ML20214N310
| ML20214N310 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1986 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20214N282 | List: |
| References | |
| NUDOCS 8706020133 | |
| Download: ML20214N310 (164) | |
Text
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SUPPLEMENTAL REPORT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS, 1986 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN FOR 1986 Vermont Yankee Nuclear Power Station 4436R 8706020133 870526 PDR ADOCK 05000271 g PDR
ERRATA In the Vermont Yankee Effluent and Waste Disposal Semiannual Report covering the first and second quarters of 1986, the following corrections should be made:
To Table 3:
See next page for Table 3, Revision 1.
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TABl.E 3 Vermont Yankee Effluent and Waste Disposal Semiannual Report First and Second Quarters, 1986 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)
Unit 6-Month Est. Total Period Error, %
- 1. Type of Waste
- a. Spent resins, filter sludges, evaporator m3 2.93E+01 bottoms, etc. C1 2.10E+02 27.50E+01
- b. Dry compressible waste, contaminated m3 2.26E+02 equipment, etc. C1 2.96E+01 27.50E+01
- c. Irradiated components, control rods, mJ etc. Ci
- 2. Estimate of Major Nuclide Composition (By Type of Vaste)
- a. Zinc-65 % 4.40E+01 b. Iron-55 % 5.49E+01 Cobalt-60 % 2.36E+01 Cesium-137 % 1.71E+01 Cesium-137 % 1.45E+01 Cobalt-60 % 1.57E+01 Manganese-54 % 8.28E+00 Zinc-65 % 5.82E+00 Iron-55 % 7.27E+00 Manganese-54 % 2.11E+00 Nickel-63 % 3.90E-01 Cesium-134 % 1.30E+00 Cesium-134 % 3.60E-01 Cobalt-58 % 7.40E-01 Plutonium-241 % 2.50E-01 Hydrogen-3 % 4.40E-01 Niobium-95 % 2.40E-01 Zirconium-95 % 3.30E-01
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 15 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information
- 1) Class of solid waste containers shipped: 8A (unstable), 7B
- 2) Types of containers used: 6 Type A, 1 Type B and 8 1.SA
- 3) Solidification agent or absorbent: None Revision 1 -111-4436R
TABLE OF CONTENTS Page ERRATA........................................................... 11 1
1.0 INTRODUCTION
2.0 METEOROLOGICAL DATA.............................................. 2 3.0 DOSE ASSESSMENT.................................................. 3 3.1 Doses From Liquid Effluents................................ 3 3.2 Doses From Noble Cases..................................... 3 3.3 Doses from Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days................................................ 3 3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation.................................................. 5 REFERENCES....................................................... 8 TABLES........................................................... 9 APPENDIX A - SUPPLEMENTAL INFORMATION.................................. A-1 APPENDIX B - LIQUID HOLDUP TANKS....................................... B-1 APPENDIX C - RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION........................................... C-1 APPENDIX D - RADIOACTIVE CASE 0US EFFLUENT MONITORING INSTRUMENTATION........................................... D-1 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM............. E-1 APPENDIX F - LAND USE CENSUS........................................... F-1 AP PENDIX G - PROCES S CONTROL PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-1 APPENDIX H - 0FF-SITE DOSE CALCULATION MANUAL. . . . . . . . . . . . . . . . . . . . . . . . . . H-1 APPENDIX I - RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS......................................... I-1
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LIST OF TABLES Number Title Page 1A Gaseous Effluents - Summation Of All Releases 9 1B Gaseous Effluents - Elevated Releases 10 1C Gaseous Ef fluents - Ground Level Releases 11 1D Gaseous Effluents - Nonroutine Releases 12 8A Liquid Effluents - Summation Of All Releases 13 2B Liquid Effluents - Nonroutine Releases 14 3 Solid Waste and Irradiated Fuel Shipments 15 4 Maximum Off-Site Doses and Dose Commitments to Members of the Public 16-17 5A to 5H Annual Summary of Upper Level Joint Frequency Distribution 18-25 t
0
-v-4436R n....... ..
i VERMONT YANKEE NUCLEAR POWER STATION SEMIANNUAL EFFLUENT RELEASE REPORT JULY - DECEMBER 1986
1.0 INTRODUCTION
Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste for the second six months of the year, with data summarized on a quarterly basis. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 1986. Tables 5A through 5H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 1986.
Radioactive effluents reported in the Semiannual Effluent Report covering the first six months of the year were used to determine the resulting doses for the first half of 1986.
As required by Technical Specification 6.7.C.1 dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the " Vermont Yankee Nuclear Power Station Off-Site Dose Calculation Manual" (0DCM). These dose estimates were made using a " Method II" analysis as described in the ODCM. A " Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 1) and actual measured meteorological data recorded during the reporting period.
As required by Technical Specification 6.7.C.1.b, this report shall also include an assessment of the radiation doses from radioactive effluents to member (s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period no recreational activities inside the site boundary were permitted, and, as a result, no dose assessments are required.
Assessment of radiation doses (including direct radiation) to the likely most exposed real member (s) of the public for the calendar year for the purposes of demonstrating conformance with 40CFR190, " Environmental Radiation Protection Standards for Nuclear Power Operations," are also required to be 4436R
I included in this report if the conditions indicated in Technical Specification 3.8.M.1, " Total Dose " have been exceeded during the year.
Since the conditions indicated in the action statement under Technical Specification 3.8.M.2 were not entered into during the year, no additional radiation dose assessments are required.
All calculated dose estimates for this reporting period are well below the dose criteria of 10 CFR Part 50, Appendix I.
Appendices B through H indicate the status of reportable items per the requirements of Technical Specifications 6.7.C.1 and 6.14.A.
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i 2.0 METEOROLOGICAL DATA Meteorological data was collected during this reporting period from the site's 300-foot met tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (94 meters) and is designed to meet the requirements of Regulatory Guide 1.23 for meteorological monitoring.
X/Q and D/Q values were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model.
All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 1). A source depletion model as described in " Meteorology and Atomic Energy - 1968" (Reference 2) was used to generate deposition factors, assuming a constant deposition velocity of 0.01 m/sec. Changes in terrain elevations in the site environment were also factored into the meteorological models.
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l f 3.0 DOSE ASSESSMENT 3.1 Doses From Liquid Ef fluents There were no routine or accidental liquid releases from Vermont Yankee during 1986. As a result, no receiving water exposure pathways could contribute to any whole body or organ doses to individuals in unrestricted areas.
3.2 Doses From Noble Gases Techr.ical Specification 3.8.F.1 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.8.F.1 assures that the releases of radioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."
Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, and nearest resident in each of the sixteen principle compass directions, as well as the point of highest off-site ground level air concentration of radioactive materials, and for each of the milk animal locations located within five miles of the plant. However, since no noble gases were reported as being above their lower limit of detectability (LLD) for this reporting period, no gamma and beta air doses were determined.
3.3 Doses From Indine-131. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days Technical Specification 3.8.G.1 limits the organ dose to a member of the public from iodine-131, iodine-133, tritium and radionuclides in 4
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particulate form with half-lives greater than 8 days (hereafter called iodines and particulates) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I (7.5 mrem per quarter, and 15 mrem per year). By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.8.G.1 assures that the releases of iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable."
Exposure pathways that could exist as a result of the release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principle compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent Annual Land Use Census as required by Technical Specitication 3.9.D.
Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, the meat pathway was assumed to exist at each milk animal location. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor.
It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding.
This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I2 ) and is available for uptake (see p. 26. Reference 4).
During the first and fourth quarters, the milk animals are assumed to receive only stored feed.
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) The resultant organ doses were determined af ter adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bone, liver, kidney, thyroid, lung and skin for adults, teenagers, children and inf ants. The maximum estimated quarterly and annual organ doses to any age group due to iodines and particulates at any of the off-site receptor locations are reported in Table 4. These estimated organ doses are well below the 10 CFR Part 50, Appendix I dose criteria of Technical Specification 3.8.G.I.
3.4 Whole-Body Doses in Unrestricted Areas From Direct Radiation The major source of dose, consisting of direct radiation and sky shine, from the station is due to N-16 decay in the turbine building. Because of the orientation of the turbine building on the site, and the shielding effects of the adjacent reactor building, only the seven westerly sectors (SSW to NNW) see any significant direct radiation.
High Pressure Ionization Chamber (HPIC) measurements have been made in the plant area in order to estimate the direct radiation from the station.
The chamber was located at a point along the west site boundary which has been determined to receive the maximum direct radiation from the plant. Using measurements of dose rate made while the plant operated at different power levels, from shutdown to 100 percent, the total integrated dose from direct radiation over each three month period was determined by considering the quarterly gross megawatts generated. Field measurements of exposure, in units of Roentgen, were modified by multiplying by 0.6 to obtain whole-body dose equivalents, in units of rem, in accordance with recommendations of HASL Report 305 (Reference 5) for radiation fields resulting from N-16 photons.
Another source of dose, including direct radiation and sky shine, to the site boundary is from low level radioactive waste temporarily stored in the north warehouse. The annual dose is based on a dose per unit curie of waste stored in the north warehouse and determined at the same most restrictive site boundary dose location as that for N-16 shine from the Turbine Building.
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The estimated direct radiation dose from all major sources combined for f
the most limiting site boundary location is listed on Table 4 for each quarter. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any structure.
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REFERENCES f
- 1. Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", U.S. Nuclear Regulatory Commission, Office of Standards Development, March 1976.
- 2. Meteorology and Atomic Energy, 1968, Section 5-3.2.2, " Cloud Depletion",
pg. 204. U. S. Atomic Energy Commission, July 1968.
- 3. C. A. Pelletier, and J. D. Zimbrick, " Kinetics of Environmental Radioiodine Transport Through the Milk-Food Chain", Environmental Surveillance in the Vicinity of Nuclear Facilities, Charles D. Thomas Publishers, Springfield, Illinois, 1970.
- 4. Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", U. S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977.
- 5. W. M. Lowder P. D. Raft, and G. dePlanque Burke, " Determination of N-16 Gamma Radiation Fields at BWR Nuclear Power Stations", Health and Safety Laboratory, Energy Research and Development Administration, Report No.
305, May 1976.
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i TABLE 1A Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarte rs . 1986 Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3 4 Error, %
A. Fission and Activation Gases
- 1. Total release Ci ND ND 21.00E+0:
- 2. AveraRe release rate for period uCi/see ND ND
- 3. Percent of Tech. Spec. limit (1) % - -
B. Iodines
- 1. Total Iodine-131 Ci ND 4.35E-05 z$.00E+01
- 2. Average release rate for period uCi/sec ND 5.54E-06
- 3. Percent of Tech. Spec. limit (2) % 4.03E-02 4.27E-01 C. Particulates
- 1. Particulates with T-1/2 > 8 days Ci '9.89E-04 9.52E-03 5.00E+01
- 2. Average release rate for period uCi/sec 1.26E-04 2.41E-03
- 3. Percent of Tech. Spec. limit % (3) (3)
- 4. Cross alpha radioactivity Ci 2.44E-06 ND D. Tritium
- 1. Total release Ci 8.26E-01 1.27E+00 25.00E+01
- 2. Average release rate for period uCi/sec 1.05E-01 1.62E-01
- 3. Percent of Tech. Spec. limit % (3) (3)
(1) Technical Specification 3.8.F.1.a for gamma air dose. Percent values for Technical Specification 3.8.F.1.a not applicable since no noble gases were detected.
(2) Technical Specification 3.8.G.1 for dose from I-131, I-133, Tritium, and radionuclides in particulate form.
(3) Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulates are included with I-131 above in Part B.
ND Not Detected.
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l TABLE IB Vermont Yankee Effluent and Waste Disposal Semiannual Report
)
Third and Fourth Quarters, 1986 Gaseous Effluents - Elevated Release (1)
Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4
- 1. Fission Cases Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Ci Unidentified Ci Total for period Ci ND ND
- 2. Iodines _
Iodine-131 Ci ND 4.35E-05 Iodine-133 Ci 8.21E-04 1.99E-04 Iodine-135 Ci ND 1.80E-03 Total for period Ci 8.21E-04 2.04E-03
- 3. Particulates Strontium-89 Ci 3.06E-05 2.97E-05 Strontium-90 Ci 2.87E-07 ND Cesium-134 Ci ND ND Cesium-137 Ci 4.67E-05 7.14E-05 Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci 7.43E-05 6.31E-05 Cobalt-60 Ci 7.17E-04 5.01E-03 Zine-65 C1 1.51E-04 2.59E-04 Unidentified C1 (1) There were no batch mode gaseous releases for this reporting period.
ND - Not detected at the plant stack.
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1 TABLE 1C i
Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1986 Caseous Effluents - Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the third or fourth quarters of 1986.
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TABLE ID f Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1986 Gaseous Effluents - Nonroutine Releases There were no nonroutine or accidental gaseous releases during the third or fourtt.
quarters of 1986.
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TABLE 2A Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1986 Liquid Effluents - Nonroutine Releases There were no liquid releases during the third or fourth quarters of 1986.
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4 TAB (E2B Vermont Yankee Effluent and Naste Disposal Semiannual Report
- (' '
Third and Fotteth Quarters 1986' l#I Liquid Effluents - Nonroutine Releases
',?( 'b. '
t There were no nonroutine or accidental releases during the third or fourth quarters of 1986.
s
. \
\
~
k 5
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TABLE 3 Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1986 Solid Waste and Irradiated Fuel Shipments A.~ Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)
Unit 6-Month Est. Total Period Error. %
- 1. Type of Waste
- a. Spent resins, filter sludges, evaporator m3 2.27E+01 bottoms, etc. C1 1.78E+01 27.50E+01
- b. Dry compressible waste, contaminated m3 2.94E+01 equipment, etc. Ci 6.00E+00 27.50E+01
- c. Irradiated components, control rods, mJ 2.24E+00 etc. (Safe ends) Ci 6.94E+01 e7.50E+01
- 2. Estimate of Major Nuclide Composition (By Type of Waste)
- n. Cesium-137 % 3.55E+01 b.(Cont'd) Cesium-137 % 2.60E-01 Cobalt-60 % 2.49E+01 c. Cesium-137 % 4.10E+01 Zine-65 % 2.15E+01 Cobalt-60 % 3.41E+01
-Manganese-54 % 6.08E+00 Iron-55 % 1.29E+01 Iron-55 % 5.78E+00 Zine-65 % 5.58E+00 Cesium-134 % 1.15E+00 Manganese-54 % 2.49E+00 Nickel-63 1 1.70E+00 Cesium-134 % 2.35E+00 Chromium-51 % 1.40E+00 Plutonium-241 % 2.10E-01 Hydrogen-3 % 8.30E-01 Strontium-90 % 2.10E-01 Carbon-14 % 1.80E-01 %
- b. Iron-55 % 7.31E+01 %
Cobalt-60 % 2.18E+01 %
Manganese-54 % 2.76E+00 %
Zine-65 % 1.93E+00 %
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 7 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information
- 1) Class of solid waste containers shipped: 2A (unstable), 3A, 1B, 1C
- 2) Types of containers used: 6 Type A, 1 Strong-tight-container
- 3) Solidification agent or absorbant: None 4436R L
TABl.EJ Vermont Yankee Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1986 Maximum
- Off-Site Doses-and Dose Commitments to Members of the Public Dose (mrem)***
1st 2nd 3rd 4th Source Quarter Quarter Quarter Quarter Year **
Liquid Effluents (a) -- -- -- -- --
Airborne Effluents-Iodines and Particulates 4.24E-03 4.08E-03 3.02E-03 3.20E-02 4.33E-02 (1) (2) (3) (4)
Noble Gases Beta Air
. (mrad) (b) -- -- -- -- --
Gamma Air (mrad) (b) -- -- -- -- --
Whole Body Dose from Facility Direct Radiation (arem) 5.88E-01 1.07E+00 5.12E+00 5.97E+00 1.27E+01
- " Maximum" means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.
- " Maximum" dose for the year is the sum of the maximum doses for each quarter.
This results in a canservative yearly dose estimate, but still well within the limits of 10CFR50.
- The numbered footnotes indicate the location of the dose receptor, age group, and organ, where appropriate.
(1) Skin, NW-2900 meters (2) Skin, NW-2900 meters (3) Skin, S-4000 meters (4) Skin, NW-2900 meters 4436R
.)
i TABLE 4.
1 (Continued)
(a) There.were no' liquid releases during this reporting period.
'(b) There were no detectable noble. gases above the lower limit of detection for i effluents released from the site during this reporting period.- ,
i.
i 4436R l .-. . . - _ - . , _ ,
Table SA VERMONT YAMEE JANii-DEC86- JOINT FREDUEN:Y DISTRI5UTION (UPFIP LEVEL)
- 297.0 FT WINO DATA 'STAEILITY CLAS5 A CLASS FPECUEN Y (PERCENT) = 1.3!
WIND CIPECTICN FR0" SPEED (MFri) > hh! ' hE - ENE E ESE SI SSE S $5d SW W5h W WNi NL N 6.~ vfl. 7;. .
CALM 10- .0 0 0 C 'O 0 C 0 0. 0 0 0 0 'C C .C-(1) 00 00 00 00 00 00 00 00 00 00 00 00 .CC .00 00 0C OC (2) 00 00 00 00 00 00 00 00 C0 00 00 00 00 00 00 00 CC ,
C-3 3 0 1 0 2 1 1 0 0 1 0 0 0 C i 1 C (1)- 2.73 00 91 00 1.82 91 91 00 00 91 .C0 00 00 00 2.73 91 00 -
-(2) 04 00 01 00 02 01 01 00 00 01 00 00 00 00 04 - 01 00 4-7 0 1 0 1 3 3 6 4 0 0 0 0 0 0 3 3 0 ;-
(1) 00 91 00- 91 2.73 2.73 5.45 3.64. 00 00 00 00 00 00 2.73 2.73 00 2 ? E.:
(2) 00- 01 00 01 04 04 07 05 00 00 00 00 00 00 04 04 .fi 2i t'
6-12 3 C 0 0 0 3 4 6 10 0 0 0 0 0 4 1C C (1) 2 73 00 00 00 00 2 73 3.64 5 45 9 09 00 0C 00 00 00 3 64 ?.0? .CC 5. :
(2) 04 O! 00 00 0C 04 C: 0? .12 00 C0 00 0; 0; .C! 12 .C C 13-18 0 0 0 0 0 1 .0 7 6 0 0 0 0 2 2 '3 .0 2' (1) 00 00 00 00 00 91 00 6.36 5.45 00 .00 00 00 1.82 1 82 2.73 00 '8 Ci
- (2) 00 00 00 00 00 01 00 09 07 00 00 00 .00 02 02 04 00 -2 19-24 0 0 0 0 0 0 0 1 0 0 0 0 0 1 3 ( 0 (1) 00 00 00 00 00 00 .00 91 00 00 00 00 00 .91 2.73 5.45 00 10 f' (2) 00 00 00 00 00 00 00 01 00 06 00 00 00 01 04 .C7 00 6T 24 'O- 0 0 0 -0 0 0 0 0 0 0 0 0 0 0 1 0 (1) .00 00 00 00 00 C:. 00 0; 00 00 00 0C 00 00 00 91 C0 (2) 00 - 00 00 00 00 00 00 00 00 .C0 00 .00 00 00 00 01 .C; t 0 $'
ALL SPEEDS- 6 1 1 1 5 8- 11 18 16 1 0 0 0 3 15 24 (1) 5 45 ~ 91 91 91 4.55 7,27 to 00 16.36 14 55 91 00 00 00 2 7313 64 21 E2 C-0 ft: ;-
-(2) 07 01 01 01 06 10 13 22 20 01 00 00 00 04 19 29 .C t
(1)tPERCENT OF ALL 0000 OBSERVATIONS FOR THIS PAGE (2)2 PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PERICD C: CALM (WIND SPEED LESS THAN OR EDUAL T3 60 r:-:
iL
< Trble SB VEf*. Chi TANKEE JANB6-DECli JOIh! FREQUEN:f DISTRIBUTI0n (UPFER LEVEL) 297 0 FT W!bD DATA STABILITT CLASS B CLASS FREQUENCY (PERCENT) = 2 93 L
WIND DIRECTICN Fitt SPEED (PPH) N WhE NE Eh! E ESE SE SSE S SSW SW WSW W WNW NW - hhk VF6. T:~
CALM 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 0C 00 00 00 0C 0:
(2) 0C. CD 00 00 00 0C 00 00 00 00 00 00 00 00 00 00 00 s C-3 4 1 1 1 2 1 0 0 0 0 1 1 0 1 2 3 C (1) 1 67 42 .42 .42 .E4 42 00 00 00 00 42 42 05 42 94 1.Ei ( .' !
