ML20137H109
| ML20137H109 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1996 |
| From: | Duffy J VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-97-41, NUDOCS 9704020058 | |
| Download: ML20137H109 (86) | |
Text
{{#Wiki_filter:- . . .. - VERMONT YANKEE , NUCLEAR POWER CORPORATION
, Ferry Road, Brattleboro, VT 05301-7002 ENGINE R N OFFICE 680 MAIN STREET BOLToN, MA 01740 (508) 779 4 711 March 28,1997 BVY 97-41 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
(a) License No. DPR-28 (Docket No. 50-271)
Subject:
1996 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. 1 Sincerely, VER ONT YANKEE NUCLEAR POWER CORPORATION
$/L// ,
James J. Du y Licensing Engineer I c: USNRC Region I Administrator (( l USNRC Resident inspector- VYNPS - USNRC Project Manager - VYNPS 1 ! 9704020058 961231 g PDR ADOCK 05000271 1 R PDR I 150,115E551%%%,E% l
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_ - . . _ _ _ _ . . . _._._m _ _ . _ _ _.__ _ _ __ _ . . . . . _ . _ _ _ . I I I i 1 I j EFFLUENT AND WASTE DISPOSAL I ANNUAL REPORT FOR 1996 i I
- I i
I i i I i !I 1 ] Vermont Yankee Nuclear Power Station 1 !,I - stru.o j 1 )
TABLE 1A Vermont Yankee Effluent and Waste Disposal Annual Report First and Second Ouarters, 1996 Gaseous Effluents - Summation of All Releases
- Est.
Quarter Quarter Total Unit 1 2 Error, % A. Fission and Activation Gases
- 1. Total release Ci 5.18E-01 1.89E+00 i2.30E+01
- 2. Average release rate for period pCi/sec 6.59E-02 2.40E-01
- 3. Percent of Tech. Spec. limit (1) %
B. Iodines
- 1. Total Iodine-131 Ci 2.11E-04 2.76E-04 ti.80E+01 l 2. Average release rate for period pCi/sec 2.68E-05 3.51E-05
- 3. Percent of Tech. Spec. limit (1) %
B C. Particulates
- 1. Particulates with T-1/2 > 8 days Ci 4.45E-05 4.4'4E-05 il.80E+01 E 3. Average release rate for period pCi/sec 5.66E-06 5.65E-06
- 3. Percent of Tech. Spec. limit (1) %
3 4. Gross alpha radioactivity Ci 4.25E-06 2.09E-06 D. Tritium I 1. Total release Ci 7.07E+00 7.90E+00 ti.50E+01 f 2. Average release rate for period pCi/sec 8.99E-01 1.00E+00 h 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. i " muwe ~9-
TABLE 1A (Continued) Vermont Yankee Effluent and Wante Disposal Annual Report Third and Fourth Quarters, 1996 Gaseous Effluents - Summation of All Releases Est. Quarter Quarter Total Unit 3 4 Error, % A. Fission and Activation Gases
- 1. Total release Ci 1.04E+00 2.72E+00. i2.30E+01
- 2. Average release rate for period pCi/sec 1.32E-01 3.46E-01
- 3. Percent of Tech. Spec. limit (1) %
B. Iodines
- 1. Total Iodine-131 C1 4.22E-04 4.83E-05 il.80E+01
- 2. Average release rate for period pCi/sec 5.37E-05 6.14E-06
- 3. Percent of Tech. Spec. limit (1) %
C. Particulates i 1. Particulates with T-1/2 > 8 days Ci 7.81E-05 1.80E-05 il.80E+01 l 2. Average release rate for period pCi/sec 9.93E-06 2.29E-06
- 3. Percent of Tech. Spec. limit (1) %
- 4. Gross alpha radioactivity Ci 3.29E-06 3.25E-06 D. Tritium
- 1. Total release Ci 7.56E+00 1.86E+00 11.50E+01
- 3. Average release rate for period pCi/sec 9.62E-01 2.37E-01
- 3. Percent of Tech. Spec. limit (1) %
(1) Percent of Technical Specification limit will be provided in the Supplemental Effluent Gnd Waste Disposal Report to be submitted per Technical Specification 6.7.C.1. 6 anoo < f
TABLE 18 1 Vermont Yankee Effluent and Waste Disposal Annual Report First cnd Second Quarters. 1996 Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode (I) Quarter Quarter Quarter Quarter _ Nuclides Released Unit 1 2 1 2
- 1. Fission Gases ls Kryoton-85 Kr_yoton-85m C1 Ci ND ND ND ND Kryoton-87 Ci ND ND l Kryoton-88 Xenon-133 C1 ND ND l Ci ND ND Xenon-135 C1 6.18E-01 ND Xenon-135m Ci ND 1.89E+00 Xenon-138 Ci ND ND Unidentified C1 ND ND Total for period Ci 5.18E-01 1.89E+00
- 2. Iodines lI Iodine-131 C1 2.11E-04 2.76E-04 lodine-133 Ci 1.71E-03 2.18E-03 Iodine-135 Ci ND ND Total for oeriod C1 1.92E-03 2.45E-03
- 3. Particulates Strontium-89 C1 4.45E-05 4.44E-05 Strontium-90 Ci ND ND Cesium-134 ,
C1 ND ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND l Mancanese-54 Ci ND ND Chromium-51 Ci ND ND Cobalt-58 Ci eld ND Cobalt-60 Ci ND ND Cerium-141 Ci NO ND [ Zinc-65 C1 ND ND l Total for oeriod Ci 4.45E-05 4.44E 05 (1) There were no batch mode gaseous releases for this reporting period. ND - Not detected at the plant stack. ame .
1 TABLE 18 (Continued) Vermont Yankee Effluent and Waste Disposal Annual Report Third and Fourth Quarters. 1996 Gaseous Effluents - Elevated Releases Continuous Mode Batch Modeil) Quarter Quarter Quarter Quarter Nuclides Released Unit 3 4 3 4
- 1. Fission Gases Krypton-85 C1 ND ND 1
Kryoton-85m Ci ND ND Krypton-87 Ci ND 5.52E-01 Krvoton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-135 Ci ND 2.17E+00 l" Xenon-135m Ci 1.04E+00 ND Xenon-138 Ci ND ND l Unidentified Ci ND ND E Total for period C1 1.04E+00 2.72E+00 [ 2. Iodines p lodine-131 C1 4.22E-04 4.83E-05 Iodine-133 C1 3.40E-03 2.27E-04 lodine-135 C1 ND ND Total for period C1 3.82E-03 2.76E-04
- 3. Particulates Strontium-89 i Strontium-90 Ci Ci 3.60E-05 ND 1.32E-05 ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND l Barium lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium-51 Ci ND ND I Cobalt-58 Ci ND ND Cobalt-60 C1 4.21E-05 4.78E-06 Cerium-141 Ci ND ND I 71nc-65 Total for period Ci ND ND Ci 7.81E-65 1.80E-05 (1) There were no batch mode gaseous releases for this reporting period.
ND - Not detected at the plant stack. nruo c W
k [ TABLE IC Vermont Yankee Effluent and Waste Disposal Annpal Report First and Second Quarters 1996 Gaseous Effluents - Ground Level Releases (1), (2) Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit 1 2 1 2
- 1. Fission Gases KryDton-85 C1 Krypton-85m C1 Krypton-87 Ci Kryoton-88 C1 Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Xenon-131m Ci Total for oeriod Ci 0.00E+00 0.00E400
- 2. Todines lodine 131 Ci lodine-133 Ci lodine-135 Ci Total for oeriod Ci 0.00E+00 0.00E+00
- 3. Particulates Strontium-89 Ci Strontium-90 C1 Cesium-134 C1 Cesium-137 Ci Barium-Lanthanum 140 Ci Manganese-54 C1 C h ron,i um- 51 C1 Cobalt-58 Ci Cobalt-60 C1 Cerium-141 C1 linc-65 Ci Iron-55 Ci Total for period Ci 0.00E+00 0.00E+00 (1) There were no ground level gaseous releases for this reporting period.
.(2) Use of the North Warehouse stack 6s a ground level release point was initiated at the beginning of the fourth quarter of 1994.
ND - Not detected in the waste oil sample. auuo TABLE 1C (Continued) Vermont Yankee Effluent and Waste Disposal Annual Report Third and Fourth Ouarters 1996 Gaseous Effluents - Ground Level Releasesa). (2) Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit 3 4 3 4
- 1. Fission Gases Krypton-85 Ci KryDton-85m Ci KryDton-87 Ci Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Xenon-131m Ci Total for period Ci 0.00E+00 0.00E+00
- 2. lodines Iodine-131 Ci lodine-133 Ci Iodine-135 Ci Total for period Ci 0.00E+00 0.00E+00
- 3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Barium-Lanthanum-140 C1 Manganese-54 Ci Chromium-51 C1 Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci linc-65 Ci Iron-55 Ci Total for period Ci 0.00E+00 0.00E+00 (1) There were no ground level 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. NO - Not detected in the waste oil sample. mue TABLE 10
, Vermont Yankee Effluent and Waste Disposal Annual Report for 1996 Gaseous Effluents - Nonroutine Releases i There were no nonroutine or accidental gaseous releases during this reporting period.
I I I I I I I I II M as tuo - W
TABLE 2A Vermont Yankee Effluent and Waste Disposal Annual Report for 1996 Liauid Effluents - Summation of All Releases There were no liquid releases during this reporting period. I I I I I I I I I I i muo -
TABLE 2B Vermont Yankee Effluent and Waste Disposal Annual Report for 1996 Liouid Effluents - Nonroutine Releases There were no liquid releases during this reporting period. I I l 1 l I I I I I airuo -
k TABLE 3 Vermont Yankee Effluent and Waste Disposal Annual Report First and Second Ouarterr.,1996 Solid Waste and Irradiated Fuel Shioments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated' Fuel): Unit 6-Month Est. Total
- 1. Type of Waste Period Error. %
f a. Spent resins, filter sludges, evaporator m' bottoms. etc. Ci i7.50E+01
- b. Dry compressible waste, contaminated
(' eautoment, etc. m' Ci *7.50E+01
- c. Irradiated components, control rods, m' etc. Ci +7.50E+01
- 2. Estimate of Major Nuclide Composition (By Type of Waste):
- a. Zine-65 % b. Iron-55 %
Cesium-137 % Zinc-65 % Cobalt-60 % Cobalt-60 % Cesium-134 % Manaanese-54 % Manaanese-54 % Cesium-137 %
- 3. Solid Waste Disposition:
Number of Shioments Mode of Transportation Destination "No solid waste was disposed during this period."
- 8. Irradiated Fuel Shipments (Disposition):
None C. Supplemental information f
- 1) Class of solid waste containers shipped:
- 2) Types of containers used:
{ 3) Solidification agent or absorbent: None unso TABLE 3 (Continued) Vermont Yankee Effluent and Waste Disposal Annual ReDort { Third and Fourth Quarters. 1996 Solid Waste' and Irradiated Fuel Shioments A. Solid Waste Shipped Off-Site for Burial or Olsposal (Not Irradiated fuel): Unit 6-Month Est. Total
-1. Type of Waste Period Error. %
r, a. Spent resins, filter sludges, evaporator m3 0.00E+00 bottoms, etc. 0.00E+00 C1 i7.50E+01
- b. Dry compressible waste, contaminated m3 1.45E+01 eauipment etc. C1 4.89E-01 i7.50E+01
- c. Irradiated components, control rods, m3 0.00E+00 etc. C1 0.00E+00 i7.50E+01
- 2. Estimate of Major Nuclide Composition -(By Type of Waste):
- a. Zinc-65 % b. Iron-55 5 8.31E+01 Cesium-137 % Zinc-65 % 9.00E-02 Cobalt-60 % Cobalt-60 % 8.30E+00
[> Manaanese 54 % Manaanese-54 % 4.00E+00 L. Nickel-63 % Cromium 51 % 1.40E+00 Iron-55 % Cesium-137 % 1.20E+00 3._ Solid Waste Disposition: Number of Shioments Mode of Transoortation Destination 11 Truck Barnwell. SC ( B. Irradiated Fuel Shipments (Disposition): None , C. Supplemental information
- 1) Class of solid waste containers shipped: 18A
- 2) Types of containers used: 18 Strong Tight
- 3) Solidification agent or absorbent: None
~
[ e m 6a 19-
i l ( I TABLE 5A VERMONT YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOIrr FREQUENC'Y DISTRIBUTION 297.0 FT WIND DATA STABILITY C1. ASS A CIASS FREQUENCY (PERCENT) = .24 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W MPH WNW NW HNW YRBL 70TAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 0 0 0 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
.00 .00 .00 .00 .00 .00 .00 .00 .00
.00
.00 .00 .00 .00 .00 .00 .00 C-3 1 0 1 1 0 0 1 1 0 C 0 0 (1) 4.76 00 4.76 4.76 1 0 0 0 0
.00 .00 4.76 4.76 .00 .00 .00 .00 4.76 .00 6
(2) .01 .00 .01 .01 .00 .00 .00 .00 28.57
.00 .01 .01 .00 .00 .00 .00 .01 .00 .00 .00 .00 .07 4-7 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 4.76 2 0 3 (2) .00 .00 .00 .00 .00 .00 .00 .00
.00 .00 .00 .00 .00 .00 .01 .00 .00
.00 9.52 - 14.29
.00 .00 .00 .00 .00 .02 .00 .03 8-12 2 2 0 0 0 0 0 1 0 0 0 0 0 (1) 9.52 9.52 .00 .00 .00 .00 .00 4.76 .00 .00 .00 .00 .00 1 0 2 0 8 (2) .02 .02 .00 .00 .00 .00 4.76 .00 9.52 .00 38.10
.00 .01 .00 .00 .00 .00 .00 .01 .00 .02 .00 .09 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 1 2 0 3 (2) .00 .00 .00 .00 .00 .00 4.76 9.52 .00
. .00 .00 .00 .00 .00 .00 .00 .00 .00 14.29
