1.85 2.19 3.03 6.74

.00 35.83 8-12 209 35 1

1 9

17 8

51 206 50 23 21 89 208 178 209 0

1315

]

(1) 2.53

.42

.01

.11

.21

.10

.62 2.50

.61

.28

.25 1.08 2.52 2.16 2.53

.00 15.94 (2) 2.53

.42

.01

.11

.21

.10

.62 2.50

.61

.28

.25 1.08 2.52 2.16 2.53

.00 15.94 1

13-18 28 3

0 0

0 1

1 6

37 5

2 0

14 77 55 23 0

252 (1)

.34

.04

.00

.01

.07

.45

.06

.02

.00

.17

.93

.67

.28

.00 3.05 (2)

.34

.04

.00

.01

.h

.07

.45

.06

.02

.00

.17

.93

.67

.28

.00 3.05 19-24 2

0 0

0 1

0 0

8 7

0 0

18 (1)

.02

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.0;

.00 01

.00

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0 0

0 1

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.00

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.00

.01 ALL SPEEDS 843 255 152 148 207 252 239 575 732 446 607 502 634 750 764 1144 0

8250 (1) 10.22 3.09 1.84 1.79 2.51 3.05 2.90 6.97 8.87 5.41 7.36 6.08 7.68 9.09 9.26 13.87

.00 100.00 (2) 10.22 3.09 1.84 1.79 2.51 3.05 2.90 6.97 8.87 5.41 7.36 6.08 7.68 9.09 9.26 13.87

.00 100.00 (1)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)e: PERCENT OF ALL OOOD OBSERVATIONS FOR THIS PERIOD Ca CAIJE (WIND SPEED LESS THAN OR EQUAL TO

.95 MPH) l' t

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APPENDIX A l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Supplemental Information for 1995 Facility:

Vermont Yankee Nuclear Power Station Licensee:

Vermont Yankee Nuclear Power Corooration j

1A.

TECHNICAL SPECIFICATION LIMITS - DOSE AND DOSE RATE l

Technical Specification and Catecory Limit a.

Noble Gases 3.8.E.1 Total body dose rate 500 mrem /yr

)

l 3.8.E.1 Skin dose rate 3000 mrem /yr j

3.8.F.1 Gamma air dose 5 mrad in a quarter 3.8.F.1 Gamma air dose 10 mrad in a year j

3.8.F.1 Beta air dose 10 mrad in a quarter 1

3.8.F.1 Beta air dose 20 mrad in a year l

b.

Iodine-131. Iodine 133. Tritium and Radionuclides in Particulate l

Form With Half-Lives Greater Than 8 Days i

3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter l

3.8.G.1 Organ dose 15 mrem in a year i

c.

Liauids 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 mrem in a year i

3.8.B.1 Organ dose 5 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year i

4 i

e m 6o A-1

l APPENDIX A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2A.

TECHNICAL SPECIFICATION llMITS - CONCENTRATION Technical SDecification and Cateaory Limit a.

Noble Gases No MPC Limits (No ECL Limits) b.

Iodine 131. lodine-133. Tritium and Radionuclides in Particulate Form With Half-lives i

Greater Than 8 Days No MPC Limits (No ECL Limits)

{

c.

Liovids 3.8.A.1 Total fraction of MPC (ECL) excluding noble gases i

(10CFR20, Appendix B.

Table II, Column 2):

f1.0 i

l 3.8.A.1 Total noble gas concentration: f2E-04 pCi/cc 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 gamma energy:

1st Quarter 8.11E-01 MeV/ dis 2nd Quarter 8.31E-01 MeV/ dis 3rd Ouarter 8.17E-01 MeV/ dis 4th Quarter-8.18E-01 MeV/ dis 1

b.

Average beta energy:

Not Applicable l

4.

MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY Provided below are the methods used to measure or approximate the ' total l

radioactivity in effluents and the methods used to determine radionuclide composition.

i f

euuo A-2

1 l

)

APPENDIX A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT a.

Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity

{

released from the plant stack.

Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present.

These are used to calculate the individual isotopic releases indicated in Table IB and the totals of Table 1A.

The error involved in these steps may be approximately 1100 percent.

b.

Todines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge.

The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately 150 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.

Waste Oil Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in Technical Specification Table 4.8.1.

Samples that have a visible water layer are not analyzed. The water must first be removed from the drum of oil and resampled.

Monthly, samples from drums that were issued burn permits are sent to the E-Lab for compositing and analysis.

The E-L6b analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample.

am6o A-3

APPENDIX A I

(Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT The waste oil samples are liquid effluents that end up as a gaseous ground level release.

l The composite waste oil sample for March did not meet the required a priori LLDs because the sample volume available for the composite was not adequate to meet the LLDs. The required LLDs and the achieved LLDs are listed below:

Required a priori LLD LLD Achieved Alpha

<1E-07 pCi/ml

<1.40E-06 C1/ml H-3

<1E-05 pCi/ml

<2.10E-04 pCi/ml Fe-55

<1E-06 pCi/mi

<2.00E-05 pCi/ml Sr-89

<5E-08 pCi/ml

<1.20E-06 pCi/ml Sr-90

<5E-08 pCi/mi

<9.20E-07 pCi/ml 1

i e.

Liauid Effluents Radioactive liquid effluents released from the facility are continuously monitored.

Measurements are also made on a representative sample of each batch of radioactive liquid effluents l

released.

For each batch, station records are retained of the total activity (mC1) released, concentration (pC1/ml) of gross l

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 releases is analyzed for j

gross gamma and gamma isotopic radioactivity.

A monthly proportional composite sample, comprising an aliquot of each batch

)

released during a month, is analyzed for tritium and' gross alpha radioactivity. A quarterly proportional composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr 89 Sr-90, and Fe-55.

enuo A-4 t

APPENDIX A (Continued)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 5.

BATCH RELEASES a.

Liauid 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.

Liauid There were no ncnroutine liquid releases during the reporting

period, b.

Gaseous There were no nonroutine gaseous releases during the reporting period.

l l

uruo A-5 L

l APPENDIX B LIQUID HOLDUP TANKS Reauirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tant.

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 Annual Effluent Release Report per Technical Specification 6.7.C.1.

l

Response

The limits of Technical Specification 3.8.D.1 were not exceeded during this reporting period.

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uruc B-1 l

APPENDIX C RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Reauirement: Radioactive liquid effluent monitoring instrumentation channe.,

are required to be operable in accordance with Technical Specification Table 3.9.1.

If an inoperable radioactive liqui 2 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 Annual Effluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7.C.1.

Response

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, no response is required.

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4 anuo C-1

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APPENDIX D RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION I

Reauirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.2.

If inoperable gaseous effluent 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 Annual Effluent Release Report of the reason (s) for l

the delay in correcting the inoperability is required per l

Technical Specification 6.7.C.1.

Response

Since the requirements of Technical Specification Table 3.9.2 governing the operability of radioactive gaseous effluent l

monitoring instrumentation were met for this reporting period no response is required.

1 1

l l

urac D-1

l APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Reauirement: The radiological environmental monitoring program is conducted in l

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 Annual Effluent Release Re. port:

(1) identify the i

cause(s) of the sample (s) no lon;er being available, (2) identify the new location (s) for obtaining available replacement samples j

and (3) include revised ODCM figure (s) and table (s) reflecting l

the new location (s).

l l

Response

No changes were needed in the milk sampling locations specified in Technical Specification Table 3.9.3 due to sample unavailability during the reporting period.

l l

l e

Ries 40 E-1

APPENDIX F l

LAND USE CENSUS Reauirement: 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.I. Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Annual Effluent Release Report.

Response

The Land Use. Census was completed in the third quarter of 1995.

No locations yielded a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.1.

l l

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'l on6e F-1

APPENDIX G PROCESS CONTROL PROGRAM Reauirement: Technical Specification 6.12. A.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the I

Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made.

I

Response

The following changes' were made to the Process Control Program (PCP) and issued as Revision 4 during this reporting period.

1.

The minimum dewatering time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was removed from Section 4.0 and replaced with a reference to OP-2511, i

Radwaste Cask Drum and Box Handling.