(2) 05 01 01 01 02 01 00 00 00 0; 01 0t 00 01 C2 .C4 .C: :
4-7 9 4 1 2 2 9 5 6 3 1 0 0 0 1 1 3 0
(1) 3.77 1.67 .42 84 84 3 77 2.09 2.51 1.26 42 00 00 00 .42 .42 1.26 0: $9.E' (2) .11 .C5 01 02 02 11 0E 07 04 01 00 00 00 01 01 04 00 5-8-12 11 4 1 3 3 7 6 15 15 1 1 0 1 4 3 15 -C ?:
(1) 4.60 1.67 .42 1.2i 1 26 2 93 2 51 6.2E 6 25 .41 .42 00 .42 1.67 1.2E 6.29 (f :" ('
(2) 12 05 01- C4 04 09 07 .12 15 .C1 01 00 .Ct 0! 0* 1E 1:
13-18 13 0 1 1 1 0 1 4 12 1 0 1 1 4 2 13 0
'. (1) - 5.44 00 42 .42 42 00 42 1.67 5.02 .42 00 .42 .42 1.67 84 5.44 00 2: '
(2) .ti 0C 01 01 01 OC _( ?! 15 01 00 .C: 01 .C! 0* if f' F 19-24 3 0 0 0 0 0 0 1 1 0 0 0 1 5 e 6 0 2' (1) 1.26 00 00 00 00 00 00 .42 .42 00 00 .C0 42 2 0? 3 3! 3 3! !. :
(2) 04 00 00 00 00 00 00 01 01 00 00 00 01 06 .10 .10 .C: T GT 24 0 0 0 0 0 C 0 0 0 0 0 0 C 1 ( '
(
(1) 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 .42 C0 (2) 00 00 00 00 0C 00 00 00 00 00 00 00 0C 01 00 01 00 (:
ALL SPEECS 40 .9 4 7 8 17 12 26 31 3 2 2 3 16 16 42 ( :
(1) 16.74 3.77 1.67 2.93 3.35 7.11 5.02 10.88 12 97 1.26 94 ,E8 1 21 6 69 6.6? 1? 9t 00 1(
(2) .49 11 05 .09 10 21 15 32 30 04 02 02 04 20 20 53 00 2 ti
-(1)= PERCENT OF ALL 6000 CBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIO3 C= CALM (WINO SPEED LESS THAN OR EGUAL TO 60 M-
Tcble SC VER Chi TAhKEE JAN86-DECE6 JOIni FAEGJE ct O!!TRIEUTION' (U W R LEVEL 2 2?7.0 FT WI C DATA STABILITY CLASS C CLA!S FRE9t'ECY (PEECENT) = 3 31 WI C DIFECTI N FA07 SPEED (MPH) N NME NE ENE E ESE SE - SSE 5 SS. SW WSW W b% hi N#4 VS.E; ':'
CAA t 0 0 0 0 0 0 C 0 0 0 0 C 0 0 0 C (1) 00 00 00 00 00 00 00 .00 00 00 0C 00 00 00 ~. 00 C0 0:-
(2) 0C _00 .0? 00 .00 00 00 00 00 00 00 00 00 0C 00 .K 0: 1 C-3 3 1 0 2 3 3 2 2 1 2 0 0 0 0 1 1 C (1) 1.11 37 00 74 1.11 1 11 .74 .74 37 .74 00 00 00 0 37 37 .C (2) 04 01 00 02 04 04 02 02 01 .C2 00 00 00 00 01 01 of 4-7 5 4 1 3 5 11 14 4 5 1 1 1 1 1 3 E : O (1) 1.85 1.48 37 1.11 1.85 4.07 5.19 1.48 1.85 37 .37 37 37 37 1.11 2.96 0C 20 '?
(2) 06 05 01 04 06 12 .17 05 06 01 01 0t 01 01 04 ,10 00 f :-
E-12 7 3 6 1 1 8 5 8 15 3 0 0 5 1 5 6- C 74 (1) 2 59 1.11 2.22 37 .37 2 9i 1.85 2.?6 5.5E 1.11 0; .00 1.B! 37 1 8! 2 22 CE 27 4' (2) 09 04 .C7 .C? 01 10 0C 10 1E .C4 00 00 .CE C' 06 .C7 0:
13 6 1 3 5 1 0 0 1 10 6 2 2 2 7 7 14 0 E'
, (1) 2 22 37 1.11 1.25 37 00 00 37 3 70 2 22 74 .74 74 2.59 2.5? ! i' 00 22 :
(2) 07 01 04 .Ci 01 00 00 01 12 - .C7 02 02 -C2 (9 -0f 1? ' 0' 19-24 2 0 1 0 0 0 0 1 4 0 0 0 1 7 9 9 C :
(1) 74 00 37 00 00 00- 00 37 t.46 00 00 00 37. 2 5? 3 33 3.33 0: . 'a (2) 02 00 01 00 00 00 00 01 05 00 00 00 01 09 .11 '.11 00 4 GT 24 1 0 0 0 0 0 0 0 0 0 0 0 0 1 2 2 (- E 4 (1) 37 00 00 00 00 00 00 00 00 . 00 00 00 00 37 74 74 - .C 2*
(2) 01 .00 00 00 00 00 00 00 00 00 00 00 00 .C1 02 .C2- 0:- I ALL SPEEDS 24 9 11 11 10 22 21 16 35 12 3 3 9 17 27 40 C :"
(i) 8 89 3 33 4.07 4 07 3.70 8.15 7.78 .5.93 12.9E 4 44 1 11 1 11 3 33 (.30 10.00 14 21 00 *C:
(2) 29 11 .13 .13 12 27 26 20 43 .15 04 04 11 21 33 .4? 02 23 (1)= PERCENT OF ALL 6000 OBSERVATIONS FOR THIS PAGE (2)= PERCENT CF ALL GOOD 00SERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR E EAL TO 60 N.-
I
Tcble 5D YEI CAT YANFEE JANSE-CEC 64 J0!kT FREQUEk:1 DISTRIfUT!0h (UPPEE LEt'EL) 297.0 FT WIC CATA STABILITY CLAS! D CLASS FRE3CE CY (PER:EC) = 39 51 hI C EIFEti!0% FF:+
SPEED (MPP) N NNE NE ENE E ESE SE $$E S SS. Sd WSW W kNd Nd NWd V51. ? ;~4 .
CA 9 0 0 C 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 0:
(2) 00 00 0* .CC .00 0: CO CC 00 ,00 00 00 0C 00 00 00 C.
C-3 45 32 25 21 34 43 42 36 26 to 11 7 9 17 20 4? C 8' (1) 1.39 99 97 65 1.05 1 33 1.30 1.12 91 143 34 22 2E 53 62 1 33 (:
(2) 55 39 34 26 42 !3 51 .44 32 17 13 09 11 21 24 53 .C0 '?
4-7 9? 26 14 14 35 EE 10' 97 96 22 12 11 11 19 3' 14E C e (1) 3.07 81 43 43 1.21 2.05 3.13 3.01 2.99 62 37 34 34 59 93 4.53 00 24 5:
(2) 1 21 32 17 17 .4E 21 1 24 1 19 1.1E 27 .1 13 13 23 37 1.79 00 ti B-12 113 2! 17 2C 15 35 61 B5 146 5E E 11 42 67 54 191 ( !'
(1) 3.50 77 53 62 .46 1 CE 1 S? 2 63 5 21 1.74 2! 50 1.4? 2 0E 1 67 5 ?2 (. *
(2) 1.35 31 21 24 .18 4? .75 1.04 2 Ci E? 10 20 59 E2 .EE 2 34 13-16 121 11 E 9 '3 7 6 25 64 2C 1 13 53 117 e' 15? C it?
. (1)- 3.75 34 25 25 09 22 25 77 1.99 62 22 40 1.i4 3.63 2-51 4 65 00 21 s ~
(2) 1.4E 13 10 11 04 09 to 31 78 24 11 .ti 65 1.43 ?? t E4 (: i '-
19-24 36 0 1 0 0 0 0 0 19 7 0 1 18 42 25 92 C 24' (1) 1.12 00 03 00 00 00 00 00 59 22, 00 03 56 1.30 77 3 (4 0:- i-(2) 44 00 01 00 00 00 00 00 23 09 00 01 22 51 31 1.20 00 3 -
f
~
GT 24 12 0 0 0 0 ( 0 0 1 0 0 0 10 10 9 26 (
(1) '.37 00 00 00 00 00 00 00 03 00 00 00 31 31 22 87 00 2 (2) 1! 00 00 00 .00 00 00 00 01 00 00 00 12 12 11 34 .00 .E ALL SPEEDS 426 94 6E 64 91 151 212 243 374 119 40 43 149 272 219 6!i 0 "':
(1) 13.21 2 11 2.11 1.98 2.82 4 65 6 57 7 53 11.59 3 69 1.24 1.49 4 62 e 43 6 7! 20 23 00 1C (2) 5.22 1.15 83 .76 1.11 1.85 2.60 2.99 4 58 1.46 49 59 1.22 3.33 2 69 9 03 00 h *~
(1)= PERCENT OF alt. 9000 OISERVATIONS FOR THIS PAGE
'(2)= PERCENT OF ALL 0003 OBSERVATIONS FOR THIS PERIOD C= CALM (WIC SPEED LESS T#w 08 ECLA'. TC E0 P8--
T-ble SE i
VEfMONT YANPEE JANSE-DECSE- J0D'T FREGUENCY DISTRIBUTICN (DeFEi LEVEL) l 2?7.0 FT WIND CATA STABILITY CLA!! E CLAS! FREGUEh:Y (PE8:EhT) = 39.24 WIN: DIEECTION FRCm SPEED (MPH)- N NhE WE ENE E ESE SE SSE $ SSW Sk WSW W WVi NW h6s V8E. ?:'
CALM 0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 ( (
(1) 00 .00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 OC (2) .CC 00 00 0; 00 00 00 0C 00 0; '. 00 00 0 00 00 0(> 0;- 0 C-3 85 of 67 40 52 74 91 59 37 13 IB 14 12 17 3E 63 (
(1) 2 72 1.58 2 15 1.2f 1 E7 2 37 2.91 1 89 1.19 42 55 .45 29 54 1.22 2 (2 0. ::
(21 1.04 59 82 .49 64 91 1 11 72 .45 .tf 22 17 1! 21 47 77 C: f 47 1&2 34 7 15 22 4f 161 112 76 34 13 9 20 35 62 237 0 1t' (1) 5 19 1.09 22 .48 90 1 47 5 16 3 59 2.50 1.09 42 29 64 1.22 1.99 7.59 -00 23 E3 (2) 1 98 42 .09 1B 34 56 1 97 1.37 96 .42 16 .11 24 .47 76 2 to 00 12 9:
'8-12 91 14 3 4 7 14 45 89 122 45 12 12 :: 72 63 22i 0 7 1
(11 2 91 45 .1C .13 22 .4! 1 44 2 E! 3 91 1.44 2! .?S 1.7( 2 2t ~ 2.C2 7 2' (0 : '
(2) 1.1t 17 .C4 .C! .C9 .t7 55 1.09 1 49 55 .t: .15 E7 .f: 77 2 7' -
13-16 33 3 0 0 1 7 13 42 15 1 3 27 75 47 117 0 :
'. (1) 1.06 .10 .0C 00 03 - 00 22 .42 1 35 48 03 .10 86 2 40 1.51 3.7! .C0 ti ~~
(2) 40 04 0C .(: 01 0! 0? 16 5 12 01 04 23 92 55 t 43 :: * '
19-24 5 0 0 0 0 0 0 0 12 2 0 0 1 12 7 32 0 (1) 16 00 00 00 00 .CC 00 00 2E 06 00 00 02 35 22 1.(2 0C : -
(2) 06 00 00 00 00 00 00 00 15 02 0C 00 01 15 09 2? OC r OT 24 1 0 0 0 0 0 0 0 1 (' 0 C 1 5 0 1 ( '
(1) 03 00 ,00 00 .00 00 00 00 03 00 00 00 03 .16 00 .C3 E :
(2)' 0; 00 .00 00 00 00 00 00 01 00 .00 00 01 0i 00 01 .C: 1*
ALL $8EE05 377 99 77 59 89 134 304 273 292 109 44 39 til 219 217 (?G 2:
(1) 12.08 3 17 2 47 1.99 2.82 4 29 9.74 6 74 9-35 3.49 1.41 1 22 3.72 7.C: E 95 21.($ C. '(:
(2) 4.62 1.21 94 .72 1.06 1.64 3.72 3.34 3.58 1.33 54 - 47 1.42 2.65 2.6E 6 20 0: 3- i.
(1)= PERCENT OF ALL 000D 08SERVATIONS FDP THIS PAGE (2)= PERCENT OF ALL 6000 08SERVATIONS FCR THIS PERIOD 'C= CALM (WIND SPEE0 LES? THAN 08 EQUAL TO .E0 Pt-f
7 Trble SF VEPMO*? YANrEE' JANPE-0EC6s JOINT FREQUENCY DIS!!!iUTION (UP8E8 LEVEL) 297.0 FT WIN: DATA STABILITY CLASS F CLASS FREQUEN:Y (8ES ENT) = 12 39 WIN DIRE TION FF2 SPEED (MPH) .N NNE NE EhE E ESE SE SSE 5 S56 SW WSW W WW H NN. VEE. ':-
C-CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 C C C (1) '00 00 00 00 '.00 00 00 00 00 00 00 00 - .00 00 00 00 :
(2) 00 00 00 00 00 00 00 00 00 00 00' 0; 00 00 0:: 0! 0:
C-3 34 26 25 24 19 29 37 25 29 10 13 9 9 14 21 3! 0 (1) 3 36 2.57 2 47 2.37 1.82 2 87 3.6E 2 47 2.77 99 1.29 89 El 1.29 2 05 3 76 .C0 (2) .42 32 31 29 23 36 .45 31 34 12 16 .11 11 17 26 .47 00 d e' 4-7 51 11 5 5 8 24 8! 61 27 E 10 14 15 ti 20 72 C l' (1) 5.04 1.09 .49 .49 .79 2.37 8.41 6.03 2 67 79 99 1.38 1.48 1.58 1.98 7.22 00 42 ?!
-(2) 62 - 13 06 06 10 29 1.04 75 33 .10 12 .17 18 20 24 99 00 5 ?!
8-12 11 0 0 0 1 0 25 22 12 12 7 E 7 20 14 4! C *:'
(1) 1.09 00 00 00 10 00 2 47 2 18 1.19 1.19 69 79 69 1.92 1.35 4 7! C'-
(2) .13 00 00 00 01 00 31 2' 15 1' 0? 10 0* 24 .17 5? 0; ;
13-18 2- 0 0 0 0 ~0 0 0 1 3 0 0 1 5 3 14 0 2; (1) 20 00 00 00 00 00 00 00 10 30 .00 .00 10 .49 30 1.3e 00- : !?
(2) 02 00 00 00 00 00 00 00 01 04 00 00 01 .CE 04 .17 .C e
.19-24 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0 1 C (1)- 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 10 00-(2) 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 01 0C GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) '00
. 00 00 .00 00 00 00 00 00 00 00 00 00 00 00 00 00 ('
(2)- 00 .00 00 00 00 00 00 00 00 00 00 00 00 00 0C 00 00- -(
ALL SPEEDS 96 37 - 30 29 28 53 147 108 68 33 30 31 32 55 58 174 0 (1) 9.69 3 66 2.97 2.67 2 77 5.24 14-54 10 6B 6.73 3 26 2 97 3 07 3.17 5 44 5 74 17.21 00 to:
(2) 1.20 .45 37 36 34 65 1.80 1.32 23 .40 37 38 39 67 71 2.13 0: O:
(1)* PERCENT OF ALL GOOD 00SE8VATIONS FOR THIS PAGE (2)= PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TC 6C *F-
Table SG VEPM0kT TAWEEE JAN86-DECf6 JOINT FIEQUEN:Y DISTRII.TION (U8PEI LEVEL)
- 2?? 0 ri W:e esTA STA!!LIIr cLsgs 0 CLASS FREGUENCY (PEfCENT) = 2.21 b!C CIRECTION FPC6 SPEED (MPH)- N hkE NE ENE E ESE SE SSE S SSW SW WSW W WNW No N6e Vif. T-CA'J 0 0 0 C 0 C 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 0?
(2) 0C 0; 00 00 ' 00 0; 00 0; 0C 00 00 00 .CC 00 40 00 .C. (
C-2 4 3 2 4 5 3 7 8 5 2 2 C 2 4 ! 9 C i f1) 2 14 1.60 1 07 2.14 2 E7 1 ft 2 74 4.2! 2 67 1.07 1.07 00 1.07 2.14 2.(7 4.81 0? b' (2) 05 04 02 05 Of 04 -0? 10 Ci 02 02 00 02 C! C; .11 0' .
4-7 5 1 2 1 1 2 1 12 4 6 4 8 4 4 E 6 0 (1) 2.67 53 1.07 53 53 1.07 - 4.81 6.42 2.14 3.21 2.14 4.28 2.14 2 14 4.28 3.21 .CC 41 if (2) 06 01 02 .01 01 C2 11 15 05 07 05 .10 05 05 10 .C7 .00 .5 6-12. 1 0 0 0 0- 1- 7- 5 2 2 0 3 7 3 4 i 0 -
-(1) .52 .CC 0( 00 0C 53 3.74 2.E7 1.07 1.07 00 1.6C 3 74 1.60 2.14 3.21 0: 2t C T2) 01 C 0" 00 00 P 09 Ci C2 .C2 0; C4 09 04 C! 07 .M '
13-tt 2 0 0 'O 0 0 0 0 0 C 1 0 0 1 0 0 C =
. (1) 1.07 00 00 00 00 00 00 00 00 00 53 00 00 53 00 .C0 cc : **
U (2? C: 00 00 00 00 0? 00 00 00 0! C' 0 0! C' (0 (t 19-24 C 0 0 0' C C 0 0 0 0 0 0 0 0 C 0 0 (11 00 0c Ct 00 0? 0C 0? 00 .CC 0C .Ct 0: 0? OC t' 0* V (2) 00' 0C 00 00 00 00 00. 0C 00 00 00 00 00 00 00 00 00 GT 24 0 0 0 C 0 0 0 0 0 0 0 0 0 t 0 0 ^
(1) 00 00 00 00 00 00 0? 00 00 0: 00 00 00 00 00 00 r*
(2) 00 00 0: 0: 00 0( 00 00 00 00 00 0" 00 .CC 00 .(; J: C'
. ALL SPEEDS 12. 4 4 5 6 E 23 25 11 10 7 11 13 12 17 2t t
(') 8.42 2 14 2 14 2.67 3 21 3 21 12.30 13-37 5 BE 5.35 3.74 5 86 i ?! ( 42 S C' 1122 U (2) .15 05 0! 06 07 07 - 28 31 13 12 09 .13 16 15 21 2i C: .
(1)* PERCENT Or ALL GOOD 08SERVATIONS F0F THIS PAGE (2)= PERCENT OF ALL GOOD Ot!!AVATIONS F09 THIS PERICL Ce CAL > (bl e SPEED LESS T m 08 ER't' 72 f: C i
3 i
t i
4 I
T i
-24 ,
f i-
Tebin 5H VEpci YAVEE JAMBE-DECli J !hi FFEWEC 0:57F:6;'i:0* <t8.:It LEt'EJ
'297.0 FT WIND CATA STAf!LITY CLA!! 4.. CLASS F8E '.E C (8E8:E G = 100 00
.b!N: 0:8ECTICs FF:'
SPEED (m?s) N NNE NE ENE E ESE SE SSE $ 55s fg W!. k Wre ha ku VFF.
C A;*. C 0 0 0 0 C C C 0 0- 0 0 0 C ( ( C (1) 0! .00 00 00 . Or. 0C 00 00 00 10:. .C0 00 00 00 03 00 .C5 (2) OC- 00 C4 00 .00 00 00 00 0: OC .00 0C 00 00 00 . ( *. .(:
C-3 172 111 124 ?2 117 154 120 130 97 42 4! 2* 32 !3 9: 15! -C 'i (1) . 2.12 1.36 1.52 1.13 1.43 1.65 2 20 1 59 1.19 5' .!' St 2? 65 1.10 1 94 00 ; '
(2) 2 18 1.36 1.52 1.13 1.43 1.89 2 20 1.!9 1.19 51 55 32 3? .E5
- 10 1 ?4
- 0f :"
4-7 33' 61 3 41 BC 16t 32' 2!i 211 72 40 47 !! ?! 12' 4?s ( I
(1) 4.05 99 37 50 1.05 1.97 4.67 3.63 2.61 ,38 .49 53 62 97 1.5s 5.83 00 -3! 7:
(2) 4 05 99 37 50 1.0 1.97 4.67 3.63 2 61 .e3 49 53 62 97 1.51 5.23 0:- 2' Y
~8-12 237 4i 27 2E 27 (? 152 230 344 119 25 3! 123 167 147 502 C 2 (1) 2 90 5i ~. 3 2 34 32 E? 1 87 2 22 4 21 1.4i 34 42 1.51 2 C! 1 8? 6 1'- Ci 2~ '
(2) 2 9' 56 3? 34 33 83-1.!? 2 53 4 21 1 4! 34 4E 1 !! 2 C5 1 et i 1! C: .F '
13-1E 177 15 -12 15 E E 16 50 13! 45 13 19 E4 211 142 3t1 ( *:-
(1) 2 17 18 15 18 07 .10 23 61- 1.65 55 .16 23 1.03 2.!f 1.74 3 21 .C0 '! c.
(2) 2.17 16 15 16 .C7 1! 20 61 1.65 55 ti 23 1.02 2 5F 1 74 5 Et G '<
19-24 46 0 2 0 0 0 0 3 36 9 0 1 21 - (7 l2 154 0 :'
(1) 56 00 02 00 00 00 00 04 .44 .11 00 01 26 92 44 1.89 0:' 4 '-
(2) 56 00 02 00 00. 00 00 04 .44 11 00 .C1 26 22 . 64 1 E? C: 4-G1 24 14 0 0 0 ( 0 0 -0 2 0 0 0 11 17 11 23 f f
'(t) .17 0C 00 00 00 00 00 00 02 00 ,00 00 13 21 13 40 E (2) .17 00 0( 00 00 OC 00 00 02 00 00 00 13 21 13 .40 . ( '.
ALL SPEEOS 993 253 195 176 236 391 730 709 827 287 126 132 322 594 56? 1634 C En-(1) 12 04 3.10 2.39 2 16 2 99 4.79 E 94 9 ES 10 13 3 52 1.!4 1.63 3 94 7 27 6.97 2L C1 0:- 1C (
(2) 12.04 3.10 2.39 2.16 2.29 4.79 E.94 B.68 10.13 3.52 1.54 1.63 3.?4 7.27 6.97 20.01 00 10 i -
(1)= PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL 6303 OBSERVATIONS FCE THI! pep!CD C= CALM (WIN 3 SPEED LESS THAN OR EQUAL TO 60 *:a '
1 APPENDIX A
-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Third and Fourth Quarters, 1986 Facility: Vermont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporation 1A. Technical Specification Limits - Dose and Dose Rate Technical Specification and Category Limit
- a. Noble Gases
-3.8.E.1 Total body dose rate 500 mrem /yr 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Gamma air dose 5 mrad in a quarter 3.8.F.1 Gamma air dose 10 mrad in a year 3.8.F.1 Beta air dose 10 mrad in a quarter
-3.8.F.1 Beta air dose 20 mrad in a year
- b. Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a year
- c. Liquids 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 mrem in a year 3.8.B.1 Organ dose 5 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year
. A-1 4436R
2A. Technical Specification Limits - Concentration Technical Specification and Category Limit
- a. Noble Cases No MPC limits
- b. Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days: No MPC limits
- c. Liquids 3.8.A.1 Total fraction of MPC excluding noble gases (10CFR20, Appendix B.
Table II, Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 uCi/cc
- 3. Average Energy Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.