.00 .00 .00 .00 .01 .02 .00 .03 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 0 0 0 0 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
.00 .00 .00 .00 .00 .00 .00 .00 .D0 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 0 1 0 1 (2) .00
.00 .00 .00 .00 .00 .00 .00 .00 4.76 .00
.00 .00 .00 .00 .00 .00 .00 .00 .00 4.76
.00 .00 .00 .00 .00 .01 .00 .01
/LL SPEEDS 3 2 1 1 0 0 1 3 0 0 0 0 1 1 7 (1) 14.29 9.52_ 4.76 4.76 .00 .00 4.76 14.29 .00 .00 .00 .00 1 0 21 (2) ,03 .02 .01 .01 .00 .00 .01 .03 .00 4.76 4.76 4.76 33.33 .00 100.00
.00 .00 .00 .01 .01 .01 .08 .00 .24 (1)mPERCEtrF OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2)sPERCENT OF ALL OOOD OBSERVATIONS FOR THIS PERIOD Ca CAIM (WIND SPEED LESS THAN OR EQUAL 70 ' (PH) i
I f TABLE SB. VERMONT YANKEE JAN 96 - DEC 96 METEOROID 01 CAL DATA JOINT FREQUENCY DIS'ITtIBUTION 297.0 PT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = .63 WIND DIRECTION FROM SPEED N leiE NE ENE E ESE SE SSE S SSW SW WSW W WNW PM 384W VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 f, 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00
.00 .00
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 C-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 0 0 0
.00 .00 .00 .00 .00 .00 .00 .00 . f.0 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00
.00 .00
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4-7 0 0 0 0 0 0 1 0 0 2 0 0 0 0 1 3 0 7 (1) .00 .00 .00 .00 .00 .00 1.85 .00 .00 3.70 .00 .00 .00 .00 (2) .00 .00 .00 .00 1.85 5.56 .00 12.96
.00 .00 .01 .00 .00 .02 .00 .00 .00 .00 .01 .03 .00 .A8 8-12 1 0 0 0 0 0 0 9 1 0 0 0 2 4 1.85 3 8 0 28 (1) .00 .00 .00 .00 .00 .00 16.67 1.85 .00 .00 .00 3.70 5.56 7.41 14.81 .00 51.85 (2) .01 .00 .00 .00 .00 .00 .00 .10 .01 .00 .00 .00 .02 .03 .05 .09 .00 .33 13-18 0 0 2 0 0 0 1 2 0 0 0 0 0 0 2
.00 8 0 15 (1) .00 3.70 .00 .00 .00 1.85 3.70 .00 .00 .00 .00 .00 .00 3.70 14.81 .00 27.78 (2) .00 .00 .02 .00 .00 .00 .01 .02 .00 .00 .00 .00 .00 .00 .02 .09 .00 .17 19-24 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 1 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.85 1.85 .00 1.85 .00 5.56 (2) .00 .C0 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .01 .00 .03 07 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.85 .00 1.*5 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 ALL SPEEDS S 0 2 0 0 0 2 11 1 2 0 0 3 4 7 21 0 54 (1) 1.85 .00 3.70 .00 .00 .00 3.70 20.37 1.85 3.70 .00 .00 5.56 7.41 12.96 38.89 (2) .01 .00 100.00
.00 .02 .00 .00 .00 .02 .13 .01 .02 .00 .00 .03 .05 .08 .24 .00 .63 (1)oPERCENT OF All .'3OD OBSERVATIONS FOR T1f18 PAGE (2)sPERCENT OF 442, GOOD OBSERVATIONS FOR THIS PERIOD Co CALM (WIND SPEED LESS ' MAN OR EQUAL to .95 MPH)
{
TABLE SC VBHNONT YANICEE JAN 96 - DEC 96 NE*ISOROLOGICAL DATA JOINT FREQUENCT DISTICSUTION 297.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) e 1.87 WIND DIRECTION FROM CPEED N SSIE NE ENE E ESE SE SSE S SSW SW WSW MPH W tefW NW telW VRRL '! OPAL CAiht 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 ,00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .62 -. 00 .00 .00 .00 .00 .00 .00 .00 .00 .62 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 4-7 1 0 0 0 0 7 5 5 2 2 0 1 0 0 0 6 0 29 (1) .62 .00 .00 .00 .00 4.35 3.11 3.11 1.24 1.24 .00 .62 .00 .00 .00 3.73 (2) .01 .00 .00 .00 18.01
.00 .00 .08 .06 .06 .02 .02 .00 .01 .00 .00 .00 .07 .00 .34 8-12 3' O O O O 3 5 20 10 0 1 1 3 0 1 17 0 64
. (1) 1.86 .00 .00 .00 .00 1.86 3.11 32.42 6.21 .00 .62 .62 1.86 . 00 .62 10.56 .00 39.75 (2) .03s
.00 .00 .00 .00 .03 .06 .23 .12 .00 .01 -. 01 .03 .00 .01 .30 .00 .75 13-18 5 1 1 0 0 0 1 2 4 1 0 0 0 5 24 4 0 48 (1)- 3.11 .62 .62 .00 .00 .00 .62 1.24 2.48 .62 .00 .00 . 00 3.11 2.48 14.91 .00 29.81 (2) - .06 .01 .01 .00 .00 .00 .01 .02 .05 .01 .00 .00 .00 .06 .05 .28 00 .56 19-24 1 0 0 0 1 0 0 0 0 0 0 0 0 3 1 7 0 13 (1) .62 .00 .00 .00 .62 .00- .00 .00 00 .00 .00 .00 .00 1.86 .62 4.35 .00 8.07 (2) .01 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .03 .01 .08 .00 .15 0T 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2- 4 0 6 (1) .00 ..00 .00 .00. .00 .00 .00 .00 .00 ' .00 .00 .00 .00 .00 1.24 2.48 .00 3.73 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .05 .00 .07 ALL SPEEDS 10 1 1 0 1 10 11 28 16 3 1 2 3 8
- 8 58 0 161 (1) 6.21 .62 .62 .00 .62 6.21 6.83 17.39 9.94 1.86 .62 1.24 1.86 4.97 4.97 36.02 .00 100.00 (2) .12 .01 .01 .00 .01 .12 .13 .33 .19 .03 .01 .02 .03 .09 .09 .68 .00 1.87
.(E)=PERCENP OF ALL GOOD OBSERVATIONS FOR THIS PAGE
- f. (3)sPERCENT OF ALL OOOD OBSERVATIONS FOR 'ntIS PElRIOD l Co CALM (WIND SPEED LESS '5 TAN OR EQUAL 'to .95 MPH) 24_
f l r l _ _ _ _ _ _ _ .J
1 I I TABLE 5D I VERNOtn YANKEE JAN 96 - DEC 96 HETEOROLOGICAL DATA JOI!G FREQUENCY DISTRIBLTTICM 297.0 FT WIND DATA STABILITY CLASS D CIASS FREQUENCY (PERCEta) = 50.45 I WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WR IM NNW VRBL TOTAL MPH I CAIJi 1 2 0 1 0 0 0 1 1 0 0 0 0 0 0 0 0 6 (1) .02 .05 .00 .02 .00 .00 .00 .02 .02 .00 .00 .00 .00 .00 .00 .00 .00 .14 (2) .01 .02 ,00 .01 .00 .00 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .07 C-3 77 40 32 30 60 45 71 49 39 16 17 13 14 20 36 p 62 0 621 (1) 1.78 .92 .74 .69 1.38 1.04 1.64 1.13 .90 .37 .39 .30 .32 .46 .83 1.43 .00 14.33 (2) .90 .47 .37 .35 .70 .52 .83 .57 .45 .19 .20 .25 .16 .23 .42 .72 .00 7.23 4-7 82 36 27 21 45 72 154 139 114 28 16 12 20 26 51 169 0 1012 (1) 1.89 .83 .62 .48 1.04 1.66 3.55 3.21 2.63 .65 .37 .28 .46 .00 (2) .95 .42 .31 .24
.60 1.18 3.90 23.36
.52 .84 1.79 1.62 1.33 .33 .19 .14 .23 .30 .59 1.97 .00 11.78 8-12 143 45 18 13 25 34 35 129 252 39 29 31 53 95 64 210 (1) 0 1215 3.30 1.04 .42 .30 .58 .78 .81 2.98 5.82 .90 .67 .72 1.22 2.19 1.48 4.85 .00 28.04
- 42) 1.67 .52 .21 .15 .29 .40 .41 1.50 2.93 .45 .34 .36 .62 1.11 .75 2.45 .00 14.15 I 13-18 148 15 16 12 11 4 6 19 115 17 15 16 64 156 113 214 0 941 (1) 3.42 .35 .37 .28 .25 .09 .14 .44 2.65 .39 .35 .37 1.48 3.60 2.61 4.94 .00 21.72 (2) 1.72 .17 .19 .14 .13 .05 .07 .22 1.34 .30 .17 .19 .75 1.82 1.32 2.49 .00 10.96 19-24 46 0 2 1 0 1 1 6 61 0 1 5 17 83 82 129 0 435 g (1) 1.06 .00 .05 .02 .00 .02 .02 .14 1.41 .00 .02 .12 .39 1.92 1.89 2.98 .00 10.04 (2) .54 .00 .02 .01 .00 .01 .01 .07 .71 .00 .01 .06 .20 .97 .95 1.50 .00 5.07 DT 24 6 0 0 0 0 0 0 4 20 0 0 0 22 10 3 38 0 103 (1) .14 .00 .00 .00 .00 .00 .00 .09 .46 .00 .00 .00 .07 .51 .23 .88 2.38 I (2) .07 .00 .00 .00 .00 .00 .00 .05 .23 .00 .00 .00 .03 .26 .12 .44
.00
.00 1.20 ALL SPEEDS 503 138 95 78 141 156 267 347 602 100 78 77 171 402 356 822 0 4333 (1)
(2) 11.61 3.18 2.19 1.80 5.86 1.61 1.11 .91 3.25 3.60 6.16 8.01 13.89 2.31 1.80 1.78 3.95 9.28 8.22 18.97 .00 100.00 1.64 1.82 3.11 4.04 7.01 1.16 .91 .90 1.99 4.68 4.15 9.57 .00 50.45 1 (1)sPERCENT OF ALL GOOD OBSERVATICNS FOR THIS PAGE (2)mPERCDC OF ALL GOOD OBSERVATIONS FOR DEIS PERIOD Cs CALM (WIND SPEED LESS DIAN OR EQUAL 70 .95 MPH) I I u r
I I TABLE SE I VERMONT YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOIYT FRE& M DISTRI NFION 297.0 FT WIND DATA STABILITY CLASS E 33.99 I CLASS FREQUENCY (PERCDrf) = sfIND DIRECTION FRCN SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TCrTAL I MPH CALM 2 0 1 2 0 1 2 0 1 2 0 2 0 0 0 0 0 13 (1) .07 .00 .03 .07 .00 .03 .07 .00 .03 .07 .00 .07 .00 .00 .00 .00 .00
.02 .00 .45 (2) .01 .02 .00 .01 .02 .00 .01 .02 .00 .02 .00 .00 .00 .00 .00 .15 I C-3 (1)
(2) 113 1.32 77
.90 .70 60 54
.63 .62 53 101 3.87 2.64 2.06 1.85 1.82 3.46 3.87 2.30 1.44 1.18 1.32 113 67
.78 42
.49 22
.75
.26 15
.51
.17 17
.58
.20 10
.34
.12 22 34
.75 1.16 2.88
.26 .40 84
.00 0 884 30.28
.98 .00 10.29 4-7 133 25 11 13 10 34 132 157 87 27 19 22 23 30 38 257 0 1018 I (1)
(2) 4.56 1.55
.86
.29
.38
.13
.45
.15
.34
.12 1.16 4.52 5.38 2.98
.40 1.54 1.83 1.01
.92
.31
.65
.22
.75
.26
.79
.27 1.03 1.30 8.80
.35 .44 2.99
.00
.00 34.87 11.85 8-12 67 6 0 1 3 2 24 73 87 22 12 22 43 46 45 219 0 672 (1) 2.30 .21 .00 .03 .10 .07 .82 2.50 2.98 .75 .41 .75 1.47 1.58 1.54 7.50 .00 23.02 (2) .78 .07 .00 .01 .03 .02 .28 I 13-18 26 0 0 0 1 0 0
.85 1.01 7 34
.26 8
.34 3
.26 5
.50 20
.54 44
.52 2.55 16 88
.00 0
7.82 252 (1) .89 .00 .00 .00 .03 .00 .00 .24 1.16 .27 .10 .17 .69 1.51 .00
.55 3.01 8.63 (2) .30 .00 .00 .00 .01 .00 .00 .08 .40 .09 .03 .06 .23 .51 .19 1.02 .00 2.93 I 19-24 (1)
(2)
.14
.05 4
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.34
.22 10 11
.38 .03 1
.00 0
.00 0
.00 0
.10 3 to
.34 24
.82 .00 0 63 2.16
.13 .01 .00 .00 .00 .03 .12 .28 .00 .73 GT 24 0 0 0 0 0 0 0 7 5 0 0 0 0 0 1 4 0 17 I (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.24
.08
.17
.06
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.03
.01
.34
.05
.00
.00
.58
.20 ALL SPEEDS 345 108 72 70 67 138 271 321 267 82 49 . 68 96 145 144 676 0 2919 (1) 11.82 (2) 3.70 2.47.84 2.40
.82 2.30 4.73 9.28 11.00 9.15 2.81 1.68 2.33 3.29 4.97 4.93 23.16 .00 100.00 I .78 4.02 1.26 1.61 3.16 3.74 3.11 .95 .57 .79 1.12 1.69 1.68 7.87 .00 33.99 (llePERCDrF OF ALL GOOD OBSERVATIONS FOR 'lHIS PAGE (2)* PERCENT OF ALL GOOD OBSERVATIONS FOR 'DtIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL 'Io .95 MPH)
I I I I
TABLE 5F I VERMOffF YANKEE JAN 96 - DEC 96 METEORO!40ICAL DATA JOINT FREQUENCY DISTRIBtTFICN 297.0 FT WIND DATA STABILITY CLASS F I WIND DIRECTI N FROM CLASS FREQUCJC1 (PERCENT) = 11.35 N NNE i SPEED NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL W TAL MPH CALM 1 1 3 1 1 0 0 2 0 0 0 0 0 1 1 0 0 11 (1) .10 .30 .31 .10 .10 .00 .00 .21 .00 .00 .00 .00 .00 .10 .10 .00 .00 1.13 (2) .01 .01 .03 .01 .01 .00 .00 .02 .00 .00 .00 .00 .00 .01 .01 .00 .00 .13 I C-3 (1) (2) 44 4.51
.51 3.79
.43 37 28 2.87
.33 19 24 30 41 27 22 1.95 2.46 3.08 4.21 2.77 2.26 2.36 1.03 1.23 1.44 1.23 3.18 3.69
.22 .28 .35 .48 .31 .26 23
.27 10
.12 12
.14 14
.16 12
.14 31
.36 36
.42 0
.00
.00 410 42.05 4.77 4-7 36 9 3 3 9 12 44 46 28 17 14 20 19 17 26 94 0 397 (1) 3.69 .92 .31 .31 .92 1.23 4.51 4.72 2.87 1.74 1.44 2.05 1.95 1 (2) .42 .10 .03 .03 .10 .14 .51 .54 .33 .20 .16 .23 .22 1.74- 2.67 9.64
.20 .30 1.09
.00
.00 40.72 4.62 8-12 7 0 0 0 0 2 15 11 13 4 8 8 7 10 5 56 0 146 (1) .72 .00 .00 .00 .00 .21 1.54 1.13 1.33 .41 .82 .82 .77 1.03 .51 5.74 .00 14.97 (2) .08 .00 I 13-18 1 0
.00 0
.00 0
.00 0
.02 0
.17 0
.13 0
.35 2
.05 0
.09 1
.09 0
.08 0
.12 1
.06 1
.65 4
.00 0
1.70 to (1) .10 .00 .00 .00 .00 .00 .00 .00 .21 .00 .10 .00 .00 .10 .10 .41 .00 1.03 (2) .01 .00 .00 .00 .00 .00 .00 .00 .02 .00 .01 .00 .00 .01 .01 .05 .00 .12 I 19-24 (1) (2)
.00 0
.00
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0 0 00
.00
.00
.00 0
.00
.00 0
.10
.01 1
.00
.00 0
.00
.00 0
.00
.00 0 0 00
.00
.00
.00 0
.00 0
.00 0
.00 0
.10 1
.00 .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1 (2) .00 .00 .00 .00 .00 .00
.00
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 89 47 34 23 34 44 100 86 66 44 33 40 40 41 64 190 0 975 (1) 9.13 4.82 3.49 2.36 3.49 4.51 10.26 8.82 6.77 4.51 3.38 4.10 4.10 4.21 6.56 19.49 .00 100.00 (2) 1.04 .40 I .55 .37 .40 (1)= PERCENT OF ALL 000D OBSERVATIONS FOR THIS PAGE (2)=PERCEtTP OF ALL GOOD OBSERVATIONS FOR 'ntIS PERIOD
.51 1.16 1.00 .77 .51 .38 .47 .47 .48 .75 2.21 .00 11.35 Ce CALM (WIND SPEED LESS '!HAN OR EQUAL M .95 MPH) l I
I I
2 TABLE SG 1 VERHONT YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCDrf') = 1.46 WIND DIRECTION FROM
, SPEED N HNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL 'KrTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 ' . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I C-3 (1)
