ML20217E447
| ML20217E447 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1997 |
| From: | Sen G VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-98-48, NUDOCS 9803310045 | |
| Download: ML20217E447 (116) | |
Text
{{#Wiki_filter:_ VERMONT YAN,KEE g NUCLEAR POWER CORPORATION 185 Old Ferry Road, Brattleboro, VT 05301-7002
.-(802) 257-5271 March 25,1998 BVY 98-48 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Corporation i License No. DPR-28 (Docket No. 50-271) 1997 Vermont Yankee Annual Effluent and Waste Disposal Report f Pursuant to Vermont Yankee Technical Specification 6.7.C.1 and 10CFR50.30a(a)(2) enclosed is the subject report, s We trust that the information provided is acceptable; however, should you have any questions, please contact this office. Sincerely, VE MONT YANKEE NUCLEAR POWER CORPORATION (tyi h s. _ utam Sen Licensing Manager cc: USNRC Region 1 Administrator l USNRC Resident inspector - VYNPS USNRC Project Manager - VYNPS VT Department of Public Service I h l 9803310045 DR 971231 ADOCK 05000271 PDR 6 + ,,
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v I I I I I I I EFFLUEN W ISPOSAL FOR 1997 g I I I LI I I I I- vermont Yankee Nuclear Power Station I. g I
I 1997 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT VERMONT YANKEE NUCLEAR POWER STATION INTRODUCTION In accordance with 10CFR50.63a and Technical Specification 6.7.C.1, this report fulfills Vermont Yankee's commitment to submit to the Nuclear Regulatory Commission (NRC) an annual report that covers the content of I. radioactive effluents released to unrestricted areas during the previous calendar year of operation. This report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the I plant using the outline provided in Appendix B of Regulatory Guide 1.21, revision 1 (June 1974), " Measuring, Evaluating and Reporting Radioactive Materials in Solid Wastes and Releases of Radioactive Materials in Liquids and Gaseous Effluents from Light Water Cooled Nuclear Power Plants." In addition, meteorological data collected over the previous year is also provided in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. ; The report also includes summaries of any unplanned radioactive releases from f the site or excess liquid radioactive materials found in outside storage I i tanks, a listing of any inoperable (greater than 30 days) gaseous or liquid effluent monitoring instrumentation, changes made in the REMP milk sampling and any changes made to the Off-Site Dose Calculation Manual (0DCM) (including I those from the annual land use census), or Process Control Program (PCP). { l A supplemental report that includes an assessment of radiation doses due to the radioactive liquid and gaseous effluents (including direct radiation) I released from the plant during the previous calendar year will be filled separately with the NRC within 180 days of January 1.
- I I
I mun. e
E l TABLE 1A j l Vermont Yankee f Effluent and Waste Disposal Annual Report l l l First and Second Quarters.1997 Gaseous Effluents - Summation of All Releases Est. Quarter Quarter Total Unit 1 2 Error. % f A. Fission and Activation Gases
- 1. Total release Ci 0.00E+00 0.00E+00 i2.30E+01
- 2. Average release rate for period pCi/sec 0.00E+00 0.00E+00
- 3. Percent of Tech. Spec. limit % 0.00E+00 0.00E+00 B. Iodines
- 1. Total Iodine-131 Ci 6.68E-05 5.77E-05 il.80E+01
- 2. Average release rate for period pCi/sec 8.59E-06 7.34E-06 l 3. Percent of Tech. Soec. limit (1) %
C. Particulates
- 1. Particulates with T-1/2 > 8 days Ci 3.08E-05 1.04E-04 11.80E+01 f 1.32E-05
- 2. Average release rate for period pCi/sec 3.96E-06
- 3. Percent of Tech. Spec. limit (1) %
. 4. Gross alpha radioactivity C1 2.48E-06 3.67E-06 D. Tritium
- 1. Total release Ci 4.18E+00 3.42E+00 il.80E+01 I 2. Average release rate for period pCi/sec 5.38E-01 4.35E-01
- 3. Percent of Tech. Spec. limit (1) %
(1) Percent of Technical Specification limit will be provided in the Supplemental Effluent and Waste Disposal Report to be submitted per Technical Specification 6.7.C.1. I onus I
)
I TABLE 1A (Continued) Vermont Yankee Effluent and Waste Disposal Annual Report Third and Fourth Ouarters. 1997 Gaseous Effluents - Summation of All Releases , I Quarter Quarter Est. Total Error, % i l 4 Unit 3 4 A. Fission and Activation Gases
- 1. Total release Ci 0.00E+00 3.44E+00 i2.30E+01
- 2. Average release rate for period pCi/sec 0.00E+00 4.33E-01
- 3. Percent of Tech. Spec. limit (1) % 0.00E+00 B. Iodines
- 1. Total Iodine-131 C1 1.61E-04 1.09E-04 il.80E+01
- 2. Average release rate for period Ci/sec 2.03E-05 1.37E-05
- 3. Percent of Tech. Spec. limit (1) %
C. Particulates
- 1. Particulates with T-1/2 > 8 days Ci 6.78E-04 6.41E-05 il.80E+01 1
- 2. Average release rate for period Ci/sec 8.53E-05 8.06E-06
- 3. Percent of Tech. Spec. limit (1) %
- 4. Gross alpha radioactivity Ci 5.51E-06 4.02E-06 D. Tritium
- 1. Total release Ci 4.36E+00 4.14E+00 il.50E+01
- 2. Average release rate for period Ci/sec 5.49E-01 5.21E-01
- 3. Percent of Tech. Spec. limit (1)
I
% i l
(1) Percent of Technical Specification limit will be provided in the Supplemental Effluent 1 and Waste Disposal Report to be submitted per Technical Specification 6.7.C.1. { I I i I unns g;
I TABLE IB Vermont Yankee Effluent and Waste DisDosal Annual Report First and Second Quarters. 1997 Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode m Quarter Quarter Quarter Quarter Nuclides Released Unit 1 2 1 2
- 1. Fission Gases Kryoton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND I Xenon-133 Xenon-135 Xenon-13}m Ci Ci Ci ND ND ND ND ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Deriod Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines Iodine-131 Ci 6.68E-05 5.77E-05 Iodine-133' Ci 1.86E 04 9.57E-05 lodin_g-135 Ci ND ND Total for Deriod Ci 2.53E-04 1.53E-04 0.00E+00 0.00E+00 a
- 3. Particulates Strontium-89 C ', 2.55E 05 1.13E-05 I Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Barium Lanthanum 140 Ci ND ND I Mancanese-54 Chromium-51 Ci Ci ND ND ND ND Cobalt-58 Ci ND ND Cobalt-60 C1 ND 1.37E-05 Cerium-141 C1 4.74E-06 ND ,
Zinc-65 Ci ND ND I Total for period Ci 3.02E-05 2.50E 05 0.00E+00 (1) There were no batch mode gaseous releases for this reporting period. 0.00E+00 ND - Not detected at the plant stack. urun ~__---______:_______-
I TABLE IB (Continued) Vermont Yankee Effluent and Waste Disposal Annual Report Third and Fourth Ouarters. 1997 Gaseous,_E_ffluents - Elevated Releases Continuous Mode Batch Mode m I Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases I KrYDton-85 Krypton-85m Ci Ci ND ND ND 3.55E-02 KryDton-87 Ci ND 4.08E-02 KryDton-88 Ci ND ND Xenon-133 Ci ND 2.57E+00 Xenon-135 Ci ND 6.98E-01 I Xenon-135m Xenon 138 Ci Ci ND ND 9.23E-02 ND Unidentified Ci ND ND Total for period Ci 0.00E+00 3.44E+00 0.00E+00 0.00E+00
- 2. Iodines I Iodine-131 Todine-133 C1 Ci 1.61E-04 5.86E-04 1.09E-04 3.04E-04 j
, Iodine-135 Ci ND ND Total for period C1 7.47E-04 4.13E-04 0.00E+00 0.00E+00 l l
- 3. Particulates l I Strontium-89 Strontium-90 Cesium-134 Ci Ci Ci ND ND ND 1.43E-05 ND ND
.g Cesium-137 Ci 3.12E-05 ND g Ja ri um-Lanthanum-140 Ci ND ND i Manaanese-54 Ci ND ND (
Chromium-51 C1 3.80E-04 ND Cobalt-58 Ci 1.44E-05 ND Cobalt-60 Ci 1.76E 04 4.98E-05 j Cerium-141 Ci ND ND Zinc-65 Ci 7.64E-05 ND Total for period Ci 6.78E-04 6.41E-05 0.00E+00 0.00E+00 1 (1) There were no batch mode gaseous releases for this reporting period.
'I ND - Not detected at the plant stack.
. utun 1 i
- i
l I TABLE 1C Vermont Yankee Effluent and Waste Disposal Annual Report first and Second Ouarters 1997 Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode r-L, ouarter ouarter cuarter auarter Nuclides Released Unit 1 (1) 2 (2).(3) 1 (2).(3) 2 (1)
- 1. Firsion Gases Krypton-85 Ci
[} KrYDton-85m Ci Krypton-87 Ci E" Kryoton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci l Xenon-138 Ci Xenon-131m Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines Iodine-131 Ci Iodine-133 Ci
(( Iodine-135 Ci Total for oeriod Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e e 3. Particulates Strontium 89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci 3.39E-07 ND Cesium-137 Ci 3.72E-05 3.90E-08 ; Barium-Lanthanum-140 Ci ND ND Manaanese-54 Ci 1.54E-06 2.34E-08 l l 3.25E-08 1.47E-08 I l Chromium-51 Cobalt-58 Cobalt-60 C1 Ci Ci 2.09E-08 8.42E-06 9.49E-09 9.74E-08 Cerium-141 Ci ND ND Zinc 65 C1 2.09E-06 5.81E-08 Iron 55 C1 2.93E-05 3.57E 07 Total for period Ci 0.00E+00 7.89E-05 5.99E 07 0.00E+00 (1) There were no ground level gaseous releases of this type for the quarter. ' 1 (2) The North Warehouse stack was used as a ground level release point for burning of waste oil. (')~ Burning of waste oil was treated as six batch releases for the first quarter and 4 as a continuous release for the second quarter. ND - Not detected in the waste oil sample. ) utsus L -_ - -- - --_
I t TABLE IC l (Continued) Vermont Yankee l Effluent and Waste Disposal Annual Report i Third and Fourth Ouarters 1997 I Gaseous Effluents - Ground Level Releases Continuous Mode Batch Mode I Nuclides Released
- 1. Fission Gases Unit Quarter 3 (1)
Quarter 4 (1) Quarter 3 (1) Quarter 4 (1) I Ci krypton 85 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci i I Xenon-133 Xenon-135 Ci Ci Ci I Xenon-135m Xenon-138 Ci ,I Xenon-131m Ci Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
- 2. Iodines 1 Iodine-131 Ci !
l g Iodine-133 Ci g lodine-135 Ci 0.00E+00 0.00E+00 0. 00 E-c00 l Total ,for period Ci 0.00E+00 o
- 3. Particulates j Strontium-89 Ci I Strontium-90 Ci l Cesium-134 Ci j N 5 Ci l Cesium 137 Barium-Lanthanum-140 Ci f l
I l Mancanese-54 Ci Chromium-51 Ci f Cobalt-58 C1 1 g Cobalt-60 Ci E Cerium-141 C1 Zinc-65 Ci Iron-55 Ci Total for Deriod Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (1) There were no ground level gaseous releases for this reporting period. ND - Not detected in the waste oil sample. l I urun 1_
=. I I TABLE 10 Vermont Yankee Effluent and Waste Disposal Annual Report for 1997 Gaseous Effluents - Nonroutine Releases ) I There were no nonroutine or accidental gaseous releases during this reporting period. j l I I I I IO I
- g I
I urun ,
I TABLE 2A ' Vermont Yankee Effluent and Waste Disposal Annual ReDort l for 1997 Liould Effluents - Summation of AlI :tel ea ses I There were no liquid releases during this reporting person. i I ; i
- I I- )
I" I I i 4 l g J
E TABLE 2B Vermont Yankee Effluent and Waste Disposal Annual ReDort for 1997 ) Liauid Effluents - Nonroutine Releases . There were no nonroutine or accidental liquid releases during this reporting period. I I I I O I I I
~' ~
I ~""
I TABLE 3 I Vermont Yankee Effluent and Waste Disposal Annual Recort Eirst and Second Ouarters. 1997 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. %
- a. Spent resins, filter sludges, evaporator m' 1.31E+02 bottoms. etc. C1 2.59E+02 +2.50E+01 __
- b. Dry compressible waste, contaminated m' 1.00E+01 eautoment. etc. Ci 1.50E-01 +2.50E+01
- c. Irradiated components, control rods, m' O.00E+00 etc. Ci 0.00E+00 +2.50E+01 ]
I 2. Estimate of Major Nuclide Composition (By Type of Waste): i I a. Zinc-65 Cesium-137
% 2.10E+01
% 1.30E+01
- b. Iron-55 Zinc-65
% 7.40E+01
% 3.00E+00 I Cobalt-60 Cesium-134
% 1,80E+01
% 1.00E+00 Mancanese-54 % 1.00E+01 Cobalt-60 Cesium-137
% 1.30E+01 Mancanese-54 % 5.00E+00
% 2.00E+00 ,
I Iron-55 % 2.60E+01
- 3. Solid Waste Disposition:
I j! umber of Shioments Mode of Transportation Destination 49 Truck Barnwell SC B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information
- 1) Class of solid waste containers shipped: 42 A, 7 B
- 2) Types of containers used: 26 Type A, 23 Strong Tight I 3) Solidification agent or absorbent: None I mun n . .
I , I TABLE 3 (Continued) Vermont Yankee Effluent and Waste Disposal Annual Report . 1 Third and Fourth Ouarters. 1997 Solid Waste and IrrPJ!iated Fuel Shipments I A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel): Unit 6-Month Est. Total ) I 1. Type of Waste m3 Period 2.42E+01 Error. %
- a. Spent resins, filter sludges, evaporator q bottoms. etc. Ci 5.86E+01 +2.50E+01 j
- b. Dry compressible waste, contaminated m3 1.49E+01 equiDment. etc. Ci 1.60E+00 +2.50E+01
- c. Irradiated components, control rods, m3 7.00E+00 etc. Ci 3.72E+04 +2.50E+01
- 2. Estimate of Major Nuclide Composition (By Type of Waste): .
1
- a. Zinc-65 % 2.10E+01 b. Icon-55 % 7.40E+01 Cesium-137 % 1.30E+01 Zinc-65 % 3.00E+00 Cobalt-60 % 1.80E+01 Cobalt-60 % 1.30E+01 1 I
Cesium-134 % 1.00E+00 Mancanese-54 % 5.00E+00 Mancanese-54 % 1.00E+01 Cesium 137 % 2.00E+00 Iron-55 % 2.60E+01 1 o
- c. Iron-55 % 4.10E+01 Mancanese-54 % 1.00E+00 j Cobalt-60 I Nickel-63
% 5.50E+01
% 3.00E+00
- 3. Solid Waste Disposition:
I I Number of Shioments Mode of Transportation Destination l 14 Truck Barnwell, SC l B. Irradiat'ed Fuel Shipments (Disposition): None
]
I C. Supplemental information I
- 1) Class of solid waste containers shipped: 19 A, 1 B, 2 C )
- 2) Types of containers used: 6 Type A, 3 Type B, 13 Strong Tight j
- 3) Solidification agent or absorbent: None {
I urun ! j i 1 1
- )
F' L- ~ TABLE 4 Vermont Yankee {. Effluent and Waste Disoosal Annual Report
.for 1997 Maximum
- Off-Site Doses'and Dose Commitments to Members of the Public
.These doses will.be provided in the Supplemental Effluent and Waste Disposal Report to
{ be' submitted p:r Technical Specification 6.7.C.1. D E E g I [ [ 4 E E E E B UAU36 [L __ -_ - -----_ --- --_-- --- ------ _ -- --_ _ _ __ _ - - __-
~ I LI-I I TABLE 5A i I VERMGIT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERC*I**) m .64 I WIND DIRECTION FROM WSW W NW Nt@f VRBL TOTAL SPEED N NNE NE ENE E ESE SE SSE S SSW SW te**W I MPH CALM (1) (2)
.00
.00 0 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
.00
.00 0
.00
.00 0 0
.00
.00 0
.00
.00
.00 00 0 0
.00
.00 I C-3 (1)
(2) 3.57
.02 2 0
.00
.00 0
.00 5.36
.00 3
.03 0 3 1 1
.00 5.36 1.79 1.79 3.57
.00 .03 .01 .01 2
.02 0
.00
.00
.00
.00 0 0
.00
.00
.00
.00 0
.00
.00 0 1 1.79 1.79
.01 1
.01 0
'. 0 0
.00 14 25.00
.16 4-7 1 0 0 0 0 3 5 0 1 1 0 0 0 0 1 1 0 13 (1) 1.79 .00 .00 .00 .00 1.79 1.79 .00 .00 .00 .00 1.79 1.79 .00 23.21
.I
.00 5.36 8.93 (2) .01 .00 .00 .00 .00 .03 .06 .00 .01 .01 .00 .00 -. 00 .00 .01 .01 .00 .15 8-12 1 0 0 0 0 0 1 3 0 0 0 0 0 1 1 4 0 11 (1) 1.79 .00 .00 .00 .00 .00 1.79 5.36 .00 .00 .00 .00 .00 1.79 1,79 7.14 .00 19.64 (2) .01 .00 .00 .00 .00 .00 .01 .03 .00 .00 .00 .00 .00 .01 .01 .05 .00 .13 13-18 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 4 0 9 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.57 3.57 1.79 7.14 .00 16.07 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .02 .01 .05 .00 .10 I 19-24 (1)
(2)
.00 0
.00 0
.00
.00
.00
.00 0 0
.00
.00
.00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00
.00
.00
.00 0 1
.00 1.79 12.50
.01 0
7
.08 0
.00
.00 0
0 8 14.29
.09 1
M 24 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1.79 .00 .00 .00 .00 1.79 I4 (1) (2) ALL SPEEDS (1)
.00
.00 7.14 4
.00
.00 0
.00
.00
.00 0
.00
.00
.00 5.36 3
.00
.00 0
.00
.00 6
.00
.00 7
.00
.00 4
.00
.00 3
.00 10.71 12.50 7.14 5.36 1.79
.00
.00 1
.00
.00
.00 0
.00
.00 0
.00
.01 3
.00 3
.00 5
5.36 5.36 8.93 30.36
.00 17
.00 6
.01
.00 100.00 56 (2) .05 .00 .00 .03 .00 .07 .08 .05 .03 .01 .00 .00 .03 .03 .06 .20 .00 .64 (M sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE )
(2).PERCDff OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS 'IHAN OR EQUAL TO .95 MPH) i 1 l
-I iI- l l
A J
o I I I I I TABLE 5B VEPJ40NT YANKEE JAN 97 - 1)EC 97 METEOROLOGICAL DATA JOIttf FREQUENCY DISTRIBLff20N s) 297.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCDrf) e .76 I SPEED N NNE NE ENE E ESE WIND DIRECTION FROM SE SSE C SSW SW WSW W WNW NW NNW VRBL 'JOTAL I MPH CALM (1) (2) 0
.00
.00 0
.00
.00
.00
.00 0
.00 0
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00 0
.00 0
.00
.00 .00 0
.00 .00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 I C-3 (1)
(2) 0
.00
.00 0
.00
.00
.00
.00 0
1.52
.01 1 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00 0
.00
.00
.00 0 0
.00
.00
.00
.00 0
0
.00
.00 0
0 0
.00
.00 0
0
.00
.00 2
0
.00
.00 0
1 1.52
.01 10 4-7 0 0 0 1 2 0 2 2 1 0 0 0 I (1) .00 .00 .00 1.52 3.03 .00 3.03 3.03 1.51 .00 .00 .00 .00 .00 .00 3.03 .00 15.15 (2) .00 .00 .00 .01 .02 .00 .02 .02 .01 .00 .00 .00 .00 .00 .00 .02 .00 .11 8-12 2 0 0 1 0 0 1 3 0 0 0 0 0 0 0 9 0 16 (1) 3.03 .to .00 1.52 .00 .00 1.52 4.55 .00 .00 .00 .00 .00 .00 .00 13.64 .00 24.24
.00 .10 .00 .18 I (2) .02 .00 .00 .01 .00 .00 .01 .03 .00 .00 .00 .00 .00 .00 13-18 1 0 0 0 0 0 0 0 2 0 0 0 1 1 1 15 0 21 (1) 1.52 .00 .00 .00 .00 .00 .00 .00 3.03 .00 .00 .00 1.52 1.52 1.52 22.73 .00 31.82 (2) .01 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .00 .01 .01 .01 .17 .00 .24 19-24 1 0 0 0 1 0 0 0 0 0 0 0 1 2 2 9 0 16 (1) 1.52 .00 .00 .00 1.52 .00 .00 .00 .00 .00 .00 .00 1.52 3.03 3,03 13.64 .00 24.24 (2) .01 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 .02 .02 .10 .00 .18 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 2
.00 .00 .00 .00 .00 .00 .00 .00 3.03 .00 3.03 I4 (1)
(2) ALL SPEEDS (1)
.00
.00 6.06 4
.00
.00
.00 0
.00
.00 0
.00 3
.00 4.55 4.55
.00
.00 3
.00
.00 0
.00
.00
.00 3
.C0
.00 5
4.55 7.58 4.55
.00 3
.00
.00 0
.00
.00 0
.00 0
.00
.00 2
.00 3
.00 3
.02 3.03 4.55 4.55 56.06 37
.00 0
.00
.02 66 100.00 (2) .05 .00 .00 .03 .03 .00 .03 '.06 .03 .00 .00 .00 .02 .03 .03 .43 .00 .76 (1)ePERCENT OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2)ePERCDrf CF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CAIJE (WIND SPEED LESS THAN OR EQUAL 'Io .95 MPH)
I I I- ,
- n. - ~
' E I
I TABLE SC I VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBt7 TION 291.0 FT WIND DATA CTABILITY CLASS C CLASS FREQUENCY (PERCENT)
- 2.22 I 8 PEED N NNE NE ENE E EG SE WIND DIRECTION FROM SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL I MPH CALM (1)
(2)
.00 0
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0
.00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0
.00
.00 0
I C+3 (1) (2)
.00
.00 0 0
.00
.00
.00 0
.00 1.04
.02 2 0
.00
.00
.52
.01 1
.52
.01 1 0
.00
.00 0
.00
.00 0
.00
.00
.00 0
,. 0 0 1
.52
.01 0
.00
.00 1
.52
.01 0
.00
.00 1
.52
.01
.00
.06 0
3.63
.08 7
41 47 4 1 0 0 0 7 6 2 1 0 1 0 0 1 2 16 0 l I (1) (2) 8-12 (1) 2.07
.05 10 5.18
.52
.01
.00 0
.00
.00 1.04 2
.00
.00
.00 0
.00
.00 1