OP-2511 controls the process of dewatering the filter liner based upon the type of liner in use. The procedure ensures that burial site criteria for freestanding water is met.

2.

AP-0620. " Chemical Material Use," was added to the list of procedures which implement the PCP because this procedure is referenced in Section 6.0 of the PCP.

I I

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ll mm c-1 u

I

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l APPENDIX H I

0FF-SITE DOSE CALCULATION MANUAL Reovirement: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site '<ose Calculation Manual (0DCM) be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made i

effective.

e i

Response

There were two licensee-initiated changes to the Off-Site Dose Calculation Manual during this reporting period.

The major changes included in Revision 18 to the ODCM are:

(1)

Page 3-3:

A clarification is added that doses calculated by Method 11 can at times be higher than would be reported using Method I equations based solely on the differences between long-term and short-term dispersion parameters (X/0s). Method I uses five-year historical average dispersion values for describing the maximum receptor location.

Method 11 calculations typically use quarterly j

average dispersion values which are determined for periods

)

that are concurrent with the reported time of release.

Maximum receptor doses determined using quarterly meteorology may be greater than doses calculated with Method I due to short time period variability of meteorological conditions from the long-term average.

(2)

Page 3-51:

Administrative corrections are made by restating the direct dose equations for fixed radioactive sources which had been accidentally left out in the last revision to this page.

(3)

Pages 4-1, 4-2a. 4-3. and Figure 4-3:

The Dominick Farms, i

REMP location TM-12 and TC-12, is reported by the plant to be no longer available as a sampling location for milk and J

silage.

Since this location had been listed as a non-Technical Specification required sampling station, it was dropped from the REMP without the need for a replacement location.

(4)

Pages 5-8 and 5-9:

The 1989 Service Water Monitor (SWM)

Evaluation provided a methodology for the determination of nmo H-1

APPENDIX H (Continued) 0FF-SITE DOSE CALCULATION MANUAL f

the minimum concentration of a mix of potential contaminates that the SWM would need to be able to detect above background in order to ensure that effluent discharges did not exceed the Technical Specification limits on radioactive discharge concentrations.

Plant i

procedures incorporated this methodology that compared a calculated Composite Maximum Permissible Concentration l

(CMPC) with the SWM detection sensitivity to determine if l

the monitor could satisfy operability requirements.

This j

change updates the previous minimum requirement that the l

SWM only need to be set at three times background.

it l

requires that detection capability of the monitor be shown to be adequate to detect the mix of radionuclides that would most likely be the source of any contamination of the i

service water.

(5)

Page 5-13:

Editorial changes are made to reflect that a new digital ratemeter readout device has replace the analog ratemeter that was part of the original Plant Stack Gas j

Activity Monitor Channt l.

These changes will not reduce the accuracy or reliability of the i

dose calculations or setpoint determinations previously approved i

l for use in the ODCM. The reasons are:

(a) the new setpoint calculations for the SWM with additional requirements are more i

restrictive than the original, (b) the other changes did not l

modify the calculation methods currently employed in the ODCM.

1 l

Revision 19 to the ODCM added the Back Tracks Farm (2.3 km south l

of the plant stack) as a new milk sampling location TM-10 and as a new silage sampling location TC-10. Table 4.1 and Figure 4-2 of the ODCM were revised to indicate the addition of TM-10 and TC-10 to the REMP.

The inclusion of the new milk and silage sampling locations to the REMP has no impact on the methods, parameters, or assumptions contained in the ODCM for the

)

calculation of doses or effluent monitor setpoints. Therefore, this change will not reduce the accuracy or reliability of any dose calculations or setpoint determinations previously approved for use in the ODCM.

I ema H-2

l APPENDIX H (Continued) 0FF-SITE DOSE CALCULATION MANUAL The revised pages for Revisions 18 and 19 are attached.

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J a m 4o H-3 l

i

i VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCllLATION MANUAL REVISION 18 i

)

Reviewed:

PM.Cd 96dFP 7/7/97 Plant OperationsL4teview Committee

/

tate Approved:

7!7[ff nt Manad/(/

Date 0(

7/[h!

Approved:

Vice PresidenI. Operations Date

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Revision 1 Date 7/20/95

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TABLE OF CONTENTS

.P3,gg LIST OF AFFECTED PAGES......................11l i

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DISCLAIMER OF RESPONSIBILITY

.................... iv ABSTRACT v

TAB LE O F CONT ENTS.......................... vi i

LIST OF TABLES

.......................... viii l

LIST OF FIGURES...........................

x l

1 l

1.0 INTRODUCTION

1-1 l

1.1 Summary of Methods. Dose Factors. Limits. Constants.

Variables and Definitions..................

1-2 l

2.0 METHOD TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS 2-1 ENG NG l

2.1 Method to Determine F 3 ggg gl 2-1 l

2.2 Method to Determine Radionuclide Concentration for Each Liquid Effluent Pathway..

2-3 l

i 2.2.1 Sample Tanks Pathways.................

2-3 l

2.2.2 Service Water Pathway.

2-3 2.2.3 Circulating Water Pathway...............

2-4 3.0 0FF-SITE DOSE CALCULATION METHODS.................

3-1 3.1

' Introductory Concepts....................

3-2 3.2 Method to Calculate the Total Body Dose from Liquid Releases 3-4 l

I 3.3 Method to Calculate Maximum Organ Dose from Liquid Releases. 3-10 i

3.4 Method to Calculate the Total Body Dose Rate From Noble Gases...........................

3-13 i

3.5 Method to Calculate the Skin Dose Rate from Noble Gases..

3-19 l

3.6 Method to Calculate the Critical Organ Dose Rate from Iodines. Tritium and Particulates with T Greater Than in 8 Days 3-26 i

Revision 1 Date 7/20/95

-vi-

3.7 Method to Calculate the Gamma Air Dose from Noble Gases..

3-30 3.8 Method to Calculate the Beta Air Dose from Noble Gases 3-34 3.9 Method to Calculate the Critical Organ Dose from Iodines, Tritium and Particulates 3-38 3.10 Receptor Points and Annual Average Atmospheric Dispersion Factors for Important Exposure Pathways..........

3-45 4

l 3.11 Method to Calculate Direct Dose From Plant Operation 3-51 5

3.12 Cumulative Doses 3-59 4.0 ENVIRONMENTAL MONITORING PROGRAM 4-1 j

5.0 SETPOINT DETERMINATIONS......................

5-1

\\

5.1 Liquid Effluent Instrumentation Setpoints..........

5-2 5.2 Gaseous Effluent Instrumentation Setpoints 5-11 l 6.0 LIQUID AND GASE0US EFFLUENT STREAMS. RADIATION MONITORS, AND RADWASTE TREATMENT SYSTEMS 6-1 6.1 In-Plant Radioactive Liquid Effluent Pathways........

6-1 6.2 In-Plant Radioactive Gaseous Effluent Pathways 6-4 REFERENCES R-1 APPENDIX A: Method I Example Calculations A-1 APPENDIX B: Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site at Vermont 1

Yankee B-1 APPENDIX C: Response to NRC/EG&G Evaluation of ODCM Update Through Revision 4 C-1 APPENDIX D: Assessment of Surveillance Criteria for Gas Releases from Waste Oil Incineration 0-1 Revision 18 Date 7/20/95

-vii-

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

l l

l LIST OF TABLES (Continued) l Number Title h

3.10-2 Site Boundary Distances 3-49 3.10-3 Recirculation Correction Factors 3-50 4.1 Radiological Environmental Monitoring Stations 4-2 5.2-1 Relative Fractions of Core Inventory Noble Gases After Shutdown 5-22l l

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Revision 1 Date 7/20/95 i

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l 3.0 0FF-SITE DOSE CALCULATION METHODS Chapter 3 provides the basis for plant procedures required to meet the 10CFR50, Appendix I, ALARA dose objectives, and the 40CFR190 total dose limits to members of the public in unrestricted areas, as stated in the Radiological Effluent Technical Specifications (hereafter called RETS).