(2) .03 3 2
.02 2
2.40 1.60 1.60 2.40
.02 3
.03 0
.00
.G0
.80
.01 1 2 4 1.60 3.20 2.40
.02 .05 3
.03 1
.80
.01 2 3 1.60 2.40 4.00
.02 .03 .06 5
.80
.01 1 1
.80
.01 1
.80
.01
.00
.00 0 34 27.20
.40 4-7 4 1 1 0 0 2 8 10 5 4 3 2 1 5 2 6 0 54 (1) 3.20 .80 .80 .00 .00 1.60 6.40 8.00 4.00 3.20 2.40 1.60 .80 4.00 1.60 4.80 .00 43.20 l I (2) .05. .01 .01 .00 .00 .02 .09 .12 .06 .05 .03 .02 .01 .06 .02 .07 .00 .63 8-12 2 0 0 0 0 1 1 3 2 1 1 2 3 2 2 13 0 33 (1) 1.60 .00 .00 .00 .00 .80 .80 .80 .80 .00 26.40 I
2.40 1.60 1.60 2.40 1.60 1.60 10.40 (2) .02 .00 .00 .00 .00 .01 .01 .03 .02 .01 .01 .02 .03 .02 .02 .35 .00 .38 13-18 0 0 0 0 0 0 0 1 0 0 0 0 1 1 0 1 0 e i (1) .00 .00 .00 .00 .00 .00 .00 .80 .00 .00 .00 .00 .80 .80 .00 .80 .00 3.20 ! (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .01 .01 .00 .01 .00 .05 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0c .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 l (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ' ALL IPEEDS 9 3 3 3 0 4 11 18 10 6 6 7 10 9 5 21 0 125 (1) 7.20 2.40 2.40 2.40 .00 3.20 8.80 14.40 8.00 4.80 4.80 5.60 8.00 7.20 4.00 16.80 .00 100.00 l (2) .10 .03 .03 .03 .00 .05 .13 .21 .12 .07 .07 .08 .12 .10 .06 .24 .00 1.46 I. (1)* PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)aPERCENT OF ALL GOOD OBSERVATICBIS FOR THIS PERIOD l Cs CALM (WIND SPEED LESS THAN OR EQUAL to .95 MPH) l I l l l l l l f t
~28-
I TABLE SH VFRMOtFF YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOINT FREQUENCY DIS *RIBUTION 297.0 FT WIND DATA STABILITY CLASS ALL CLASS FRdQUF. JCT (PERCGT) = 100.00 , i WIND DIRECTION FROM , SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH i CALM l 4 3 4 4 1 1 2 3 2 2 0 2 0 1 1 0 0 30 j (1) .05 .03 .05 .05 .01 .01 .02 .03 .02 .02 .00 .02 .00 .01 .01 .00 .C0 .35 l (2) .05 .03 .05 .05 .01 .01 .02 .03 .02 .02 .00 .02 .00 .01 .01 .00 .00 .35 ) I C-3 (1) (2) 238 156 123 107 137 177 22E 2.77 1.83 1.43 1.25 1.60 2.06 2.65 1.73 1.23 2.77 1.82 1.43 1.25 1.60 2.06 2.65 1.13 1.23 149 106 62
.72
.72 44
.51
.51 45
.52
.52 44
.51
.51 Sb 102 183
.64
.64 1.19 2.13 1.19 2.13
.00
.00 0 1956 22.78 22.75 4-7 256 71 42 37 64 127 344 358 236 80 52 57 63 78 118 537 0 2520 (1) 2.98 .83 .49 .43 .75 1.48 4.01 4.17 2.75 .93 .61 .66 73 .91 1.37 6.25 .00 29.34 (2) 2.58 .83 .49 .43 .75 1.48 4.01 4.17 2.75 .93 .61 .66 .73 .91 1.37 6.25 .00 29.34 8-12 225 53 18 14 28 42 80 246 365 66 51 64 111 157 121 525 0 2166 (1) 2.62 .62 .21 .16 .33 .49 .93 2.86 4.25 .77 .59 .75 1.29 1.83 1.41 6.11 .00 25.22 (2) 2.62 .61 .21 .16 .33 .49 .93 2.86 4.25 .77 .59 75 1.29 1.83 1.41 6.11 .00 25.22 13-18 180 16 19 12 12 4 8 31 155 26 19 21 85 207 137 341 0 1273 (1) 2.10 .19 .22 .14 .14 .05 .09 .36 1.80 .30 .22 .24 .99 2.41 1.60 3.97 .00 14.82 (2) 2.10 .19 .22 .14 .14 .05 .09 .36 1.80 .30 .22 .24 .99 2.41 1.60 3.97 .00 14.82 19-24 51 0 2 1 1 1 1 16 *13 1 1 5 18 90 93 161 0 515 (1) .59 .00 .02 .01 .01 .01 .01 .19 .85 .01 .01 .06 .21 1.05 1.08 1.87 .00 6.00 I (2) .59 .00 .02 .01 .01 .01 .01 .19 .85 .01 .01 .06 .21 1.05 1.08 1.87 .00 6.00 GT 24 6 0 0 0 0 0 0 11 25 0 0 0 3 22 13 48 0 128 I (1)
(2) ALL SPEEDS
.07
.07
.00
.00
.00
.00
.00
.00 960 299 208 175 243 352
.00
.00
.00
.00
.00
.00 663
.13
.13 814
.29
.29 962 237
.00
.00
.00
.00
.00
.00 167 194 324
.03
.03 (1) 11.18 3.48 2.42 2.04 2.83 4.10 7.72 9.48 11.20 2.76 1.94 2.26 3.77 7.10 6.81 20.90
.26
.26
.15
.15 610 585 1795
.56
.56
.00
.00 0
.00 1.49 1.49 8588 100.00 I (2) 11.18 3.48 2.41 2.04 2.83 4.10 7.72 9.48 11.20 2.76 1.94 2.26 3.77 7.10 6.81 20.90 (1)ofERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)sPERCDff OF ALL 000') CBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS 'n!AN OR EQUAL TO .95 MPH)
.00 100.00 l
TABLE 6A I VERMOtff YANKFE JAN 96 - DEC 96 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCDrr) . 1.95 g WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL '!VTAL PPH I CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1 C-3 (1) (2) 3
.04 2
.02 2
.02 .05 4
.05 4
1.81 1.20 1.20 2.41 2.41 2.41 1.20
.05 4
.02 2 1
.60
.01 1
.60
.01 1
.60
.01 0
.00
.00 0
.00
.00
.60 1
.01 0
.00
.00 0
.00
.00
.00
.00 0 0
.00 15.06 25
.00 .29 4-7 12 1 1 1 1 7 5 9 1 0 0 0 1 2 13 27 0 81 (1) 1.23 .60 .60 .60 .60 4.22 3.01 5.42 .60 .00 .00 .00 .60 .00 I (2) .14 .01 .01 .01 .01 .08 .06 .11 .01 .00 .00 .00 .01 1.20 7.83 16.27
.02 .15 .32 .00 48.80
.95 8-12 12 0 0 0 0 0 0 5 1 0 0 0 0 5 5 19 0 47 (1) 7.23 .00 .00 .00 .00 .00 .00 3.01 .60 .00 .00 .00 .00 3.01 3.01 11.45 .00 28.31 (2) .14 .00 .00 .00 .00 .00 .00 .06 .01 .00 .00 .00 .00 .06 .06 .22 .00 .55 I 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 3 5 5 0 13 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.81 3.01 3.01 .00 7.83 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .06 .06 .00 .15 19-24 0 0 0 0 I (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 '. 00 .00 .00 .00 .00 .00 .00 .00 I (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 27 3 3 5 5 11 7 15 3 1 0 0 2 10 23 51 0 166 (1) 16.27 1.81 1.81 3.01 3.01 6.63 4.22 9.04 1.81 .60 .00 .00 1.20 6.02 13.86 30.72 .00 100.00 (2) .32 .04 .04 .06 .06 .13 .08 .18 .04 .01 .00 .00 .02 .12 .27 .60 .00 1.95 I (llePERCENT OF ALL 000D OBSERVATIONS FOR THIS PAGE (2)* PERCENT OF ALL OOOD OBSERVATIONS FOR 'IEIS PERIOD Co CAIJ4 (WIND SPEED LESS THAN OR EQUAL 29 .95 HPH) I b r W W
i TABLE 6B 1 VERMONT YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOIWi FREQUNCY DISTRIBUTION 35.0 FT WIND DATA STABILIT1f CLASS B CLASS FPEQUMCY (PERCENT) e 1,73 I WIND DIRECTION FROM SPEED N NNE NE WE E ESE SE SSE S SSW SW WSW W ICM NW I@M VRBL TCffAL MPH I CALM
.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 1 1 0 1 4 0 1 1 0 0 0 0 0 0 0 9 y (1) .00 .00 .68 .68 .00 .68 2.72 .00 .68 .68 .00 .00 .00 .00 .00 .00 .00 6.12 (2) .00 .00 .01 .01 .00 .01 .05 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .11 4-7 13 0 1 0 1 7 10 12 5 0 0 1 1 1 7 15 0 74 (1) 8.84 .00 .68 .00 .68 4.76 6.80 8.16 3.40 .00 .00 .68 .68 .68 4.76 10.20 .00 50.34 (2) .15 .00 .01 .00 .01 .08 .22 .14 .06 .00 .00 .01 .01 .01 .08 .18 .00 .87 8-12 18 0 0 0 0 0 1 6 5 1 0 0 1 4 4 11 0 51 (1) 12.24 .00 .00 .00 .00 .00 .68 4.08 3,40 .68 .00 .00 .68 2.72 2.72 7.48 .00 34.69 (2) .21 .00 .00 .00 .00 .00 .01 .07 .06 .01 .00 .00 .01 .05 .05 .13 .00 .60 P 13-18 2 0 0 0 0 0 0 1 2 0 1 0 1 4 0 1 0 12 (1) 1.36 .00 .00 .00 .00 .00 .00 .68 1.36 .00 .68 .00 .68 2.72 .00 .68 .00 8.16 (2) .02 .00 .00 .00 .00 .00 .00 .01 .02 .00 .(1 .00 .01 .05 .00 .01 .00 .14 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .68 .00 .00 .68 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .01 er 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 A% SPEEDS 33 0 2 1 1 8 15 19 13 2 1 1 3 9 12 27 0 147 (1) 22.45 .00 1.36 .68 .68 5.44 10.20 12.93 8.84 1.36 .68 .68 2.04 6.12 8.16 18.37 .00 100.00 (2) .39 .00 .02 .01 .01 .09 .18 .22 .15 .02 .01 .01 .04 .11 .14 .32 .00 1,73 m (1) PERCENT OF ALL GOOD OBSERVATICX4S FOR THIS PAGE (3)oPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Co CAIJE (WIND SPEED LESS '!HAN OR EQUAL 'm .95 MPH) l l
e
r TABLE 6C VERNONT YANKEE JAN 96 - DEC 96 NEMOROLOGICAL DATA JOIwr FRSQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS C CIASS FREQUENCY (PERCENT) = 2.81 WIND DIRECTION FROM
~
SPEED N NNE NE ENE E ESE SSE SE S SSW. SW WSW W NNW NW NNW VRBL W TAL NPH - CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) 00 .00 .00
.00 .00 .00 .00
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 90 '.00 .00 C-3 4 3 1 0 0 1 1 2 0 0 0 0 0 0 2 2 0 16 (1) 1.67 1.26 .42 .00 .00 .42 .42 .84 .00 .00 .00 .00 .00 .00 .84 (2) .05 .04 .01 .00 .84 .00 6.69
.00 .01 .01 .02 .00 .00 .00 .00 .00 .00 .02 .02 .00 .19 4-7 22 3 0 3 8 7 10 10 22 3 0 2 5 6 6 18 0 125 (1) 9.21 1.26 .00 1.26 3.35 2.93 4.18 4,18 9.21 1.26 .00 .84 (2) .26 .04 .00 .04 .09 .08 2.09 2.51 2.51' 7.53 .00 52.30
.12 .11 .26 .04 .00 .02 .06 .07 .07 .21 .00 1,47 8-12 16 2 0 0 0 1 1 4 12 3 6 '1 7 8 (1) 6.69 8 15 0 84
.84 .00 .00 .00 .42 .42 1.67 5.02 1.26 2.51 .42 (2) .19 .02 .00 .00 2.93 3.35 3.35 6.18 .00 35.15
.00 .01 .01 .05 .14 .04 .07 .01 .08 .09 409 .18 .00 .99 13-18 2 0 0 0 0 0 0 0 3 1 0 2 0 4 0 2 0 14 (1) .84 .00 .00 .00 .00 .00 .00 .00 1.26 .42 .00 .84 .00 1.67 .00 .84 .00 5.86 (2) .02 .00 .00 .00 .00 .00 .00 .00 .04 .01 .00 .02 .00 .05 .00 .02 .00 .16 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
-(1) .00 .0D .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00
.00 .00
.00 .00 .00 .00 . 00 .00 .00 .00 .00 00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 (1). .00 .00 0 0 0 0- 0 0 0
.00 .00 .00 .00 .00 .00 .60 .00 .00 .00 .00 .00 .00 .00 .00 00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 f' ALL SPEEDS. 44 8 1 3 8 9 12 16 37 7 6 5 12 18 16 37 0 239 l (1) 18.41 3.35 (2) .52 .09 .42
.01 1.26
.04 3.35
.09 3.77
.11 5.02
.14 6.69 15.48 2.93 2.51 2.09 5.02 7.53 6.69 15.48 .00 100.00
.19 .44 .08 .07 .06 .14 .21 .19 .44 .00 2.81 (1)oPERCENT 09 ALL 000D OBSERVATIONS FOR '!HI.1 PAGE
[ (2)ePERCENT OF ALL OOOD OBSERVATICBIS FOR '!HIS PERIOD
. Co CAIM (WIND SPEED LESS THAN OR EQUAL M .95 MPH) l l
i TABLE 6D VERMONT YANKEE JAN 96 - DEC 96 NETEOROIAXIICAL DATA JOINT FRBQUENCY DIS 7RIBUTION 33.0 FT WIND DATA STABILITY CLASS D CLASS FRRQUENCY (PERCENT) = 40.82
) WIND DIRECTION FRON SPEED N 331E NE ENE E ESE SE SSE S SSW SW NEW WM NW NNW VRBL 70TAL NPH CAtm 1 0 2 0 1 0 0 1 0 1 0 2 0 1 1 2 0 12 (1) .03 .00 .06 .00 .03 .00 .00 .03 .00 .03 400 .06 .00 .03 .03 .06 .00 .35 (2) .01 .00 .02 .00 .01 .00 .00 .01 .00 .01 .00 .02 .00 .01 .01 .02 .00 .14 C 92 68 53 48 73 57 62 79 62 37 33 25 31 32 60 137 0 949 (1) 2.65 1.96 1.53 1.38 2,10 1.64 1,79 2.28 1.79 1.07 .95 .72 .89 .92 1.73 3.95 .00 27.33 (2) 1.08 .80 .62 .56 .86 . 67 ~ .73 .93 .73 .44 .39 .29 .36 .38 .71 1.61 .00 11.16 4-7 160 61 40 46 100 90 49 154 210 34 27 25 51 58 68 205 0 1378 (1) 4.61 1,76 1.15 1.32 2.88 2.59 1.41 4.44 6.05 98 .78 .72 1.47 1.67 1.96 5.90 .00 39.69 (2) 1.88 .72 .47 .54 1.18 1.06 .58 1.81 2.47 .40 .32 29 .60 .68 .80 2.41 .00 16.20 8-12: 171 42 17 8 14 11 2 20 135 14 19 17 el 139 112 111 0 893 (1) 4.93 1.21 .49 .23 .40 .32 .06 .58 3.89 .40 .55 .49 1.76 4.00 3.23 3.20 .00 25.72 (2) -2.01 .49 ,20 .09 .36 .13 .02 .24 1.59 .16 .22 .20 .72 1.63 1.32 1.31 .00 10.50 f 13 14 1 1 0 0 0 0 0 49 2 1 2 8 71 58 20 0 227 (1) .40 .03 .03' .00 .00 .00 .00 .00 1,41 .06 .03 .06 .23 2.04 1.67 .58 .00 6.54 (2) .16 .01 .01 .00 .00 .00 .00 .00 .58 .02 .01 .02 .09 ' .83 .68 .24 .00 2.67 5
19-24 0 0 0 0 0 0 0 0 2 0 0 0 0 4 6 0 0 12 (1) .00 .00 .00 .00 .00 .00 .00 .00 .06 .00 .00 .00 .00 .12 .17 .00 .00 .35 (2) .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .00 .00 .05 .07 .00 .00 .14
, OT 24 . 0^ 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 i (1) .00 .00 .00 .00 .60 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .03 (2) .00 .00 .00 ~. 0 0 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 l
ALL EPEEDs 438 172 113 102 188 158 113 254 458 88 80 71 151 306 305 475 0 3472
-(1) 12.62 4.95 3.25 2.94 5.41 4.55 3.25 7.32 13.19 2.53 2.30 2.04 4.35 8.81 8.78 13.68 .00 100.00 (2) 5.15 2.02 1.33 1.20 2.21 1.86 1.33 2.99 5.39 1.03 .94 .83 1.78 3.60 3.59 5.58 ,00 40.82 (1)sPERCENT OF ALL 000D OBSERVATIONS FOR 7HIS PAGE (21sPERCERPP OF ALL 000D OBSERVATTotiS FOR 7HIS PERIOD Cm Calm (WIND SPEED LESS *tHAN OR EQUAL 70 .95 MPH) r
- f. .