.52 3.63 3.11 1.04
.08 3
.07 2
.02 1.55 1.04 5.70 1.55 11
.52
.01 3
.00
.00 0
.00
.52
.01
.00 0
.00
.00 2
.00
.00 3
.52 1.04 8.29
.01 4
.02 4
1.04 1.55 2.07 2.07 9.33
.18 18
.00
.00
.00 0
21.24
.47 63 32.64 1
I (2) .11 .00 .02 .00 .01 .03 .02 .13 .03 .00 .00 .02 .03 .05 .05 .21 .00 .72 13-18 5 0 0 1 1 0 1 1 5 0 0 2 4 3 8 15 0 46 (1) 2.59 .00 .00 .52 .52 .00 .52 .52 2.59 .00 .00 1.04 2.07 1.55 4.15 7.77 .00 23.83 (2) .06 .00 .00 .01 .01 .00 .01 .01 .06 .00 .00 .02 .05 .03 .09 .17 .00 .53 19-24 1 0 0 0 1 0 0 0 1 0 0 0 2 6 5 13 0 29 (1) .52 .00 .00 .00 .52 .00 .00 .00 .52 .00 .00 .00 1.04 3.11 2.59 6.74 .00 15.03 (2) .01 .00 .00 .00 .01 .00 .00 .00 .01 .00 .00 .00 .02 .07 .06 .15 .00 .33 GT 24- 0 0 0 0 0 0 0 0 0 0 0 0 1 1 3 2 0 7 1 4 .00 .00 .00 .52 .52 1.55 1 04 .00 3.63 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 l (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .03 .02 .00 .08 ALL SPEEDS 20 1 2 3 3 11 to 14 10 0 1 5 10 16 22 65 0 193 (1) 10.36 .52 1.04 1.55 1.55 5.70 5.18 7.25 5.18 .00 .52 2.59 5.18 8.29 11.40 33.68 .00 100.00
.25 .00 2.22 I
(2) .23 .01 .02 .03 .03 .13 .11 .16 .11 .00 .01 .06 .11 .18 .75 1)* PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3)*PERCDTP OF ALL GOOD OBSERVATIONS FOR THIS PERIOD ( Ce CALM (WDID SPEED LESS '!1(AN OR EQUAL TO .95 MPH) I l I I I
I !I TABLE 5D l l VEPMOfft YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DhTA STABILITY CLASS D CLASS FREQUENCY (PERCErff) = 48.91 WIND DIRECTION FROM SE SSE S SSW SW WSW W WNW NW NNW VRBL TCyrAL SPEED N NNE NE ENE E ESE I MPH CMR (1) (2) 0
.00
.00 0
.00
.00 2
.05
.02 0
.00
.00 1
.02
.01 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 1
.02
.01 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00 1
.02
.01 2
,05
.02 0
.00
.00
.16
.08 7
C-3 56 31 38 42 41 55 61 47 26 12 6 11 12 9 32 48 0 527 (1) 1.32 .73 .89 .99 .96 1.29 1.43 1.10 .61 .28 .14 .26 .28 .21 .75 1.13 .00 12.39 (2) .64 .36 .44 .48 .47 .63 .70 .54 .30 .14 .07 .13 .14 .10 .37 .55 .00 6.06 4-7 104 33 23 20 48 76 107 118 92 20 21 16 15 27 55 200 0 975 (1) 2.44 .78 .54 .47 1.13 1.79 2.52 2.77 2.16 .47 .49 .38 .35 .63 1.29 4.70 .00 22.92 (2) 1.20 .38 .26 .23 .55 .87 1.23 1.36 1.06 .23 .24 .18 .17 .31 .63 2.30 .00 11.21 8-12 151 29 25 11 20 28 63 119 162 41 38 44 95 121 63 245 0 1255 (1) 3.55 .68 .59 .26 .47 .66 1.48 2.80 3.81 .96 .89 1.03 2.23 2.84 1.48 5.76 .00 29.50
.72 2.82 .00 14.43 I (2) 1.74 .33 .29 .13 .23 .32 .72 1.37 1.86 .47 .44 .51 1.09 1.39 13-18 119 9 2 5 2 4 11 29 125 20 13 19 110 203 111 249 0 1031 (1) 2.80 .21 .05 .12 .05 .09 .26 .68 2.94 .47 .31 .45 2.59 4.77 2.61 5.85 .00 24.24 l
(2) 1.37 .10 .02 .06 .02 .05 .13 .33 1.44 .23 .15 .22 1.26 2.33 1.28 2.86 .00 11.85 l 19-24 24 2 0 0 0 0 0 1 18 3 0 4 43 89 63 112 0 359 (1) .56 .05 .00 .00 .00 .00 .00 .02 .42 .07 .00 .09 1.01 2.09 1.48 2.63 .00 8.44 (2) .28 .02 .00 .00 .00 .00 .00 .01 .21 .03 .00 .05 .49 1.02 .72 1.29 .00 4.13 l OT 24 12 0 0 0 0 0 0 0 0 1 1 0 5 28 19 34 0 100 I (1) .28 .00 .00 .00 .00 .00 .00 .00 .00 .02 .02 .00 .12 .66 .45 .80 .0C 2.35 (2) .14 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .06 .32 .22 .39 .00 1.15 ALL SPEEDS 466 104 90 78 112 163 242 314 423 98 19 94 280 477 344 890 0 4254 (1) 10.95 2.44 2.12 1.83 2.63 3.83 5.69 7.38 9.94 2.30 1.86 2.21 6.58 11.21 8.09 20.92 .00 100.00 (2) 5.36 1.20 1.03 .90 1.29 1.87 2.78 3.61 4.86 1.13 .91 1.08 3.22 5.48 3.95 10.23 .00 48.91 (llaPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE [ (2)aPERCENT OF ALL 000D OBSERVATIONS FOR THIS P".RIOD l Ce CALM (WIND SPEED LESS THAN OR EQUAL '!V .95 MPH) f I \ l I 1
I I I TABLE SE
- I VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOIttP FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CIASS E CLASS FREQUENCY (PERCE2fT) = 33.39 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL l MPH CALM 2 0 6 3 1 0 1 1 0 0 1 0 0 0 1 2 0 18 l
I (11 .07 .00 .21 .10 .03 .00 .03 .03 .00 .00 .03 .00 .00 .00 .03 .07 .00 .62 (2) .02 .00 .07 .03 .01 .00 .01 .01 .00 .00 .01 .00 .00 .00 .01 .02 .00 .21 C-3 til 76 55 44 56 72 77 50 47 21 12 16 12 17 37 77 0 780 g (1) 3.82 2.62 1.89 1.52 1.93 2.48 2.65 1.72 1.62 .72 .41 .55 .41 .59 1.27 2.65 .00 26.86 (2) 1.28 .87 .63 .51 .64 .83 .89 .57 .54 .24 .14 .18 .14 .20 .43 89 .00 8.97 4-7 156 18 15 14 17 45 137 115 71 26 18 12 20 30 63 272 0 1029 I (1) (2) 8-12 5.37 1.79 64 2.20
.62
.21 4
.52
.17 0
.00
.48
.16
.03 1
.59
.20 1
.03 1.55 4.72 3.96 2.44
.52 1.58 1.32 8
.28 28
.96 73
.82 75
.90
.30 20
.69
.62
.21 18
.62
.41
.14 28
.96
.69
.23 56 1.03 2.17 9.37
.34 75 72 3.13 63 1.93 2.58 2.17 8.51 247
.00
.00 0
.00 35.43 11.83 761 26.21 (1) .14 2.51 2.58 (2) .74 .05 .00 .01 .01 .09 .32 .84 .86 .23 .21 .32 .64 .86 .72 2.84 .00 8.75 264
[3 13-18 (1) 11
.38 1
.03 0
.00 .00 0 0
.00 .00 0
.10 3 5
.17 37 1.27 15
,52 .00 0
.14 4 28
.96 44 40 1.52 1.38 2.62 76 0
.00 9.09 (2) .13 .01 .00 .00 .00 .00 .03 .06 .43 .17 .00 .05 .32 .51 .46 .87 .00 3.04 19-24 1 1 0 0 0 0 0 1 6 10 0 0 2 8 6 9 0 44 (1) .03 .03 .00 .00 .00 .00 .00 .03 .21 .34 .00 .00 .07 .28 .21 .31 .00 1.52 (2) .01 .01 .00 .00 .00 .00 .00 .01 .07 .11 .00 .00 .02 .09 .07 .10 .00 .51 M 24 0 0 0 0 0 0 0 0 2 1 1 0 1 2 0 1 0 8 4 .00 .03 .07 .00 .03 .00 .28
- (1) 00 .00 .00 .00 .00 .00 .00 .00 .07 .03 .03 (2) .00 .00 .00 .00 .00 .00 .00 .00 .02 .01 .01 .00 .01 .02 .00 .01 .00 .09 ALL SPEEDS 345 100 76 62 75 125 246 245 238 93 50 60 119 176 210 684 0 2904 (1) 11.88 3.44 2.62 2.13 2.58 4.30 8.47 8.44 8.20 3.20 1.72 2.07 4.10 6.06 7.23 23.55 .00 100.00 (2) 3.97 1.15 .87 .71 .86 1.44 2.83 2.82 2.74 1.07 .57 .69 1.37 2.02 2.41 7.86 .00 33.39 1
(llePERCENT OF ALL 0000 OBSERVATIONS FOR THIS PAGE (2)aPERCENT OF ALL 0000 OBSERYATIONS FOR THis PERIOD Ca CALM (WIND SPEED LESS 'IMAN OR EQUAL TO .95 MPH) I I I I I I
l I TABLE 5F VERMOtfr YANKEE JAN 97
- DEC 97 METUOROLOGICAL DATA JOINF FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 12.57 WItiD DIRECTION FROM SPEED N - NNE ME ENE E ESE SE SSE- 8 SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM 1 1 0 2 0 0 0 1 0 0 0 0 1 1 1 0 0 8 (1) .09 .09 .00 .18 .00 .00 .00 .09 .00 .00 .00 .00 .09 .09 .09 .00 .00 .73
.(2) .01 .01 .00 .02 .00 .00 .00 .01 .00 .00 .00 .00 .01 .01 .01 .00 .00 .09 I. C-3 65 37 29 31 30 33 44 30 19 16 8 6 7 8 27 35 0 425 (11 5.95 3.39 2.65 2.84 2.74 3.02 4.03 2.74 1.74 1.46 .73 .55 .64 .73 2.47 3.20 .00 38.88 4.89 (2) .75 .43 .33 .36 .34 .30 .51 .34 .22 .18 .09 .07 .08 .09 .31 .40 .00 l 1
47 59 19 29 51 55 32 14 9 20 14 18 20 96 0 449
.'5.40 2
.18 .46 5
.55 6
1,74 2.65 4.67 5.03 2.93 1.28 .82 1.83 1.28 1.65 1.83 8.78 .00 41.08 ] (1) I- (2) 8-12
.68 5
.02 1
.06 0
.07 0
.22 2
.33 1
.59 10
.63 14
.37 20
.16 15
.10 8
.23 6
.16 12
.21 19
.23 1.10 8 60
.00 0
5.16 181 (1) .46 .09 .00 .00 .18 09 .91 1.28 1.83 1.37 .73 .55 1.10 1.74 .73 5.49 .00 16.56 (2) .06 .01 .JO .00 .02 .01 .11 .26 .23 .17 .09 .07 .14 .22 .09 .69 .00 2.08 13-18 0 0 0 0 0 0 0 2 1 3 0 2 4 4 1 13 0 30 (1) .00 .00 .00 .00 .00 .00 .00 .18 .09 .27 .00 .18 .37 .37 .09 1.19 .00 2.74 (2) .00 .00 .00 .00 .00 .00 .00 .02 .01 .03 .00 .02 .05 .05 .01 .15 .00 .34 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 er 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 .00 .00 .00 .00 .00 .00 .00 .00 .00 (1) .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 110 41 34 39 51 63 105 102 72 48 25 34 38 50 57 204 0 1093 (1) 11.P9 3,75 3.11 3.57 4.67 5.76 9.61 9.33 6.59 4.39 2.29 3.11 3.48 4.57 5.22 18.66 .00 100.00 (2) 1.49 .47 .39 .45 .59 .72 1.21 1.17 .83 .55 .29 .39 .44 .57 .66 2.35 .00 12.57 (llePERCENT OF ALL 000D OBSERVATIONS FOR '1HIS PAGE (3)sPERCENT OF ALL GOOD OBSERVATIONS FOR '1HIS PERIOD Ce CAIR (WIND SPEED LESS THAN OR EQGAL TO .95 MPH) I l l 1 b_
s (.p .. g D TABLE'5G' I ~ VERN000T YANKEE JAN 97 - DEC 97 METEORO14GICAL DATA JOINT FREQUENCY DISMIBUTION
.297.0 FT WIND DATA STABILITY CIAS8 O CLASS FREQUENCY (PERCEffr) = 1.52 WIND DIRECTION FRON SPEED N- DefE ME ENE E ESE SE SSE ~S SSW ~ SW WSW W WNW NW NNW VRSL MTAL I
l MPH CALN (1)
.(2)'
O
.00-
.00
~
O
. 00 -
.00 O
.00
,00 0
.00
.00-0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00
.00
.00 0 0
.00
.00 0
.00
.00
.00
.00 0
.00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
- C-3 5 2- 3 4 1 4 3 1 1 2 3 2 2 1 3 3 0 40 (1) 3.79~ 1.52 2.27 3.03 .76 3.03 2.27 .76 76 1.52' 2.27 1.52 1.52 .76 2.27 2.27 .00 - 30.30 (2) . .06 02 .03 .05- .01 .05 .03 .01 .01 402 .03 .02 .02 .01 .03 .03 .00 .46 l'"- 54 4-7 2 1 0 0 3 0 2 6 7 7 1 6 4 3 4 8 0 (1) 1.52 .76 .00 .00 2.27 .00 1.52 4.55 5.30 5.30 76 4.55 3.03 2.27 0.03 6.06 .00 40.91 (2) .02 .01 .00 .00 .03 .00 .02 .07 .08 .08 .01 .07 .05 .03 .a5 .09 .00 .62 8 12 1 0 0 0 0 0 0 -2 0 0 2 4 6 9 2 8 0 34 (1) .76 .00 .00 .00 .00 .00 .00 1.52 .00 .00 1.52 3.03 4.55' 6.82 1.52 6.06 . 00 - 25.76 (2) .01 .00 .00 .00 .00 .00 .00 .02 .00 .00 .02 - .05 .07 .10 .02 .09 .00 .39 13 18 0 0 0 0 0 0 0 0 1 1 0 0 1 1 0 0 0 4 (1) .00 .00 .00 .00 .00 .00 .00 .00 76 .76 .00 .00 .76 .76 .00 .00 .00 3.03
[ . (2)- .00 .00 .00 .00 .00 .00- ,00 :. 00 .01 .01 .00 .00 .01 .01 .00 .00 .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 .00 .00
. 00 - .00 .00 .00 .00 .00 .00 .00- .00 .00 .00 .00 .00 H
l (2) .00 00 .00 .00 .00 L' 07 24 . 0 0 0 0 0 0' O 0 0 0 0 0 0 0 0 0 0 0
* .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (1) .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 8 3 3 4 4 4 5 9 9 to 6 12 13 14 9 19 0 132 (1) - 6.06. 2.27 2.27 3.03 3.03 3.03 3.79 6,82 6.82 7.58 4.55 9.09 9.85 10.61 6.82 14.39 .00 100.00 Q (2) .09 .03 .03 .05 .05 .05 .06 .10 .10 .11 .07 .14 .15 .16 .10 .22 .00 1.52
'(1)ePERC8NT OF ALL 000D OBSERVATIONS FOR 'INIS PAGE F (21sPERCElf! OF ALL 000D OBSERVATIONS FOR THIS PERIOD Ce CAIJi (WIND SPEED LESS THAN OR EQUAL M .95 NPH)-
{ .. i E g
+
3
'.2
- b;.-
- I I
I I - ss VERMONT YANKEE JAN 97 a DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCDff) a 100.00 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WIM IM NtM VRBL 'IOTAL MPH CALM 3 1 8 5 2 0 1 2 0 1 1 0 1 1 3 4 0 33 (1) .03- .01 .09 .06 .02 .00 .01 .02 .00 .01 .01 .00 .01 .01 .03 .05 .00 .38 (2) .03 .01 .09 .06 .02 .00 .01 .02 .00 .0? .01 .00 .01 .01 .03 .05 .00 .38 C-3 239 146 125 127 128 168 187 129 95 51 29 36 33 36 100 165 0 1794 (1) 2.75 1.68 1.44 1.46 1.47 1.93 2.15 1.48 1.09 .59 .33 .41 .38 .41 1.15 1.90 .00 20.63 (2) 2.75 1.68 1.44 1.46 1.47 1.93 2.15 1.48 1.09 .59 .33 .41 .38 .41 1.15 1.90 .00 20.63 4-7 326 55 43 41 89 160 310 298 205 68 50 54 53 79 145 595 0 2571 I (1) 3.75 .63 .49 .47 1.02 1.84 3.56 3.43 2.36 .78 .57 .62 .61 .91 1.67 6.84 .00 29.56 (2) 2.75 .63 .49 .47 1.02 1.84 3.56 3.43 2.36 .78 .57 .62 .61 .91 1.67 6.84 .00 29.56 8-12 234 34 27 13 24 40 105 225 260 76 66 84 172 229 141 591 0 2321 (1) 2.69 .39 .31 .15 .28 .46 1.21 2.59 2.99 .87 ,76 .97 1.98 2.63 1.62 6.79 .00 26.68
.87 .76 .97 1.98 2.63 1.62 6.79 .00 25.68 I
(2) 2.69 .39 .31 .15 .2s .46 1.21 2.59 2.99 13-18 136 10 2 6 3 4 15 37 171 39 13 27 150 258 162 372 0 1405 (1) 1.56 .11 .02 .07 .03 .05 .17 .43 1.97 .45 .15 .31 1,72 2.97 1.86 4.28 .00 16.15 (2) 1.56 .11 .02 .07 .03 .05 .17 .43 1.97 .45 .15 .31 1.72 2.97 1.86 4.28 .00 16.15 19-24 27 3 0 0 2 0 0 2 25 13 0 4 48 105 77 150 0 456 (1) .31 .03 .00 .00 .02 .00 .00 .02 .29 .15 .00 .05 .55 1.21 .89 1.72 00 5.24 (2) .31 .03 .00 .00 .02 .00 .00 .02 .29 .15 .00 .05 .55 1.21 .89 1.72 .00 5.24 OT 24 12 0 0 0 0 0 0 0 2 2 2 0 8 31 22 39 0 118
* (1) .14 .00 .00 .00 .00 .00 .00 .00 .02 .02 .02 .00 .09 .36 .25 .45 .00 1.36 (2) .14 .00 .00 .00 .00 .00 .00 .00 .02 .02 .02 .00 .09 .36 .25 .45 .00 1.36 ALL SPEEDS 977 249 205 192 248 372 618 693 758 250 161 205 465 739 650 1916 0 8698 (1) 11.33 2.86'2.36 2.21 2.85 4.28 7.11 7.97 8.71 2.87 1.85 2.36 5.35 8.50 7.47 22.03 .00 100.00 (2) 11.23 2.86 2.36 2.21 2.85 4.28 7.11 7.97 8.71 2.87 1.85 2.36 5.35 8.50 7.47 22.03 .00 100.00 I (
1)ePERCDff OF ALL 000D OBSERVAT10NS FOR 'IHIS PAGE (8).PERCDff OF ALL OOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL '!D .95 MPH) l I .I -I , I M ._ i
s I TABLE 6A VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT! a 1.87 WIND DIRECTION PROM SPEED N NNE NE ENE E ESE SE SSE S SS* SW WSW W WNW NW NNW VRBL TOTAL MPH 0 0 0 0 0 0 0 0 CALM
.00 0 0
.00 0 0 0
.00 0
.00 0
.00 0
.00 .00 0 0
.00 .00 .00 .00 .00 .00 .00 .00 .00 'f (1) .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) 4-7 1.27
.02 13 2 0
.00
.00 0
1.27 2
.02 1
0
.00
.00 2
2 1.27 1.27
.02 2
2
.02 5
.01 1
.63 5
2 1.27
.02 6
.63
.01 1
1 0
.00
.00 1
1.27
.02 2
0
.00
.00 0
1 0
.00
.00 0
.00
.00 0
1 1
.63
.01 12
.00
.00 0
21 0
.00
.00 0
15 9.49
.18 71 4
j l 1 7.59 13.29 .00 44.94 I (1) 8.23 .00 .63 1.27 1.27 3.16 3.16 3.80 .63 .63 .00 .63 .00 .63 l (2). .15 .00 .01 .02 .02 .06 .06 .07 .01 .01 00 .01 .00 .01 .14 .25 .00 .84 1 8-12 12 0 0 0 0 0 0 0 3 0 0 1 3 7 7 30 0 63 (1) 7.59 .00 .00 .00 .00 .00 .00 .00 1.90 .00 .00 .63 1.90 4.43 4.43 18.99 .00 39.87 (2) .14 .00 .00 .00 .00 .00 .00 .00 .04 .00 .00 .01 .04 .08 .08 .35 .00 .75 13-18 1 0 0 0 0 0 0 0 1 0 0 0 0 2 5 0 0 9 (1) .63 .00 .00 .00 .00 .00 .00 .00 .63 .00 .00 .00 .00 1.27 3.16 .00 .00 5.70 (2) .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .02 .06 .00 .00 .11 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 l (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I W 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 !
(2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l ALL SPEEDS 28 0 3 2 4 7 6 8 6 1 2 2 3 10 25 51 0 158 (1) 17.73 .00 1.90 1.27 2.53 4.43 3.80 5.06 3.80 .63 1.27 1.27 1.90 6.33 15.82 32.28 .00 100.00 (2) .33 .00 .04 .02 .05 . 08 .07 .09 .07 .01 .02 .02 .04 .12 .30 .60 .00 1.87
- (1)ePERCENT OF ALL OOOD OBSERVATIONS FOR 'IltIS PAOl3 (2)ePERCDTF OF ALL 000D OBSERVATIONS FOR THIS PERIOD Ce CAlht (WIND SPEED LESS THAN OR EQUAL '!V .95 MPH)
I j
~ . . .
r I I TABLE 6B l VERMorff YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOItfr FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY C1. ASS B CLASS FREQUENCY (PERCErff) = 1.69 I SPEED N NNE NE ENE E ESE SE WIND DIRECTION FROM SSE S SSW SW WSW W WNW NW NtM VRBL '!VTAL 1 1 I MPH CALM (1)
.(2) 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0
.00 0
.00 0
.00
.00
.00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 I - C-3 (1)
(2) 0
.00 1.40
.00 2
,02 0
.00
.00 0
.00 1.40
.00 2
.02
.00
.00 0 0
.00
.00 0
.00
.00
.00 0
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00 2
1
.70
.01 6
1
.70
.01 15 0
.00
.00 0
6 4.20
.07 73 l
4 4-7 18 2 1 3 0 5 6 7 4 0 1 1 2 f (1) 12.59 1.40. .70 2.10 .00 3.50 4.20 4.90 2.80 .00 .70 .70 1.40 1.40 4.20 10.49 .00 $1.05 I
.02 .02 .07 .18 .00 .86 )
I- (2) 8-12
.21 11
.02 0
.01 0
.04 0
.00 1
.06 0
.07 0
.08 5
.05 1
.00 1
.01 0
.01 2 5 1 9 16 0 $2 l (1) 7.69 .00 .00 .00 .70 .00 .00 3.50 .70 .70 .00 1.40 3.50 .70 6.29 11.19 .00 36.36
.02 .06 .01 .11 .19 .00 .62 I
(2) .13 .00 .00 .00 .01 .00 .00 .06 .01 .01 .00 0 0 0 0 0 0 5 3 3 0 11 13-18 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.50 2.10 2.10 .00 7.69 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .06 ,04 .04 .00 .13 i 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 4 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .70 .00 .00 .00 .70 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M 24 0 0 0 0 0
.00
.00 I (1) .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 j I
35 0 143 I ALL SPEEDS 29 4 1 3 3 5 6 12 5 1 1 3 7 9 19 (1) 20.28 2.80 .70 2.10 2.10 3.50 4.20 8.39 3.50 .70 .70 2.10 4.90 6.29 13.29 24.48 .00 100.00 I
.04 .04 .06 .07 .14 .06 .01 .01 .04 .08 .11 .22 .41 .00 1.69 I
(2) .34 .05 .01 1)*PERCDff OF ALL OOOD OBSERVATIONS FOR THIS PAGE ((21sPERCDff CF ALL OOOD OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL 70 .95 MPH) I l I I I I ~
g i I t 1 I L J TABLE 6C l VERMOtTP YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOIlff FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS C CLASS ThEQUENCY (PERCE!ft) e 2.76 I l l SPEED N HNE NE ENE E ESE SE WIND DIRECTION FROM SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL I ) [ MPH CALM (1) (2)
.00
.00 0
.00
.00 0 0
.00
.00
.00
.00 0 0
.00
.00
.00 0
.00
.00 0
.00 0
.00
.00
.00
.00 0
.00 0
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00
.00
.00 0 0
.00
.00 .00 0
.00 0
.00
.00 I C-3 (1)
(2)
.86
.02 2
.43
.01 1
2.15
.06 5
.00
.00 0 1
.43
.01
.43
.01 1 0
.00 1.29
.00 3
.04
.00
.00 0
.43
.01 1
.43
.01 1
.00 0
.00 0
.00
.00 0
.00
.00
.00
.00 0
18 2
.86
.02 29
,00
.00 0
0 17 7.30
.20 136 4-7 24 4 1 2 8 6 to 8 4 3 1 4 8 6 (1) 10.30 1.72 .43 .86 3.43 2.56 4.29 3.43 1.72 1.29 .43 1,72 3.43 2.58 7.73 12.45 .00 58.37 (2) .28 .05 .01 .02 .09 .07 .12 .09 .05 .04 .01 .05 .09 .07 .21 .34 .00 1.61 8-12 18 2 0 0 0 1 0 3 6 3 2 5 5 5 7 12 0 69 (1) 7.73 .86 .00 .00 .00 .43 .00 1.29 2.58 1.29 .86 2.15 2.15 2.15 3.00 5.15 .00 29.61 (2) .21 .02 .00 .00 .00 .01 .00 .04 .07 .04 .02 .06 .06 .06 .08 .14 .00 .82 13-18 0 0 0 0 0 0 6 0 0 0 0 0 2 4 4 0 0 10 (1) .00 .00 .00 .00 .00 .00 .00 .00 ,0 .00 .00 .00 .86 1.72 1.72 .00 .00 4.29
. (2) .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .02 .05 .05 .00 .00 .12 19-24 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 .43 .00 .00 .00 .43 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .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 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 44 1 6 2 9 8 10 14 10 7 4 9 15 16 29 43 0 233 (1) 18.88 3.00 2.58 .86 3.86 3.43 4.29 6.01 4.29 3.00 1,72 3.86 6.44 6.87 12.45 18.45 .00 100.00 (2) .52 .08 .07 .02 .11 .09 .12 .17 .12 .08 .05 .11 .18 .19 .34 .51 .00 2.76 (1)sPERCENT OF ALL GOOD OBSERVATIONS FOR TAIS PAGE (2)=FERCElff OF ALL 000D OBSERVATIONS FOR THIS PERIOD Cs CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) i l-I L
I l
)
l l I
q sf t 4 TABLE 6D VERN0KF YANKEE JAN 97
- DEC 97 NETEOROLOOICAL DATA JOINT FREQUENCY DISTRIBt/f!ON 135.0 FT WIND DATA ' STABILITY CLASS D ' CLASS FREQUENCY (PERCENT) = 38.552 A
WIND DIRECTION FRON L SPEED N NNE NE ENE E ESE SE SSE 'S- SSW SW WSW W NNW NW NNW VRSL TOTAL NPH
- CALM '0 2 0 0 0 1 1 0 0 0 -0 -1 0 0 0 2 0 7 (1). . 00 - .06 .00 .00 .00 '. 0 3 .03 .00 .00 .00 .00 .03. .00 .00 .00 .06 ..00 .21 J- <(2), .00 ' . .02 .00 ,00 .00 . 01 ' .01 .00 .00 .00 .00 .01 .00 .00 .00 .02 .00 .08 C-3 91 68 - 49 59 54 42 56 48 38 31 24 18 26 31 54 95 0 784 (1) 2.79' 2.09 1.50 1.81 1.66 1.29 1.72 1.47 1.17 .95 .74 .55 .80 .95 1.66 2.92 .00 24.06 r- (2) 1.08 80 .58 70 - 64 .50 .66 .57 .45 .37- .28 ,21 .31 .37 .64 1.12 .00 9.28 4-1 216 63 '40 52 67- 78 68 119 142 ' 47 -
35 31 -79 58 90 246 0 1431.