A simple, conservative method (called Method I) is listed in Tables 1.1-2 to 1.1-7 for each of the requirements of the RETS.

Each of the Method I Gquations is presented, along with their bases in Sections 3.2 through 3.9 and Section 3.11.

Appendix A provides example calculations for all Method I dose equations as guidance to their use.

In addition, reference is provided to more sophisticated but still conservative methods (called Method II) for use l

i when more accurate results are needed. This chapter provides the methods, data, and reference material with which the operator can calculate the needed doses and dose rates.

Setpoint methods for effluent monitor alarms are described in Chapter S.

Demonstration of compliance with the dose limits of 40CFR190 is considered to be a demonstration of compliance with the 0.1 rem limit of 10CFR20.1301(a)(1) for members of the public in carestricted areas (Reference 56 FR23374, 3rd column).

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Revision 1 Date 7/20/95 3-1 l

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selection and definition of critical receptors. The radioisotope specific dose factors in each " Method I" dose equation represent the greatest dose to any organ of any age group accounting for existing or potential pathways of exposure. The critical receptor assumed by " Method I" equations is typically a hypothetical individual whose behavior - in terms of location and intake -

results in a dose which is expected to be higher than any real individual.

The Method I equations employ five-year historical average atmospheric dispersion factors to define receptors of maximum impact. Method II allows for a more exact dose calculation for real individuals, if necessary, by considering only existing pathways of exposure, or actual concurrent meteorology with the recorded release. Maximum receptor doses determined using quarterly meteorology may be greater than doses calculated with Method I due to short time period variability of meteorological conditions from the long-term average. Quarterly ave age dispersion values for maximum receptors have been observed to differ from five-year average values by as much as 54%.

R is the quantity calculated in the Chapter 3 dose r3t1 equations.

It is calculated using the plant's effluent monitoring system reading and an annual average or long-term atmospheric dispersion factor.

Dispersion factors based on actual concurrent meteorology during effluent releases can also be used via Method II, if necessary, to demonstrate compliance with off-site dose rate limits.

Each of the methods to calculate dose or dose rate are presented in separate sections of Chapter 3, and are summarized in Tables 1.1-1 to 1.1-7.

Each method has two levels of complexity and are called Method I and Method II. Method I is the simplest; generally a linear equation. Method II is a more detailed analysis which allows for use of site-specific factors and variable parameters to be selected to best fit the actual release conditions, within the bounds of the guidance provided.

The plant has both elevated and ground level gaseous release points:

the main vent stack (elevated release), and the North Warehouse waste oil burner (ground level release). Therefore, total dose calculations for skin, whole body, and the critical organ from gaseous releases will be the sum of the elevated and ground level doses.

Appendix D provides an assessment of the survelliance needs for waste oil to ensure that off-site doses from its incineration is maintained within the ALARA limits of the Technical Specifications.

(

Revision _la_, Date 7/20/95 3-3 l

l

3.11 Method to Calculate Direct Dose From Plant Ooeration Technical Specification 3.8.M.1 restricts the dose to the whole l

body or any organ to any member of the public from all station sources l

(including direct radiation from fixed sources on-site) to 25 mrem in a calendar year (except the thyroid, which is limited to 15 mrem).,

3.11.1 Turbine Buildino The maximum contribution of direct dose to the whole body or to l

any organ due to N-16 decay from the turbine is:

e E

(3-27) l D

"KN16( L) d l

(mrem)

(MW,h)

MW,h where:

l Dd The dose contribution from 4-16 decay at either the site

=

boundary of maximum impact (west site boundary) or closest off site residence - (mrem).

l E

Gross electric output over the period of interest (MW,h).

=

l KN16(L)

The N-16 dose conversion factor for (L) equal to either:

(1) 3.23E-06 for the maximum west site boundary; or (2) 1.29E-06 for the closest residence (mrem /MW,h).

3.11.2 North Warehouse Radioactive materials and low level waste can be stored in the north warehouse. The maximum annual dose contributions to off-site receptors (west site boundary line) from sources in the shielded (east) end and the unshielded (west) and of the north warehouse are:

6 Revision J.g_ Date 7/20/95 3-51

-~.

l

\\

l l

As for the shielded end (3-28)l Ds 0.25 x

mrem /yr'

' mrem'

' mrem '

f yr,

mrem /hr hr,

j (3-29) and Au for the shielded end Du 0.53 x

' mrem' fmrem /yr'

' mrem' yr mrem /hr, hr where:

D3 The annual dose contribution at the maximum site boundary I

location from fixed sources of radiation stored in the i

shielded east end of the North Warehouse mrem',

yr,

4 l

Du The annual dose contribution at the maximum site boundary location from fixed sources of radiation stored in the unshielded west end of the North Warehouse mrem',

yr ks Dose rate measured at 1 meter from the source in the shielded end of the north warehouse mrem',

hr,

t d

Dose rate measured at 1 meter from the source in the u

unshielded end of the north warehouse mrem',

hr,

g l

l 0.25 Dose rate to dose conversion factor which relates mrem /yr at the west site boundary per mrem /hr measured at 1 meter from t

Revision 1 Date 7/20/95_

3-52

Table 4.1 U)

Radiolooical Environmental Monitorino Stations Exposure Pathway Sample Location Distance and/or Samole and Desianated Code (2)

(km)(5)

Direction (5) l 1.

AIRBORNE (Radioiodine and Particulate)

AP/CF-11 River Station 1.9 SSE No. 3.3 AP/CF-12 N. Hinsdale. NH 3.6 NNW AP/CF-13 Hinsdale Substation 3.1 E

AP/CF-14 Northfield, MA 11.3 SSE AP/CF 15 Tyler Hill Road")

3.2 WNW l

AP/CF-21 Spofford Lake 16.1 NNE 2.

WATERBORNE a.

Surface WR-11 River Station 1.9 Downriver l

No. 3.3 WR-21 Rt. 9 Bridge 12.8 Upriver On-Site b.

Ground WG-11 Plant Well WG-12 Vernon Nursing Well 2.0 SSE WG-22 Skibniowsky Well 14.3 N

c.

Sediment SE-11 Shoreline Downriver 0.8 SSE From SE-12 North Storm 0.15 E

l Shoreline Drain Outfa11(3) i l

3.

INGESTION l

a.

Milk TM-11 Miller Farm 0.8 WNW TM-14 Brown Farm 2.1 S

l l

TM-16 Meadow Crest Farm 4.4 WNW/NW TM-18 Blodgett Farm")

3.4 SE TM 24 County Farm 22.5 N

b.

Mixed TG-11 River Station 1.9 SSE Grasses No. 3.3 TG-12 N. Hinsdale. NH 3.6 NNW l

TG-13 Hinsdale Substation 3.1 E

i l

TG-14 Northfield. MA 11.3 SSE l

TG-15 Tyler Hill Rd.")

3.2 WNW TG-21 Spofford Lake 16.1 NNE i

Revision 18 Date 7/20/95 l

4-2 1

1

Table 4.1 (Continued)

Radiolooical Environmental Monitorino Stations")

Exposure Pathway Sample location Distance and/or Samole and Desionated Code (2)

(km)(5)

Direction (s) l c.

Silage TC-11 Miller Farm 0.8 WNW TC-14 Brown Farm 2.1 S

l TC-16 Meadow Crest Farm 4.4 WNW/NW TC-18 Blodgett Farm (*)

3.4 SE TC-24 County Farm 22.5 N

d.

Fish FH-11 Venion Pond (6)

(6) l FH-21 Rt. 9 Bridge 12.8 Upriver 4.