- a. Average gamma energy: 3rd Quarter 1.09E+00 MeV/ dis 4th Quarter 1.22E+00 MeV/ dis
- b. Average beta energy: Not Applicable
- 4. Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
A-2 4436R
1
- a. Fission and Activation Gases Daily samples are drawn at-the discharge of the air ejector.
Isotopic breakdown of the releases are determined from these samples. A logarithmic chart of the stack gas monitor is read daily to determine the gross release rate. .At the very low release rates normally encountered during operation with the augmented-off-gas system the error of release rates may be approximately
!100 percent.
- b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridge are removed weekly (if releases are less than 4 percent of the Tech Spec limit), or daily (if they are greater than 4 percent of the limit), and are analyzed for radioiodine 131, 132, 133, 134, and 135. The iodines found on the filter are added to those on the charcoal cartridge. The error involved in these steps may be approximately 150 percent.
- c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately !50 percent.
- d. Liquid Effluents Radioactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liquid effluents released. For each batch, station records are retained of the total activity (mci) released, concentration (uCi/ml) of gross A-3 4436R
radioactivity, volume (liters),_and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.
Each batch of radioactive liquid effluent released is analyzed for gross gansna and gantna isotopic radioactivity. A monthly-proportional ~ composite sample, comprising an aliquot of'each batch released during a month, is also analyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition to gamma spectroscopy.
There were no liquid releases during the reporting period.
- 5. . Batch Releases
- a. Liquid There were no routine liquid batch releases during the reporting period.
- b. Gaseous There were no routine gaseous batch releases during the reporting period.
- 6. Abnormal Releases
- a. Liquid There were no nonroutine liquid releases during the reporting period.
- b. Gaseous There were no nonroutine gaseous releases during the reporting period.
A-4 4436R
El APPENDIX B LIQUID HOLDUP TANKS Requirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a' description of the events leading to this condition is required in the next Semiannual Effluent Release Report per Technical Specification 6.7.C.1.
Response: The limits of Technical Specification 3.8.D.1 were not exceeded during this reporting period.
I t
i B-1 4436R t
APPENDIX C RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION-Requ'irement : Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3.9.1, an explanation in the next Semiannual Effluent Release Report of 4
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 eff1 vent monitoring instrumentation were met for this reporting period, no response is required.
[
C-1 4436R
APPENDIX D RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be' operable in accordance with Technical Specification Table 3.9.2. If inoperable gaseous 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 Semiannual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.1.
Response: Since the requirements of Technical Specification Table 3.9.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.
D-1 4436R i
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement: The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.9.C. With milk
. samples no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3, Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Report:
(1) identify the cause(s) of the sample (s) no longer being available, (2) identify the new location (s) for obtaining available replacement samples and (3) include revised ODCM
- figure (s) and table (s) reflecting the new location (s).
Response: All required milk samples were available during this reporting period. Changes made to the milk sampling program and-0DCM, as part of the Land Use Census, are described in Appendix H.
E-1 4436R
APPENDIX F LAND USE CENSUS
-Requirement: A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a location (s).which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report.
Response: No locations were identified by the 1986 land use census that would yield at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to Technical Specification 4.8.G.I.
F-1 4436R
APPENDIX G PROCESS CONTROL PROGRAM Requirement: Technical Specification 6.12.A.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.
Response: There was no licensee initiated change (s) to the Process Control Program during this reporting period.
G-1 4436R
APPENDIX H r
OFF-SITE DOSE CALCULATION MANUAL Requirement: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) .
was made effective.
Response:- There were three licensee initiated change (s) to the Off-Site Dose Calculation Manual during this reporting period.
- 1. The changes proposed and implemented for Section 4.0 (Environmental Monitoring) of the ODCM in the Semiannual Radioactive Effluent Release Report for the first and second quarters of 1986 were approved as Revision 1 to the ODCM during the reporting period for this report. These changes were as follows:
- a. Milk sampling locations TM-11 (Miller Farm 0.8 km, WNW) and TM-13 (Newton Farm, 5.1 km, SSE'were replaced with TM-14 (Brown Farm, 2.1 km, SSW) and TM-15 (Coombs Farm, 4.7 km, NW) based on a dosimetric analysis done pursuant to Technical Specification 3.9.D.2 (Land Use Census);
- b. Milk sampling location TM-12 (Whitaker Farm, 2.6 km, S) was also replaced with location TM-13 (Newton Farm, 5.1 km, SSE) when TM-12 went out of business. (The choice of TM-13 as a replacement was based on the dosimetric ranking of available locations done as part of the Land Use Census);
- c. Milk sampling location TM-11 (Miller Farm 0.8 km WNW) and air sampling location AP/CF-15 (Tyler Hill Road, 3.2 km, WNW) were also added to the ODCM as non-Technical Specification locations.
H-1 4436R
l
{ Based on the 1986 Land Use Census, the required milk sampling locations were identified as TM-14 (Brown Farm. 2.1 km, SSW),
TM-15 (Coombs Farm, 4.7 km, NW), and TM-16 (Tall Oaks Farm, 4.7 km, WNW), (TM-21, Moore Farm, remains the control location). Location TM-16 was, therefore, added to Section 4.0 as part of Revision 1, along with the other changes discussed above.
- 2. Additional pages of text were also added to Section 4.0, as Revision 2, to identify the Intercomparison Program which is being participated in and discusses the basis of the Airborne Pathway Monitoring Program.
- 3. The ODCM was also revised in Revision 3 to reflect additional liquid dose pathways, and the clarification of existing basic assumptions involved in gaseous dose and dose rate calculations. These changes are identified as follows:
- a. Section 1 of the ODCM has been expanded to clarify the specific plant and corporate office responsibility assignments and requirements for making changes to the ODCM.
It also includes corrected Table of Contents and summary tables of dose equations, variable definitions, and dose factors necessary to reflect changes made in Chapters 3 and
- 5. It should be noted that new liquid dose factors (Table 1.1-11) have been included resulting from the recent identification of additional exposure pathways not considered in the original ODCM.
- b. Sections 3.1, 3.4, 3.5, and 3.6 have been reworded to clarify the concepts of dose and dose rate as used in the ODCM for implementation of the Technical Specification requirements.
It should also be noted that in addition to the rewording of the explanation of where the noble gas dose rate equations apply, the dose rate equations have also been modified to change the assumption of credit taken from residential H-2 4436R
[
building shielding factor (S ) fr m the value of 0.7 to F
1.0. This additional conservatism to be used in the dose rate calculations is applied on an instantaneous basis since no assurances can be given that the critical receptor will be inside residential structures at all times. For accumulated doses, the use of a 0.7 shielding factor is still applicable.
- c. Sections 3.2 and 3.3 (liquid doses) identifies changes in dose factors to reflect the inclusion of additional exposure pathways not previously identified. These new pathways include the ingestion of vegetables and leafy vegetation which were irrigated by river water, the consumption of milk and meat from cows and beef cattle who had river water available for drinking, as well as having feed grown on irrigated land, and the direct exposure from the ground plane associated with radioactivity deposited by the water pathway.
- d. Sections 3.7 and 3.8 have been expanded to clarify concerns where beta and gamma air doses from noble gases are being calculated based on SJAE nuclide analysis for the determination of radionuclide mix ratios. The expanded Sections 3.7 and 3.8 identifies that the dose calculations should not use the SJAE noble gas release rate determinations directly for determination of off-site noble gas releases as this leads to overly conservative dose calculations which have no direct bearing on actual off-site doses. The radionuclide mix ratios at the SJAE should be used with the plant stack gross release rate (in lieu of detactable gas mixes at the stack) to determine the off-site doses. During periods when the plant is shut down, alternate assumptions on where to obtain radionuclide release six ratios are provided such that off-site doses being calculated are conservative, but still consistent with the gas inventory potentially available for release.
H-3 4436R
e
- e. Section 3.11 has been expanded to address the determination of direct dose off-site from other than N-16 scatter sources in the turbine hall. Fixed sources of direct radiation, such as on-site solid waste storage,-is also required to be considered.
- f. Section 5.2 addresses gaseous effluent monitor setpoint methodology and has been modified to reflect the change in the credit taken for residential building shielding factor as noted above in Item 6.
- g. A new Appendix A is added to the end of the ODCM to provide example calculations of Method I dose equations for reference and guidance information.
None of the above changes will reduce the accuracy or reliability of dose calculations or setpoint determinations.
Revised ODCM pages reflecting the above changes are included as part of this appendix.
H-4 4436R
t VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REV. #1 Reviewed VJ id r.d 2 h rue n, .r. n / tei.? n he Plant OpeFational Review Date Committee Approved I A 3 / /0/Z6/86 '
[/Dlant Manager D6te Approved / wt b / /[7/fIo
/
Vi/:e Pr'esfd,enffand dat'e Manager F ugerations i
3,
( LIST OF AFFECTED PAGES '
y +
Changes, deletions or additions in the most recent revision are indicated by a tar the margin or by a dot near the page number if the entire page is affected. l Pace Revision- Date i - 4.1 0 3/1/84 4.2 - 4.2a 1 10/23/86 4.3 - 4.4 0 3/1/84 4.5 1 10/23/86 4.6 - 6.11 0 3/1/84 t
9 f
"iiia-1
l k Tablo 4.1
- Radioloaical Environmental Monitorino Stations
- Distance From Exposure Pathway Sample Location the Plant Direction From and/or Sample and Designated Code ** Stock (km) the Plant
- 1. AIRBORNE (Radioiodine and Particulate)
AP/CF-11 River Station 1.9 SSE No. 3.3 AP/CF-12 N. Hinsdale, NH 3.6 NNW AP/CF-13 Hinsdale Substation 3.1 E AP/CF-14 Northfield, MA 11.3 SSE
- 1AP/CF-15 Tyler Hill Rd. 3.2 WNW AP/CF-21 Spofford Lake 16.1 NNE
- 2. WATERBORNE
- b. Ground WG-11 Plant Well --
On-site WG-12 Vernon Nursing Well 2.0 SSE WG-21 Brattleboro CC 12.1 NNW
- c. Sediment SE-11 Shorline Downriver 0.8 On-site From SE-12 North Storm *** 0.15 On-site Shorline Drain Outfall
- 3. INGESTION
- a. Milk *1TM-11 Miller Farm 0.8 WNW TM-14 Brown Farm 2.6 S
- 1TM-13 Newton Farm 5.1 SSE TM-15 Coombs Farm 4.5 NW TM-16 Tall Oaks Fart 4.7 WNW TM-21 Moore Farm 15.9 N
- b. Mixed TG-11 River Station 1.9 SSE Grasses No.3.3 TG-12 N. Hinsdale, NH 3.6 NNE TG-13 Hinsdale SJbstation 3.1 E TG-14 Northfield, MA 11.3 SSE
- 1TG-15 Tyler Hill Rd. 3.2 WNW TG-21 Spofford Lake 16.1 NNE 4-2 Revision 1 DATE: 7 8 Approved by: Md/> k
/ 6/ (_)
I Trble 4.1 (Continued)
Radiolooical Environmental Monitorino Stations
- Distance From Exposure Pathway Sample Location the Plant Direction From and/or Sample and Desianated Code ** Stack (km) the Plant k
- c. Silage *1TC-11 Miller Farm 0.8 WNW TC-14 Brown Farm 2.6 S
- 1TC-13 Newton Farm 5.1 SSE TC-15 Coombs Farm 4.5 NW TC-16 Tall Oaks Farm 4.7 WNW TC-21 Moore Farm 15.9 N
- d. Fish FH-11 Vernon Pond --
On-site FH-21 Rt. 9 Bridge 12.8 Upriver
- 1 Non-Tech Spec Station d
i
{
l l
l l
Revision 1 Date: h Approved by: ML,O[
t UC)
l Table 4.1 (continued)
Radiological Environmental Nonitoring Stations
- Distance From Exposure Pathway Sample location the Plant Direction From and/or Samole and Designated Code Stack (km) the Plant
- 4. DIRECT RADIATION DR-1 River Station 1.9 SSE No. 3.3 DR-2 N. Hinsdale NH 3.6 NNW r
DR-3 Hinsdale Substation 3.1 E l DR-4 Northfield, MA 11.3 SSE DR-5 Spofford Lake 16.1 NNE DR-6 Vernon School 0.6 SW i DR-7 Site Boundary 0.32 SSW DR-8 Site Boundary 0.45 S DR-9 Inner Ring 1.8 N DR-10 Outer Ring 4.3 N DR-11 Inner Ring 1.8 NNE DR-12 Outer Ring 3.4 NNE DR-13 Inner Ring 1.2 NE DR-14 Outer Ring 4.2 NE DR-15 Inner Ring 1.4 ENE DR-16 Outer Ring 2.9 ENE DR-17 Inner Ring 1.3 E DR-18 Outer Ring 3.1 E DR-19 Inner Ring 3.6 ESE DR-20 Outer Ring 5.5 ESE DR-21 Inner Ring 2.1 SE DR-22 Outer Ring 3.5 SE DR-23 Inner Ring 2.1 SSE DR-24 Outer Ring 4.2 SSE DR-25 Inner Ring 2.3 5 DR-26 Outer Ring 4.0 S DR-27 Inner Ring 1.2 SSW l
DR-28 Outer Ring 2.4 SSW DR-29 Inner Ring 0.8 SW l DR-30 Outer Ring 2.4 SW DR-31 Inner Ring 0.8 WSW DR-32 Outer Ring 5.0 WSW DR-33 Inner Ring 0.8 W DR-34 Outer Ring 4.8 W DR-35 Inner Ring 1.2 WNW DR-36 Outer Ring 4.5 WNW DR-37 Inner Ring 2.7 NW l
DR-38 Outer Ring 7.4 NW l
DR-39 Inner Ring 2.9 NNW l DR-40 Outer Ring 4.8 NNW
- Sample locations are shown on Figures 4.1 to 4.6.
- Station 1Xs are indicator stations and Station 2Xs are control stations (for all but the Direct Radiation stations).
- To be sampled and analyzed semi-annually.
4-3 l
I I I
W 12 AP/ 7-12 g a
K is
\ \ TM*IS
/ # HINSDALE, N.H.
T
\Tc. s s
/(
tc-15 ~~~
AP/CF-15 */ '7*l Q bt De ggutY l l 8
r
- I I I I W 13 I
^"- 2 3 ptggy 5 }
M SEE ENLAMENENT IN FIGURE 41 I T i I
8 VERNON DAM i b.,3 60-12 ' l' M * * %
VERNON, V.T. \
- ll W il Tm.a % AP/G-11 TCe tte I
m-12 m-13 0 1 2 3 x!LorITERs figure 4-2 Environemntal Samnline Locations h'ithin Skm of Plant 4-5
\
Revision 1 Date: 7!86 Approved by: /d (
VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REV. #2 t
Reviewed O~I lu W r t Wl f' 1r-, / /2/.2/N!
Plant Operational Review Date Committee Approved / /R// 6/86.
flantManager Date Approved ,e h WW / l9/16lb nce President and Date Manager of Operations
LIST OF AFFECTED PAGES
- , Changes, deletion or additions in the most recent revision are indicated by a bs ;
the margin or by a dot near the page number if the entire page is affected.
Pace Revision Date i - 3.43 0 3/1/84 4.1 - 4.lb 2 12/9/86 i
4.2 - 4.2a 1 10/23/86 4.3 - 4.4 -0 3/1/84 4.5 1 10/23/86 i
4.6 - 6.11 0 3/1/84
-iiib-
L 4.0' ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring stations are listed in Table 4.1. The locations of the stations with respect to the Vermont Yankee plant.are shown on the maps in Figures 4-1 to 4-6.
4.1 Intercomparison Proaram All routine radiological analyses for environmental samples are performed at the Yankee Environmental Laboratory. The Laboratory participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for all the species and matri-ces routinely analyzed.
4.2 Airborne Pathway Monitorino The environmental sampling program is designed around several major objec-tives, including sampling air in predominant up-valley and down-valley wind directions, and sampling air in nearby communities and at a proper control location, while maintaining continuity with two years of preopera-tional data and 13 years-of operational data (as of 1985). The chosen air sampling locations are discussed below.
To assure that an unnecessarily frequent relocation of samplers will not be required due to short-term or annual fluctuations in meteorology, thus incurring needless expense and destroying the continuity of the program, long term, site specific ground level D/Qs (5-year averages - 1978 through 1982) were evaluated in comparison to the existing air monitoring loca-tions to determine their adequacy in meeting the above-stated objectives of the program and the intent of the NRC general guidance. The long-term average meteorological data base precludes the need for an annual re-evaluation of air sampling locations based on a single year's meteorological history.
4-1 Revision 2 Date: V/I6/8G Approved by: . I[n [D- (b V'
The Connecticut River Valley in the vicinity of the Vermont Yankee plant has a pronounced up- and down-valley wind flow. Based on five years of meteorological data, wind blows into the 3 "up-valley" sectors (N, NNW, NW) 27 percent of the time, and the 4 "down-valley" sectors (S, SSE, SE, 4
ESE) 49 percent of the time, for a total "in-valley" time of 76 percent.
Station AP/CF-12 (NNW, 3.6 km) in North Hinsdale, NH, monitors the up-valley sectors. It is located in the sector that ranks fourth overall in terms of wind frequency (i.e., in terms of how often the wind blows into that sector), and is approximately 0.5 miles from the location of the calculated maximum ground level D/Q (i.e., for any location in any sector, for the entire Vermont Yankee environs). This station provides a second function by its location in that it also monitors North Hinsdale, NH, the community with the second highest ground level D/Q for surrounding com-munities, and it has been in operation since the preoperational period.
The down-valley direction is monitored by two stations - at River Station Number 3.3 (AP/CF-11, SSE, 1.9 km) and at Northfield, MA (AP/CF-14, SSE, 11.3 km). They both reside in the sector with the maximum wind frequency and they bound the down-valley point of calculated maximum ground level D/Q (the second highest overall ground level D/Q for any location in any sector). Station AP/CF-11 is approximately one mile from this point, be-tween it and the plant. Station AP/CF-14 also serves as a community moni-tor for Northfield, MA. Both stations have been in operation since the preoperational period.
4-1A n
(?
Revision 2 Date: d/hM9b Approvedby:'/dnrS A NJ
z HE - In additicn to th2 up- and down-vallsy locaticns, two communitics hava been chosen for community sampling locations. The four nearest population groups with the highest long-term average D/Q values, in decreasing order, are Northfield, MA; North Hinsdale, NH; Brattleboro, VT; and Hinsdale, NH. The community sampler for Northfield is at Station AP/CF-14 (mentioned above). North Hinsdale is already monitored by the up-valley station (AP/CF-12, NNW, 3.6 km), which also indirectly monitors the city of Brattleboro, located further out in the same sector. The second sampler specifically designated for a community is at Hinsdale Substation (AP/CF-13, E, 3.1 km) in Hinsdale. The control air sampler was located at Spofford Lake (AP/CF-21, NNE, 16.1 km) due to its distance from the plant and the low frequency for wind blowing in that direction based on the long-term (5-year) meteorological history. Sectors in the general west to southwest direction, which would otherwise have been preferable due to lower wind frequencies, were not chosen since they approached the region surrounding the Yankee Atomic plant in Rowe, MA. An additional air sampler is maintained at the Tyler Hill site (AP/CF-15, WNW, 3.4 km), which is along the western side of the valley in general proximity of historical dairy operations. (The sixth location is not a specific Technical Specification requirement.) l l 4-1B I C-R; vision 2 Date: $////f- &) Approved by: /0 (
)bk-l i
i VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REV. 33 Reviewed hA-(lhT atf A 76 % / I U.'lW. Plant Operati6nal Review Date' Committee Approved h i / /2//8/84 - Plant Manager Oste ' Approved d s W%\ / \QlD2l% 4~ce President and Date Manager of Operations
LIST OF-AFFECTED PAGES
. Changes, deletions or additions in the most recent revision are indicated by a bs the margin or by a dot near the page number if the entire page is affected.
Pace Revision Date i-v 0 3/1/84 vi - vii 3 12/9/86 ix 0 3/1/84 1.1 3 12/9/86 1.2 - 1.5 0 3/1/84 1.6 - 1.11 3 12/9/86 1.12 0 3/1/84 1.13 - 1.19 3 12/9/86 1.20 - 2.4 0 3/1/84 3.1 - 3.46 3 12/9/86 4.1 - 4.1B 2 12/9/86 4.2 - 4.2a 1 10/23/86 4.3 - 4.4- 0 3/1/84 4.5 1 10/23/86 4.6 - 5.8 0 3/1/84 5.9 - 5.21 3 12/9/86 6.1 - 6.11 0 3/1/84 Appendix A 3 12/9/86
-iiic-
l TABLE OF CONTENTS Pace REVISION REC 0RD.................................................. 11 LIST OF EFFECTIVE PAGES........................................... 111 DISCLAIMER OF RESPONSIBILITY..................................... iv ABSTRACT......................................................... v LIST OF FIGURES.................................................. vili L I S T O F TA B L E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - ix
1.0 INTRODUCTION
..................................................... 1-1 1.1 Summary of Methods, Dose Factors, Limits, Constants, Variables and Definitions.................................. 1-2 2.0 METHOD TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS............... 2-1 2.1 Method to Determine F ENG and C NG 2-1 2.2 MethodtoDetermineRkdlonucilhe........................... Concentration
, for Each Liquid Effluent Pathway........................... 2-2
[ 2.2.1 Sample Tanks Pathway............................... 2-2 2.2.2 Service Water Pathway.............................. 2-3 2.2.3 Circulating Water Pathway.......................... 2-3 3.0 0FF-SITE DOSE CALCULATION METH0DS................................ 3-1 3.1 Introductory Concepts...................................... 3-2 3.2 Method to Calculate Total Body Dose from Liquid Releases................................................... 3-5 3.3 Method to Calculate Maximum Organ Dose from Liquid Releases................................................... 3-11 3.4 Method to Calculate the Total Body Dose Rate from Noble Gases................................................ 3-14 3.5 Method to Calculate the Skin Dose Rate from Noble Gases.... 3-18 l 3.6 Method to Calculate the Critical Organ Dose Rate from ; lodines, Tritium and Particulates with T 1/2 Greater Than 8 Days............................ ................... 3-22 3.7 Method to Calculate the Gamma Air Dose from Noble Gases.... 3-26 3.8 Method to Calculate the Beta Air Dose from Noble Gases..... 3-29 3.9 Method to Calculate the Critical Organ Dose from Trittum, Iodines and Particulates................................... 3-32
*f Revision U Dale JEC 2 2 1966 Approved By:
bd .- 7 \J J -vt-4771R e
TABLE OF CONTENTS (Continued)
' Pape i
e 3.10 Receptor Points ana Anr.ual Average Atmospheric Dispersion Factors for Important Exposure Pathways......... 3-38 3.11 Method to Calculate Direct Dose from Plant Operation....... 3 42 3.12 Cumulative Doses........................................... 3 4' 4.0 ENVIRONMENTAL MONITORING PR0 GRAM................................. 4-1 5.0 SETPOINT DETERMINATIONS.......................................... 5-1 5.1 Liquid Effluent Instrumentation Setcoints.................. 5-2 5.2 Gaseous Effluent Instrumentation Setpoints................. 5-9 6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWASTE TREATMENT SYSTEMS................................... 6-1 6.1 In-Plant Liquid Effluent Pathways.......................... 6-1 6.2 In-Plant Gaseous Effluent Pathways......................... 6-3 REFERENCES....................................................... R-1 e APPENDIX A: Method I Example Calculations....................... A-1
~
(.