.00 43.92 (1) 16.63 1.93 -1.23 1.60 2,06 2.39 .2.09 3.65 4.36 1.44 1.07 .95 2.42 1.78 2.76 7.!5 16.93
- (2) 2.56 .75 .47 .62 .79 .92 ,80 1,41 1,68 .56 .41 .37 .93 .69 1.06 2.91 .00 c 8-12 ~ 142 16 8 2 9 8 1 18 109 19 21 22 78 163 88 109 0 813-
-. (1) 4.36 .49 .25 .06 28 .25- '.03 .55 3.35 .58 .64 .68 2.39 5.00 2.70 3.35 .00 24.95 (2)- 1.68- .19 .09 .02 .11 .09 .01 .21' 1.29 .22 .25 .26 .92 1.93 1.04 1.29 .00 9.62 13-18 16 0 0 0 0 0 0 0 17 2 0 2 23 90 40 11 0 201 (1) .49. .00' .00 .00 ,00 - .00 .00 .00 .52 .06 .00 .06 .71 2.76 1.23 .34 .00 6.17
.27 1.06 .47 .11 .00 2.38 (2) .19 .00 .00 .00 '. 0 0 .00 .00 .00 .20 .02 .00 .02
.19-24 1 0 0 0 0 0 0 0 0 0 1 0 1 11 8 0 0 22 (1) .03 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .03 .34 .25 00 .00 .68 c.-
~
(2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 .33 .09 .00 .00 .26 l V QT 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 .
I- 'ALL SPEEDS 466 '149 97 113 130 125 126 185 306 99 81 74 207 353 280 463 0 3258
-(1) 14.30 4.57' 2.98 3.47 3.99 3.96 3.87 5.68 9.39 3.04 2.49 2.27 6.35 10.83 8.59 14.21 .00 100.00 L' (2) -5.51 1,76 1.15 1.34 1.54 1.53 1.49 2.19 3.62 1.17 .96 .88 2.45 4.18 3.31 5.48 .00 38.55 (llePERCEKF OF ALL 0000 OBSERVATIONS FOR 'lif!S PAOE
,. (2)sFERCEKr OF ALL OOOD OBSERVATIONS FOR THIS PERIOD
,'- , Ce CAIJi (WIND SPEED LESS THAN OR EQUAL '1V .95 MPH) 1 s
I i' {, - ' Q- .
- ..n. .
r .. ..x.. ...,2 i . . , , . . . . . . , . , , , . . , , . . , , . . _ _. ..
~
I I TABLE 65 h I VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUT10N 35.0 FT WIND DATA. STABILITY CLASS E CLASS FREQUENCY (PERCENT)
- 35.94 WIND DIRECTION FROM SPEED 'N t@iE NE ENE E ESE SE SSE S SSW SW WSW W WNW IM NNW VRBL TOTAL I
MPH CALM 1 0 3 6 1 3 1 0 1 2 5 3 4 0 1 2 0 33 (1) .03 .00 .10 .20 .03 .10 .03 .00 .03 .07 .1(_ .10 .13 .00 .03 .07 .00 1.09 (2) .01 .00 .04 .07 .01 .04 .01 .00 .01 .02 .06 .04 .05 .00 .01 .02 .00 .39 C-3 110 46 36 29 44 48 56 98 98 114 172 145 160 141 163 167 0 1627 (1) 3.62 1.51 1.19 .95 1.45 1.58 1.84 3.23 3.23 3.75 5.66 4.77 5.27 4.64 5.37 5.50 .00 53.57 (2) 1.30 .54 .43 .34 .52 .57 .66 1.16 1.16 1.35 2.04 1.72 1.89 1.67 1.93 1.98 .00 19.25 4-7 85 11 5 6 16 29 38 95 85 29 33 34 83 121 158 189 0 1016 (1) 2.80 .76 .16 .20 .53 .95 1.25 3.13 2.80 .95 1.09 1.12 2.73 3.98 5.20 6.19 .00 33.45 (2) 1.01 .13 .06 .07 .19 .34 .45 1.12 1.01 .34 .39 .40 .98 1.43 1.87 2.22 .00 12.02 8-12 24 3 0 0 3 4 1 10 57 20 1 2 30 65 57 26 0 303 (1) .79 .10 .00 ,00 .10 .13 .03 .33 1.88 .66 .03 .07 .99 2.14 1.88 .86 00 9.98 (2) .28 .04 .00 .00 .04 .05 .01 .12 .67 .24 .01 .02 .35 .77 .67 .31 .00 3.59 13-18 6 0 0 0 1 0 0 0 14 5 1 1 3 8 12 1 0 52 (1) .20 .00 .00 .00 .03 .00 .00 .00 .46 .16 .03 .03 .10 .26 .40 .03 .00 1,71 (2) .07 .00 .00 .00 .01 .00 .00 .00 .17 .06 .01 .01 .04 .09 .14 .01 .00 .62 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 4 1 0 0 5 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .13 .03 .00 .00 .16 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .01 .00 .00 .06 0T 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1
.00 .00 .03 I
4 (1) .C0 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 ALL SPEEDS 226 60 44 41 65 84 96 203 255 170 212 185 280 340 392 384 0 3037 (1) 7.44. 1.98 1.45 1.35 2,14 2.77 3.16 6.68 8.40 5.60 6.98 6.09 9.22 11.20 12.91 12.64 .00 100.00 (2) 2.67 .71 .52 .49 .77 .99 1.14 2.40 3.02 2.01 2.51 2.19 3.31 4.02 4.64 4.54 .00 35.94 I ( 1)* PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3)aPENCE!T!' OF ALL 000D OBSERVATIONS FOR 'IHIS PERIOD Ce CALM (WIND SPEFD LESS THAN OR EQUAL TO .95 MPH) f l I I I i I I: i 1 j
l E F I l t TABLE 6F VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 15.87 I SPEED N HNE NE ENE E ESE SE WIND DIRECTION FROM SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL I l } MPH CALM (1) (2)
.07 1
.01 0
.00
.00
.00
.00 0
.07
.01 1 0
.00
.00 0
.00
.00 1
.07
.01
.00
.00 0 0
.00
.00 0
.00
.00
.07
.01 1
.07
.01 1 1
.07
.01 0
.00
.00
.07
.01 1
.00 0
.00 0
.00
.00 .08 7
.52 C-3 32 13 19 16 8 14 20 26 68 115 276 200 153 110 70 56 0 1196 (1) 2.39 .97 1.42 1.19 .60 1.04 1.49 1.94 5.07 8.58 20.58 14.91 11.41 8.20 5.22 4.18 .00 89.19 (2) .38 .15 .22 .19 .09 .17 .24 .31 .80 1.36 3.27 2.37 1.81 1.30 .83 .66 .00 14.15 4-7 1 2 0 1 1 3 2 2 15 15 19 9 18 13 22 14 0 137 (1) .07 .15 .00 .07 .07 .22 .15 .15 1.12 1.12 1.42 .6' 1.34 .97 1.64 1.04 .00 10.22 (2) .01 .02 .00 .01 .01 .C4 .02 .02 .18 .18 .22 .11 .21 .15 .26 .17 .00 1.62 3-12 0 0 0 0 0 0 0' O 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .07 .00 .00 .00 .07 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .01 .00 .00 .00 .01 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 p (1) .00
.00
.0J
.00
.00
.00
.00
.00
.00
.00
.00
.00 .00
.00
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) 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 l
0 L d M 24 0 0 0 0 0 0 0
.00 0 0
.00 .00 0
.00 0 0
.00 .00 0
.00 0
.00 0
.00 0 0
.00 .00 (1) .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 70 1341 I ALL 8PEEDS 34 15 19 18 9
.67 17 23 28 83 130 296 210 172 124 2 27 1.72 2.09 6.19 9.69 22.07 15.66 12.83 9.25 6.94 5.22 93 0
.00 100.00 L <25 (2) 2.54 2.22 2.42 2.24
.40 .18 .22 .21 .11 .20 .27 .33 .98 1.54 3.50 2.48 2.04 1,47 1.10 .83 .00 15.87 (1)ePERCENT OF ALL 000D OBSERVATIONS FOR THIS PAGE (21sPERCENT OF ALL 000D OBSERVATIONS FOR THIS PERIOD Cm CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH)
E E E D E - _
I g TABLE 6G t VERM0fff '."ANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOIttr FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY C1J.SS O CLASS FREQUENCY (PEPJCD17) = 3.33 WIND DIRECTION FROM EPEED N NNE NE ENE E ESE SE SSE S ssw SW WSW W WNW NW NNW VRBL TOTAL HPH CAW 0 0 0 0 0 0 0 0 0 0 1 0 1 1 1 0 0 4 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .36 .00 36 .36 .36 .00 .00 1.42 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 .01 .01 .00 .00 .05 I C-3 (1) (2) 4-7 12 4.27 1.78
.34 0
.06 5
0
.71
.02 2
0 4
.05 1
5
.06 0
.06 5
0 4
.05 0
12
.14 0
16
.19 1
28
.33 4
52
.62 10 28
.33 1
32 0 18 1,42 1.78 1.78 1.42 4.27 5.69 9.96 18.51 9.96 11.39 6.41 4.63 4.98
.38 .21 5
13
.15 3
14
.17 1
.00
.00 0.
0 250 88.97 2.96 26
.00 .36 .00 9.25 I
(1) .00 .00 .00 .36 .00 .00 .00 .00 .36 1.42 3.56 .36 1.78 1.07 (2) .00 .00 .00 .01 .00 .00 .00 .00 .01 .05 .12 .01 .00 .06 .04 .01 .00 .31 P-12 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 .36 .00 .36 (2) .00 .00 00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 I 13-18 (1) (2)
.00
.00 0
.00
.00 0
.00
.00 0 0
.00
.00
.00
.00 0
.00
.00 0 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
.00 0
.00 0
.00
.00 l
0 0 0 0 0 0 0 0 0 0 0 0 lb24 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .uo .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 C (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 p) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l ALI, SPEEDS 12 5 2 5 5 5 4 12 17 32 63 29 33 24 17 16 0 281 (1) 4.27 1.78 .71 1.78 1.78 1.78 1.42 4.27 6.05 11.39 22.42 10.32 11.74 8.54 6.05 5.69 .00 100.00 l (2) .14 .06 .02 .06 .06 .06 .05 .14 .20 .38 .75 .34 .39 .28 .20 .19 .00 3.33 : 1 (1)=PERCDrf OF ALL 000D OBSERVATIONS FOR THIS PAGE I I (3)= PERCENT OF ALL GOOD OBSERVATIONS I"OR THIS PERIOD C= CALM (WIND SPEED LESS 'INAN OR EQUAL TO .95 MPH) i 1 l Ei I: . j A
I l l 1 l I 1 li TABLE 6H i VERMOtrf YANKEF. JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION ) 35.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH I CALW (1) (2) 2
.02
.02
.02 2
.02
.04
.04 3 7
.08
.03 1
.01
.01
.05
.05 4 3
.04
.04 0
.00
.00
.01
.01 1 2
.02
.02 7
.08
.08 .06 5
.06 6
.07
.07
.01
.01 1 3
.04
.04 4
.05
.05 0
.00
.00 51
.60
.60 C-3 249 135 113 108 116 112 137 189 221 289 527 391 371 300 302 335 0 3895 (1) 2.95 1.60 1.34 1.28 1.37 1.33 1,62 2.24 2.62 3.42 6.24 4.63 4.39 3.55 3.57 3.96 .00 46.09 (2) 2.95 1.60 1.34 1.28 1.37 1.33 1.62 2.24 2.62 3.42 6.24 4.63 4.39 3.55 3.57 3.96 .00 46.09 4-7 357 82 48 67 94 126 129 237 252 99 99 81 190 206 309 514 0 2890 (1) 4.22 .97 .57 .79 1.11 1.49 1.53 2.P0 2.98 1.17 1.17 .96 2.25 2.44 3.66 6.08 .00 34.20 (2) 4.22 .97 .57 .79 1.11 1.49 1.53 2.80 2.98 1.17 1.17 .96 2.25 2.44 3.66 6.08 .00 34.20 0-12 207 21 8 2 13 13 2 36 176 43 24 32 121 242 168 194 0 1302 (1) 2.45 .25 .09 .02 .15 .15 .02 .43 2,08 .51 .28 .38 1.43 2.86 1.99 2.30 .00 15.41 (2) 2.45 .25 .09 .02 .15 .15 .02 .43 2,08 .51 .26 .38 1.43 2.86 1.99 2.30 .00 15.41
- 283 1)-18 23 0 0 0 1 0 0 0 32 7 1 3 28 109 64 15 0 (1) .27 .00 .00 .00 .01 .00 .00 .00 .38 .08 .01 .04 .33 1.29 .76 .18 .00 3.35 (2) .27 .00 .00 .00 .01 .00 .00 .00 .38 .08 .01 04 .33 1.29 .76 .18 .00 3.35 19-24 1 0 0 0 0 0 0 0 0 0 1 0 1 17 9 0 0 29 (1) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 .20 .11 .00 .00 .34 (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 .20 .11 .00 .00 .34 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 C (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01
.00 .01
'I (2) ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 QLL SPEEDS 839 240 172 184 225 255 271 462 682 440 659 512 717 876 855 1062 0 8451 (1) 9.93 2.84 2.04 2.18 2.66 3.02 3.21 5.47 8.07 5.21 7.80 6.06 8.48 10.37 10.12 12.57 .00 100.00 (2) 9.93 2.84 2.C1 2.18 2.66 3.02 3.21 5.47 8.07 5.21 7.80 6.06 8.48 10.37 10.12 12.57 .00 100.00 I ( 1)mPERCElf? OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3)ePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Cm CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) I LI . I -
~ APPENDIX A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Supplemental Information I for 1996 Facility: Vermont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporation ) 1A. TECHNICAL SPECIFICATION LIMITS - DOSE AND DOSE RATE ) i Technical Soecification and Category Limit
- a. Noble Gases i
3.8.E.1 Total body dose rate 500 mrem /yr I 3.8.E.1 3.8.F.1 Skin dose rate Gamma air dose 3000 mrem /yr 5 mrad in a quarter 10 mrad in a year l 3.8.F.1 Gamma air dose 3.8.F.1 Beta air dose 10 mrad in a quarter 3.8.F.1 Beta air dose 20 mrad in a year
- b. Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Ha_1_f-lives Greater Than 8 Da_ys 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 I 3.8.B.1 3.8.B.1 Organ dose Organ dose 5 mrem in a quarter 10 mrem in a year y urun A-1 i
_w
i j l APPENDIX A ' (Continued) EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i 2A. TECHNICAL SPECIFICATION LIMITS - CONCENTRATION Technical SDecification and Category Limit
- a. Noble Gases No ECL Limits l b. Ipdine-131. lodine-133. Tritium and Radionuclides in Particulate Form Mi'ch Half-lives Greater Than 8 Days No ECL Limits W c. Liauids 3.8.A.1 Total fraction of ECL excluding noble gases (10CFR20, Appendix B, I Table 2, Column 2): 11.0E+01 3.8.A.1 Total noble gas concentration: 12E-04 pCi/cc
- 3. AVERAGE ENERGY Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.
Ie a. Average gamma energy: Not Applicable
- b. Average beta energy: Not Applicable
- 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition,
- a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity I . released from the plant stack. .Because release rates are normally below the detection limit of these monitors, periodic grab samples unus A-2 I
1_ . _ _
p l a l " APPENDIX A (Continued) { EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT p are taken and analyzed for the gaseous isotopes present. These are-L- used to calculate the individual isotopic releases indicated in , Table 18 and the totals of Table 1A. The error involved in these steps may be approximately 123 percent. {
- b. Iodines
[ Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and b cartridges are norme11y removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these 7 steps may be approximately 118 percent. L
- 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 L
Grab samples from the plant stack are taken monthly through a cold r trap collection device and analyzed for tritium. The error involved L . in this sample is approximately il5 percent. i
- 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. 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. h The u,*ror involved in this sample is approximately il5 percent. {7
.. neun A3 Ei - - _ __ _ _ .
u APPENDIX A (Continued) ( EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT r The LLDs for gross alpha, Sr-89, and Sr-90 were not met for the L March 1997 composite sample due to insufficient sample size. The LLD for Sr-89 was not met for the May 1997 composite sample due to F delay in counting. L
- f. Liauid Effluents L 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 r- activity (mC1) released, concentration ( Ci/ml) of gross L radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release E to the Connecticut River.
u 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 L' 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 I
- a. Liouid
[ There were no routine liquid batch releases during the reporting period.
- b. Gaseous l l
- 1) Number of batch releases: 6 )
i
- 2) Total time period for batch releases: 1.21E+02 hours
- 3) Maximum time period for a batch release: 1.12E+02 hours
( 4) 5) Average time oeriod for batch releases: 2.02E+01 hours Minimum time period for a batch release: 8.33E-02 hours ] umn A-4 g- -__ - __ ___
L I APPENDIX A. (Continued) [ EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT r The gaseous releases from burning waste oil are treated as either U batch or continuous releases based on the total hours of burning in a calendar quarter. E ' 6. ABNORMAL RELEASES [ a. Liauid There were no nonroutine liquid releases during the reporting 7 L period. r b. Gaseous L There were no nonroutine gaseous releases (measured) during the [ reporting period. One condition was identified during the third quarter that involved ! small cracks in the Radwaste Building Ventilation exhaust duct L downstream of the HEPA filters. Design ventilation exhaust from p-this area is directed to the plant vent stack for discharge to the L environment. The air loss from the cracks was estimated to be much less than 1% of the design flow. The design flow of the duct is r 12.200 cfm. Gas samples from both Radwaste Building air and from 4 the ventilation duct system showed no detectable activity down to l the Technical Specification gas sample LLD (IE-04 Ci/cc). Smear j samples from the ductwork at the edge of the cracks also showed no detectable particulate activity. A review of air monitoring records in the Radwaste Building upstream of the HEPA filters confirmed that there was no history of routine airborne activity in the building that could have lead to any significant dose to the public without having been detected and quantified at the main plant stack. b
' unin A-5 E --- - -- _- _ _
L APPENDIX B { LIQUID HOLDUP T/NKS 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.D.1. a description of the events leading to this condition is required in the next Annual Effluent Release Report per Technical Specification 6.7.C.1. { Response: The limits of Technical Specification 3.8.D.1 were not exceeded l during this reporting period. f l. l l N c l I l I 1 k
- .1
APPENDIX C RADI0 ACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION Reauirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3.9.1. an explanation in the next Annual Effluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7.C.1. Response: Since the requirements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid effluent I monitoring instrumentation were met for this reporting period, no response is required. I
- I I
I I I anun . C-1
- I
APPENDIX D , I RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION Recuirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Ta'le o 3.9.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Annual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.1. Response: Since the requirements of Technical Specification Table 3.9.2 I governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required. I i I O ll I
;I I
ll _ 01 I
c i APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Reauirement: The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.9.C. With milk samples no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3, Technical Specification 6.7.C.1 requires the following to be included in the next Annual Effluent Release Report: (1) identify the 1 cause(s) of the sample (s) no longer being available, (2) identify the new location (s) for obtaining available replacement samples I l and (3) include revised ODCM figure (s) and table (s) reflecting the new location (s). , I Response: No changes were needed in the milk sampling locations specified in Technical Specification Table 3.9.3 due to sample unavailability during the reporting year. I I I. I-I urun E-1
APPENDIX F I LAND USE CENSUS f I Recuirement: A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a J i location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in l f Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Annual Effluent Release Report. ResDonse: The Land Use Census was completed in the third quarter of 1997. No locations yielded a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.I. i I i 4 I l
- I i
1 I < l I I urun F-1
y jn u P APPENDIX G F= PROCESS CONTROL PROGRAM L Reauirement: Technical' Specification 6.12.A.1 requires that licensee initiated [. changes to the Process Control Program (PCP) be submitted to the Commission.in the Annual Radioactive Effluent Release Report for r- -the period in which the change (s).was made. L Response: The following changes were made to the Process Control Program (PCP) and issued as Revision 6 during this reporting period. Title Page: Added " Tech. Spec.:6.12(A)(2)" next to PORC and VP/M00 titles. Added this note after all signature blocks: " Verify or obtain current revision from Document Control prior to L submitting this document for future revision." E Section 2: Added the quantification of "<200 mR/hr @ 30 cm" for low activity cartridge filter elements. Section 3: Revised the definition for a noncorrosive [ solution. A solution is not considered corrosive if the pH is greater than 4.0 and less c L than-10.0. i F. Section 6: Added a reference to AP-0619. L ,_ Section 7: Added a reference to AP-0619. 4 p Section 8: Added a reference to AP-0619. (. Page 4: Added the Procedure AP-0619. " Chemical Control / Hazard Communication Program." In this revision. Vermont Yankee added criteria for determining if a solution is corrosive. This change compiles with the Barnwell Site Criteria. Other changes in this revision were {- administrative in nature. Therefore, the changes implemented.in Revision'6 did not reduce the overall conformance of the ) (T dewatered spent resins / filter media waste product to existing j criteria for solid waste shipments _and disposal. [a urun G-1 bi _ . _
I APPENDIX G
- (Continued)
PROCESS CONTROL PROGRAM I The revised Process Control Program is attached. The revised Process Control Program documents the fact that the change has been reviewed by PORC and approved by the Manager of Operations (M00). I I I I -I ji I I I I I I urun G-2 I
J VERMONT YANKEE NUCLEAR POWER CORPORATION PROCESS CONTROL PROGRAM REV6 3/21/97
~
r L -- r L 9 [. [ . Submitted I/ d K~ .; Y
hadiation ProMon Manager l L- c 1 !
I Approved Q.twcr.dfa O 97-029 ' I Sc. 6.12(A)(2))
. N kA L A h eld T7 i
Approved . y, g,w v - Approved J kTfl?- VP, MOO (Tecl. Spec.'6.12(A)(2)) l { [ .. l l Verify or obtain current revision from Document Control prior to
.l<* ' submitting this document for future revision. (ER 96-255)
E -- __
[ VERMONT YANKEE NUCLEAR POWER CORPORATION PROCESS CONTROL PROGRAM (
Introduction:
b The Vermont Yankee Nuclear Power Corporation Process Control Program (PCP) describes the administrative and technical controls on the radioactive waste systems which provide assurance that Vermont Yankee meets federal shipping and burial site ~ { requirements. The PCP compiles with Technical Specification 6.12 by describing process parameters, controls, tests, sampling and analysis to ensure compliance with 10 CFR 20,10 CFR 71, and 10 CFR 81 Energy,49 CFR 172-173 Transportation, state, and burial site regulation requirements. 1.0 solidification Vermont Yankee Nuclear Power Corporation does not routinely solidify liquid waste. If the use of solidification to dispose of any liquid waste is required,it will be done by an outside vendor under the vendor's PCP. The vendor PCP will be reviewed and [ approved by the Plant Health Physicist, the Radiation Protection Manager, PORC and VP, MOO prior to implementation. This review is to identify that there is sufficient supporting documentation of the vendor's PCP to give assurance thatthe final product will meet all requirements for transport and burial, and that sufficient procedural [ controls exist to assure safe operations. [TS 4.8.N] [ 2.0 Cartridae Filter Elements
-l Low activity cartridge filter elements (< 200 mR/hr @ 30cm) will be air dried (~ 24hr or as determined by the Radwaste Supervisor) and handled as dry active waste. Filters
[ d determined to be above the dose limitations per 49CFR,.will be placed in casks and shipped for disposal. [ 3.0 Resins l i Normal operations produce radioactive waste in the form of depleted resins. These [- . resins are processed in the burial container using a rapid dewatering system (RDS-1000) manufactured by Chem-Nuclear Systems, Inc. [OP 2153] The system has been tested, by Chem-Nuclear, for certification 8n meeting the Bamwell Site Criteria and disposal requirement for free standing liquid. These tests are described in Chem-Nuclear's Topical Report on the RDS-1000 Radioactive Waste {. - Dewatering System. In addition, to comply with the statement, "Any liquids present in waste packages shall be non-corrosive with respect to'the container," Vermont Yankee tested the pH of various resin mixtures used by the plant in solution with {- water. The range was found to be 4.2 - 8.4. A solution la not considered corrosive
'l if the pH is greater than 4.0 and less than 10.0.
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I l A resin sample is taken from each liner prior to shipment. The sample is counted to i determine the activity and waste classification. Class A resins that exceed 1.0 yCl/cc I of isotopes with greater than 5 year half-lives and all Class B And C resins will be disposed of in an approved High Integrity Container (HIC). Vendor supplied or temporary methods of processing resins may be used in lieu of the above process provided that the vendor or temporary process meets the requirements I of quality described above and does not conflict with accepted burial criteria or safety requirements. Such methods will be reviewed and approved by the Plant Health Physicist and the Radiation Protection Manager prior to implementation. 4.0 Filter Liners During refueling outages and normal operation, liquid radwaste processing may require j
- use of a decanting filter on the condensate phase separators. A floating suction is used to decant the water and resin into a filter liner. Filtered water is pumped from the I liner. The liner is dewatered in accordance with OP 2511 (MOOID9409-03) such that the burial site criterion for free-standing water is met. A resin sample is taken from the ilner and analyzed to determine the activity and waste classification.
s 5.0 Drv Active Waste (DAW) DAW is compacted, as practical, or shipped to a vendor that sorts the material for I, processing or tecycling. A!! DAW is examined before being compacted or shipped. Any liquids or items found that would compromise the integrity of the package are removed and separated as specified by procedure. (OP 25121 Containers used for I, DAW shipments meet the criteria of 49 CFR 173.425a. or b. "No leakage of radioactive material," as specified in 49 CFR 173.425.b.1 will be met provided that no radioactive materials in quantitles equal to or exceeding those specified in 49 CFR I 173.443 are detected on the external surfaces of the package at any time during shipment. l Id 6.0 Chelatino Acents ; In order to comply with 10 CFR 20 Appendix F, chelating agents are c'ontrolled by the Il plant chemistry department using procedure AP 0620 and AP 0619. 1 7.0 Exolosive Waste I No waste capable of detonation or of explosive decomposition or reaction wiii be . disposed as per 10 CFR 61.56(a)(4). Refer to MSDS via AP 0620 along with f I ll AP 0619. 8.0 Toxic Weste I No waste capable of generating toxic gases, vapors, or fumes will be disposed as per 10 CFR 61.56(a)(5). Refer to MSDS via AP 0620 along with AP 0619. Il 2
h ., 9.0 Pvrochoric Waste . No waste that is pyrophoric will be disposed as per 10 CFft 61'.56(a)(6). Refer to { MSDS via AP 0620. ~
' L 10.0 Hlah intaarity cs..u:r.ars (Nical Vermont Yankee Nuclear Power Corporation has contracted with various suppliers of p approved HICs. ' South Carolina has approved PCPs for HICs used by Vermont Yankee.