DIRECT RADIATION DR-1 River Station 1.6 SSE No. 3.3 DR-2 N. Hinsdale. NH 3.9 NNW DR 3 Hinsdale Substation 3.0 E

DR-4 Northfield. MA 11.0 SSE DR 5 Spofford Lake 16.3 NNE DR-6 Vernon School 0.46 WSW DR-7 Site Boundary (7) 0.27-W DR-8 Site Boundary 0.25 SW l

DR-9 Inner Ring 2.1 N

DR-10 Outer Ring 4.6 N

DR 11 Inner Ring 2.0 NNE DR-12 Outer Ring 3.6 NNE DR-13 Inner Ring 1.4 NE DR-14 Outer Ring 4.3 NE DR-15 Inner Ring 1.4 ENE DR-16 Outer Ring 2.9 ENE DR-17 Inner Ring 1.2 E

DR-18 Outer Ring 3.0 E

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

{

Revision 1 Date 7/70tos 4-2a

i

~

i i

Table 4.1 (Continued) l Radiolocical Environmental Monitorina Stations (D j

i Exposure Pathway Sample Location Distance and/or Samole and Designated Code (2)

(km)(5)

Direction (s) l l

DR-26 Outer Ring 3.7 S

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

DR-32 Outer Ring 5.0 WSW DR-33 Inner Ring 0.9 WNW DR-34 Outer Ring 4.9 W

DR-35 Inner Ring 1.4 WNW 1

DR-36 Outer Ring 4.7 WNW DR-37 Inner Ring 3.0 NW l

DR-38 Outer Ring 7.7 NW j

l DR-39 Inner Ring 3.2 NNW DR-40 Outer Ring 5.8 NNW l

i

?

1 (1)

Sample locations are shown on Figures 4.1 to 4.6.

(2)

Station Nos. 10 through 19 are indicator stations.

Station Nos. 20 through 29 are control stations (for all but the direct radiation stations).

(3)

To be sampled and analyzed semiannually.

l (4)

Non-Tech Spec station.

(5)

Distance and direction from the center of the Turbine Building for l

direct radiation monitors; from the plant stack for all others.

(6)

Fish samples are collected from anywhere in Vernon Pond, which is l

adjacent to the plant (see Figure 4-1).

(7)

DR-8 satisfies Technical Specification Table 3.9.3 for an inner ringHowever, it i direct radiation monitoring location.

Boundary TLD due to its close proximity to the plant.

Revision 18 Date 7/20/95 4-3

l 1

1 l

)

l 1

l l

(

)

l l

A TM 24 TC+24

$PQFFOR0 LAKE TG 21 4+

h A w 22 A n/Cr 21 l

4 fN 21 W-21 NOG 8Act Mr.

CHESTERFIELD A

MARLBORO

'h e

K 1

o l

BAATTLEBORO 4 O

SZr rztRCDEE a FIcar 4 2 f

_ _ _v_ _ _ _,

S 1

l I

I I

e g

HINSDALE 8 GUILF RD e l

I l

WINCHESTER I VERNON e g

e PLANT i

1 I

I YEMIT 8

NEW HAMPSHIRE l

MASSACHUIETTS t1ASSACHUSETTS e NORTHFIELD l

A AP/CF-14 l

TG 14 l

l t

GREENFIELO

l O

5 10 E

I I

KILOMETERS 4

Figure 4-3 Environrnental Sampling Locations Greater than 5 kra frorn Plant l

Revision 18 Date 07/20/95 4-6

5.1 Liauid Effluent Instrumentation Setooints Technical Specification 3.9.A.1 requires that the radioactive liquid effluent instrumentation in Table 3.9.1 of the Technical Specifications have alarm setpoints in order to ensure that Specification 3.8.A.1 is not exceeded.

Specification 3.8.A.1 limits the activity concentration at any time in liquid effluents to the appropriate effluent concentration values in Appendix B.

Table 2, Column 2 of 10CFR20, and a total noble gas concentration limit of 2E-04 pCi/ml.

5.1.1 Liouid Radwaste Discharge Monitor (RM-17-350) l The sample tank pathways shown on Figure 6-1 are monitored by the liquid radwaste discharge monitor (RM-17-350).

Periodic batch releases may be made l

from the waste sample tanks, detergent waste tank or floor drain sample tank.

5.1.1.1 Method to Determine the Setooint of the Licuid Radwaste Discharce Monitor (RM-17-350) l The instrument response (in counts per second) for the limiting concentration at the point of discharge is the setpoint, denoted R,,tp,3ng, and l

is determined as follows:

R,spagne -

Si C,j s

(5-1) l (cps)

(#)

( cps-m1)

(pCi) f pC) ml Where:

d Dilution factor (as a conservative measure, DF 5

a DF of at least 1000 is used) l (dimensionless).

(5-2)

F, Flow rate past monitor (gpm)

Flow rate out of discharge canal (gpm) l F

d Minimum allowable dilution factor (dimensionless)

D F,i n (5-3)

Revision 18 Date 7/20/95 5-2 l

i Usually F /I is greater than DF,i,(i.e., there is more dilution than d m necessary to comply with Equation 5-7).

The response of the liquid radwaste discharge monitor at the setpoint is therefore:

i R,gp ing S i C,i (5-1)

' cps-m1'

'pCi '

(cps)

(#)

pCi

, ml,

5.1.2 Service Water Discharce Monitor (RM 17-351) l The service water pathway shown on Figure 6-1 is continuously monitored by the service water discharge monitor (RM-17-351). The water in this line is not radioactive under normal operating conditions. The alarm setpoint on the Service Water Monitor (SWM) is set in accordance with the monitor's ability to detect dilute concentrations of radionuclide mixes that are based on measured nuclide distributions in reactor coolant.

From routine coolant sample gamma isotopic analyses, a Composite Maximum Permissibli: Concentration (CMPC) is calculated as follows:

C(f /MPC1 + f /MPC2...)

- C/CMPC i

2 or CMPC - 1/(f /MPC1 + f /MPC2...)

(5-22) i 2

where:

C

- Total concentration of detected radioactivity in reactor coolant j

sample (pCi/ml) fg

- Fraction of total radionuclide concentration represented by the ith radionuclide in the mix MPC, - Maximum Permissible Concentration limit for radionuclide "i" as listed in 10CFR20.106, Appendix B Table II, Column 2 (pCi/ml)

The Composite Effluent Concentration Limit (CECL) is also calculated using the equation above by substituting the appropriate ECL value from 10CFR20.1001-20.2401, Appendix B. Table 2 Column 2, for MPC, Revision 18 Date 7/20/95 5-8

{

(

If the SWM's minimum achievable alarm setpoint is higher than the required CMPC equivalent count rate (or the CECL equivalent count rate if it is lower than the CMPC count rate), the monitor is declared inoperable, and daily SWM grab samples are collected and analyzed until the calculated coolant CMPC (or CECL) equivalent count rate is above the SWM's alarm setpoint.

For example, if the reactor coolant radionuclide mix distribution is as listed below, then the corresponding CMPC is calculated as follows:

Nuclides Conc (pCi/ml) f, 10CFR20 HPC, fj/MPC, (concg/ total

( Ci/ml)

(ml/ C1) conc)

I-131 6.00E-6 6.59E-2 3.0E-7 2.20E+5 I-133 5.00E-6 5.49E-2 1.0E-6 5.49E+4 Co-60 8.00E-5 8.79E-1 3.0E-5 2.93E+4 Totals 9.10E-5 1.00 3.04E+5 CMPC - 1/3.04E+5 - 3.29E-6 (pCi/ml)

The CECL is also calculated by using the above methodology and substituting the appropriate ECL listed in 10CFR20.1001-20.2401 Appendix B.

[

Table 2 Column 2, for MPC values.

For this example, the calculated CECL is equa1 to 2.73E-6 pCi/m1.)

If the SWM alarm is set.at 5 CPS (300 CPM) above background, and the current calibration factor for this monitor is 1.17E+8 CPM /pCi/ml, then the

(

SWM will alarm if a concentration as low as 2.56E-6 pCi/ml above background passes by the monitor. Since the most limiting CMPC or CECL (calculated above to be 2.73E-6 Ci/ml) is above the alarm setpoint (equal to 2.56E-6 pCi/ml),

{

the SWM will be capable of alarming if radioactivity in excess of limiting concentration values for release to unrestricted areas passes by the monitor.

However, if the composite concentration (CMPC or CECL) for the service water was found to be less than the SWM alarm setpoint of 2.56E-6 Ci/m1, then daily service water grab samples would have to be collected and analyzed until the composite concentration becomes greater than the concentration corresponding to the SWM's alarm setpoint.