1 1 TABLE 6E VERNotrF YANKEE JAN 96 - DEC 96 NETEOROI4GICAL DATA JOINT FREQUENCY DISMIBUTION 35.0 FT WIND DATA STABILITY CLASS E CLASS FRBQUENCY (PERCENT) = 35.91 WIND DIRECTION FRON SPEED N. Saft NE ENE E ESE SE SSE. S SSW SW NPH WSW W tedW NW 3BBt VRSL 70TAL CALN 2 1 0 3 2 2 1 2 1 2 1 1 5 4 3 4 0 34 (1) .07 .03 .00 .10 .07 .07 .03 .07 .03 .07 .03 .03 .75 .13 .10 .13
'(2) .02 .01 .00 .03 1.11
.04 .02 .02 .01. .02 .01 .02 .01 .01 .06 .05 .04 .05 .00 .40 C-3 77 45 37 38 35 45 74 116 143 151 173 143 145 147 11) 148 166 0 1643 (2) 2.52
.91 1.47 .53 1.21
.44 1.24
.45 1.15
.41 1.47
.53 2.42 3.80 4.68 4.94 5.66 4.68 4.75 4.01 4.85 5.44 .00 55.11
.87 1.36 1.68 1.78 2.03. 1.68 1.70 1,73 1.74 1.95 .00 19.79 47 79 10 1 6 10 22 28 94 104 44 20 30 62 (1) 2.59 .33 .03 .20 82 138 234 0 964
.33 .72 .92 3.08 3.41 1.44 .65 .98 2.03 2.69 4.52 7.66 .00 31.57 (2) .93 , .12 .01 .07 .12 .26 .33 1.11 1.22 .52 .24 .35 .73 .96 1.62 2.75 .00 11.33 8-12 24 3 2 1 2 2 0 17 56 13 3 3 19 53 52 40 <0 290 (1) .79 .10 .07 .03 .07 .07 .00 .56 1.83 .43 . .10 .10 .62 1,74 1.70 1.31 (2) .28 .04 .02 .00 9.50
'. 01 .02 .02 .00 .20 .66 .15 .04 .04 .22 .62 .61 .47 .00 3.41 13-18 4 0. 0' 0 0 0 0 11 26 0 0 'O O 14' 17 2 0 74 (1) .13 .00 .00 .00 00 .00 .00 .36 .85 .00 .00 .00 .00 .46 .56- .07 (2) .05 .00 .00 .00
.00 2.42
.00 .00 .00 .33 .31 .00 .00 .00 .00 .16 .20 .02 .00 .87 19-24 0 0 0 0 0 0 0 1 3 0 0 0 0 5 0 (1) .00 0 0 9
.00 ,00 .00 .00 .00 . 00 .03 .10 .00 .00 .00 .00 .16 .00 .00 .00 .29 (2) .00 .00 .00 00 00 .00 .00 .01 .04 .00 .00 .00 .00 .06 .00 .00 .00 .11 OT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 ,00 .00 .00 (2) .00 .00 .00
.00 .00 00 .00 .00 .00 .00 .00 .00 . 00 - .00 ,00 .00 .00 .00 .00
-ALL SPEEDS - 186 59 40 48 49 71 ; 103 241 333 210 197 177 231 305 358 446 0 (1) 3054 6.09 1.93 1.31 1,57 1.60 2.32 3.37 7.89 10.90 6.88 6.45 5.80 7.56 9.99 11.72 14.60 .00 100.00 (2) 2.19 .69 47 .56 .58 .83 1.21 2.83 3.92 2.47 2.32 2.08 2.72 3.59 4.21 5.24 .00 35.91 (1)= PERCENT OF ALL OOOD OBSERVATIONS POR 7HIS PAGE (M oPERCElrF OF ALL OOOD OBSERVATIONS FOR W IS PERIOD
,J C= CAIM (WIND SPEED LESS WAN OR EQUAL 10 .95 MPH) k 1
i TABLE 6F VERMONT YANKEE JAN 96 + DEC 96 ME'IEOROLOGICAL DATA JOINT FREQUDK'Y DISTRIBUTION 35.0 FT WIND DATA ST UILITY CLASS F CLASS FREQUENCY (PERCENT) = 13.50 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE SSW SW WSW W MPH S WNW NW NNW VRBL WTAL CALM 0 1 0 0 0 0 0 0 1 1 0 1 2 2 0 1 0 9 (1) .00 .09 .00 .00 .00 .00 .00 .00 .09 .09 .00 .09 .17 .17 .00 .09 .00 .78 (2) .00 .01 .00 .00 .00 .00 .00 .00 .01 .01 .00 .01 .02 .02 .00 .01 .00 .11 C-3 30 25 16 8 14 12 16 24 48 105 252 173 118 94 64 51 0 1050 (1) 2.61 2.18 1.39 .70 1.22 1.05 1 39 2.09 4.18 9.15 21.95 15.07 10.28 8.19 5.57 4.44 .00 91.46 (2) .35 .29 .19 .09 .16 .14 .19 .28 .56 1.23 2.96 2.03 1.39 1.11 .75 .60 .00 12.35 4-7 0 0 2 0 1 2 1 4 2 4 16 8 3 18 16 9 0 86 (1) .00 .00 .17 .00 .09 .17 .09 .35 .17 .35 1.39 .70 .26 1.57 1.39 .78 .00 7.49 (2) .00 .00 .02 .00 .01 .02 .01 .05 .02 .05 .19 .09 .04 .21 .19 .11 .00 1.01 8-12 0 0 0 0 0 0 0 0 1 0 0 0 0 1 1 0 0 3 (1) .00 .00 .00 .00 00 .00 .00 .00 .09 .00 .00 00 .00 .09 .09 .00 .00 .26 (2) .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .01 .01 .00 .00 .04 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00-ALL SPEEDS 30 26 18 8 15 14 17 28 52 110 268 187 123 115 81 0 61 1148 (1) 2.61 2.26 1.57 .70 1.31 1.22 1.48 2.44 4.53 9.58 23.34 15.W5 10.71 10.02 7.06 5.31 .00 100.00 (2) .35 .31 .31 .09 .18 .16 .20 .33 .61 1.29 3.15 2.14 1.45 1.35 .95 .72 .00 13.50 (1)=PERCDff CF ALL 000D OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL M .95 MPH) I
l I i 1 1 i 1 1 I i i i i i 1 TABLE 6G i
) !
VERMONT YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOIKf FREQUENCY DIS'11t!B7 PION 35.0 FT WIND DATA STABILITY CLASS O CLASS FREQUENCY (PERCEtif) = 3.28 WIND DIRECTION FROM 1 SPEED N NNE NE DIE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL W TAL MPH CALM 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 (1) .00 .36 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .16 (2) .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 C-3 6 7 4 3 5 6 5 5 17 28 $8 29 23 22 16 13 0 247 (1) 2.15 2.51 1.43 1.08 1.79 2.15 1.79 1.79 6.09 10.04 20.79 10.39 8.24 7.89 5.73 4.66 .00 88.53 (2) .07 .08 .05 .04 .06 .07 .06 .06 .20 .33 .69 .34 .27 .26 .19 .15 .00 2.90 4-7 0 0 0 0 0 0 1 0 0 6 16 1 2 2 1 2 0 31 (1) .00 .00 .00 .00 .00 .00 36 00 .00 2.15 5.73 .36 .72 .72 .36 .72 .00 11.11 (2) .00 .00 .00 .00 .00 .00 .01 .00 .00 .07 .19 .01 .02 .02 .01 .02 .00 .36 i 8-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 ) 1 l 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
.00 l (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 i (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 j 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 l (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l i
ALL SPEEDS 6 8 4 3 5 6 6 5 17 34 74 30 25 24 17 15 0 279 (1) 2.15 2.87 1.43 1.08 1.79 2.15 2.15 1.79 6.09 12.19 26.52 10.75 8.96 8.60 6.09 S.35 .00 100.00 ] (2) .07 .09 .05 .04 .06 .07 .07 .06 .30 .40 .87 .35 .29 .28 .20 .18 .00 3.28 : (1)sPERCENT OF ALL OOOD OBSERVATIONS FOR 7HIS PAGE (2)sPERCENT OF ALL OOOD OBSERVATIONS FOR THIS PERIOD Co CALM (WIND SPEED LESS THAN OR EQUAL M .95 MPH) l i i TABLE 6H ; VERMONT YANKEE JAN 96 - DEC 96 METEOROLOGICAL DATA JOINT in.vvem i DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 I WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH I CAIJE 3 3 2 3 3 2 1 3 2 4 1 4 7 7 4 0 7 56 (1) .04 .04 .02 .04 .04 .02 .01 .04 .02 .05 .01 .05 .08 .08 .05 .08 .00 .66 (2) .04 .04 .02 .04 .04 .02 .01 .04 .02 .05 .01 .05 .08 .08 .05 .08 ,00 .66 C-3 212 150 114 102 131 126 164 227 272 323 516 370 318 295 290 369 0 3979
- (1) 2.49 1,76 1.34 1.20 1.54 1,48 1.93 2.67 3.20 3.80 6.07 4.35 3.74 3.47 3.41 4.34 .00 46.78 (2) 2.49 1,76 1.34 1.20 1.54 '.48 1.93 2.67 3.20 3.80 6.07 4.35 3.74 3.47 3.41 4.34 .00 46.78 1
4-7 286 75 45 56 121 135 104 283 344 91 79 67 125 169 249 510 0 2739 i (1) 3.36 .88 .53 .66 1.42 1,59 1.22 3,33 4.04 1.07 .93 .79 1.47 1.99 2.93 6.00 .00 32.20 (2) 3.36 .88 .53 .66 1.42 1.59 1.22 3.33 4.04 1.07 .93 .79 1.47 1.99 2.93 6.00 .00 32.20 8-12 241 47 19 9 16 14 4 52 210 31 28 21 88 210 182 196 0 1368 (1) 2.83 .55 .22 .11 .19 .16 .0F .61 2.47 .36 .33 .25 1.03 2.47 2.14 2.30 .00 16.08 (2) 2.83 .55 .22 .11 .19 .16 .01 .61 2.47 .36 .33 .25 1.03 2.47 2.14 2.30 .00 16.08 ; 13-18 22 1 1 0 0 0 0 12 80 3 2 4 9 96 80 30 0 340 (1) .26 .01 .01 .00 .00 .00 .00 .14 .9d .04 .02 .05 .11 1.13 .94 .35 .00 4.00 (2) .26 .01 .01 .00 .00 .00 .00 .14 .94 .04 .0~ .05 .11 1.13 .94 .35 .00 4.00 19-24 0 0 0 0 0 0 0 1 5 0 0 0 0 9 7 0 0 22 (1) .00 .00 .00 .00 .00 .00 .00 .01 .06 .00 .00 .00 .00 .11 08 .00 .00 .26 (2) .00 .00 .00 .00 .00 .00 .00 .01 .06 .00 .00 .00 .00 .11 .08 .00 .00 .26 07 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 ALL SPEEDS 764 276 '181 170 271 277 273 578 913 452 626 466 547 787 812 1112 0 8505 (1) 8.98 3.25 2.13 2.00 3.19 3.26 3.21 6.80 10.73 5.31 7.36 5.48 6.43 9.25 9.55 13.07 .00 100.00 (2) 8.98 3.25 2.13 2.00 3.19 3.26 3.21 6.80 10.73 5.31 7.36 5.48 6.43 9.25 9.55 13.07 .00 100.00 (1)oPERCENT OF ALL GOOD OBSERVATICNS FOR 'DtIS PACE (2)oPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Co CALM (WIND SPEED LESS THAN OR EQUAL 'Jo .95 MPH) APPENDIX A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Supplemental Information for 1996 ; l Facility: Vermont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporation 1A. TECHNICAL SPECIFICATION LIMITS - DOSE AND DOSE RATE Technical Specification and Category Limit
- a. Noble Gases l
3.8.E.1 Total body dose rate 500 mrem /yr i 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Gamma air dose 5 mrad in a quarter 3.8.F.1 Gamma air dose 10 mrad in a year 3.8.F.1 Beta air dose 10 mrad in a quarter 3.8.F.1 Beta air dose 20 mrad in a year l
- b. Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate l Form With Half-Lives Greater Than 8 Days 3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a year
- c. 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 3.8.B.1 Organ dose 5 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year auuo A-1
APPENDIX A (Continued) EFFl.UENT AND WASTE DISPOSAL ANNUAL REPORT 2A. TECHNICAL SPECIFICATION LIMITS - CONCENTRATION Technical Specification and Cateoory Limit
- a. Noble Gases No MPC Limits (No ECL Limits)
- b. Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days No MPC Limits (No ECL Limits)
- c. Liouids 3.8.A.1 Total fraction of MPC (ECL) f excluding noble gases (10CFR20, Appendix 8 Table II, Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 pCi/cc
- 3. AVERAGE ENERGY f Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.