*f '
asc 2 ? E55 . < Revision 23 Date Approved By:' L- 1/3 ^ (" tr
-vil-
! ,4771R
LIST OF TABLES Title { Number Page 1.1-1 Summary of-Radiological Effluent Technical Specifications and Implementing Equations 1-3 1.1-2 Summary of Methods to Calculate Unrestricted Area Liquid Concentrations 1-6 1.1-3 Summary of Methods to Calculate Off-Site Doses from Liquid Releases , 1-7 1.1 . Summary of Methods to Calculate Dose Rates 1-8 1.1-5 Summary of Methods to Calculate Doses to Air from Noble Gases 1-9 1.1-6 Summary of Methods to Calculate Dose to an Individual from-Tritium, Iodine and Particulates 1-10 1.1-7 Summary of Methods for Setpoint Determinations 1-11 1.1-8 Summary of Var'lables 1-12 1.1-9 Definition of Terms 1-16 1.1-10 Dose Factors Specific for Vermont Yankee 1-18 1.1-11 Dose Factors Specific for Vermont Yankee for Liquid Releases 1-19 1.1-12 Dose and Dose Rate Factors Specific for Vermont Yankee for Tritium, Iodine and Particulate Releases 1-20 3.2-1 Environmental Parameters for Liquid Effluents at Vermont Yankee 3-9 3.2-2 Usage Factors for Various Liquid Pathways at Vermont Yankee 3-10 3.9-1 Environmental Parameters for Gaseous Effluents at Vermont Yankee 3-38 3.9-2 Usage Factors for Various Gaseous Pathways at Vermont Yankee 3-39 3.10-1 Vermont Yankee Dilution Factors 3-43 4.1 Radiological Environmental Monitoring Stations 4-2 5.2-1 Relative Fractions of Core Inventory Noble Gases , After Shutdown -20 {
, , . . . . f
. Revision 3 Date' ' ApprovedBy:[ O_ r'
-vtil-4771R
1.0 INTRODUCTION
This 00CM (Off-Site Dose Calculation Manual) provides formal and approved I methods for the calculation of off-site concentration, off-site doses and effluent monitor setpoints in order to comply with the Vermont Yankee Technical Specifications 3.8/4.8 and 3.9/4.9, hereafter referred to as the Radiological Effluent Technical Specifications. The ODCM forms the basis In for plant procedures and is designed for use by the procedure writer. addition, the ODCM will be useful to the writer of periodic reports The required by the NRC on the dose consequences of plant operation. methods contained herein follow accepted NRC guidance (Regulatory Guide 1.109) unless otherwise noted in the text. It shall be the responsibility of the Chemistry and Health Physics Supervisor to ensure that the ODCM is used in the performance of the sur-veillance requirements and administrate controls of the appropriate por-tions of the Technical Specifications. All changes to the ODCM must be reviewed by PORC and approved by M00 in All accordance with Technical Specification 6.13 prior to implementation. approved changes shall be submitted to the NRC for their information in the Semiannual 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.
-t ,-
- Approved By: /W d M Revision O Date. -
\I
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1-1 I _ - - _ . . _ _ _ _ _ - , _ _ _ . . _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . . _ - _ _ _ _ - ~ . . _ _ _ , _ _ _ _ _ . _ _ _ . _ . _ _ _ , _ .
{ Table 1.1-2 Summary of Methods to Calculate ( Unrestricted Area Liquid (cnr.entrations Equation Reference . Number Category Ecuation Section , 2-1 Total Fraction of MPC in E 1 2.1 F;NG- MPC g I Liquids Except Noble Gases 2-2 Total Activity of Dissolved C 0($)- C NG 2,1 , and Entrained Noble Gases 1 ml 1 ' from all Station Sources _< 2 -04 ( f ,
~ ,
Revision 3 Date Approved sy: .;c. z w 4771R hmm---ms... -e i
p Table 1.1-3
/
Summary of Methods to Calculate
\ Off-Site Doses frcm Liquid Releaset Equation Reference Number Category Equation Section I
3-1 Total Body 3.2.1 Dose D tb (mrem).{QOFL i itb I i 3-3 Maximum 3.3.1 Organ Dose D mo (mrem).{QOFL i Imo i {. Revision 3 Dat[ ApprovedBy! V 7 i 1-7 4771R
7 Table 1.1-4
~
Summary of Methods to Calculate Cose Rates Equation Reference Number Category Ecuation Section
.ST -
3-5 Total Body Dose Rate
- 3,4,g l from Noble Gases R
tb(mrem)=0.72{Q yr j g DFB g i I
" {0
* .ST I 3-7 Skin Dose Rate R DF.g 3.5.1 from Noble Gases skin (mrem}
yr g 1 l 3-16 Critical Organ Dose T .STP 3.6.1
,(" 'r ) " d*0 Rate from Iodines, R DFGjg, e 1 Trittum 1 and Particulates with T 1/2 Greater Than Eight Days e
9 f Reviston 3 Date ApprovedBy:/I A bl / 3,, V~ 4771R 9
Table 1.1-5 Summary of Methods to Calculate ( Doses to Air frcm Noble Gases Equation . Reference : Number category Ecuation Section : 3-21 Gama Dose to Air S DFy 3.7.1 DY Qi i from Noble Gases air (mrad) - 0.023 g 3-23 Sv;a Dose to Air B ST 6 3.8.1 , Q1 OF fiom Noble Gases Dair (mrad) = 0.02 g 1
$ 1 _
V ( l-9 4771R
Table 1.1-6 Sumary cf Methods to Calculate Dose to an Individual from Tritium, Iodine and Particulates Equation Reference Number Category Ecuation Section , 3.9.1 3-25 Dose to Critical Organ from Iodines, Og ,(mrem) - {Q ST g OM ge, j Tritium and Particulates 3-27 Direct Dose .3.11.1 Od (mrem) - 1.29E-06 E Revision 3 Date - Approved By: $3 c
1 Table 1.1-7 Summary of Methods for SetDeint Determinations Equation Reference Number Category Ecuation Section 5-1 Liquid Effluents: Liquid Radwaste L OF 5.1.1.1 E Discharge Monitor spt ICES' " 0F "I min 1 (17/350) Gaseous Effluents: Plant Stack (RR-108-1A, RR-108-18) and A0G Offgas System (3127, 3128) Noble Gas Activity Monitors 5-9 Total Body tb 11 5.2.1.1 gspt (cpm) - 694 Sg F OFB 5-10 Skin 1 1 5.2.1.1 Rskin spt (com) = 3000 S gFOFj 5-21 SJAE Noble Gas RSJAE (cpm) - 1.6E+05 S 1 5.2.2.1 Activity Monitors spt gF (17/150A, 17/1508)
/
Revision J Date Approved sy: s .c(' ( - i 1-11 4771R
\
Table 1.1-8 (continued) l( Summary of Variables Variable Definition Units 3 DF' = Composite skin dose factor mrem-m pC1-yr DFB,
= Total body gamma dose factor for nuclide "1" DF8 g - Composite total body dose factor DFL = Site-specific, total body dose factor for a mrem itb 11guld release of nuclide "1" Ci DFL = Site-specific, maximum organ dose factor for a mrem 9 ,
liquid release of nucitde "1" Ci DFG = Site-specific, critical organ dose factor for a mrem ICO gaseous release of nuclide."1" Ci
= Site-specific, critical organ dose rate factor mrem-sec DFG'CO I
for a gaseous release of nuclide "1" pCi-yr l.
*#'*-"3 DFS i
= Beta skin dose factor for nu~clide "1" pCl-yr
*#'*~5' DF' 1
= Combined skin dose factor for nucilde "1" pct-yr
'd
= Gamma air dose factor for nuclide "1" DF{ ,
3 S mrad-m DF 1
= Beta air dose factor for nuclide*'t pCi-yr R = Critical organ dose rate due to lodines yr
#0 and particulates
- Skin dose rate due to noble gases R g *h'r "I'
R = Total body dose rate due to noble gases r tb b l c 2.2 $36 & k i Revision 3 Defe Approved By: h4 @ ._ , 1-13 4771R
Table 1.1-8 (continued) Summary of Variables Variable Definition Units D/Q = Deposition factor for dry deposition of 1 elemental radiolodines and other particulates [ E = Gross electric output over the period of MW,h interest F d
- Flow rate out of discharge canal gpm F, = Flow rate past Itquid radwaste monitor gpm F - Flow rate past gaseous radwaste monttor E seC ENG F = Total fraction of MPC in liquid pathways fraction (excluding noble gases)
MPC g - Maximum permissible concentration for gC) radionucilde "1" (10CFR20, Appendix 8, cc Table 2. Column 2) 1- - Release for radionucilde "1" from the curtes Qg point of interest . Q, = Release rate for radionuclide "1" pcuries/sec at the point of interest
.ST j Qg . The noble gas radionuclide "t" release g rate at the plant stack sec
.SJAE
. The noble gas radionucilde "1" release $
01 rate at the steam jet air ejector I'C
.A0G Qg - The noble gas radionuclide "1" release rate g at the exhaust of the augmented Off-Gas System sec .STP Qg . The lodine, tritium, and particulate g radionuclide "1" release rate from the see plant stack ST . The release of noble gas radionuclide curies qi "1" from the plant stack
( ,o. Revision 1 D e ~ ~ s,,v Approved By: JA
'[. [
1-14 - 4771R
{ Table 1.1-8 (continued) Sumcary of Vartaoles Variable Definition Units STP - The release of lodine, trittum, and curies Q particulate radionuclides "1" from the plant stack L - Liquid monitor response for the limiting cps R spt concentration at the point of discharge R S I" - Response of the noble gas monitor at the epm spt limiting skin dose rate R tb - Response of the noble gas monttor to cpm spt Ilmiting total body dose rate 5 7
- Shielding factor Ratio 5 - Detector counting efflctency com mR/h-9 pct /cc 0' pCi/cc i
- Detector counting efficiency for noble
( S gg gas "1" com pct /cc or pD
/c:
Sj Detector counting effletency from the most ces recent liquid monitor calibration pct /mi S jg - Detector counting efficiency for ces radionucitde "1" pC1/ml X/Q = Annual or long-term average undepleted atmospheric disperston factor y m (X/Q)T - Effective annual or long-term average gamma atmospheric dispersion factor y m e f Revision 1 Date 9 .w "' Approved By: Qi(
._ w
(~ 1-15 ( 4771R
Table 1.1-9 Definttlon of Terts PAGE .ELETED ! I s
...,,, s .w.<
,,,,.... .,, 1c c-477,R
f- > Table 1.1-9 (Cor.tinued)
- {
Definition of Terms PAGE DELETED , n.viii.a.l_o.t. h 4,, rov.4 syc /- _A _ J
-~
i ,.n 4771a
1 1 Table 1.1-10 l Dose Factors Specific for Vermont Yankee for hotle Gas Releases Gama Beta Air Gam.-a a Total Body 8 eta Skin Combined Skin Dose h Dose Factor Dose Factor Dose Factor Dose Factor g({I*y[) 0FS g (((*y*)DFj(*[8') yr DFf( -)) y DF}( Radlonuclide OF8 3.28E-03 9.3CE-: 2.69E-03 9.13E-03 Ar-41 8.84E-03* ' 2.88E-04 1.93E-:
----- 1.54E-05 Kr-83m 7.56E-08 1.97E-03 1.23E .
1.46E-03 1.90E-03 Kr-85m 1.17E-03 1.95E-03 1.72E-:. 1.34E-03 8.58E-04 Kr-85 1.61E-05 1.11E-02 1.03E-02 6.17E-: 5.92E-03 9.73E-03 Kr-87 2.93E-03 1.52E-: 2.37E-03 1.37E-02 Kr-88 1.47E-02 1.06E-02 1.73i-1.01E-02 2.02E-02 Kr-89 1.66E-02 7.83E-03 1.63E-:' 7.29E-03 1.76E-02 1.56E-02 Kr-90 [' 9.15E-05 4.76E-04 4.25E-04 1.11E-03 1.5f! Xe-131m 1.48E-03 3.27E . 9.94E-04 8.88E-04 Xe-133m 2.51E-04 1.05E-03 3.53E . 3.06E-04 4.75E-04 Xe-133 2.94E-04 l 3.36E-3.14E-03 7.39E-04 3.12E-03 7.11E-04 ; Xe-135m .
' 2.46E-03 1.92E .
1.86E-03 2.71E-03 Xe-135 1.81E-03 1.27E-02 1.E'!- 1.22E-02 8.89E-03 Xe-137 1.42E-03 4.75E-03 9.2iE . 4.13E-03 9.97E-03 Xe-138 8.83E-03
- 8.84E-03 8.04 x 10-3 Revision d Date
- ' Approved 8y:
r [ 1-18 I 4771R
( Table 1.1-11 Dose Factors Specific for Vermont Yankee for Liquid Releases Total Body Maximum Organ Dose Factor Dose Factor RadionucIlde OFL itb < mrem) Ci OR3,g (mrem) Ci H-3 1.75E-04 1.75E-04 Na-24 1.66E-03 1.66E-03 Cr-51 2.11E-05 3.13E-03 Mn-54 1.79E-02 1.61E-01 Mn-56 1.67E-06 1.89E-04 Fe-59 2.96E-02 1.34E-01 Co-58 1.41E-02 5.35E-02 Co-60 8.27E-02 2.67E-01 Zn-65 4.86E-01 7.97E-01 Sr-89 6.80E-02 2.38E+00 . Sr-90 2.07E+01 8.15E+01 Zr-95 4.09E-04 8.49E-02 Mo-99 5.32E-04 4.42E-03 Tc-99m 6.48E-05 2.02E-03 Sb-124 7.80E-03 1.92E-01
. 1-131 2.52E-03 1.46E+00 f I-132 1.99E-06 5.82E-06 . \ I-133 1.91E-04 9.34E-02 I-135 1.49E-05 2.38E-03 Cs-134 5.26E+00 7.01E+00 Cs-137 3.15E+00 -
6.07E+00 Ba-140 1.01E-03 1.72E-02 Ce-141 2.27E-05 3.14E-02 M-187 4.23E-04 3.17E-01
=m _
s F 1-19 v (. 4771R l
1 3.0 OFF-SITE DOSE CALCULATION HETH005 Chapter 3 AJetdes he basis fer plant prxecures requir ed to meet tr.e (' Radiological Effluent Technical Specifications (hereafter called RETS). A simple, conservative method (called Method I) is listed in Tables 1.1-2 to 1.1-7 for each of the requirements of the RETS. Each of the Method I equations is presented, along with their bases in Sections 3.2 through 3.9 ar.c Section 3.11. Appendix A provides example calculations for all Method I dcse equations as guidance to their use. In addition, reference is provided to more sophisticated methods (called Method II) for use when more accurate results are needed. This chapter provides the methods, data, and reference , material with which the operator can calculate the needed doses and dose g rates. Setpoint methods for effluent monitor alarms are described in Chapter 5. r-Revislon d Date Approved By: _ h.~ 3-1 4172R
3.1 Introductory Concepts (. The Radiological Effluent Technical Specifications (RETS) either litrit dose or oose rate. 1heterm" Dose"forinhestedorinhalea radioactivity means the dose commitment, measured in mrem, which results frcm the exposure to radioactive materials that, because of uptake and deposition in the bocy, will continue to expose the body to radiation for some period of time after the source of radioactivity is stopped. The time frame over which the dose ! commitment is evaluated is 50 years. The phrases " annual Dose" or " Dose in one year" then refers to the fifty-year dose commitment from one year's worth of releases. " Dose in a quarter" similarly means a fifty-year dose <ommitme-: from one quarter's releases. The term " Dose," with respect to external exposures, such as to noble gas clouds, refer only to the doses received during the actual time period of exposure to the radioactivity released from r the plant. Once the source of the radioactivity is removed, there is no longer any additional accumulation to the dose commitment. Gaseous effluents from the plant are also controlled such that the maximum " dose rates" at the site boundary at any time are limited to h 500 mrem / year. The annual dose limits are the doses associated with the concentrations of Appendix B, Table II, Column 1 of 10CFR Part 20 (10CFR20.106(a)). The use of the annual dose limits embodied in 10CFR Part 2C as plant " dose rate" values (to be applied at any time consistent with the capabilities of the monitoring instrumentation to determine) provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of member (s) of the pubite either within or outside the site boundary to annual average concentrations exceeding the federal regulations. It should also be noted that a dose rate due to noble gases that exceeds for a short time period (less th'an one hour in duration) the equivalent 500 arem/ year dose rate limit stated in Technical Specification 3.8.E.1.a. does not necessarily, by itself, constitute a Licensee Event Repor: (LER) under 10CFR Part 50.73 unless it is determined that the #1 Approved By: Revision J Date 3-2 4172R
1 i concentration of radioactive effluents in unrestricted areas has also exceede: two times MPC when averaged over one hour (four-hour notification per !(. 10CFR50.72, and 30-day LER per 10CFR50.73). The quantitles 0 and R are introduced to provide calculable quantities, i related to off-site dose, or dose rate which demonstrates compliance with thE RETS. t l The dose D is the quantity calculated by the Chapter 3 dose equations. The D calculated by " Method I" equations is not nece'ssarily the actual dose received by a real individual but usually provides an upper bound for a given release because of the conservative margin built into the dose factors and the selection and definition of critical receptors. The radioisotope specific dose factors in each " Method I" dose equation represent the greatest dose to any organ of any age group accounting for existing or potential pathways of exposure. The critical receptor assumed by " Method I" equations is typically L a hypothetical individual whose behavior - in terms of location and intake - results in a dose which is expected to be higher than any real individual. II Method II allows for a more exact dose calculation for real individuals, if necessary, by considering only existing pathways of exposure, or actual concurrent meteorology with the recorded release. R is the quantity calculated in the Chapter 3 dose rate equations. It is calculated using the plant's effluent monitoring system reading and an annual average or long-term atmospheric dispersion factor. Dispersion fact m based on actual concurrent meteorology during effluent releases can also be used via Method II, if necessary, to demonstrate compliance with off-site cese rate limits. It should be noted that if plant release rates were such that an i R equal to the Technical Specification (3.8.E.1) value was continued for one However, since year, the annual dose limits of 10CFR20 would be reached. maximum allowed release rates and the resulting dose rates in the range of the Technical Specification limits are very infrequent and are typically of short GEC 2 2 1986 Approved By: /s A, _ C l Revision U Date - -._ ' 3-3 4172R
l time duration, this approach of limiting dose rates equivalent to the annual dose limits then assures that 10CFR20.106 limits on an annual average air ( concentration in unrestricted areas will be fret. I Each of the methods to calculate dose or dose rate are presented in separate sections of Chapter 3, and are summarized in Tables 1.1-1 to 1.1-7. Each method has two levels of complexity and conservative margin and are called Method I and Method II. Method I has the greatest margin and is the simplest; generally a linear equation. Method II is a more detailed analysis f which allows for use of site-specific factors and variable parameters to be selected to best fit the actual release. Guidance is provided but ttie appropriate margin and depth of analysis are determined in each instance at the time of analysis under Method II. h
...J bO C Reviston J Dat~e'*. Approved By: /q y AL ,
( 3-4 4172R
\
l 3.2 Method to Calculate the To9al Body Dose from Liauld Releases I Technical Specification 3.8.B.1 limits the total bocy dose ccmmitment { to 1 Me@r of the Public from r adioactive material in liqcM effluer.ts to i 5 mrem per quarter and 3 mrem per year. Technical Specification 3.8.C.1 requires liquid radwaste treatment when the total body dose estimate exceeds 0.06 mrem in any month. Technical Specification 3.8.M.1 limits the total bec,. dose commitment to any real member of the public from all station sources (including 11gulds) to 25 mrem in a year. Dose evaluation is required at least once per month. If the 11guld radwaste treatment system is not being used, dose evaluation is required before each release. . Use Method I first to calculate the maximum total body dose from a liquid release to the Connecticut River as it is simpler to execute and more conservative than Method II. Use Method II if a more accurate calculation of total body dose is needed (i.e., Method I indicates the dose is greater than the limit), or if Method I cannot be applied. (. If the radwaste system is not operating, the total body dose must be estimated prior to a release (Specification 3.8.C.1). To evaluate the total body dose, use Equation 3.1 to estimate the dose from the planned release arc add this to the total body dose accumulated from prior releases during the month. 3.2.1 Method I The increment in total body dose from a liquid release is: D tb
" 01 OR itb (mrem) (Cl)(*]*)
Revision J Dat T . .. 2 Approved By:
<m Nr'& q-f~
- C 4172R
l l l where: DFLitb = Site-specific total body dose factor (mrem /C1) for a liqui: i j( release. See Table 1.1-11. Q1 = Total activity (C1) released for radionuclide "1". (For strontiums and Fe-55, use the most recent measurement available.) Equation 3-1 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event),
- 2. Liquid releases were to the Connecticut River, and
- 3. Any continuous or batch release over any time period.