[

Also, service water is sampled if the monitor is out of service or'if the alarm sounds.

I I

{

Revision 18 Date 7/20/95

]

5-9

l t

Under normal operating conditions, the concentration of radionuclides at the point of discharge to an unrestricted area from the service water effluent pathway will not exceed the effluent concentration limits specified in 10CFR20.1001-20.2401, Appendix 8. Table 2. Column 2.

l I

t l

l l

\\

l l

i 1

1 1

I l

l l

t I

l.

Revision 18 Date 7/20/95 5-10 l

(

5.2 Gaseous Effluent Instrumentation Setooints 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.K.1 limits the gross radioactivity release rate at the steam jet air ejector (SJAE) to 0.16 Ci/sec.

5.2.1 Plant Stack Noble Gas Activity Monitors (RM-17-156 and RM-17-157) and Auomented Off-Gas System Noble Gas Activity Monitors (RAN 0G-3127 and RAN-0G-3128)

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

i 5.2.1.1 Method to Determine the Setooint of the Plant Stack Noble Gas

(

Activity Monitors (RM-17-156 and RM-17-157) and the Auamented Off-Gas System Noble Gas Activity Monitors (RAN-0G-3127 and RAN 0G-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.

spt.

R,pg is the lesser of:

denoted R h

R t-818 S

(5-9) g 3

3

{

(cpm)

(yr m-uCi-m ) (com-cm ) g ) ( DCi-vr) mre pct-sec 901 3

cm mrem m

(

and:

(

h (5-10)

R U = 3,000 S g (cpm)

( "y"'* ) (CDm m) g

) g

- eC)

Vf m

Revision 1 Date 7/20/91 5-11

^

1 I

where:

R

= Response of the monitor at the limiting total body dose t

l rate (cpm) 3 500 mrem-uC1 m 818 gy npa -sec )

(1E+06)

(6.11E-07) 500

- Limiting total body dose rate (mrem /yr) 1E+06

- Number of pCi per pCi (pCi/ Ci) 6.11E-07

= [X/0 F, maximum five-year 3 average gamma atmospheric dispersion factor (sec/m )

5

- Appropriate (plant stack or A0G system) detector 9

]

counting efficiency from the most recent calibration j

l (cpm /( Ci/cc))

3 F

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

OFB

- Composite total body dose factor (mrem-m /pCi-yr) c 0FB l

fi j

(5-11) f 0' j j

6

- The relative release rate of noble gas "i" in the mixture 4

j' atthemonitor(eitherthestack,6ST ortheA0G,6A0G) for noble gases identified (pCi/sec) 3 DFB

- Total body dose factor (see Table 1.1-10) (mrem m /pCi-yr) j R

= Response of the monitor at the limiting skin dose rate (cpm) 3,000

- Limiting skin dose rate (mrem /yr)

D F'c

- Composite skin dose factor (mrem-sec/pCi-yr) l Revision 18 Date 7/20/95 l

5-12

~--

l fi is (5-12)

IO g

i l

DF'4 8

- Combined skin dose factor (see Table 1.1-10)

(mrem sec/ Ci-yr) l l

5.2.1.2 Plant Stack Noble Gas Activity Monitor Setooint Examole l

l The following setpoint example for the plant stack noble gas activity monitors demonstrates the use of Equations 5-9 and 5-10 for determining l

j setpoints.

The plant stack noble gas activity monitors, referred to as " Stack l

Gas I" (RM-17-156) and " Stack Gas II" (RM-17-1,57), consist of beta sensitive l

scintillation detectors, electronics, a ratemeter readout, and a digital l

l scaler which counts the detector output pulses. A strip chart recorder provides a permanent record of the ratemeter output. The monitors have typical calibration f actors, S. of about 1E+08 cpm per Ci/cc of noble gas.

l g

The nominal plant stack flow is 8.3E+07 cc/sec ((175,000 cfm x 28.300 3

cc/ft )/60 sec/ min).

l When monitor responses indicate that activity levels are below the LLDs at the stack (or A0G) monitors, the relative contribution of each noble gas j

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 DFB, and DF'g):

6,sJAE OFBt D F's,

3 i

Ci )

(mrem-m )

( mrem-sec )

sec pCi-y r pCi-y r Xe-138 1.03E+04 8.83E-03 1.06E-02 Kr-87 4.73E+02 5.92E-03 1.43E-02 Kr-88 2.57E+02 1.47E-02 1.28E-02 Kr-85m 1.20E+02 1.17E-03 2.35E-03 Xe-135 3.70E+02 1.81E-03 3.24E-03 Xe-133' 1.97E+01 2.94E-04 5.58E-04 1

i I

Revision 18 Date 7/20/95 5-13

l l

E0lJ^EDFBi l

DFB = '

(5-11) e E 0lJAE f

1 E0fJAEDFBt = (1.03E+04)(8.83E-03) + (4.73E-02)(5.92E-03) 1

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

+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) 3

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

E0lJAE

- 1.03E+04 + 4.73E+02 + 2.57E+02 1

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

- 1.15E+04 pCi/sec 9.83E+01 DFB*

1.15E+04 3

l

- 8.52E-03 (mrem-m /pCi-yr) tb 2

1 1

R

- 818 S J

spt 97 %

1 1

- (818) (1E+08)

(8.3E+07) ( 8. 52E-03 )

= 115,674 cpm Lu.t:

EOfJAED F't,

D F'e = *

(5-11) pgsJAE 1

i Revision 18 Date 7/20/95 l

5-14

i t

E Og *DF'g, - (1.03E+04)(1.06E-02) + (4.73E-02)(1.43E-02)

S 1

+ (2.57E+02)(1.28E-02) + (1.20E+02)(2.35E-03)

+ (3.70E+02)(3.24E-03) + (1.97E+01)(5.58E-04)

- 1.14E+02 (pCi-mrem-sec/sec pCi-yr)

DF'*

1.14 E+02 1.15 E +04 j

= 9.91E-03 (mrem-sec/ Ci-yr)

I I

R

- 3,000 S skin S T O F'e l

I 1

= (3,000) (IE+08) i

( 8. 3 E +07 ) ( 9. 91 E-03 )

- 364,728 cpm The setpoint, R,,t, is the lesser of R,yt and R,'ftI".

For the noble gas mixture in this example R,$t i s l es s tha n R,'fti", indicating that the i

total body dose rate is more restrictive.

Therefore, in this example the' l

" Stack Gas I" and " Stack Gas II" noble gas activity monitors should each be set at 115,674 cpm 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 beled 20 x ECL when averaged over an hour), or to account for other minor releases from the waste oil burner.

For examDie, if an administrative limit of 70 percent of the f

Technical Specification whole body dose limit 500 rem /yr (115,674 cpm) is chosen, then the noble gas monitor alarms should be set at no more than 80,972 cpm above background (0.7 x 115,674 - 80,972).

5.2.1.3 Basis for the Plant Stack and A0G System Noble Gas Activity Monitor l

Setooints The setpoints of the plant stack and A0G system noble gas activity i

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

Sections 3.4 and 3.5 show that Equations 3-5 and 3-7 are acceptable methods for determining compliance with that Technical Specification. Which equation (i.e., dose to total body or skin) is more limiting depends on the noble gas mixture. Therefore, each equation must be considered separately, lne Revision 18 Date 7/20/95 5-15

. ~. -.

i

~

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

R={.

Sgi C,,

5-13)

(

t t

r 3 -r 3

3 cpm-rm pCi (cpm) pC1 3

cm,

i where:

R

= Response of the instrument (cpm) l 3

S,,

= Detector counting efficiency for noble gas "i" (cpm /(pCi/cm ))

C,3'

- Activity concentration of noble gas "i" in the mixture at the 3

noble gas activity monitor (pCi/cm )

t The relative release rate of each noble gas, 6 (pCi/sec), in the total 3

release rate is normally determined by analysis of a sample of off-gas obtained at the Steam Jet Air Ejector (SJAE).

Nobin gas release rates at the plant stack and the A0G discharge are usually so low that the activity concentration is below the Lower Limit of Detection (LLD) for sample analysis.