- a. Average gamma energy: Not Applicable
- b. Average beta energy: Not Applicable
- 4. MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine 'radionuclide f composition.
- 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 airuo A-2
. - - - . _ - _ . - . . . . - . - . ~ -
APPENDIX A (Continued) 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present, These are j used to calculate the individual isotopic releases indicated in l Table 18 and the totals of Table 1A. The error involved in these { steps may'be approximately 123 percent. {
- b. lodines i 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 lodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately 118 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 118 percent. ' '
- d. Tritium Grab samples from the plant stack are taken monthly through a cold trap collection device and analyzed for tritium. The error involved in this sample is approximately il5 percent.
- e. 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-Lab analyzes for tritium, alpha, Fe 55, Sr-89, and Sr-90 on the composite sample. struo A-3
't APPENDIX A (Continued)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT The waste oil samples are liquid effluents that end up as a gaseous ground level release.
- f. Liauid Effluents s
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 released. For each batch, station records are retained of the total activity (mC1) released, concentration (pCi/ml) of gross 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 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.
- 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 f a. Liauid There were no nonroutine liquid releases during the reporting period.
mue A-4
APPENDIX A (Continued) EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT
- b. Gaseous There were no nonroutine gaseous releases during the reporting period.
I i i i f i atmo A-5
APPENDIX B L10010 HOLDUP TANKS Recuirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.0.1, 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. Response: The limits of Technical Specification 3.8.0.1 were not exceeded during this reporting period. Ctll%0 0*1 l
APPENDIX H (Continued) 0FF-SITE DOSE CALCULATION MANUAL It should also be noted that the recalculation of I-133 resulted in a slight difference in the last decimal place of the original dose factor listed in the ODCH. This is believed to be the result of a slight change in the last digit round off due to the use of an updated half-life value for this radionuclide. No significant differences in off-site doses would result from this change, but it should be reflected in plant procedures to ensure consistency with the ODCH. (4) Page vi, Appendix E: By letters, dated November 18, 1991 and July 10, 1992 Vermont Yankee submitted to the NRC a request or approval of proposed procedures for in place disposal of slightly contaminated radioactive soil under the Chem Lab floor which had resulted from a break in a chem sink drain line. The NRC responded to this request with their approval (letter NVY 96-48, dated March 7, 1996) documented in a Safety Evaluation. The NRC acceptance of our plans to dispose of the soil in-place required that their SE be incorporated into the ODCM as an Appendix. A new Appendix E containing the NRC SE has been added to the ODCM to complete this requirement (LAI No. 11308). (5) Pages 4-2, 4-2a, and 4-5: On April 9, 1996, it was identified that the Back Tracks- Farm in Vernon, Vermont (location TM-10 and TC-10) had gone out of business. It. has been added to the Radiological Environmental Monitoring Program (REMP) in the fall of 1995 as a result of the 1995 Land Use Census ranking it among the highest potential receptor locations that warranted inclusion in the monitoring program. As a consequence Table 4.1, Parts 3.a and 3.c as well as Figure 4-2, have been revised to remove this milk and silage sampling location from the REMP. No f new replacement stations need to be added to the program since the required number of highest dose-potential farms, g as listed in the 1995 Land Use Census are already part of l the REMP. (6) Page 5-17: Curre : plant calibration procedures use Xe-133 as the reference ladionuclide to determine counting ( muo 11 3
I l APPENDIX H (Continued) 0FF-SITE DOSE CALCULATION MANUAL efficiencies of the Stack Gas I and II, and A0G monitors. {' This is based on the combination of its expected presence j in the off-gas, and a relatively long half-life that makes it practical to detect before decay eliminates it. Xe-133 is a commonly used gas in the industry for monitor calibrations. During normal plant operations where off-gas is processed through the A0G. short-lived gases are decayed away before being seen by the monitors. leaving only long-lived Xe-133 and Kr-85. The use of Xe-133 instead of' Kr-85, or a mix of the two. is based on the fact that the expected response of the detectors is conservative for Xe-133 in comparison to Kr-85. If short-lived noble gases were present in significant amounts due to some off-normal condition, the use of Xe-133 as a reference gas for counting efficiency would still lead to a conservative monitor response relative to Xe-133 since short-lived gas mixes tend to have higher response factors (i.e., high energy noble gases will cause the monitor to respond as if a higher concentration of radioactivity were being f discharged than actually is). The new wording also clarifies that grab samples and lab analysis of gas releases can be used to determine the release rate of noble gases from the stack or A0G at any time. This ensures operational flexibility if monitor readings are suspected of over responding to actual release conditions. This is f considered an administrative change to simplify plant procedures. (7) Page 6-10: Figure 6-2 illustrates the basic operational layout of the Advanced Off-Gas (A0G) System. Based on the results of an A0G System review. Figure 6-2 has been corrected to indicate that the A0G bypass line that provides a discharge path around the moisture removal / dryer subsystem and charcoal adsorber subsystem feeds back into the main discharge line downstream of the A0G noble gas monitors (RAN-0G-3127 and RAN-0G 3128) and before the final 60% section of the original delay pipe. This had been f incorrectly shown that the bypass line returned gas flow upstream of these two monitors. This is considered an administrative change to reflect "as built" conditions. e m 6o H-4
i APPENDIX H 1 (Continued) !
.)
0FF-SITE DOSE CALCULATION MANUAL (8) Page 4-1: In 1995, the EPA announced that they would not
- . be able to supply a full range of environmental control samples in 1996 for use in laboratory intercomparison j studies program in which all nuclear power plants are required to participate. Vermont Technical Specification
- 3/4.9.E requires that the approved NRC Intercomparison Program used by the laboratory perfcrming environmental
- analyses be identified in the ODCM. Section 4.1 of the ODCM has been ' updated to indicate the various NIST traceable quality assurance programs in which the YAEL participates. A recent NRC Region I inspection of the YAEL p OA Programs concluded that the intercomparison studies in which the YAEL participates satisfy NRC requirements to meet the Technical Specification commitments.
(9) Pages 3-14 and 3-20: A clarification has been included in the definition of stack release quantities that provides for direct isotopic measurement (grab samples with laboratory analysis) of the radionuclide mixes in the gas stream being discharged from the stack, and the alternate method of inferring the radionuclide mixes at the stack by using SJAE measurements. These two approaches are part of current plant procedures, and provides operational < flexibility to estimate the continuous radionuclide release I rate from the plant stack. This is considered an administrative change to reflect existing practices. (10) Pages 5-13, 5-14, 5-15, and Appendix A: With the routing of the turbine hall exhaust air to the plant stack, and the replacement of the stack gas monitors (I and II) with new detectors, both effluent flow rate and monitor response j factors have changed slightly from values originally used i in example calculations used to illustrate the use of I various dose and dose rate applications. This revision updates these illustrations to provide plant staff with 9 examples that reflect information more relevant to the current plant configuration. These changes are considered administrative in nature in that no change is made in the methodology used to calculate doses, aing H-5
_ _ . . _ ~ . _ _ _ _ _ _ _ _ . _ . ~ . _ . _ . . . . _ _ _ _ . _ . . _ _ . _y.__ _ _._.__.m
-APPENDIX H (Continued) i 1
0FF-SITE DOSE CALCULATION MANUAL j The above changes will not reduce the accuracy or reliability of the dose calculations or setpoint determinations previously approved for use in the ODCM. This conclusion is based on the nature of the changes that: (a) adjust existing methodology for calculating direct dose by factoring changes in turbine i i efficiency to maintain the same level of N-16 impact as a l function of electric power as previously used. (b) include
- additional fixed radiation sources in estimating a better total
- site boundary dose. (c) use the existing dose methodology to expand the listing of radionuclides that can be considered in c31culating Method I dose impacts. (d) expand the description of oxs monitor calibrations to reference Xe-133 as the standard reference gas in keeping with common industry practices, (e) clarify existing plant procedures for direct measurement of effluent gas mixes in addition to estimates derived from SJAE ;
measurement, and (f) describe administrative changes that update system flow diagrams to existing plant configurations, add new documentation for the approval to dispose of slightly contaminated soil, replace REMP sampling locations due to sample , unavailability,' describe the currently approved intercomparison l } 0A Program at the YAEL, and show examples of the type of calculations that can be addressed by the ODCM methods. 4 I The revised pages from Revision 20 to the ODCM are attached. 1 i 1 i 1 i a i J 42uo H-6 , k
VERMONT YANKEE NUCLEAR POWER STATION 0FF-SITE DOSE CALCULATION MANUAL REVISION 20 2 9
. Reviewed: bCC,1/lM L MMH %fd4 9f2c,[96 PlantOperationsjevie@ Committee date Approved:
P4n
. ( fj a ce % d 7 tik Date Approved: /w #4 hv 7 J# 9( l Vice 'fresident. Dperations Date 4
e . .
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-iii-
. ___-_n
i I 3.7 Method to Calculate the Gamma Air W se 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 I 3.11 Method to Calculate Direct Dose from Plant Operation . . . 3-51 3.12 Cumulative Doses . . . . . . . . . . . . . . . . . . . . . 3-59 4.0 ENVIRONMENTAL MONITORING PROGRAM ........ ......... 4-1 5.0 SCTPOINT DETERMINATIONS . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 Liquid Effluent Instrumentation Setpoints . . . . . . . . . . 5-2 5.2 Gaseous Effluent Instrumentation Setpoints ......... " - 11 6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS. AND RADWASTE TREATMENT SYSTEMS .................... 6r1 6.1 In-Plant Radioactive Liquid Effluent Pathways . . . . . . . . 6-1 6.2 In-Plant Radioactive Gas.eous 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 l Yankee B-1 APPENDIX C: Response to NRC/EG&G Evaluation of ODCH Update l Through Revision 4 C-1 APPENDIX 0: Assessment of Surveillance Criteria for Gas l Releases from Waste Oil Incineration 0-1 APPENDIX E: NRC Safety Evaluation for Disposal of Slightly Contaminated Soil On-Site at VY (Below the Chem Lab Floor) - TAC No. M82152 E-1 Revision 20 Date 7/30/96 r
-vii-t f
1 7 umme summe umme uma e m'-- TABLE 1.1-1 (Continued) Summary of Radiolooical Effluent Technical Specifications and Implementing Ecuations Technical Specification Category Method (II Limit 3.9.A.1 Liquid Effluent Monitor Setpoint Liquid Radwaste Alarm Setpoint Eq. 5-1 T.S. 3.8.A.1 Discharge Monitor 1 3.9.B.1 Gaseous Effluent Monitor Setpoint Plant Stack and A0G Alarm / Trip Setpoint for Eq. 5-9 T.S. 3.8.E.la Offgas System Noble Gas Total Body Dose Rate (Total Body) Activity Monitors Alarm / Trip Setpoint for Eq. 5-10 T.S. 3.8.E.la Skin Dose Rate (Skin) SJAE Noble Gas Activity Alarm Setpoint Eq. 5-21 T.S. 3.8.K.1 Monitors (1) More ar. urate methods may be available (see subsequent chapters). (2) Technical Specification 3.8.M.2 requires this evaluation only if twice the limit of Equations 3-1 3-3. 3-21. 3-23. or 3-25 is reached. If this occurs a Method 11 calculation shall be made considering available information for pathways of exposure to real individuals from liquid gaseous, and direct radiation sources. Revision 20 Date 7/30/96 1-5
F TABLE 1.1-12 Dose and Dose Rate Factors Specific for Vermont Yankee for lodines. Tritium, and Particulate Releases Stack Release Ground Level Release
- Critical Organ Critical Organ Critical Organ Critical Organ Dose Factor Dose Rate Factor Oose Factor Dose Rate Factor mrem' mrem-sec '
Radio-nuclide 0FG,ico Ci 0FG,ico
, y r-pC i ,
0FG gic, *9*
, C1 OFG,4c, $
5 , , , yr - C1 , I H-3 3.13E-04 9.87E-03 1.06E-02 3.34E-01 C-14 1.90E-01 5.99E+00 6.43E+00 2.03E+02 Cr-51 6.11E-03 2.11E-01 4.16E-02 1 Hn-54 7.01E-01 2.77E+01 4.71E+00 1.43E+00
' 1.84E+02 Fe-55 3.17E-01 1.00E+01 2.05E+00 6.47E+01 l Fe-59 6.99E-01 2.32E+01 4.60E+00 1.52E+02 l Co-57 2.18E-01 8.23E+00 1.41E+00 5.33E+01 l Co-58 3.62E-01 1.30E+01 2.39E+00 8.52E+01 Co-60 7.63E+00 3.41E+02 4.99E+01 2.16E+03 l Zn-65 3.71E+00 1.20E+02 2.36E+01 7.63E+02 Se-75 2.41E+00 7.76E+01 1.53E+01 4.92E+02 l Sn-113 1.03E+00 3.25E+01 6.58E+00 2.08E+02 l Sr-89 1.14E+01 3.60E+02 7.27E+01 2.29E+03 Sr-90 4.31E+02 1.36E+04 2.82E+03 8.89E+04 Zr-95 6.91E-01 2.28E+01 4.51E+00 1.49E+02 Sb-124 1.26E+00 4.23E+01 8.35E+00 2.79E+02 Sb-125 1.25E+00 4.89E+01 8.01E+00 3.13E+02
( I-131 7.71E+01 2.43E+03 5.02E+02 1.58E+04 I-133 8.22E-01 2.59E+01 8.30E+00 2.62E+02 Cs-134 l 1.58E+01 5.27E+02 1.02E+02 3.37E+03 Cs-137 1.63E+01 5.55E+02 [ Ba-140 1.13E-01 3.66E+00 1.04E+02 2.18E+00 3.53E+03 6.94E+01 Ce-141 1.70E-01 5.42E+00 1.19E+00 3.78E+01 Ce-144 3.85E+00 1.22E+02 2.52E+01 7.98E+02 [ o The release point reference is the North Warehouse. These dose and dose rate factors are conservative for potential release applications associated with ground level effluents from other major facilities (i.e.. Turbine Building. Reactor Building. A0G. and CAB). , Revision 20 Date 7/30/96 e
ft tbs = 0.61 Ei d isT DFB, (3-5) r 8 f ' pCi-sec P pC i ' mrem-m 3
' mrem}
yr ) pCi-m 3 j ,s e c , , pCi -y r , I where: dji - In the case of noble gases, the release rate from the plant stack ( Ci/,sec) for each radionuclide. "i", identified. The release rate at the plant stack is based on measured radionuclide concentrations and distributions in periodic grab samples taken at the stack. As an alternative method, the radionuclide distribution in the off-gas at the Steam Jet Air I Ejector (SJAE) can be used during plant operations, along with the Stack Gas Monitor effluent count rate, to estimate stack radionuclide releases. The release rate at the stack when I using SJAE samples can be stated as follows: gsJAE i
~
