ML20249C374
| ML20249C374 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1997 |
| From: | Sen G VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-98-85, NUDOCS 9806290144 | |
| Download: ML20249C374 (129) | |
Text
{{#Wiki_filter:_ _ _ - _ _ _ _ _ - - - - _ _ _ __ ____ _ __ _ _______ ___-__ __ __ _ . _ _ _ _ _ _ _ _ . - - _ - _ _ - _ _ _ _ _ _ _ _ _ . i VERMONT YANKEE ! y NUCLEAR POWER CORPORATION 185 Old Ferry Road, Brattleboro, VT 05301-7002 (802) 257-5271 l June 24,1998 BVY 98-85 United States Nuclear Regulatory Conunission ATTN: Document Control Desk l Wasldngton, DC 20555
Subject:
Vermont Yankee Nuclear Power Corporation License No. DPR-28 (Docket No. 50-271) Vermont Yankee Sunnlemental Emuent and Waste Disposal Annual Report for 1997 The enclosed report is provided pursuant to Vermont Yankee Te,chnical Specification 6.7.C.1 and 10CFR50.36a(a)(2). We trust that the information provided is acceptable; however, should you have any questions, please contact this office. Sincerely, i VERMONT YANKEE NUCLEAR POWER CORPORATION Gautam Sen Licensing Manager l 'l Cc: USNRC Region 1 Administrator i USNRC Resident Inspector- VYNPS USNRC Project Manager-VYNPS VT Department of Public Senice f
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l .,.m juvOU 9906290144 971231' PDR ADOCK 05000271 R PDR
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aq. i I SUPPLEMENTAL EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR 1997 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN l Vermont Yankee Nuclear Power Station I WFW13tLMOBl.108
ERRATA
- In past Vermont Yankee Effluent and Waste Disposal Annual Report (s), the following corrections should be made:
None. Holn: Table 3, " Solid Waste and Irradiated Fuel Shipments," has been expanded from that presented in the 1997 Effluent and Waste Disposal Report submitted in March. Additional information on the breakdown of shipments between the plant and off-site processors has been included. 1. l mmmanos -ii-b
TABIE OF CONTENTS Eage E RRATA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii
- 1.0 INTRODUCTI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 2.0 METEOROLOGICAL DATA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.0 DOS E AS S ES S MENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.1 Doses From Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.2 Doses From Noble Gases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 3.5 Whole-Body Doses in Unrestricted Areas From Direct Radiation . . . . . . . . . . . . . . . .
Doses From On-Site Disposal of Septic Waste and Cooling Tower Silt . . . . . . . . . . . . 4 5
)
)
3.6 On-Site Recreational Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 i REFEREN CES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 APPENDIX A- SUPPLEMENTAL INFORMATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 APPENDIX B - . LIQUID HOLDUP TANKS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B- 1 . APPENDIX C - RADIOACTIVE LIQUID EFFLUENT MONITORING IN STRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C- 1 l APPENDIX D - RADIOACTIVE GASEOUS EFFLUENT MONrrORING INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D- 1 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . E-1 ! ' APPENDIX F - LAND US E CEN S US . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F- 1 APPENDIX G - PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-1 1 l APPENDIX H - OFF-SITE DOSE CALCULATION MANUAL . . . . . . . . . . . . . . . . . . . . . . H-1 APPENDIX 1 - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT S YSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 1 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC WASTE . . . . . . . . . . . . . . . . . . . . . . . . . . J-1 i l ermaumms -lii-
f i i IST OF TABIFR i Number Iitic Eage
.IA First and Second Quarters,1997 Gaseous Effluents - Summation of All Releases 7 1A Third and Fourth Quarters,1997 i Gaseous Effluents - Summation of All Releases 8 IB First and Second Quarters,1997.
Gaseous Effluents - Elevated Releases 9 IB Third and Fourth Quarters,1997' Gaseous Effluents - Elevated Releases 10 IC First and Second Quarters,1997 Gaseous Effluents - Ground Level Releases 11 1C Third and Fourth Quarters,1997 Gaseous Effluents - Ground Level Releases 12 ID Gaseous Effluents - Nonroutine Releases 13 2A Liquid Effluents - Summation of All Releases 14 2B Liquid Effluents - Nonroutine Releases 15 3 First and Second Quarters,1997 Solid Waste and Irradiated Fuel Shipments 16 3 Third and Fourth Quarters,1997 Solid Waste and Irradiated Fuel Shipments 18 4A Maximum Off-Site Doses / Dose Commitments to Members of the Public from Liquid and Gaseous Effluents for 1997 (10CFR50, Appendix I) 20 4B Maximum Annual Dose Commitments from Direct External Radiation, Plus Liquid and Gaseous Effluents for 1997W (40CFR190) 21 4C- Receptor Locations for Vermont Yankee 22 4D. Usage Factors for Various Gaseous Pathways at Vermont Yankee 23 4E Enwonmental Parameters for Gaseous Effluents at Vermont Yankee 24 mauwanos -iv-
I_TST OF TABI FR (Continued) Number lille Eagc SA to SH Annual Summary of Upper level Joint Frequency Distribution 26-33 6A to 6H Annual Summary of Lower Level Joint Frequency Distribution 34-41 I WNat2NIALM *v*
SUPPLEMENTAL EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR 1997 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN
1.0 INTRODUCTION
i Tables I through 3 list the recorded radioactive liquid and gaseous effluents and solid waste for l the year, with data summarized on a quarterly basis for both liquids and gases. Table 4A sununarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 1997 in response to the ALARA objectives of 10CFR50, Appendix 1. Also included on Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 1997. Radioactive effluents reported in the Annual Effluent Report covering the year were used to determine the resulting doses for 1997. As required by Technical Specification 6.7.C.1 dose commitments resulting from the release of r:dioactive materials in liquids and gases were estimated in accordance with the " Vermont Yankee Nuclear Power Station Off-Site Dose Calculation Manual" (ODCM). These dose estimates were made using a " Method II" analysis as described in the ODCM. A " Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 3) and actual measured meteorological data recorded during the reporting period. As required by Technical Specification 6.7.C.I.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. For this reporting period the only recreational cctivity permitted was employee access to a boat launching ramp adjacent to the intake structure during the summer. 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 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. However, Table 4B does provide the combination of doses and dose c:mmitments from plant effluents and direct radiation sources for the limiting member of the public cff-site as a demonstration of compliance with the dose standards of 40CFR190. All calculated dose estimates for this reporting period aie well below the dose criteria of 10CFR Part 50, Appendix I, and 40CFR190. Appendices B through H indicate the status of reportable items per the requirements of Technical Specifications 6.7.C.1 and 6.14.A. mamanos _ _ _ - _
7 / 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 l
each quarter using a straight-line airflow model. All dispersion factors have been calculated employmg l . 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 for all stack (elevated) releases. Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate. Table 4C list the distances from the plant stack to the nearest site boundary, resident, and milk tuimalin each of the 16 principle compass directions as determined during the 1997 land use census. These locations were used in the calculation of atmospheric dispersion factors. i mamanos - - _ _ _ _
3.0 DOSE ASSESSMENT 3.1 Doses From Liquid Effluents Technical Specification 3.8.B.1 limits total body (1.5 mrem per quarter, and 3 mrem per year) and Ergan doses (5 mrem per quarter, and 10 mrem per year) from liquid effluents to a member of the public ts those specified in 10CFR Part 50, Appendix I. By implementing the requirements of 10CFR Part 50, Appendix I, Technical Specification 3.8.B.1 assures that the release of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." For periods in which liquid waste discharges actually occur, the exposure pathways that could exist are fish, direct exposure from river shoreline sedimentation, milk and meat via animal ingestion of the Connecticut River water, and meat, milk and vegetable pathways via crop irrigation with water withdrawn from the Connecticut River. The drinking water and aquatic invertebrate pathways do not exist downriver of the Vermont plant at Vernon. There were no recorded liquid radwaste discharges during the report period, and therefore, no dose impact. 3.2 Doses From Noble Gases Technical Specification 3.8.F.1 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10CFR Part 50, Appendix I. By implementing the requirements of 10CFR 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, nearest resident in each of the sixteen principal compass directions, the point of highest off-site ground level air concentration of radioactive materials, and for each of the milk animallocations loccted within five miles of the plant. 3.3 Doses From Iodine-131. Iodine-133. 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 particulate form with half-lives greater than 8 days (hereafter called iodines and particulate) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10CFR Part 50, Appendix I (7.5 mrem per quarter, and 15 mrem per year). By implementing the requirements of 10CFR Part 50, Appendix I, Technical Specification 3.8.G.1 assures that the releases of iodines and particulate in gaseous effluents will be kept "as low as is reasonably achievable." Exposure pathways that could exist as a result of the release ofiodines and particulate 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 ermucum resident in each of the sixteen principal compass directions, as well as all milk animallocations 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 Specification 3.9.D.1 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, l the meat pathway was assumed to exist at each milk cow location since this data category is not part of l the annualland use census. Doses were also calculated at the point of maximum ground level air l concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground planc 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 iodira deposited from gaseous effluent is in elemental form (12 ) and is available for uptake (see p. 26, Reference 3). During the first and fourth quarters, the milk animals are assumed to receive only stored feed. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D. Table 4E provides other dose model parameter assumptions used in the dose assessments. The resultant organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bone, liver, kidney, thyroid, lung and skin for adults, teenagers, children and infants. The maximum estimated quarterly and annual organ doses to any age group due to iodines and particulate at any of the off-site receptor locations are reported in Table 4A. These estimated organ doses are well below the 10CFR Part 50, Appendix I dose criteria of Technical Specification 3.8.G.I. 3.4 Whole-Bodv Doses in Unrestricted Areas From Direct Radiation The major source of dose, consisting of direct radiation and skyshine, 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 4) for radiation fields resulting from N-16 photons. The other sources of dose, including direct radiation and skyshine, to the site boundary are from low level radioactive waste stored in the north warehouse, the low level waste storage pad facility, and old turbine rotors and casings in the turbine storage facility. The annual dose is based on dose rate mmuna ..
measurements in these three storage facilities and determined at the'same most restrictive site boundary dose location as that for N-16 shine from the Turbine Building. The estimated direct radiation dose from all major sources combined for the most limiting site
. boundary location is listed on Table 4A . These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.
Table 4B list the combination of direct radiation and effluent release. doses at the limiting nearest .
- residence for the purpose of demonstrating compliance with the dose standards contained in 40CFR190.
For direct radiation, no credit for actual occupancy time is taken (i.e., occupancy is equal to 100%). 3.5 ' Doses From On-Site Disposal of Sentic Waste and Cooling Tower Silt Off-Site Dose Calculational Manual, Appendices B and F, requires that all applications of septage
. and the cooling tower silt within the approved designated disposal areas be limited to ensure the dose to a maximally-exposed individual be maintained at less than 1 mrem / year to the whole body.and any organ,-
and the dose to the inadvertent intruder be maintained at less than 5 mrem / year. The projected dose from cn-site disposals of septic waste and the cooling tower silt is given in Appendix J. 3.6 On-Site Recreational Activities During the summer of 1997, limited access to a boat launching ramp located on-site just north of
. the intake structure was permitted for employees, their families and guest. An assessment of the second and third quarter fence line Thermoluminescent Dosimeters (TLD's) situated along that section of the river next to the boat ramp were used to estimate the direct radiation exposure rate for this recreational activity. The shoreline recreational usage factor of 67 hours / year (Regulatory Guide 1.109, Table E-5) was applied to the net TLD exposure rate value to generate a dose estimate for use of the boat ramp area.
The resulting individual dose is estimated to be 0.24 mrem. This is considered conservative since most i of the ramp area is shielded from plant facilities by the river embankment and below the plant fence line where the TLD measurements were taken. There was no significant gaseous contribution to dose since the close proximity of the ramp area to the 94 meter tall phr.t stack kept gaseous effluents well over head. ! l I L i wn m uw e nos - _ _ _ _ _ - _ _ _ _ _ . - _ - _ _ _ _ __ __ _ _ _ _ - _ _ -
REFERENC'ES
- 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.
4
- 2. Meteorology and Atomic Energy,1968, Section 5-3.2.2, " Cloud Depletion", pg. 204. U. S.
Atomic Energy Commission, July 1968. 4
- 3. 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.
- 4. 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.
4 i i i mmwmms ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - . .- _ _ _ _ _ ____.
TARIE1A Vermont Yankee Effluent and Waste Disnosal Annual Renort l First and Second Quarters.1997 l
, Gaseous EfY1uents - Summation of All Relenses Quarter Quarter Est. Total Unit 1 2 Error. %
A. Fission and Activation Gases I. Total release Ci 0.00E+00 0.00E+00 t2.30E+01
- 2. Average release rate for period pCi/sec 0.00E+00 0.00E+00
- 3. Percent of Tech. Spec. limit (1) % 0.00E+00 0.00E+00 B. lodines
- 1. TotalIodine-131 Ci 6.68E-05 5.77E-05 1.80E+01 t 2. Average release rate for period pCi/sec 8.59E-06 7.34E-06
- 3. Percent of Tech. Spec. limit (2) % 1.47E-02 4.53E-02 C. Particulate t
- 1. - Particulate with T-1/2 > 8 days Ci 3.08E-05 1.04E-04 tl .80E+01
- 2. Average release rate for period pCi/sec 3.96E-06 1.32E-05
- 3. Percent of Tech. Spec. limit (3) % (3) (3)
- 4. Gross alpha radioactivity Ci- 2.48E-06 3.67E-06 D. Tritium
- 1. Total release Ci 4.18E+00 3.42E+00 ~ 1.80E+01
- 2. ' Average release rate for period pCi/sec 5.38E-01 4.35E-01
' 3. Percent of Tech. Spec. limit % (3) (3)
-(1)- Technical Specification 3.8.F.1.a for gamma air dose.
.(2) Technical Specification 3.8.G.1 for dose from I-131, I-133, Tritium, and radionuclides in y particulate form.
~ Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulate are (3) included with I-131 above in Part B.
.c e tw mms- w_ _ - - _ _ _ - - _ = _ . - - __-
TABI E 1 A (Continued) Vermont Yankee Effluent and Waste Disnosal Anriunt Rgpo,gi Third and Fourth Ouarters.1997 Gaseous Effluents - Summation of All Relences Quarter Quarter Est. Total Unit 3 4 Error. % A. Fission and Activation Gases
- 1. Total release - Ci 0.00E+00 3.44E+00 2.30E+01
- 2. Average release rate for period pCi/sec 0.00E+00 4.33E-01 1 3. Percent of Tech. Spec. limit (1) % 0.00E+00 1.22E-03 B.' lodines
- 1. Totallodine-131 Ci 1.6] E-04 1.09E-04 21.80E+01
- 2. Average release rate for period pCi/sec 2.03E-05 1.37E-05
- 3. Percent of Tech. Spec, limit (2) % 1.33E-01 2.13E-02
- j. C. Particulate 1.- Particulate with T-1/2 > 8 days Ci- 6.78E-04 6.41 E-05 1.80E+01
- 2. Average release rate for period - pCi/see - 8.53E-05 8.06E-06 3.~ Percent of Tech. Spec. limit % (3) (3)
- 4. Gross alpha radioactivity '
Ci 5.51E-06 4.02E-06 D. Tritium f
- 1. Total release Ci 4.36E+00 4.14E+00 t1.50E+01
( 2. Average release rate for period pCi/sec 5.49E-01 5.21E-01
- 3. Percent of Tech. Spec. limit % (3) (3) t (1)- Technical Specification 3.8.F.1.a for gamma air dose.
.. (2) ' Technical Specification 3.8.G.1 for dose from I-131, I-133, Tritium, and radionuclides in
. particulate fonn.
l (3)-. Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulate are included with I-131 above in Part B.
%.ig . . _ _ . _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ __ _ ______ _ _ _
TABLEIB yermont Yankee EfY1uent and Waste Dienosal Annunt Renort First and Second Ouarters.1997 Gaseous Effluents Flevated Relences Continuous Mode Batch Mode (l) Quarter Quarter Quarter Nuclides Released Unit 1 2 1 2
- 1. Fission Gases Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Totalfor Period Ci 0.00E+00 0.00900 0.00E+00 0.00E+00
- 2. Iodines Iodine-131 Ci 6.68E-05 5.77E-05 lodine-133 Ci 1.86E-04 9.57E-05 Iodine-135 Ci ND ND Totalfor Period Ci 2.53E-04 1.53E-04 0.00E+00 0.00E+00
- 3. Particulate Strontium-89 Ci 2.55E 1.13E-05 Strontium-90 Ci ND ND-Cesium-134 -- Ci ND ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium-51 Ci ND ND Cobalt-58 Ci ND ND
. Cobalt-60 Ci ND 1.37E-05 Cerium-141 ' Ci 4.74E-06 ND Zinc-65 Ci ND ND Total for Period Ci 3.02E-05 2.50E-05 0.00E+00 0.00E+00 (1)- There were no batch mode gaseous releases for this reporting period.
ND - Not detected at the plant stack, wnsintnuanos .
TABLE IB (Continued) Vermont Yankee Effluent and Waste Disnosal Annual Renort Third and Fourth Ouarters.1997 Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode (l) Quarter Quarter Quarter Nuclides Released Unit 3 4 3 4
- 1. Fission Gases Krypton-85 Ci ND ND Krypton-85m Ci ND 3.55E-02 Krypton-87 Ci ND 4.08E-02 Krypton-88 Ci ND ND Xenon-133 Ci ND 2.57E+00 Xenon-135 Ci ND 6.98E-01 Xenon-135m Ci ND 9.23E-02 Xenon-138 Ci ND ND Unidentified Ci ND ND Totalfor Period Ci 0.00E+00 ? '1E+00 0.00E+00 0.00E+00
- 2. Iodines Iodine-131 Ci 1.61E-04 1.09E-04 lodine-133 Ci 5.86E-04 3.04E-04 Iodine-135 Ci ND ND Total for Period Ci 7.47E-04 4.13E-04 0.00E+00 0.00E+00
- 3. Particulate Strontium-89 Ci ND 1.43E-05 Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci 3.12E-05 ND Barium-Lanthanum-140 Ci ND ND Manganese 54 Ci ND ND Chromium-51 Ci 3.80E-04 ND Cobalt-58 Ci 1.44E-05 ND Cobalt-60 Ci 1.76E-04 4.98E-05 Cerium-141 Ci ND ND Zine-65 Ci 7.64E-05 ND f Total for Period Ci 6.78E-04 6.41 E-05 0.00E+00 0.00E+00 i
(1) ' - Ihere were no batch mode gaseous releases for this reporting period. ND- Not detected at the plant stack. cmsawumms 2
i 1-TABLE IC Verrnont Yankee Effluent and Waste Disnosal Annual Reoort l First and Second Ouarters.1997 ' Gaseous Effluents - Ground Izvel Releases Continuous Mode Batch Mode (l) Quarter Quarter Quarter Nuclides Released Unit 1(1) 2(2),(3) 1(2),(3) 2(1) ! 1. Fission Gases 1 Krypton-85 Ci j Krypton-85m Ci Krypton-87 Ci { Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulate Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci 3.39E-07 ND Cesium-137 Ci 3.72E-05 3.90E-08 Barium-Lanthanum-140 Ci ND ND 3 Manganese-54 Ci 1.54E-06 2.34E-08 Chromium-51 Ci 3.25E-08 1.47E-08 Cobalt-58 Ci 2.09E-08 9.49E-09 Cobalt-60 Ci 8.42E-06 9.74E-08 Cerium-141 Ci ND ND Zinc-65 Ci 2.09E-06 5.81E-08 Iron-55 C1 2.93E-05 3.57E-07 Total for Period Ci 7.89E-05 5.99E-07 0.00E+00 (1) Here were no ground level gaseous releases of this type for the quarter.