As a result, the release rate mix ratios measured at the SJAE are used to represent any radioactivity being discharged from.the stack, such as may have l

resulted from plant steam leaks that have been collected by building ventilation; For the A0G monitor downstream of the charcoal delay beds, this' leads to'a conservative setpoint since several short-lived (high dose. factor)

' noble gas radionuclides are then assumed to be present at the monitor, which in reality, would not be expected to be present in the system at that point.

During periods when the plant is shutdown (after five days), and no l

radioactivity release rates can be measured at the SJAE, Xe-133 is the l

dominant long-lived noble gas and may be used as the referenced radionuclide to determine off-site dose rates and monitor setpoints. Alternately..a relative radionuclide "i", mix fraction (fg), r */ '.e taken from Table 5.2-1 as a function of time after shutdown (including periods shorter than five days) to determine tLt. relative fraction of each noble gas potentially available for release to the total.

However, prior to plant startup 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 i

alarm setpoints which have been determined to be conservative under any plant l

conditions may be utilized at any time in lieu of the above assumptions.

j C,j, the activity concentration of noble gas "i" at the noble gas activity Revision __lB_

Date 7/20/95 5-16

monitor, may be expressed in terms of 0, by dividing by F, the appropriate flow rate.

In the case of the plant stack noble gas activity monitors tha appropriate flow rate is the plant stack flow rate and for the A0G noble gas activity monitors the appropriate flow rate is the A0G system flow rate.

C,=

0, (5-14)

( pCi ) g Ci ) g sec) 3 3

cm sec cm where:

O The release. ate of noble gas "i" in the mixture for each

=

i noble gas identified (pCi/sec).

3 Appropriate flow rate (cm /sec)

F

=

Substituting the right half of Equation 5-14 into Equation 5-13 for C,i yields:

5 0

(5-15)

R

=

91 1

r 3

3 cpm-cm

'pCi )

sec (cpm)

C1 secJ cm 3

, s The detector calibration procedure establishes a counting efficiency for a given mix of nuclides seen by the detector. Therefore, in Equation 5-15 one May substitute S, for 5,i, where 5, represents the counting efficiency Jetermined for the current mix of nuclides.

If the mix of nuclides changes significantly, a new counting efficiency should be determined for calculating the setpoint.

R=

S, Os 3

(cpm) ( cpm-cm ) ( sec )

g pCi) pC1 cm sec 3

Revision 18 Date 7/20/95 5-17

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

A es =

0.61 0,

DFB (3-5) g i

~

mrem 3

g y g pCi-sec )

g pCi) g mrem-m )

3 yr pCi-m sec pCi-y r Where:

A es t

total body dose rate (mrem /yr) due to noble gases from stack release 3

0.61 (1.0E+06) x (6.11E-07) (pCi-sec/ Ci-m )

1E + 06 number of pCi per Ci (pCi/ C1) 6.11E - 07

[x/0F, maximum long term average gamma 3

atmospheric dispersion factor (sec/m )

0 1 the release rate of noble gas "i" in the mixture for each noble gas identified ( Ci/sec)

(Equivalent to 0,57 for noble gases released at the plant stack.)

DFB, total body dose factor (see Table 1.1-10) 3 (mrem m /pCi-yr)

A composite total body gamma dose factor. DFB, may be defined such e

that:

DFB 0,

O DFB i

i (5-17) c r

3 r

3 3

3 mrem-e

' Ci '

mrem-m pCi-yr,

sec,

,,sec,

pC i -y r,

+

Revision 18_ Date 7/20/95 5-18

Solving Equation 5-23 for DFBe yields:

E Og DFBi (5-11)

DFB e

E01 1

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

By setting Atb equal to 500 mrem /yr and substituting DFB for DFBq e

in Equation 3-5. one may solve for E Os at the limiting whole body noble gas dose rate:

E Os -

-818 (5-18) 3

( pCi ) ( mrem-gCi-m )

( pCi-yr )

3 sec y r-pCi-s ec mrem-m Substituting this result for E O in Equation 5-16 yields R,*,b the i

t, response of the monitor at the limiting roble gas total body dose rate:

tb 1

1 Rspt,

gyg 3

(5-9) 9 T

DFB e 3

3

) ( mrem-$tci-m ) ( cpm-cm ) (sec) ( pCi-yr )

y r-pCi-s e c pC1 cm mrem-m 3

3 The skin dose rate due to noble gases is determined with Equation 3-7:

Alp$" - E Og D F',,

( 3 -7 ')

{

t (mrem)

( pCi ) ( mrem-sec )

yr sec pCi-y r Where:

i Al,"g "

Skin dose rate (mrem /yr)

Og The release rate of noble gas "i" in the mixture

=

for each noble gas identified (pCi/sec)

Revision 18 Date 7/20/95 l

5-19

(equivalent to 0," for noble gases released at l

the plant stack).

D F',,

Combit..d skin dose factor (see Table 1.1-10)

(mrem-s e c/gCi -y r ).

A composite combined skin dose factor, DF'e, may be defined such that:

DF[

E 0,

=E O

D F ',

(5-19) i g

1 i

fmrem-sec' fpCi '

'pCi '

fmrem-s e c '

pCi -y r

sec, s e c,, pCi -y r,

j Solving Equation 519 for DF' yields:

E 0 DF',

1 DF* =

E 0, 1

Technical Specification 3.8.E.1.a limits the dose rate to the skin from noble gases at any location at or beyond the site boundary to 3,000 mrem /yr.

By setting A5"" equal to 3,000 mrem /yr and substituting DF[ for DF,' in Equation 3-7 one may solve for E Os at tiie limiting skin noble gas dose rate:

1 E 0, - 3,000

( pCi ) (mrem) ( pCi-yr )

sec yr mrem-s e c Revision 18 Date 7/20/95 5 20

i in Equation 5-16 yields R i", the Substituting this result for E d spt 1

response of the monitor at the limiting noble gas skin dose rate:

1 1

(5-10)

R,s ki n 3.000 5

pg 9

7 g

3 (cpm)

( mrem) ( cpm-cm ) ( sec ) ( gCi-y r

)

3 vr pCi cm mrem-sec 1

Revisicn 18 Date 7/20/95 5-21

\\

~-

TABLE 5.2-1 Relative Fractions of Core Inventory Noble Gases After Shutdown Time Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 t < 24 h

.02

.043

.001

.083

.118

.002

.010

.306

.061

.093

.263

.001

.004

.022

.758

.010

.198 l

.003

.004 24 hr i t < 48 h

.006

.024

.907

.001

.058

.005 48 h i t < 5 d

.008

.016

.969

.007 5 d i t < 10 d

.014

.006

.966

.014 10 d I t < 15 d

.022

.002

.950

.026 15 1 t < 20 d

.034

.001

.917 20 i t < 30 d

.048

.152

.070

.777 301 t < 40 d

.517 l

.378

.105 40 1 t < 50 d

.108

.240 50 1 t < 60 d

.652

.082

.003 60 1 t < 70 d

.835

.055

.024 t 2. 70 d

.920 l

Revision 18 Date 7/20/95 5-22

5 2.2 Steam Jet Air Elector (SJAE) Noble Gas Activity Monitors (RM-17-150A and RM-17-1508) l The SJAE noble gas activity monitors are shown in Figure 6-2.

5.2.2.1 Method to Determine the SetDoints of the Steam Jet Air Eiector Offoas Activity Monitors (RM-17-150A and RM-17-150B) l The SJAE noble gas activity monitor response in mR/hr at the limiting release rate is the setpoint, denoted RfffE, and is determined as follows:

RfffE 1.6E 45 5

(5-21) 9 (mR/hr)

( pCi )

mR-cc g sec)

( hr-pCi )

cc sec Where:

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

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

Detector counting efficiency from the most recent S

o calibration ((mR/hr)/( Ci/cc))

SJAE gaseous discharge flow (cc/sec)

F 5.2.2.2 Basis for the SJAE Noble Gas Activity Monitor Setooint 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 release rate at the SJAE for 0 yields Equation 5 21, the setpoint equation for the SJAE noble gas activity monitor.