sJAE (3-28) l uCi - (cpm) fuci/cc'(cc) sec cpm see j M - Plant Stack Gas Monitor I or II count rate (cpm). S, - Appropriate or conservative plant stack monitor detector counting efficiency for the given nuclide I mix (cpm /( Ci/cc)). F = Stack flow rate (cc/sec). 6fJAE
=
The last measured release rate at the steam jet air ejector of noble gas i (pCi/sec). [ OFB j - Total body gamma dose factor (see Table 1.1-10). [ Revision 20 Date 7/30/96 3-14
kskins " D1 O if 's
)
' mrem ' ' Ci ' ' mrem-sec '
yr , ,sec j , C i -y r , where: 6fT In the case of noble gases, the noble gas release rate from the plant stack (pCf/sec) for each radionuclide. "i". identified. The release rate at the plant stack is based on measured radionuclide concentrations and distributions in periodic grab samples taken at the stack. As an alternative method, the I radionuclide distribution in the off-gas at the Steam Jet Air I Ejector (SJAE) can be used during plant operations along with the Stack Gas Monitor effluent count rate, to estimate stack radionuclide releases. The release rate at the stack when using SJAE samples can be stated as follows: gsJAE bi ~ M gsJAE (3-28) t gCi ( Ci/cc) (cc) (cpm) sec cpm sec I H - Plant stack gas monitor I or Il count rate (cpm). I S o Appropriate or conservative plant stack monitor detector counting efficiency for the given nuclide mix (cpm /(pCi/cc)). I Stack flow rate (cc/sec). F - 6fJAE - The last measured release rate at the steam jet air ejector of noble gas i ( Ci/sec). I 0F'q, - combined skin dose factor (see Table 1.1-10) for stack release. Revision 20 Date 7/30/96 3-20
3.11 Method to Calculate Direct Oose From Plant Operation Technical Specification 3.8.M.1 restricts the dose to the whole body or any organ to any member of the public from all station sources (including direct radiation from fixed sources on-site) to 25 mrem in a calendar year (except the thyroid, which is limited to 75 mrem). 3.11.1 Turbine Building The maximum contribution of direct dose to the whole body or to any organ due to N-16 decay from the turbine is: t - Od "KN16( L) . E (3-27) I } (mrem) (MW,h ) I where: I Od - The dose contribution from N-16 decay at either the site boundary of maximum impact (west site boundary) or closest off-site residence - (mrem). E - Gross electric output over the period of interest (HW,h). KN16( L) The N-16 dose conversion factor for (L) equal to either: I (1) 5.17E-06 for the maximum west site boundary; or (2) 1.26E-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 j 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) end of the north warehouse are: l Revision 20 Date 7/30/96 3-51
f, c The fraction of a year that the intermodular gap is not shielded. 2.44E-2 - The activity to site boundary dose conversion factor for a one-inch wide intermodular gap mrem . ', yr-i n-C i j The site boundary dose from waste materials placed into storage on the Low Level Waste Storage Pad Facility is determined by combining the dose contribution due to direct radiation (line of sight) from Part (a) above with the skyshine scatter dose from Part (b). resin liner transfer dose from Part (c), and any intermodular gap dose from Part (d). 3.11.4 Iotal Direct Oose Summary i The dose contributions from the N-16 source in the Turbine Building, fixed sources in the north warehouse, and fixed sources on the Low Level Waste Storage Pad Facility, shall be combined to obta'" the estimate of total off-site dose to any member of the public from all fixed sources of radiation I located on-site. 3.11.5 .0ther Fixed Sources In addition to the fixed sources noted above (Turbine Building, North Warehouse, and LLW Storage Pad), other identified temporary or fixed sources that are created due to plant operations will be included in the total direct summary of 3.11.4 f f the projected annual dose contribution would add any notable addition to the reported total (i.e., 2. 0.1 mrem /yr). In 1995, turbine rotors and casings were replaced in the Turbine Hall I with the old rotors and casings placed in storage sheds located on site west of the switchyard along the railroad spur. Radiation surveys (December 1995) of low level contamination (principally Co-60) on the components led to a projected maximum west site boundary dose of 0.2 mrem /yr. This contribution will be added to the maximum Jite boundary total dose until the contribution is less than 0.1 mrem /yr, or the components are removed from storage location. I i i Pe ,s,on z. . ate ,,,g,g 3-58
i 4.0 ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring stations are listed in Table 4.1. The locations of the stations with respect to the Vermont Yankee plant are shown on the maps in Figures 4-1 to 4-6. 4.1 Intercomparison Program All routine radiological analyses for environmental samples are performed at the Yankee Atomic Environmental Laboratory (YAEL). The YAEL participates in several government and commercial intercomparison quality assurance programs (OAPs) that are traccable to the National Institute of Standards and Technology [NIST). These include: Nuclear Energy Institute (NEI)/NIST Measurement Assurance Program for the Nuclear Power Industry: U.S. Environmental Protection Agency's Intercomparison Program for Drinking Water: and Analytics, Inc. (commercial). YAEL also participates in the OAP for environmental media conducted by the Environmental Measurements Laboratory of the U.S. Department of Energy. 4.2 Airborne Pathway Monitoring lB The environmental sampling program is designed to achieve several major objectives, including sampling air in predominant up-valley and down-valley wind directions, and sampling air in nearby communities and at a proper control location, while maintaining continuity with two years of preoperational data and 18 years of operational data (as of 1990). The chosen air sampling locations are discussed below. To assure that an unnecessarily frequent relacation of samplers will not be required due to short-term or annual fluctuations in meteorology, thus incurring needless expense and destroying the continuity of the program, long term, site specific ground level 0/0s (five-year averages - 1978 through 1982) were evaluated in comparison to the existing air monitoring locations to determine their adequacy in metting the above-stated objectives of the program and the intent of the NRC general guidance. The long-term average meteorological data base precludes the need for an annual re-evaluation of air sampling locations based on a single year's meteorological history. The Connecticut River Valley in the vicinity of the Vermont Yankee plant has a pronounced up- and down-valley wind flow. Based on five years of meteorological data, wind blows into the 3 "up-valley" sectors (N. NNW. and NW) 27 percent of the time, and the 4 "down-valley" sectors (S. SSE. SE, and ESE) 40 percent of the time, for a total "in-valley" time of 67 percent. Revision 20 Date 7/30/96 41
~ Station AP/CF-12 (NNW. 3.6 km) in North Hinsdale, New Hampshire, monitors the up-valley sectors. It is located in the sector that ranks fourth overall in terms of wind frequency (i.e., in terms of how often the wind blows into that sector), and is approximately 0.5 miles from the location of the calculated maximum ground level 0/0 (i.e.. for any location in any sector, for the entire Vermont Yankee environs). This station provides a second function by its location in that it also monitors North Hinsdale, New Hampshire, the community ! with the second highest ground level 0/0 fer surrounding communities, and it has been in operation since the preoperational period. The down-valley direction is monitored by two stations - at River Station Number 3.3 (AP/CF-11. SSE 1.9 km) and at Northfield. Massachusetts (AP/CF-14, SSE. 11.3 km).' They both reside in the sector with the maximum wind frequency and they bound the down-valley point of calculated maximum ground level 0/0 (the second highest overall ground level 0/0 for any location in any sector). Station AP/CF-11 is approximately one mile from this point, between it and the plant. Station AP/CF-14 also serves as a community monitor for Northfield, Massachusetts. Both stations have been in operation since the {' preoperational period. In addition to the up- and down-valley locations, two communities have been chosen for community sampling' locations. The four nearest population i groups with the highest long-term average 0/0 values, in decreasing order, are Northfield, Massachusetts, North Hinsdale, New Hampshire. Brattleboro, Vermont, and Hinsdale. New Hampshire. The community sampler for Northfield is at Station AP/CF-14 (mentioned above). North Hinsdale is already monitored by the up-valley station (AP/CF 12, NNW. 3.6 km), which also indirectly monitors the city of Br; tieboro, located further out in the same sector. The second i sampler specifically designated for a community is at Hinsdale Substation (AP/CF-13. E, 3.1 km) in Hinsdale. The control air sampler was located at Spofford Lake (AP/CF-21, NNE,16.1 km) due to its distance from the plant and the low frequency for wind blowing in that direction based on the long-term (five-year) meteorological history. Sectors in the general west to southwest direction. which would otherwise have been preferable due to lower wind frequencies, were not chosen since they approached the region surrounding the Yankee Atomic plant in Rowe, Massachusetts, An additional air sampler is maintained at the Tyler Hill site ( AP/CF-15. WNW, 3.4 km) . which is along the western side of the valley in general proximity of historical dairy operations. (The sixth location is not a specific Technical Specification requirement.) Revision 20 Date 7/30/96 4-la.
I Table 4.1 Radiolooical Environmental Monitorino Stations (u Exposure Pathway Sample Location Distance and/or Samole and Desionated Code (2) (km)(5) Direction (5)
- 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 RoadH) 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 Downriver 0.8 SSE From SE-12 North Storm 0.15 E Shoreline Drain Outfall(3)
- 3. INGESTION
- a. Mil k(8) TM-11 Miller Farm 0.8 WNW l TM-14 Brown Farm 2.1 S
( TM 16 Meadow Crest Farm Blodgett Farm") 4.4 WNW/NW TM-18 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.") 3.2 WNW TG-21 Spofford Lake 16.1 NNE i
Revision 20 Date 7/30/96 4-2
(~ I Table 4.1 (Continued) Radiological Environmental Monitoring StationsU) Exposure Pathway Sample Location Distance and/or Sample and Designated Code (2) (km)(5) Direction (S)
- c. Silage TC-11 Miller Farm 0.8 WNW l TC-14 Brown Farm 2.1 S TC-16 Meadow Crest Farm 4.4 WNW/NW TC-18 Blodgett FarmH) 3.4 SE TC-24. County Farm 22.5 N
- d. Fish FH-11 Vernon Pond (6) (6)
I 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 OR-3 Hinsdale Substation 3.0 E OR-4 Northfield, MA 11.0 SSE DR-5 Spofford Lake 16.3 I DR-6 Vernon School 0.46 NNE WSW OR-7 0.27 Site Boundary") W l OR-8 Site Boundary 0.25 SW l DR-9 Inner Ring 2.1 N OR 10 Outer Ring 4.6 N OR-11 Inner Ring 2.0 NNE OR-12 Outer Ring 3.6 NNE OR-13 Inner Ring 1.4 NE OR-14 Outer Ring 4.3 NE OR-15 Inner Ring 1.4 ENE OR-16 Outer Ring 2.9 ENE OR-17 Inner Ring 1.2 E OR-18 Outer Ring 3.0 I OP-19 Inner Ring 3.5 E
ESE OR-20 Outer Ring 5.3 ESE OR-21 Inner Ring 1.8 SE OR-22 Outer Ring 3.2 SE OR-23 Inner Ring 1.8 SSE OR-24 Outer Ring 3.9 SSE OR-25 Inner Ring 2.0 S Revision 20 Date 7/30/96 e 4-2a
{ [; q N t
)
,. . , c-
"/ci 12 8
p/ HINSDALE, N.H. - g l g Thal 6 TC 16
%j
/
c___ -_I 4s i TG 15 8
@f f A M/CF-15 8
- tc-13 1
g d v/CF 13 L i I
' t g'
PLANT & szt escaccen IN tic;r71
/ '-1 l
8 vtRNON 041 e rc* ' A n /cF-is t VERNON' V.7* 1M*1 Tc tt {- t'C 12 g,g g TM 18 4 TC 16 o 1 2 3 L1LY PGQ KILOffTEP.S s rigure 4-2 Environmental Sa:Pling i.ocations uichin 5 k= of Planc Revision 2_0 Date 7/30/96 4-5
I 0" g DF'i s
, (5-12) ee I 0 5 g
DF'4 s - Combined skin dose factor (see Table 1.1-10) (mrem-sec/ Ci-yr) 5.2.1.2 Plant Stack Noble Gas Activity Monitor Setoofnt Example The following setpoint example for the plant stack noble gas activity monitors demonstrates the.use of Equations 5-9 and 5-10 for determining setpoints. The plant stack noble gas activity monitors, referred'to as " Stack Gas I" (RM-17-156) and " Stack Gas II" (RM-17-157), consist of beta sensitive scintillation detectors, electronics, a ratemeter readout, and a digital scaler which counts the detector output pulses. A strip chart recorder providas a permanent recard of the ratemeter output. The monitors have typical calibration facters. S . gof about 3E+07 cpm per Ci/cc of noble gas. The nominal plant stack flow is 7.32E+07 cc/sec ((155.000 cfm x 28,300 cc/f t 3)/60 sec/ min). When monitor responses indicate that activity levels are below the LLDs at the stack (or A0G) monitors, the relative contribution of each noble gas radionuclide can conservatively be approximated by analysis of a sample of off-gas obtained during plant operations at the steam jet air ejector (SJAE). This setpoint example is based on the following data (see Table 1.1-10 for DFB, and DF'g ): QsJAE OF8 1 D F's , i 3 ( pCi ) ( mrem-m ) ( mrem-sec ) sec pCi -yr uC i -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 Revision 20 Date 7/30/96 5-13
I [ EQfJAEDFBi i 0FB c E0lJAE 1 {OfJAEDFBy - (1.03E+04)(8.83E-03) + (4.73E-02)(5.92E-03)
+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)
+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04)
- 9.83'E+01 ( Ci-mrem-m 3
/sec-pCi yr)
{ 6,sJAE - 1.03E+04 + 4.73E+02 + 2.57E+02
+ 1.20E+02 + 3.70E+02 + 1.97E+01
- 1.15E+04 Ci/sec 0FB c -
1.15 E +04
- 8.52E-03 (mrem-m3 /pCi-yr)
R, -8185 9 7 0FB e
- (818) (3E+07)
( 7. 32 E +07 ) ( 8. 52 E-03 )
- 39.348 cpm Next:
EQfJAE0F's s i DF'c EDf # 1 Revision 20 Date 7/30/96 5-14
[ E 6f*DF'i, - (1.03E+04)(1.06E-02) + (4.73E-02)(1.43E-02) i
+ (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 ( Ci-mrem-sec/sec-pCi-yr)
- 1.14 E +02 D F'C 1.15 E +04
- 9.91E-03 (mrem-sec/ Ci-yr) spt 1
R - 3,000 5 _1. 1 skin 9F O F'c / s
- (3,000) (3E+07) 1 1
( 7. 32 E +07 ) ( 9. 91 E -03 )
- 124,067 cpm D
The setpoint, R,pt, is the lesser of R,*pe a n d R,'p tkI" . For the noble D gas mixture in this example R,*pe is less than R,'ptki" , indicating that the total body dose rate is more restrictive. Therefore, in this example the
" Stack Gas I" and " Stack Gas II" noble gas activity monitors should each be set at 39,348 cpm above background or at some conservative value below this l (such as that which might be based on controlling release rates from the plant in order to maintain off-site air concentrations below 20 x ECL when averaged over an hour), or to account for other minor releases from the waste oil burner, For example, if an administrative limit of 70 percent of the ,
Technical Specification whole body dose limit 500 rem /yr (39,348 cpm) is [ chosen, then the noble gas monitor alarms should be set at no more than 27,543 cpm above background (0.7 x 39,348 - 27,543). l 5.2.1.3 Basis for the Plant Stack and A0G System Noble Gas Activity Monitor Setpoints , The setpoints of the plant stack and A0G system noble gas activity 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. The Revision 20 Date 7/30/96 5-15
i 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 the 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. Cs - 05 (5-14) ( pCi ) ( Ci) (sec) cm 3 sec cm 3 where: .