L. . Any HIC Vermont Yankee may choose to use at some future time, will meet all applicable requirements. b 11.0 Wasta class patermination Along with an approved outside laboratory, Vermont Yankee periodically performs laboratory analysis on all wasta streams to determine the activity of radionuclides h- listed in Tables 1 and 2 of 10 CFR 61. Correladon analysis verifies that the relative concentration of each radionuclide, with respect to the overall activity in a given 4, Vermont Yankee waste stream, remains constant over time. A set of scaling factors [ ,, is determined which allows the activity of 10 CFR 61 radionuclides to be estimated using the results of gamma spectronistric analysis or direct gamma dose rate measurements. { For resin wastes, analysis is performed on samples of each source of resin comprising 4 the contents of a burial container. Scaling factors are appIIed to the activity of [ " radionuclides identified by gamma spectrometry analysis to determine the activity of those radionuclides which are not detected in the gamma spectrum. " For DAW, dose rate-to-curie conversion calculations are performed to determine the total activity present in a container. Scaling factors are applied to the container's total curie content to determine the activity of individual radionuclides. [ a Specific procedures for determining 10 CFR 61 scaling f' actors are contained in OP 2527, " Sampling and Analysis for Radwaste Classification." Once the, activity of each [. radionuclide in a burial container is estimated, the waste classification is derived using l methods required by 10 CFR 61. Specific procedures for waste class determination l are contained in AP 0504, " Shipment of Radioactive Material." .1 l V- ,
, 12.0 Mixed Wasta (c
C! No mixed waste will be disposed as per 10 CFR 61.56(a)(8) unless properly treated.
)
Refer to MSDS via AP 0620. b , 1 [: [l 3 [L [~ .
E PROCEDURES WHICH IMPLEMENT THE PCP
- 1. . AP 0504 Shipment of Radioactive Materials
- 2. OP 2511 Radweste Cask / Liner Handling
- 3. OP 2527 Sampling and Analysis for Radweste Classification r- . - 4. ' OP 2151 - Liquid Radweste 5.- . OP 2153 Solid Radwaste .
. 6. - AP 0620 Chemical Material Use
- 7. OP 2512 Radwasta Drum, Box and Sealand Handling L Chemical Control / Hazard Communication Program l 8.- . AP 0619
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APPENDIX H j I 0FF-SITE DOSE CALCULATION MANUAL 1 l j Reauirement: Technical Specification 6.13. A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made effective. Resoonse: Revision 21 to the Off-Site Dose Calculation Manual was made I during this reporting period. l I The major changes included in Revision 21 to the ODCH are: l (1) A new Appendix F has been added. The NRC granted the plant permission for the on-site disposal of slightly contaminated silt in response to our request filed under j 10CFR20,2002. Currently, there is an estimated 14,000 cubic feet of cooling tower silt. This silt contains low levels of Co-60 and Cs-137. Dose assessments for this material show that it can be disposed of on-site in the same manner as that already approved for contaminated I i septic waste. The permission granted by the NRC requires ! that the NRC Safety Evaluation for silt disposal be added to the plant's ODCM prior to the implementation of any disposal operation. This amendment to the ODCM fulfills a that requirement. Appendix F also includes a copy of our l 10CFR20.2002 request and dose analysis that supports this j on-site disposal. ] (2) A new Appendix G has also been added. This appendix contains a listing of the MPC values which originally was part of the 10CFR20 before the change to ECL values. MPC I values have been used and accepted as licensing conditions for the control of radioactive materials in situations other than those directly covered by the requirements of the regulations. One example is the on-site disposal of septic waste (ODCM Appendix B) which uses MPC values as one of the criteria for determining acceptability for land spreading of contaminated material. With the final , publication of the revised 10CFR20.1001-20.2401, the I original MPC tables of the old 10CFR20 are no longer in print. As such, Appendix G to the ODCM was added to astun H-1
APPENDIX H E (Continued) g 0FF-SITE DOSE CALCULATION MANUAL-provide a reference source for the concentration limits for those conditions that still refer to them. I (3) The NRC allows the instantaneous radioactive liquid effluent concentrations discharged to unrestricted areas to be ten times the ECL values listed in Appendix B to the new 10CFR20.1001-20.2401. This change, allowing the effluent concentrations to be ten times the ECL values, reflects that the ECL numbers are actually annual average concentrations, not instantaneous limits. By allowing the instantaneous concentrations in effluents to be ten times the absolute values of the ECL provides flexibility in plant discharge operations. This is equivalent, on a dose basis, to the old MPC limits that were also applied on an instantaneous basis by Technical Specifications. Over a year, the average ECL values must not be exceeded. Changes to the ODCM to establish the method for calculating l acceptable liquid effluent concentrations and monitor alarm setpoints for batch release pathways have been made. For continuous discharge pathways, i.e., the service water, the alarm setpoint has been k t the same despite changes to allow higher effluent concentration (a factor of ten). This is done to insure that potential leaks into a normally clean system will set off a monitor alarm when the annual average requirements of 10CFR20 are exceeded. (4) Minor editorial changes have been added to reflect: (a) that the Chemistry Manager is now assigned responsibility for the implementation o'f septic waste disposal in place of the Senior Environmental Program Manager, (b) a correction of a typographical error on Page 5-15 that changes 500 rem /yr to 500 mrem /yr, and (c) consideration of instrument uncertainty when effluent monitor alarm setpoints are calculated using plant I procedures. l I The above changes are provided in response to NRC licensing conditions. The dose methodologies have not been changed. Changes to the setpoint methodology, which include an additional I mun H-2 I
L APPENDIX H (Continued) 0FF-SITE DOSE CALCULATION MANUAL factor of- ten on the instantaneous ECL limit, reflect the permission granted by the NRC and restore the dose basis (i.e.. 500 mrem /yr) for the setpoint criteria. It is therefore determined that these changes will maintain the level of radioactive effluent control required by 10CFR20.1302, 40CFR190, 10CFR50.36a. and Appendix I to 10CFR Part 50. These changes do j not adversely impact the accuracy or reliability of the effluent
' dose or setpoint calculations.
The revised pages from Revision 21 to the ODCM are attached. l 1 4 i mrun H-3
L E g Table 10 Dose Impact Due to Single (14.000ft3) Silt Sorcadine. ; Radiation Exposure Individual / Organ Disposal Site Access Controlled by VYNPS 0.064 arem/yr adult /whole body (max, exposed individual 0.219 mrem /yr max. child / bone in 1995) Uncontrolled by'VYNPS 0.224 mrem /yr adult /whole body L 0.393 mrem /yr max. child / bone-(inadvertent intruder after license termination) r Table 10 shows that the application of the silt material initially collected (14,000 cubic feet) accounts for about '27 percent of the maximum individual organ dose durin5 the control period as compared to the scenario of contin-ued periodic silt spreading over the balance of the operating license. This illustrates that dose impacts from the material currently collected are well below the acceptance criteria of limiting the dose from any two acre plot to no more than 1 mrem / year during the control period, and 5 mrem / year after { termination of the license, and is expected to remain below the a'cceptance criteria throughout plant life. If une,xpected buildup of radioactivity in future silt clean out operations were to ' occur, the option for use of alter-nate disposal plots remains available to ensure that the impact from any single two acre plot stays within the acceptance criteria. Also of interest 'are derived dose conversion factors which provide a means of ensuring that septic and silt disposal operations remain within the pre-t scribed. radiological guidelines noted above. The critical organ (worst case), and.whole body dose factors for all' pathways on a per acre bases are
V' . L-J given on Table 11 for periods during Vermont Yankee control of the disposal cite, and on Table 12 for post control periods associated with the inadvert-cnt intruder scenario. The dose conversion factors have been expanded to include other potential radionuclide beyond the original five that were cadressed in Reference 1. This provides a means to assess other nuclides if future disposal operations identify additional radionuclides not previously ebserved. The development of these additional nuclide dose conversion factors utilize the same modeling and pathway assumptions as used to derive the factors for the original five radionuclide identified in septic waste. The models for these site and pathway specific dose factors are those in Regulatory Gaide 1.109 (Reference 2), and are described in detail in Attach-ment II to Reference 1. L, e L-r l e I l L 1 l
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0 [ ' Table 11 All-Pathway Critical Orman / W ole Body Dose Conversion Factors Durine Vermont Yankee Control of Discosal Sites Nuclide. Individual / Organ Critical Organ Wole Body , Dose. Factor Dose Factor b (arem/yr per uCi/ acre) I Cr-51 . Teen / Lung 1.14E-05 5.76E-06 Mn-54 Adult /GI-LLI 3.75E-04 1.93E-04 l' Fe-55 Child / Bone 6.45E-06 1.06E-06 Fe-59: Teen / Lung 4.61E-04 2.13E-04 Co-58 Teen / lung 3.27E-04 2.01E-04 { ~ Co-60 -Teen / Lung i 7.17E-04 5.31E-04 Zn-65. Child / Liver 1.64E-02 1.03E-02 Zr-95 . Teen / lung 4.47E 04 1.34E-04 Ag110m. Teen /GI-LLI 1.32E-02 5.24E-04 Sb-124 Teen / Lung 8.34E-04 3.54E-04 (: 1.28E-03
- Cs-134' Child / Liver 3.18E-03 LCs-137' ; Child / Bone -
2.66E-03. 7.02E-04
-Ce-141; < Teen / Lung 1.54E-04 1.50E-05 Ce-144 Teen / Lung' '6.00E-04' 2.44E-05 ;
l [y ' [; .
h , N 1 (; i h Table 12 AL_1-Pathway Critical Ornan / Whole Body Dose Conversion Factors . Post Vermont Yankee Control- of Discosal Sites (Inadvertent Intruder)' 1
- Nuclide Individual / Organ Critical Organ Whole Body Dose Factor Dose Factor
[ (arem/yr per uC1/ acre) t Cr Teen / Lung 5.89E-04 1.19E-04 Mn-54 Teen /Inng 1.02E-02 3.12E-03
- Fa-55. Teen / Inns 3.50E-04 2.27E-05 h
Fa-59 Teen / Lung 2.55E 4.43E-03
- 3.72E-03 Cs-58 Teen / lung 1.59E-02
{: Co-60 Teen /Inng - 3.19E-02 9.09E-03 Zn-65 Child / Liver 1.89E-02 1.25E-02
- T
~Zr-95 Teen / lung 2.93E-02 2.99E-03 q Ag110m . Teen / Lung 3.59E-02 9.53E-03 J Sb-124 Teen / Lung 4.73E-02 7.04E-03
{ g. C3-134 1.21E-02 9.36E-03 Child / Liver: i C3-137_- . Child / Bone 6.98E-03 3.85E-03 C2-141- Teen / Lung 1.21E-02 3.44E-04 Co-144- - Teen /Inng. 5.00E-023 1.52E-03 1 t'l J y E
u, , r. c [ L, F U 5.0 RADIATION PROTECTION: 'I i h .The disposal operation of silt material- from the cooling tower basins will ! follow the. applicable Vermont Yankee procedures to maintain doses as low as l reasonable achievable and within the specific dose.. criteria as previously cpproved for septic. waste disposal (Reference 1). l U !
6.0 CONCIllSIONS
e l. " Silt collected from the cooling tower basins is an earthen type material that is.similar in characteristics to septic waste residual solids with re-spect to the radiological pathway behavior and modeling, and can be disposed l through on site land spreading on the.same disposal plots as previously evaluated and approved for septic waste disposal. The radiological assess-ment of low level contaminated silt shows that the projected dose from the ] r cn site. periodic spreading of this material will have no significant dose l t1 impact to members of the public and can be maintained below the approved dose limitations already in-place for septic waste.
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7.0 REFERENCES
r L: l (1) Vermont Yankee ODCM, Appendix B; " Approval of Criteria for Disposal of-Slightly Contaminated Septic Waste On-Site at Vermont Yankee". (Included { NRC approval letter dated August 30, 1989, VY request for approval date June ! p 28, 1989_with Attachments I and II) l L J
- (2) USNRC Regulatory Guide 1.109, Rev. 1; " Calculation of Annual Doses to Man'from Routine Releases of Reactor Effluents.for the Purpose of Evaluating 1
[ Compliance with 10 CFR Part 50, Appendix I", date October 1977. I L (3) NUREC/CR-5512, Vol. 1, " Residual Radioactive Contamination From Decom-nissioning", Final Report, date October, 1992. .j L. r e f b f [ t [ [; [! [i file: 'vsilt. mss > [ . - . _ _
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S L. [: 1 4 [ E a r L- ) c-l E-t APPENDIX G r MAXIMUM PERMISSIBLE CONCENTRATIONS (MPCs1 L i IN AIR AND WATER AB0VE NATURAL BACKGROUND [.. TAKEN FROM 10CFR20.1 TO 20.602. APPENDIX B 2 u I i [' l [: [1 [: [ [L
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. APPENDIX G L .
With the. implementation of the revised Part 20 to Title 10 of the Code of
. -Federal Regulations (10CFR20.1001-20.2401). the Maximum Pev.nissible
. Concentrations-(MPCs) that were part of the old.10CFR20 were replaced by a new Appendix B to 10CFR20 for the limits that apply to effluents released to-
.; unrestricted areas. However. MPC values were also used and accepted as
{ licensing conditions for the control of radioactive materials in situations other than those directly covered by the-requirements of the regulations. One
; example 'is the on-site disposal of septic waste which used the MPC values as
(? - one criteria of acceptability for land spreading. Appendix B to the ODCM
-references 10CFR20.1-20.601 Appendix B HPCs as. concentration criteria for this
- b. disposal option.
With the final publication of the revised 10CFR20.1001-20.2401, the original MPC tables of. the old 10CFR20 are no longer in print. As such, this appendix { to the.0DCM is added to provide a reference source for the MPC values .) contained in the original Appendix B to 10CFR20.1-20.601 for those conditions { that'.still refer to these requirements, r L
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[ [ e [ [L [i l Revision 21: Ih t 91' OR /14 /U '
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I Appendix G 1 I Maximum Permissible Concentrations (MPC's) (From 10CFR20.1 to 20.602, Appendix B) I I I APPENDtX G TO $9 20.1-20.602--CONCENTRATIONS IN AtR AND WATER AsovE NATURAL BACKGROUND (See footnotes at end of Appenduc 8) isotope 8 Tabte Table 11 j Element (atomic number) Col.1-M Col.2- g i_g Col. 2-( Gml) g g) (pGml) gy ,,) Actinium (89) Ac 227 S 2 x 10"8 6 x 10'* 8 x 10 * " 2 x 10-* i 3 x 10-" 9 x 10-a g xio- u 3 x 10" A3 228 S 8 x 10*
- 3 x 10-8 3 x 10" 9 x 10" I 2 x 10" 3 x 10-8 6 x 10-" 9 x10" I
Amerknum (95) -. Am 241 S 6 x 10-" 1 x 10** 2 x to-es 4 x 10*
- 1 1 x 10*" 8 x 10" 4 x 10-" 3 x 10-8 Am 242m _ . S 6 x10* " 1 x10" 2 x10-u 4xio-.
I 3 x 10-" 3 x 10*
- 9x10"8 9 x 10*
- Am 242 S 4 x 10** 4 x10-8 1 x10" 1x10" l 5x10-8 4 x 10-s 2 x107' 1 x10" Am 243 S 6 x 10-" 1 x10" 2 x 10-" 4 x10-*
1 1 x10*" 8 x10-* 4 x10-" 3 x10-8 Am 244 S 4 x 10" 1 x10-8 1 x 10-' 5 x10-8 1 2x10" 1 x10-' 8 x 10-' 5x10-8 Antimony Sb 199 S 2 x 10-' 8 x 10-* 6 x 10-' 3 x 10-* 1 1 x 10-' 8 x 10** 5 x 10*
- 3 x10**
Sb 124 S 2x10" 7x10" 5 x 10-' 2 x 10*
- I 2 x10-8 7 x10" 7 x 10* " 2x 10" 4
Sb 125 S 5 x 10-' 3 x 10** 2 x 10-* 1 x10" l 3 x 10-' 3x10-8 9 x10* " 1 x10" l Argon (16) A 37 Sub8 6 x 10- 3 x go" j A 41 Sub 2 x 10** 4 x 10** l Arsenic (33) As 73 S 2 x 10-* 1 x10-8 7 x10" 5x10" l I 4 x 10-' 1 x10-8 1 x 10-* 5x10" l As 74 S 3 x10-' 2 x10-s 4 x10" 5x10-8 i 1 1 x 10-' 2 x10-' 4 x10*
- 5x10-s As 76 S 1 x 10-' 6 x10-* 4 x10-' 2x10-8 1 1 x109 6 x 10" 3 x 10-' 2 x 10*
- As 77 S 5 x 10*' 2x10-s 2x10-8 8 x10-8 I 4 x 10" 2x10*s gxto-a 8 x10" Astatine (85) At 211 S 7 x10" 5 x10-8 2 x10-" 2 x 10-*
I 3 x10" 2x10-8 1 x 10-' 7x10-8 Barium (56) Ba 131 S 1 x10-8 5 x to-8 4 x10"8 2 x10" l 4 X 10-' 5 x10" 1 x10-8 2 x 10-* Ba 140- S 1 x 10" 8x10" 4 x10-' 3 x10-8 f 4 x 10-e 7 x 10" 1 x 10-8 2 x10-8 i
.I Berkelium (97) Ok 249 S i
9 x 10"* 1 x 10" 2 x10-8 2 x 10*
- 3 x 10* "
4 x 10*
- 6 x10" 6 x 10-*
I Ok 250 S 1 x 10" 6 x 10' 8 5 x to" 2x to" j 1 x 10" 4 x 10" 2 x 10*
- t 6 x 10-Berynom (4) . Be?- S 6 x 10*
- 5 x 10" 2 x 10" 2 x 10" ;
i 1 x 10-* 5 x 10-8 4 x 10*
- 2x10" l Brsmuth (83),- Be 206 S 2 x 10" 1 x 10" 6 x 10" 4 x 10' 1 1 x 10* ' 1x10" 5 x 10" 4 x 10" Bi 207 ... _. S 2 x 10" 2x10" 6 x 10" 6 x 10" I 1 x 10" 2 x 10*
- 5 x 10* = 6 x 10" 8 210.. . . _ . . S 6 x 10" 1 x 10" 2 x 10*
- 4 x 10" i
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r: L-1 ~. 1 c I L- Nuclear Regulatory Commission Pt. 20 [(( 20.1 '20.602], App. B APPENOfx B TO ff 20.1-20.602-CONCENTRATIONS IN AIR AND WATEn ABOVE NATURAL - f' BACKGROUNO-Continued L (See footnotes at end of Appendus 8) Isotope
- Table i Table in r
Element (atomic numbed g , _g Col. 2- Col.1-M Col.' 2- ; vCamo ,TL SCo o utA ; I 6 x 10" t w 10" 2 x 10"* 4 x 10" 3 Bi212- S 1 x 10" is to 3xt0" 4 x 10" ) i 2 x 10" i x 10 *
- 7 x 10" 4 x 10*
- Bromine (35) .-- Br 82. -
S 1 x 10" e x to" 4 x 10" 3 x 10** '. f I 2 x 10" 1 x 10- 8 6 x 10" 4 x 10" l L Cadmsum (48) Cd 109 S 5 x 10" 5 x 10'8 2 x 10" 2 x 10" ; I 7 x 10" 5 x 10- 8 3 x 10" 2 x 10" i Cd 115m S 4 x 10*
- 7x10" 1 x 10" 3 x 10-8 j p I 4 x 10-e 7 x 10-
- 1 x 10" 3 x 10" ]
Cd 115 $ 2 x 10-8 1x10" 8 x 10*
- 3 x 10" L 4 2 x 10" 1 x 10-8 6 x 10" 4 x 10" Caldum (20) Ca 45 S 3 x10" 3 x 10" 1 x 10" 9 x 10" I 1 x 10" 5x10" 4 x 10" 2x10"
[ Ca 47 S I 2 x 10" 2 x10" 1 x 10" 1 x 10" 6 x 10" 6 x 10" 5 x 10" 3 x 10"
' Califomium (98). _... Cf 245 S 2 x 10"8 1 x 10" 5 x 10"* 4 x to" I 1 x 10* " 7 x 10*
- 3 x 10-" 2 x 10" Cf 250 S 5 x 10-" 4x10" 2 x )0"8 1 x 10-8 h 1 1 x 10* " 7x10" 3 x 10* " 3 x 10*
- L Cf 251 S 2 x 10"* 1x10" 6 x 10"* 4 x 10-8 8 1 x 10-" 8x10" 3 x 10* " 3 x10" Cf 252 S 6x10"8 2 x10" 2 x 10"8 7 x 10**
F I 3 x 10-" 2 x10" 1 x 10-" 7 x 10*
- h i Cf 253. S I
8x10-" 8 x 10* " 4 x10-8 4 x10* 8 3 x 10-" 3 x 10* " 1 x10" 1 x10" Cf 254 S 5 x 10-" 4 x 10*
- 2 x10"8 1 x10-8 I 5 x 10"8 4 x10*
- 2 x 10"8 1 x10" h
L Cert *1 (6) C 14 S 4 x10" 2x10*8 1 x 10" 8 x 10-* (CO ) Sub 5 x10-8 . 1 x 10-* Cerium (56) Ce 141 S 4 x10-' 3 x10-8 2 x10" 9 x10-8
- 4 1 2 x 10-' 3 x 10-8 5 x10" 9 x 10" c' Ce 143 - S 3 x 10-' 1 x10'8 9 x 10" 4 x10"
[ Ce 144 l S 2 x 10-' 1 x10-8 1 x 10-8 3 x 10" 7 x10" 3 x 10-" 4 x 10-8 1 x 10-8 8 6 x 10 3 x 10" 2 x 10*
- 1 x10" Cesium (55) Cs 131 S 1 x 10-8 7x10-8 4 x 10*' 2x10-8 l 3 x10-8 3 x 10-8 1 x 10" 9 x 10"
[" Cs 134m S 4 x10-8 2x10" 1 x10-8 6 x10" 1 6 x10-* 3 x 10*
- 2 x 10*' 1 x10*
- 4 Cs 134 S 4 x10" 3 x 10" 1 x 10" 9x10-* j t 1 x10*
- 1 x 10-8 4 x 10-" 4 x10-s j
[. ' Cs135 S 5 x 10-' 3 x10-8 2 x10" 1 x 10" 1 l 9 x10-e yxto- 3xto-e 2 x 10" ) Cs 136 S 4 x10-' 2x 10-8 1 x10" 9 x10-8 ! 1 2 x 10-' 2x10-8 6 x 10-* 6 x10-8 l Cs 137 S 6 x 10-* 4 x10" 2 x 10-8
- 2x10-8
[.~ ~.. > I 1 x 10-* 1 x10-s 5 x 10-" 4 x10-8 ' Oiiodne (17) _. . CI36 S 4 x 10" 2 x10.s txgo-e ex,o-e - 1 2 x10-* 2 x 10-8 8 x 10"* 6 x10-8 Cl 36 .. S 3 x 10*
- 1 x 10- 8 9 x 10-* 4x10" I 2 x 10-* 1 x 10-e 7 x 10" 4 x 10"
[ Chromaum (24) - Cr $1 - S 1 x 10" 5 x 10" 4 x to" 2 x to" 1 2 x 10-* 5 x 10" 8 x 10" 2 x 10" Coball(27). '
. Co 57 .. S 3 x 10-* 2 x 10* 8 1 x 10" 5x10" I 2 x 10-' 1x10" 6 x 10*
- 4 x 10* *
[2 CoS8m 8 x10" - 3 x 10" - S 2 x 10-8 6 x 10" . 3 x 10" 2 x 10" I 9 x 10-8 16 x 10" Co S6 ..- S 8 x 10- 8 4 x 10" 3 x 10" 1x10" I 5 x 10" 3x10" 2 x 10" 9 x 10" Co 60.. .; S 3 x 10' 1 x 10" 1 x t0" 5 x 10" [i. ' l 9 x 10*
- 1 x 10* 8 3 x 10- a 3 x 10" Copper (2W . Cu 64 '.. S 2 x 10" 1 x 10" 7 x t0' 3 x 10 *
- 1 1 x 10-* . 2 x 10*
- rbnum #GM' Cm 'S ti t e v e n- w ^ *s6 xen-io".I i ' 4 xe10"
. m s' m y Sn= t
a 1 W u. m t. Pt. 20 [s@ 20.1-20.602], App.' B 10 CFR Ch. I (1-1-93 Edition) ,- APPENDIX 8 TO ff 20.1-20.602-CONCENTRATIONS IN AIR AND WATER AeovE NATURAL i BACKGROUND-Continued (See footnotes at end of Appendix B) m I
, isotope ' Table i Table si L Cat 2- Cet2-oement (awne numba) u,a coi.i- ,
bW"II (pC mi) 4Ce% 4 c$,) r i - i 2 x 10-" 7 x 10" 6 x 10"8 Cm 243 S 6 x 10"8 1 x 10" 2 x 10- u 2
$ xx to-10". 1 1 1 x 10-" 7 x 10" 3 x 10-" 2 x 10- 8 ,j Cm 244 S 9 x10* '8 . 2 x 10" 3 x 10-" 7 x 10*
- u I 1 x 10* " 8 x 10" 8 3 x 10" Cm 245 $ 5 x 10-" 1 x 10" 3 2 xx1010". a 4 xgo-. ;
1 1 x 10* " 8 x 10-* 4 x 10* '8 3 x 10" r- Cm 246 S 5 x 10-$8 1 x 10" 2 x 10"8 4 x 10"
- I 1 x 10-" 8 x 10" 4x10*" 3 x 10" ]
L Cm 247 S 5 x 10*" 1 x 10" 2 x 10-" 4 x 10-* j i 1 x 10-" 6 x 10" 4 x 10*'8 2 x 10-8 Cm 248 S 6 x 10": 1 x 10" 2 x 10-" 4 x 10" F i 1 x 10- 4 x 10" 4 x 10- u gxto-a Cm 249 S 1 x 10*
- 6 x 10* 8 4 x 10" 2 x 10- 8 .