Revision 18 Date 7/?n/os 5 23

1 r

x_

r m

m v

~

N n4

_ _I.ab we.

I ""'

" " " = >

I Oeedeaf 88*Ta. Sake Tank Tank

[heregess Q

4.000 ed 1.000 pl p y,g;,,,4,, p,,,, gg,g,,,

he Fume p

x n

~

n N

Drein

ggy, b

M nuwai.e Pteer bein O

+

Tank IUwr Dunia 30 gen 0 m M ga y

N 13 gen 23.M gel (33 q A) 10,000 d 1P 7

37 3

>- 3did Wet 3 " 805""

LeePw4ry W ee Dry =d E,mper.m Dreias 5gesu Re.

Itearme Beinding Pl.se Dreias De=ea es in Badee.e. 9 Mens Rear heime

%W hbine Dead.g ther base 9r th e

3y JL JL 15s> Pwley Meme M88 b

We, p,a y,4 oy-d m..

-od O*==

Sange w, D,,,4.,

Op g33,, ;,

Tg S

p Test

.Rm. B.eiWias.E.9.dr,==a8 Delas g,y,qg h

g t,,,

we.

-* u.a=.d

+ me=,

ii. -

o.sen run.seyeres.

~

._p

,,7,,*

Tedene Buildag Equipmeres Done I10 go.

)5 OramP.Ph=. s.y.en.

m.i. me

%=

4 Mee Wese Osaketen Seege Sery Pseer Dasein.

Yenk y g,,,,

Ito pe (33 etR) gN Tema s

33.000 get u,waae

~....q 8mw

,$,',Q*"

n '"*

r t-no. coo go o

i.e., we.,

360.000 gpm meet () g=eg.)

t=6.

'r u

8****

Da.n.e w Omh. =

20.Ono pa 1meew s

JL r38 der F=me.

Mesme (RM ti-358)

>t mi FIGURE 6-1: Radioactive Liquid Efiluent Streams, Radiation Monitors, and Radwaste Treatment System at Vermont Yankee *

Normal (design) radioactive process streams only are shown.

OrmLCOOVYOOCMNEWF1GS

N r) 9ehome C2 Amagewee JL Rsbase to Amnes@

$ f,d f

,,,,i,

.$- 1YS$

Meam(

l BeiMag %nailnese Ga&dina Mism BuiMag) hebine Cimed senVMschnairst Vanam Purg U

j Seaney Gas te omen (Cornamurene brie) l N8SWk ta Ms. Oit Bwner Searng Dypse ms 8

(North Wwehemar)

W g{,y yw, WM"!GI CDI y

pg, F

C8eli"8 Sep.,.,,

"Stenew Bed C'*I'd yo,%,,

Omlenw, Enchantee y

g, Hyactes W

if 5s Monna

Fiher Oma*I r er M**'*' " #

o gg c,,,,,,

3eenud =

cryc.ym,

Hg ir

,p g

C_y y "1,";;"c d..

nwa s

n JL No. 2 N Jk A

A' in Air b 9r s

B bed Btred

'72 1 9F N3

..in, Regenrembw

>A>A

>4H spewen Fuer (One f%eTWm)

I h

2L 11,0 Drals 9F N*d

-v{k Ihwa Air

4 7

Vanaws 1r k

[b W NW SJAE Neh 0.s Acehig Me...

s6 g

(RM 17-130A+B) pg g)

N., 3 g gg b

2 1P Sepreer y

,X AOO Noble ces Jh 1r

~^

Cmier Na6 M 2 8Am3123)

I1yhtsem C,4,.

3r mmm sg M

Warr/Clyce4 Na7 v4 Cooled yg gr Moisneer I

3*P*'**'P7 Omlet

Seperma, a3m.ci,,* Ded Ad.e g.g l l l l em Om & owe m

,),

~

r Prehreer CamWe Omwirnser sJ l sier Omrwel

Far, v.cman #

s6 Ceard hm9 '

Iteennbiner l

l",*,,,J Ba Ca;,r,,

Yf,-

sy D,,,,,,,

AOO Bypean

t u,,u,,

m.am osxme mo urmu== wins =

l uormen nuowumm euurm l

aimmeany. em u m -

FIGURE 6-2: Radioactive Gascous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Vermont Yankee *

' Normal (design) radioactive process streams only are shown.

omooovvoocwevncs

b VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REVISION 19 l

Reviewed:

/N8 8/kI Plant Operations Review Committee Date Approved:

8!/ /9[

flant Manager [/ ()

Date'

/)8N#7

~ h fl '

Approved:

Vice Pfesident, Operations Date

.t.

LIST OF AFFECTED PAGES Pace Revision Date i

19 11/01/95 11 19 11/01/95 iii 18 07/20/95 iv 0

03/01/84 V

17 05/31/94 vi 18 07/20/95 vii 18 07/20/95 viii 17 05/31/94 ix 18 07/20/95 x

17 05/31/94 1-1 19 11/01/95 l

1-2 15 07/08/93 1-3 to 1-4 17 05/31/94 1-5 to 1-6 15 07/08/93 1-7 to 1-9 17 05/31/94 1-10 15 07/08/93 1-11 17 05/31/94 1-12 16 10/28/93 1-13 to 1-18 15 07/08/93 1-19 to 1-20 17 05/31/94 1-21 15 07/08/93 1-22 17 05/31/94 2-1 to 2-4 15 07/08/93 3-1 18 07/20/95 3-2 17 05/31/94 3-3 18 07/20/95 3-4 to 3-7 17 05/31/94 3-8 to 3-12 15 07/08/93 3-13 to 3-17 17 05/31/94 3-18 16 10/28/93 3-19 15 07/08/93

/

3-20 to 3-50 17 05/31/94 3-51 to 3-52 18 07/20/95 3-53 to 3-58 17 05/31/94 3-59 15 07/08/93 4-1 to 4-la 17 05/31/94 4-lb 19 11/01/95 4-2 19 11/01/95 4-2a 19 11/01/95 4-3 19 11/01/95 4-4 10 04/04/91 4-5 19 11/01/95 l

4-6 18 07/20/95 4-7 to 4-9 10 04/04/91 5-1 15 07/08/93 5-2 18 07/20/95 5-3 to 5-6 15 07/08/93 5-7 17 05/31/94 5-8 to 5-23 18 07/20/95 Revision 19 Date 11/01/95 -

1.0 INTRODUCTION

This ODCM (Off-Site Dose Celculation Manual) provides formal and approved methods for the calculation of off-site concentration, off-site doses, and effluent monitor setpoints in order to comply with the Vermont Yankee Technical Specifications 3.8/4.8 and 3.9/4.9. hereafter referred to as the Radiological Effluent Technical Specifications. The ODCM forms the basis for plant procedures and is designed for use by the procedure writer.

In addition, the ODCM will be useful to the writer of periodic reports required by the NRC on the dose consequences of plant operation. The dose methods contained herein follow accepted NRC guidance for calculation of doses necessary to demonstrate compliance with the dose objectives of Appendix I to 10CFR50 (Regulatory Guide 1.109) unless otherwise noted in the text.

Demonstration of compliance with the dose' limits of 40CFR190 (see Technical Specification 3.8.M) will be considered as demonstrating compliance eith the 0.1 rem limit of 10CFR20.1301(a)(1) for members of the public in unrestricted areas (Reference 56 FR 23374, third column).

It shall be the responsibility of the Chemistry Manager and Radiation Protection Manager to ensure that the ODCM is used in the performance of the surveillance requirements of the appropriate portions of Technical Specifications. The administration of the program for the disposal of slightly contaminated septic waste, as described in Appendix B. is the responsibility of the Senior Environmental Program Manager.

All changes to the ODCM must be reviewed by PORC and approved by M00, in accordance with Technical Specification 6.13, prior to implementation.