3.2.2 Basts for Method I This section serves three purposes: (1) to document that Method I complies with appropriate NRC regulations, (2) to provide background and training information to Method I users, and (3) to provide an introductory ( user's guide to Method II. Method I may be used to show that the Technical Specifications which limit off-site total body dose from liquids (3.8.B.1 and 3.8.C.1) have been met for releases over the appropriate periods. These Technical Specifications are based on design objectives and standards in 10CFR and 40CFR. Technical Specification 3.8.B.i is based'on the ALARA design objectives in l'OCFR50, Appendix I Subsection II A. Technical Speelfication 3.8.C.) is an
" appropriate fraction", determined by the NRC, of that design objective (hereafter called the Objective). Technical Specification 3.8.M.1 is based on Environmental Standards for Urantum Fuel Cycle in 40CFR190 (hereafter callec the Standard) which applies to direct radiation as well as liquid and gaseous effluents.
o Approved By: M n e L- _ 3 Date Revision 3-6 ( 4172R
Exceeding the Objective or the Standard does not immediately limit plant operation but requires a report to the NRC within 30 days. In addition.
-[ a waiver may be required. This is ur.like exceed 1ig 10CFR20 limits wht;n could result in piant shutdown.
Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated"-(10CFR50, Appendix I). The definition, below, of a single " critical receptor" (a hypothetical individual whose behavior results in an unrealistically high l dose) provides part of the conservative margin to the calculation of total i body dose in Method I. Method II allows that actual individuals, with real j behaviors, be taken into account for any given release. In fact, Method I was based on a Method II analysts for the critical receptor with maximum exposure . conditions instead of any real individual. That analysis was called the " base case"; it was then reduced to form Method I. l The steps performed in the Method I derivation follow. First, in the base case, the dose impact to the critical receptor (in the form of dose factors DFLitb, mrem /C1) for a 1 curie release of each radioisotope in b liquid effluents was derived. The base case analysis uses the methods, data and assumptions in Regulatory Guide 1.109 (Equations A-2. A-3, A-7, A-13 and A-16, Reference A). The 11guld pathways identified as contributing to an - Individual's dose are the consumption of fish "from the Connecticut River, the ingestion of vegetables and leafy vegetation which were irrigated by river {I water, the consumption of milk and meat from cows and beef cattle who had {. river water available for drinking as well as having feed grown on irrigated land, and the direct exposure from the ground plane associated with activity deposited by the water pathway. A plant discharge flow rate of 44.6 ft /sec l was used with a mixing ratto of 0.0346 which corresponds to a minimum regulated river flow of 1250 cfs at the Vernon Dam just below the plant j discharge outfall. Tables 3.2-1 and 3.2-2 outline human consumption and environmental parameters used in the analysis. The resulting, site-specific, total body dose factors appear in Table 1.1-11. ( Revision d Da @ 2 I Approved By: ,b 3-7 u . 4172R
f- i l l For any'11guld release, during any period, the increment in annual average total body dose from radienuclide "1" is: i AD tb *0 1 0FL g (3-2; (mrem) (C1) ( *) t where: OFLitb = Site-specific total body dose factor (mrem /C1) for a liquid release. See Table 1.1.11. Qt - Total activity (Cl) released for radionuclide "1". Method I is conservative because it is based on dose factors DFL itb which were chosen from the base case to be the highest of the four age groups l for each radionuclide, as well as assuming minimum river dilution flow. i 3.2.3 Method II ; If Method I cannot be appiled, or if the Method I dose exceeds the limit or if a more exact calculation is required, then Method II should be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable, such as the use of actual river flow at the time of actual discharge as opposed to the minimum river l flow of 1,250 cfs that is assumed in the Method I dose factors. The base case ! analysts, documented above, is a good example of the use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented. ( Revision d Deft ; Approved By: k-Qi h - 3-8 0 4172R
m - -- -. ~ ~ ._ Table 3.2-1 Environmental Parameters for Liquid Effluents at Vermont Yankee (Derived from Reference A) POTABLE AQUATIC SHORELINE FOOD CROWN WITH CONTAMINATED WATF.R VARIABLE WATER FOOD ACTIVITY VEGETABLES LEAFY VEC. MEAT COW MILK MP Mixing Ratio - 0.0356 0.0356 0.0356 0.0356 0.0356 0.03S6 TP Transit Time (HRS) - 24.0 0.0 0.0 0.0 480.0 48.0 YV Agricultural (KC/M2 ) 2.0 2.0 2.0 2.0 Productivity P Soil Surface (KC/M2 ) 240.0 240.0 240.0 240.0 Density IRR Irrigation Rate (L/M2/HR) 0.152 0.152 0.152 0.152 TE Crop Exposure (HRS) 1440.0 1440.0 1440.0 1440.0 Time TH Holdup Time (HRS) 1440.0 24.0 2160.0 2160.0 QAW Water Uptake Rate (L/D) 50.0 60.0 for Animal Feed Uptake Rate (KC/D) 50.0 50.0 QF i for Animal FI Fraction of Year Crops Irrigated 0.5 0.5 0.5 0.5 Location of Connecticut River below Vernon Dam. Critical Receptor j C' Revision f Datc.DI.L 1-9 ApprovedBy,./ .(_ -
p _ ._ Table 3.2-2 Usaae Factors for Various Liquid Pathways at Vermont Yankee (From Reference A Table E-5. Zero where no pathway exists) ACE VEG. LEAFY MILK MEAT FISH INVERT. POTABLE SHORELINE VEC. WATER (KC/YR) (KC/YR) (LITER /YR) (KC/YR) (KC/YR) (KC/YR) (LITER /YR) (MR/YR) Adult 520.00 64.00 310.00 110.00 21.00 0.00 0.00 12.00 4 Teen 630.00 42.00 400.00 65.00 16.00 0.00 0.00 67.00 . Child $20.00 26.00 330.00 41.00 6.90 0.00 0.00 14.00 Infant 0.00 0.00 330.00 0.00 0.00 0.00 0.00 0.00 l 1 n
'a "
r- 3-10 Approved By_ N
- ph '-- ~'
Revision d Date _ __
3.3 Method to Calculate Maximum Organ Oose from Licuid Releases ( Technical Specificat un 3.8.B.1 limits th9 maximum orcar, dose commitment to a Member cf the Public from radioactive material in 11guia effluents to 5 mrem per quarter and 10 mrem per year. Technical Specificatier. 3.8.C.1 requires 11guld radwaste treatment when the maximum organ dose estimate exceeds 0.2 mrem in any month. Technical Specification 3.8.M.1 ) limits the maximum organ dose commitment to any real member of the public frc all station sources (including 11gulds) to 25 mrem in a year except for the thyrold, which is limited to 75 mrem in a year. Dose evaluation is requirec at least once per month if releases have occurred. If the liquid radwaste treatment system is not being used, dose evaluation is required before each release. Use Method I first to calculate the maximum organ dose from a liquid release to the Connecticut River as it is simpler to execute and more 4 conservative than Method II. Use Method II if a more accurate calculation of organ dose is needed [, (i.e., Method I indicates the dose is greater than the limit), or if Method I cannot be applied. If the radwaste system is not operating, the maximum organ dose must te estimated prior to a release (Specification 3.8.C.1). To evaluate the maxima organ dose, use Equation 3-3 to estimate the dose from the planned release ar:: add this to the maximum organ dose accumulated from prior releases during the month. 3.3.1 Method I The increment in maximum organ dose from a 11guld release is: (3-3) D, = Qg DFL g , Revision 3 Da Approved By: b - y 3-11 f 4172R
(crem) (C1) (*]*) where: DFL imo - S'te-specific maximum Organ dose factor (m-em/C') for a 11guld release. See Table !.1-11. Qt - Total activity (C1) released for radionuclide "1". (For strontiums and Fe-55, use the most recent measurement available.) Equation 3-3 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event),
- 2. Liquid releases were to the Connecticut River, and
- 3. Any continuous or batch release over any time period.
3.3.2 Basis for Method I This section serves three purposes: (1) to document that Method I complies with appropriate NRC regulations, (2) to provide background and training information to Method I users, and (3) te provide an introductory user's guide to Method II. The methods to calculate maximum organ dose parallel the total body dose methods (see Section 3.2.2). Only the differences are presented here. For each radionuclide, a dose factor (mrem /C1) was determined for each of seven organs and four age groups. The largest of these was chosen to be the maximum organ dose factor (DFL) ,) for that radionuclide. For any liquid release, during any period, the increment in annual average dose from radionuclide "1" to the maximum organ is: G.[ Revision d Dat'e" Approved By: / t ( u 3-12 4172R
l AD, =Q g 0FL
% (3-0 (mrem) (C1)
(*]*)
~
where: OFLimo = Site-specific maximum organ dose factor (mrem /C1) for a 11guld release. See Table 1.1-11. Qg - Total activity (C1) released for radionuclide "1". \ Because of the assumptions about receptors, environment, and radionuclides; and because of the low Objective and Standard, the lack of immediate restriction on plant operation, and the adherence to 10CFR'0 2 concentrations (which limit public health consequences) a failure of Method I (i.e., the exposure of a real individual being underestimated) is improbatle and the consequences of a failure are minimal. 3.3.3 Method II If Method I cannot be applied, or if the Method I dose exceeds the limit or if a more exact calculation is required, then Method II should be (, applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applic'able. The base case analysis, documented above, is a good example of the use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Methc: II calculations should be referred to YNSD to be performed and documented. f Revision d Dake-c - Approved By: %C1Q Q I 3-13 4172R
3.4 Method to Calculate the Total Body Dose Rate From Noble Gases i, Technical Specificatien 3.8.E.1 limits the dose rate at any time to tN total body from noble gases at any location at or beyond the site boundary equal to or less than 500 mrem / year. By limiting the maximum Rtb to a rate equivalent to no more than 500 mrem / year, assurance is provided that the total body dose accrued in any one year by any member of the general public will be less than 500 mrem in accordance with the annual dose limits of 10CFR Part 20 to unrestricted areas. Use Method I first to calculate the Total Body Dose Rate from the peak release rate via the plant stack. Method I applies at all release rates. Use Method II if Method I predicts a dose rate greater than the Technical Specification limit (i.e., use of actual meteorology over the period of interest) to determine if, in fact, Technical Specification 3.8.E.1 had actually been exceeded during a short time interval. Compliance with the dose rate limits for noble gases are continuously i demonstrated when effluent release rates are below the plant stack neble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit of Technical Specification 3.8.E.1, or a value below it. Determinations of dose rates for compliance with Technical Specifications (3.8.E.1) are performed when the effluent monitor alarm setpoint is exceeded and the corrective action required by Specification 3.8.E.2 is unsuccessful, or as required by the notations to Technical Specification Table 3.9.2 when the stack noble gas monitor is inoperable. 3.4.1 Method I The Total Body Dose Rate due to noble gases can be determined by multiplying the individual radionuclide release rates by their re pective dose o C Revision 3 Date Approved 8y: ]S _7 N_ 3-14 4172R
I factors, summing all the products together, and then multiplying this total by a conversion constant (C.72), as seen in the following Equation 3-5 (an g example calculation is p*ovided in Appendix A): 4 (3-D it tb
= 0.72 1
hf DFB, 3 gmrem) (DC1-sec) (uC1) gmrem-m ) yr 3 sec pC1-yr Cl-m where: hf . In the case of noble gases, the release rate from the plant stack (pCi/sec) for each radionuclide, "i", identified. The release rate at the plant stack is based on the measured radionuclide distribution in the off-gas at the Steam Jet Air 4 Ejector (SJAE) during plant' operation when the activity at the stack is below detectable levels, and the recorded total gas effluent count rate from the Stack Gas Monitor I or II. The release rate at the stack can also be stated as follows:
'SJAE hST ,
b g L F (3-28) I JAE SI 1 uC1 , gep,) (uC1/cc) (cc ) sec cpm see M = Plant Stack Gas Monitor I or II count rate (cpm). Sg . Appropriate or conservative plant stack monitor detector counting efficiency for the given nuclide mix (cpm /(pC1/cc)). F = Stack flow rate (cc/sec). hyJAE = The last measured release rate at the steam jet air ejector of noble gas 1 (pC1/sec). DFBq = Total body gamma dose factor (see Table 1.1-10). C ' CD i Revision U Cathn99~ ~ 1986 Approved By: M 3-15 4172R L
During periods (beyond the first five days) when the plant is shutdow9 and no radioactivity release rates can be measured at the SJAE, Xe-133 rray be used in place of the last SJAE measured mix as the referenced radionuclide to determine off-site dose rate and monitor setpoints. :n t!.is case, the ratio of eachhSJAE tothesumofallhSJAE in Equation 3-28 above is assumed to reduce to a value of 1, and the total body gamma dose factor DFBg for Xe-133 3 (2.94 E-04 mrem-m / C1-yr) is used in Equation 3-5. Alternately, a relative radionuclide "1" mix fraction (f )gmay be taken from Table 5.2-1 as a function of time after shutdown, and substituted in place of the ratio of hSJAE tothesumofallh3A in Equation (3-28) above to determine the relative fraction of each ncble gas potentially available for release to the total (example calculations can be found in Appendix A). Just prior to plant startup before a SJAE sample can be taken and analyzed, the monitor alarm setpoints should be based on Xe-138 as representing the most prevalent high dose factor noble gas expected to be present shortly after the plant returns to power. Monitor alarm setpoints which have been determined to be i conservative under any plant conditions may be utilized at any time in lieu c' the above assumptions. ( Equation 3-5 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Noble gas releases via the plant stack to the atmosphere.
3.4.2 Basis for Method I Method I may be used to show that the Technical Specification which limits total body dose rate from noble gases released to the atmosphere (Technical Specification 3.8.E.1) has been met for the peak noble gas release rate. C
~'~ '
Revision J Date Approved By: @ bk 3-16 4172R
Method I was derived from Regulatory Guide 1.109 as follows: k = IE+06 S p [X/Q1Y hST DFB, (3-6) tb 3 (mrem) 4C1) g) (sec) gft) gerem-m )
-yr pC1 ,3 sec pCi-yr where:
Sp - Shielding factor = 1.0 for dose rate determination. i (X/Q]Y = Maximum annual average gamma atmospheric dispersion factor
- 7.2E-07 (sec/m3 )
Release rate from the plant. stack of noble gas "1" (pC1/sec). hf = DFB, = Gammatotalbodydosefactor,({[, ). See Table 1.1-10. Equation 3-6 reduces to: tb
= 0.72 hf DFB g (3,5)
( 3 gmrem) (DCl-sec) guci) gmrem-m ) yr 3 sec pCi-yr Cl-m The sel.sction of critical receptor, outlined in Section 3.10 is inherent in Method I, as are the maximum expected off-site annual or long-term average atmosphirit i dispersion factors. Due to the holdup and decay of gases allowed in the A0G, off-gas concentrations at the plant stack during routine plant operations are usually too low for determination of the radionuclide mix at the plant stack. It is then conservatively assumed that most of the noble gas activity at the plant stack is the result of in-plant steam leaks which are removed to the plant stack by building ventilation air flow, and that this air flow has an isotopic distribution consistent with that routinely measured at the SJAE. i
- = = . '
Revision J Date Approved By: . 1 l( l J ' 3-17 4172R I
i In the case of noble gas dose rates, Method Il cannot provide much ( extra realism because R tb is already based on several factors which make use ( of current plant parameters. However, should it be needed, tne dcse rate analysis for critical receptor can be perfermed making use of current meteorology during the time interval of recorded peak release rate in place of the default atmospheric dispersion factor used in Method I. 3.4.3 Method II If Method I cannot be applied, or if the Method I dose exceeds the limit, then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more appilcable. The base case analysis, documented above, is a good example of the use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented. Revision U Date Approved By: I, k l 3-18 4172R
1 3.5 Method to Calculate the Skin Dose Rate from Noble Gases I Technical Specification 3.8.E.1 limits the dose rate at any time to the skin from noble gases at any location at or beyond the site boundary to 3,000 mrem / year. By limiting the maximum R skin to a rate equivalent to no nore than 3,000 mrem / year, assurance is provided that the skin dose accrued in any one year by any member of the general public is much less than 3,000 mrem. Use Method I first to calculate the Skin Dose Rate from the peak release rate via the plant vent stack. Method I applies at all release rates. Use Method II if Methed I predicts a dose rate greater than the Technical Specification limits (i.e., use c' a:tual meteorology over the period of interest) to determine if, in fact, Technical Specification 3.8.E.1 had actually been exceeded during a short time interval. ; Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant stack noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site Technical Specificatier dose rate limit, or a value below it. Determinations of dose rate for compliance with Technical Specifications (3.8.E.1) are performed when the effluent monitor alarm setpoint is exceeded and the corrective action required by Specification 3.8.E.2 is unsuccessful, or as required by the notations to Technical i Specification Table 3.9.2 when the stack noble gas monitor is inoperable. ! 3.5.1 Method I 1 The skin dose rate due to noble gases is determined by multiplying the individual radionuclide release rates by their respective dose factors, and summing all the products together as seen in the following Equation 3-7 (an example calculation is provided in Appendix A): , { Revision d DatF 2 2 2 ,,,,,,,,,,;Qsct
+3 k L ,
3-19 4172R
. 1 (3-7)
R DFj skin - (mym ., gg) g:nram se ) -( yr sec pCl-yr where: In the case of noble gases, the noble gas release rate from tne hf. plant stack (pC1/sec) for each radionuclide, "i", identified. The release rate at the plant stack is based on the measured radionuclide distribution in the off-gas at the Steam Jet Air Ejector (SJAE) during plant operation when the activity at the stack is below detectable levels, and the recorded total gas The effluent count rate from the Stack Gas Monitor I or II. release rate at the stack can also be stated as follows:
*SJAE (3-2E) 01 L gST , g 7 I' JAE 69 1
g , (cpm) (uCiItc) (cc_) cpm sec sec H - Plant stack gas monitor I or II count rate (cpm). Appropriate or conservative plant stack monitor Sg detector counting efficiency for the given nuclice g' mix (cpm /(pC1/cc)). F - Stack flow rate (cc/sec). hyAE - The last measured release rate at the steam jet ai-ejector of noble gas 1 (pC1/sec). DFj
- combined skin dose factor (see Table 1.1-10).
During periods (beyond the first five days) when the plant is shutdc=- and no radioactivity release rates can be measured at the SJAE, Xe-133 may te used in place of the last SJAE measured mix as the referenced radionuclide to In this case, the ratic determine off-site dose rate and monttor setpoints. eachofhfA tothesumofallhSUA in Equation 3-28 above is assumed to r Approved By: b Revision O Date " _ vif 3-20 4172R
reduce to a value of 1. and the combined skin dose factor DF'g for Xe-133 (3.90 E-04 mrem-sec/pC1-year) is used 'n Equation 3-7. Alternately, a ( relative radioquelide "1" mix fraction (f )gmay be taken from Table 5."-1 as a function of time after shutdown, and substituted in place of the ratlo of eachh$^ tothesumofallhSJAE in Equation 3-28 above to determine the relative fraction of each noble gas potentially available for release to the total (example calculations can be found in Apper. dix A). Just prior to plant startup before a SJAE sample can be taken and analyzed, the monitor alarm setpoints should be based on Xe-138 as representing the most prevalent high dose factor noble gas expected to be present shortly after the plant returns to power. Monitor alarm setpoints which have been determined to be conservative under any plant conditions may be utilized at any time in lieu of the above assumptions. Equation 3-7 can be applied under the following conditions (otherwise, justify Method I or consider Method II): ,
- 1. Normal operations (not emergency event), and h 2. Noble gas releases via the plant stack to the atmosphere.
3.5.2 Basis For Method I The methods to calculate skin dose rate parallel the total body dose rate methods in Section 3.4.3. Only the differences are presented here. Method I may be used to show that the Technical Specification which limits skin dose rate from noble gases released to the atmosphere (Technical Specification 3.8.E.1) has been met for the peak noble gas release rate. Method I was derived from Regulatory Guide 1.109 as follows: S + 3.17E+04 Qg (X/Q) 0FS g (3-8) D - 1.11 S p D tr 1 Approved By: t<AKic( ~ Revision d Date J 3-21 , ( 4172R I
3 mrem DCl-yr Ci sec mrem-m I yr I# I} I} Imrad} yr IC1-sec' 7,I Y pct-yr } y where: 1.11 - Average ratio of tissue to air absorption coefficients will convert mrad in air to mrem in tissue. DFgY (3_g; O ir
- 3.17E+04 Qg (X/Q) 3 mrad y pC1-yr g g) (s_ec)e mrad-m g
yr gC1-sec) yr ,3 pct-yr now D /Q /[X/Q) (3- m O finite - air 3 see I mrad m Imrad} I yr yr II ,3 Isec' and Og - 31.54 hST (3 11) g ) (C1-sec) guCl)
- pCl-yr see (3-1:)
so R skin
" I II S F
1E+06 [X/Q)Y 1 hf 0F{ (mrem} ( } ( } (pg' set uC1' mrad-m pCl-yr ' yr pC1 sec
+ IE+06 X/Q hf 0FS g 3
oC1 sec utt mrem-m g ) gCi ) ,3 see pCi-yr substituting I- [X/Q)Y - 7.2E-07 sec/m3 X/Q - 6.3E-07 sec/m3 Revision J Date- Approved By O. -
>-22 t .,,,,
SF - Shielding factor - 1.0 for dose rate determinations gives k nin - 0.50 hf 0F{
+ 0.63 hf 0FSg (3- E i 1 3 3 g
mrem y (DC1-sec-mremygg) gmre'm-m ) gott-sec) gg) gmrem-m ) yr 3 sec pCl-yr 3 sec pCi-yr C1-m -mrad C1-m
- (3 10 1
hf(0.80DF{+0.630FS) g define OFj-0.80DFJ+0.630FS g (3-15: then k - DFj (3-7) skin g mrem y gg) gmrem-sec) yr sec pCl-yr The selection of critical receptor, outlined in Section 3.10 is inherent Method I, as it determined the maximum expected off-site atmospheric dispersict I factors based on past long-term site-specific meteorology. 3.5.3 Method II If Method I cannot be applied, or if the Method I dose exceeds the limit. then Method II may be applied. Method II consists of the models, input cata at: assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The base case analysis, documented above, is a good example of the use of Method II. It is a-acceptable starting point for a Method II analysis. Analyses requiring Methcc I: calculations should be referred to YNSO to be performed and documented. [ i Revision J DatpEC 2 2 1986 A roved By:,
, v b
3-23 4172R
1 3.6 Method to Calculate the Critical Organ Dose Rate from Iodines, Tritium a.: Particulates a with T1/2_ Greater Th6n 8 Days i Technical Specification 3.8.E.1.b limits the dose rate to any organ, denoted Rgn, from I-131. I-132, 3H, and radionuclides in particulate form wi'.h half lives greater than 8 days to 1500 mrem / year to any organ. The peak release rate averaging time in the case of todines and particulates is comensurate with the time the lodine and particulate samplers are in service between changeouts (typically a week). By limiting the maximum R gn to a rate equivalent to no more than 1500 mrem / year, assurance is provided that the critical organ dose accrued in any one year by any member c' the general public will be less than 1500 mrem. Use Method I first to calculate the critical organ dose rate from the peak release rate via the plant vent stack. Method I applies at all release rates. Use Method II if Method I predicts a dose rate greater than the Technical Specification limits (i.e., use of actual meteorology over the period of interest) to determire if, in fact, Technical Specification 3.8.E.1.b had actually been exceeded during the sampling period. 3.6.1 Method I The critical organ dose rate can be determined by multiplying the individual radionuclide release rates by their respective dose factors and i summing all their products together, as seen in the following Equation 3-16 (an example calculation is provided in Appendix A): 1 ite , - h5TP DFG ggo (3 16) 1 g mrem y guC1) gmrem-sec) yr sec pCl-yr Revlsion d Da h Approved By: . C _. V (. 3-24 4172R l
( where: hSTP - Stack activity release rate dete:ctnation cf radier.e.1;de "t" I s (Iodine-131. Iodine-133, particuid tes with half-lides greater than 8 days, and tritium), in pC)/sec. For 1 - Sr89, Sr90 or tritium, use the best estimates (such as most recent
. measurements).