I 1 x 10*
- 6 x 10" 4 x 10- ' 2 x 10" Oysprosium (66) - Dy 165 S 3 x 10-* 1 x 10" 9 x to-* 4 x to" y 1 2 x10-8 1 x 10-8 7 x 10" 4 x 10" l Dy 166 S 2 x10" 1 x 10-8 8 x 10-' 4 x 10" 1 L- 1 2x10" 1 x10-8 7 x 10" 4 x 10" Onsleimum (99) Es 253 S 8 x 10-" 7 x t o-* 3 x 10-" 2 x 10-*
I 6 x 10-" ' 7 x 10-
- 2x10 " 2x 10-8 P- Es 254m. S 5x10-8 5 x10" 2x10 " 2 x 10-*
l 1 6 x10-' 5 x 10** 2 x 10-" 2 x10-8 Es 254 S 2 x 10- ** 4 x10" 6 x10"8 1 x 10-8 1 1 x10-# 4 x 10*
- 4 x10"8 1 x10-8 )
Es 255 S 5 x 10-" 8 x 10-* 2 x 10"8 3 x 10-* i [' i' 4 x10-" 8x10" 1 x 10-" 3 x10-8 L: Erbium (68) Er169 S 6 x10-' 3 x10*8 2 x 10*
- 9 x10-8 1 4 x 10-' 3 x 10-8 1 x 10-* 9 x 10-8 4
Er 171 S 7 x 10-' 3 x 10-8 2 x10" 1 x 10"
-- I 6 x 10-' 3 x 10-8 2 x 10-* 1 x 10-*
- l. Europium (63) Eu 152 - S 4 x 10-' 2 x 10*
- 1 x10-8 6 x 10" j (T/2=9.2 in) . I 3 x 10-' 2x to" 1 x10-8 6 x to-*
Eu 152 S 1 x10-a 2x 10* 8 4 x 10-" 8 x 10" (T/2=13 yrs) i 2x10 8 2 x 10*
- 6 x to-" 8x10 8 f Eu 154 S 4x10-* e x 10-* 1 x 10-" 2 x to-8 L_ . I 7x10-' 6 x10-* 2 x 10-" 2 x 10*
- Eu 155 S 9x10-8 6x10-8 3 x 10-* 2 x 10" l 7 x 10*
- 6 x10-8 3 x 10-' 2 x 10-* i Femeum (100) Fm 254- S 6 x10-8 4 x to-8 . 2 x10-8 1xto"
- I 7 x10-8 4 x10" 2 x10" 1 x 10" Fm 255 S 2x10-8 1 x10-8 6 x 10-" 3 x10-8 1 1 x10-s gxio-s 4 x to-" 3 x10-8 Fm 256 S 3 x 10-' 3 x10-8 1 x 10-" 9 x 10-'
f I 2 x 10-' 3x10" 6 x 10-" 9 x 10" L Fluonne (9) F 18 S 5 x10-* 2 x10-e 2 x10" 8 x10" l 3 x10-8 1 x 10-8 9 x 10-8 5 x 10" hea4ium(64) . Gd 153 S' 2 x 10-' 6 x 10-: 8 x 10-' ' 2x to-* I 9 x 10*
- 6 x 10-8 3 x 10" 2 x 10" Gd 159 $ 5 x 10-' 2 x 10-8 2 x 10-
- 8 x 10- 8 I 4 x 10* ? 2 x10" 1 x 10" 8 x 10"
. Gallium (31)- . .. Ga 72 S 2 x 10" 1 x to-
- 8xto" 4 x 10" I 2 x 10-' 1 x 10- 8 6 x 10*
- 4x10" i Germanium (32) . Ge 71... .. . . S 1 x 10-* $ x 10" 4 x 10" 2 x 10" I 6 x 10-* 5 x 10- 8 2 x 10" 2 x 10" -
2 Gold (79) Au 196 ..... ... S 1 x 10-* 5 x 10" 4 x 10" 2 x 10- *
- 1. 6 x 10" 4 x 10- 8 2 x 10" 1 x 10" Au 198. S- 3 x 10" 2 x 10" 1 x 10" 5 x 10" 2 x 10 ' 5 x 10" 1 1 x 10 8 8 x 10- *.
~
Hf 161 -
=
S'
- n:::
d x 10- *' 2 x 10 *
- 1 x 10-
- i
>c:::
7 x 10-
- HaftWm (72L. , ., ... a. .
,,w . I i v ..n.. ..e., a, * .no
b Nuclear Regulatory Commission Pt. 20 [ss 20.1-20.602], App. B APPENDIX B TO (( 20.1-20.602-CONCENTRATIONS IN AIR AND WATER A00VE NATURAL BACKGROUNO-Continued { (See footnotes at end of Append.: a) isotope
- Table i Table it Element (atome number) Col.1-Air Col. 2- Col.1-Air Col. 2-( Ci/ml) [Ci)M (pCdml) [Cj*h l I 2x 10" 9 x 10' 6 x 10" 3 x 10" Hydrogen (l) H3 S 5 x 10*
- 1 x 10" 2 x 10" 3 x 10" l 5 x 10** 1 x 10" 3xJ0" Sub 2 x 10* * .
2 4 xx10 10".s Indium (49) _ in 113m S 8 x to-* 4 x to" 3 x 10* ' 1 x to- [.. i 7 x 10*
- 4 x 10" 2 x 10" 4 x 10" 1 x 10-s in 114m S 1 x 10" 5 x 10" 2 x 10" j i 2 x 10*
- 5x10" 7 x 10* " 2 x 10" 1 In 115m S 2 x 10*
- 1 x 10** 8 x 10*
- 4 x 10" l 2 x 10*
- 1 x 10*
- 6 x 10 *
- 4 x 10"
[. in 115_ S 2 x 10-8 3 x 10-8 9 x to" 9 x 10" 1 3 x 10*
- 3 x 10-8 1 x 10*
- 9 x 10* *
. todine f53) I125. S S x 10" 4 x to" 8 x to"" 2 x 10" t 2 x 10* ' 6 x 10*
- 6 x 10-* 2 x 10* *
[-' i126 S 8 x to" 5 x 10" 9 x 10* " 3 x 10* ' 1 3 x 10" 3 x 10*
- 1 x 10" 9 x 10" j l129 S 2 x 10" 1 x 10" 2 x 10* H 6 x 10" !
l 7 x 10" 6 x 10* 8 2 x 10" 2 x 10" t131 S 9 x 10" 6 x 10" 1 x 10"* 3 x10" [? I 3 x 10*' 2x10" 1 x 10" 6x 10-8 gxion 1122 S 2 x10" 2x10-s 3xtoo i 9 x10" 5 x10" 3 x 10** 2 x10" j 1133 S 3 x10-e 2x10" 4 x 10-" 1 x10"
- - 1 2 x10" 1 x 10*
- 7 x 10*
- 4 x10"
~~
l134 S 5x10" 4 x10* 8 6 x 10" 2x10" 1 3 x10-* 2 x10*: yxjo-s 6 x10" 1135 S 1 x10" 7 x10" 1 x 10*
- 4 x 10**
I 4 x 10*' 2 x10-s gxyo-e 7x 10-8 [.. Iridium (77) ir190 S 1 x 10-* 6 x10-8 4 x 10" 2x 10" 1 4 x 10-' 5 x 10-s gxio-e 2 x10" 4 tr192 S 1 x10" 1 x10-8 4 x 10" 4 x 10" l 3 x10** 1 x10*8 9 x 10"* 4 x10 s [ it194 S i 2 x 10*' 2 x 10* ' 1 x10's 9 x 10-* exto-o 5 x 10*
- 3x ton 3 x 10*
- 1ron (26)- Fe 55 S 9 x10*' 2 x to" 3 x 10-
- 8 x 10" i 1 x 10** 7 x 10*
- 3 x10-e 2 x10-8 Fe 59 S 1 x 10*' 2x10-s sxto-o ex 3on
[- 1 5 x10" 2x10*s 2x10" 5 x 10" Kryptori(38) Kr85m Sub 6 x10-8 1 x10" Kr 85 Sub 1 x 10*8 3 x t o-' ; Kr27 Sub 1 x 10-* 2 x 10-* i Kr 88__ Sub 1 x10-8 2 x 10* * [ '. Lanthanum (57) La 140 S 2 x 10-' 7 x10" 5 x 10"* 2 x 10*
- 1 1 x10" 7x10" 4 x10" 2x10" Leed (82) . Pb 203 S 3 x10-8 1 x10-s gxgon 4xion 4 x 10" 1 2 x10-8 1 x10-8 6 x 10* *
[. . : Pb 210 S 1 x 10*" 4 x 10-8 4 x 10-" 1 x 10-' 1 2 x 10* " 5x10- ex3ons 2 x10" Pb 212 S 2 x 10-* 6 x10-* 6 x 10* ** 2x10" I 2 x 10*
- 5 x 10-* 7 x 10* " 2x10"
[. Lutetium (71) Lu 177 . S 8 6 x 10* ' 5 x 10* ' 3 x to-8
- 3 x 10-8 2 x 10*
- 2 x 10*
- 1xto" 1 x 10" Manganese (25) - ~ Mn 52 -. S 2 x 10" 1 x 10" 7 x 10" 3 x 10" i 1 x 10* ' 9 x 10*
- 5 x 10*
- 3 x 10
; Mn54 . S- 4 x 10*
- 4 x 10-8 1 x 10" 1 x 10" a$ l 4 x 10*
- 3 x 10" 1 x 10" 1 x 10" Mn56. S- 8 x 10" 4 x 10*
- 3 x 10" 1x10" 1 5 x 10" 3 x 10-s 2 x 10*
- 1 x 10" Meicury (80) - ... Hg 197m S 7 x 10" 6 x 10' 8 3 x 10 * * . 2 x to'*
2 x 10" 8 x 10" 3 x 10"
~ ~
l 5 x 10- 8
- Hg 19 7 ..... ..- S 1 x 10 ' 9 x 10" 4 x 10 *
- 3 x 10 *
- I -- 3 x 10** 1 x 10* ' 9 x 10 * * . 5 x 10
- Hg 203.. S 7 x 10* * . 5 x 10 c . .. .... . . . " . . ' 2 x 10".
, .e , 2 x .n
. 8 0'. '.
I I-Pf, 20 [@ 20.1--20.602), App. B 10 CFR Ch.1 (1-1-93 Edition) APPENDIX 8 TO kl 20.1-20.602-CONCENTRATf0NS IN AIR AND WATER ABOVE NATURAL BACKGROUNO-Continued (See footnotes at end of Append.s B) isotope ' Table i Table it Element (atome number) gy4 Col. 2- Col.14 Col 2-Oscilmn z,$)Ry (pCumQ j')Q Molytsdenum (42) Mo 99 S 7 x 10" 5 x 10- 8 3 x to-* 2 x 10" I Neodymsum (60) _ ._, Nd 14 4 . . Nd 147 1 S 1 S 2 x 10" 8 x 10-" 3 x 10"* 4 x 10" 1 x 10' 2 x 10- 8 2 x 10-8 2 x 10* 8 7 x 10" 3 x 10"8 1 x 10-" 1 x 10" 4 x 10" ' 7 x 10" 8 x 10' 6 x 10" i 2 x 10-' 2 x 10.s 8 x 10- 8 6 x 10" Nd 149 S 2 x 10*
- 8 x 10-8 6 x 10*
- 3 x 10" 1 1 x 10-* 8 x 10- 8 5 x 10" 3 x 10" Neptunium (93) Np 237 S 4 x 10-" 9 x10" 1 x 10 " 3 x 10" 1 1 x 10".* 9 x 10" 4 x 10* " 3 x 10" Np 239-- S 8 x 10-' 4 x 10" 3 x10" 1 x 10" l 7 x 10" 4 x 10- s 2 x 10" 1 x 10" Nickel (28) - - - . . . Ni 59. S 5 x 10-' 6 x 10-8 2 x 10" 2 x 10" 1 8 x 10" 6x 10" 3 x 10" 2 x 10" I Ni 63. . _.. S 6 x 10-8 8 x 10-* 2 x 10" 3 x 10*
- 1 3 x 10" 2 x 10" 1 x 10 8 7 x 10" Ni65 S 9 x 10-' 4 x 10-8 3 x 10-8 1 x 10" i 5 x 10-8 3 x 10" 2 x 10" 1x10" Nb 93m S 1 x 10*
- 1 x10" 4 x 10" 4 x to" I
Niobeum (Columbaum) (41) . l 2 x 10-' 1 x10-8 5 x 10" 4 x 10" Nb 95 S 5 x 10-' 3 x 10-8 2 x 10-8 1 x10" i 1 x 10-' 3 x10* 8 3 x 10" 1 x 10" Nb 97 S 6 x10-8 3 x 10-8 2x.u* 9 x 10" I I 5 x 10-8 3 x10* 8 2x10" 9x10" Osmium U6) Os 185 S 5 x 10-' 2 x10-8 2x to" 7 x10" 2 x 10" 2 x 10-* 7 x 10-* 1 5 x 10-8 Os 191m S 2x10-8 7 x 10* 8 6 x 10" 3 x 10-8 1 9 x 10-* 7 x 10" 3 x 10-' 2 x 10-8 I4 Os 191 Os 1E S 1 S 1 1 x 10-8 4 x 10-' 4 x 10" 3 x 10" 5x10" 5 x10-8 2 x 10-8 2 x 10*
- 4 x 10" 1 x 10-*
1 x 10" 9 x 10" 2 x 10" 2 x10" 6 x 10-s 5 x 10" 5x 10" 3 x 10" I Palladium (46) Pd 103 S 1 x10-* 1 x 10" l 7x10" 8 x 10-8 3 x10-8 3 x10" Pd 109 S 6 x10" 3 x 10- 2 x 10" 9 x 10-8 1 4 x 10-' 2 x 10-8 1 x 10-8 7 x 10-8 Phosphorus (15) P 32 S 7 x10-8 5x10" 2 x 10-' 2 x 10" I Platimr? p8) Pt 191 Pt 193m 1 S l S 8 x10-8 8 x 10-' 6 x 10-' 7 x10-8 7 x 10-* 4 x 10-8 3 x 10-s 3 x 10-8 3 x 10" 3 x 10" 2 x10" 2 x 10" 2 x 10-8 1 x 10" 1 x 10" 1 x 10-8 5 x10-8 3 x10" 2 x 10-' 1 x 10- 8 I I Pt193 S 1 x10-8 3 x 10-8 4 x10" 9 x 10" 1 3 x 10-' 5 x 10-8 1 x to-8 2 x10- 8 Pt 197m .., . _ S 6 x 10-* 3 x 10" 2 x 10" 1 x 10" 1 5 x10-8 3 x10-8 2 x 10-' 9 x 10-* I Plutonium (94) Pt 197-Pu 238. S 1 S I 8 x 10-' 6 x 10-' 2 x to-" 3 x 10-" 4 x 10-8 3 x 10-* 1x10" 8 x 10" 3 x 10" 2 x 10" 7 x 10"* 1x10-" 1 x 10" 1 x
- 0*
- 5 x to-*
3 x 10- 8 Pu 239_ S 2 x 10* " 1 x 10' 6 x 10-" 5 x 10" I l 4 X 10-" 8 x 10" 1 x 10 " 3 x 10" Pu 240.. S 2 x 10-" 1x10" 6 x 10-" 5 x 10" i I 4 x 10* " 8 x 10" tx10-" 3 x 10-
- Pu 241.- S 9 x 10-" 7 x 10" 3 x 10-" 2 x to" I 1 4 x 10" . 4 x 10" 1 x 10" 1. 10 "
Pu 242 S 2x10*" 1 x 10" 6x 10-" 5 x 10" l 4 x 10* " 9 x 10" 1 x 10 * " 3x10-* Pu 243 S 2 x 10
- 1 x 10" 6 x 10" 3 x 10' I '. 2 x 10' 1 x 10-' B y 10" ! 3 s 10
- Pu 244 S 2 x 10- " '1 x 10' 6 x 10- " 2 ._10'*
l i ! 3 x 10-" 3 x 10 * , 1 x 10- " ! tsto-',
, t' - , . ,
I N.
.q 1
r.- . L I
~ Nudear Regulatory Commission Pt. 20 [ ) 20.1-20.602 }, App. 8 APPENDIX 8 TO {f 20.1-20.602-CONCENTRATIONS IN AIR ANO WATER ABOVE NATURAL
{ BACKGROUNO---Continued (See footnotes at end of Append. 8) isotope
- Table a f atse at E6ement (atomic riumber) gg Col 2- g% Cos 2-a (pCs/ml) (pCa/ml) g *)*h.
Potassium (l'9) . K4 2. . .. S 2 x 10" 9 x 10' 7x10" + 3 x 10' 1 1 x 10' 6 x 10" 4 x 10" 2 x 10"
' Preseodymiuro (59) - Pr 142.. S 2 x 10" 9 x 10" 7 x 10" 3 x 10" 3 x 10 "
1 2 x 10* ' 9 x 10 8 5 x 10 *
- Pr 143... . . _ , S 3 x 10" 1 x 10" 1 x 10" 5 x 10"
[.- I 2 x 10' 1 x 10' 6 x 10" 5 x 10" Promethium (61) Pm 147 5 6 x 10" 6xto a 2 x 10*
- 2 x 10' i 1x10" 6 x 10* ' 3 x 10*
- 2 x 10' Pm 149 5 3 x 10" 1 x 10" 1 x 10" 4x10" i 2 x 10" 1 x 10* 8 8 x 10" 4 x 10"
' Protoactiruum (91) Pa 230 - S 2 x 10" 7 x 10" 6 x 10 * " 2 x 10" l 8 x 10* " 7 x 10* 8 3 x 10 * " 2x10" Pa 231 - S 1 x 10"' 3 x 10" 4 x 10* " 9 x 10' 1 1 x 10'" 8 x 10*
- 4 x 10"8 2 x 10" Pa 233 S 6 x to" 4 x 10" 2 x 10" 1 x 10" 1 2 x 10 * ' 3 x 10" 6 x 10" 1 x 10' Radeum (88). Ra 223 5 2 x 10" 2 x 10" 6 x 10 * " 7 x 10" i 2 x 10"* 1 x 10" C x 10"' 4 x 10" Ra 224- S $ x 10" 7 x 10*
- 2 x 10* " 2 x 10*
- I 7 x 10* " 2 x 10*
- 2 x 10* " 5 x 10**
Ra 226 S 3 x 10* H 4 x 10" 3 x 10"' 3 x 10"
- 1 5 x 10* " 9 x 10*
- 2 x 10* " 3 x 10*
- Ra 228 7 x 10 * " - 8 x10" 2 x 10'" 3 x 10"
_I ' 4 x 10* " 7 x 10" 1x10": 3xio-a Radori(86) Art 220 _ , S 3 x 10" 1 x 10" Rr1222 : 3 x 10*
- _ 3 x 10" -
Rheaum (75) Re 183 S 3 x 10*
- 2 x 10* 8 9 x 10" 6 x 10" i 2 x 10" 8 x 10-8 5 x 10*
- 3 x 10"
[- - Re 186 S 6 x 10*' 3 x 10- 8 2 x 10" 9 x 10" i 2 x 10" 1 x10" 8 x10" 5 x 10*
- 4 Re 187 $ 9 x 10** 7 x 10*
- 3 x 10* ' 3 x 10-8 1
5 x 10" 4 x 10" 2 x 10*
- 2 x 10"
[. ~' Re 188-1 4 x 10" 2 x 10* ' 2 x 10-8 9 x 10*
- 1 x 10*
- 6 x 10*'
6 x 10*
- 3 x 10*
- Rhodium (45) - Rh 103m S 8 x 10" 4 x 10" 3 x 10" 1 x 10" l 6x10 8 3 x 10" 2 x 10*
- 1 x 10"..
[ Rh 105 . S I 8 x 10" 5 x 10-' 4 x 10-s 3 x 10" 3xto-e 2 x 10" ixio 1 x 10" Rubdum (37) . Ab 86 S 3 x10" 2 x10-a y x ion 7x3oo I 7 x10** 7 x 10*
- 2 x 10*
- 2 x 10*
- RO 87 $ 5 x 10" 3 x 10-8 2 x 10** 1 x 10* *
[ Ruthensum (44) ? Ru 97 . I S 7x10" 2 x 10*
- 5 x 10*
- 1 x10" 2 x 10*
- 8 x 10*
- 2 x 10*
- 4 x 10**
1 2 x 10*
- 1 x 10-s 6 x 10*
- 3 x 10* *
. Ru 103 S 5 x to" 2 x 10*
- 2 x 10*
- 8 x10" 1 8 x 10*
- 2 x 10* 8 3 x 10-' 8 x 10*
- Ru t05 S 7x 10" 3 x10" 2 x 10*
- 1 x10" l 5 x 10* ' 3 x 10*
- 2 x 10*
- 1 x 10*
- Ru 106 . S 8 x 10" 4 x 10" 3 x 10" 1 x 10"
~
l 6 x 10*' 3 x 10*
- 2 x 10* " 1 x 10*
- Samarium (62) . . . . - Sm 147 .. S ' 7 x 10* " 2 x 10" 2 x 10"' 6 x 10*
- I 3 x 10"" 2 x 10*
- 9 x 10* " 7 x 10- 5 Sm 151. - . . . S 6x10" t x 10-8 2 x 10" 4 x 10" I 1 x 10* ' 1 x 10*
- 5 x 10*
- 4 x 10*
- 11 Sm 153. S 5 x 10*
- 2x10" 2xto" 8 x 10" J t 4 x 10" 2 x 10" 1 x 10 8 x 10'
' Scand um (21),. .a Sc 46... 5 2 x 10' 1 x 10" 8 x 10" 4 x 10" I 2 x 10" 1 x 10" 8 x 10*
- 4 x 10" Sc 4 L _ S 6 x 10 * ' 3 x 10" 2 x 10" 9x10" 8 5 x 10" 3 ,10** 2r10** 9 x 10" 6 = 10 " 6 x 10" 3 x 10 "
Sc 48 S 2 x 10' ' 1 x to 1' 6 10'* S e 10" 3 x 10'
. . Scien.um 34)
So 75 : S 1 1 x 10-* ! 9 E 10 ' ' 4e10 " 3 x 10'
Pt. 20 [s@ 20.1-20.602],' App. B 10 CFR Ch.1 (1-1-93 Edition) i APPENOlX 8 TO {j 20.1-20.602-CONCENTRATsONS IN AIR ANO WATER ABOVE NATURAL l BACKGROUNO-Cooli:1Ued (See too' notes at end of Appendes 01 i I isotope ' Tadie i Tabte it Element (atomic number) gga Col. 2- Col 1-h Cot 2-( C./mq d'h (pCs/m0 gNn t-l S# cori(14), . Si 31 S 6 x 10** 3 x 10" 2 x 10* ' 9 x 10"
- l l 1x10" 6 x 10-s 3 x 10*
- 2 x 10' Ag 105 S 6 x 10" 3 x 10*
- 2 x 10" 1 x 10"
( S4ver (47) - 3 x 10- 8 1 x 10* *
' I 8 x 10*
- 3 x 10* ' l
' Ag 110m -. S 2 x 10" 9 x 10" 7 x 10" 1 3 x 10" I i 1 x 10" 9 x 10" 3 x 10*
- 3 x 10" S 3 x 10" 1 x 10-s g gou 4 x too Ag 111 .
i 2 x 10" 1 x 10* 8 8 x 10" 4 x 10*
- Na 22_ S 2 x 10" 1 x 10*
- 6 x 10" 4 x 10" l Sosum (11) l l 9 x 10" 9 x 10" 3 x 10* " 3 x 10*
- Na 24_ S 1x10" 6 x 10" 4 x to" 2 x 10" j l
1- 1 x 10" 8 x 10" 5x10" 3 x 10" Sr 85m. S 4 x 10" 2 x 10" 1 x to" 7 x 10' 8 Strontium (38) ~ . . - 7 x 10" I 3 x 10" 2 x 10" 1 x 10*
- l Sr 85 S 2 x 10" 3 x 10- 8 8 x 10" 1 x 10" i i 1 x 10" 5 x 10
- 8 4 x 10" 2 x 10" l l
Sr89. S ~3x10" 3 x 10" 3 x 10* " 3 x 10" l l 4 x 10" 8 x 10" 1x10" 3 x 10" l Sr90 S 1 x 10" 1 x 10" 3 x 10* " 3 x10" , l I 5 x 10" 1 x 10" 2 x 10* " 4x10" St et S 4 x 10* 8 2 x 10-s 2 x 10-8 7 x 10- 8 1 3 x 10-8 1x10-8 9 x 10" 5 x 10*
- l Sr P2 S 4 x 10*' 2 x10" 2 x10" 7 x10"
' I 3 x10" 2 x10" 1 x10" 6 x 10" S 35 - . S 3 x 10~ 8 2 x10" 9 x 10" 6 x 10" Sulfur (18) 3 x10" 1 3 x 10*' 8 x 10-8 9 x10" Tantalum (73) - Ta 182 S 4 x to" 1 x to" 1 x to" 4 x 10-8 1 2 x 10-8 1 x 10" 7 x 10* " 4 x10" Technetium (43) Tc 96m . S 8 x10~8 4 x 10" 3 x10" 1 x10*
- gxgo-s 1 3 x 10-s 3xto-a gg30-4 l
i 4 Tc 96 S 6 x 10" 3 x 10*
- 2 x 10" 1 x 10" I 2 x 10" 1 x 10" 8 x 10*
- 5 x 10" q Tc 97m. . . S 2 x10" 1x10" 8 x10" 4 x 10" i 2 x10" 5x10* 8 5 x 10*' 2 x10" I~ Tc 97 'S 1 x 10" 5x10" 4 x 10" 2 x 10*
- I 3 x10" 2 x 10-s i x ton ex to" f Tc 99m S 4 x 10-s 2 x 10" 1 x 10" 6 x 10-8 I' i 1x10" 8 x10* 8 5x10" 3 x 10*
- Tc 99. . _. .. S 2 x 10-* 1 x10** 7 x10" 3 x10" l 6 x10" 5 x 10-8 2 x 10*' 2 x 10*
- Tellurium (52) Ta 125m . S 4 x10" 5 x 10*
- 1 x 10" 2 x10" 1 1x10" 3 x 10-s 4 x10" 1x10" Te 127m S 1 x10" 2 x 10* 8 5 x 10" 6 x10" 1 I 4 x10" 2 x 10* 8 1 x 10*
- 5 x10" ']
Te 127 S 2 x 10" 8 x10-8 6 x 10" 3 x 10" I 9 x 10" 5x10-8 3 x 10" 2 x 10" Te 129m . S 8 x10" 1 x10" 3 x10" 3 x10" ] 4 3 x 10" 6 x10" 1 x 10" 2 x 10" { Te 129.. S 5 x 10" 2 x 10" 2 x 10" 8 x 10" I 1 4 x 10.e 2 x 10" 1x10" 8x10" Te 131m S 4 x 10" 2 x 10
- 8 1x10" 6xto" i 2 x 10" 1 x 10" 6x1r)" 4 x 10" '
Te 132. S 2 x 10" 9 x 10' 7 x 10" 3 x 10" i 1x10" 6 x 10" 4 x 10*.' 2 x 10" Tb 160. 5 1 x 10" 1 x 10" 3 x 10" 4x10"
. TertWum (65) ~ . . .
l 3 x 10*
- 1 x 10*
- 1 x 10*
- 4 x 10*
- il 200.. S 3 x to" 1 x 10" 9 x 10" 4 x to" Tha!!.um (81) -
i 1 x 10" . 7 x 10" a x 10" 2 x 10*
- Tl 201.. S 2 x 10" 9 x 10" 7 x 10" 3x10" t 9 x 10" 5x10*' 3 x 10" 2 x 10" Tl?o2J 8x10** as10*', 3 x to", i r 10 ' '
S~ 7x10 I 2 x 10' ' 2 x 10* ' > 8 x 10" : 6 x t0*
- 3 w 10* ' I 2 x 10" i ivio**
it 204 ' S - , ri , .~. Eh _ - - . __A.______ -
r . l 2 f P le _ It t i
~
.I; L
Nuclear Regulatory Commission ' Pt. 20 [f@ 20.1-20.602], App. B. !,
- APPENOtX B TO (( 20.1-20.602-CONCENTRATIONS IN AIR AND WATER 'ADOVE NATURAL BACKGROUND-Continued (See footnotes at end of Appends 81 !