All approved changes shall be submitted to the NRC for their information in the Annual Radioactive Effluent Report for the period in which the change (s) was l

made effective. The plant's Document Control Center (DCC) shall maintain the current virsion of the ODCM and issue under controlled distribution all approved changes to it.

s Revision 19 Date 11/01/95 1-1

4.3 Distances and Directions to Monitorino Stations It should be noted that the distances and directions for direct radiation mo' itoring locations in Table 4.1, as well as the sectors shown in n

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.

l Technical Specification 6.7 and Table 3.9.3, Footnote a, specify that in the Annual Aaoiolcaical Environmental Surveillance Report and ODCM, the reactor shall be useo c the origin for all distances and directions to sampling locations. Vermont Yankee interprets "the reactor" to mean the reactor site which includes the olant stack and the Turbine Building. The distances to the plant stack and Terbine Building will, therefore, be used in the Annual Radiological Environmenta! Surveillance Reports and ODCM for the sampling and TLD monitoring stations, respectively.

Revision 19 Date 11/01/95 4-lb l

1

Table 4.1 Radiological Environmental Monitoring Stations (D Exposure Pathway Sample Location Distance and/or Samole and Designated Code (2)

(km)<5)

Direction (s) 1.

AIRBORNE (Radiciodine and Particulate)

AP/CF-11 River Station 1.9 SSE No. 3.3 AP/CF-12 N. Hinsdale,-NH 3.6 NNW AP/CF-13 Hinsdale Substation 3.1 E

AP/CF-14 Northfield, MA 11.3 SSE AP/CF-15 Tyler Hill Road (4) 3.2 WNW AP/CF-21 Spofford Lake 16.1 NNE 2.

WATERBORNE a.

Surface WR-11 River Station 1.9 Downriver No. 3.3 WR 21 Rt. 9 Bridge 12.8 Upriver b.

Ground WG-11 Plant Well On-Site WG-12 Vernon Nursing Well 2.0 SSE WG-22 Skibniowsky Well 14.3 N

c.

Sediment SE-11 Shoreline Cownriver 0.8 SSE From SE-12 North Storm 0.15 E

Shoreline Drain Outfa11(3) 3.

INGESTION a.

Milk (s)

TM 10 Back Tracks Farm 2.3 S

l TM-11 Miller Farm (4) 0.8 WNW TM-14 Brown Farm 2.1 S

TM-16 Meadow Crest Farm 4.4 WNW/NW TM-18 Blodgett Farm (d) 3.4 SE TM-24 County Farm 22.5 N

b.

Mixed TG-11 River Station 1.9 SSE Grasses No. 3.3 TG-12 N. Hinsdale NH 3.6 NNW TG-13 Hinsdale Substation 3.1 E

TG-14 Northfield, MA 11.3 SSE TG 15 Tyler Hill Rd.(d) 3.2 WNW TG-21 Spofford Lake 16.1 NNE Revision 19 Date 11/01/95 4-2

Table 4.1 (Continued)

Radiolooical Environmental Monitorina Stationsm Exposure Pathway Sample Location Distance and/or Samole and Desionated Codem (km) m Directionm c.

Silage TC-10 Back Tracks Farm 2.3 S

I TC-11 Miller Farm 0.8 WNW TC-14 Brown Farm 2.1 S

TC-16 Meadow Crest Farm 4.4

'WNW/NW W

TC-18 Blodgett Farm 3.4 SE TC-24 County Farm 22.5 N

d.

Fish FH-11 Vernon Pond (6)

(6)

FH-21 Rt. 9 Bridge 12.8 Upriver 4.

DIRECT RADIATION DR-1 River Station 1.6 SSE No. 3.3 DR-2 N. Hinsdale, NH 3.9 NNW DR 3 Hinsdale Substation 3.0 E

DR-4 Northfield, MA 11.0 SSE DR-5 Spofford Lake 16.3 NNE DR-6 Vernon School 0.46 WSW DR-7 Site Boundary (D 0.27 W

DR-8 Site Boundary.

0.25 SW DR-9 Inner Ring 2.1 N

DR-10 Outer Ring 4.6 N

DR-11 Inner Ring 2.0 NNE DR-12 Outer Ring 3.6 NNE DR-13 Inner Ring 1.4 NE DR-14 Outer Ring 4.3 NE DR-15 Inner Ring 1.4 ENE DR-16 Outer Ring 2.9 ENE DR-17 Inner Ring 1.2 E

OR-18 Outer Ring 3.0 E

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

Revision 19 Date 11/01/95 4-2a 1

Table 4.1 (Continued)

Radiolocical Environmental Monitorino Stationsm Exper,ure Pathway Sample Location Distance and/or Samole and Desionated Codem (km)W DirectionW

(

DR-26 Outer Ring 3.7 5

g DR-27 Inner Ring 1.0 SSW l

DR-28 Outer Ring 2.2 SSW DR-29 Inner Ring 0.7 WSW DR-30 Outer Ring 2.3 SW f

DR-31 Inner Ring 0.8 W

DR-32 Outer Ring 5.0 WSW DR-33 Inner Ring 0.9 WNW

{

DR-34 Outer Ring 4.9 W

DR-35 Inner Ring 1.4 WNW DR-36 Outer Ring 4.7 WNW

(

DR-37 Inner Ring 3.0 NW DR-38 Outer Ring 7.7 NW DR-39 Inner Ring 3.2 NNW

{

DR 40 Outer Ring 5.8 NNW (1)

Sample locations are shown on Figures 4.1 to 4.6.

(2)

Station Nos. 10 through 19 are indicator stations.

Station Nos. 20 through 29 are control stations (for all but the direct radiation f

stations).

(3)

To be sampled and analyzed semiannually.

(4)

Non-Tech Spec station.

(5)

Distance and direction from the center of the Turbine Building for direct radiation monitors; from the plant stack for all others.

[

(6)

Fish samples are collected from anywhere in Vernon Pond, which is adjacent to the plant (see Figure 4-1).

[

(7)

DR-8 satisfies Technical Specification Table 3.9.3 for an inner ring i

direct radiation monitoring location.

However, it is averaged as a Site Boundary TLD due to its close proximity to the plant.

(8)

In accordance with Technical Specification Table 3.9.3, notation a, samples will be collected on the required schedule as availability of milk permits. All deviations from the sample schedule will be reported in the Annual Radiological Environmental Surveillance Report.

Revision d.,

Date 11/01/95 7

4-3

I 1

l N

t

)

/

'2 O

HINSDAl.E N.H.

T A TM-16 TC 16

++e s

pt.$

I

'e'p 8

I TG 15 I

l AN/.c A "/C'*13 I

I PLANT E l

I M

j szt utaccar a rzcun a.1 I

VERNON DAM 1

A n /cr 11 YERNON, V.T.

* A A

Tc 11 W 12 w.11 TM 18 A Tc 18 TM-10 TC-10 0

1 2

.3 L1LY PQNQ

=

KIL0tETERS a

Figure 4-2 Environmental Sampling Locations Within 5 k:n of Plant Revision 19 Dace 11/01/95 4-5

APPENDIX 1 RADI0 ACTIVE LIOUID, GASE0US, AND SOLID WASTE TREATMENT SYSTEMS Reauirement: Technical Specification 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and so, lid) 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

There were no licensee-initiated major changes to the radioactive waste systems during this reporting period.

ainsa 1-1 l

APPENDIX J ON-SITE DISPOSAL OF SEPTIC WASTE Reauirement: Off-Site Dose Calculational Manual. Appendix B requires that the dose impact due to on-site disposal of septic waste during the reporting year and from previous years be reported to the Commission in the Annual Radioactive Effluent Report if disposals occur during the reporting year.

Response

There was one on-site disposal of septic waste during the reporting year.

The total volume of septage spread was approximately 9,500 gallons.

The total activity spread on the 1.9 acres (southern) on-site disposal field during 1995 and from previous years was:

Nuclide Activity (C1)

Mn-54 1.14E-07 Co-60 1.28E-05 Zn 65 1.33E-07 Cs-137 2.24E-06 The projected hypothetical dose from on-site disposals of septic waste is 9.14E-03 mrem / year.

This dose was calculated according to the model and the assumptions of Off-Site Dose Calculational Manual. Appendix B.

k

ML20101K185

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