(2) ne North Warehouse stack was used as a ground level release point for burning of waste oil. l l (3) Burning of waste oil was treated as six batch releases for the first quarter and as a continuous release for the second l quarter. i ND - Not detected in the waste oil sample. l I eu num mtos 1
TABIF1C (Continued) Vermont Yankee Effluent and Waste Disnosal Annual Renort ~ Third and Fourth Ouarters.1997 ~ Gaseous Effluents - Ground 12 vel Relencec Continuous Mode Batch Mode (l) Quarter Quarter Quarter Nuclides Released Unit 3(1) 4(1) 3(1) 4(1)
- 1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci
. Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Totalfor Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulate Strontium-89 Ci Strontium-90 Ci
~ Cesium-134 - Ci Cesium-137 Ci Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci
- Cobalt-58 Ci' Cobalt 60 Ci Cerium-141 ' Ci Zinc-65 Ci Iron-55 CI Total for Period .
Ci 0.00E400 0.00E+00 0.00E+00 0.00E+00
- (1). 'Ihere were no ground level gaseous releases for this reporting period.
ND- Not detected in the waste oil sample. manum.ms . .
TABIE 1D Vermont Yankee Effluent and Waste Disposal Annual Renort for 1997 f Gaseous Effluents - Nonroutine Releases There were no nonroutine or accidental gaseous releases during this reporting period. cumw nas ,
w TABI E 2 A Vermont Ynnkee Effluent and Waste Disnosal Annunt Renort for 1997 Liould Effluents - Summation of All Releases ) I l There were no liquid releases during this reporting period. mmmunas L J TABLE 2B Vermont Yankee Effluent and Waste Disnosal Annual Renort for 1997 Liould Effluents - Nonroutine Releases There were no nonroutine or accidentalliquid releases during this reporting period. 1 m m uotws . .
TABLE 3 Vermont Yankee Effluent and Waste Disnosal Annual Renort First and Second Ouarters.1997 ' Solid Waste and Irradiated Fuel Shinments A. Solid Waste Shipped Off-Site for Burial or Disposal (not irradiated fuel)
- 1. Type of Waste Ist and 2nd Est. Total Error, Shipped from VY for Burial or Disposal Unit Quarters 1997 %
- a. Spent resins, filter sludges, evaporator bottoms, etc. m3 1.31E+02 12.50E+01 Ci 2.59E+02
- b. Dry compressible waste, contaminated equipment, m3 None 2.50EW1 etc. Ci
- c. Irradiated components, control rods, etc. m3 None 2.50E+0!
Ci
!st and 2nd Est. Total Error, Shipped from Processor (s) for Burial or Disposal Unit Quarters 1997 % l
- a. Spent resins, filter sludges, evaporator bottoms, etc. m3 None 12.50E41 Ci
- b. Dry compressible waste, contaminated equipment, m3 1.29E+01 12.50E+01 etc. Ci 1.26E-01
- c. Irradiated components, control rods, etc. m3 None 2.50E+01 Ci
- 2. Estimate of Major Nuclide Composition (By Type of Waste)
- a. Spent resins, filter sludges, evaporator bottoms, etc. b. Dry compressible waste, contaminated equipment, etc.
Isotope Isotope i Zinc-65 % 2.10E401 Iron-55 % 7.40E+01 Cesium-137 % 1.30E+01 Zine-65 % 3.00E400 I Cobalt-60 % 1.80E+01 Cobalt-60 % 1.30E+01 ] I Cesium-134 % 1.00E+00 Manganese-54 % 5.00E+00 l Manganese-54 % 1.00E401 Cesium-137 % 2.00E+00 Iron-55 % 2.60E+01 Nickel-63 % l.00E+00 j l Nickel-63 % 8.00E400 Chromium-51 % 1.00E400 Cobalt-58 % 1.00E+00 cumwancs I
TABIR3 (Continued)
. 3. Disposition of Solid Waste Shipments (1st and 2nd Quarters)'
Destination No. of From VY From Mode of Processor Burialor Disposal Shipments Processor Transportation 26 X Truck CNS. Inc. Barnwell, SC 26 X Truck CNS,Inc. Barnwell, SC 1 X Truck CNS,Inc. Barnwell. SC
'B. Irradiated Fuel Shipments (Disposition): None.
Ce - Additional Data (1st and 2nd Quarters) SupplementalInformation Shipments from Shipments from VY Shipments from Processors VY to Processors for Burial or Disposal for Burial or Disposal Class of Solid Waste Shipped 1A 19A A (quantity of containers not 7B requird) Type of Containers Used 1 Strong Tight 26 Type A Strong Tight (quantity of cor. tainers not required) Solidification Acent or Absorbent None None None Nate: Sections A.1 and A.2 above do not include the data for the waste shipments from VY to the processors. The data for this waste will be included in the report that covers the year that this waste is shipped from the processor for burial or disposal. l f .' l j I l cem uo. l t
TABLE 3 (Continued) Vermont Yankee Effluent and Waste Disposal Annual Report Third and Fourth Ouarters.1997 Solid Waste and Irradiated Fuel Shinments A. Solid Waste Shipped Off-Site for Burial or Disposal (not irradiated fuel)
- 1. Type of Waste 3rd and 4th Est. Total Error, Shipped from VY for Burial or Disposal Unit Quarters 1997 %
- a. Spent resins, filter sludges, evaporator bottoms, etc. m3 2.42E+01 2.50E+01 Ci 5.86E+01
- b. Dry compressible waste, contaminated equipment, m3 1.20E+01 2.50E+01 etc. Ci 1.59E+00
- c. Irradiated components, control rods, etc. m3 7.00E+00 2.50E+01 Ci 3.72E+04 3rd and 4th Est. Total Error, Shipped from Processor (s) for Burial or Disposal Unit Quarters 1997 %
- a. Spent resins, filter sludges, evaporator bottoms, etc. m3 None 2.50E+01 Ci
- b. Dry compressible waste, contaminated equipment, m3 2.00E+00 2.50E+01 etc. Ci 1.42E-02
- c. Irradiated components, control rods, etc. m3 None 12.50E+01 Ci
- 2. Estimate of Major Nuclide Composition (By Type of Waste)
- c. Spent resins, filter sludges, b. Drycompressible waste, contaminated c. Irradiated components, control evaporator bottoms, etc. equipment, etc. rods, etc.
Isotope Isotope Iso: ope Zine-65 % 2.1OE+01 Iron-55 % 7.40E401 fron-55 % 4.1OE+01 Cesium-137 % 1.30E+01 Zinc-65 % 3.00E+00 Manganese-54 % 1.00E+00 Cobalt-60 % 1.80E+01 Cobalt-60 % 1.30E+01 Cobalt-60 % 5.50E+01 C:sium-134 % 1.00E+00 Manganese-54 % 5.00E+00 Nickel-63 % 3.00E+00
, Manganese-54 % l.00E+01 Cesium-137 % 2.00E+00 Iron-55 % 2.60E+01 Nickel-63 % l.00E+00 Nickel-63 % 8.00E+00 Chromium-51 % l.00E+00 Cobalt-58 % l.00E+00 mmmmws -__
TABLE 3 (Continued)
- 3. Disposition of Solid Waste Shipments (3rd and 4th Quarters)
Des:ination No. of From VY From Mode of Processor Burialor Shipments Processor Transportation Disposal 10 . X Truck CNS,Inc. Barnwell, SC 6 X- Truck CNS,Inc. Earnwell, SC 1 X Truck CNS,Inc. Barnwell, SC 1 X Truck GTS Duratek Oak Ridge,TN 2 X Truck Alaron, Wampum. PA Be Irradiated Fuel Shipments (Disposition): None. C. Additional Data (3rd and 4th Quarters) SupplementalInformation Shipments from Shipments from VY Shipments from Processors for VY to Processors for Burial or Disposal Burialor Disposal Class of Solid Waste Shipped . 4A 15A A (quantity of containers not l IB required) 2C Type of Containers Used 4 Strong Tight 6 Type A - Strong Tight (quantity of 3 Type B containers not required) - 9 Strong Tight Solidification Acent or Absorbent None None None Noic: Sections A.1 and A.2 above do not include the data for the waste shipments from VY ' to the processors. The data for this waste will be included in the report that covers the year that this waste is shipped from the processor for burial or disposal. l l l' omauwanos ! j
TABLE 4A Vermont Yankee Maximum Off-Site Doses / Dose Commitments to Members of the Public from Liquid and Gaseous Effluents for 1997 (10CFR50, AppendixI) Dose (mrem)W lst 2nd 3rd 4th Source Quarter Quarter Quarter Quaner Year
- _
Liquid Effluents Total Body Dose 0 0 0 0 0 Footnotes (1) (1) (1) (!) Organ Dose 0 0 0 0 0 Footnotes (1) (1) (1) (1) Airborne Effluents Organ Dose (Iodine + Part.) 1.1E-3 3.4E-3 1.0E-2 1.6E-3 1.6E-2 Footnotes (2) (3) (4) (5) Noble Gases
&ta Air (mrad) ND ND ND 1.3E-4 1.3E-4 Footnotes (6) (6) (6) (7)
Gamma Air (mrad) ND ND ND 6.1E-5 6.1E-5 Footnotes (6) (6) (6) (7) External Dose at Max. West -- -- -- -- 15.9 Fenceline (Direct Radiation) (a) The numbered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate. (1) There were no Liquid Releases (5) Child / Thyroid /NW,2600 meters (2) Child / Thyroid /WNW,2400 meters '(6) ND; no detected .tctivity (noble gases) (3) Infant / Thyroid /SSE,5240 meters (7) NW,2600 meters (4) Infant / Thyroid /NW,4260 meters (b) " Maximum" dose for the year is the sum of the maximum doses for each quarter. This results in a conservative yearly dose estimate, but still well within the limits of 10CFR 50, Appendix 1. wnin-nos _ _ - _ __
TABLE 4B Vermont Yankee Maximum Armual Dose Commitments from Direct External Radiation. Plus Liouid and Gaseous Effluents for 1997(*) (40CFR190) Pathway Total Body Maximum Organ Thyroid (mrem) (mrem) (mrem) Direct External (*) 6.3 6.3 6.3 Liquids 0 0 0 Gases 2.0E-4 6.4E-4 7.3E-5 Annual TotalN 6.3 6.3 6.3 (*) The location of the projected maximum individual doses from combined direct radiation plus liquid and gaseous effluents corresponds to residences beyond the west site boundary. (a) No occupancy ti,ne fraction (assumed 100%) or residential shielding credit is assumed which would reduce real doses below the calculated values. Expected direct extemal radiation doses would be reduced by about 54% with a realistic residential shielding credit and occupancy time (0.7 shielding factor from Regulatory Guide 1.109, and annual occupancy time 6760 hours). (b) Anneal dose limits contained in the EPA radiation protection standards (40CFR190) equal 25 mrem to the total body and any organ, except 75 mrem to the thyroid of a real member of the public. wanumms TABLE 4C Recentor Imcations for Verrnont Yankee l Nearest Milk l . Animal
- Within l Site Boundarf" Nearest Resident
- 10 km l Sector (Meters) (Meters) (Meters)
N 400 1470 -- l NNE 350 1400 4480 l (goats) l l NE 350 1250 3590 I (cows) i ENE 400 970 -- E 500 930 - l~ ESE 700 2830 - SE 750 1970 3600 (cows) SSE 850 2050 5240 (cows) S 385 450 2220 (cows) SSW 300 450 - SW 250 410 8203 (cows) WSW 250 450 9590 (goats) W 300 620 820 (cows) WNW 400 1060 6980 (cows) NW 550 2600 4260 (cows) NNW 550 2600 -- l
-(1)~ Vermont Yankee UFSAR Figure 2.2-5.
1(2) The location (s) given are based on data from the Vermont Yankee 1997 Land Use Census relative to the plant stack. Gardens are assumed to be present at all resident locations. mauwain i TABLE 4D l Usage Factors for Various Gaseous Pathways at Vermont Yankee (From Reference 1, Table E-Sm) i Veg. Leafy Veg. Milk Meat Inhalation Age Group (kg/yr) (kg/yr) (1/yr) (kg/yr) (m3/yr) l Adult 520 64 310 110 8,000 l l Teen 630 42 400 65 8,000 Child 520 26 330 41 3,700 Infant 0 0 330 0 1,400 l r (I) Regulatory Guide 1.109. l l wemuwonos u
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TABLE 5A VERMOfff YANKEE JAN 97
- DEC 97 METEORO1CGICAL DATA JOINT FREQUENCY DISTRIBUTION 397.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) e .64 WIND DIRECTION FROM SPEED N NNE NE DIE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL F.PH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 2 0 0 3 0 3 1 1 2 0 0 0 0 0 1 1 0 14 (1) 3.57 .00 .00 5.36 .00 5.36 1.79 1.79 3.57 .00 .00 .00 .00 .00 .00 (2) .02 .00 .00 1.79 1.79 25.00
.03 .00 .03 .01 .01 .02 .00 .00 .00 .00 .00 .01 .01 .00 .26 47 1 0 0 0 0 3 5 0 1 1 0 0 0 0 1 1 0 13 (1) 1.79 .00 .00 .00 .00 5.36 8.93 .00 1.79 1.79 .00 .00 .00 .00 1.79 1.79 .00 23.21 (2) .01 .00 .00 .00 .00 03 .06 .00 .01 .01 .00 .00 .00 .00 .01 .01 .00 .15 4-12 1 0 0 0 0 0 1 3 0 0 0 0 0 1 1 4 0 11 (1) 1.79 .00 .00 .00 .00 .00 1.79 5.36 .00 .00 .00 .00 .00 1.79 1.79 7.14 .00 19.64 (2) .01 .00 .00 .00 .00 .00 .01 .03 .00 .00 .00 .00 .00 .01 .01 .05 .00 .13 13-18 0 0 0 0 0 0 0 0 0 0 0 0 2 2 1 4 0 9 (18 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.57 3.57 1.79 1.14 .00 16.07 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .02 .01 .05 .00 .30 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 8 (1) .00 .00 .00 .00 .00 .00 .00 < .00 .00 .00 .00 .00 .00 1.79 12.50 .00 14.29 (2) .00 .00 .00 .00 .00 .00 .00 .6 .00 .00 .00 .00 .00 .00 .01 .08 .00 .09 CT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.79 .00 .00 .00 .00 1.79 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .01 ALL SPEEDS 4 0 0 3 0 6 7 4 3 1 0 0 3 3 5 17 0 56 (1) 7.14 .00 .00 5.36 .00 10.71 12.50 7.14 5.36 1.79 .00 .00 5.36 5.36 8.93 30.36 .00 100.00 (2) .05 .00 .00 .03 .00 .07 .08 .05 .03 .01 .00 .00 .03 .03 .06 .20 .00 .64 (1)sPERCENT OF ALL GOOD OBSERVATIONS FOR 7EIS PAGE (21sPERCENT OF ALL GOOD OBSERVATIONS FOR 'IMIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)
I l l TABLE 5.H l-( 1PERat3Pr YABECEE JAN 97 - DEC 97 NE'! TOPOLOGICAL DATA JOINT FREQUENCY DISTRIBUTION [ 297.0 FT wtam DATA STA31LITY C1 ASS S CLASS PREQUENCY (PERCENT) = .76 WINO DIRECTION rRon i SPEED N BBIE NE ENE E ESE SE SSE S SSW SW WSW. W tem - NW NNW VRBL 10TAL MPH CALM 01 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ( (1) ' .00 .00 .00 .00 .00 .00- .00 .00 . .00 .00 .00 ,00 .00 .00 .00 .00 .00 .00 (23 .00 .00 .00 .00 .00 .00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
'c-3 0 0 0 '1 0 0 0 0- .0 0 0 0 0 0 0 0 0 1 (1) .00 .00 - .00 1.52 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.52 (2) .00 - .00 .00 .01 .00 .00 .00 .00 .00 s.00 .00 .00 .00 .00 .00 .00 .00' .01 I' 7 0. 0 0 1 2 0 2 2 1 0 0 0 0 0 0 2 0 10
- j. (1) . 00 .00 .00 1.52 3.03 .00 3.03' 3.03 1.52 -
.00 . .00 .00 .00 .00 .00 3.03 .00 15.15
'(2) .00 - .00 .00 .01 .02 .00 .02 .02 .01 .00 .00 .00 .00 .00 .00 .02 .00 ' .11
'S-12 2 0 0 1 0 0 1 3 0 0 0- 0 0 0 0 9 0 16 (1) 3.03 .00 .00 1.52 .00 .00 1.52 4.55 .00 .00 .00 .00 .00 .00 .00 13.64 .00 24.24 l (2) .02 .00 .00 .01 .00 .00 .01 .03 .00 .00 .00 .00 .00 00 .00 .10 .00 - .18 i
13-18 1 > 0 0 0 0 0 0 0 2 0 0 0 1 1 1 15 0 21 I (1) 1.52 .00 .00- .00 .00 .00 .00 .00 3.03 .00 .00 .00 1.52 1.52 1.52 22.13 .00 31.82
' (2) .01 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .00 .01 .01 .01 .17 .00 .24.