- 0, =
The release rate of noble gas "i" in the mixture for each noble gas identified ( Ci/sec).
, F =
Appropriate flow rate (cm 3/sec) Substituting the right half of Equation 5-14 into Equation 5-13 for Cg yields: R - S 01 9i (5-15) (cpm) cpm-cm 3 ' Ci ' sec l pCi sec, 3 s , cm , i The detector calibration procedure establishes a counting efficiency for a reference radionuclide. Xe-133 (half life 5.24 days). For routine conditions where offgas is processed through the A0G, all short lived gases are decayed away before discharge leaving only long lived radionuclides as the significant contributors to the monitor response. In this case. Xe-133 as the reference radionuclide for the detector counting efficiency is representative of the expected release conditions. For off normal conditions that might lead I to inclusion of short lived radioactivity in the gas stream being released. Xe-133 as the reference radionuclide is expected to lead to a conservative response factor for the detectors since the short lived noble gases tend to have higher energies that can cause them to over respond. Therefore, in Equation 5-15. one may substitute Sg for S where 59 represents the detector 91 counting efficiency determined from the Xe-133 calibration. If necessary, the actual concentration and discharge rate of individual gases being released ' Revision 20 Date 7/30/96 5-17 '
from the stack (or A0G) can be determined by direct grab sample and laboratory analysis during specific periods of interest. (5-16) l R- S, Qi 3 (cpm) { cpm-cm ) ( sec ) (gCi) pCi cm 3 sec I The total body dose dte due to noble gases is determined with Equation 3-5: 1 Atbs - 0.61 E 0i 1 OF81 (3-5) lB (mrem) ( pCi-sec ) yr (pCi) (mrem-m3 pCi-yr ) Ci-m3 sec Where: k tbs - total body dose rate (mrem /yr) due to noble gases from stack release O.61 - (1.0E+06) x (6.11E-07) (pCi-sec/pCi-m3) 1E + 06 - number of pCi per pCi (pCi/pC1) 6.11E - 07 - [X/0F, maximum long term average gamma atmospheric dispersion factor (sec/m3) Os - the release rate of noble gas "i" in the mixture for each noble gas identified ( Ci/sec) (Equivalent to 0,si for noble gases released at the plant stack.) DFB, - total body dose factor (see Table 1.1-10) 3 (mrem-m /pCi yr) Revision 20 Date 7/30/96 5-18
A composite total body gamma dose factor, OFBc , may be defined such that: OFB c Di - E , og 0FB I (5-17) e mrem-<n 3
' Ci ' 'pC i ' mrem-m 3
, pc i -y r , ,sec, sec, pCi-yr ,
Solving Equation 5-23 for DFBc yields: E og 0FB, 1 OFB c 1 (5-11) eof t Technical Specification 3.8.E.1.a limits the dose rate to the total body 1 from noble gases at any location at or beyond the site boundary to 500 mrem /yr. By setting A tb equal to 500 mrem /yr and substituting 0FB for DFB, c in Equation 3-5, one may solve for E 0, at the limiting whole body noble gas dose rate: i E 6, - 818 1 (5-18)
$ OFB c 3
( Ci ) ( mrem-gCi-m ) ( pCi-yr ) I sec yr-pCi -s ec mrem-m 3 i Substituting this result for E , in Equation 5-16 yields R[ptb , the i response of the monitor at the limiting noble gas total body dose rate: R[,De- 818 5 9 0FB c 3 (cpm) ( mrem-pCid ) ( cpm-cm ) (sec y ( pCi-yr ) y r-pCi -s ec pCi cm 3 mrem-m 3 Revision 20 Date 7/30/96 5 ,
The skin dose rate due to noble gases is determined with Equation 3-7:
$,'ff" - [ g D F't , (3-7)
(mrem) g Ci) g mrem-sec) yr sec pCi-y r Where: A,5fl" - Skin dose rate (mrem /yr) 0, - The release rate of noble gas "i" in the mixture for each noble gas identified ( Ci/sec) equivalent to 0,5 for noble gases released at the plant stack). O F'j , - Combined skin dose factor (see Table 1.1-10) (mrem sec/pCi-yr). A composita combined skin dose factor, DF'c, may be defined such that: I 0F[ Ei os -E 1 0, DF', (5-19)
' mrem-s ec ' ' Ci ' 'uCi ' ' mrem-sec '
Ci -y r , sec, sec j pCi-y r j i Solving Equation 5-19 for DF' yields: l E D 0F i , 1 l OF' = i l EDi i Revision 20 Date 7/30/96 5-20
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 N5d" equal to 3,000 mrem /yr and substituting DF for DF, in Equation 3-7 one may solve for [ Og at the limiting skin noble gas dose rate: 1 I E0-i 3.000 D F,c ( Ci ) g mrem) g pCi-yr y sec yr mrem-sec Substituting this result for { 0, in Equation 5-16 yields R,*p'tI". the i response of the monitor at the limiting noble gas skin dose rate: Rs 'p"t - 3,000 Sg 1 1 (5-10) 7 D F'c 3 (cpm) (mrem) g cpm-cm ) g sec)g Ci-yr ) yr C1 cm 3 mrem-s ec I I I I Revision 20 Date 7/30/96 S-21
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EXAMPLE CALCULATION N0. 2 Type Total Body Dose Rate from Noble Gases References a) 00CH Section 3.4 (Method I). b) Technical Specification 3.8.E.1.a. Problem Calculate the off-site total body dose rate resulting from the release of noble gases from the plant stack during power operations. Plant Data I a) Maximum plant stack gas monitor (I or II) Count rate during period of interest (H): 80.000 cpm b) Stack flow rate during release (F): I (155.000 cfm x 4.72E+02 cc/sec _ ) 7.32E+07 cc/sec cfm c) Plant stack monitor detector counting 3E+07 cpm per l efficiency (Sg): gCi/cc I ' d) The last measured release rate mix of Q,sJAE noble gas from the SJAE and corresponding I dose factor OFB, from Table 1.1-10. 9 6 sJAE OFB, (uCi/sec) (mrem-m /DCi-yr) 3 Xe-138 5.15E+03 8.83E-03 Kr-87 2.37E+02 5.92E-03 Kr-88 1.29E+02 1.47E-02 Xe-135 1.85E+02 1.81C 03 Revision 20 Date 7/30/96 - A-3
EXAMPLE CALCULATION NO. 2 (Continued) ft 1 0.sJAE /5.70E+03 Relattve Fraction of Total Xe-138 5.15E+03/5.70E+03 - 0.904 Kr-87 2.37E+02/5.70E+03 - 0.042 Kr-88 1.29E+02/5.70E+03 - 0.023 Xe-135 1.85E+02/5.70E+03 - 0.032 Next, the stack release rate of each noble gas i from Equation (3-28) can be substituted into Equation (3-5) to give the dose rate as: Atbs - 0.61 M F fi 0FB,
- 0.61 80,000 1/ 3 E +07 7 . 32 E +07 E f, OFB i 1 1 s
- 1.19E+05 [(0.904)(8.83E-03) + (0.042)(5.92E-03) +
(0.023)(1.47E-02) + (0.032)(1.81E-03)] = l Answer A tbs - 1.027 mrem / year noble gas total body dose rate." l I
- Note: This exceeds the li: nits of Technical Specification 3.8.E.1.a I (500 mrem /yr).
1 [ Revision 20 Date 7/30/96 L A-5
EXAMPLE CALCULATION NO. 3 Type , Total Body Dose Rate From Noble Gases References a) ODCM Section 3.4 (Method I). b) Technical Specification 3.8.E.1.a. Problem Calculate the off-site total body dose rate resulting from the release of noble gases from the plant stack recorded to have occurred 32 days after plant shutdown. Plant Data I a) Maximum plant stack gas monitor (I or II) Count rate during period of interest (M): 80.000 cpm b) Stack flow rate during release (F): 7.32E+07 cc/sec (155,000 cfm x 4.72E+02 cc/sec , ) cfm c) Plant stack monitor detector counting 3E+07 cpm per efficiency (Sg): l Ci/cc d) The noble gas mix fractions f,(t) corresponding to 32 days taken from Table 5.2 1. i l, (32 day)* OFB,** Kr-85 0.152 1.61E-05 Xe-131m 0.070 9.15E-05 Xe-133 0.777 2.94E-04 Fraction of nuclide in mix as function of time (see Table 5.2-1). ~ Dose factors from Table 1.1-10. [ [ Revision 20 Date 7/30/96 s A-6
EXAMDLE CALCULATION NO. 3 (Continued) Calculation The dose rate is calculated from Equations (3-5) and (3-28): Atbs - 0.61 Et 6fT DFB, 3 (mrem) ( pCi-sec ) ( pCi ) ( mrem-m yr Ci-m3 sec pCi-yr ) and where the stack release rate is determined from: 0,si - Df M 1 (3-28) F sJAE N E Ds 1 ( Ci ) (cpm) ( uCi/cc ) ( cc ) sec cpm sec However, for a time (t) after shutdown, the ratio of of " to the sum release rate of all noble gases can be replaced in Equation (3-28) by the relative fraction [fg(t)] of each noble gas available in the system; therefore, Equation (3-28) can be written: oft - fg(t) 1 M . _ . F Sg Therefore, using the above data for a time period 32 days after shutdown, the dose rate equation can also be written as: Atbs - 0.61 MSg1 F E fg(t) 3 0FB,
- 0.61 80,000 1/3 E +07 7.32E+07 [(0.152)(1.61E-05) + l
[ (0.070)(9.15E-05) + (0.777)(2.94E-04)] - Answer A tes - 28.3 mrem / year noble gas total body dose rates at 32 days after I shutdown. Revision 20 Date 7/30/96 A-7
EXAf4PLE CALCULATION NO. 4 Type Skin Dose Rate From Noble Gases References a) ODCM Section 3.5 (Method I). b) Technical Specification 3.8.E.1.a. Problem ' Calculate the off-site skin dose rate resulting from the release of noble gases from the plant stack during power operations. Plant Data a) Maximum plant stack gas monitor (I or II) I Count rate during period of interest (M): 80,000 cpm b) Stack flow rate during release (F): .7.32E+07 cc/sec I (155.000 cfm x 4.72f +02 cc/sec , ) cfm c) Plant stack monitor detector counting 3E+07 cpm per efficiency (Sg): l Ci/cc d) The last measured release rate mix of noble gas from the SJAE (0fJAE), andcorrespondingdosefactorDF[ from Table 1.1-10. 0,saAE g g, 4 (mrem-sec/uCi-yr) (uCi/sec) Xe-138 5.15E+03- 1.06E-02 Kr-87 2.37E+02 1.43E-02 ," Kr-88 1.29E+02 1.28E-02 Xe-135 1.85E+02 3.24E-03 Revision 20 Date 7/30/96 A-8
EXAMPLE CALCULATION NO. 4 (Continued) N9xt, the stack release rate of each noble gas i from Equation (3-28) can be substituted into Equation (3-5) to give the skin dose rate as: Ashins - H F ft O F'i ,
- 80,000 1/3E+07 7.32E+07 [(0.904)(1.06E-02) + l (0.042)(1.43E-02) + (0.023)(1.28E-02) + (0.032)(3.24E-03)] -
- 1.95E+05 (9.58E-03 + 6.01E-04 + 2.94E-04 + 1.04E-04)
- 1.95E+05 (1.06E-02)
Answer As uns - 2,065 mrem / year noble gas skin dose rate.* l
- Note: This does not exceed the limit of Technical Specification 3.8.E.1.a (3,000 mrem / year).
= I I I I I E Revision 20 Date 7/30/96 L A-10
f J EXAMPLE CALCULATION NO. 5 Type Skin Oose Rate from Noble Gases References [ a) 00CM Section 3.5 (Method I). b) Technical Specification 3.8.E.1.a. Problem Calculate the off-site skin dose rate resulting from the release of noble [- gases from the plant stack six days after plant shutdown. Plant Data a) Maximum plant stack gas monitor-(I or II) Count rate during period of interest (M): 120.000 cpm b) Stack flow rate during release (F): 7.32E+07 cc/sec (155,000 cfm x A.72E+0? cc/sec , [- cfm
)
c) Plant stack monitor detector counting 3E+07 cpm per l efficiency (Sg): pCi/cc [ d) _ Since the plant is shut down for more than five days Xe-133 may be used as the referenced radionuclide in place of the ratio of OfJAE t0'the sum of all ' OfJAE in Equation (3-28). [ - 0 F'j , i fi (t >5 days) mrem-sec { pCi-yr Xe-133 1. 5.58E-04 [ [ [ Revision 20 Date 7/30/96 A-11
l l EXAMPLE CALCULATION NO. 5 (Continued) Calculation The skin dose rate is calculated from Equations (3-7) and (3-28): Astins " E 0 si 1 D F'i s (3-7) t g mrem) ( pCi ) ( mrem-sec ) l yr sec Ci -y r I and, the stack release rate is determined from: I 6fT , gt sJAE M 169 F (3-28) gsJAE I - However, for times greater than five days.after shutdown, Xe-133 may be used I as the referenced radionuclide alone. Therefore, in Equation (3-28) the ratio of ofJAE to the sum of all f# can be replaced by a value of 1 which indicates that all the cr%tiibution to the release is from Xe-133. Therefore: I of,T 333 - 1.0 x 120,000 x 1/3E+07 x 7.32E+07 l l f uci/ce' (cpm) (cc/sec) r C9* s of,T_333 = 292,800 pCi/sec ! Therefore,replacingthisvalueof6fT into Equation (3-7) we find the skin _ dose rate as: k skins - 292,800 x 5.58E-04 l f mrem' 'pC i ' ' mrem-sec' yr , sec j , Ci-yr , Revision 20 Date 7/30/96 I L A-12 m
1 l l EXAMPLE CALCULATION NO.'5 l i (Continued) l Answer j A, gin, - 163 mrem / year. l 4 4 s l l l l 1 i Revision 20 Date 7/30/96 e A-13
I l EXAMPLE PROBLEM NO. 6 Type Critical Organ Dose Rate From lodine. Tritium, and Particulates References a) ODCM Section 3.6 (Method I). b) Technical Specification 3.8.E.1.b. Problem Calculate the critical organ dose rate due to measured effluent data taken from the plant stack for a seven-day sample collection period. Plant Data a) Stack particulate analysis for the seven-day period of interest. D FG', ,,,( D j Activi ty 0 STP 1 (pCi/sec) ( mrem-sec ) yr-gCi l Sr-89* 1.42E-04* 3.60E+02 Sr-90* 3.50E-03* 1.36E+04 Co-60 4.89E-02 3.41E+02 Cs-137 3.90E-03 5.55E+02 Zn-65 1.01E-02 1.20E+02 Na-24** 2.76E-03** -- Mn-54+ <2.87E 06+ 2.77E+01 Notes (U DFG',5c, dose rate factor for each radionuclide is taken from Table 1.1-12. For Sr-89/90. use the most recent available measurement from quarters composite analysis. Na-24 has a half life of less than 8-1/2 days. and therefore is not included in the dose analysi per requirements of Technical Specification 3.8.E.1.b even though it was detected. Revision 20 Date 7/30/96 l L A-14
~ ~
EXAMPLE PROBLEM NO. 6 (Continued)
+
Ha-54 is not included in the dose analysis since it was not detected as being present after counting to at least the LLD. b) Stack iodine (charcoal and particulate activities combined for the seven-day period of interest): 3" D FG, m j Activity 0 ( mrem-sec ) ( Cf/sec) yr- Ci l 1-131 1.16E-03 2.43E+03 I-133* <6.35E-05* 2.59E+01 1-135'* 7 . 21 E - 03" -- and H-3+ 3.17E-02 9.87E-03 Notes I-133 is not included in the dose analysis for this case since it was not detected is being present in the stack analysis. I-135 is not included in the dose analysis because it has a half life - less than 8-1/2 for particulates, and is not included as a required iodine in Technical Specification 3.8.E.1.b. Tritium value based as latest available stack grab sample. Calculation The dose rate is calculated from Equation (3-16): Acos " E Of DFG'st co (3-16) t g mrem) { pCi ) g mrem-sec ) yr sec pCi-yr The dose rate factors (DFG',,c, ) for each of the radionuclides detected in the plant stack ~ charcoal and particulate filter sample (plus tritium) is taken from Table 1.1-12 of the ODCM. Revision 20 Date 7/30/96 y A 15
EXAMPLE PROBLEM NO. 9 (Continued) Na-24 has a half life of less than 8-1/2 days, and therefore is not included in accordance with Technical Specification 3.8.G.I.