DFGje,-Sitespecificcriticalorgandosefactorrate(*}f,C) for a gaseous release. See Table 1.1-12. Equation 3-16canbeappliedunderthefollowingconditionskotherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Tritium, todine, and particulate releases via the plant stack to the atmosphere.
3.6.2 Basis for Method I k The methods to calculate critical organ dose rate parallel the total body dose rate methods in Section 3.4.3. Only the differences are presente: here. Method I may be used to show that the Technical Specification which Ilmits organ dose rate from todines, tritium and radionuclides in particulate form with half lives greater than 8 days (hereafter called Iodines and Particulates or "I+P") released to the atmosphere (Technical Specification 3.8.E.1.b) has been met for the peak I + P release rates. The equation for kg ,is derived by modifying Equation 3-25 from i Revision J Date Approved By: b v 4172R
7 Section 3.9 as follows: k, g
= Qg 0FG gg, (3-17)
(mrem) (C1) (*]*) applying the conversion factor, 31.54 (Cl-sec/pC1-yr) and converting Q to Q ir pCl/see as it applies to the plant stack yields: STP (3-1E: i kg , 31.54 Q OFG gg, i gmrem) gCl-sec) gg)gmrem) yr pCi-yr sec C1 Eq. 3-18 is rewritten in the form: k, g t [ OFGlC0 (3 @ g mrem y gg) (mrem-sec) yr sec pCi-yr where
- 31.54 0FG ggg (2-2:.
OFGje gmrem-sec) (Cl-sec) pct-yr pC1-yr (mrem)C1 The selecticn of critical receptor, outlined in Section 3.10 is inherent in Method I, as are the maximum expected off-site atmospheric dispersion factors based on past long-term site-spectfle meteorology. Should Method II be needed, the analysis for critical receptor critical pathway (s) and atmospheric dispersion factors may be performed wtth actual meteorologic and latest land use census data to identify the location of these pathways which are most impacted by these type of releases. M. J C
' Revision J Date - . Approved By: .~
i .d% k A 3-26 4172R
3.6.3 Method !! If Method I cannot be appliad, er if the Method I dose exceeds the limit, then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The base case analysis, documented above, is a good example of the use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented. O l i l Approved By: ,C Revision d Da h V 3-27 4172R
3.7 Method to Calculate the Gamma Air Dose from Noble Gases Technical Specification 3.8.F.1 limits the gamma dose to air frem ncble gases at any location at or beyond the site boundary to 5 mrad in any quarter and 10 mrad in any year. Dose evaluation is required at least once per month. Use Method I first to calculate the gamma air dose for the plant stack releases during the period. Method I applies at all dose levels. Use Method II if a more accurate calculation is needed. 3.7.1 Method I The gamma air dose from plant stack releases is: (3-21) D ar = 0.023 i Qg 0F{ 3 (mrad) (D'-#) 3 (C1) (mrad-m )
/~ C1-m pC1-yr where:
Q3 = total noble gas activity (Curies) released to the atmosphere via the plant stack of each radionuclide "1" during the period of interest. OFJ-gammadosefactortoairforradionuclide"i". See Table 1.1 10 Equation 3-21 can be applied under the following conditions (otherwise justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Noble gas releases via the plant stack to the atmosphere.
Revision O Date Approved By: k
/ '
3-28 4172R i
\ - I 3.7.2 Basis for Method I , k tiethod ,I'may be used to show that the Technica? Specification which limits off-site gamma air dose from gaseous effluents (3.8.F.1) has been met l' for releases over appropriate periods. This Technical Specification is based on the Objective in 10CFR50, Appendix I, Subsection 8.1, which limits the estimated annual gamma air dose at unrestricted area locations. Exceeding the Objective does not immediately limit plant operation but requires a report to yhe NRC. For any noble gas release, in any period, the dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109 with the added assumption that Ofinite=DD/QF/u/O. (3-22) D ar
=3.17E+04[XIQF Qg DF{
1
# 3 8d' (mrad) ( g) (sec/m ) (C1) ( ,,C
}
s where:
.[X/Q)Y . maximum annual average gama atmospheric dispersion factor 3
- 7.2E-07 (sec/m )
Qg
- number of curies of nooie gas "1" released which leads to:
(3-21) 0,{r - 0.023 1 Qg DF{ d , (mrad) (D '-{} (Cl) ( _
)
Cl-m
.ne main cifference between Method I and Method 11 is that Method 11 would allow the ese of actual meteorology to determine [X/Q]Y rather than use the maximum long-term average value obtained for the ye 1978 to 1982 Approved By: / 7 Revision 3 Date' .
3-29 4172R i
3.7.3 MeQhod II
' If the Method I dose determination indicates that the Technical Specification limit may be exceeded, or if a more exact calculation is required, then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A),
except where site-specific models, data or assumptions are more applicable. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented. (. t r [s Revision 3 Dah Approved By: E uk gv 3-30 4172R i l..
3.8 Method to calculate the Beta Air Dose from Noble Gases Technical Specificatier. 3.8.F.1 limits the Deta dose to air from noble gases et any location at or beyond the site boundary to 10 mrad in any quarte-and 20 mrad in any year. Dose evaluation is required at least once per month, i Use Method I first to calculate the beta air dose for the plant stack releases during the period. Method I applies at all dose levels. Use Method II if a more accurate calculation is needed or if Metho:! ! cannot be applied. 3.8.1 Method I The beta air dose from plar.t vent stack releases is: 0 = 0.02 Q3 0F (3-:21 tr 1 [' (mrad) (D '-*#) 3 (Ci) (mrad-m 3 pCl-yr ) C1-m where: See Table 1.1-10. DFf=betadosefactortoairforradionuclide"1". Qg - total noble gas activity (Curies) released to the atmosphere via the plant stack of each radionuclide "i" during the period of interest. Equation 3-23 can be applied under the following conditions (otherwise justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Noble gas releases via the plant stack to the atmosphere.
Revision 3 Date Approved By: Bt c ,.,, e 4172R
f 3.8.2 Basis for Method I ; x This section serves three purposes: (1) to document that Metnod I complies with appropriate NRC regulattens, (2) to provide background and trtining information to Method I users, and (3) to provide an introductory user's guide to Method II. The methods to calculate beta air dose parallel the gamma air dose methods in Section 3.7.3. Only the diff'erences are presented here. Method I may be used to show that the Technical Specification.which limits off-site beta air dose from gaseous effluents (3.8.A.1) has been met " ,j for releases over appropriate periods. This Technical Specification is base: on the Objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated annual beta air dose at unrestricted area locations. Exceeding the Objective does not immediately limit plant operatien b.: requires a report to the NRC within 30 days. For any noble gas release, in any period, the dose is taken from [. i Equations B-4 and B-5 of Regulatory Guide 1.109: 0F (3-20 0 tr
- 3.17E+04 X/Q Qg 1
3 (mrad) (pCi-yr' (see ' (mrad-m pC1-yr ' Ci-sec substituting X/Q = Maximum annual average undepleted atmospheric dispersion factor. 3
- 6.3E-07 sec/m q f c Revision J Date Approved By: / k 3-32 {
4172R l
We have Dlg7 0.02 (3-23) 1 Qg DFf d (mrad) ( r) (C1) ( _
)
3.8.3 Method II , If Method I cannot be applied, or if the Method I dose determination indicates that the Technical Specification limit may,be exceeded, or if a morE exact calculation is required, then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109. I Rev. 1 (Reference A), except where site-specific models, data or assum;;tions are more applicable. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented. [ i I~*99 ,, ,I #" Revision d* Datr* ~ ~ Approved By: y
. r, .x
- f. 3-33 4172R
3.9 Method to Calculate the Critical Organ Dose from Iodines. Tritium and Particulates
\.
Technical Specification 3.8.G.1 limits the critical organ dose to a Member of the Public from radioactive Iodines, Tritium, and particulates with half-lives greater than 8 days (hereafter called "I+P") in gaseous effluents to 7.5 mrem per quarter and 15 arem per year. Technical Specification 3.8.M.1 limits the total body and organ dose to any real member of the public from all i-station sources (including gaseous effluents) to 25 mrem in a year except for \ .the thyroid, which is limited to 75 mrem in a year. .
)
Use Method I first to calculate the critical organ dose fron a vent stack release as it is simpler to execute and more conservative than Method II. Method I is conservative for total body, critical organ, and thyroid dose greater than 0.1 mrem. Use Method II if a more accurate calculation of critical organ dose is needed (i.e., Method I indicates the dose is greater than the limit), or if Method I cannot be applied, or if the majority of the release is Iodine and the 75 mrem limit for Specification 3.8.L.1 needs to be evaluated. 3.9.1 Method I ( 3- 2 5 :- D gg = Qg DFG gg 1 (mrem) (C1) (*]*)
- Total activity (C1) released to the atmosphere of radionuclice Qg For strontiums, use the mest l
"1" during the period of interest.
recent measurement. For each DFG yg,- Site-specific critical organ dose factor (mrem /C1). radionuclide it is the age group and organ with the largest dose factor. See Table 1.1-12. Approved By: f. Revision U Datb 4-3-34 4172R
I Equation 3-25 can be applied under the following conditions (otherwise,
~ justify Method I or consider Method II):
*=
- 1. Normal operations (not emergency event),
- 2. I+P releases via the plant stack to the atmosphere, and
- 3. Any continuous or batch release over any time period.
/ 3.9.2 Basis for Method I This section serves three purposes: (1) to document that Method I complies with appropriate NRC regulations, (2) to provide background and training information to Method I users, and (3) to provide an introductory user's guide to Method II. Method I may be used to show that the Technical Specifications which limit off-site organ dose from gases (3.8.G.1 and 3.8.L.1) have been met for releases over the appropriate periods. These Technical Specifications are based on Objectives and Standards in 10CFR and 40CFR. Technical Specificatic-3.8.G.1 is based on the ALARA Objectives in 10CFR50, Appendix I, Subsection II C. Technical Specification 3.8.M.1 is based on Environmental Standards for Uranium Fuel Cycle in 40CFR190 (hereafter called the Standard) which applies to direct radiation as well as 11guld and gaseous effluents. These methods apply only to I+P in gaseous effluents contribution. f Exceeding the Objective or the Standard does rat immediately limit In addltien. plant operation but requires a report to the NRC within 30 days. a waiver may be required. Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I). The use below of a single " critical receptor" provides part of Revision 3 Date - Approved By: fb 3-35 4172R
f the conservative margin to the calculation of critical organ dose in Method l I. Method II allows that actual individuals, with real behavior:. be take-into account for any given release. In fact, Method I was based on a Heine: I ( II analysis of the critical receptor for the annual average conditions. For purposes of complying with the Technical Specifications 3.8.G.2 maximum annua; average atmospheric dispersion factors are appropriate for batch and continuous releases. That analysis was called the " base case"; it was then reduced to form Method I. The base case, the method of reduction, and the f assumptions and data used are presented below. The steps performed in the Method I derivation follow. First', in the base case, the dose impact to the critical receptor in the form of dose
)
i factors (mrem /C1) of I curie release of each I+P radionuclide to gaseous effluents was derived. Then Method I was determined using simplifying and further conservative assumptions. The base case analysis uses the methods, data and assumptions in Regulatory Guide 1.109 (Equations C-2, C-4 and C-13 in Reference A). Tables 3.9-1 and 3.9-2 outline human consumption and environmental parameters used in the analysis. It is conservatively assumec
' that the critical receptor lives at the " maximum off-site atmospheric
( dispersion factor location" as defined in Section 3.10. However, he is exposed, conservatively, to all pathways (see Section 3.10). The resulting site-specific dose factors are for the maximum organ and the age group witn the highest dose factor for that organ. These critical organ, critical age dose factors are given in Table 1.1-12. For any gas release, during any period, the increment in annual average dose from radionuclide "1" is: (3-20 ADgge - QgDFG ggo "1" and Qg is where DFG,gn is the critical dose factor for radionuclide the activity of radionuclide "1" released in curies. a r
- Revision O Date Approved By: .
[ 4172R 3-36
f Method I is more conservative than Method II in the region of the t Technical Specificatien 1121:s bacat.se it is based on the fcilowing re n : tic-of the base case. The dose factors DFG gen used in Method I were choser. fro-the base case to be the highest of the set for that radionuclide. In effect each radionuclide is conservatively represented by its own critical age gro;; and critical organ. Because of the assumptions about receptors, environment, and radionuclides and because of the low Objective and Standard, the lack of [ h immediate restriction on plant operation, and the adherence to 10CFR20 concentrations (which limit public health consequences) a failure of Method : ( (i.e., the exposure of a real individual being underestimated) is improbable and the consequences of a failure are minimal.
-3.9.3 METHOD II If Method I cannot be applied, or if the Method I dose exceeds the limit or if a more exact calculation is required, then Method II should be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The base case analysis, documented above, is a good example of th's use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Mett::
l II calculations should be referred to YNSD to be performed and documentet. l i s a s
, ~ 1986 Approved By:
Revision J Dafe - 3-37 4172R I
-. ,- , ,. w., -----, - - -- . . , - - - , , - , - ~ - - -
ba3.9-1 Environmentral Parameterra fer Caseous Ef fluentn et Vermont Yeekco (Derived from Reference A) Vegetables- Cow Milk Coat Milk Meat' Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored YV Agricultural (Kg/M2 ) 2. 2. 0.75 2. 0.75 2. 0.75 2. Productivity P Sail Surfqce (KC/M2 ) 240. 240. 240. 240. 240. 240. 240. 240. Density T 'ransport Time (HRS) 48. 48. 48. 48. 480. 480. to User TB Soil Exposure (HRS) 131400. 131400. 131400. 131400. 131400. 131400. 131400. 131400. Time TF Crop Exposure (HRS) 1440. 1440. 720, 720. 720. 720. 720. 720. Time to Plume TH Holdup After (HRS) 1440. 24. O. 2160. O. 2160. O. 2160. Harvest QF Animals Daily (KC/ DAY) 50. 50. 6. 6. 50. 50. Feed FP Fraction of Year 0.50 0.50 0.50 on Pasture FS Fraction Pasture 1. 1. 1. when on Pasture FG Fraction of Stored 0.76 Veg. Crown in Carden FL Fraction of Leafy 0.50 Veg. Crown in Carden FI Fraction Elemental Iodine = 0.5 1 H Alisol ut e Humid i t y = H.00 (gm/Ml) ;
i \' Table 3.9-2 Usage Factors for Various Gaseous Pathways at Vermont Yankee (from Regulatory Guide 1.109, Table E-5) 1 Age Leafy Group Vegetables Vegetables Milk Meat Inhalaticn (kg/yr) (kg/yr) (1/yr) (kg/yr) (m3 /yr)
;- Adult 520.00 64.00 310.00 110.00 8000.00 Teen 630.00 42.00 400.00 65.00 8000.00 Child 520.00 26.00 330.00 41.00 3700.00 Infant 0.00 0.00 330.00 0.00 1400.00 Revision 3 _ Date , '.J Approved By:. % G O /
3-39 4172R
[. l l
.3.10 Rece dor Potrts and Annual Average Atmospheric Dispersion factors fo-Important Exposure Path.ays
/ The gaseous effluent dose methods have been simplified by assuming ar individual whose behavior and living habits inevitably lead to a higher dcse than anyone else. The following exposure pathways to gaseous effluents liste: in Regulatory Guide 1.109 (Reference A) have been considered: ( l 1. Direct exposure to contaminated air;
- 2. Direct exposure to contaminated ground;
- 3. Inhalation of air;
- 4. Ingestion of vegetables;
- 5. Ingestion of goat's milk; and
- 6. Ingestion of meat.
Section 3.10.1 details the selection of important off-site locations and receptors. Section 3.10.2 describes the atmospheric model used to convert meteorologic data into atmospheric dispersion factors. Section 3.10.3 presents the maximum atmospheric dispersion factors calculated at each of tre off-site receptor locations. l 3.10.1 Receptor Locations l Three important receptor locations are considered in the dose and dese l l rate equations for gaseous radioactive effluents. They are: l 1. The point of maximam gamma exposure; l f Re .'i s ion 3 Date,_
'~
Approved By:i _ k 5 3-40 4172R
f
- 2. The point of maxtrum ground level air concentration of radionuclides; ard
- 3. The point of maximum ground level air concentration of radionuclides where a real allk animal exists.
The point of maximum gamma exposure (5 sector, 400 meters) was determined by finding the maximum annual average gamma X/Q at any off-site 1 location. The location of the maximum ground level air concentration of radionucIldes (WNW sector, 2415 meters) was determined by finding the maxte r annual average undepleted X/Q at any off-site location. The point of maxim.- ground level air concentration of radionuclides where a real milk animal exists (WNW sector, 3000 meters) was determined by finding the maximum depleted X/Q at a real milk animal location. 3.10.2 Vermont Yankee Atmospheric Dispersion Model The annual average atmospheric dispersion factors are computed for routine (long-term) releases using Yankee Atomic Electric Company's (YAEC) AEOLUS Computer Code (Reference B). AEOLUS is based, in part, on the straight-line airflow model discussed in Regulatory Guide 1.111 (Reference C). The valley in which the plant is located is considered by the model. AEOLUS produces the following annual average atmospheric dispersten factors for each location:
- 1. Undepleted X/Q dispersion factors for evaluating ground level concentrations;
- 2. Depleted X/Q dispersion factors for evaluating ground level concentrations; Revision '3 DayC 2 2 MO Approved By w -
3-41 4172R
L
- 3. Gawna X/0 dispersion factors for evaluating gamma dose rates frc a sector averaged finite cloud (multiple energy undepleted scurce);
and
- 4. 0/Q deposition factors for evaluating dry deposition of elemental radiolodines and other particulates.
{ Gamma dose rate is calculated throughout this ODCM using the finite l ' cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, Section 7-5.2.5). That model is implemented through the definition of ar effective gamma atmospheric dispersion factor, (X/QY ) (Reference B, Section 6), and the replacement of X/Q in infinite cloud dose equations by the [X/QY ). 3.10.3 Annual Averace Atmospheric Olspersion Factors for Receptors Actual measured meteorological data for the five-year period, 1978 through 1982, were analyzed to determine all the values and locations of the maximum off-site annual average atmospheric dispersion factors. Each dose a : dose rate calculation incorporates the maximum applicable off-site annual average atmospheric dispersion factor. The values used and their locatiens are summarized in Table 3.10-1. Table 3.10-1 also indicates which atmospheric dispersion factors are used to calculate the varicus doses or dose rates cf interest. e I e h8V j dQQ 3 hd( AhhICvcd 8f - 3-42 4172R
Table 3.10-1 Vermont Yankee Dilution Factors Dose to Critical Dose Rate to Individual Dose to Air Organ Total Body _ Skin Critical Organ Gaanns Beta _Thysold
# - 4.6E-07( - - 4.6E-07( '
X/Q depleted (**3 ) - a 6.3E-07 2) 6.3E-07 - X/Q undepleted (* - -
) -
a
- 8.9E-10 - - 8.9E-10( '
C/Q ( ) - a 7.2E-07 7.2E-07( ' - 7.2E-07 - - X/QI( ) (1) Maximum gamma exposure point: S sector. 400 meters (0.25 miles). (2) Maximum ground level concentration: WNW sector. 2415 meters (1.50 miles). (3) Worst real milk animal concentration: WNW sector. 3000 meters (1.86 miles). I (,
- m. l #* 3 A I'I' V"d OVdf' _ d. 3.
lie v is.iessi Date _'__ _ t
[
; 3.11 Method to_ calculato Dose from Plant Operation Technical Specification 3.8.M.1 restricts the dose to the whole body or any organ to any member of the public from all station sources (including direct radiation from the turbine and reactor building) to 25 mrem in a calendar year (except the thyroid, which is limited to 75 arem).
3.11.1 Method The maximum contribution of direct dose to the whole body or to any organ due to N-16 decay from the turbine is: Dd = 1.29E-06 E (3-27) (mres) (arem) (Web) Wh e where: E = gross electric output over the period of interest (Neh) 1.29E-06 = (2.14E-06 mR/W ,h) (0.6 mrem /mR) In addition to the calculations of direct dose due to N-16 decay from the turbine hall, direct dose contribution to off-site receptors from iden-tified fixed sources, such as solid waste storage facilities, shall be included in the estimate of total direct dose off-site to any member of the public. Analytical design calculations of direct dose from these sources can be used in lieu of direct measurements, such as with a high pressure ion chamber. Revision 3 DaSO 2 Approved By: e 3-44 u
[ l 3.11.2 Basis of Method The majer scurce of direct radiation (including sky shine) from the station during normal operation is due to N-16 decay in the turbine building. Because of the orientation of the turbine building on the site, and the shielding effects of the adjacent reactor building, only the seven westerly sectors (SSW to NNW) see any significant direct radiation. High pressure ionization chamber (HPIC) measurements have been made in the plant area in order to estimate the direct radiation from the station. The chamber was located at a point along the west site boundary which has beer, determined to receive the maximum direct radiation from the plant. Using measurements of dose rate made while the plant operated at different power levels, from shutdown to 100 percent, a gross electric output to dose rate conversion facter of 2.14E-06 mR/MWh has been derived at the location of the nearest resident based on measurements at the site boundary. Field measurements of exposure, in units of Roentgen, were modified by multiplying by 0.6 to obtain whole body dose equivalents in units of rem in accordance
- with recommendations of HASL Report 305 (Reference F) for radiation fields resulting from N-16 photons.