19-24 1.52 1 0 0 0. 1 0 0 '0 0 0 0 0 1 2 2 9 0 16 i (ll- 's0 .00 .00 1.52 .00 ,00 .00 .00 .00 .00 .00 1.52 3.03 3.03 13.64 .00 24.24 (2) . .01 .00 .00 .00 .01 .00 .00 .00 .00- .00 .00 .00 . 01 ,02 .02 .10 .00 .38
- M 24 0 0 0 0 0- 0 0 0 0 0 0 0 0 0 0 2 0 2 l (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,00 .00 .00 .00 .00 3.03 .00 3.03 (2) .00 .00- .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 00 .02 3
q P ALL SPEEDS- 4 0 0 3 3 0 -3 5 3 0 0 0 2 3 3 37 0 E6 : (1) 6.06 .00 .00 4.55 4.55 .00 4.55 7.58 4.55 .00 .00 .00 3.03 4.55 4.55 56.06 .00 100.00 1 (2) .05 .00 .00 .03 .03 .00 .03 .06 .03 .00 .00 .00 .02 .03 .03 .43 .00 76 j 1 . (1)aPERCENT OF ALL 000D OBSERVATIONS FOR '!HIS PAGE I(2)tPERCENT OF ALL 000D OBSERVATIONS FOR THIS PERIOD ! ( C2 CAus (WIND SPEED LESS THAN OR EQUAL 10 .95 MPH) j i t , L 1 i L__._____________ _ _ . _ _ . _ _ . _ _ _ . _ -_- - - -
TABLE SC VERMONr YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISMIBUTION 397.0 PT Wise DATA - STABILITY CLASS C CLASS FREQUENCY (PERC8NTI = 2.22 WIND DIRECTION FROM - SPEED. N' lett ' NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL HPN
. CALM . 0 0 0 0 . 0- 0 0 0 0 0 0 0 0 0 0 0 0 0 (1)' .00 . 00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00. .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 C-3 0 0 0 2 0 1 1- .0 0 0 0- 1 0 1 0 1 0 - 7 (1) .00 .00 '.00 1.04 .00- .52 .52. .00 .00 .00 .00 .52 .00 .52 .00 .52 .00 3.63 (2)- .00 .00 .00 .02 .00 .01- .01 .00 .00 .00 .00 .01 .00 .01 . 00 .01 00 .08 4-7 4 -' 1 0 0 0 7 6 2 1 0 1 0 0 1 2 16 0 . 41
' (1) 2.07- .52' .00 .00 .00 3.63 3.11 1.04 .52 .00 .52 .00 ..00 .52 1.04 8.29 .00 21.24 j
- (23 .05 .01 .00 .00 .00 .08 .07 .CJ .01 .00 .01 .00 .00 .01 .02 .18 .00 .47 l
8-12 10- 0. 2 0 1' 3 2 11 3 0 0 2 3 4 4 18 0 63 (1)- 5.18 .00 1.04. 'f
.00 .52 1.55. 1.04 5.70 1.55 .00' .00 1.04 '1,55 2,07 2.07 9.33 00 32.64 J (2) . .11 . 00 . .02 '.00 .01 .03 .02 .13 .03 .00 . 00 .02 .03 .05 .05 .21' .00 .72
.13-18 $ 'O' O 1 . 1' 0 1 1 5 0 0- 2 4 3 8 15 0 46 (1) 2.59 .00 .00 .52 .52 .00 .52 .52 2.59 .00 .00 1.04 2.07 1.55 4.15 7.77' .00 23.83 (2) - .06 . 00 .00 . . 01 ' .01 .00 .01- .01 .06 .00 .00 .02. . 05 03 .09 .17 .00 .53 19 1.- 0- 0. 0 1 0 0 0 1 0 0 0 2 6 5 13 0 29 -
(1) ..52 ~ .00 .00 .00 .52 .00 .00 . .52 .00 .00 .00 1.04 3.11 2.59 6.74 .00 15.03 (2)- .01 .00 .00 .00 .01 .00 .00 '.00 00 .01 .00 .00 - . 00 .02 .07 .06 .15 .00 .33 GT 24 'O- 0 0 0- 0- 0 0 0- 0 0 0 0 1 1 3 2 0 7 (1)' .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .52 .52 1.55 1.04 .00 3.63 (2) .00 .00 .00 - .00 .00 .00 .00 - .00 .00 .00 .00 .00 .01 .01 .03 .02 .00 .08
- ALL SPEEDS ~20' 1 '2 ~3 .3 11 10 14 10 0 1 5 10 16 22 E5 0 193 )
-(1) 10.36 .52 1.04 1.55 1.55 5.70. 5.18 7.25 5.18 400 .52 2.59 5.18 8.29 11.40 33.68 .00 100.00 j (2) .23 .01 .02 .03 .03 .13 .11 416 11 .00 .01 .06 .11 .18 .25 .75 .00 2.22 (1)sPERCENT OF ALL 000D OBSERVATIONS FOR WIS PAGE
' 421sPERCENT OF ALL 000D OBSERVATIONS FOR WIS PERIOD Ca CALM (WIND SPEED LESS M AN OR EQUAL To .95 MPH) i j '.
4 j .- l L. L E_-_ __ _ ___ - - _ _ -_.
_ = _ _ _ _ . . _ __ _._ _ _._.._.._..___ _ .__ _ .___.._____.._.__ __ _ .__._. _ _ ___ _ _______ _ ___ ___ ___ _ _ _ _ _ _ _ _ _ _ . ._,
' TABLE-SD VB8MCBff YAtatEE JAN 97 = DEC 97 NE7500t0140! CAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WDID DATA STABILITY CLASS D - CLASS FREQUENCY (PERCEDFF) = 48.91 WIND DIRECTION FRON l
SPEED 38 3 DIE NE ENE E ESE . SE . SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL I
- ItPM
' CAut 0 0" 2 0 1 '0 0 0 0 1 0 0 0 0 1 2 0 7 (1) .00 .00 .05- .00 .02 '. 00 .00 .00 .00 .02 .00 .00 00 .00 02 .05 .00 .16 (2) .00 .00 .02 .00 .01 .00 .00 .00 .00 .01 '. 0 0 .00 .00 .00 .01 .02 .00 .08 )
C-3 ' 56 31. 38- 42 41 55 61 47 26 12 6. 11 - 12 9' 32 48 0 527 (1) 1.32 .73 - .89 .99 .96 1.29 1.43' 1.10 .61 .28 .34 .26 28 .21 .75 1.13 .00 12.39 (2) .64 .36 .' 4 4 .48 ' 47 ' .63
. .70- .54 .30- .14 ,07 .13 .34 .10 .37 .55 .00 6.06
- 47. 104. 33 23 20 48 76 107 118 92 20 21 16 15 27 .55 200' 0 975
-(1)- 2.44 78 .54 .47 1.13 1.79 2.52 2.77~ 2.16 .47 .49 .38 .3 5 ' .63 1.29, 4.70 .00.. 22.92 (2) 1.20 .38 .26 . 23 .55 .87 1.23 1.36 1.06- .23 -. 2 4 .18 .11 - .31 .63 ,2.30. .00 11.21 8-12 151 29 ' 25 11 20 28 63- 119- 162 41 38 44 95 121 63 245 0 1255
-(1) 3.55 .58 .26
.59 .47 .66 1.48 2.80 3.81 .96 .89 1.03 2.23 2.84 1.48 5.76 .00 29.50 (2) 1.74 .33 -.29 . .13 .23 .32 72 1.37 1.86 - .47 .44 - -. 51 1.09 1.39 .72 2.82 .00 14.43 13-18. 119 9 2 5- 2 4 11 29 125 20 13 19 110 203 111. 249 0 1031 (1) 2.80 .21- .05 .12 .05 .09 - 26 .68 2.94 .47 . . 31 . .45 2.59 4.77 2.61- 5.85 .00 ' 24.24 (2) 1.37 .10 .02 .06 .02' .05 .13 .33 1,44 .23; .15 .22 1.26 2.33 1.28 2.86 .00 11.85 19-24 24 2 0 0 0 0- 0 1 ~ . 18 3 . 0 4 43 89 63 112 0 359
- til c .56 .05 .00 .00 .00 .00 .00 .02. .42' 07 .00 .09 1.01 2.09 1.48 2.63 .00 8.44 (1) - .28 .02 ' .00 .00 .00 .00 .00 .01 .21 .03 . 00 .05- .49 1.02- .72 1.29 .00 4.13
' OT 24 '12 0' 0 0 0- 0- 0 0 0 1 1 0 .5 28 19 34 0 100 (1) .28 .00 .00 .00 .00 .00 .00 .00 .00 .02 .02 .00 .12 .66 .45 .80 00 2.35
. .(2) .14 .00 .00 .00 00 .00' .00 .00 .00 .01 . 01 .00 .06 .32 .22 .39 .00 1.15 l ALL SPEEDS . 466' 104 90 -78 112 163- 242 314- 423 98 79 94 280 477 344 890 0 4254 (1)( 10.95 2.44 2.12 1.83 2.63. 3.83 5.69 7.38 9.94 2.30 1.86 2.21 6.58 11.21 8.09 20.92 .00 100.00' (2)- 5.36 1.20- 1.03' .90 1.29. 1.87 2.78 3.61 4.86 1.13 .91 1.08 3.22 5.48 3.95 10.23 .00 48.91
[ :' (11sPERCDft OF ALL 000D OBSERVAT10NS FOR THIS PAGE
, 62)aPERCENT OF ALL 000D OBSERVATIONS FOR THIS PERIOD 3
- C2 CAuf (WIND SPEED LESS THAN OR Equi 10 ' .95 NPH) !
I I l 4
^
1 l.4
-- ______________2___-_. __ _ _ _. . - _ -
s TABLE'SE VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 1
'291.0 FT W18W DATA STABILITY CLASS E CLASS FREQUDICY (PERCENT) e 33.39 WIND DIRECTION FROM
- f. PEED . N 9BIE NE ONE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRSL SVTAL MPH -
- CALet: 2 0. '6 3 1 0 1 1 0 -0 1 0 0 0 1 2 0 18 (1) .07 .00 .21 .10 .00
.03 .03 .03 .00 .00 .03 .00 .00 .00 .03 .07 .00 .62 l (2)' .02 . .00 07~ .03 .01 .00 .01 .01 .00 .00 .01 . 00 .00 .00 .01 .02 .00 .21
' C-3 l111 76 55 44 56 12 77 50 47 21 12 16 12 17 37 77 0 780
-(1) 3.82' 2.62' 1.89 1.52 1.93 2.48 2.65 1.12 1.62 .72 .41 .55 .41 .59 1.27 2.65 .00 26.86 ,
(2) 1.28 .87 .63 .51 .44 .83 .89 .57 .54 .24 .14 .18 .34 .20 .43 89 .00 8.97 ! 4 156' 18 15 14- 17 45 137 115' 71' 26 18 12 20 30 63 272 0 1029
'(1). 5.37 .62 .52 '. 4 8 .59 1.55 4.72 3.96 2.44 .90 . 62 .41 .69 1.03 2.17 9.37 .00 35.43 I
. (2) 1.79 .21 .17 .16 .20 .52 1.58 1.32 .82 .30 .21 .14 .23 .34 72 '3.13 - .00 11.83
. 5-12 C4 .4 0 1. 1 8 28 13 75 20 18 28 56 75 63 247 0 161 (1) 2.20 .14 .00 .03 .03 28 .96 2.51 2.58 69 . .62 .96 1.93 2.58 2.17 8.51 .00 26.21 l(2); .74 ' .05 .00 .01 .01 .09 . 32 .84 .86 .23 .21 .32 .64 .86 .72 2.84 .00 8.75 13-18 11 1 0 0 0 0' 3 5 37 15 0 4 28 44 40 76 0- 264 (1) .38 : 03 . 00 .00 .00 .00 .10 ,17 1.27 .52 .00 .14 .96 1.52 1.38 2.62 .00 9.09 (2) .13: .01 .00 _. 0 0 .00 .00 .03 .06 .43. .17 . 00 .05 .32 .51 46 .87 .00 3.04 i 19 24 1' 1 .. 0 0 0 0 0~ 1 6 10 0 0 2 8 6 0 44 I
9 i (1) .03 ' .03 .00 .00 00 .00- .00 .03 .21 .34 .0J .00 .07 .28 .21 .31 .00 1.52 -l (2) .01 .01 .00 .00 .00 .00 .00 .01 .07 .11 .00 .00 02 .09 .07 .30 .00 . 51 _ l
- ST 24 - 0 0 0 0 .0 0 0 0 2 1 1 0 1 2 0 1 0 8 til .00 .00 .00 .00 .00 .00 .00 .00 .07 .03 .03 .00 .03 .07 .00 .03 .00 .28 (2) .00 .00 00 .00 .00 .00 .00 .00 .02 .01 .01 .00' .01 .02 .00 .01 .00 .09
' 2 AIL 5PEEDS' 345 100 76'. ' 62 - 75 '125 246 245 238 93 50 60 119 176 210 684 0 2904 (1) 11.88 3.44 2.62 2.13 2.58 4.30 8.47 8.44 8.20 3.20 1.72 2.07 4.10 6.06 7.23 23.55 .00 100.00 (2). .3.97 '1.15 .87 .71 .86 1.44 2.83 2.82 2.74 1.07 .57 .69 1.37 2.02 2.41 7.86 .00 33.39 ] 1 (llahMtCDrF OF ALL 000D OBSERVATIONS FOR THIS PAGE ' , (21sPE3 CENT OF ALL GOOD OBSERVATIONS FOR 7HIS PERIOD Ca CA'Jt (WIND SPEED LESS THAN OR EQUA6 TO .95 MPH) l l i t i i [' E__ _ - - - - - - _-- - - - - - - -- - - -_
TABLE 5F VERM0tfr ?ANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOIlrF FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 12.57 WIND DIRECTION FROM SPEED N HNE NE ENE E ESE SE ESE S SSW SW WSW W WNW NW NNW VRSL 70TAL F.PH CALM 1 1 0 2 0 0 0 1 0 0 0 0 1 1 1 0 0 8 (1) .09 .09 .00 .18 .00 .00 .00 .09 .00 .00 .00 .00 .09 .09 .09 .00 .00 .73 (2) .01 .01 .00 .02 .00 .00 .00 .01 .00 .00 .00 .00 .01 .01 .01 .00 .00 .09 C-J 65 37 29 31 30 33 44 30 19 16 8 6 7 8 27 35 0 425 (1) 5.95 3.39 2.65 2.84 2.74 3.02 4.03 2.74 1.74 1.46 .13 .55 .64 .73 2.47 3.20 .00 38.88 (2) .75 .43 .33 .36 .34 .38 .51 .34 .22 .28 .09 .07 .08 .09 .31 .40 .00 4.89 4-7 59 2 5 6 19 29 51 55 32 14 9 20 14 18 20 96 0 449 (1) 5.40 .18 .46 .55 1.74 2.65 4.67 5.03 2.93 1.28 .82 1.83 1.28 1.65 1.83 8.78 .00 41.08 (2) .68 .02 .06 .07 .22 .33 .59 .63 .37 .16 .10 .23 .16 .21 .23 1.10 .00 5.16 8-12 5 1 0 0 2 1 10 14 20 15 8 6 12 19 8 60 (1) .46 0 181
.09 .00 .00 .18 .09 .91 1.28 1.83 1.37 .73 .55 1.10 1.74 .73 5.49 .00 (2) .06 .01 .00 16.56
.00 .02 .01 .11 .26 .23 .17 .09 .07 .14 .22 .09 .69 .00 2.08 13-18 0 0 0 0 0 0 0 2 1 3 0 2 4 4 1 13 0 30 (1) .00 .00 .00 .00 .00 .00 .00 .18 .09 .27 .00 .38 .37 .37 .09 1.19 .00 2.74 (2) .00 .00 .00 .00 .00 .00 .00 .02 .01 .03 .00 .02 .05 .05 .01 .25 .00 .34 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00
.00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 130 41 34 39 51 63 105 102 12 48 25 34 39 50 57 204 0 1093 (1)
(2) 11.89 1.49 3.75.47 3.11
.39 3.57
.45 4.67
.59 5.76
.72 9.61 9.33 6.59 4.39 2.29 3.11 3.48 4.57 5.22 18.66 .00 100.00 1.21 1.17 .83 .55 .29 .39 .44 .57 .66 2.35 .00 12.57 (1)sPERCDff CF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)ePERCDTP OF ALL C00D OBSERVATIONS FOR THIS PFR10D Ce CALM (WIND SPEED LESS THAN OR EQUAL 'IO .95 MPH)
TABLE SG-l- i f VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUINCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCDrf) e 1.52 WIND DIRECTION FRON. SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRSL WTAL NPK
, CAIJt 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
,(1) .00 .00 ' .00 .00 .00 '. 00 .00 . 00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
- 82) ~ .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 '. 0 0 .00 .00 .00 .00 .00 .00 .00 C-3 5 2 3 4 1 4 3 1 l' 2 3 2 2 1 3 3 0 40 (1) 3.79 1.52 2.27 3.03 .76 3.03 2.27 .76 .76 1.52 2.27 1.52 1.52 .76 2.27 2.27 .00 30.30 (2) .06 .02 .03 .05 .01 .05 .03 .01 .01 02 .03 .02 .02 .01 .03 .03 .00 .46 4-7 2 1 0- 0 3 0 2 6 7 7 1 6 4 3 4 8 0 54 (1) -1.52 76 .00 .00 2.27 .00 1.52 4.55 5.30 5.30 .76 4.55 3.03 2.27 3.03 6.06 .00 40.91 (2) .02 .01 .00 .00 .03 .00 .02 .07 .08 .08 .01 .07 .05 .03 .05 .09 .00 .62 0 12 1 '. O' 0 0 0 0 0 2 0 0 2 4 6 9 2 8 0 34 (1), 76 .00' .00 .00 .00 .00 .00 1.52 .00 .00 1.52 3.03 4.55 6.82 1.52 6.06 .00 25.76 (2) ' .01 .00 .00 .00' .00 .00 .00 .02 .00 .00 .02 .05 .07 .10 .02 .09 .00 .39 13 18 0 0 0 0 0 0 0 0 1 1- 0 0- 1" 1 0 0 0 4 (1) .00 .00 .00; .00 .00 .00 .00 .00' . '8 6 .76 .00 .00 .76 .76 .00 -. 00 .00 3.03 (3) .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .01. .01 .00 .00 .00 .05 19-24 0 0 0 'O O O O 0 0 0 0 0 0 0 0 0 -0 0 (1) .00 .00' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
- (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
' 07 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 MO .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS ' S - 3 3 4 4 4 5 9 9 10 6 12 13 14 9 19 0 132
.(1) 6.06 2.27 2.27 3.03. 3.03 3.03 3.79 6.82 6.62 7.58 4.55 9.09 9.85 10.61 6.82 14.39 .00 100.00
- (2) .09 .03 .03 .05 .05 .05 .06 .10 .30 .11 .07 .14 .15 .16 .10 .22 .00 1.52 (1)sPERCENT OF ALL COOD OBSERVATIONS FOR THIS PAGE
.(2)sPERCENT OF ALL GOOD OBSERVATIONS FOR ThfS PERIOD
' Cs CAIAI O.'IND SPEED LESS THAN OR EQUAL M .95 NPH) l
TABLE SH l VERMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 307.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) 100.00 WIND DTRECTION FROM SPEED N NNE NE ENE E ESE SE $$E S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM 3 1 8 5 2 0 1 2 0 1 1 0 1 1 4 0 3 33 (1) .03 .01 .(9 .06 .02 .00 .01 .02 .00 .01 .01 .00 .01 .01 .03 .05 .00 .38 (2) .03 .01 .09 .06 .02 .00 .01 .02 .00 .01 .01 .00 .01 .01 .03 .05 .00 .38 C-3 239 146 125 127 128 168 187 129 95 51 2r 36 33 36 100 165 0 1794 (1) 2.75 1.68 1.44 1.46 1,47 1.93 2.15 1.48 1.09 .59 .33 .41 .38 .41 1 15 1.90 .00 20.63 (2) 2.15 1.68 1.44 1.46 1.47 1.93 2.15 1.48 1.09 .59 .33 .41 .38 .41 1.15 1.90 .00 20.63 4-7 326 55 43 41 89 160 310 298 205 68 50 54 53 79 145 595 0 2571 (1) 3.75 .63 .49 .47 1.02 1.84 3.56 3.43 2.36 .78 .57 .62 .61 .91 1.67 6.84 .00 29.56 (2) 3.75 .63 .49 .47 1.02 1.84 3.56 3.43 2.36 .78 .57 .62 .61 .91 1.67 6.84 .00 29.56 8-12 234 34 27 13 24 40 105 225 260 76 66 84 172 229 141 591 0 2321 (1) 2.69 .39 .31 .15 .28 .46 1.21 2.59 2.99 .87 .76 .97 1.98 2.63 1,62 6.79 .00 26.68 (2) 2.69 .39 .31 .15 .28 .46 1.21 2.59 2.99 .87 .76 .97 1.98 2.63 1.62 6.79 .00 26.68 13-18 136 10 2 6 3 4 15 37 171 39 13 27 150 258 162 372 0 1405 (1) 1.56 .11 .02 .07 .03 .05 .17 .43 1.97 .45 .15 .31 1.72 2.97 1.86 4.28 .00 16.15 (2) 1.56 .11 .02 .07 .03 .05 .17 .43 1.97 .45 .15 .31 1.72 2.97 1.86 4.28 .00 16.15 19-24 27 3 0 0 2 0 0 2 25 13 0 4 48 105 77 150 0 456 (1) .31 .03 .00 .00 .02 .00 .00 .02 .29 .15 .00 .05 .55 1.21 .89 1.72 .00 5.24 (2) .31 .03 .00 .00 .02 .00 .00 .02 .29 .15 .00 .05 .55 1.21 .89 1.72 ,00 5.24 GT 20 12 0 0 0 0 0 0 0 2 2 2 0 8 31 22 39 0 118 (1) .14 .00 .00 .00 .00 .00 .00 .00 .02 .02 .02 .00 .09 .36 .25 .45 .00 1.36 (2) .14 .00 .00 .00 .00 .00 .00 .00 .02 .02 .02 .00 .09 .36 .25 .45 .00 1.36 ALL SPEEDS 977 249 205 192 248 372 618 693 758 250 161 205 465 739 650 1916 0 8698 (1) 11.23 2.86 2.36 2.21 2.85 4.28 7.11 7.97 8.71 2.87 1.85 2.36 5.35 8.50 7.47 22.03 .00 100.00 (2) 11.23 2.86 2.36 2.21 2.85 4.28 7.11 7.97 8.71 2.87 1.85 2.36 5.35 8.50 7.47 22.03 .00 100.00 (1)sPERCEN!' OF ALL GOOD OBSERVATIONS FOR 7HIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS TH44 OR EQUAL TO .95 MPH)
TABLE 6A VERMONT YANKEE JAN 97 - DEC 97 METEOR 014GICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 PT WIND DATA STABILI'IY CIASS A ' CLASS FREQUENCY (PERCENT) e 1.87 WIND DIRECTION FROM SPEED 5 WE- NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL RPN CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
.(1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00-
- (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 2 0 2 0 2 2 1 2 1 0 2 0 0 0 1 0 0 15 (1) 1.27- .00 1.27 .00 1.27 1.27 .63 1.27 .63 .00' 1.27 .00 .00 .00 .63 .00 .00' 9.49 (2) .02 .00 .02 .00 .02 .02 .01 .02 .01 .00 .02 .00 .00 .00 .01 .00 .00 .18 4-7 13 0. 1 2 2 5 '5 6' 1 1 0 1 0 1 12 21 0- 71
- (1) 8.23 .00 .63 1.27- 1.27 3.16 3.16 3.80 .63 .63 .00 .63 .00 .63 7.59 13.29 .00 44.94 (2) .15 - .00 .01 .02 .02 ,06 .06 .07 .01 .01 .00 .01 .00 .01 .14 .25 .00 .84 4-12 12 0 0 0 0 0 0 0 3 0 0 'l 3 7 7 30 0 63
. (1) 7.59 .00 .00 .00 ,00 .00 .00 .00 1.90 .00 .00 .63 1.90 4.43 4.43 18.99 .00 39.87 (2) .14 .00 .00 .00 .00 .00 .00 .03 .04 .00 .00 .01 .04 .08 ' .08 .35 .00 75 13-18 1 0 0 0 0 0 0 0 1 0 0 0 0 2 5- 0 .0 . 9
~ (1) .63 .00 .00 .00: .00 .00 .00 .00 .63 .00 .00 .00 .00 1.27 3.16 .00 .00 5.70 (2) .01 .00- .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .02 .06 ,00 .00 .11 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 j (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 '
(3) .00 .00 .00 .00 .00 .00 .00 ' ' 00
. .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24-. .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i (1) .00 .00 .00 .00. .00 .00 .00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l
.00 'I ALL SPEEDS 28 0- 3 2 4 7 6 8 6 1 2 2 3 10 25 51 0 158 (1) 17.72 .00 1.90 1.27 2.53 4.43 3.80 5.06 3.80 .63 1.27 1.27 1.90 +.33 15.82 32.28 .00 100.00 .