Isotope ' Table i Tabse et Elemord (atomic number) Col.1 4 Cof. 2- Col 1 Ak Cot. 2 - W 6 Wmi) g,[,,) 6 C4 W ) g y'[3 Thorium (90) _. -- Th 227 . . .. S . 3 x 10-" 5 x 10" 1 x 10-" 2 x 10*M 1 2 x 10 " 5 x 10" 6 x 10"' 2 x 10" ' Th 228 . S 9 x 10"" 2 x 10" 3 x 10"8 7 x 10*
- I 6 x 10-" 4 x 10" 2 x 10"8 1 x 10" i Th 230. . S 2 x 10"8 5xto" 8 x to-" 2 x to" j 1 1 x 10-" 9x10" 3 x 10"8 3 x 10" .i Th 238- S 1 x 10" 7x 10" 5 x 10" 2x 10" i 1 x 10*
- 7 x 10-s 4xgo-e 2 x 10" Th 232 S 3 x 10-" 5 x 10" - 1 x 10"' 2 x 10" -
1 3 x 10-" 1 x 10* 8 1x10-" 4 x 10-8 Th natural S 6 x 10-" 6 x 10-* 1 x 10"' 2 x 10" 1 6 x 10*" 6x10" 2 x 10-" 2 x 10" ) Th 234 S 6 x 10" s 5 x 10" 2 x 10*
- 2 x 10" i I 3 x 10-8 5 x 10*
- 1 x 10-* 2 x 10" Thulium (69) . -. . . Tm 170 - S 4 y 10" 1 x10" 1 x to" 5 x to" 1 3 x 10*
- 1 x10-8 1 x 10" 5 x 10" Tm 171 _ S 1 x 10" 1 x 10-8 4 x 10" 5 x 10" q l 2x10" 1 x 10-' e x 10-* 5 x t0" 1 i.. Tat (50) . Sn 113 . S 4 x10*8 2x10-s 4 x10" 9 x 10" l- 1- 5 x10-e 2x10-8 2 x 10" 8 x 10-8 Sn 125 S 1 x 10*
- 5 x10" 4 x 10" 2 x 10" I e x t0-* 5 x10" 3 x 10" 2 x 10" Tunessen tweeang (74) w ies S 2 x 10-* 1 x10" ex10-* 4x10" j i s x10*' 1 x10" 4 x 10-* 3 x 10" w ies S a::10-' 4x10" 3 x10" 1xt0" I 1 x 10-' 3 x10-8 4 x 10" 1 x10" w ter S 4 x 10-' 2 x 10-' 2 x 10-* 7x10" 1 3 x10-' 2x10-8 1 x 10" 6 x 10" ,
Uranium (s26 U 230 S 3 x10-" 1 x10" 1x10-" 5x10 8 i' I 1 x 10-" 1x10" 4 x 10- a 5 x 10-* U 232 S 1x10-" e x t0" 3 x 10-" 3 x10" 3 x 10-" ex t0" 9 x 10- a 3 x 10" U 233 S 5 x 10-" e x10-* 2 x 10-" 3 x 10*
- 1 1 x 10-" e x t0" 4 x 10- a 3 x 10" s- U 234 S* 6 x10* " 9 x10" 2 x 10"' 3 x 10-*
f i 1 x 10* " 9x10" 4 x 10"8 3 x10" l U 235 S* . Ex10*" 8 x10" 2 x 10* " 3 x 10-8 1 1 x 10*" 8 x10" - 4 x 10"8 3 x10** U 236. . S 4 x 10-" 1 x10" 2 x 10-" 3 x 10" ~
- t. 1 x 10-" 1 x 10-8 4 x 10-" 3 x 10". -
l- U 238 . S* 7x10"' 1 x10-8 3 x 10"' 4 x10" 1 1 x 10* " 1 x 10-8 E x 10- 88 4 x 10** U 240 . S 2 x10-' 1 x 10*
- 8 x 10-* 3 x 10" I 2 x 10-' 1 x10-s 4 x 10*
- 3 x10-8
[1 U. natural S* 1 x 10* " 1 x10-8 5x10"8 3x10-8 l . I 1 x 10*" 1x10-s 5x10"' 3 x10" Venedium (23) V 48 S 2 x 10-' 9 x10" 6x to-' 3 x 10"
, . . I 6 x 10-8 8 x10" 2 x 10" 3 x 10"
._ Xenon (54) - _ Xe 131m .. Sub' 2x10" 4 x 10-! ..
Xe 133 Sub 1 x 10" 3 x 10- ' (' Xe 133m .. Sub ' 1 x 10-* 3x to" .
, Xe 135. - - Sub 4 x 10* * . . - 11 x 10" 3 x10" 2 x 10" 1 x 10" '
Ytterbaum (70)- Yb 175 S 7 x 10-' I ~6 x 10*' 3 x 10-s 2 x 10" 1 x 10" -' _ f Yttrium (30) '
.. Y 90J .. . , S 1 x 10" 6 x 10" 4 x to" 2 x 10" '
I 1 x 10" 6 x 10' 3 x 10" 2 x 10" Y 91m ? S. 2 x 10*
- 1 x 10" . 8 x 10" 3 x 10' -
. I ~ 2 x 10" 1 x 10" 6 x 10" 3 x 10 * *
> Y 91 S 4 x 10" ' 8 x 10" 1 x 10-* 3x10" t 3 x 10*
- 8 x 10 * * .1v10** 3 x 10 *
- Y 92 ; 5- . 4 x 10" ; 2 x 10 - t v 10
- 6x20**
I> . 3 x 10-8 2 x 10*
- 1 x 10*
- v .n c . m. m o ...m. e e..- 6 n x .a-10' '. -
b 1 hn-. .. .. . .. _ . . , . . . . . . ', ..
G j 1 i l C l l Pt.20[ 20,1-20.602Ji App, B .10 CFR Ch.1 (1-1-93 Edition) f i j Avecnoix B To 95 20.1--20.co2-conCENTRATIOr4S IN AIR AND WATER ABOVE NATURAL
' BACKGROUND-Continued h (See footnotes at end of Appendix 0)
#sotope
- Table i Tatde u L Element (atorruc number) Col 2- Col NAi, Cof. 2-Col NAir WCdmG jmn WCdmG- h*?nn Zinc 00) --. m.-....... Zn 65..~ S t x 10" 3 x 10" d x 10" 1 x 10" 1 6 x 10" 5x t0" 2xto" 2 x 10" Zn 69m S 4 x 10" 2 x 10" 1 x 10" 7 x 10" l 3x10" 2 x 10" 1 M 10" 6 x 10" 2n 69 S 7 x 10-* 5 x 10" 2 x 10" 2x10" 4
[- l 9 x to" 5 x 10*
- 3 x 10" 2 x 10"
' Zrconsum (40)._ .. . Zr 93 _.- . . S 1 x 10" 2 x 10" 4 x 10" 8 x 10" .
1- 3xt0" 2 x 10" 1 x 10" 8 x 10" Zr 95.. S 1x10" 2x10" 4 x 10" 6 x 10" 4 x 10" 6 x 10" [. Zr 97 - I S 3 x 10" 1 x 10" 2 x 10-s 5 x 10" 4 x to" 2 x 10" i I g x t0" 5 x 10" 3 x 10" 2 x 10" Arty single redsonuchde not hsted above Sub 1 x 10* * . 3 x 10" with decay mode other than alpha
~
emissinn or spontaneous fission and with radioactrve half-life less than 2 hours. l Any single redsonuclide not listed above . - 3 x 10" 9 x 10" 1xto"* 3 x 10" with decay anode other than alpha emiselon or sporitaneous dission and with radioactree hew.ble greater than 2 hours. radionuclide not listed .. 6 x10"8 . 4 x 10- r 2 x 10"* 3 x10" Any ,.weingle.f, ~,s b, a-. elon or spontaneous sesion.
'Solubic (S); Insoluble (t).
'"Sub" means that weiues given are for submersion in a r 4 M infinite cloud of airbome metertal
'These redon concentrations are appropriate for proteolion from redon222 combined with its short. lived daughters ;
T M;, the weius in Table i may be supleoed by one. third (%) "wortung level" (A " working levet" is defined as any 4 combineton of short tved redorb222 daughters, polonium-tie, lead-214, bismuth.214 and polonium-214, in one meer of air, tuitiotA sogerd to.Wie degree of equulbrium. that wut result in the uitmete emiseson of 1.3x108 MeV of alpha particle energy.) The Teben it welue may be replaced by one-Wiirteth (b) of a " working. level" The limit on redon-222 concentrations in sestricted areas may be besec' on an annual average. Yor soluble mhttures of U-238. U-234 and U-235 in air chemical toxidly sney be the limiting " factor, if the percent by C -.r _.; of U-235 is less then 5, the concentration value for a 404scur teorkweek. Table 4. is 0.2 milhgrams Uranium per omic snoter of air everage. For any enrichment. the product of the average concentration and tirne of esposure d. uring a 404 tour teorkweek shes not exceed 8x10" SA pCide/mt, where SA is Wie speci8c actMty of the uranium Inhaled. The ( ,. conoontraton weius for Tobie at is 0.007 minigrams uranium per cubic meter of air. The specetic scevity for naturet uranium is
- 6.77x10" ourtes por gram U. The speceric actMey for other enintures of U-236. U-235 and U-234, if not known, ehen be:
SA-3.6 x10" curies /ararn U ' U<6epleted SA=(0.4 +0.3e E+0.0bS4 E 8) 10" E BO.72 where E is the percentage by weight of U-235, empressed as percent h Nott in any asse twhere there is a mixture in air or water of more than one redsonuchde, the hmiting values for purposes of this Appendlu should be determined as follows: 1.'il 9te identitr and conoontration of endi radionuchde in the mixture are known, the limiting welues should be derived as . follows: Determine, lor sech radionuclirle in the eniature the ratio between the quantity present in the mixture and the hmit otherwise estabsehed in Appendin a see the specNic radionuchde when not in a morture. The sum of such ratios for es the radionusades in the mixture may not exceed "i" (i.e.," unity") Esasapuc tf redlonuchdes A, p and C are present in concerWrations Ca. C.. and Cc, and if the apphcable MPC's, are MPC., and MPC., and MPCe sa : ri, then ttw concentrations shen be hmited so that the following reistoonsrup exists:
~ (C /MPC )+(C,/MPC.)+(Cr/W'Cc) S1
'i-
-- 2. Il either the idecepty or the concentration of any radenuchde in the m rture is not known the listing values for purposes a c of Appenda B shalt be;
- a. For purposes of Table 1. Col.1-6 x 10* "
x ; b. For purposes of Tatde I. Cof 2-4 x to"
. c. For purposes of Table it, Col.1-2x 10"*
- i. - d. For purposes of Table it, Col. 2-3 x 10" l 13, it any of the conditens specif.ed baiow are met, the corresponding values specaf*ed below may be used en I.eu of anose specteed in peregraph 2 atnve ,
- 4. If the idenkty of each radonuchde en the muture es known but the concentrat on of one or more of the f adonuchdes en the mature es not known the concenteat on km.: toe the muture is'the hmet specit.ed art Appendia 0" tor the radionuchde en the
- i mature hawng the towest concentraten hmt or
. : b. It me identity of each rad onuchoe en the mature es not known, but it is known that certa.n vaa.onuchdus specihed an
' Append: -Ir are not present en the m.ture. ino concentraton hm: for the nature is the towest conconwet on hmit sr**t'ed
, z in Aaaww% "n" fN ene r witan..re.M h.ch k nM n nnwn en te o, ene ,t,% sh.. m, A sm nr
g__ y 1 {. L i I r. Nuclear Regulatory Commission . Pt. 20 [ 20.1-20.602], App C Tause i Table it Coi 1- [' . c. Element (atorme number) and isotope g,, Col 2-Water Col.1-A r (POI Col. 2-Water lj O# (pO/in )
* (pO/ing mo )
-. = . --- ..
.t
[I if it is known that Sr 90. I 125. I 126. I 129. I 138 (1 133 Tabee II only). PD 210. Po 210. At 215. Ra 223. Ra 224. Ra 226. Ac 227. Ha 228. Th 230. Pa 231. Th 232. Theat. Cm 248. Cf 254. and Fm 256 are not presord 9 x 10" . 3 x 10" W it is known that Sr 90.1 125. I 126. I 129 (1 131. I 133. Table II ordA. Pb f 210. Po 210, Ra 223. Ra 226. Ha 228. Pa 231, Theet, Cm 248. Cf 254 [ and Fm 256 are not present - 6 x 10" 2 x 10" - 1 j j W 8 is known that Sr 90, t 129 (1 125. I 126. I 131, Table it only). Pb 210. Ra 226. Ha 228. Cm 248, and Cf 254 are not present 2x 0" . 6 x 10* ' 1 W it is known that (I 129. Table il only). Ra 226. and Ra 228 are not present. .. 3 x 10" 1 x 10-' l if it is known that alpha.emetters and Sr 90.1 129. Pb 210. Ac. 227. Ra 228 1 3 x to" 1 x 10" " j Pa 230. Pu 241. and Ok 249 are not present- . If it is known that alpha. emitters and Pb 210. Ac 227. Ha 228. and Pu 241 are not present . 3 x 10-" , t x 10-" L N lt is known that alpha 4rnitters and Ac 227 are not present If it is known that M 227. Th 230. Pa 231. Pu 238. Pu 239. Pu 240. Pu 242. 3 x 10- " . 1 x 10"8 i i Pu 244. Cm 248. Cf 249 and Cf 251 are not present . 3 x 10"8 . . . . , 1 x 10"8 .
- 4. If a enisture of radionuchdes consists of uranium and as daughters in ore dust prior to chemical separation of the uranium trem Wie ore. De values specified below may be used for uranium and its daughters through radium-226. Instead of those from
[' '~ peregraphs 1. 2. or 3 above.
- a. For purposes of Table 1. Col. 1-1 x10-" pO/mi gross alpha activitr, or 5x10-" pO/rrd natural uranium or 75 l micrograms per cubic meter of air natural uranium.
- b. For purposes of Table 11. Col.1-3 x10"8pO/mi gross alpha actndty: 2x10"8pO/mi natural uranium; or 3 micrograms -3
[ por edic meter of air natural uranium. S. For purposes of this note, a radionuclide may be considered as not present in a mixture if (a) the ratio of the J conoontratson of that radionuchde in the mruture (C.) to the concentration firnit for that rad.oriuchde specified in Table 11 of Appendu *1B (MFC.) does not exceed %e. fi.e. C./MFC 51/10) and (b) the surn of such ratios for au the redonuclides 4 considered as not present in the rnirture does not exceed % te [.- ' (C./M/C.+C,/MPC;r + a %). l [- [: 0
L: ' I~ L APPENDIX 1 [L RADIDACTIVE LIQUID, GASEOUS, AND SOLID WASTE. TREATMENT SYSTEMS Reaui rement: 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 Annual' { Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee, b: . Response: -There were no licensee-initiated major changes to the radioactive waste systems during this reporting period. 4
)
[ 4 [ .- 4 E [ [: E C. m m., 11 p _' _ _ _ - _ _ __ _
L L APPENDIX J r L ON-SITE DISPOSAL OF SEPTIC WASTE AND COOLING TOWER SILT r L Reauirement: Off-Site Dose Calculational Manual, Appendices B and F requires that the dose impact due to on-site disposal of septic waste and 4 r the cooling tower silt during the reporting year and from L previous years be reported to the Commission in the Annual Radioactive Effluent Report if disposals occur during the ' reporting year. VYNPC will report in the Annual Radiological Effluent Release Report a list of the radionuclides present and y the total radioactivity associated with the on-site disposal L activities at Vermont Yankee. i - Response: There was one on-site disposal of septic waste during the reporting year. The total volume of the septage spread was approximately 10,600 gallons. The total activity spread on the 1.9 acres (southern) on-site disposal field during 1997 and from l ' previous years was: 1 Nuclide Activity (Ci) [' Mn 54 2.47E-07 ) L Co 60 1.17E-05 J Zn-65 1.90E-08 ! Cs-137 2.51E-06 j L I The projected hypothetical dose from on-site disposals of septic waste is 8.16E-03 mrem /yr. This dose was calculated according to I [. ! the model and the assumptions of Off-Site Dose Calculational Manual, Appendix B. [ [ [ [ urun J-1
[ [: [ l [ VERMONT-YANKEE NUCLEAR POWER STATION [. OFF-SITE DOSE CALCLUATION MANUAL REVISION 21 [ [ [ [ [ 4 [ {. , Reviewed : VM7MMMA MId 97-665' f//3/f7 Plant Operations Review Commiftse Date
. Approved: 9R Jor M TI LLO P Manager Date
{
' Approved: b O
( Sr. Vice President, Cherations Date [i ( _ _ - - - - - - - - - - - _ - - - - - - - - - - _ - - - - - - - - - - - - - - - - -
I LIST OF AFFECTED PAGES l l l Paqe Revision Date 1 1 l 1 21 l 11 20 07/30/96 iii 20 07/30/96 l ,3 iv 0 03/01/84 l 3 v 17 05/31/94 vi 18 07/20/95 vii 21 08/14/97 l ) lI 05/31/94 viii 17 ix 18 07/20/95 x 17 05/31/94 1-1 21 08/14/97 l 12 15 07/08/93 f 1-3 21 08/14/97 i l 14 17 05/31/94 1-5 20 07/30/96 4 1-6 21 08/14/97 l l I 1-7 to 1-9 05/31/94 l 17 1-10 15 07/08/93 1-11 17 05/31/94 1-12 10/28/93 I 16 1 1-13 to 1-18 ~15 07/08/93 l 1-19 to 1-20 17 05/31/94 l 1-21 15 07/08/93 1-22 20 07/30/96 l 2-1 to 2-2 21 08/14/97 l
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I Revision 21 Date 08/14/97
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' LIST OF.AFFECTED'PAGES.
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'Paae Revision Date 4 lb. -19 11/01/95
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17 05/31/94 A-1 to A-2 15 07/08/93
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.A-16.to A-21 17 05/31/94 A-22 to A-23 20 -07/30/96 0' 'A-24' 17 05/31/94 B l'.to C-39
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J l Revision) 1L. Date 08/14/97-m ;
.jjj.
r1 L3 3.7 Method to: Calculate .the Gamma Air Dose-from Noble Gases . . 3-30 3.8- Method to Calculate the Beta Air Dose from Noble' Gases. . . 3-34 3.9 Method to Calculate the Critical Organ Dose'from lodines.
. Tritium and Particulates. . . . . . . . . . . . . . . . . . 3 38:
[ 3.10 Receptor Points and Annual Average Atmospheric Dispersion Factors for Important Exposure Pathways . . . . . . . . . . .-3 45 3.11. Method to Calculate Direct Dose From Plant Operation . . . .'3-51. 3.12 Cumulative Doses ......u. . . . . . . . . . . . . . . 3-59 {. , 4.0? ' ENVIRONMENTAL MONITORING' PROGRAM. ................. 4-1 5.'0; 'SETPOINT. DETERMINATIONS . . . . . . . . . . . . . . . . . . . . . . 5-1 i
=5.1 Liquid Effluent Instrumentation Setpoints . . . . . . . . . . 5-2 F
Li 5.2 Gaseous Effluent Instrumentation Setpoints . . . . . . . . 5-11 6.0 LIOUID:AND GASEOUS EFFLUENT STREAMS,' RADIATION MONITORS,'AND h RADWASTE TREATMENT' SYSTEMS . . .................. 6-1 6.1 In Plant Radioactive Liquid Effluent Pathways . . . . . . . . 6-1 6.2 In Plant Radioactive Gaseous Effluent Pathways 6-4 { ..... .. REFERENCES R-1 4 APPENDIX A: Method I Example Calculations A1
- p. APPENDIX B: Approval of Criteria for Disposal of Slightly U Contaminated Septic Waste On Site at Vermont-Yankee B1 b APPENDIX C: Response to NRC/EG&G Evaluation of ODCM Update Through Revision 4 C-1 h APPENDIX-D: Assessment of Surveillance C'riteria'for Gas Releases from Waste Oil Incineration 0 : APPENDIX: E: NRC Safety Evaluation for Disposal of Slightly
{' Contaminated Soil On-Site at VY (Below the Chem , LabtFloor) -TAC No. M82152 E-1 [1( : APPENDIX F: Approval = Pursuant to 10CFR20.2002 for Onsite-Disposal of: Cooling' Tower. Silt F1 h
, APPENDIX G'i Maximum Permissible Concentrations (MPCs) in Air "and. Water'Above. Natural Background Taken from L 10CFR20.lito 20.602', Appendix 8 G-1 b
~
; Revision: 2L ;Date ' 08/14/97 vil-
- . . . . . . ....__u....... .. . . .
1 1 I l I I 1
1.0 INTRODUCTION
j
)
i This ODCM (Off-Site Dose Calculation Manual) provides formal and l approved methods for the calculation of off site concentration, off-site l I doses, and efflue' monitor setpoints in order to comply with the Vermont Yankee Technical Specifications 3.8/4.8 and 3.9/4.9. hereaf ter referred to as i The ODCM forms the basis I I the Radiological Effluent Technical Specifications. for plant procedures and is designed for use by the procedure writer. In addition, the ODCH will be useful to the writer of periodic reports required by the NRC on the dose consequences of plant operation. The dose methods contained herein follow accepted NRC guidance for calculation of doses ; necessary to demonstrate compliance with the dose objectives of Appendix I to , 10CFR50 (Regulatory Guide 1.109) unless otherwise noted in the text. Demonstration of compliance with the dose limits of 40CFR190 (see j Technical Specification 3.8.H) will be considered as demonstrating compliance l with the 0.1 rem limit of 10CFR20.1301(a)(1) for members of the public in unrestricted areas (Reference 56 FR 23374, third column). ) It shall be the responsibility of the Chemistry Manager and Radiation Protection Manager to ensure that the ODCM is used in the performance of the surveillance requirements of the appropriate portions of Technical
, Specifications. The administration of the program for the onsite disposal of slightly contaminated waste, as described in Appendices, is also the responsibility of the Chemistry Manager, j 1
All changes to the ODCM must be reviewed by PORC and approved by M00, in accordance with Technical Specification 6.13. prior to implementation. All approved . changes shall be submitted to the NRC for their information in the Annual Radioactive Effluent Report for the period in which the change (s) was made effective. The plant's Document Control Center (DCC) shall maintain the current version of the ODCM and issue under controlled distribution all approved changes to it. j I ! l l I i Revision 21 Date 08/14/97 l a
l;ji jIIll O l O c t r r
. . c o
c_ q y r t r y m m
/
a a q a a . . r r 1 t C a . p n n a n n ry y y O i i m i i n i n i i
/
/
m
/
m mm 4 L ' m m i m e e e e m e e e r r 0 r r m e r r r m~ m 1 m m er r m mm 0 m 0 O 0 x 5 0 m 0 0 6 2 0 0 0 0 0 5 1 2 1 3 5 1 0 5 3 1 0 s s s s s s s s s s s s O n o i t a m 8 60 c d o 9 1 4 3 3 53 73 O .i f i h t 1 2 2 2 1 3 3 1 3 3 33 33 33 c e . . e M . . . . . . . . . . p g q q q q q qq qq qq S r E E E E E EE EE EE O l a s n c o i i m e 8 n t o l h a e r b > O c e u c f onl ob f N o 2
/
1 T E si o e md 1 -
- t m onT _
ntN 1 t g y oa a o ra _ O1 n r R f h e in r o i rg tt n f - mt 3 u t g cni s e e e eui 1 E l n a s s s e ti w L f e e aed rcu o o t at B f t Gn o m a F nl o D D D a Ri s _ A E re e .oc s R UT
- C ei i eC x l t y e y e ye eTt l
D h E b a d s d s d s e s a ac m tt[ or o o o o oa s o o .l I n Nt B D B O BG D s u i o d f es] n D ec o n out s l e l n l n l e s nni l i e ac a a a a al ne ait s D l i o a mf ms ufi a oo o SELG TC T t n t g r O t T o g tb i s r oo k a roaa O TN SG gd ry OI PD d a R f e O. o e t y s o y s i ' D r ' o l a D i s m Q S m u n t n en t n e ea t r~ se b t n e u 7 9
/
4 o uo u ap l
)
1 l i l i l wO f / 8 at ft f d f' d @ i c ca ni f a E r t f E at R n e E s e u n 0 e hf d n d d m u~ i ci i e i it o t t ec uc u ua ee n a T e q'on q qe st o D. Q S p i LC i L i r LT GR aa C ( 1 2 Q'
~
1' 1 1 1 1 E n 8 C. E 'o A. ' . . i 8 8 8 8 s
- 8. ~
i 3 3 3 3 3 v @ e R
~
g' Q' '
l I i i TABLE 1.1-2 I I Summary of Methods to Calculate Unrestricted Area liauid Concentrations
'l Equation Reference Number Category Equation Section 2-1 Sum of the Fractions of ENG C 1 2*l l Combined Effluent F1 -E' s 10 Concentrations in Liquids '
[Except Noble Gases) 2 2. Total Activity of Dissolved NG ' Ci ' - NG 2*1
- Ci C3 and Entrained Noble Gases
> l from all Station SQurces '
s2E-04 i I l I I l c I l l L Rev i s i on _2_L. Da t e 08/14/97 1 f3 m-
.t : I 2.0 METHOD TO CALCULATE OFF-SITE LIOV10' CONCENTRATIONS I Chapter 2 contains the basis for plant procedures that the plant operator requires to meet Technical Specification 3.8.A.1 which limits the I total fraction of combined effluent concentration in liquid pathways, excluding noble gases, denoted here as EFfG, at the point of disch'arge at any ENG is limited to less than or equal to ten, i .e., time (see Figure 6-1). F l l I
.' Ff"6 s10 The total concentration of all dissolved and entrained noble gases at I the point of discharge from all station sources, denoted d[. is limited to 2E-04 C1/mi, i.e.,
d[12E-04pCi/ml. Evaluation of FfG E and df is required concurrent with the sampling and analysis program in Technical Specification Table 4.8.1. , 2.1 Method to Determine F,NG E anddf Determine the total fraction of combined effluent concentrations at the E point of discharge in liquid pathways (excluding noble gases), denoted F[0, and determine the total concentration at the point of discharge of all dissolved and entrained noble gases in liquid pathways from all station j sources, denoted d[, as follows-C ! pfNG , p pi g
, ECL, (2-1)
I 'pC1/ml' C1/ml, and: I L
- .Revis1on 21 Date' 08/14/97 2-1 m__ -
I G CfG" Cft s 2E-04 (2-2) ( Ci/ml) (pCi/mi) ( Ci/mi) where:
-FfG
= Total sum of the fractions of each radionuclide concentration in liquid effluents (excluding noble gases) at the point of discharge to an unrestricted area, divided by each radionuclide*s ECL valut.