Therefore, knowing the gross megawatts generated during the period of interest, one may obtain an estimate of the maximum dose from direct radiation at the nearest residence through the use of Equation 3-27 due to N-16 decay. The direct dose contribution from other significant sources are accounted for by analytical calculations of source strength, geometry, and shielding facters as they relate to off-site receptors, Revision 3 Da Approved By: b c 3-45 4172R
3.12 Cumulative Ooses Cumulative Doses fcr a calendar quarter and a calendar year must be 7 i maintained to meet Technical Specifications 3.8.B.1, 3.8.F.1 and 3.8.G.I. I r. addition, if the requirements of Technical Specification 3.8.H.2 dictate, cumulative doses over a calendar year must be determined for Technical Specification 3.8.M.I. To ensure the limits are not exceeded, a running total must be kept for each release. 0 0 4 0 3-46 4172R
k l 5.2 Gaseous Effluent Instrumentation Setpoinh Technical Specification 3.9.B.1 requirec that the radicactive gaseces effluent instrumentation in Table 3.9.2 of the Technical Specifications have their alarm setpoints set to insure that Technical Specifications 3.8.E.1 and 3.8.K.1 are not exceeded. Technical Specification 3.8.E.1.a limits the activity concentration in off-site gaseous effluents to well below the appropriate MPCs in 10CFR20 by limiting the whole body and skin dose rates to areas at or beyond the site boundary. Technical Specification 3.8.K.1 limits the gross radioactivity release rate at the steam jet air ejector (SJAE) to 0.16 Cl/sec. 5.2.1 Plant Stack Noble Gas Activity Monitors (RR-108-1A and RR-108-18) and Augmented Off-Gas System Noble Gas Activity Monitors (3127 and 3128) The plant Stack and A0G noble gas activity monitors are shown on Figure 6-2.
. 5.2.1.1 Method to Determine the Setpoint of the Plant Stack Noble Gas Activity Monitors (RR-108-1A and RR-108-18) and the Augmented O'f-Gat System Noble Gas Activity Monitors (3127 and 3128)
The setpoints of the plant stack and A0G system noble gas activity monitors are determined in the same manner. The plant stack or A0G system noble gas activity monitor response in counts per minute at the limiting off-site noble gas dose rate to the total body or to the skin is the setpoint, denoted R spt. R spt is the lesser of: R 094 S (5-9) t" g 0FB 3 (cpm) (mrem-uCl-m ) (com-cM) (m) ( DCl-yr) yr-pCl-sec pCl e,3 arem-m 3 f Revision 3 Dater' Approved By: Lhr - - 5-9 4773R
and: h R - 3,000 5 -- 0 (5 1C ' 9 3 (CP"} (mrem) yr geom-cm } ([see I uCi-yr } ( pC1 mrem-sec where: R t
= Response of the monitor at the limiting total body dose rate (cpm) 3 500 cmrem-uC1 ,)
694 - (IE+06) (7.2E-07) yr-pCl-sec 500 - Limiting total body dose rate (mrem /yr) IE+06 - Number of pCl per pC1 (pCl/pC1)
. 7.2E-07 = [X/Q)T, maximum annual average gamma atmospheric dispersic-factor (sec/m3)
S g
- Appropriate (plant stack or A0G system) detector counting efficiency (com/(pC1/cc))
F = Appropriate (plant stack or A0G system) flow rate (cm3 /se:) DFB g
= Composite total body dose factor (mrem-m3 /pCl-yr) hg DFB g i
- (5 m o I e Revision O Date ' - Approved By: 0 "
5-10 4773R 6 he iin i -
hg - The relative release rate of noble gas "1" in the mixtre atthemoniter(eitherthestack,hN or the ACG. Q # ) for noble gases identified (pCl/sec) 3 DFB g - Total body dose factor (see Table 1.1-10) (mrem-m /pCi-ye 3 " . Response of the monitor at the limiting skin dose rate R, (cpm) ? 3,000 = Limiting skin dose rate (mrem /yr) - DF' = Composite skin dose factor (mrem-sec/pCl-yr) hg DFj 1
. (5.':
bg 1 DFj Combined skin dose factor (see Table 1.1-10) (mrem-sec/pC1-yr) 5.2.1.2 PlantStackNobleGasActivity58cniterSetootntExample The following setpoint example for the plant stack noble gas activit. monitors demonstrates the use of equations 5-9 and 5-10 for determining setpoints. The plant stack noble gas activity monitors, referred to as " Stack Gas !" (RR-108-1A) and " Stack Gas II" (RR-108-18), consist of beta sensit',e scintillation detectors, electronics, an analog ratemeter readout, and a digital scaler which counts the detector output pulses. A strip chart recorder provides a permanent record of the ratemeter output. The monitors have typical calibratton factors, 5 , of IE+08 cpm per 1 pC1/cc of noble 9
? -
Revision 3 Date Approved By: $ - 5-11 4773R
L pas. The ncminal plant stack flow is 7.5E+07 cc/sec ((160.000 cfm x 28.300 3 cc/ft )/60 sec/ min). When monitor responses indicate that activity levels are below the LL0s at the stack (or A0G) monitors, the relative contribution of each noble gas radionuclide can conservatively be approximated by analysis of a sample of off-gas obtained during plant operations at the steam jet air ejector (SJAE). This setpoint example is based on the following data (see Table 1.1-10 for OF8g andDFj): h5AE OF8 g 0Fj gg) z mrem-m DCi-yr mrem-sec) uCt-yr i see Xe-138 1.03E+04 8.83E-03 9.97E-03 Kr-87 4.73E+02 5.92E-03 1.11E-02 Kr-88 2.57E+02 1.47E-02 1.37E-02 Kr-85m 1.20E+02 1.17E-03 1.90E-03
. Xe-135 3.70E+02 1.81E-03 2.69E-03 Xe-133 1.97E+01 2.94E-04 4.75E-04
.SJAE Qg 0FB,
' <$~I '
OF8 - g .SJAE Qg 1 7 .SJAE L Qg 0FB, - (1.03E+04)(8.83E-03) + (4.73E,02)(5.92E-03)
+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)
+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) 3
= 9.83E+01 (pCl-mrem-m /sec-pCl-yr)
Revisten 3 OsE Approved By -- _ 5-12 4773R
hSJAE 1.03E+04 + 4.73E+02 + 2.57E+02
+ 1.20E+02 + 3.70E+02 + 1.97E+01 1.15E+04 pCl/sec 9.83E+01 0FB g
= 1.15E+04 8.52E-03 (mrem-m3 /pC1-yr) tb = 694 5 (5-9)
R p 9 h
= (694) (IE+08) (7.5E+07) (8.52E-03)
= 109,000 cpm Next:
P .SJAE
/_, Qg 0Fj
' (5-12)
OF'C fSJAE
.SJAE Qg 0Fj.(1.03E+04)(9.97E-03)+(4.73E+02)(1.11E-03)
+ (2.57E+02)(1.37E-02) + (1.20E+02)(1.90E-03)
+ (3.70E+02)(2.69E-03) + (1.97E+01)(4.75E-04)
. 1.08E+02 (pCl-mrem-sec/sec-pCl-yr) 1.08E+02 0F g = 1.15E+04
~
?
..n n;;J C Revision l Date Approved By:_ f _
5-13 4773R
= 9.39E-03 (mrem-secluct-yr)
R ,g
,5 " ' " - 3,C009 5 hD (5-M
- (3,000) (IE+08)
(7.5E+07) (9.39E-03)
- 426,000 com D 3 A The setpoint, Rspt, is the lesser of and R .
Dt For the noble gas mixture in this example R spt is less than , R ", indicating that the total body dose rate is more restrictive. Therefore, in this example the " Stack Gas I" and " Stack Gas II" noble gas activity monitors should each be set at 109,000 cpm above background or at some conservative value below this (such as that which might be based on controlling release rates from the plant in order to maintain off-site air concentrations below 2 x MPC when averaged over an hour). 5.2.1.3 Basis for the Plant Stack and AOG' System Noble Gas Activity Monit0* Setpoints The setpoints of the plant stack and A0G system noble gas activity monitors must ensure that Technical Specification 3.8.E.1.a is not exceeded. Sections 3.4 and 3.5 show that Equations 3-5 and 3-7 are acceptable methecs for determining compliance with that Technical Specification. Which equatier (i.e., dose to total body or skin) is more limiting depends on the noble gas mixture. Therefore, each equation must be considered separately. The derivations of Equations 5-9 and 5-10 begin with the general equation for the response R of a radiation monitor: R . 5 C,g (5 13) 9g (cpm). (C *)( )
^
q' g[; p Revision 3 Date Aonroved By: t rk" c' . __ 5-14 4773R
where: I R = Response of the instrument (com) 3 S Detector counting efficiency for noble gas "1" (cpm /(pCi/cm )) 9g C,g - Activity concentration of noble gas3 "1" in the mixture at the noble gas activity monttor (pCl/cm ) Therelativereleaserateofeachnoblegas,hg(pCl/sec), in the tota release rate is normally determined by analysis of a sample of off-gas obtained at the Steam Jet Air Ejector (SJAE). Noble gas release rates at the plant stack and the A0G discharge are usually so low that the activity concentration is below the Lower Limit of Detection (LLD) for sample analysts. As a result, the release rate mix ratios measured at the SJAE are used to present any radioactivity being discharged from the stack, such as tray have resulted from plant steam leaks that have been collected by but1 ding ventilation. For the A0G monitor downstream of the charcoal delay beds, this leads to a conservative setpoint since several short-1tved (high dose facter) noble gas radionucitdes are then assumed to be present at the monitor, whter in reality, would not be expected to be present in the system at that point. During periods when the plant is shutdown (after five days), and no radioactivity release rates can be measured at the SJAE, Xe-133 is the dominant long-lived noble gas and may be used as the referenced radionuctice to determine off-site dose rates and monitor setpoints. Alternately, a relative radionuclide, "1", mix fraction (f ),gmay be taken from Table 5.2-1 as a function of time after shutdown (including periods shorter than five days) to determine the relative fraction of each noble gas potentially available for release to the total. However, prior to plant startup before a SJAE sample can be taken and analyzed, the monitor alarm setpoints should te based on Xe-138 as representing the most prevalent high dose factor noble gas expected to be present shortly after the plant returns to power. Monttor alarm setpoints which have been determined to be conservative under any plant conditionsmaybeuttllzedatanytimeinlieuoftheaboveassumptions. r t Q Approved Byi L _- Resiston 2 Date 5-15 4773R
,C,g. the activity concertration of noble gas "1" at the noble gas activity monitor, ma,v be expressed in terms of Og by dividing by F, the ap;ropriate flow rate. In tne case of the plant stack noble gas activity monitors the appropriate flow rate is the plant stack flow rate and for the A0G noble gas activity monitors the appropriate flow rate is the A0G system flow rate.
1 (5-u-C,g = hg p (h) ($) em "C (E) cm 3 where: Qg The release rate of noble gas "1" in the mixture for each noble gas identified. F - Appropriate flow rate (cm 3/sec) - Substituting the right half of Equation 5-14 Into Equat1on 5-13 for C,g yteIcs-(5 15 R = S 9g hg h (com) (CD *) (h) ( ) Cm The detector calibration procedure estabitshes a counting effleter:y for a given mix of nucitdes seen by the detector. Therefore, in Equation 5 5 one may substitute 59 for Sgg, where Sg represents the counting efficiency determined for the current mix of nucildes. If the mix of nutildes changes significantly, a new counting efficiency should be determined for calculat'r; the setpoint. 4 W Revision 3 Dath ApprovedBy:b fe
~
5-16 4773R
R = 5 9 h hi (5-1f" (cpm) (CD*-C*3)(E) pCl g,3 ($) see The total body dose rate due to noble gases is determined with Equation 3-5: R = 0.72 hg 0F8 g ( 3 - 5 ', tb 1 3 gerem) (DCl-sec) gg) gmrem-m ) yr Cl-m 3 sec pCl-yr where: k tb
= total body dose rate (mrem /yr)
. 0.72 = (1.0E+06) x (7.2E-07) (pCl-sec/pCl-m3 ) lE + 06 = number of pCI per pCl (pCl/pCl) 7.2E - 07 = (X/Q)Y, maximum annual average gamma atmospheric dispersion factor (sec/m ) h, = the release rate of noble gas "i" in the mixture for ea:- noble gas identified (pCl/sec) (Equivalent to
.ST Qg for noble gases released at the plant stack.)
DFB, = total body dose factor (see Table 1.1-10) (arem-m3 /pCl-yr) f ,-
** 3 D, \ m \
Revision d, Date ,_ Approved By:, s y ( 3 _ 5-17 4773R
l A ccmposite total body gamma dose factor, OF8g , may be defined such that: DF8 g hg = hg 0F8 g (5-17) 1 1 3 mrom-m 3 gg) gg)gmrem-m ) pCi-yr sec sec pC1-yr Solving Equation 5-23 for DF8 g yleids: hgDF8 g .
' (5-11)
DF8 g = , Og i Technical Specification 3.8.E.1.a ilmits the dose rate to the total 4 body from noble gases at any location at or beyond the site boundary to 500 mrem /yr. By setting R equal to 500 mrem /yr and substituting 0F8g for DFB g-tb
~. In Equation 3-5, one may solve for [ Qg at the limiting whole body noble gas I
j dose rate: h= g 694 0F8 c (S M l' i 3 guCl) gmrem-uC1-m ) goCl-yr ) sec yr-pCl-sec mrem-m 3 Substituting this result for hg in Equation 5-16 yields R t. the response of the monitor at the limiting noble gas total body dose rate: tb i 1 (5-9) y-R spt
- OI4 5 9 %
' 3 3 gg,,) gerem-uCl-m ) geom-cm ) )gDCl-yr )
yr-pCl-sec pCl cm arem-m 3 Revision d Date, 4. Approved By: '. _ i 5-18 4773P .! 4
l r The skin dose rate due to noble gases is determined with Equation 3-7: k5 0
. hg DFj (3-7)
[ gmrem) ggCl) gmrem-sec) L yr see pCl-yr r L where: k3
" - Skin dose rate (mrem /yr) hg -Thereleaserateofnoblegas"1"inthemixture{oreach g
{ noble gas identified (pC1/sec) (Equivalent to Qg for noble gases released at the plant stack.) l 0Fj - Combined skin dose factor (see Table 1.1-10) (mrem-sec/pCl-yr) Acompositecombinedskindosefactor,OFj,maybedefinedsuchthat: hg = hg 0Fj (5-19) OFj (mrem-sec) (gCl) guC1) (mrem-sec) pC1-yr sec sec pCi-yr Solvingequation5-19forDFjyields: l hg 0Fj OF' - 1 (5-12) C . 01 Technical Specification 3.8.E.1.a limits the dose rate to the skin frem noble gases at any location at or beyond the site boundary to 3,000 mrem /yr. By setting jskin equalto3,000 mrem /yrandsubstituting0F'forDFjin Equation 3-7 one may solve for [ Qg at the limiting skin noble gas dose rate: m 1 r Revision ~1 Date Approved By: (i f __ _, 5-19 4773R
T 1 (5-20)
- . 4 hg = 3,000 y i e gy.C 1 ) erem pCl-yr g
sec yr ygmrem-sec) 5 I" Substituting this result for hg in Equation 5-16 yields R5 t , the respM se of the monitor at the Ilmiting noble gas skin dose rate: I" R t
= 3,000 S g h ( 5- l 'J )
3 (cpm) (mrem}yr Icom-em pC) } (]see } I uCl-yr ) mrem-sec d l l l l Revision .3 o.te approved sy:<~ A s k ' - 5-20 4773R
.- ~ _
TABLE 5.2-1 Relative Fractions of Core Inventory - Noble Gases After Shutdown Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe- 138 Time Kr-83m Kr-8Se Kr-85 Kr-87
.118 .002 .010 .306 .061 .093 .263 t < 24 h .02 .043 .001 .083
.001 .004 .022 .758 .010 .198 --
24 hr < t < 48 h -- .003 .004 --
.006 .024 .907 .001 .058 --
l
.005 -- --
48 h i t < 5 d -- -- l
.016 .969 -- ,
-- .007 -- -- .008 !
5 d 3 t < 10 d
-- .014 -- -- .014 .006 .966 -- -- --
10 d I t < 15 d --
.950 -- --
.026 -- -- .002 .002 --
15 < t < 20 d -- --
-- .048 -- -- .034 .001 .917 -- --
20 i t < 30 d --
.070 -- .777 -- --
-- -- .152 -- --
30 $ t < 40 d --
.105 -- .517 -- --
-- -- .378 -- --
40 $ t < 50 d --
.108 -- .240 -- --
-- -- .652 - --
50 i t < 60 d --
.083 -- .082 -- --
-- -- .835 -- --
60 $ t < 70 d --
.055 -- .024 -- --
-- .920 -- --
t1 70 d G[ Approved By:fL h 3 D ' O Date DEC 2 2 M s Revision V 5-21 4183R
~ - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
e S l l I APPENDIX A METHOD I EXAMPLE CALCULATIONS f ( - MkN.. n vision 3 o.t. - ,,,,,y,, 3,. , 5103R
'(
s
- EXA.'*P LE C A LC'.'1..tT
- 0N NO . I f
IZEe Total Body Dose From Liquid Effluents References a) CDCM Sections 3.2 and 3.3 (Method I). f b) Technical Specifications 3.8.B.1 and 3.8.C.1. Problem Calculate the of f-site dose to the total body and maxic:um organ resulting f rcm the batch release of radioactive liquid effluents. Plant Data I a) Analysis from a representative grab sareple of the liquid waste volume to be discharged indicates the following radionuclide activities were
]
released to the Connecticut River: Activity Q g DFl imo itb Released (C1) (mrem /Ci) (mrem /Ci) i 3.40 E+00 1.75 E-04 1.75 E-04 E-3 1.72 E-03 8.27 E-02 2.67 E-01 Co-60 5.26 E+00 7.01 E+00 Co-134 3.51 E-03 7.20 E-02 2.52 E-03 1.46 E+00 I-131
- Total body dose factor from Table 1.1-11.
** Maximum organ dose factor from Table 1.1-11.
t I c i 's A -1 Approved By b - Rev!sion 3 Date u 5121R
,Ca_1;ulation The total body dose is calculated from Equation (3-1):
D
- N tb i itb (3-1)
(arem) (Ci) (arem/Ci) l therefore: Dtb = (3.40 E+00)(1.75 E-04) + (1.72 E-03)(8.27 E-02) + (3.51 E-03)(5.26 E+00) + (7.20 E-02)(2.52 E-03) = . Answer (1) D mrem e ta dy. tb = . Next, the maximum organ dose is calculated frem Equation (3-3): D,, = Qg DRg ,, g3,3)
,- (arem) (Ci) (mrem /Ci) \
therefore: D = (3.40 E+00)(1.75 E-04) + (1.72 E-03)(2.67 E-01) + (3.51 E-03)(7.01 E+00) + (7.20 E-02)(1.46 E+00) = Answer (2) i D , = 1.31 E-01 arem to maximum organ. I ~ Ravision 3 Date' _ t.- 2 Approved By _ 5121R
l I L EXAMPLE CALCULATION NO. 2 r l Int Total Body Dose Rate From Noble Cases References a) CDCM Section 3.4 (Method I). b) Technical Specification 3.8.E.1.a. t Problem a Calculate the off-site total body dose rate resulting from the release of noble gases from the plant stack during power operations. Plant Data i a) Maximum plant stack gas monitor (I or II) Count rate during period of interest (M): 80,000 epm b) Stack flow rate during release (F): 7.55 E+07 cc/sec (160,000 cfm x 4.72 E+02 **g#'** = ) c) Plant stack monitor detector counting i E+08 cpm per efficiency (Sg): uCi/cc d) The last measured release rate mix of
.SJAE noble gas from the SJAE (Q g ),
and corresponding dose factor DFB g from Table 1.1-10. c' nre R 2 1986 C ' Revision .3 Dat( 1 [ Approved By: ,y yr ~___ _- A-3 5103R
.SJAE DFB Qg i i (uci/see) (mrem-m /pci-yr)
Xe-138 5.15 E+03 8.83 E-03 Kr-87 2.37 E+02 5.92 E-03 Kr-88 1.29 E+02 1.47 E-02 Xe-135 1.85 E+02 1.81 E-03 ( Calculation The dose rate is calculated from Equations (3-5) and (3-28): (- k tb = 0.72 Q DFB g i (mrem) IpCi-see) uCi yr uCi-m 3 D Imrem-m pci-yr
}
and where the stack release rate is determined from:
* ^ (3-28)
.ST Qg g S
i
.SJAE E S (epm) i g (uCi/ce) cpm (E) sec
(" )
.SJAE First, determinethesum([)ofallQ g and the fraction that each ncble i
gas i represents in the total gas mix.
.SJAE Qi = (5.15 E+03) + (2.37 E+02) + (1.29 E+02) + (1.85 E+02)
= 5.70 E43 uCi/sec and the relative fraction of each noble gas:
9 f O \ Revision 3 oatlu - Approved 3y:.ck7% -
~
A-4 5103R
i Relative Fraction Qi /5.70 E+03 ( of Total f Xe-138 5.15 E+03/5.70 E+03 = 0.904 Kr-87 2.37 E+02/5.70 E+03 = 0.042 Kr-88 1.29 E+02/5.70 E+03 = 0.023 Xe-135 1.85 E+02/5.70 E+03 = 0.032 Next, the stack release rate of each noble gas i from Equation (3-28) can be substituted into Equation (3-5) to give the dose rate as: I M F fg DFB g ktb = 0.72 gg g
= 0.72 80,000 1/1E+08 7.55 E+07 g f
g DFB g
= 4.35 E+04 [(0.904)(8.83 E-03) + (0.042)(5.92 E-03) +
(0.023)(1.47 E-02) + (0.032)(1.81 E-03)] = Answer 4
= 375 mrem / year noble gas total body dose rate.