(2) .33 .00 .04 .02 .05 .08 .07 .09 .07 .01 .02 .02 .04 .12 .30 .60 .00 1.87 (llePERCENT OF ALL GOOD OBSERVATIONS FOR 'MIIS PAGE (2)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Co CALM'(WIND SPEED LE43 THAN OR EQUAL '30 .95 MPH) l. 1 J l
]
I l j
TABLE 6B VLHMONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS B CLAais FREQUENCY (PERCDIT) = 1.69 WIND DIRECTION FROM SPEED N HNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL '!OTAL kPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 2 0 0 2 0 0 0 0 0 0 0 0 0 1 1 0 6 (1) .00 1.40 .00 .00 1.40 .00 .00 .00 .00 .00 .00 .00 .00 .00 .70 .70 .00 4.20 (2) .00 .02 .00 .00 .02 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .07 4-T 18 2 1 3 0 5 6 7 4 0 1 1 2 2 6 15 0 73 (1) 12.59 1.40 .70 2.10 .00 3.50 4.20 4.90 2.80 00 .70 .70 1.40 1.40 4.20 10.49 .00 51.05 (2) .21 .02 .01 .04 .00 .06 .07 .08 .05 .00 .01 .01 .02 .02 .07 .18 .00 .86 8-12 11 0 0 0 1 0 0 5 1 1 0 2 5 1 9 16 0 52 11] 7.69 .00 .00 .00 .70 .00 .00 3.50 .70 .70 .00 1.40 3.50 .70 6.23 11.19 .00 36.36 (2) .13 .00 .00 .00 .01 .00 .00 .06 .01 .01 .00 .02 .06 .01 .11 .19 .00 .62 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 5 3 3 0 11 (1) .00 .00- .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.50 2.10 2.10 .00 7.69 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .06 .04 .04 .00 .33 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .70 .00 .00 .00 .70 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 CT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 29 4 1 3 3 5 6 12 5 1 1 3 7 9 19 35 0 143 (1) 20.28 2.80 .70 2.10 2.10 3.50 4.20 8.39 3.50 .70 70 2.10 4.90 6.29 13.29 24.48 .00 100.00 (2) .34 .05 .01 .04 .04 .06 .07 .14 .06 .01 .01 .04 .08 .11 .22 .41 .00 1.69 (llePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)(PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD CD CALM (WIND SPEED LESS '!HAN OR EQUAL TO .95 MPH) 6 l l l i !
TABLE 6C VERN0erP YANKEE JAN 97 = DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION
, 35.0 FT WIND DATA STABILITY CLASS C CLASS FREQUDICT (PERCENT) e 2.76 WIND DIRECTION FROM
. SPEED N. Sem NE ENE E ESE SE SSE SW WSW W WNW NPH S SSW NW NNW VRBL TOTAL CAIJt 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 ,00 .00 .00 .00
- 12) .00 .00 .00 .00 .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 '2 1. 5 0 1 1 0 3 0 1 1 0 0 0 0 2 0 17 (1). .86 .43 2.15 .00 .43 .43 .00 1.29 .00 .43 .43 .00 .00 .00 .00 .86- .00 1.30 (2) .02 .01 .06 .00 .01 .01 .00 .04 .00 .01 .01 ,00 ~ .00 .00 .00 .02 .00 .20 4-7 -24 4 1 2 8 6 10 8 4 3 1 4 8 6 18 29 .0 136 (1). 10.30 1.72- .43 .86 3.43 2.58 4.29 3.43 1.72 1.29 .43 1.72 3.43 2.58 7.73 12.45 .00 58.37 (2) .28 .05 .01 .02' .09 .07 .12 .09 .05 .04 .01 .05 .09 .07 .21 .34 .00 1,61 8 12 18 2 0 0- 0 1 0 3 6 3' 2 5 5 5 7 12 0 69 (1) 7.73 .86 .00 .00 .00 .43 .00 1,29 2.58 1.29 .86 2.15 2.15 2.15 3.00 5.15 .00 29.61 (2) .31 .02 .00 .00 .00 .01 .00 .04 . .07 .04 .02 .06 .06 .06 .08 .14 .00 .82 13-10' 0 0 0 0 0 0 0 0 0 0 0 0 2 4 4 0 0- -10 (1) .00 .00 .00 .00 ..00- .00 .00 , .00 .00 .00 .00 . 00 .86 1.72 1.72 .00 .00 4.29 (2)' .00 .00 .00 .00 .00 .00 .00 . 00 - .00 .00 .00 .00 .02 .05 .05 .00 .00' .22
'19-24 0 0 0 0 0 0 0 0 0. 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .43 .00 .00 .00 .43 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00. .00 .01 .00 .00 .00 .01 0T 24 .0 . 0 0 0 0 0 0 0 0- '0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 . .00 .00 '.00 .00 .00 .00 .00 .00 .00 ,00 .00
. (2) .00 .00 .00 .00' .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00
. ALL SPEEDS- 44 7 6 2 9 8 to ' 14 10 7 4 9 15 16 29 43 0 233 (1) .18.88E 3.00 2 "8 .86 3.86 3.43 4.29 6.01 4.29 3.00 1.72 3.86 6.44 6.87 12.45 18.45 .00 100.00
- (2 ) .52- .08 .07 .02 .11 .09 .12 .17 .22 .08 .05 .11 .18 .19 .34 .51 .00 2.76
' (1)sPERCDfT OF ALL GOO'- ASERVATIONS FOR THIS PAGE (21sPEACENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD
- C2 CA1Al (W1HD SPEED LESS THAN OR EQUAL 'IO .95 MPHI f
i 1 i i c l t
- n. i j
TABLE 6D VERMQNT YANKEE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND IATA STABILITY CLASS D CLASS FREQUDICY (PERCDIT) = 38.55 WIND DIRECTION TROM SPEED N NNE NE DTE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL EPH CALM 0 2 0 0 0 1 1 0 0 0 0 1 0 0 0 2 0 7 (1) .00 .06 .00 .00 .00 .03 .03 .00 .00 .00 .00 .03 .00 .00 .00 (2) .00 .06 .00 .21
.02 .00 .00 .00 .01 .01 .00 .00 .00 .00 .01 .00 .00 .00 .02 .00 .08 C-3 91 68 49 59 54 42 56 48 38 31 24 18 26 31 54 95 0 784 (1) 2.79 2.09 1.50 1.81 1.66 1.29 1.72 1,47 1.17 .95 .74 .55 .60 .95 (2) 1.08 1.66 2.92 .00 24.06
.60 .58 .70 .64 .50 .66 .57 .45 .37 .28 .21 .31 .37 .64 1.12 .00 9.28 4-7 216 63 40 52 67 78 68 119 142 47 35 31 79 (1) 58 90 246 0 1431 (2) 6.63 1.93 2.56 .75 1.23
.47 1.60 2.06 2.39 2.09 3.65 4.36 1.44 1.07 .95 2.42 1.78 2.76 7.55 .00 43.92
.32 .79 .92 .80 1.41 1.68 .56 .41 .37 .91 .69 1.06 2.91 .00 16.93 8-12 142 16 8 .2 9 8 1 18 109 19 21 22 78 (1) 4.36 .49 .25 163 88 109 0 813
.06 .28 .25 .03 .55 3.35 .58 .64 .68 2.39 5.00 2.70 3.35 .00 24.95 (2) 1.68 .19 .09 .02 .11 .09 .01 .21 1,29 .22 .25 .26 .92 1.93 1.04 1,29 .00 9.62 13-18 16 0 0 0 0 0 0 0 17 2 0 2 21 90 40 11 (> 201 (1) .49 .00 .00 .00 .00 .00 .00 .00 .52 .06 .00 .06 .71 .00 (2) .19 .00 .00 2.76 1.23 .34 6.17
.00 .00 .00 .00 .00 .20 .02 .00 .02 .27 1.06 .47 .13 .00 2.38 19-24 1 0 0 0 0 0 0 0 0 0 1 0 11 1 8 0 0 22 (1) .03 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .03 .34 .25 .00 (2) .01 .00 .00 .68
.00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 .13 .09 .00 .00 .26 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
.00 .00 .00 .00 ALL SPEEDS 466 149 97 113 130 129 126 185 306 99 81 14 207 353 280 463 0 3258 (1) 14.30 4.57 2.98 3.47 3.99 3.96 3.87 5.68 9.39 3.08 2.49 2.27 6.35 10.83 8.59 14.21 .00 100.00 (2) 5.51 1.76 1.15 1.34 1.54 1.53 1.49 2.19 3.62 1.17 .96 .88 2.41 4.18 3.31 5.48 .00 38.55 (1)sPERCDrf CF ALL GOOD OBSERVATIONS FOR THIS PAGE (21ePERCENT OF ALL COOD OBSERVATIONS FOR THIS PERIOD Ce CA1M (WIND SPEED LESS THAN OR EQUAL 70 .95 MPH) 4
' TABLE 6E VERNONT YANKEE JAN 97 - DEC 97 METEOROLOGICAL EATA J0INF FREQUENCY DISTRIBUTION "35.0 FT W1MD DATA STABILITY CLASS E- CLASS FREQUDiCY (PERCENT) = 35.94 .
WIND DIRECTION FROM f REED . ' at NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL '!VTAL RPM CAIJE 1 0 3 6 1 3 1 0 1 2 5 3 4 0 1 2 0 33 (1) ..03 00 .10 .20 .03 .10 .03 .00 .03 .07 .16 .10 .13 ,00 .03 .07 .00 1.09 (2) .01 .00 .04 .07 -, 01 .04 .01 .00 .01 .02 .06 .04 .05 .00 .01 .02 .00 .39 C 110 .46. 36 29 44 48 56 98 98 134 172 145 160 141 163 167 0 1627 (1) 3.62 1.51 1.19 .95 1.45 1.58 1.84 3.23 3.23 3.75 5.66 4.17 5.27 4.64 5.37 5.50 .00 53.57 (2) 1.30 ' .54 .43 .34 .52 .57 .66 1.16 1.16 1.35 2.04- 1.72 1.89 1,67 .1.93 1.98 .00 19.25 4-7 . 85 -11 5 6 16 29 38 95 85 29 33 34 83 121 158 188 0 1016 (1) 2.80 " .36 .3 6 . .30 .53 .95 1.25 3.13' 2.80 .95 1.09 1.12 2.73 3.98 5.20' 6.19 .00 33.45 (2) 1,01 '3 .06 .07 .19 .34 .45 1.12 1.01 .34 .39 .40 .98 1.43 1.87 2.22 .00 12.02 0-12 24 3 0- -0 3 4 1 10 - 57 20'- 1 2 30, 65 57 26 0 303
.(1) '.79 .30 . 30 .00 .10 .13 " .03 .33 1.88 .66 .03 .07 .99 '2.14 1.88 .86 '.00 9.98 (2) .28 .04' 40- .00 . 04 ' .05 . 01 , .12 .67 .24 . 01 - .02 .35 *
.17 .67 .31 .00- 3.59 13 6, 0 0 0 1 0 0- 0 14 5 1 1 3 8 12 1 0 52 st) . .30 .00 ; .00 . 00 .03 . 00 .00 .00 .46 .16 .03- .03 .10 .26 .40 .03 .00 '1.71
-(2) .07 - .00 00 ,00- '. 01 .00 .00 .00 .17 .06 .01 .01 .04 .09 .14 - .01 .00 - .62 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 4 1 0 0 5 (1) . .00 .00. '. 0 0 .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 .13 .03 .00 .00 .16
.(2) .00 .00 . .00 . .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 ,01 .00' .00 .06
- 07 24 0 0 0 0 0 0- 0 0 0 0 0 0 -0 1 0 0 0 1
. (1) .00 .00 ' .00 .00 .00 .00 - .00 .00 .00 .00 00 .00 .00 .03 .00 .00 .00 .03 (2) -- .00 .00 .00 .00 .00' .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 ALL SPEEDS' 226 60 44 41- 65 - 84 ' 96 203 255. 170 212 .185 280 340 392 384' 0 3037
- (1) 1.44 1.98 1.45 :1.35- 2.14' 2.77 3.16 6.68 8.40 5.60 6.98 6.09 9.22 11.20 12.91 12.64 .00 100.00 (2) 2.67 .71 .52 .49 .77 .99 1.14 2.40 3.02 2.01 2.51 .2.19- 3.31 4.02 4.64 4.54 .00 35.94
-(1)aPERCENT OF ALL GOOD OBSERVATIONS FOR 7EIS PAGE (21sPERCENT OF ALL 000D OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO 495 MPH) t
(~' i i-l
i l-l l t
- i. .