+
Mn-54 is not included in the dose analysis since it was not detected as being present after counting to at least the LLD. b) Total iodine release for the month based on the combined charcoal and particulate filter samples taken during the month: sTP O sico j ,. gI ( mrem) (Ci) Ci I-131 4.30E-03 7.71E+01 1-133* 1.12E-04* 8.22E-01 l l I-135** 2 . 01 E - 0 2 ** i and H-3+ 0.15 3.13E-04 i i Calculation The dose is calculated from Equation (3-25): sTP l~ De ,, - E Oi DFG 3ic, (3-25) 1 (mrem) (C1) (mrem /C1) l Notes for Plant Data b) Above i In this case, I-133 was found in one of the weekly stack samples to be present, and therefore based on that value is included in the dose analysis. I-135 is not incit. dad in the dose anclysis because it has a half life less than 8-1/2 days for particulates and is not included as a required iodine in Technical Specification 3.8.B.1. Tritium value based on the monthly stack grab sample. Revision 20 Date 7/30/96 A-22
EXAMPLE PROBLEM NO. 9 (Continued) The dose factor (OFG,4c ) for each radionuclide detected in the plant stack charcoal and particulate filter sample (plus tritium) is taken from Table 1.1-12 of the OOCH. Therefore: Oco, - (5.42E-04)(1.14E+01) + (1.10E-02)(4.31E+02) + (2.30E-01)(7.63E+00) + (1.15E-02)(1.63E+01) + (2.60E-02)(3.71E+00) + (4.30E-03)(7.71E+01) + (1.12E-04)(8.22E-01) + (0.15)(3.13E-04) - l Answer - Oco, = 7.12 mrem maximum organ dose for the month. \ Revision 20 Date 7/30/96 f A-23
{ [ [ l { - [ APPENJIX E NRC Safety Evaluation for Disposal of Slightly Cont:minated Soil On-Site at VY (Be. low the Cher.1 Lab Floor) TAC No. M82152. [ { E-1 Revision 20 Date 7/30/96 L I E
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.7 UNITED STATES
[ Y 't E NUCLEAR REGULATORY COMMISSION "g .;
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***** ,o March 7,1996 INY 96-48 I
Hr. Donald A. Reid Vice President, Operations i Vermont Yankee Nuclear Power Corporation Ferry Road Brattleborof VI "05301' "- '* "
* ~
SUBJECT:
PROPOSED DISPOSAL OF SLIGHTLY CONTAMINATED SOIL ONSITE AT THE VERHONT YANKEE P0ifER STATION (TAC NO. H82152)
Dear Mr. Reid:
By letters dated November 18, 1991, and July 10, 1992, the Vermont Yankee I Nuclear Power Corporation (VYNPC) submitted a request pursuant to 10 CFR Part 20, Subpart K, Section 2002, for approval of proposed procedures Yankee Nuclear Power Station.for disposing of slightly contaminated radioactive soil o I The staff has completed its review of the r: quest are and finds that VYtjPC's procedures, including documented comitments, acceptable. The enclosed Safety Evaluation willi be incorporated into the licensee's Offsite Oose Calculation Manual (ODCH) as an appendix. Pursuant to the provisions of 10 CFR Part 51, the Comission has published in I Impact (61 FR 8984).th: federal Reoister an Environmental Assessment and Finding Dorman at (301) 415-1429.If you have any questifons regarding this matter, please con l Sincerely, i 1 gvenA. 0(ctor a, O Division of Reactor rojectc - I/II Office of Nuclear Reactor D.egulation 0:cket No. 50-271
Enclosure:
Safety Evaluation et w/ encl: See next page - r L - Revision ,2_0_ Date 7/30/96 _ E-2
- 0. Reid Vermont Yankee Nuclear Power Station Vermont Yankee Nuclear Power Corporation cc:
Regional Administrator, Region I G. Dana Bisbee, Esq. U. S. Nuclear Regulatory Comission Deputy Attorney General 475 Allendale Road 33 Capitol Street I King of Prussta, PA 19406 Concord, NH 03301-6937 R. K; Gad, IH * * ' Resident Inspector - s I Ropes & Gray Vermont Yankee Nuclear Power Stat' ion 1 One International Place U.S. Nuc lear Regulatory Comission Boston, MA 02110-2624 ' P.O. Box 176 Vernon, /T 05354 I Hr. Richard P. Sedano, Comissioner Vermont Department of Public Service Chief, Safety Unit 120 State Street, 3rd Floor Office of the Attorney General I Montpelier, VT 05602 One Ashburton Place, 19th Floor Boston, MA 02108 Public Service Board State of Vermont Mr. David Rodham, Director l 120 State Street ATTN: James Muckerheide Hintpelier, VT 05602 ; Massachusetts Civil Defense Agency 400 Worcester Rd. I Chairman, Board of Selectmen P.O. Box 1496 Tcwn of Vernon Framingham, MA 01701-0317
- P.O. ?ox 116 l Ver % VT 05354-0116 Hr. Raymond N. McCandless Vermont Division of Occupational Mr. cay Thayer, Vice President and Radiological Health Vermont Yankee Nuclear Power Administration Building Corporation Montpelier, VT 05602 Ferry Road Brattleboro, VT 05301 Nr. J. J. Duffy Licensing Engineer Vermont Yankee Nuclear Power Corporation 580 Main Street Boltori, MA 01740-1398 Mr. Robert J. Wanciyk, Plant Manager Vermont Yankee Nuclear Power Station P.O. Box 157, Governor Hunt Road Vernon, VT 05354 r
r Revision 20 Date 7/30/96 , E-3
pn afCg 5 UNITED STATES [ )y NUCLEAR REGULATORY COMMISSION
$ f WASHINGTON, D.C. 20555-4001 5
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ONSITE DISPOSAL OF CONTAMINATED SOIL VERHONT YANKEE NUCLEAR POWER CORPORATION VERHONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letters dated November 18, 1991, and July 10, 1992, the Vermont Yankee 1 Nuclear Power Corporation (the licensee) requested approval pursuant to Section 20.2002 of Title 10 of the Code of Federal Regulations (CFR) for the disposal of licensed material not previously considered in the Vermont Yankee I Final Environmental Statement (FES), dated 1972. The Vermont Yankee request contains: (a) a detailed description of the li I pr:ce;nsed material to be disposed of, including the physical and chemical perties important to risk evaluation, and the proposed manner and conditions of waste disposal; (b) an analysis and evaluation of pertinent information oa the nature of the environment; (c) the nature and location of oth:r potentially affected licensed and unlicensed facilities; and (d) analyses and procedures to ensure that doses are maintained as-low-as is reasonably achievable and within the dose limits in 10 CFR Part 20. DESCRIPTION OF WASTE In 1991, a leak was discovered in a chemistry laboratory drain inside the radiation control area (RCA) that allowed discharge from the chemistry fic:r slab. lab:ratory sink to seep directly into the structural fill soil beneath the I The fill soil is a 15 foot layer of f-ine-grained sand with some silt and minor gravel. The area is confined on three sides by existing fcundations and on the bottom by bedrock. All of the soil volume under the ISO-foot length of buried pipe is contaminated; the total volume is about 58,500 cu'oic feet. The end of the pipe has been capped and the area of excavation has been backfilled with concrete to the original floor line so that the line is inaccessible. N:w piping for the sink has been run above the floor to the collection tank. This new piping is accessible over its full length for periodic inspection to preclude a repeat of this event. The licensee has no way of determining how long the drain has been leaking; in order to bound the potential impacts associated with the leakage, the licensee assumed that the drain line had been leaking for 10 years. Samples of soil from grade to bedrock were obtained . l
/
Revision 20_ Date _J230/96 II-4
i lp from a split-spoon boring through the floor of the chemistry laboratory. Samples were analyzed for chemical and radionuclide distribution and ccncentration. Estimated amount of the principal radionuclides bound in the a c:ntaminated soil are listed in Table 1. The activity remaining after a 20 g y2ar decay period are also presented in the table. Table 1 Radionuclide Activity and Concentration Nuclide . (hal f-li fe) Activity Activity 1 (in years) Ci yCi H-3 (12.2) . 6.0E+04 2.6E+04 Hn-54 (0.85) 5.4E+01 4.9 E-06 Fe-55 (2.7) 4.4E+02 2.6E+00 Co-60 (5.27) 4.1E+02 3.0E+01 Cs-134 (2.06) 3.9E+01 4.8E-02 l Cs-127 (30.17) 1.4E+02 8.7E+01 Sr-90 (28.6) 3.2E-01 2.0E-01 1
- Activity after 10 years of weekly " batch" releases .
** That activity after a 20 year decay period.
The chemistry laboratory is located in the lower level of the office building ' at the north end of the turbine building complex. During plant construction, I this area was excavated to bedrock,15 feet below the chemistry laboratory (El. 233 feet). The area under the laboratory was then filled to its current grade and the concrete laboratory floor was poured. It is impractical to \ l structures. remove this contaminated material because it is located underneath building PROPOSED DISPOSAL HETH00 1 The licensee proposed to leave the contaminated soil in place. ' By terminating the release of liquids into the failed drain line, there is no significant driving force to cause any further movement of the activity now in the soil below the chemistry laboratory floor any deeper toward the groundwater level. The natural groundwater surface appears to be below the bedrock surface beneath the chemistry laboratory. The total quantity now present is I sufficiently small that it does not present a direct radiation exposure hazard in the chemistry laboratory. To remove the material would, however, require major excavation under the laboratory floor in proximity to the reactor building foundation and other critical structures, and would directly expose l workers perfonning the excavation to the hazard. The direct exposure, as well Revkion 20 Date 7/30/% . E-5
( f as potential airborne exposures to workers performing remediation, outweigh the risk of leaving the contamination in place, and exceed by far the [ pstential risk to a future population from leaving the contaminated soil where it is. There is no practical way for this material to be removed from the plant at this time. RADIOLOGICAL IMPACTS The licensee evaluated the following potential exposure pathways to members of the general public from the. radionuclides in the contaminated soil: (1) external exposure caused by farming on the contaminated grounds, (2) internal exposure caused by inhaling of resuspended radionuclides, and (3) internal exposure from ingesting groundwater, and water from onsite potable wells. Table 2 presents the doses calculated by the licensee for the maximum exposed member of the public from the contaminated soil under the floor of the chemistry laboratory. These doses are based on the radionuclide activities in Table 1. The doses were calculated for an inadvertent intruder for the { following pathways: ingestion of food from crops raised on contaminated land, ingestion of milk from cows grazing on the contaminated land, and inhalation of suspended material. It is also assumed that the family and animals raised j on the land also drink water from the contaminated land and breathe only air I affected by the contaminated area. Table 2 Intruder Exposures - Pathway Whole Body Organ (mrem) (mrem) s Drinking water ingestion 2.5E-05 6.3 E-05 Irrigation exposure pathway 1.2E-04 4.0E-04 j Well water ingestion 3.8E-01 1.9E-01 ( Direct ground plane 2.7E-01 0.0E-00 Inhalation (resuspension) 1.lE-01 6.5E-01 Leafy vegetable . 2.5E-02 2.4E-01 ( Cow milk 1.6E-01 1.5E-01 I I The licensee conservatively calculated these values with the assumption that the total exhumation of the 58,500 cubic feet of radioactive material and spreading in a layer equivalent to the plow depth, results in a continuous annual exposure of less than 1 mrem. This is a small fraction of the 300 mrem received annually by members of the general public in the United States and Canada from sources of natu.ral background radiation. The guidelines used by the NRC staff for onsite disposal of licensed material and the staff evaluation of how each guideline has been satisfied are given in Table 3. Revision _'LO Date 7/30/96 E-6
The staff ha's reviewed the licensee's calculational methods and assumptions and find that they are consistent with NUREG-1101, "Onsite Disposal of Radioactive Waste," Volumes 1 and 2, November 1986 and February 1987, and Regulatory Guide 1.109, " Calculation of Annual Doses to Han From Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I," Revision 1 (October 1977). The staff finds the assessment methodology acceptable. On this basis, the staff finds the licensee's procedures and amendments acceptable as documented in,.this safety evaluation. This safety evaluation will be added to the licensee's Offsite Dose Calculation Manual (00CH). No future modifications are necessary prior to decomissioning of the plant. The licensee's proposal to dispose of the contaminated soil under the chemistry laboratory (onsite) in a manner described in the Vermont Yankee submittal dated July 10, 1992, is acceptable.
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l L [ t - Revision 10 Date 7/30/96 E7
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Table 3 Guidelines for Onsite Disposal of Licensed Haterial l hhffjf$$ [5d$ heJ %s@M. Ebb 2NID5tiiNENikSDbh!k ONSITE?DISPOSAdEsk
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.U$Nk I The radioactive material should The nature of the disposed be disposed of in such a manner material makes it unlikely that it that it is unlikely that the would be recycled to the general I material would be recycled. public.
Doses to the total body and any This guideline is addressed in body organ of a minimally I exposed individual (a member of Table 2. the general public or a non-occupationally exposed worker) I from the probable pathways of exposure to the disposed material should be less than 1 mrem / year. Doses to the total body and any 3Because the material is insitu, body organ of an inadvertent the staff considers the miximally I intruder from the probable pathways of exposure should be exposed individual scenario to also address the intruder less than 5 mrem / year. scenario. Doses to the total body and any Even if recycling were to occur body organ of an individual from after release from regulatory assumed recycling of the control, the dose to a maximally I disposed material at the time exposed member of the public is the disposal site is released not expected to exceed 1 from regulatory control from all mrem / year, based on exposure likely pathways of exposure I should be less than 1 mrem. scenarios considered in this analysis. Principal Contributor: J. Minns l Date: l l l I Revision 20 D ne 7/30/96 ES r 4
APPENDIX I RADIDACTIVE LIQUID, GASEOUS. AND SOLIO WASTE TREATMENT SYSTEMS Reauirement: Technical Specification 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee. Res t>onse : There were no licensee-initiated major changes to the radioactive waste systems during this reporting period. I I I I I I I I [ man I-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 no on-site disposal of septic waste during the reporting year. I I I I I I I [ [ [ L attuo J-1 i _ _ _ _ _ _ _ _ _}}