4 Revirion O Date, Approved By: (- V A-5 5103R
i EXAMPLE CALCULATION NC _3 . / IY.P' Y Total Body Dose Rate From Noble Cases [ References a) ODCM Section 3.4 (Method I). b) Technical Specification 3.8.E.1.a. Problem Calculate the off-site total body dose rate resulting from the release of noble gases from the plant stack recorded to have occurred 32 days after plan:
) shutdown.
Plant Data a) Maximum plant stack gas monitor (I or II) Count rate during period of interest (M): 80,000 cpm b) Stack flow rate during release (F): 7.55 E+07 cc/se (160,000 cfm x 4.72 E+02 **g#* = ) c) Plant stack monitor detector counting i E+08 cpm per efficiency (Sg): uCi/cc d) The noble gas six fractions f g (t) corresponding to 32 days taken from Table 5.2-1.
.r - ?, 2 I336 ,e Revision _ Date' Approved By: bAr b_ -
~
A-6 5103R
- _ - - _ _ _ ~ . _ _ _ . -
i day)* DFBg ** i i( Kr-85 0.152 1.61 E-05 Xe-131m 0.070' 9.15 E-05
'Xe-133 0.777 2.94 E-04 f
L
- Fraction of nuclide in mix as function of time (see Table 5.2-1).
t
** Dose factors from Table 1.1-10.
f Calculation The dose rate is calculated f rom Equations (3-5) and (3-28): k 0.72 Q DFB g tb = i 3 (erem} (pCi-sec uCi mrem-m PCi-yr I
- yr 3 8ec
, uci4 and where the stack release rate is determined from:
. AE : (3-25)
.ST Qg g
- F Si .SJAE Sg Si (cpm) guCi/ce) guci) epm (c1 see
)
sec
.SJAE However, for a time (t) after shutdown, the ratio of Qg to the sum release rate of a11' noble gases can be replaced in Equation (3-28) by the relative fraction [f (t)] g of each noble gas available in the system; therefore, Equation (3-28) can be written:
, g(, '. . 'Y 5 Approved By: R m (_-
Pevision J Date A-7 5103R
.ST Qg = f g(t) .M F Therefore, using the above data for a time period 32 days af ter shutdown, the j dose rate equation can also be written as:
1 l I ktb = 0.72 M S8 i 'i( ' i
= 0.72 80,000 1/1E+08 7.55 E+07 [(0.152)(1.61 E-05) +
(0.070)(9.15 E-05) + (0.777)(2.94 E-04)] = Answer ktb = 10.3 mrem / year noble gas total body dose rates at 32 days after shutdown.
?
.a i (Ir I Revision d Datb- Approved By: LN Mf . 7
'J A-8 5103R
) EXAMPLE CALCULATION NO. 4 IYlle Skin Dose Rate From Noble Cases References l a) ODCM Section 3.5 (Method I). b) Technical Specification 3.8.E.1.a. - Problem Calculate the off-site skin dose rate resulting from the release of noble gases from the plant stack during power operations. I Pisnt Data a) Maximum plant stack gas monitor (I or II) Count rate during period of interest (M): 80,000 cpm b) Stack flow rate during release (F): 7.55 E+07 cc/sec (160,000 cfm x 4.72 E+02 **g*** e
= )
c) Plant stack monitor detector counting i E+08 cpm per efficiency (Sg): uCi/cc d) The last measured release rate mix of
.SJAE noble gas from the SJAE (Q g ),
and corresponding dose factor DF from Table 1.1-10.
~
Revision U Date Approved Byr i, A-9 5103R -
1 i n
.SJAE DF{
S erem-se: i 1 (uCi/seel uCi/ year Xe-138 5.15 E+03 9.97 E-08 Kr-87 2.37 E+02 1.11 E-02 Kr-88 1.29 E+02 1.37 E-02 Xe-135 1.85 E+02 2.69 E-03 Calculation 1 The skin dose rate is calculated from Equations (3-7) and (3-28): .
* .ST (3-7) 97, skin , g i i gerem) guy ) (mrem-see) yr see uCi-yr i
and where the stack release rate is determined from:
.SJAE (3-2S) c
.ST Qg g Si "
.SJAE E Si (cpm) g guci/ce) (E) cpm see
(" )
.SJAE First,determinethesum([)ofallQ g and the fraction that each noble i
gas i represents in the total gas mix.
.SJAE Qg = (5.15 E+03) + (2.37 E+02) + (1.29 E+02) + (1.85 E+02)
= 5.70 E+03 uCi/sec.
and the relative fraction of each noble gas: i C r% _ _ > Ruvision d Da:e_DEC 2 2 1986 Approved By: p A-10 5103R
1 i f.
* *b ^
Relative Fraction g Qg /5.70 E+03 ,, 7,t,1 Xe-138 5.15 E+03/5.70 E+03 = 0.904 Kr-87 2.37 E+02/5.70 E+03 = 0.042 Kr-88 1.29 E+02/5.70 E+03 = 0.023 Xe-135 1.85 E+02/5.70 E+03 = 0.032 Next, the stack release rate of each noble gas i from Equation (3-28) can te substituted into Equation (3-5) to give the skin dose rate as: 1 skin
- Sg i i i -
= 80,000 1/1E+08 7.55 E+07 [(0.904)(9.97 E-03) +
(0.042)(1.11 E-02) + (0.023)(1.37 E-02) + (0.032)(2.69 E-03)) I
= 6.04 E+04 (9.01 E-03 + 4.66 E-04 + 3.15 E-04 + 8.61 E-05)
= 6.04 E+04 (1.03 E-02)
Answer k, g = E25 mrem / year noble gas skin dose rate. e
. ., - e fr Revision h _ Date _' Approved By: k ? .s _ _
A-11 d
$103R
? EXAMPLE CALCUIATION NO. 5 T_ype / Skin Dose Rate From Noble Gases s References a) ODCM Section 3.5 (Method I). b) Technical Specification 3.8.E.1.a. Problem Calculate the off-site skin dose rate resulting from the release of noble gases from the plant stack six days after plant shutdown.
)
Plant Data a) Maximum plant stack gas monitor (I or II) Count rate during period of interest (M): 120,000 cpm b) Stack flow rate during release (F): 7.55 E+07 cc/sec (160,000 cf m x 4.72 E+02 **g[** = ) c) Plant stack monitor detector counting i E+08 cpm per efficiency (Sg): uCi/cc d) Since the plant is shut down for more than five days, Xe-133 may be used as the referenced radionuclide in place
.SJAE of the ratio of Q g to the sum 4SJAE of all Qg in Equation (3-28). r ~
Revisionh,_Date _ Approved By: M % __ 1
~
A-12 5103R
1 DF{
***-C i_ fi (t >5 days) (*Ci-year) u Xe-133 1. 4.75 E-04 I
Calculation The skin dose rate is calculated from Equations (3-7) and (3-28):
.ST (3-7)
R S akin " i i DF{ , (arem) gy)u (mrem-see) yr set uCi-yr and, the stack release rate is determined from:
.SJAE 3-28)
.ST Qg 7 01 "
.SJAE (
i However, for times greater than five days after shutdown, Xe-133 may be usec as the referenced radionuclide alone. Therefore, in Equation (3-28) the ratic
.SJAE .SJAE of Q g to the sum of all Q g can be replaced by a value of 1 which indicates that all the contribution to the release is from Xe-133.
Therefore:
.ST QXe-133 = 1.0 x 120,000 x 1/1E+08 x 7.55 E+07 (cpm) (cc/sec)
(uci/ce) cpm
.ST QXe-133 = 90,600 uN ,sec.
C is Revision 3 Date , Approved By: [_ R A-13 5103R
.ST Therefore, replacing this value of Q g into Equation (3-7) we find the skin dose rate as:
[ i skin = 90,600 x 4. 75 E-04 l mrem) (uy ) mrem-sec) ( yr sec uCi-yr Answer l kskin = 43.0 mrem / year. 1 k r
\
~ /
Revision d Dste t.pproved By:. s}'\ '^' - -
\
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A-14 5103R
EXAMPLE PROBLEM NO. 6 Typ.g Critical Organ Dose Rate From Iodine Tritium, and Particulates References a) CDCM Section 3.6 (Method I). b) Technical Specification 3.8.E.1.b. Problem l Calculate the critical organ dose rate due to measured effluent data taken from the plant stack for a seven-day sample collection period. I Plant Data a) Stack particulate analysis for the seven-day period of interest. DFG' (}
.STP Activity Q i
Imrem s e} i (uci/see) yr-uci Sr-89* 1.42 E-O'+* 3.48 E+01 Sr-90* 3.50 E-03* 1.34 E+03 Co-60 4.89 E-02 2.26 E+01 Co-137 3.90 E-03 8.45 E+01 Zr-65 1.01 E-02 3.55 E+00 Na-24** 2.76 E-03** -- Mn-54+ < 2. 8 7 E-06 + 1.45 E+00 (1) DFGieo dose rate factor for each radionuclide is taken from
~
Table 1.1-12.
, e --
Ravision 3 Deem 2. 3 N Approved By: k) . rby " J A-15 5103R
1 hotes
*For Sr-89/90, use the most recent available measurement from quarters
- composite analysis.
**Na-24 has a half life of less than 8-1/2 days, and therefore is not included in the dose analysis per requirements of Technical Specification 3.8.E.1.t even though it was detected. +Mn-54 is not included in the dose analysis since it was not detected as being present above the LLD.
b) Stack iodine (charcoal and particulate activities combined for the seven-day period of interest):
.STP DFG' Activity Q g f[
(,y,,r,-u C i i (uCi/sec) I-131 1.16 E-03 2.64 E+02 I-133* <6.35 E-05* 4.04 E+00 I-135** 7.21 E-03** 3.69 E-01 and H-3+ 3.17 E-02 5.36 E-03 Notes
*I-133 is not included in the dose analysis for this case since it was net detected is being present in the stack analysis. **I-135 is not included in the dose analysis because it has a half lif e less than 8-1/2 for particulates, and is not included as a required iodine in Technical Specification 3.8.E.1.b. + Tritium value based as latest available stack grab sample.
('y I ,-
. a . -o f
\1 Q Revisiva 3 d Approved By: 2) 7 .c' t Date -
A-16 5103R
i Calculation The dose rate is calculated from Equation (3-16):
.STP I
co " i { S i ico (3-16) arem) yr gy) u see gerem-sec) uCi-yr The dose rate factors (DFG'g,,) for each of the radionucHdes detected in the plant stack charcoal and particulate filter sample (plus tritium) is taker. from Table 1.1-12 of the ODCM. Therefore: k = (1.42 E-04)(3.48 E+01) + (3.50 E-03)(1.34 E+03) + (4.89 E-02) (2.26 E+01) + (3.90 E-03)(8.45 E+01) + (1.01 E-02)(3.55 E+00)
+ (1.16 E-03)(2.64 E+02) + (3.17 E-02)(5.36 E-03) =
Answer k,=6.47 c ares /yearcriticalorgandoseratefromiodine, tritium,and particulate. Revision 3 Date Approvej By: D e A-17 5103R
i r EXAMPLE PROBLEM NO. 7 IY.E1 Gamma Air Dose From Noble Gases References a) ODCM Section 3.7 (Method I). b) Technical Specification 3.8.F.1. Problem Calculate the maximum gama air dose resulting from noble gases released f rer the plant stack over a calendar month. l Plant Data Based on the daily off-gas analysis, the total activity released during the month of interest is: DF{* Activity Q mrad-m i I pci-yr i (Ci) Kr-88 3.55 E-01 1.52 E-02 Kr-85m 4.71 E40 1.23 E-03 Xe-138 2.75 E40 9.21 E-03 Xe-135 3.51 E+01 1.92 E-03 Xe-133 9.42 E41 3.53 E-04
- Gamma air do'se factors taken from Table 1.1-10.
& n
~
.. 1s. .n a m.
A - em,, J W K 1 c A-18 5103R
1 Calculation The maximum gama air dose of f-site is calculated f rom Equation (3-21): Y Y D,g, = 0.023 g Qg Dr g (3-21) 3 (mrad) goci-yr) (CL) gerad-m ) 3 PCi-yr Ci-m Therefore: Y D,1, = 0.023 [(3.55 E-01)(1.52 E-02) + (4.71 E+00)(1.23 E-03)
+ (2.75 E+00)(9.21 E-03) + (3.51 E+01)(1.92 E-03) +
(9.42 E+01)(3.52 E-04)]
= 0.023 (5.40 E-03 + 5.79 E-03 + 2.53 E-02 + 6.74 E-02 +
3.31 E-02) Answer Y D = 3.15 E-03 mrad gamma air dose during the month. air e Revision s Da:e CEC 2 2 1966 L{. ( Approvad By: [_f 77^'N _ V A-19 5103R
EXAMP*.E CALOULATION NO. 8 L Beta Air Dose From Noble Cases References a) ODCM Section 3.8 (Method I). b) Technical Speeification 3.8.F.1. Problem Calculate the maximum beta air dose resulting from the same noble gas releases given in Example Calculation No. 7. Plant Data From Example No. 7, the total activity determined to be released during the month is: DF
- Activity Q i mrad-m I pci-yr i (Ci)
Kr-88 3.55 E-01 2.93 E-03 Kr-85m 4.71 E40 1.97 E-03 Xe-138 2.75 E40 4.75 E-03 Xe-135 3.51 E41 2.46 E-03 Xe-133 9.42 E41 1.05 E-03
- Beta air dose factors taken from Table 1.1-10.
( .~ Revisian Cate Approved By: $ c, A-20 5103R
Calculation The maximum beta air dose off-site is calculated from Equation (3-23): D air
= 0.02 Qg DF g (3-23) i 3
(mrad) (pci-yr) (Ci) gerad-m ) 3 pCi-yr Ci-m Therefore:
/3 D
air
= 0.02 ((3.55 E-01)(2.93 E-03) + (4.71 E+00)(1.97 E-03)
+ (2.75 E+00)(4.75 E-03) + (3.51 E+01)(2.46 E-03) +
(9.42 E+01)(1.05 E-03)]
= 0.02 (1.04 E-03 + 9.28 E-03 + 1.31 E-02 + 8.63 E-02 +
9.89 E-02) Answer
/3 D = 4.17 E-03 mrad beta air dose during the month.
dr I Revision 3 Date Approved By: 6/ A-21 5103R
EXAMPLE PROBLEM NC. 9 T .E1 _Y Critical Organ Dose From Iodine Tritium, and Particulates References a) CDCM Section 3.9 (Method I). b) Technical Specification 3.8.G.I. Problem Calculate the critical organ dose due to the total activity recorded as being released from the plant stack during a calendar month. Plant Data a) From the combined stack analyses during the month, the following activit., released is: DFG g, (1) i i (Ci) (mrem Ci Sr-89* 5.42 E-04* 1.10 E+00 Sr-90* 1.10 E-02* 4.25 E+01 Co-60 2.30 E-01 7.15 E-01 Cs-137 1.15 E-02 2.68 E+00 Zn-65 2.60 E-02 1.13 E-01 Na-24** 7.11 E-03** -- Mn-54 <2.76 E-06+ 4.60 E-02 f Revision 3 DateEEC2 3 l9S6 Approved By: Dr '% A-22 5103R
Notes for Plant Data a) Above (1) Critical organ dose factor taken from Table 1.1-12. {
*For Sr-89/90, use the most recent available measurement from the quarterly composite analysis.
**Na-24 has a half life of less than 8-1/2 days, and therefore is not included in accordance with Technical Specification 3.8.G.I.
4 -54 is not included in the dose analysis since it was not detected as being present above the required LLD. b) Total iodine release for the month based on the combined charcoal and particulate filter samples taken during the month: OFG ico 91 i (Ci) (mrem Ci I-131 4.30 E-03 8.36 E+00 I-133 1.12 E-04* 1.28 E-01 I-135** 2.01 E-02** and H-3+ 0.15 1.70 E-04 Calculation The dose is calculated from Equation (3-25): D co " i Si ico (3-25) (arem) (Ci)- (arem/Ci) m - 25
..visio, a .te A,,rovee y, d4R s
A-23 5103R
Notes for Plant Data b) Aboy
*In thi4 case, I-133 was found in one of the weekly stack samples to te present, and therefore based on that value is included in the dese analysis. **I-135 is not included in the dose analysis because it has a half life less than 8-1/2 days for particulates and is not included as a required iodine in Technical Specification 3.8.B.1. + Tritium value based on the monthly stack grab sample.
The dose factor (DFG g ) for each radionuclide detected in the plant stack charcoal and particulate filter sample (plus tritium) is taken from Table 1.1-12 of the ODCM. . Therefore: D , = (5.42 E-04)(1.10 E400) + (1.10 E-02)(4.25 E+01) + (2.30 E-01)(7.15 E-01) + (1.15 E-02)(2.68 E+00) + (2.60 E-02)(1.13 E-01) + (4.30 E-03)(8.36 E+00) + (1.12 E-04)(1.28 E-01) + (0.15)(1.70 E-04) = Answer D = 0.70 mrem maximum organ dose for the month.
/
Revision 3 Date ___ Approved By: g _ A-24 5103R
EXAMPLE CALCULATION NO.10 l Irms l Releases Limited to 2X MPC Average Over an Hour io.0ff-Site Air Concentrations References I t a) 10CFR50.72 b) 10CFR50.73 Problem Find the minimum stack gas monitor response which would require an assessment to determine if a four-hour notification to NRC is required per 10CFR50.72. Assumptions a) Maximum expected stack flow rate (F) 8.73 E+07 cc/sec C* *** r(185,000 cfm x 4.72 E+02 ,g = ')
;i b) Plant stack monitor detector 1 E+08 counting efficiency (Sg) cpm per uCi/cc c) Maximum off-site ground level 6.3 E-07 dispersion parameter (X/Q undepleted) sec/m
')/
/' (from ODCM Table 3.10-1)
- U' 44 d) Most restrictive MPC value for ncble 2 E-08 gases (10CFR20, Appendix B. Table II, uCi/sec ,
Column 1) for Kr-87 r e- > /- Revision O Date Apprevco Ey: b -- - A-25 5103R
Calculation (Part I) The setpoint R r e s ac m t. tor w ch would correspond to an spt instantaneous off-site air concentration of 2 x MPC for the most restrictive noble gas can be calculated by: Sg i E+06 R,pg = 2 MFC f (Cpe) (gC,1) com see cc {uCi/cc) (,3 -) (E)
,3 (cc )
=
2 x (2 E-08)(1E-08)(1/6.3 E-07)(1E +06)(1/8.73 E+07) R,,g = 72,700 cpm setpoint alarm value. ! Now if the monitor alarmed at a setpoint of 72,700 cpm, an additional evaluation would be necessary to determine if the 2 x MPC limit for the actual radionuclide gas six would be exceeded when averaged over one hour. As an example, assume the following: Plant Data a) Recorded stack flow rate during release (F) 7.55 E+07 cc/sec (160,000 cfm x 4.72 E+02 **g# ,
= )
b) Duration of release spike. 50 minutes c) Maximum recorded stack monitor 210,000 cpm count rate. l
^
. Revision 3 DateG w *r-n , o jggg Approved By: /
e
.c %
\j ~
A-26 5103R
d) Time trace of stack monitor response during release. F i 210,000 - l cpm \
\
\
1,000 -- Background t=0 1 50 *1 hr Total counts = area under trace Approximately 210,000 cpm x 50 minutes x 1/2 Approximately 5,250,000 counts.
. - Total counts averaged over one hour =
6 nut
= 87.500 cpm Since the average count rate over one hour still exceeds the instantaneous alarm setting of 72,700 cym, we must now look at the individual radionuelide concentrations off-site and see if the sum cf the ratios of each nuclide concentrations over its MPC value is less than 2.0 in order to determine if the 2 x MFC notification rule had been reached.
Therefore, the mix fractions (f )g that each noble gas represents of the total release must be determined from a representative off-gas or stack release sample. e) Assume the following fractions were determined: ('~h* !, z 7~ Revision 3 Date - Approved By: 1 -
\J" ~
A-27 5103R _ __ ..~. _ ___ . _ . _ _ _ _ . . _ . . . , _ . _ . _ _ _ _ J: T '1 _ _ . . ._ _.- - . _ . _ ..
S i MFC, guci) g i cc- i (10CFR20 Appendix B) Xe-133 3.50 E-04 0.40 3 E-07 uCi/cc Xe-133m 2.98 E-04 0.34 3 E-07 Xe-135 1.23 E-04 0.14 1 E-07 Kr-88 1.04 E-04 0.12 2 E-08 Total 6.75 E-04 Calculation (Part II) . The air concentration off-site of each noble gas i can be found from:
-6 C g= f g M F X/Q 10 3
(u.C_i ) (cpm) guci/ce) gee ) (m) 3 (* ) cc cpm sec ,3 -
=f g (87,500)(1/1E+08)(7.55E+07)(6.3E-07)(10' )
Cg=fg (4.16 E-08) Therefore, using the fg from the table above we find: Cg l 1 (uci/ce) Xe-133 1.66 E-08 Xe-133m 1.42 E-08 Xe-135 5.83 E-09 l Kr-88 4.99 E-09 l nevision 3 LatpEC 2 i N App;oved By: I s1 C x__ d A-28 5103R
Finally, tha sum cf th2 ratio of egncentrctions to MPC can ba fcund: C C C Cg 1 2 3 ? MPC g MPC MPC
- MPC g 2 3 or 1.66 E-08
- 1.42 E-08 5.82 E-09 4.99 E-09~
3 E-07 3 E-07 1 E-07 2 E-08 0.055 + 0.047 + 0.058 + 0.250 = 0.41 <2 Answers Since the sum of the ratios of the time averaged individual radionuclides air concentrations over their MPC limits is less than 2, there is no reporting requirement under 10CFR50.72 or 10CFR50.73. e Revision 3 Date DEU Approved By: Gt - A-29 5103h l
,, - mum e
APPENDIX I l RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement: Technical Specification 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee. Response: There were no licensee initiated majcr changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting period. i I-l 4436R _ _ - _ _ _ _ _ _ ______ _ _ _ _ _ _ )}}