l i ,7 j ,t f i' l;
- TABLE 6F l
VERNONt YA303E JAN 97
- DEC 97 NET 50RO14GICAL DATA JOINT FREQUDCf DIS 7R15UT10N
.35.0 FT WIND DATA STAS!LITY CLASS F CLASS FREQUENCY (PERCENT) = 15.87 l WIND DIRECTION FROM l
l- 'sPsED: w NNE NE ENE E EsE 'sE SsE S SsW SW wsw W WNW
. NPn NW NNW VRBL WTAL '
CAIJE 1 0 0 1 0 0 1 0 0 0 1 0 1 1 1 0 0 7 (1) .07 .00 .00 .07 .00 .00 .07 .00 .00 .00 .07 .07 .07 .00 .07 .00 .00 .52 (2) .01 .00 .00 .01 .00 .00- .01 .00 .00 .00 .01 .01 '. 01 .00 .01 .00 .00 .08
-~
C-3 32 13- 19 16 8 14 20 26 68 115 276 200 153 110 70 56 0 1196
.. (11 2.39 .97 1.42 1.19 60 1.04' 1.49~ 1.94 5.07 8.58 20.58 14.91 11.41 8.20 5.22 4.18 .00 89.19 (21~ .38 .15 .22 .19 -- .09 .17 ,24 .31 .80 1.36 3,27 2.37 1.81'1.30 . 83 . .66 .00 14.15
- 4-7 1 2 0 1 1 3 2 .2 15 . 15 19 9 18 13 22 14- 0 137 (1) .07 '. .15 .00- .07 .07 _.22- .15 415 1.12 1.12 1.42 .67 1.34 .97 1,64 1.04 . 00 ' 10.22 l
(2). .01 02 . 00 .01 .01 .04 .02 .02 .18 .16 - .22 .ti .21 .15 .26 .17 .00 . 1.62 8-12 -0 0 0 0 0 0 0 .0 0 0 s 0 0 1 0 0 0 1 , (1)" .00 . .00 .00 .00 .00 .00 .00 . .00- .00 .00 .00 -. 00 .00 .07 .00 .00 00 .07 ' l (2) .00 .00 .00 .00 .00 .00 .00 .00- .00 .00 .00 .00 . 00 .01 .00 .00 .00 .C1 13-18' 0 0- 0~ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i (1)' .00 .00 . . 00. - .00 .00 ' ..00 00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 (2). .00_ .00 .00 .00 .00 .00 .00 .00 .00 00 .00 00 .00 .00 .00 .00 . 00 ' .00 19-24 0. 0 0 0 0 0- 0 0 0 0 -0 0 0 0 0 0 0 0 (1) .00 - .00 00 .00 00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
,(21- .00 .00 .00' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 . 0' O O O 0 0 0 0 0 0 0 C. 0 0 0 0 0 0 j
- (1) .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 i (2) .00 00 .00- .00 ,00' .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00
'ALL $PEEDs , 34 15 . . 19 18 . 9 17 23 28 83 130 296 210 172 124 93 10 0 1341 J . (1) .2.54 1.12 1.42' 1.34- .67. 1.27 1.72 2.09 6.19 9.69 22.07 15.66 12.83 9.25 6.94 5.22 .00 100.00 (2) .40 .18 .22 .21 .11 .20 .27 .33 .98 1.54 3.50 2.48 2.04 1.47 1.10 .83 .00 15.87 1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE
' .- ((2)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD j Cs CALM (WIND SPEED LESS 1HAN OR EQUAL TO .95 MPH) i P > :l l lt L
i TABLE 6G VEIUGONT YANKEE JAN 97 - DEC $1 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION
- 25.0 FT WIND DATA $ M ILITY CLASS O CLASS FREQUENCY (PERCDIT) = 3.33 WIND DIRECTION FROM SPEED N 84fE WE W E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL
-- nPn -
CALM 'O- 0 0 0 0 ? 0 0 0 0 1 0 1 1 1 0 0 4 (1) - .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 .36 .00 .36 .36 .36 .00 .c3 '1.42 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 01 .01 .00 .00 .05 C-3 12 5 2 4 5 5 1 12 16 28 52 28 32 18 13 14- 0 .- 250 l- (1) 4.27 '1.78 .71 1,42 1.18 1.78 1,42 4.27 5.69 9.96 18.51 9.96 11.49 6.41 4.63 4.98 .00 88.97
-(2). .14 06 .02 .05 ,06- .06 .05 .14 .19 ,33 .62 433 .38 .21 .35 .17 .00 2.96-7 0 0 0 1 '0' O O 'O . 1 .4 10. 1 0 5 3 1 0' 26 (1) .00 .00 .00 .36 .00- .00 .00 .00 .36 1.42 3.56 .36 ,00 1.78 1.07 .36 .00 9.25
-(2). .00 . .00 .00 .01' .00 .00 .00 .00 .01 .05 .12 .01 .00 .06 .04 .01 '.00 .31 8-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1-l
- (1) ' .00 . .00 .00 .00 . .00 .00- .00 .00 .0C .00 .00 .00 .00 .00 .00 .36 '. 00 .36 (2) .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 13 18 0 0- 0 '0-0 0- 0 . 0 0 0' '/ 0- 0 0 0 0 0 0 (1) . 00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) ' .00- .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19 0' 0 0 0 0- 0 '0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 ' .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) ' .00 .00 . 00 .00 . 00 .; .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00
@T 24 . 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (ll .- .00 .00 .00 .00 . .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1 (2) .00 .00 .00 . -. 0 0 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 j l
ALL SPEEDS 12 . 5 2 - 5 5 5 4 12 17 32 63 29 33 24 17 16 0 281 (1) . 4.27 1.78 .71 1.78 1.78 1.78 1.42 4.27 6.05 11.39 22.42 10.32 11.74 8.54 6.05 5.69 .00 100.00 (2) - .14 ,06 .02 .06 406 .06 ,05 .14 .20 .38 .75 .34 .39 .28 .20 .19 .00 3.33 ! (1)aPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE l ' 425aPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD i C2 CAIJi (WIND SPEED LESS THAN OR EQUAL To .95 MPH) ) i I I i i
t l ? l I-TABLE 6H VB30n00f7 YANFRE JAN 97 - DEC 97 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WImp DATA ~ sTASILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00
- j. WIND DIRECTION FROM
' SPEED 'N' NNE NE 'ENE E ESE SE .SSE S SSW SW WSW W MM NW NNW VRBL TOTAL MPH.
CALM - 2. 2 3 7 1 4 3 0 1 2 7 5 6 1 3 4 0 51 (1): .02 .02 .04 .08 .01 .05- .04 .00 - .01 .02 .08 .06 .07 .01 .04 .05 .00 - .60 (2) .02 - .02 .04 .08 . 01 .05- .04 .00 .01 .02 .08 .06 .07 .01 .04 .05 .00 .60 C-3 249 135 113 108 116 112 131 189 '221 289 527 . 391 371 300 302 335 0 3895
' ill . 2.95. 1.60 1.34 1.28 1.37 "1.33 1.62 -2.24 2.62 3.42 6.24 4.63 4.39 3.55 3.57 3.96 .00 - 46.09' i (2) 2.95 1.60 1.34 1.28 1.37 1.33 1.62' 2.24 2.62 3.42 6.24 4.63 4.39 3.55 3.57 3.96 .00 46.09 !
4 357 82 48 67 94 126 129 237 252 99 99 81 190 206 309 514 0 2890 (1): 4.22 .97 .57 .19 1.11 1.49 1.53 2.80 2.98 1.17 1.17- .96 2.25 2.44 3.66' 6.08 .00 34.20
. (2 ) - 4.22 .97 = .51 .79 1.11 1.49 1.53 2.80 2.98 1.17 1.17 .96 2.25 2.44 3.66 6.08 - .00 34.20 8-12, '207 21 8 2 13 13 2 36 176 43 24 32 . 121 242- 168 194- 0 1302 "
(1) 2.45 25 .09 .02 15 .15 .02 .43 2.08 .51 .28 .38 1.43 2.86 1.99- 2.30 .00 .15.41 (2) 2.45 .25 . .09 .02 .15 '.15 .02 .43 2.08 .51 .28 .38 1.43 2.86 1.99 2.30 .00 15.41 - 13-18 23' 0 0 0 1 0 0 0 32 7 .1 3 28 109 64 15- 0 283 (1) .27 . 00 - .00 .00 .01 .00 .00 .00 .38 .08 .01 .04 .33 1,29 .76 .18- .00 3.35 (2) .47 .00 .00 .00 .01 . 00 ' .00 .00 .38 .08 .01 .04 .33 1.29 .76 ,18 .00 3.35 19-24 1 0 0- -0 0 0 0 0 0 0 1 0 1 17 9 0 0 L29
-(1)- 01 .00 .00 .00 .00 .00 00 .00 .00 . 00 .01 .00 .01 .20 .11 .00 .00 .34 (2) - . 01 . .00 .00 .00 .00 .00 .00 .00 - .00 .00 .01 .00 01 .20 .11 .00 .00 34 GT 24 0" 0 0 0 0 0 0 0 'O 0 0 0 0 1 0 0 0 1 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 . .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 1
-(2)- .00 .00 .00 .00 .00 .00 ~ .00 .00 .00 .00 - .00 .00 .00 .01 .00 .00 .00 .01 I
'ALL SPEEDS' 039 240 172 184 225 255- 271 462 682 440 659 512- 717 -876 855 1062 0 6451 (1) 9.93 2.84 2.04 2.18 2.66 3.02 3.21 5.47 0.07 5.21 7.80 6.06 8.48 10.37 10.12 12.57 .00 100.00 (2) 9.93 2.84 2.04 2.18 2.66 3.02 3.21 5.47 8.07 5.21 7.80 6.06 8.48 10.37 10.12 12.57 .00 100.00 (1)sPE* CENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE
' (2)sPERCENT OF ALL GOOD OBSERVATIONS FOR 'm!S PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 1 I
APPENDIX A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SupplementalInformation for 1997 Facility: Vermont Yankee Nuclear Power Station Licensee: Vermont Yankee Nuclear Power Corporation IA, TECHNICAL SPECIFICATION LIMITS - DOSE AND DOSE RATE Technical Specification and Categorv Lunit
- a. Noble Gases 3.8.E.1 Total body dose rate 500 miem/yr 3.8.E.1 Skin dose rate 3000 m m/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. Todine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Davs 3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.I. Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a year
- c. I iquids 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 mremin a year 3.8.B.1 Organ dase 5 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year 2A. TECHNICAL SPECIFICATION LIMITS - CONCENTRATION Technical Specification and Category Linnt
- a. Noble Gases No ECL Limits
- b. Iodine-131 Todine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days No ECL Limits i
muuwenos A-1 i i I'
APPENDIX A (Continued) , EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l l
- c. Liquids l 3.8.A.1 Total fraction of ECL j excluding noble gases l (10CFR20, Appendix B,
. Table 2, Column 2): si.0E+01 l 3.8.A.1 Total noble gas concentration: s2E-04 pCi/cc l 3. AVERAGE ENERGY, Provided below are the average energy (E) of the radionuclides mixture in releases of fission l and activation gases, if applicable.
- a. Average gamma energy: Not Applicable -
- b. Average beta energy: Not Applicable
- 4. MEASUREMENTS AND APPROXIMATIONS OFTOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclides composition.
- a. Fission and Activation' Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table IB and the totals of Table I A. The error involved in these steps may be approximately 23 percent.
- b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131,132,133,134, and 135. The error involved in these steps may be approximatelyil8 percent.
I l wnm. mms . A-2
I APPENDIX A (Continued) EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT I
- c. Particulate j l
The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximatelyil8 percent. 3
- d. Tritium Grab samples from the plant stack are taken monthly through a cold trap collection device and analyzed for tritium. The error involved in this sample is approximately f 15 percent.
- e. Warte Oil Prior to issuing the permit to turn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in Technical Specification Table 4.8.1.
Monthly, samples from drums that were issued burn permits are sent to the E-Lab for compositing and analysis. The E-Lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample. The error involved in this sample is approximately 15 percent. The LLDs for gross alpha, Sr-89, and Sr-90 were not met for the March 1997 composite sample due to insufficient sample size. The LLD for Sr-89 was not met for the May 1997 composite sample due to delay in counting.
- f. Lianid 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 (pCi/ml) of gross radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut Riyer. Each batch of radioactive liquid effluent releases is analyzed for gross gamma and ganuna isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity. A quarterly proportional composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55. mmmunas A-3 i
APPENDIX A (Continued) EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT
- 5. BATCH RELF ASES
- a. Liquid There were no routine liquid batch releases during the reporting period.
- b. Gaceous
- 1) Number of batch releases: 6
- 2) To:al time period for batch releases: 1.21E402 hours
- 3) Maximum time period for a batch release: 1.12E+02 hours
- 4) Average time period for batch releases: 2.02E+01 hours
- 5) Minimum time period for a batch release: 8.33E-02 hours The gaseous releases from burning waste oil are treated as either batch or continuous releases based on the total hours of burning in a calendar quarter.
- 6. ABNORMAL RELF ASES
- a. Liquid There were no nonroutine liquid releases during the reporting period,
- b. Gaseous There were no nonroutine gaseous releases (measured) during the reporting period.
One condition was identified during the third quarter that involved small cracks in the Radwaste Building Ventilation exhaust duct downstream of the HEPA filters. Design ventilation exhaust from this area is directed to the plant vent stack for discharge to the environment. The air loss from the cracks was estimated to be much less than 1% of the design flow. The design flow of the duct is 12,200 cfm. Gas samples from both Radwaste Building air and from the ventilation duct system showed no detectable activity down to the Technical Specification gas sample LLD (IE-04 pCi/cc). Smear samples from the ductwork at the edge of the cracks also showed no detectable particulate activity. A review of air monitoring records in the Radwaste Building upstream of the HEPA filters confirmed that there was no history of routine airborne activity in the building that could have lead to any significant dose to the public without having been detected and quantified at the main plant stack. cat cum A-4
l l APPENDIX B l l I LIQUID HOLDUP TANKS Requirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material i contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a description of the events leading to this condition is required in the next Annual Effluent Release Report per Technical Specification 6.7.C. I. Resnonse: The limits of Technical Specifica; ion 3.8.D.1 were not exceeded during this reporting period. i mmwanos B-1
l l APPENDIX C RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement- Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3.9.1, an explanation in the next Annual Effluent Release Report of the reason (s) for delay in correcting the
- ._ inoperability are required per Technical Specification 6.7.C.I.
]
Remonse: Since the requirements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this ! reporting period, no response is required. i l l C-1 mm-nos l
[ APPEliDIX D RADIOACT!VE 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. Ifinoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Annual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.I. Recnnnce: 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.
~
m -no. D-1
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Reanirement: The radiological environmental monitoring prograrr is conducted in accordance with Technical Specification 3.9.C. .With nsk samples no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3,
...- Technical Specifi ition 6.7.C.1 requires the following to be included in the next AnnualEffluent Release Report: (1) identify the cause(s) of the sample (s) no longer being av4'lable, (2) identify the new location (s) for obtaining available replacement samples and (3) include revised ODCM figure (s) and table (s) reflecting the new lacation(s).
l
' Recnonce- No changes were needed in the milk sampling locations specified in Technical Specification Table 3.9.3 due to sample unavailability during the reporting year, j l
i i L l 1 I. l
== manos E-1 l
1 l l APPENDIX F l LAND USE CENSUS Requirement: A land use censos is conducted h 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 coinmitment than the values currently being calculated in Technical Specification 4.8.6.1, Technical Specification 6.7.C.1 requires the , identification of the new location (s) in the next Annual Effluent Release Report. Recnonse: The Land Use Census was completed in the third quarter of 1997. No. locations yielded a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.I. I i_ wmmaine. F-1 l l
l L l- APPENDIX G i-PROCESS CONTROL PROGRAM l Reapirement: Technical Specification 6.12.A.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the Annual ! Radioactive Effluent Release Report for the period in which the cht.nge(s) was made. De< nance: The following changes were made to the Process Control Program (PCP) and issued as Rcvision 6 during this reporting period. l Title Page: Added " Tech. Spec. 6.12(A)(2)" next to PORC and VP/ MOO titles. Added this note after all signature blocks: L Verify or obtain current revision from Document Control
- prior to submitting this document for future revision."
, Section 2: Added the quantification of"<200 mR/hr @ 30 cm" for low I activity cartridge filter elements. Section 3: Revised the definition for a noncorrosive solution. A solution is not unsidered corrosive if the pH is greater than 4.0 and less than 10.0. Section 6: ' Added a reference to AP-0619. I Section 7: Added a reference to AP-0619. Section 8: Added a reference to AP-0619. Page 4: Added the Procedure AP-0619, " Chemical Control /Haz rd l Communication Program." In this revision, Vermont Yankee added criteria for determining if a solution is r corrosive. This change complies with the Barnwell Site Criteria. Other changes in l this revision were administrative in nature. Therefore, the changes implemented in Revision 6 did not reduce the overall conformance of the dewatered spent resins / filter media waste product to existing criteria for solid waste shipments and
- - disposal.
I The revised Process Control Program is attached. The revised Process Control lx Program documents the fact that the change has been reviewed by PORC and l approved by the Manager of Operations (MOO). l f '~ Natrc In the last Supplemental Effluent and Waste Disposal Report (1996),- change pages for Revision 5 to the PCP were included and described. However, the declaration that the changes had been reviewed and approved in accordance with Technical Specification 6.12.A.I.b was inadvertently lef tout. It has been determined that the changes implemented in Revision 5 of the PCP did not reduce the overall conformance of the dewatered spent resins / filter media waste product to existing criteria for solid waste shipments and disposal. matamma G-1
l i, ( VERMONT YANKEE NUCLEAR POWER CORPORATION PROCESS CONTROL PROGRAM REV 6 3/21/97 I
]
Submitted I/ Sf I' hadiation ProTe'Etion Manager 2 Approved Q.MC/'ldbO 97-OZ9 I . P C Vec. 6.12(A)(2))
\
l Approved . MIt A ~(A h g)v' 97 s@ Tank Approved t $$ VP, MOO (Tecl. Spec.'6.12(A)(2)) [ l NOTE . I l' Verify or obtain current revision from Document Control prior to submitting this document for future revision. (ER 96-253) { l~ i
VERMONT YANKEE NUCLEAR POWER CORPORATION PROCESS CONTROL PROGRAM
Introduction:
~
L The Vermont. Yankee Nuclear Power Corporation Process Control Program (PCP) describes the administrative and technical controls on the radioactive waste systems
- which provide assurance that Vermont Yankee meets. federal shipping and burial site -
requirements. l The PCP complies with Technical Specification 6.12 by describing process parameters, controls, tests, sampling and analysis to ensure compliance with to CFR 20,10 CFR i- 71, and 10 CFR 61 Energy,49 CFR 172-173 Transportation, state, and burial site regulation requirements. 1.0 Solidification l! Vermont Yankee Nuclear Power Corporation does not routinely solidify liquid waste. If the use of solidification to dispose of any liquid waste is required,it will be done by an outside vendor under the vendor's PCP. The vendor PCP will be reviewed and l approved by the Plant Health Physicist, the Radiation Protection Manager, PORC and VP, MOO prior to implementation. This review is to identify that there is sufficient supporting documentation of the vendor's PCP to give assurance that the final product will meet all requirements for transport and burial, and that sufficient procedural controls exist to assure safe operations. [TS 4.8.N] 2.0 Qrtridae Filter Elements )[ l-Low activity cartridge filter elements (< 200 mR/hr @ 30cm) will be air dried (-24hr or as determined by the Radwaste Supervisor) and handled as dry active waste. Filters l ! determined to be above the dose limitauons per 49CFR,,will be placed in casks and ( shipped for disposal. t 3.0 Resins Normal operations produce radioactive waste in the form of depleted resins. These
~
. resins are processed in the burial container using a rapid dewatering system (RDS- '
1000) manufactured by Chem-Nuclear Systeras, Inc. [OP 2153] , The system has been tested, by Chem-Nuclear, for certification 'n meeting the Bamwell Site' Criteria and disposal requirement for free standing liquid. These tests are described in Chem Nuc!aar's Topical Report on the RDS-1000 Radioactive Waste > Dewatering System. In addition, to cc,mply with the statement, "Any liquids present in waste packages shall be non-corrosive with respect to'the container," Vermont f Yankee tested the pH of various resin mixtures used by the piant in solution with water. The range was found to be 4.2 - 8.4. A solution is not con $dered corrosive l if the pH is greater than 4.0 and less than 10.0. 1
( A resin sample is taken from each liner prior to shipment. The sample is counted to determine the activity and waste classification. Class A resins that exceed 1.0 yCl/cc of isotopes with greater than 5 year half-lives and all Class B knd C resin: will be h disposed of in an approved High Integrity Container (HIC). Vendor supplied or temporary methods of processing resins may be used in lieu of the above process provided that the vendor or temporary process meets the requirements of quality described above and does not conflict with accepted burial criteria or safety
- requirements. Such methods will be reviewed and approved by the Plant Health Physicist and the Radiation Protection Manager prior to implementation.