C, p
- Concentration at point of discharge to an unrestricted area of radionuclide "i", except for dissolved and entrained noble gases, from any tank or other significant source, p, from which a discharge may be made (including the floor drain sample tank, the waste sample tanks, the detergent waste tank and any other significant source from which a discharge can be made) ( C1/ml). This concentration can be calculated from: Cpi - Cygt x F TK/ [Fo!L + FTK] where: C TK1 equals the concentration of radionuclide i in the tank to be discharged (pCi/mi): F DIL is equal to the dilution flow provided by the liquid radioactive waste dilution pumps I (20,000 gpm): F TK equals the liquid waste discharge pump flow rate which regulates the rate at which liquid from a waste collection tank is discharged (gpm).
ECL, - Annual average effluent concentration limits of radionuclide I "i", except for dissolved and entrained noble gases, from 10CFR20.1001-20.2401, Appendix B, Table 2, Column 2 ( Ci/ml). CyG - Total concentration at point of discharge to an unrestricted area of all dissolved and entrained noble gases in liquid pathways from all station sources ( Ci/ml). CN - Concentration at point of discharge to an unrestricted area of dissolved and entrained noble gas "i" in liquid pathways from all station sources (pci/ml).
'Date 08/14/97 I Revision '21 2-2
I I Under expected or anticipated operating conditions, the concentration at any time of radionuclides at the point of discharge from the service water effluent pathway to an unrestricted area will not exceed ten times the effluent concentration values of 10CFR20.1001-20'.2401, Appendix B, Table 2. I Column 2. 2.2.3 Circulating Water Pathway The circulating water pathway shown on Figure 6-1, flows from the intake structure through the condenser and the discharge structure. Under normal operating conditions, the water in this line is not radioactive. For this reason, the circulating water line is not sampled routinely but it is I monitored continuously by the discharge process monitor (No. 17/359) located in the discharge structure. The alarm setpoint on the discharge process monitor is set at a level which is three times the background of the instrument. The circulating water is simpled if the monitor is out of service of if the alarm sounds. Under normal operating conditions, the average concentration of radionuclides at the point of discharge from the circulating water pathway to an unrestricted area will not exceed the annual effluent concentration limits in 10CFR20.1001-20.2401, Appendix B. Table 2 Column 2. I4 I I I j I Revi s t'on 21 Date' 08/14/97 2-4 m ._..........m.s.m.m sw. .-
l I 4 5.1 Liouid Effluent Instrumentation Setooints l I Technical Specification 3.9.A.1 requires that the radioactive liquid I effluent instrumentation in Table 3.9.1 of the Technical Specifications have alarm setpoints in order to ensure that Specification 3.8.A.1 is not exceeded. Specification 3.8. A.1 limits the activity concentration at any time in liquid effluents to ten items or less the effluent concentration values in Appendix B, Table 2. Column 2 of 10CFR20.1001 through 20.2401, and a total noble gas concentration limit of 2E-04 pCi/ml. I 5.1.1 Licuid Radwaste Discharge Monitor (RM-17-350) The sample tank pathways shown on Figure 6-1 are monitored by the liquid radwaste discharge monitor (RM 17 350). Periodic batch releases may be made from the waste sample tanks, detergent waste tank or floor drain sample tank. 5.1.1.1 Method to Determine the Setooint of the liauid Radwaste Discharge Monitor (RM-17-350) The' instrument response (in counts per second) for the limiting concentration at the point of discharge is the .setpoint, denoted R,,tpoint, and is determined as follows:
'I R setpoint "
0F S1 E C,i
! (5-li q (cps) (#) (cp M ) g A) j pC1 m1 l Where: j l
DF = b= Dilution factor (as a conservative measure, fm a DF of at least 1000 is used) l (dimensionl ess ) . (5-2) F, = Flow rate past monitor (gpm)
- F = Flow rate out of discharge canal (gpm) e ; DF min -
Minimum allowable dilution factor. (dimensionless) I
=
0.1 E (5-3) l i EC"l i Revision.-21 Date 08/14/97-n __ b
[:5 [
$ : C,i - 2.15E ~+ . 7 48E-05 + 2.56E-05 1
( pC1 ) Ci ( pCi ) ( pCi ) ml . ml ) m1 ml (-
.1.22E-04
(.. ~ ( pC1 ) ml "I
- DF,, n - 0'.1 -(5-3) l L (pCi-ml) ml -pCi
[ .. L '
- 0.1 2.15E-05 . 7.48E-05 . 2.56E-05 ' l
, 9E-07 1E-06 ' 3E-06 ,
[ .- C1-ml Ci-ml ( ( pCi-m1 ) ( ml- Ci ) mi -pC1 ) ml- C1 r.: I 4 y ' - 10. 7 The minimum dilution factor. DFmin, needed to discharge the mixture of (. radionuclides -in this example is 10.7. As a conservative measure, an actual l
' dilution factor, OF. of 1,000 is usually used. The release rate of the floor f : drain sample tank.may'be adjusted from 0 to 50 gpm and the dilution pumps can supply up..to 20,000 gpm of di.lution water. With the dilution flow taken as- )
.18.000' gpm. .the release rate from the floor drain sample tank may be j
/ L determined ,as foilows: I Fd f? F, -
'g, (5-4)
(gpm)- (gpm). ; i ['
. /18.000.gpm ,.18 gpm -
.1,000 '
f-f N/ Revision 21
'l 0a t'e 08/14/97~- . , +
I j
'P
- 'a
l I Under these conditions, the setpoint of the liquid radwaste discharge { rr.onitor is: 0F (5-1) I Rsetpoint " DFmin St E 1 C,5 (cps-ml) Ci (cps) (#) pCi ( ml ) 1
= 000 4.9E+06 1.22E-04 l 10.7 (cps) (#) (cps-m1 ( pCi )
Ci ml
- 55.869 cps l I- In this example, the calculated limiting count rate alarm point for the f liquid radwaste discharge. monitor would be 55.869 cps above background. Plant procedures apply administrative limits below the calculated limiting count rate to account for such elements as instrument uncertainty and early alarm i warning before exceeding Technical Specification limits.
5.1.1.3 Basis for the Liouid Radwaste Discharoe Monitor Setooint 'I The liquid radwaste discharge monitor setpoint must ensure that o Specification 3.8. A.1 is not exceeded for the appropriate in-plant pathways.
- I -The liquid radwaste discharge monitor is placed upstream of the major source ,
of dilution flow and responds to the concentration of radioactivity discharged l in batch releases as follows: (5-5) R =E' C,i S ii
\
(cps) ( pC1 ) ( cps-m1) mi pC1 Where: R - Response of the monitor (cps) I S,i Detector counting efficiency for radionuclide "1" i
-(cps /(pCi/mi)) l 1
j C,5 - Activity concentration of radionuclide "1" in mixture at the m monttor (pCi/ml) m- Reviston- '21 Date 08/14/97-g 5-5
- i
I I' The detector calibration procedure establishes a counting efficiency for a given mix of nuclides seen by the detector. Therefore, in Equation 5-5 one may substitute Sj for Sii, where Si represents the counting efficiency determined for the current mix of nuclides. If the mix of nuclides changes significantly, a new counting efficiency should be determined for calculating the setpoint. R - Si E C,i (5-6) (cps) cps-m1' 'pci ' pCi , , ml , The effluent concentration for a given radionuclide must not exceed 10 times the 10 CFR Part 20 ECL at the point of discharge to an unrestricted area at any time. When a mixture of radionuclides is present, the concentration at the point of discharge to an unrestricted area shall be limited as follows: Cdi (5-7) l Et ECL i s10 Ci -ml ( ml- Ci ) .l . Where: I C df - Activity concentration of radionuclide "i" in the mixture at the point of discharge to an unrestricted area ( Ci/ml) ECL, - Effluent concentration limit for radionuclide "i" from 10CFR20.1001-20.2401. Appendix B. Table 2, Column 2 ( Ci/ml) The activity concentration of radionuclide "i" at the point of discharge is related to the activity concentration of radionuclide "i" at the monitor as follows: Co, - (5-8)
- C mi
[Fd ( pCi ) ( pCi ) ( gpm ) mi mi gpm I Revisinn ?! 'nate 08/14/97 w
l' Where: . h C oi- - Activity concentration of radionuclide "1" in the mixture at the point of discharge (pCi/ml)
. F, -
Flow rate past monitor (gpm)
,F e_
- ' Flow rate out of discharge canal (gpm)
. Substituting 'the right' half of Equation 5-8 for C dt in Equation 5-7 and solving for. F o/F; yields the minimum dilution factor needed to comply with
~
Equation 5-7: b .. 0F min 6 2 (5-3) l ECL
- 10 C
'gpm' 'pCi-ml'
{ gpm, mi -gC1, w Where: ] Fd - Flow rate out of discharge canal (gpm) F E F, = Flow rate past monitor (gpm) - . C,g - Activity concentration of radionuclide "1" in mixture at the L. monitor (pCi/mi) ECL, - Effluent concentration limit for radionuclide "1" from b 10CFR20.1001-20.2401, Appendix 8. Table 2. Column 2 ( C1/ml) 10 = - The instantaneous concentration multiplier allowed by h Technical. Speci fi. cation. 3.8. A.1 h JIf 'F4 /F, is less than DFmin, then the tank may not be discharged until, either_Fl0F d f mor.both are adjusted such that: h' 'F (5-3)
.2 OF ,,.
[m l E- g gpm ') ,
.gpm-UDouleton '91) ' n s t n' ; ' OQ /1 A / 0 7
.- ' i. -
~
I E b,3#D F',3 . - (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-pC1-yr) 1.14 E +02 I D F'C 1.15E+04
- 9.91E-03 (mrem-sec/pCi-yr) spt 1 1 R - 3,000 S 9
skin F 0 F'c 1 I
- (3,000) (3E+07)
(7.32E+07) ( 9. 91 E-03 )
- 124,067 cpm The setpoint, R3pt, is the lesser of R spt andRlptki" . For the noble gas mixture in this example Rspt i s l es s tha n Rlp"tI" , indicating that the total body dose rate is more restrictive. Therefore, in this example the
" Stack Gas 1" and " Stack Gas II" noble gas activity monitors should each be j set at some administrative value below 39,348 cpm above background to provide
, conservatism for such issues as instrument uncertainty and secondary releases from other locations. As an example, a conservative value might be based on j controlling release rates from the plant in order to maintain off-site air I concentrations below 20 x ECL when averaged over an hour, or to account for other minor releases from the waste oil burner. Ffqr example, if an I administrative limit of 70 percent of the Technical Specification whole body dose limit 500 mrem /yr (39,348 cpm) is chosen, then the noble gas monitor alarms should be set at no more than 27.543 cpm above background l
(0.7 x 39,348 - 27,543). 5.2.1.3 Basis for the Plant Stack and A0G System Noble Gas tetivity Monitor I' Setooints I , The setpoints of the plant stack and.A0G system noble ga; ictivity 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 i 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 I mixture. 'Therefore, each equation must be considered separately. The I
~
m--__ . . . . . . - - - - . w I 9 I I I I I I APPENDIX F APPROVAL PURSUANT TO 10CFR20.2002 l l FOR ONSITE DISPOSAL OF COOLING TOWER SILT Ic I I I l I l I t I 1 1 1 I ..nevision 2L Date 08/14/97 L
i
$p ato t UNITED STATES i g
t j NUCLEAR REGULATORY COMMISSION WA8HINGTON, D.C. 20665-0001 p . June 18, 1997 W ~ - -- -
<s
%***** NVr 97-85 i .,. bp ,lf L jjj JUN 2 3193 3~
Mr. Donald A. Reid I- - -" l Vice President, Operations DA.ED V:rmont Yankee Nuclear Power Corporation gy~Q g e Fcrry Road Brattleboro, VT 05301 l-
SUBJECT:
REVISED SAFETY EVALUATION - APPROVAL PURSUANT TO 10 CFR 20.2002 FOR l ONSITE DISPOSAL OF COOLING TOWER SILT - VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. M96371)
Dear Mr. Reid:
By letter dated August 30, 1995, Vermont Yankee Nuclear Power Corporation
-(VYNPC) requested approval, pursuant to 10 CFR 20.2002, for the onsite disposal of slightly contaminated silt material removed from Vermont Yankee Nuclear Power Station's (Vermont Yankee's) cooling towers. In a safety evaluation (SE) dated March 4,1996, the NRC staff approved the proposed silt disposal. However, because of discrepancies VYNPC identified between the l
safety evaluation and -VYNPC's lette of August 30, 1995, VYNPC postponed l imp 1'ementstion of the silt disposal until resolution of the discrepancies. By letter dat,ed August 2, 1996, VYNPC informed the NRC staff of the discrepancies l and requested that the SE be revised accordingly. Recognizing the discrepancies, the NRC staff has prepared the enclosed SE to resolve the
, discrepancies and to replace the SE of March 4,1996.
The NRC staff's approval of VYNPC's silt disposal request is granted provided } the enclosed replacement SE is permanently incorporated into Vermont Yankee's p g Offsite Dose Calculation Manual as an appendix. Any modification to the L proposed action that may be considered in the future must have prior NRC staff
)
I approval. ! I Pursuant to the provisions of 10 CFR Part 51, the Commission has published in the Federal Reaister an Environmental Assessment and Finding of No Significant { Impact (61 FR 6662). ( , s.
u c l L D. Reid . F. L If you have any further questions regarding this matter, please contact r Mr. Kahtan Jabbour at (301) 415-1496. L-Sincerely, E emN - Patrick D. Milano, Acting Director E ' Project Directorate I-3 Division.of Reactor Projects - I/II Office of Nuclear Reactor Regulation E Docket No. 50-271 E
Enclosure:
Safety Evaluation u See next page j cc w/ enc 1: ,. l L . 1 1 r L b E E E 1 E. I i [L E.
Vermont Yankee Nuclear Power Vermont Yankee Nuclear Power Station Corporation CC: Mr. Peter LaPorte, Director Regional Administrator, Region 1 ATTN: James Muckerheide U. S. Nuclear Regulatory Commission Massachusetts Emergency Management 475 Allendale Road Agency King of Prussia, PA 19406 400 Worcester Rd. P.O. Box 1496 R. K. Gad, III Framingham, MA 01701-0317 Ropes & Gray-One International Place Mr. Raymond N. McCandless .
~ Boston, MA '02110-2624 Vermont Division of Occupational and Radiological Health Mr. Richard P. Sedano, Commissioner Administration Building Vermont Department of Public Service Montpelier, VT 05602 120 State Street, 3rd Floor Mr. J. J. Duffy Montpelier, VT 05602 Licensing Engineer Public Service Board Vermont Yankee Nuclear Power State of Vermont Corporation 120 State Street 580 Main Street Montpelier, VT 05602 Bolton, MA 01740-1398 Chairman, Board of Selectmen Mr. Robert J. Wanczyk Town of Vernon Director of Safety and Regulatory P.O. Box 116 Affairs Vornon, VT 05354-0116 Vermont Yankee Nuclear Power Corp.
Ferry Road Mr. Richard E. McCullough Brattleboro, VT 05301 d Operating Experience Coordinator Vermont Yankee Nuclear Power Station Mr. Ross B. Barkhurst, President P.O. Box 157 Vermont Yankee Nuclear Power Governor Hunt Road Corporation Vernon, VT 05354 Ferry Road , Brattleboro, VT 05301 ! G. Dana Bisbee, Esq. Deputy Attorney General Mr. Gregory A. Haret, Plant Manager
'33 Capitol Street Vermont Yankee Nuclear Power Station l
Concord, NH .03301-6937 P.O. Box 157
- Governor Hunt Road Resident Inspector .
Vern'on, VT 05354 Vermont Yankee Nuclear Power Station U.S. Nuclear Regulatory Commission P.O. Box 176 Vernon, VT 05354 Chief, Safety Unit Office of the Attorney General
'One Ashburton Place, 19th Floor Boston, MA 02108
L I I. e acog UNITED STATES "p I
- NUCLEAR REGULATORY COMMISSION
-;j WASHINGTON, D.C. 20C%-0001 j $ .
L \, * * *.** / r SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION Bf16T.ED TO ONSITE DISPOSAL OF SLIGHTLY CONTAMINATED COOLING TOWER SI VERMONT YANKEE NUCLEAR POWER CORPORATION [ VERMONT YANKEE NUCLEAR POWER STATION r DOCKET NO. 50-271 ( F 1
1.0 INTRODUCTION
F By letter dated August 30, 1995, Vermont Yankee Nuclear Power Corporation ' (VYNPC) requested approval for the onsite disposal of slightly contaminated silt material removed from Vermont Yankee Nuclear Power Station's (Vermont r Yankee's) cooling towers. In a safety evaluation (SE) dated March 4,1996, L the NRC staff approved the proposed silt disposal. However, because of discrepancies between the SE and VYNPC's letter of August 30, 1995, VYNPC ~ postponed implementation of the silt disposal until resolution of the ! discrepancies. By letter dated August 2,1996, VYNPC informed the NRC staff
- of the discrepancies and requested that the SE be revised accordingly.
Recognizing the discrepancies, the NRC staff has prepared this SE to resolve the discrepancies and to replace the SE of March 4,1996. [
2.0 BACKGROUND
7 L VYNPC has previously obtained NRC staff approval of the onsite disposal of very-low-level radioactive material similar to the proposed silt disposal. By letter dated June 28, 1989, VYNPC proposed the onsite disposal of slightly -
~ contaminated septic waste material by land application at Vermont Yankee. By
(- letter dated August 30, 1989, the NRC staff approved this request pursuant to 10 CFR 20.302.(now 10 CFR 20.2002). The NRC staff considered this site-specific application for Vermont Yankee to have insignificant radiological [ impact because the proposed septic waste material disposal involved licensed material containing less than 0.1 percent of the radioactive material,
. primarily cobalt-60 and cesium-137, already considered acceptable in the Final
[- Environmental Statement (FES) of July-1972, and involved exposure pathways much less significant than those in the FES. In addition, the proposed septic waste material disposal satisfied the following applicable boundary conditions for the disposal of licensed material: [
- a. The whole body dose to the hypothetical maximally exposed individual must be less the 1.0 mrem / year.
{ E g__- _____ __
r g F' L
. r L b. Doses to the whole body and any organ of an inadvertent intruder from the probable pathways of exposure are less than 5 mrem / year.
- c. The disposal must be at the same' site.
Following the NRC staff's approval on August 30, 1989, VYNPC implemented the [ disposal of the contaminated septic waste material as proposed. < r By letter dated August 30, 1995, VYNPC requested that the previous L' authorization for the onsite disposal of very-low-level radioactive material be amended to permit the onsite disposal of slightly contaminated silt 4 traterial, within the boundary conditions of the previously approved septic r L waste eaterial disposal. 3.0 EVALUATION I L In its letter of August 30, 1995, VYNPC stated that the proposed silt disposal 1 method is the same as the previously approved septic waste disposal method, r and utilizes land spreading in the same onsite areas approved for septic waste ; L disposal. The volume of silt proposed for onsite disposal consists of 14,000 cubic feet (396 cubic meters) accumulated through August 1995 plus approximately 4,000 cubic feet (113 cubic meters) to be removed from the cooling towers during each 18-month operating cycle. The activity. contained [ in the currently accumulated silt, based on samples taken by VYNPC in June 1995, is 0.193 mil 11 curies, principally from 0.034 mil 11 curies of cobalt-60 and 0.159 mil 11 curies of cesium-137. The activity contained in the additional L silt to be removed from the cooling towers each 18-month operating cycle is anticipated to be 0.059 millicuries, principally from 0.012 millicuries of
- cobalt-60 and 0.047 mil 11 curies of cesium-137.
b VYNPC's radiological assessment enclosed with its August 30, 1995, letter demonstrates that the combined radiological impact for all onsite disposal F cperations, the proposed disposal of silt and the previously approved-disposal of. septic waste material, will continue to meet the applicable boundary Therefore, conditions (given above) for the disposal of licensed material. the proposed onsite disposal of slightly contaminated silt is acceptable. As discussed in VYNPC's letter of August 2, 1996, if the onsite disposal.of l cooling tower silt or septic waste material would result in exceeding the applicable boundary conditions (given above), then VYNPC must obtain prior NRC {
)
staff approval of the disposal. In addition, VYNPC made the following i commitments: f-
$ a. VYNPC will~ report in the Annual Radiological Effluent Release 3g . Report a list of the radionuclides present and the' total radioactivity associated with the onsite disposal activities kgu: , at. Vermont Yankee.
m_ ~- _A_ _-__m _ ___ _ _ _ _ ________ _ _ __ -
W
.o c.
w i F t '
- b. VYNPC will maintain records of radionuclide concentrations and 0- total activity associated with onsite disposal. activities at Vermont Yankee in accordance with 10 CFR 50.75(g).
u
4.0 CONCLUSION
I ' The NRC staff finds that the radiological conditions at the Vermont Yankee site (see' attachment) that would result from the onsite disposal of slightly contaminated silt material, .as proposed by YYNPC pursuant to 10 CFR 20.2002, ; m L and the previously approved onsite disposal of slightly contaminated septic waste material, are within the applicable boundary conditions (given above) for the disposal of licensed material. Therefore, the proposed onsite E disposal of slightly contaminated silt removed from Vermont Yankee's cooling towers is acceptable. VYNPC is required to permanently incorporate this SE into the Vermont Yankee ! Offsite Dose Calculation Manual as an Appendix to document the the radioactive ' material onsite disposal activities approved for Vermont Yankee, and VYNPC s related commitments regarding reporting and _ record keeping. Any additional modification of VYNPC's. disposal activities which go beyond those proposed in the August 30, 1995, submittal, and are not addressed above must have prior NRC staff ~ approval. In addition, any onsite disposal of cooling ' tower silt or septic waste material that would result in exceeding the applicable boundary H conditions (given above), must also have prior NRC staff approval. r Principal Contributors: J. Minns D. Dorman C. Harbuck 4 Date: June 18, 1997 ) I " {
Attachment:
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fERMONT YANKEE FS 30 N'S 3 ~Y LBJ M44 CwsGD $UCLEAR POWER CORPORATION
.- Ferry Road. Brattleboro. VT 05301-7002 ENGINEERING OFFICE
[ - 580 MMN STREET 00LTON. MA 01740 l * (508) 779-6711 l August 30,1995 BVY 95 - 97 United States Nuclear Regulatory Commission Washington,DC 20555 ATrN: Document Control Desk
References:
(1) License No. DPR-28 (Docket No. 50-271) (2) Letter fmm R. W. Capstick, Vermont Yankee, to USNRC, " Request to Routinely Dispose of Slightly Contaminated waste in Accordance with 10CFR20.302(a)", BVY 89-59, June 18,1989. (3) Letter fmm M. B. Fairtile, USNRC, to L.A.Tremblay, Vermont Yankee, "Appmval Under 10 CFR 20.302(a) of Procedures for Disposal of Slightly Contaminated Septic Waste On Site at Vermont Yankee (TAC No. 73776)", dated August 30,1989.