4.0 Filter Liners . During refueling outages and normal operation, liquid radwaste processing may require
. use of a decanting filter on the condensate phase separators. A floating suction is used to decant the water and resin into a filter liner. Filtered water is pumped from the liner. The lineris dewatered in accordance with OP 2511 (MOOID9409-03) such that the burial site criterion for free-standing water is met. A resin sample is taken from the s liner and analyzed to determine the activity and waste classification.
5.0
,Drv Active Waste (DAW)
DAW is compacted, as practical, or shipped to a vendor that sorts the material for processing or recycling. All DAW is examined before being compacted or shipped. Any liquids or items found that would compromise the integrity of the package are removed and separated as specified by procedure. [0P 25121 Containers used for DAW shipments meet the criteria of 49 CFR 173.425a. or b. "No leakage of radioactive material," as specified in 49 CFR 173.425.b.1 will be met provided that no radioactive materials in quantities equal to or exceeding those specified in 49 CFR 173.443 are detected on the external surfaces of the package at any time during shipment. . 6.0 Chefatina Acants in order to comply with 10 CFR 20 Appendix F, chelating agents are c'ontrolled by the l plant chemistry department using procedure AP 0620 and AP 0619. 7.0 Exciosive Waste. No waste capabie of detonation or of explosive decomposition or reaction will be ._ l disposed as per 10 CFR 61.56(a)(4). Refer to MSDS via AP 0620 along with l AP 0619. 8.0 Toxic Waste No waste capable of generating toxic gases, vapors, or fumes will be disposed as per , [ 10 CFR 61.56(a)(5). Refer to MSDS via AP 0620 along with AP 0619. ! 2
9.0 Pyronhoric Waste . No waste that is pyrophoric will be disposed as per 10 CFR 61.56(a)(6). Refer to MSDS via AP 0620. 10.0 Hloh Inteority Containers (HICs) l l_
~ Vermont Yankee Nuclear Power Corporation has contracted with various suppliers of approved HICs. South Carolina has approved PCPs for HICs used by Vermont Yankee.
l ~Ar.y Hic Vermont Yankee may choose to use at some future time, will meet all applicable requirements. 11.0 Waste class Determination Along with an approved outside laboratory, Vermont Yankee periodically performs laboratory analysis on all waste streams to determine the activity of radionuclides listed in Tables 1 and 2 of 10 CFR 61. Correlation analysis verifies that the relative concentration of each radionuclides, with respect to the overall activity in a given c Vermont Yankee waste stream, remains constant over time. A set of scaling factors is determined which allows the activity of 10 CFR 61' radionuclides to be estimated using the results of gamma spectronistric analysis or direct gamma dose rate
- . measurements.
For resin wastes, analysis is performed on samples of each sour:e of resin comprising the contents of a burial container. Scaling factors are applied to the activity of I 1 radionuclides identified by gamma spectrometry analysis to determine the activity of those radionuclides which are not detected in the gamma spectrum. l l ! For DAW, dose rate-to-curie conversion calculations are performed to determine the total activity present in a container. Scaling factors are applied to the container's total curie content to determine the activity of individual radionuclides. Specific procedures for determining 10 CFR 61 scaling factors are contained in OP 2527," Sampling and Analysis for Radweste Classification." Once the, activity of each .' radionuclides in a burial container is estimated, the waste classification is derived using methods required by 10 CFR 61. Specific procedures for waste class de, termination are contained in AP 0504, " Shipment of Radioactive Material." t 1'2.0 Mixed Wasta
~
No mixed waste will be disposed as per 10 CFR 61.56(a)(8) unless properly treated. Refer to MSDS via AP OG20. l \. . l 1 3 l l
o R PROCEDURES WHICH IMPLEMENT THE PCP
- 1. AP 0504 Shipment of Radioactive Materials
- 2. OP 2511 Radwaste Cask / Liner Handling
- 3. OP 2527 Sampling and Analysis for Radwaste Classification
. 4. OP 2151 Liquid Radweste
- 5. - OP 2153 Solid Radwaste
, 6. AP 0620 , Chemical Material Use
- 7. OP 2512 Radwaste Drum, Box and Sealand Handling 8.- . AP 0619 Chemical Control / Hazard Communication Program
[ l e O
,- 4
I APPENDIX H OFF-SITE DOSE CALCULATION MANUAL I 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 I Annual Radioactive Effluent Release Report for the period in which the change (s) was made effective. Response- Revision 21 to the Off-Site Dose Calculation Manual was made during this reporting period. The major changes included in Revision 21 to the ODCM are: (1) A new Appendix F has been added. The NRC granted the plant permission for the on-site disposal of slightly contaminated silt in response to our request filed under 10CFR20.2002. Currently, there is an estimated 14,000 cubic feet of cooling tower silt. This silt contains low levels of Co-60 and Cs-137. Dose assessments for this material show that it can be disposed of on-site in the same manner as that already approved for contaminated septic waste. The permission granted by the NRC requires that the NRC Safety Evaluation for silt disposal be added to the plant's ODCM prior to the implementation of any disposal operation. This amendment to the ODCM fulfills that requirement. Appendix F also includes a copy of our 10CFR20.2002 request and dose analysis that supports this on-site disposal. (2) A new Appendix G has also been added. This appendix contains a lidng I of the MPC values which originally was part of the 10CFR20 before f he change to ECL values. MPC values have been used and accepted as licensing conditions for the control of radioactive materials in situations other than those directly covered by the requirements of the regulations. I One example is the on-site disposal of septic waste (ODCM Appendix B) which uses MPC values as one of the criteria for determining acceptability for land spreading of contaminated material. With the final publication of I the revised 10CFR20.1001-20.2401, the original MPC tables of the old 10CFR20 are no longer in print. As such, Appendix G to the ODCM was added to provide a reference source for the concentration limits for those conditions that still refer to them. (3) The NRC allows the instantaneous radioactive liquid effluent concentrations discharged to unrestricted areas to be ten times the ECL ,I values listed in Appendix B to the new 10CFR20.1001-20.2401. This ) ! change, allowing the effluent concentrations to be ten times the ECL I E values, reflects that the ECL numbers are actually annual average B concentrations, not instantaneous limits. By allowing the instantaneous concentrations in effluents to be ten times the absolute values of the ECL provides flexibility in plant discharge operations. This is equivalent, on a I dose basis, to the old MPC limits that were also applied on an instantaneous basis by Technical Specifications. Over a year, the average l' ECL values must not be exceeded, usmmmu H-1 I m
I t APPENDIX H l (Continued) OFF-SITE DOSE CALCULATION MANUAL i l Changes to the ODCM to establish the method for calculating acceptable liquid effluent concentrations and monitor alarm setpoints for batch release pathways have been made. For continuous discharge pathways, i.e., the service water, the alarm setpoint has been kept the same despite changes to allow higher effluent concentration (a factor of ten). This is done to insure that potentialleaks into a normally clean system will set off a monitor alarm when the annual average requirements of 10CFR20 are exceeded. (4) Minor editorial changes have been added to reflect: (a) that the Chemistry Manager is now assigned responsibility for the implementation of septic waste disposal in place of the Senior Environmental Program Manager, (b) a correction of a typographical error on Page 5-15 that changes 500 rem /yr to 500 mrem /yr, and (c) consideration ofinstrument uncertainty when effluent monitor alarm setpoints are calculated using plant procedures. The above changes are provided in response to NRC licensing conditions. The dose methodologies have not been changed. Changes to the setpoint methodology, which include an additional factor of ten on the instantaneous ECL limit, reflect the permission granted by the NRC and restore the dose basis (i.e., 500 mrem /yr) for the setpoint criteria. It is therefore determined that these changes will maintain the level of radioactive effluent control required by 10CFR20.1302,40CFR190,10CFR50.36a, and Appendix I to 10CFR Part 50. These changes do not adversely impact the accuracy or reliability of the effluent dose or setpoint calculations. The revised pages from Revision 21 to the ODCM are attached. t cwmuunmi H-2
I l I k I VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCLUATION MANUAL REVISION 21 l { i l 1 J
. I I
i i Riviewed : V32 44c1 M7d 97665' f//3/f7 Plant Operations Review Commit %e Date Approved: R "K
~
la O P Manager Date Approved: b Sr. Vice President, Oberations _O Date 3 l i L _ _ ___--.- _______ ._,_ _ . _ . _ __
LIST OF AFFECTED PAGES
- l. .
Pace Revision Date
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3 19 15 07/08/93 3-20 20 07/30/96 3 21.to 3-50 17 05/31/94 3 51 20 07/30/96 3 52.. 18 07/20/95 3 53 to 3-.57 17 05/31/94 3 58 20. 07/30/96 3 59 15 07/08/93 41 20 07/30/96 4 la 20 07/30/96 Revision 21- Date 08/14/97 11-
l . l LIST OF AFFECTED PAGES (Continued) l Paqg, Revision Date 41b 19 11/01/95
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6-10 20 07/30/96
-R-1 17 05/31/94 A-1 to A 2 15 07/08/93 A3 20' 07/30/96 A4 .
17 05/31/94 A 5 to A-8 20' 07/30/96 _A-9 -17 05/31/94
'A 10 to A-15 20 07/30/96
~
A-16 to'A-21 17 05/31/94
- - 'A-22 to A-23 20 -07/30/96 A-24. 17 05/31/94 l
-B-1.to C 39 9 03/02/90 0 l'to D-3 16 10/28/93 p E-1 to E-8 20 07/30/96
. All F 21 08/14/97 All . G 21 08/14/97 L
I o i Revis' ion '21 Dete 08/14/97
-iii-
l' l i i l > 3. 7. Method to Calculate the Gamma Air Dose from Noble Gases . . 3-30 l 3.8 Method to Calculate the Beta Air Dose from Noble Gases . . . 3-34 3.9 Method to Calculate the Critical Organ Dose'from lodines. Tritium and Particulate . . . . . . . . . . . . . . . . . 3-38
.3.10 Receptor Points and Annual Average Atmospheric Dispersion .
Factors for.Important Exposure Pathways . . . . . . . . . . 3-45 3.11 Method to Calculate Direct Dose From Plant Operation . . . . 3-51 3.12i cumulative Doses . . . . . . . . . . . . . . . . . . . . . 3 59 4.'O- ENVIRONMENTAL MONITORING PROGRAM ,................ 4-1 ] 5.0 SETPOINT DETERMINATIONS . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 . Liquid Ef fluent Instrumentation Setpoints . . . . . . . . . . 5-2 5.2 Gaseous Effluent Instrumentation Setpoints
. . . . . . . . 5-11 6.0 LIOUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS. AND RADWASTE. TREATMENT SYSTEMS .................... 6-1 6.1 In-Plant Radioactive ~ Liquid Effluent Pathways . . . . . . . . 6-1 6.2 In-Plant Radioactive Gaseous Effluent Pathways ..... . . 6-4 REFERENCES R1 F APPENDIX A: Method 1 Example Calculations A-1 l APPENDIX B: Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site at Vermont Yankee B-1 APPENDIX C: Response to NRC/EG&G Evaluation of ODCM Update Through Revision'4' C-1
- APPENDIX D
- Assessment of Surveillance Criteria for Gas
' Releases from Waste Oil incineration 01 F
APPENDIX E: NRC Safety Evaluation for Disposal of Slightly , i Contaminated Soil On-Site at VY (Below the Chem l L Lab Floor) - TAC No. M82152 E1 i l:
- APPENDIX F: Approval Pursuant'to 10CFR20.2002 for Onsite Disposal of Cooling Tower Silt F-1 APPENDIX G: Maximum Permissible Concentrations (MPCs) in Air and Water Above Natural Background Taken from
.10CFR20.' to 20.602. Appendix B G-1
- LRevision'~ 21 Date 08/14/97 l -vil-l
> i _J
1.0 INTRODUCTION
This ODCM (Off-Site Dose Calculation Manual) provides formal and approved methods for the calculation of off-site concentration, off-site doses, and effluent monitor setpoints in order to comply with the Vermont Yankee Technical Specifications 3.8/4.8 and 3.9/4.9, hereafter referred to as the Radiological Effluent Technical Specifications. The ODCM forms the basis for plant procedures and is designed for use by the procedure writer. In addition. the ODCM will be useful to the writer of periodic reports required by the NRC on the dose consequences of plant operation. The dose methods contained herein follow accepted NRC guidance for calculation of doses necessary to demonstrate compliance with the dose objectives of Appendix ! to 10CFR50 (Regulatory Guide 1.109) unless otherwise noted in the text. Demonstration of compliance with the dose limits of 40CFR190 (see Technical Specification 3.8.M) will be considered as demonstrating compliance with the 0.1 rem limit of 10CFR20.1301(a)(1) for members of the public in unrestricted areas (Reference 56 FR 23374, third column). It shall be the responsibility of the Chemistry Manager ard Radiation Protection Manager to ensure that the ODCM is used in the performance cf the surveillance requirements of the appropriate portions of Technical Specifications. The administration of the program for the onsite disposal of slightly contaminated waste, as described in Appendices, is also the responsibility of the Chemistry Manager. All changes to the ODCM must be reviewed by PORC and approved by M00, in accordance with Technical Specification 6.13, prior to implementation. All
. approved. changes shall be subnitted to the NRC for their information in the Annual Radioactive Effluent Report for the period in which the change (s) was made effective. The plant's Document Control Center (DCC) shall maintain the current version of the ODCM and issue under controlled distribution all approved changes to it.
Revision 21 Date 08/14/97 1.1
[ r . . . c t r . . o o c q y r t r y m m
/ q i a a a a . .
t C a . r r i p n n a n n r y y m i i n i i y / / i d n i / m m L ' m m i m m m e e e r e m e e e r r 0 r m e r r r m m 1 m m er r m m m m 0 0 x 5 0 m 6 2 0 0 0 0 . . 0 0 . 0 0 5 1 2 1 3 5 1 0 5 3 1 0 s s s s s s s s s s s s n o i
)
t a u c d 9 8 60 i o 1 2 1 3 1 3 53 73 1 4 f h - - - - - - - - - - - - i t 2 2 3 3 3 3 33 33 33 c e e M . . . . . . . . . . . . p g q q q q q qq qq qq S r E E E E E EE EE EE l a s c n o i i m e 8 n t o l h e r > c au f onl f b o e 2 1 T a E si o ob e N md
/
1 1 t ntN t m onT
. n a y oa a o r a 1 e n r i rg R r f h i
u t o tt n f mt E l g cni s e e e eui L f n e a ed a s s s e t i w B f e t rcu G n o o o t at A E m a F nl o D D D a Ri s T e C oc ei s R r e l l p eC x l t y e y e ye eT t a h E b a d s d s d s e s a c Im t t[ or o o o o oa s o .l i n N t B D B D BG o D s u g f es] n D e c o dn out s l e l n l n l e s nni l l i e a c a a a a al ne ait s g g o a mf ms uf i a t n oo t o r t o r t b i s oo k a gd r y r oaa i d SELG TC T O T O TN SG OI PD a R f e o y s
~
y e t o s i D r o l a D i s m b t m t t ea n u n n t r e S n en e s e u o uo u a p l l i l i l wO f ) at f t f d f d ca f a f at E e i c E r E R n u ni t e s n hf d n d d m u i ci i e i i t o t ec uc u ua ee n T e qn q qe st o a a C _ p i o i ir _ S LC L LT GR ( 1 1 1 1 1 _ E E A. B. C. . . 8 8 8 8 R. . . . 3 3 3 3 3 l
TABt.E 1.1-2 1 Summary of Methods'to Calculate
-Unrestricted Area liauid Concentrations 1
. Equation Reference
~
Number Category quation Section 2 : Sum of the Fractions of gas C, 21 l Coinbined Effluent F 3 -E' ECLi Concentrations in Liquids ~ [Except Noble Gases] 2 2- Total Activity of Dissolved NG = ' Ci ' NG 2.1 and Entrained Noble Gases Ci =ECi
-from'all 5+.ation Squrces ' '
52E-04 l
- l
, < 1 Revision 21 Date 08/14/97 _ sus
l
- f. '2.0 ' METHOD TO CALCULATE OFF-SITE 'll0U10 'CONCENTRAT10NS Chapter 2 contains the basis for plant procedures that the plant operator requires to meet Technical Specification 3.8.A.1 which limits the total fraction of combined effluent concentration in liquid pathways.
l ' excluding noble gases, denoted here as tf"G. at the point of disch'arge at any f"G .is limited to less than or equal to ten,
~
-time (see Figure 6-1), i i.e.. l ENG I Fi s10.
The total concentration of all dissolved and entrained noble gases at thepointofdischargefromallstationsources,denoteddf.islimitedto
- 2E-04 pCi/ml. i.e..
d[f.2E-04pCi/ml. Evaluation of fNG and Cf is required Concurrent with the sampling and i analysis program. in Technical Specification Table 4.8.1. 2.1 MethodtoDetermine6[G and d,G
' Determine the total fraction of combined effluent concentrations at the point of discharge in liquid pathways (excluding noble gases), denoted f"G. i
.and: determine the total concentration at the point of discharge of all dissolved and entrained noble gases in liquid pathways from all station sources, denoted d[. as follows:
C p, s ,, g s10 t ECLt q (2 1) > f pCi/ml' C1/ml, and: 1 L , l 1
;..Rev i s i on 21 -Date 08/14/97
, 2-1
G C "G = E 1 Ci "i s 2E-04 (2-2) (pCi/ml) ( Ci/mi) ( Ci/mi) where: F!NG
=
Total sum of the fractions of each radionuclides concentration in liquid effluents (excluding noble gases) at the point of discharge to an unrestricted area, divided by each radionuclides *s ECL value. Cg p
= Concentration at point of discharge to an unrestricted area of radionuclides "i", except for dissolved and entrained noble gases, from any tank or other significant source. p.
from which a discharge may be made (including the floor drain sample tank, the waste sample tanks the detergent waste tank and any other significant source from which a discharge can be made) (pCi/ml). This concentration can be calculated from: Cpi - CTK1 x FTK /EIDIL + ITK] where: C yg3 equals the concentration of radionuclides i in the tank to be discharged ( Ci/ml): F OIL is equal to the dilution flow provided by the liquid radioactive waste dilution pumps (20,000 gpm); F TK equals the liquid waste discharge pump flow rate which regulates the rate at which liquid from a l waste collection tank is discharged (gpm). l i
= J ECL, Annual average effluent concentration limits of radionuclides "1", except for dissolved and entrained noble gases, from 10CFR20.1001 20.2401, Appendix B. Table 2, Column 2 4 (pCi/ml).
C$G
= Total concentration at point of discharge to an unrestricted area of all dissolved and entrained noble gases in liquid pathways from all station sources (pC1/ml).
C$I
= Concentration at point of discharge to an unrestricted area l of dissolved and entrained noble gas "i" in liquid pathways from all station sources (pCi/ml).
t L Revision 21 Date 08/14/97 2-2
i Under expected or anticipated ~ operating conditions, the concentration at any time of radionuclides at the point of discharge from the service water effluent pathway to 'an unrestricted area will not exceed ten times the effluent concentration values of 10CFR20.1001-20'.2401, Appendix B. Table 2 Column 2.
'2.2.3 Circulating Water Pathway The circul'ating water pathway shown on Figure 6-1, flows from the intake structure through the condenser and the discharge structure. Under normal l ' operating conditions, the water in this line is not radioactive. For this reason, the circulating-water line is not sampled routinely but it is
- l. monitored continuously by the discharge process monitor (No.17/359) locateu in the discharge structure.
l The alarm setpoint on the discharge process monitor is set at a level which is'three times the background of thL instrument. The circulating water is sampled if the monitor is out of service of if the alarm sounds. L .Under normal operating conditions, the average concentration of radionuclides at the point of discharge from the circulating water pathway to an unrestricted area will not exceed the annual effluent concentration limits l- in 10CFR20.1001-20.2401. Appendix B. Table 2. Column 2. i L Revision 21 Date J /14/97 24
- f. __
5.1 Liauid Effluent instrumentation Setooints Technical Specification 3.9.A.1 requires that the radioactive liquid effluent instrumentation in Table 3.9.1 of the Technical Specifications have alarm'setpoints'in' order to ensure that Specification 3.8.A.1 is not exceeded. Specification 3.8. A.1 limits the activity concentration at any time in liquid
- effluents to. ten items or less the effluent concentration values in ,
. Appendix B, Table 2 Column 2 of 10CFR20.1001 through 20.2401, and a total noble gas concentration limit of 2E 04 pCi/ml.
.5.1.11'Liouid Radwaste Discharoe Monitor (RM-17-350)
-The sample tank' pathways shown on Figure 6-1 are monitored by the liquid ,
radwaste discharge monitor (RM-17-350). Periodic batch releaser may be made from.the waste sample tanks. detergent waste tank or floor drain sample tank. 5.1.1.1 : Method to Determine the Setooint of the liauid Radwaste Discharge Monitor (RM 17-350) The. instrument response (in counts per second) for the limiting concentration at the point of discharge is the setpoint, denoted R setpoint, and
-is determined as follows:
R 3 ,t,, int -
- 0F min (5-1)
(cps) (#) ( cps 4 ) (gQ) C1 mi k!here: OF - b- Dilution factor (as a conservative measure, Fm a DF of at least 1000 is used) l (dimensionless). (5-2) l- F, - Flow rate past' monitor (gpm) l l- F d
- Flow rate out of discharge canal (gpm) 0F ein - Minimum allowable dilution factor (dimensionless) 0.1 E EC "Li (5-3) l 1 i Revision 21- Date' 08/14/97 g 52 !
I E 1 C,i - 2.15E-05 + 7.48E-05 + 2.56E-05 C1 s ( C1) ( pC1 ) C1 ( ml ) mT mi ( ml ) 1.22E-04 Ci \ ( ml ) 0F,in = 0.1 E EC (5-3) l Ci -ml ( mi-pC1 )
- 0.1 2.15E-05 . 7.48E-05 . 2.56E-05 ' ;
, 9E-07 1E-06 3E-06 .
g pCi-m1 Ci-ml Ci-ml ( mi -pCi ) ( ml- Ci ) ml- Ci )
- 10.7 I The minimum dilution factor. OFini n , needed to discharge the mixture of radionuclides in this example is 10.7. As a conservative measure, an actual l dilution factor. OF. of 1.000 is usually used. The release rate of the floor drain sample tank may be adjusted from 0 to 50 gpm and the dilution pumps can supply up to 20.000 gpm of dilution water. With the dilution flow taken as 18.000 gpm the release rate from the floor drain sample tank may be determined as follows:
" Fd
'f m g (5-4)
(gpm) (gpm) 18.000 gpm
. - 18 gpm 1.000 Revision 21 Date 08/14/97 es
i Under these conditions, the setpoint of the liquid radwaste discharge Gonitor is: . OF (5-1)
- j. Rsetpoint " "i 0F,in
( cps-ml ) C1 (cps) (#) g ~il i ;. Ci m ,)
,1,000 4.9E+06 1.22E-04 10.7 . !
'(cps)'- (#) ( cps-ml ( pCi )
pCi ml
- 55,869 cps j In this' examp'le, the calcula' ted limiting count rate alarm point for the liquid radwaste discharge monitor would be 55,869 cps above background. Plant procedures apply administrative-limits below the calculated limiting count rate to account for.such elements as instrument' uncertainty and~early alarm
-warning before exceeding Technical Specification limits.
5.1.1.3 Basis for the t.iouid Radweste 01scharoe Monitor Setooint The liquid radwaste discharge monitor setpoint must ensure that
- Specification 3.8.A.1 is not exceeded for the appropriate in-plant pathways.
.The liquid radwaste. discharge monitor is placed upstream of the major source of. dilution flow and responds to the concentration of radioactivity discharged-
- l. 'in batch releases as follows:
Sg (5 5) R' -Et C,g. i
-(cps): (Emi ) (cps-m1) C1 l
Where:
'R == Response of the monitor (cps)
- Detector counting efficiency for radionuc1'1e "i" Su (cps /(pCi/ml))
-C,n
= Activity concentration of radionuclides *i" in mixture at the monitor (pCi/mi)-
Revision: 21 Date 08/14/97 e
The detector calibration procedure establishes a counting efficiency for a given mix of nuclides seen by the detector. Therefore, in Equation 5-5 one may substitute Si for Sg. where Si represents the counting efficiency determined for the current mix of nuclides. If the mix of nuclides changes significantly, a new counting efficiency should be determined for calculating the setpoint. R - Si }[ 1 C,, (5-6) (cps) ' cps-ml' 'gCi ' Ci , ml , The effluent concentration for a given radionuclides must not exceed 10 times the 10 CFR Part 20 ECL at the point of discharge to an unrestricted area at any time. When a mixture of radionuclides is present, the concentration at the point of discharge to an unrestricted area shall be limited as follows: C di s10 (5-7) I
][, ECL, g pCi-ml) ml- Ci Where:
C d1 - Activity concentration of radionuclides "i" in the mixture at the point of discharge to an unrestricted area ( Ci/ml) ECL, - Effluent concentration limit for radionuclides "i" from 10CFR20.1001-20.2401, Appendix B, Table 2, Column 2 (pC1/ml) The activity concentration of radionuclides "1" at the point of discharge is related to the activity conceritration of radionuclides "i" at the monitor as follows: F* C,- o C,i q-d (5-8) (pCi) ( pCi ) (gpm) m1 mi gpm Revision 21 Date 08/14/97 5-6
l l l Where: i C, d
=
Activity concentration of radionuclides "1" in the mixture at the point of discharge ( Ci/ml) F, - Flow rate past monitor (gpm) - Fd - Flow rate out of discharge canal (gpm) Substituting the right half of Equation 5 8 for C ,a in Equation 5-7 and solving for F d/Im yields the minimum dilution factor needed to comply with Equation 5-7:
"i" ECL
- 10 (5-3) l
'gpm' 'pCi -mi '
s gpm, ml- Ci j , Where: , Fd - Flow rate out of discharge canal (gpm) F, - Flow rate past monitor (gpm) C eg = Activity concentration of radionuclides "i" in mixture at the monitor (pCi/ml) ECL, Effluent concentration limit for radionuclides "1" from 10CFR20.1001-20.2401, Appendix B. Table 2, Column 2 ( Ci/ml) 10 - The instantaneous concentration multiplier allowed by Technical Specification 3.8.A.1 If F d/f mis less than DF,93, then the tank may not be discharged until either Fdor F, or both are adjusted such that: Fo
--. 2 0Fn ni (5-3)
F. (gpm) gpm s Revision 21 Date 08/14/97 - 5-7
l
} bS#IOF'is i
i - (1.03E+04)(1.06E-02) + (4.73E 02)(1.43E-02)
. i I + (2.57E+02)(1.28E-02) + (1.20E+02)(2.35E 03)
+ (3.70E+02)(3.24E-03) + (1.97E+01)(5.58E-04)
- 1.14E+02 ( Ci-mrem-sec/sec pCi-yr) 1.14E+02 0F 1.15E+04
- 9.91E-03 (mrem-sec/ C1-yr) spt y 7
R - 3,000 5 _ skin 9 _F OF'c
- (3,000) (3E+07) 1 I (7.32E+07) (9.91E-03) ,
- 124.067 cpm b
The setpoint, R,pt. is the lesser of R[pt andRlptkI" . For the noble D kin gas mixture in this example R[pt is less than Rlpt , 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 monicors should each be set at some administrative value below 39,348 cpm above background to provide conservatism for such issues as instrument uncertainty and secondary releases from other locations. As an example, a conservative value might be based on controlling release rates from the plant in order to maintain off-site air concentrations below 20 x ECL when averaged over an hour, or to account for
- other minor releases from the waste oil burner. For examDle, if an administrative limit of 70 percent of the Technical Specification whole body dose' limit 500 mrem /yr (39,348 cpm) is chosen. then the noble gas monitor l alarms should be set at no more than 27,543 cpm above background (0.7 x 39.348 - 27,543).
3.2.1.3 Basis for the Plant Stack and A0G System Noble Gas Activity Monitor Setpoints The setpoints of the plant stack and A0G systen noble gas activity monitors must ensure that Technical Specification 3.8.E.1.a is not exceeded. Sections 3.4 and 3.5 show that Equations 3-5 and 3-7 are acceptable methods for determining compliance with that Technical Speci fi cati on. Which equation (i.e., dose to total body or skin) is more limiting depends on the noble gas mixture. Therefore, each equation must be considered separately. The , Revision 21 Date 08/14/97
APPENDIX F APPROVAL PURSUANT TO 10CFR20.2002 FOR ONSITE DISPOSAL OF COOLING TOWER SILT Revision 21 Date 08/14/97 F-1
..~
f $ UNITED STATES j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 c001
~ - - - -
June 18, 1997 ns
%*** tay gn85 La f f b b b ,!TE 1
41 T M JUN 2 319a7 .l.i Mr. Donald A. Reid 1- - ~a Vice President, Operations D.A. fi3D n nkee Nuclear Power Corporation gyy~g Brattlebe . :, VT 05301
SUBJECT:
REVISED SAFETY EVAlliATION - APPROVAL PURSUANT TO 10 CFR 20.2002 FOR l ONSITE DISPOSAL OF COOLING TOWER SILT - VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. M96371)
Dear Mr. Reid:
By letter dateu August 30, 1995, Vermont Yankee Nuclear Power Corporation (VYNPC) requested approval, pursuant to 10 CFR 20.2002, for the onsite disposal of slightly contaminated silt material removed from Vermont Yankee Nucleir Power Station's (Vermont Yankee's) cooling towers. In a safety evaluation (SE) dated March 4,1996, the NRC staff approved the proposed silt disposal. However, because of discrepancies VYNPC identified between the safety e. valuation and VYNPC's letter of August 30, 1995, VYNPC postponed l implementation of the silt disposal until resolution of the discrepancies. By letter dat'ed August 2,1996, VYNPC informed the NRC staff of the discrepancies and requested that the SE be revised accordingly. Recognizing the discrepancies, the NRC staff has prepared the enclosed SE to resolve the discrepancies and to replace the SE of March 4,1996.
'The NRC staff's approval of VYNPC's silt disposal request is granted provided g the cnclosed replacement SE is permanently incorporated into Vermont Yankee's Offsite Dot.e Calculation Manual as an appendix. Any modification to the proposed action that may be considered in the future must have prior NRC-staff appr val.
Pursuant to the provisions of 10 CFR Part 'il, the Commission has published in the Ee.dttral Egoister an Environmental Assessment and Finding of No Significant Impact (61 FR G562). l Revision .21 Date R/14/97 Page F 2 l l
D. Reid .. . If you have any further questions regarding this matter, please contact l Mr. Kahtar. Jabbour at (301) 415-1496.- Stricerely, . 9mW : -
. Patrick D. Milano, Acting Director Project Directorate I-3 Division.of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosure:
Safety Evaluation cc w/ enc 1: See next page Revision .21 Date 8/l4/97 P8Ee F-3
1 Vemont Yankee Nuclear Power Vemont Yani.ee helear Power Station Corporation - CC: l Mr. Peter LaPorte, Director Regional Administrator, Region I ATTN: James Muckerheide U. S. Nuclear Regulatory Comission Massachusetts Emergency Management 475 Allendale Road Agency King of f curria, PA IM06 400 Worcester Rd. P.O. Box 1496 R. K. Gad, sti Framingham, MA 01701-0317 R: pes & Gray' One International Place Mr. Raymond N. McCandless . Boston, MA 02110-2624 Vermont Division of Occupational and Radiological Health Mr. Richard P. Sedano, Commissioner Administration Building Vermont Department of Public Service Montpelier, VT 05602 120 State Street, 3rd Floor Montpelier, VT 05602 Mr. J. J. Duffy Licensing Engineer Public Service Board Vermont Yankee Nuclear Power State of Vermont _ Corporation 120 State Street 580 Main Street Montpelier, VT 05602 Bolton, MA 01740-1398 Chairman, Board of Selectn.en Mr. Robert J. Wanczyk Town of Vernon Director of Safety and Regulatory P.O. Box 116 Affairs Vernon, VT 05354-0116 Vermont. Yankee Nuclear Power Corp.
. . Ferry Road Mr. Richard E. McCullough Brattleboro, VT 05301 Operating Experience Coordinator Vermont Yankee Nuclear Power Station Mr. Ross B. Barkhurst, President P.O. Box 157 Vermont Yankee Huclear Power Governor Hunt Road Corporation Vernon, VT 05354 Ferry Road ,
Brattleboro, VT 05301 G. Dana Bisbee, Esq. Deputy Attorney General- Mr. Gregory A. Maret, Plant Manager 33 Capitol Street Vemont YLnkee Naclear Power Station 0:ncord, NH .03301 v937 P.O. Box 157
- Governor Hunt Road Resident Inspector Vernon, VT 05354 V;rmont Yankee Nuclear Fower Station U.S. Nuclear Regulatory Comission P.O. Box 176 Vernon, VT 05354 i Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Revision E Date R/14/97 Page F-4
b
/
1 gutoy [ % UNITED STATES g g NUCLEAR REGULATORY COMM!SSION WASHINGTON, D.C. 20555 4 001 g ! .. .
'oo ,,,*
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR _BfGULATION RELATED TO ONSITE DISPOSAL OF SLIGHTLY CONTAMINATED COOLING TOWER SILT VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
1.0 INTRODUCTION
By letter dated August 30, 1995, Vermont Yankee Nuclear Power Corporation (VYNPC) requested approval for the onsite disposal of slightly con'aminated silt material removed from Vermont Yankee Nuclear Power Station's (nrmont Yankee's) ccoling towers. In a safety evaluation (SE) dated March 3,1996, the NRC staff approved the proposed silt disposal. However, because of discrepancies between the SE and VYNPC's letter of August 30, 1995, VYNPC postponed implementation of the silt disposal until resolution of the discrepancies. By letter dated August 2,1996, VYNPC informed the NRC staff of the discrepancies and requested that the SE be revised accordingly. Recognizing tie dis:repancies, the NRC staff has prepared this SE to resolve the discrepancies and to replace the SE of March 4,1996.
2.0 BACKGROUND
I VYNPC has previously obtained NRC staff approval of the onsite disposal of very-low-level radioactive material similar to the proposed silt disposal. By letter dated June 28, 1989, VYNPC proposed the onsite disposal of slightly c:ntaminated septic waste material by land application at Vermont Yankee. By - letter dated August 30, 1989, the NRC staff approved this request pursuant to 10 CFR 20.302 (now 10 CFR 20.2002). The NRC staff considered this site-specific application for Ven:. ant Yankee to have insignificant radiological impact because the propos4d septic waste material disposal involved licensed ht rial containing ,less than 0.1 percent cf the radioactive materiel, primarily cobalt-60 and cesium-137, ~already considered acceptable in the final Environmental Statement (FES) of July 1972, and involved exposure pathways much less significant than those in the FES. In addition, the proposed septic waste material disposal satisfied the following applicable boundary conditions for the disposal of licensed material:
- a. The whole body dose to the hypothetical maximally exposed f individual must be less than 1.0 mrem / year.
i l l I l fhMnm M hmWi)02@ Pagge F 5 l
.. . b. Doses to the whole body and any organ of an inadvertent
> intruder from the probable pathways of exposure are less than 5 mrem / year.
- c. _The disposal must be at the same site.
Following the NRC staff's approval on August 30, 1989, VYNPC implemented the disposal of the cont'aminated septic waste material as proposed. By letter dated August 30, 1995, VYNPC requested that the previous authorization for the onsite disposal of very-lew-level radioactive material be amended to permit the onsite disposal of slightly contaminated silt ' caterial, within the boundary conditions of the previously approved septic waste material disposal. 3.0' EVALUATION In its letter of. August 30, 1995, VYNPC stated that the proposed silt disposal method is the same as the previously approved septic waste disposal method, and utilizes land spreading in tha same onsite areas approved for septic waste disposal. The volume of silt proposed for onsite disposal consists of 14,000 cubic feet (396 cubic meters) accumulated through August 1995 plus approximately 4,000 cubic feet (113 cuoic seters)- to be removed from the cooling towers during each 18-month operating cycle. The activity. contained in the currently accumulated silt, based on samples taken by VYNPC in Jue - 1995, is 0.193 mil 11 curies,-principally from 0.034 millicuries of cobebdC and 0.159 millicuries of cesium-137. The activity contained in the at,ditional silt to be removed from the cooling towers each 18-month operating cycle is anticipated to be 0.059 millicuries, principally from 0.012 millicuries of c:balt-60 and 0.047 mil 11 curies of cesium-137.
'"YMPC's radiological' assessment enclosed with its August 30, 1995, ' letter duanstrates that,the combined radiological impact for all onsite disposal operations, the proposed disposal _ of silt ~and the previously approved-disposal af septic waste material, will continue to meet the applicable boundary cenditions (given above) for the disposal of licensed material. Therefore,
.the proposed onsite disposal of slightly contaminated silt is acceptable.
As discussed in VYNPC's letter of August 2,1996, if the onsite disposal of cooling tower silt or septic waste material would result in exceeding the
' applicable boundary conditions (given above), then VYNPC must ootain prior NRC
_ staff approval of the disposal. In addition, VYNPC made the following
- commitments
- a. . VYNPC will report in the Annual Radiological Effluent Release Report a list of: the radionuclides present and the total hf radioactivityTassociated with the onsite disposal activities at. Vermont Yankee.
l.
. Revision .2.1, Date 8/14/97 Page F-6
i
- b. VYNPC will maintain records of radionuclides concentrations and
- b. total activity associated with onsite disposal activities at Vermont Yankee in accordance with 10-CFR 50.75(g).