Subject:
Request to Amend Previous Approval Gmnted Under 10 CFR 20.302(a) for Disposal of Contaminated Septic Waste 1 < In acconiance with the criteria of the Code of Federal Regulations, Title 10, Section 20.2002 (previously cited 10CFR20.302(a)), enclosed please find the subject application to amend the previously granted appmval(Reference 3) to dispose of slightly contaminated septic waste on site at Vermont Yankee by exaanding the allowable waste stream to include slightly contaminated Cooling Tower silt materia.. This application specifically requests approval to dispose of Cooling Tower silt deposits, L contaminated at minimallevels, which have been or might be generated thmugh the end of station I operations at the Vermont Yankee Nuclear Power Plant. The proposed silt disposal method is the same as the septic waste disposal method requested in Reference 2 and approved in Reference 3. } 'Ihe disposal method utilizes on site land spreading in the same designated areas used for septic l waste. Disposal of this waste in the manner proposed, rather than holding it for future disposal at a 10CFR Part 61 licensed facility when access to one becomes available, will save substantial costs and valuable disposal site space for waste of higher radioactivity levels. A radiological assessment and pmposed operational contmis based on continued on site disposal of accumulated river silt removed from the basins of the plant's mechanical daft cooling towers is L contained in Enclosure A. The assessment demonstrates that the dose impact expected from die disposal of silt removed from the cooling towers during normal maintenance will not exceed the dose limits already imposed for septic waste disposal. The combined radiological impact for all on site disposal operations shall be limited to a total body or organ dose of a maximally exposed member of the public of less than one mrem / year during the period of active Vermont Yankee
k I t ! VERMONT YANKEE NUCLEAR POWER CORPORATION I L septic waste (References 2 and 3) for your use and reference in evaluating the pmposed amendment.
~
r Upon receipt of your approval, Enclosure A will be incorporated into the Vermont Yankee ODCM. f We trust that the information contained in the submittalis sufficient, however, should you have i any questions or require further information conceming this matter, please contact this office. Sincerely, r VERMONT YANKEE NUCLEAR POWER CORPORATION
?/ f/Wc' "
f- James J. Duffy Licensing Engineer i Enclosures A & B g c: USNRC Region I Administrator (L:tter and Enclosure A) USNRC Resident Inspector - VYNPS (Ixtter and Enclosure A) e USNRC Project Manager - VYNPS (Letter and Enclosure A) I r L I L f L. l .
r L t F L r L ENCLOSURE A VERMONT YANKEE NUCLEAR POWER PLANT e F ASSESSMENT OF ROUTINE DISPOS AL OF COOLING TOWER SILT IN L AREAS ON Sill? PREVIOUSLY DESIGNATED FOR SEFFIC WASTE DISPOSAL 6 M W r L r b [ [ r L E---_---------_---------_----------_---_--___
-I I- , l I I Table of Contents 1 Page lI 3
1.0 INTRODUCTION
4 l 2. 0. WASTE STREAM DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 DISPOSAL METHOD ........................................... 9 l. 3.1 Silt Disposal Procedure Requirements ................ 9 3.2 Administrative Procedure Requirements ............... 12 4.0 EVAWATION OF ENVIRONMENTAL IMPACTS . . . . . . . . . . . . . . . . . . . . . . . 13 4.1 Site Characteristics ................................ 13 1 I
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4.2 Radiological Impact ................................. 13 l l
- 5. 0 RADIATION PROTECTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23
'6.0 CONCMSIONS ............................................... 23
7.0 REFERENCES
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t I 1 I f l I I .I l 1 I I
E VERMONT YANKEE NUCLFAR POWER PLANT Assessment of Routine Disposal of Cooline Tower Silt In Areas On Site Previousiv Designated fc,r Sentic Waste Disposal
1.0 INTRODUCTION
Vermont Yankee Nuclear Power Corporation (Vermont Yankee) requested from the NRC in 1989 permission to routinely dispose of slightly contaminated septic vaste in designated on site areas in accordance with 10CFR20.302(a). The l NRC responded to this request on August 30, 1989 by granting approval of the t proposed procedures for on site disposal of septic waste concluding that the L commitmenes as documented in our request were accept,31e, provided that our request and analysis be permanently incorporated into the plant's Offsite Dose Calculation Manual (ODCM). Revision 9 to the ODCM (Appendix B) incor-porated the assessment and approval of the methods utilized for on site dis-pose of slightly contaminated sewage sludge. In addition to the previously identified solids content of septic waste as a i cource of environmental lov level radioactive contaminated material, cooling l tower silt deposits resulting from the settling of solids from river water , passing through the mechanical draft cooling tower system have been identi- ' fied to also contain low levels of plant specific radionuclides. Periodic removal of the silt from the cooling tower basins is a necessary maintenance practice to insure operability of the cooling system. However, due to the ' presence of by-product materials in the silt, proper disposal requirements l must be applied to insure that the potential radiological impact is within ccceptable limits. l This assessment of silt disposal expands the original septic waste disposal . cssessment to include earthen type materials (cooling tower silt deposits) l while maintaining the original radiological assessment modeling and dose limit criteria that have been approved for septic waste spreading on site. This assessment demonstrates that cooling tower silt can be disposed of in {.' the same manner, and under the same dose limit criteria as previously ap-proved for septic waste in Appendix B to the Vermont Yankee ODCM. Implemen-tation of the following commitments as an amendment to the original 10 CFR L , ..
Part 20,302(a) approval for septic waste shall be incorporated into the 4 Vermont Yankee ODCM upon approval by the NRC. 2.0 WASTE STREAM DESCRIPTION: The waste involved in~this assessment is residual solids (silt) collected in ']
'the basins of the plant's mechanical draft cooling tower system. The silt !
' consists of organic and inorganic sediments and earthen type materials that
.have settled from the cooling water flow taken from the Connecticut River as-h it passes through the towers. As a result of de-sludging of the tower f
. basins in 1993, an estimated 14,000 cubic feet of silt was accumulated on
. cite. Clean-out operations will also occur periodically to ensure continued l system operability. Sample analysis performed to the plant's environmental j lower limits -of detection requirements, as contained 'in Technical Specifica-p tion Table 4.9.3., has identified Cobalt-60 and Cesium-137 in low concentra-e tions as being present in silt collected in 1993. 1
(;' The cooling towers are located at the southern and of the plant facility j
. complex, but are not directly connected to any system in the plant that ,'
b contains radioactivity. The postulated mechanism of how plant-related - j radionuclides .have been introduced into the cooling system silt assumes that { - past routine effluents discharged from nearby plant gaseous release points
. ware entrained in the large mechanically induced air flow that is pulled
.through the. towers as a heat exchange medium. The cooling water flow pro-
-vides a scrubbing action as-it is breaks up into fine water droplets due to the splash pans of the towers. This scrubbing action washes any airborne
- h. :particulates out of-the air. Over long periods of operation, any radioac -
' tivity removed from the air flow could buildup to' measurable levels in silt that-settles out in the basins at the bottom of the towers.
{
' Table 1 lists'the; analyses of twenty-one samples collected from the silt
,- pile removed from the cooling tower basins. . Radioactivity measurements,' i
. lcveraged over. ell-the samples, indicate that the silt material can be char-
. ceterized as containing approximately. 50 pCi/kg (dry wt.) of Cobalt-60,' and "D 198 pCi/kg (dry we.) Cesium-137. Eight of the samples indicated no positive-Cobalt-60:LaboveLa minimum detectable level achieved for the analysis.
x
a 2 Table 1
-Cooling Tower' Silt Radioactivity
'(1993 samples *)
Sample'#' Co.60 Cs.137 (pCi/kg dry) (pCi/kg dry) G12759 53 144
.G12758' 72 172 G12757 <14 201 G12756 <17 245 G12755 73 206
'G12754- <16 165 G12753 <27 240 G12752- 79 181 G12751 <29 180 G12750 35 107 1
012749L 59 171 G12748 419 205 C12747- <38 209 G12746 <7 218 G12745 50 241 G12744 40 220 G12743 68 264 , i G12742 45 195 G12724 71 115 G12723 104 264 G13940'. 126 218- ! 1
-50 198 .;
Average:
' Max. 126 264
<7 107 l
> Min- )
f Standard deviation: 30 42 l LO-Average wet to dry sample weight: ratio equal to 1.6. ' Dry. weight silt density equal-to 1.3 gm/cc.
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L ! L
- For. the purpose of estimating the total activity in the silt pile, the less th:n values =in Table 1 are included as positives- in the calculation of the j
~
'cvarage radioactivity concentration.
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' Cobalt.60, due to its relatin ly short half life, is typically associated
{ with plant operations when mecsured in the near environment. However, Cecium-137 when measured in the environment may have a background component -j [I th:t is not related.to power plant operations. Past weapons testing fallout ! 1 h:u imposed a man made background level of Cesium-137 in New England soils l cnd sediments that can vary over several hundred pCi/kg. The plant's Envi-r nmental Monitoring Program'has shown that Connecticut River sediment in ths. vicinity of Vermont Yankee averair,es about 123 pCi/kg (dry wt.) of Cesi-um-137 (Table 2), with no plant related detectable level of Cobalt-60. The vslue of 123: pCi/kg may represent an estimate of the background level of Csolum 137 in sediment that would be subject to entrainment in cooling water
.ficv that enters the plant. In comparing the measured levels of Cesium-137 en Table 1 with the' past river sediment level, the average concentration in
. th2 cooling tower silt is higher than that of the river sedfsent data, but does fall within the observed range of recorded sediment Cs-137. The river r- cediment Cesium-137 concentration averages about 62% of the concentration
[ value detected in the tower silt. For purposes of this assessment of plant
'r lated dose' impact from the on site disposal of silt material, it is con- a J
csrvatively assumed that all detectable Cs-137 in cooling tower silt is directly related to plant operations. No background component is subtracted
-from the measured values for this case study since only a single sampling i 1ccation (down stream) is included in the Environmental Monitoring Program
'which may.not fully describe the true background levels in the region.
{ The total radioactivity for the current 14,000 cubic feet of silt collected on site can be' estimated by multiplying this volume by its "as is" density cf 2.1 gm/cc (i.e.1.3 gm/ce' dry weight density- x 1.6 wet / dry weight ratio),
~
'l cnd then conservatively. assume that the measured average dry weight radioac-h tivity concentrations for Cobalt and Cesium would be the same as in the
.es11ectsd silt. Multiplying the average Cobalt-60 and Cesium-137.concen-
' tration ~in silt by the mass of the collected materia 1' produces estimates (Table 3).of total ~ radioactivity that'was removed from the cooling tower b$ sin' iniSepteinber , 1993.
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[ ( { Table 2
~, Cesium-137 in
. Connecticut River Sediments *-
( Date Cs-137: 05/24/94 61 ( 10/13/93 85 06/02/93 60 10/15/92 137 { 05/20/92 176 10/24/91 178 05/16/91 230 10/25/S0 84 05/16/90 62 (. <174 10/04/89 05/26/89 179 7 L 10/12/88 115 05/12/88 62 Average: 123 Max. 230 , Min. 60 Standard deviation: 56 l [
.0 Samples collected as part of the Vermont Yankee Radiological Environmen-
'tal Monitoring Program (REMP) for river sediment sample location SE-11.
{ (L t; L_ . -
L: [i [: Table 3
-Estimated Total Radioactive Material for 1993 Tower clean-out Volume.of* Mass Average Total Act. Decayed Act.
([ Silt Concentration (as of (as of 11/93) 6/95) { (ft3) (kg) (pci/kg) (uci) (uci) 34 (- Co.60 :14,000 8.32E+5 50 42 Cs-137 14,000 8.32E+5 198 165 159 [- In addition to 14,000 cubic feet of' silt already accumulated, it is antici-pr.ted that' periodic maintenance work in cleaning out the cooling tower { basins will generate approximately 4,000 cubic feet of new silt material -
; over'each successive 18 month operating cycle. Assuming.the same level of plant-related radioactivity concentration that was originally observed, the
, additional amounts of radioactivity that will require on site dispocal h :following each refueling cycle can also be estimated. Table 4 lists an ;
catimate of the total radioactivity that might be present at each 18 month j clean.out cycle, i Table 4 i 1 l Estiented Total Radioactive Material for Each 18 Month Maintenan'ce Cvele
'. . Volume;of- Mass Average Total Activity i Silt ., Concentration-p (ft3). .(kg) (pCi/kg) (uci)
Co-601 4,000- 2.38E+5- 50 12 Cs.137.
=4,000- 2l38E+5 198 47
E [ - 3.0 DISPOSAL METHOD:
- he ~ method of. silt disposal shall utilize a technique of land spreading in a .
- manner consistent with the current commitments for the on site disposal of ocptic waste as approved by the NRC and implemen**d as Appendix B of the -
Varmont Yankee ODCM (Reference 1). The same land areas designated and s.pproved for septic waste disposal shall be used for the placement of silt removed from the cooling tower basins. Determination of the radiological dose; impact shall also be made based on the same models and pathway assump-h . Ctans as indicated in Appendix B of the ODCK. ,
' 3.1 Silt Disoosal Procedure Reautrements:
{ Camma isotopic analysis'of silt samples shall be made prior to each disposal by obtaining representative composite samples in sufficient numbers to characterize the material removed from the cooling tower basins. Each gamma icotopic analysis shall be required to achieve the environmental lower limits of detection as indicated for sediment on' Table 4.9.3 of the Vermont Y:nkee Technical Specifications. The estimation.of total radioactivity to be disposed of shall be made based en the average of all composite sample analyses. The estimation of total rcdicactivity and projected dose impact shall be made prior to placing the es11ected silt on the designated disposal plots. The dose impact from each disposal operation shall be included with all past septic waste and silt ! cpreading operations to ensure that the appropriate dose limits are not h exceeded on any waste disposal area for the combination of all past opera- ;
. tions.
i
'l
, n e established dose criteria requires that all applications of earthen' type '
- ' materials within the' approved designated disposal areas shall be limited to
' snsure that dose'to a' maximally exposed individual (during the Vermont Ycnkee control period) be maintained less-than 1-mrem / year to the whole body cnd any organ, and the dose to an inadvertent intruder following termination
{ taf ice control beimaintaihed less than 5 arem/ year to the whole body and cny. organ. !
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' The limits on concentrations of radionuclides as addressed in Appendix B to
--. the ODCM for septic waste (i.e.' each tank of septic sludge to be disposed cre limited to a combined MPC ratio of less than 0.1) were included to
;cnsure proper control.was in-place to address the situation of small quanti-
[ ties 'of reletively high concentration material. This limitation does not , directly apply.to silt deposits since the slit is handled as dewatered cadiments as. opposed to liquid slurries of septic waste. Fcr dry earthen type material such as silt, a specific radionuclide concen- [- tration limit shall be applied'in place of the of.the septic waste liquid MPC ratio. No soil associated with a sample analysis that identifies a plant related radionuclide in excess of the concentration limits of Table 5 will-be-permitteo regardless of the total pathway dose assessment determined = fer the quantity material under consideration. For the case where more than ( cne radionuclide is detected, the sum of the ratio rule will be applied.
'The measured concentration of each radionuclide divided by its limiting eencontration value shall be added with the sum of all fractions equal to or Icas than 1. . This limiting condition ~ will prevent small volumes of rela-
' tively high specific radioactivity from being spread on the disposal- plots, b.. cud therefore reduce the potential for creating unexpected hot spots of
.ccncentrated material.
A Tcble 5 lists, by.radionuclide, soil concentration values that would gener- ;
- -cte an annual external effective dose equivalent of 25 area / year if it were l
assumed that an individual continuously stood on an infinite plane of soil ! ccntaminated to a depth of 15 ca. . The assumptions of an infinite plane and
' continuous' occupancy are conservative for situations where the amount of j h
contaminated soil identified would not provide for a 15 cm soil depth over l cn extended surface' area, and where disposal site acesas is limited. -Twen- J
? ;ty-five arem/ year was selected as'a reference value based on the fact that Lit was aLauitable fraction of the NRC annual dose limit (100 mrem / year per
.10'CFR'Part 20.1301). applied to members of.the.public from all station h
-c urces'.- The. 25 mres/ year also equals. the EPA dose limit from 40 CFR Part 190: which would apply. to real- members of the public offsite; and allow for ' i I credit to be taken iri accounting for. actual . usage patterns such .as occupancy -
- f. time' i The externa 1Tdose factors provided.on. Table 5 were derived.from' Table h $E-2 of NUREC/CR-5512L(Reference 13),
a +
,a e
.m - _ _ _ _ _ _ _ . _ _ _-_ ___ -_ . - m -
p [ (.. . Table 5 Dry Soil Maximum Concentration Values f Radionuclide Soil Concentration PCi/kg (eaual to 25 mrem /vri Cr-51 1.51EM S Mn-54 5.50E+03 Fe-59 3.83E+03 f' Co-58 4.70E+03 CO-60 1.82E+03 Zn-65 7.85E+03 { Zr-95 6.18E+03 Ag-110m 1.66E+03 Sb-124- 2.51E+03 Cs-134 2.95E+03 Cs-137 8.13EM3 f Ce-141 7.85E+04 Ce-144 8.75E+04 f- l
' Assumptions include infinite planar distribution, uniform depth distribution to 15 cm, sofi density at 1.625EM6 gm/m3, external 1
-direct dose pathway only with a 100% occupancy factor.
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I I 3.2 Administrative Procedure Reauirernents: Dry silt material shall be dispersed using typical agricultural dry bulk surface spreading practices only in approved disposal areas on site. Complete records of each disposal will be maintained. These records will include the concentration of radionuclides detected in the silt, an estimate of the total volume of silt disposed of, the total radioactivity in each
.I disposal operation as well as the total accumulated on each disposal plot .it the time of the spreading, the plot on which the silt was applied, and the results of any dose calculations or maximum allowable accumulated activity determinations required to demonstrate that the dose limits imposed on these land spreading operations have not been exceeded. The determination of the I total radioactivity and dose calculations shall also include all past septic waste and silt disposal operations that placed low level radioactive materi-al on the designated disposal plots.
The periodic disposal of silt on each of the approved land spreading areas I will be Ifmited to within the same established dose and radioactivity crite-ria that have been approved for septic waste disposal. o Concentration limits that are applied to the disposal of earthen type mate-rials (dry soil) shall restrict the placement of small volumes of material I that have relatively high concentrations of radioactivity such that direct exposure could not exceed a small proportion (25%) of the annual dose limits to members of the public that is contained in 10 CFR Part 20.1301. Any farmer leasing land used for the disposal of silt deposits will be notified of the applicable restrictions placed on the site due to the land spreading of low level contaminated material. These restrictions are the I' same as detailed for septic waste spreading as given in Reference 1. I I _ l p... .
I I I ~ 4.0 EVAIEATION OF ENVIRONMENTAL IMPACTS: 4.1 Site Characteristic 2 The designated disposal sites consist of two fields located on the Vermont Yankee Nuclear Power Plant site. Both ficids are on the plant property within the site boundary security fence. Site A contains an approximate ten-acre parcel of land centered approximately 2,000 feet northwest o5 the I Reactor Building. - Site B consist of approximately two acres and is centered cpproximately 1,500 feet south of the Reactor Building. These are the same land parcels approved by the NRC for the land disposal of septic waste, and cre described in detail in Reference 1 along with the boundary restrictions for the placement of contaminated material. Radiological assessments of septic waste disposal have determined that a j single two-acre plot would be sufficient for the routine disposal of that waste stream over a 20 year period without exceedin5 the dose criteria to a. maximum exposed individual or inadvertent intruder. As a result, the ten-
-I ccre field to the northwest can be divided into five disposal plots, with j the two-acre site at the south end of the plant site providing a sixth plot. I It is therefore concluded that there is sufficient space within the already
*cpproved disposal plots to accommodate additional material from the cooling tower basins along with the septic waste without the likelihood of exceeding
'I the. approved dose limit criteria.
Since the residual organic and inorganic solids associated with river sedi-rent (silt) are similar to the sand and residual orga'nic material remaining cfter decomposition of septic waste that is removed form the plant's septic l tanks, the conclusions of no significant environmental (non-radiological) impact associated with the disposal of septic waste are not changed by the cddition of another earthen type material, namely silt. 4.2 Radiolonical Imoact: The amount of cooling tower silt, in combination with any septic waste disposals,- will be procedurally controlled to insure doses are maintained within the prior approved limits (Reference 1). These limits are based on 11
1 pcst NRC proposed guidance:(described'in AIF/NESP-037,' August 1986). -The d3se criteria require that the maximally exposed member of the general-public receive a. dose less than 1 ares / year to the whole body or any organ
-dueito the' disposed material, and less.than 5 ares / year to the whole body'or-cny organ of an inadvertent intruder.
lTo assess'the doses received'by the maximally exposed individual and inad-i- vartent intruder resulting from silt spreading, the same pathway modeling, casumptions, and dose calculation methods as approved for septic disposal cre used. 'These dose models implement the methodologies and dose conversion fcctors as provided in Regulatory Guide 1.109 (Reference 2). Six potential' pathways have been identified and include: (a) Standing on contaminated ground, L . (b) Inhalation of.resuspended radioactivity, i L* (c). Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and
' (g) Ingestion of cow's milk L-Btsed on the septic waste evaluations, the liquid pathway was determined to bs insignificant.-
l Both the maximum individual and inadvertent intruder are assumed to exposed tp these pathways with difference between them related to occupancy time. The basic assumptions used in the radiological analyses. include:
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.(a) Exposure to ground contamination and resuspended radioactivity is
- for a period of 104 hours per year. during the Vermont Yankee active
- control'of the disposal sites,'and continuous thereafter. The 104 L
hour interval is 3 representative of a farmer's time 7 spend on a plot of land.(4 hours per week for 6 months). 1( ), For the purpose .of projecting and' illustrating the magnitude of - 2 dose l impacts;over the' remaining life of the plant,'it is assumed that: -{ 4 the. current! concentration levels of activity detected in silt remain-
~
;j os
. f
? t-
I J 1 i i constant. Table 1 indicates the measured radioactivity levels for j g'm Cobalt-60 and Cesium-137 first noted in silt material. l (c) The maximum radiation source corresponds to the accumulation of radioactive material on a single plot (two acre) within the approved disposal sites over a period of 13 operating cycles. This extends over the next 18 years until after the operatin6 license expires in 2012. The initial application (referenced to June, 1995) consists of I 14,000 cubic feet of silt collected in 1993 along with the first periodic clean out of the tower basins that adds an additional 4,000 I
, cubic feet. All subsequent applications of 4,000 cubic feet occur at l
18 month intervals. (d) For the analysis of the radiological impact during the Vermont Yankee active control of the disposal sites, no plowing is assumed to take place and all dispersed radioactive material remains on the surface, forming a source of unshielded direct radiation. (e) No radioactive material is dispersed directly on crops for human or animal consumption. Crop contamination is only through root up-take. (f) The deposition on crops of suspended radioactivity is insignifi-cantly small. (g) Pathway data and usage factors used in the analysis are the same as those used in the plant's ODCM assessment of off-site radiological impact from routine releases, with the exception that the f'raction of stored vegetables grown on the contaminated land was conservatively increased from 0.76 to 1.0 (at present no veSetable crops for human I consumption are grown on any of the approved disposal plots) . (h) It is conservatively assumed that Vermont Yankee relinquishes control of the disposal sites after the operating license expires in 2012. (i.e., the source term accumulated on a single 2 acre disposal I plot applies also for the inadvertent intruder). I
[ ,
.(i) For the ! analysis o.f the impact after Vermont Yankee control of the site is relinquished, the radioactive. material is plowed under and forms a uniform mix with the top six inches of soil; but nonetheless,
. undergoes resuspension in air at the same rate as the unplowed surface contamination. For direct ground plane exposure the self shielding due to the six inch plow layer reduces the surface dose rate by about a factor of four,
'Ihe dose models and methods used to generate deposition values and accumu-f'
' lated activity over the operating life of the plant are documents in Attach-ment 2 to Reference 1. Based on the measured concentrations and silt volumes noted in Sect: ion 2.0 above, the total radioactivity that remains on the -l disposal plots after the operating license expires is estimated on Table 6.
[ Table 6 Protected Radioactivity Buildun Due To Silt Screading Nuclide Contribution from Accumulation from 13 Total Remaining initial 14,000 ft3 cycles at 4,000 ft3/ea. in year 2013
-(uci) (uci) (uci) l Cobalt.60 3.2 61.9 65.1
- Cisium.137.' 104.9 '500.5 605.4 i
p' The . calculated potential radiation exposure following the spreading of all i . cilt material; anticipated to be generated th' ough the remainder of the
, cperating' license 'on a single.two acre plot is provides on' Table 7.
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Table 7 Dose Imoact Due to Continued Screading to End of License-Discosal Site' Access Radiation Excosure Individual /Orran
'Crntrolled by VYNPS 0.228. arem/yr adult /whole body (max.' exposed individual) 0.820 mres/yr max. child / bone
' Uncontrolled' by VYNPS 1.46 mres/yr adult /whole body (inadvertent intruder after 2.41 mrem /yr max child / bone
-license termination)
-The' individual pathway contributions to the total dose due to continued silt cpreading are shown on Table 8:
Table 8 Pathwav-Decendent Critical Orean Doses
. Maximally exposed Inadvertent Intruder Individual / Organ Critical Individual / Organ (Child / Bone) (Child / Bone)
Zathway (arem/vear) (arem/ve'ar) Ground Irradiation 0.0474 0.957 Inhalation 0.00814 0.685
. Stored; Vegetables 0.528' O.528 Lleafy. Vegetables. 0.0265 0.0265 Milk Ingestion :0.201 0.201 Meat Ingestion 0.00833'., 0.00833 T tal: -O.82 .2.41 0,
%. t
' 1 *9
p p In addition, the isotopic breakdown.of the critical' organ doses listed above
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(Table 8)-for the two detected radionuclides is seen to be: Table 9 I i Isotonic Breakdown of Maximum Radiation Exoosures Radioactivity Dose. Percent of Descriotion Isotone (uci/2 acres) (mrem /vri total J l During control Cs-137 605.4 0.805 98.2 l Co-60 65.1 0.0144 1.8 of disposal sites Max. organ: child / bone O.82 I
* -Termination of. Cs-137 605.4 2.12 88.0 1
disposal site Co-60 65.1 0.29 12.0 Max. organ: child / bone 2.41 f. {.- For comparison to the total dose calculated assuming the continued disposal of 'sile removed from the tower basins through the end of the operating license, the dose from just the original 14,000 cubic feet collected is !
.chown.on Table 10.
l t 18}}