4.0: CONCLUSION
' The NRC staff finds that the radiological conditions at the Vermont Yankee site (see attachment) that would result from the onsite disposal of slightly contaminated silt material, .as proposed by VYNPC pursuant to 10 CFR 20.2002, and the previously approved onsite disposal of slightly contaminated septic waste material, are within the applicable boundary conditions' (given above) for the disposal of licensed material. Therefore, the proposed onsite disposal of sliohtly contaminated silt removed from Vermont Yankee's cooling
. towers is acceptable.
VYNPC is required to permanently incorporate this SE into the Vermont Yankee
'Offsite Dose Calculation Manual as an' Appendix to document the the radioactive p eaterial .onsite disposal activities approved for Vermont Yankee, and VYNPC's related commitments regarding reporting and record keeping. Any additional modification of VYNPC's disposal activities which go beyond those proposed in
{ the August 30, 1995, submittal, and are not addressed above'must have prior NRC staff approval. In addition, any onsite disposal of cooling tower silt or septic waste material that would result in exceeding the applicable boundary conditions. (given above), must also have prior NRC staff approval. Principal Contributors: J. Minns D. Dorman C. Harbuck Date: June 18, 1997
Attachment:
. Vermont Yankee Site Area Map 9 r p l ! Revision ll Date RIN/97 Page F-7
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l 1 ERMONT YANKEE RES301S 3 F"I PUCLEAR POWER CORPORATION LM KW Cws&D
\
i y Ferry Road, Brattleboro. VT 05301-7002 i j mwo N ENGINEERING OFFICE
- 580 MAIN STREET BOLTON. MA 01740 (508) 779 4 711 August 30,1995 BVY 95 - 97 United States Nuclear Regulatory Commission Washington, DC 20555 ATTN: Document Control Desk
References:
(1) License No. DPR-28 (Docket No. 50-271) , (2) Letter from R. W. Capstick, Vermont Yankee, to USNRC, " Request to l Routinely Dispose of Slightly Contaminated waste in Accordance with 10CFR20.302(a)", BVY 89-59, June 18,1989. (3) Letter from M. B. Fairtile, USNRC, to L.A.Tremblay, Vermont Yankee,
" Approval Under 10 CFR 20.302(a) of Procedures for Disposal of Slightly Contaminated Septic Waste On Site at Vermont Yankee (TAC No. 73776)",
dated August 30,1989.
Subject:
Request to Amend Previous Approval Granted Under 10 CFR 20.302(a) for Disposal of Contaminated Septic Waste J In accordance with the criteria of the Code of Federal Regulations, Title 10, Section 20.2002 (previously cited 10CFR20.302(a)), enclosed please find the subject application to arnend the previously granted approval (Reference 3) to dispose of slightly contaminated septic waste on site at Vermont Yankee by expanding the allowable waste stream to include slightly contaminated CoolingTower silt material i This application specifically requests approval to dispose of Cooling Tower silt deposits, contaminated atAi=1 levels, which have been or might be generated through the end of station operations et the Vermont Yankee Nuclear Power Plant. The proposed silt disposal method is the same as the septic waste disposal method requested in Reference 2 and approved in Reference 3. ] The disposal method utili7n c on s'te land spreading in the same designated areas used for septic waste. Disposal of this waste in the manner proposed, rather than holding it for future disposal at a 10CFR Pan 61 licensed facility when access to one becomes available, will save substantial costs and valuable disposal site space for waste of higher radioactivity levels. I A radiological assessment and proposed operational controls based on continued on site disposal of accumulated river silt removed from the basins of the plant's mechanical draft cooling towers is contained in Enclosure A. 'Ihe assessment demonstrates that the dose impact expected from the disposal of silt removed from the cooling towers during normal maintenance will not exceed the dose limits already imposed for septic waste disposal. The combined radiological impact for all on site disposal operations shall be limited to a total body or organ dose of a maximally exposed member of the public of less than one mrem / year during the period of active Vermont Yankee control of the site _, or less than fi.ve mrem / year
- - - mm to an inadvenent mtruder oafter terc.ination
_ _ _ _ n_m_m of actisc
L VERMONT YANKEE NUCLEAR POWER CORPORATt0N l ' septic waste (References 2 and.3) for your use and reference in evaluating the proposed amendment. - Upon receipt of your approval, Enclosure A will be incorporate' d into the Vermont Yankee ODCM. Wa trust that the information contained in the submittal is sufficient, however, should you have any questions or require further information conceming this matter, please contact this office. Sincerely, VERMONT YANKEE NUC. LEAR POWER CORPORATION
?/ fMfc' -
James J. Duffy Licensing Engineer Enclosures A & B c: USNRC Region I Administrator (Letter and Enclosure A) USNRC Resident Inspector - VYNPS (Letter and Enclosure A) USNRC Project Manager- VYNPS (Letter and Enclosure A) l
' Revision 2], Date R'14/97 Page F 10
ENCLOSURE A VERMONTYANKEENUCLEARPOWER PLANT ASSESShENT OF ROUTINE DISPOSAL OF COOLING TOWER SILT IN AREAS ON SITE PREVIOUSLY DESIGNATED FOR SEFTIC WASTE DISPOSAL Revision 11 Date 8/14/97 Page F-il
1 1 1
\
l i
)
Table of Contents l Page l l
1.0 INTRODUCTION
........... .................................. 3 2.0 WASTE STREAM DESCRIPTION .................................. 4 3.0 DISPOSAt METNOD ............................................-9 4 1
3.1 Silt Disposal Procedure Requirements ................ 9 3.2 Administrative Procedure Requirements'.............. 12 4.0 EVAWATION OF ENVIRONMENTAL ' IMPACTS . . . . . . . . . . . . . . . . . . . . . . . 13 4.1 Site Characteristics ................................ 13.
~
4.2 Radiological Impact ................................. 13
- 5. 0 RADIATION PP.0TECTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 6 . 0 CONCWS ION S ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23
27.0 REFERENCES
................................................ 24 i
2 b t . &_ o A_ on hm enon ricao rhm RJ9
r VERMONT YANKEE NUCLEAR POWER PLANT > Assessment of Routine Discesal of Cooline Tower Silt In-Areas On Site Previous 1v Desienated for Sentic Waste Discosal
1.0 INTRODUCTION
'. Vermont. Yankee Nuclear. Power Corporation (Vermont Yankee) requested from the 1NRC.in"1989 permission' to routinely dispose of slightly contaminated septic
~
Lw:cto in designated on site areas in accordance with 10CFR20.302(a). The (NRC responded,to this request on August' 30, 1989 by granting approval of the
. perpssediprocedures for on site disposal of septic waste concluding that the
-cramitments as documented in our request were acceptable, provided that our requ2st'and analysis be permanently incorporated into the plant's Offsite
;Dosa Calculation Manual (ODCM). Revision.9 to the ODCM (Appendix B) incor-perated the assessment and approval of the. methods utilized for on site dis-
.poso of slightly: contaminated sewa5e sludge.
In cddition' to the previously identified solids content of septic waste as a c:urce of environmental low level radioactive contaminated material, cooling
-tswsr sile deposits resulting from the settling of solids from river water pr.coing through the mechanical draft cooling tower system have been'identi-firdi to also contain' low ' levels of plant specific. radionuclides. Periodic removal of the silt from the cooling tower basins is a necessary maintenance
.prcctice to insure operability of.the' cooling system. However, due to the
~
prs =ence of by-product materials 'in the silt, proper disposal requirements
'aust be' applied to insure that the potential radiological impact is within
- ccceptable limits.
This assassment of sil.t ' disposal expands the original septic waste disposal feesassment to include' earthen type materials (cooling tower silt deposits) L h ile maintaining the1 original radiological assessment modeling and dose ,
' licit' criteria that have been approved for' septic waste spreading on site.
~ '
b iThis assessment demonstrates that cooling tower silt can be disposed of in
~
'tha i same manner. and under the same dose limit criteria as previously ap-
. proved for septic waste in. Appendix B ' to the Vermont Yankee ODCM. Implemen.
Jtatior of"the' following commitments as an amend:nent to the original 10 CFR 3 L uA weanam rpma %n ;
r l-Part 20.302(a) approval for septic waste shall be incorporated into the Vermont Yankee ODCM upon approval by the NRC. 2.0 VASTE STREAM DESCRIPTION: The vaste involved in this assessment is residual solids (silt) collec.ted in the basins of the plant's mechanical draf t cooling tower system. The silt consists of organic and inorganic sediments and carthen type materials that hava settled from the cooling water flow taken from the Connecticut River as it passes through the towers. As a result of de-sludging of the tower basins in 1993, an estimated 14,000 cubic feet of silt was accumulated on site. Clean-out operations will also occur periodically to ensure continued system operability. Sample analysis performed to the plant's environmental lowsr limits of detection requirements, as contained in Technical Specifica-tion Table 4.9.3., has identified Cobalt-60 and Cesium-137 in low concentra-tions as being present in silt collected in 1993. Tha cooling towers are located at the southern end of the plant facility complex, but are not directly connected to any system in the plant that contains radioactivity. The postult.ted mechanism of how plant-related radionuclides have been introduced into the cooling system silt assumes that past routine effluents discharged from nearby plant gaseous release points ware entrained in the large mechanically induced air flow that is pulled through the towers as a heat exchange medium. The cooling water flow pro-vidas a scrubbing action as it is breaks up into fine water droplets d o te the splash pans of the towers. This scrubbing action washes any airborn., particulate out of the air. Over long periods of operation, any radioac-tivity removed from the air flow could buildup to measurable levels in silt that settles out in the basins at the bottom of the towers. Table 1 lists the analyses of twenty-one samples collected from the silt pile removed from the cooling tower basins. Radioactivity measurements, averaged over all the samples, indicate that the silt material can be char-acterized as containing approximately 50 pCi/kg (dry wt.) of Cobalt 60, and 198 pCi/kg (dry vt.) Cesium-137. Eiriht of the samplea indicated no positive Cobalt-60 above a minimum detectable level achieved for the analysis. 4 Re ision l[ DateJ8114L97 Pee N4
Table 1 Cooling Tower filt Radioactivity (1993 samples *)
- Sample #- Co.60 'Cs.137 (pci/kg dry) (pci/kg dry)
C12759 53 144 C12758 72 172 C12757 <14 201 C12756 <17 245 C12755 73 206 C12754 <16 165 C12753 <27. 240 C12752 79 181 ) C12751 <29 180 G12750 35 107 C12749 59 171 i
.C12748- <19 205' C12747 <38 .209 C12746- <.7- 218 3
C12745 50 241 C12744 40 220 C12743- 68- 264 C12742 45 195 C12724 71 115 C12723 104 264 j C13940 126 218 j Average: 50 198 264 ! Max.= 126
. Min.- <7 107 l
Standard deviation: 30 42
- 0, Average wet to dry,- sample weight ratio equal to 1.6. Dry weight silt
' density equal to 1.3'gm/cc.
l 5 g Y. & 6 4 - L eve nn:c M ct&G
l I' For the purpose of estimating the total' activity in the silt pil'e, the less
- then values in Table 1 are included as positives in the calculation of the cvarcge radioactivity concentration. -C;bsit-60, due.to its relatively short half life,.is typically associated with plant operations when measured in the near environment. However, C0cium-137 when measured in the environment may have a background component ;th:t is not related to power plant operations. Past weapons testing fallout .has imposed'a man made background level of Cesium-137 in New England soils cnd e diments that can vary over several hundred pCi/kg. The plant's Envi-rens:ntal Monitoring Program has-shown that Connecticut River sediment in ths vicinity of Vermont -Yankee averai;es about 123 pCi/kg (dry vt.) of Cesi-um-137 (Table 2), with no plant related detectable level of Cobalt-60. The valus_of 123 pCi/k5 may represent an estimate of the background level of cocium-137 in sediment thac would be subject to entrainment in cooling water fisw that enters the plant. In comparing the measured levels of Cesium-137 en Table 1 with the past river sediment level, the average. concentration in 'ths otoling: cower silt is higher than that of the river sediment data, but decs fall within the observed range of recorded' sediment Cs-137. 1The river stdia:nt Cesium-137, concentration averages about 62% of the concentration valus detected in the tower silt. : For purposes of this assessment of plant ralstad dose-impact from the on site disposal of silt material, it is con-corntively assumed that all detectable Cs-137 in cooling tower silt is dirtetly related to plant operations. No background component is subtracted fr:s the measured values for this case study since only a single sampling icettion (down stream) is included in the Environmental Monitoring Program which may not fully dascribe the true background levels in the region.
Th3 total radioactivity for the current 14,000 cubic feet of sile collected en site can te estimated by multiplying this volume by its "as is" density i: L ef 2.1 gs/cc (i.e.1.3 ga/cc -dry weight density x 1.6 wet / dry weight ratio),
. , cnd then conservatively assume that the measured average dry weight radioac-t>
L iivity _ concentrations for Cobalt and Cesium would be the same as in the cellseted sile. Multiplying the average Cobalt-60 and Cesium-137 concen-
.tration-in silt by the mass ~ of the collected material produces estimates (Tcble 3)Dof total radioactivity that was removed from the cooling tower ,
basin'in September, 1993. j i l- 4 t 6 1 _ . . . ~ _.,. _. 1
Table 2 i
, Cesium.13 in Connecticut River Sediments
- Date Cs.137 (pCi/kg der) 05/24/94 61 10/13/93 85 06/02/93 60 10/15/92 137 05/20/92 176 10/24/91 178 05/16/91 230 10/25/90 84 05/16/90 62 10/04/89 <174 05/26/89 179 10/12/88 115 05/12/88 62 Average: 123 Max. 230 .
Min. 60 Standard deviation: 56
- Samples collected as part of the Vermont Yankee Radiological Environmen-tal Monitoring Program (REdP) for river sediraent sample location SE.11.
l 7 Revision 21_Date R/14/97 Page F.17
I l l l i I Table 3 l I Estimated Total Radioactive Material for 1993 Tower Clean-out I
. Volume of' Mass Average Total Act. Decayed Act. )
Silt Concentration (as of (as of 11/93) 6/95) j (ft3) (kg) (pci/kg) (uC1) (uCi) l I Co~60 14,000 8.32E+5 50 42 34 Cs-137 14,000 8.32E+5 198 165 159 In addition to 14,000 cubic feet of silt already accumulated, it is antici-pated that periodic maintenance work in cleaning out the cooling tower basins will generate approximately 4,000 cubic feet of new silt material - I over'each successive 18 month operating cyc.le. plant-related radioactivity concentration that was originally observed, the Assuming the same level of additional amounts of radioactivity that will require on site disposal l 1 following each refueling cycle can also be estimated. Table 4 lists an I estimate of the total radioactivity that might be present at each 18 month clean-out cycle. Table 4 I Estimated Total Radioactive Material for Each 18 Month Maintenan'ee Cvele l i l i Volume of Mass Average Total Activity Silt Concentration I 1 l (fc3) (kg) (pCi/kg) (uci) l Co.60 4,000 2.38E+5 50 12 l
<g 5 Cs-137 4,000 2.38E+5 198 47 8 l G .:,:.. 9 n.ie, R/1.1/Q7 ' Pb ~
;3.0 DISPOSAL METHOD:
Th2 method of silt disposal shall utilize a technique of land spreading in a manner consistent with the current commitments for the on site disposal of asptic waste as approved by the NRC and implemented as Appendix B of the
~
V:rmont Yankee ODCM (Reference 1). The same land areas designated and
, 2 cpproved for septic waste disposal shall be used for the placement of silt rcmoved from the cooling tower basins. Determination of the radiological
- doso impact shall also be made based on the same models and pathway assump-ticus as indicated in Appendix B of the ODCM.
~
3.1 silt Discosal Procedure Requirements Camma isotopic analysis of silt samples shell be made prior to each disposal
'by.cbtaining. representative composite samples in sufficient numbers to
. characterize the material removed from the cooling tower basins. Each gamma ic; topic analysis shall be required to achieve the environmental lower ~
limits of detection as -indicated' for sediment on' Table 4.a.3 of the Vermont Ycnkee Technical Specifications. Ths estimation of total radioactivity to be disposed.of shall be made based
.cn the average of all composite sample analyses. The estimation of total
! radioactivity and projected dose impact shall be made prior to placing the es11ected silt on the designated disposal plots. 'The dose impact from each
. dicposal operation shall be included with all past septic waste and silt
- cprsading operations to ensure t. hat the appropriate dose limits are not cxeneded'on any waste disposal area for the combination of all past opera-tiens.
Th2 established dose criteria requires that all applications of earthen-type
.'matsrials.within the approved designated disposal areas shall be limited to L ;snrure that dose to a maximally exposed individual (during the Vermont
-Ycnkee control period) be maintained less than 1 mrem / year to the whole body
~cnd.any organ,1and the dose to an inadvertent intruder following termination of site control.be maintained less than 5 mrem / year to the whole body and
.eny organ.
1' i. 9 l l . C __ h iRnnB M FB i __________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Page F 19
4 Tha limits on concentrations of radionuclides as' addressed in Appendix B to tthoLODCM for septic waste'(i.e. each tank of septic sludge to be disposed cro limited' to a combined MPC ratio of 'less than 0.1) were included to ensure proper control was in-place to address the situation of small quanti-ties of relatively high concentration material. This limitation does not diractly apply to silt deposits since the slit is handled as dewatered eediments as opposed: t'o liquid slurries of septic waste, iFar dry earthen type material such as silt, a specific radionuclides concen-trction~1imit shall be applied in place of the of.the septic waste liquid
'MPC ratio.e.No soil associated with a sample analysis-that identifies a ;plcat related radionuclides-in excess of the concentration limits of Table 5
- vill be permitted regardless'of the total pathway dose assessment determined'
.for the quantity material under consideration. For the case where more-than ens radionuclides is detected, tho' sum of the ratio rule will be applied.
Tha measured concentration of each radionuclides divided by its limiting concentration value shall.ba added with the sum of all fractions equal to or
;Icco than 1. This' limiting condition will prevent small volumes of. rela-
~
tivsly high specific radioactivity from being spread on the disposal plots,. cnd therefore reduce the potential for creating unexpected hot spot.. of Ecencentrated material. 4 Table 5 lists,lby-radionuclides, soil concentration values that would gener-sto an annual external effective dose equivalent of 25 mrem / year if.it were cocused that'an individual continuously stood on an infinite plane of soil contaminated to a depth of 15 cm. .The assumptions of an infinite plane and cantinuous, occupancy.are conservative for situations where the amount of
. c:ntaminated soil identified would not provide for a 15 cm soil depth over cn extended surface' area, and where disposal. site access is limited. Twen-(ty-five~mrom/ year was selected as.a reference value based on the fact that
- it was a' suitable fraction of.the NRC annual dose
- limit (100 mrem / year per
~
1 !. 110 CFR Part 20.1301) applied to members of the public from all station I L l ocurces. .The 25 arem/ year also equals the EPA dose limit from 40 CFR Part
-190 which would apply to real' members of the public offsite, and allow for
~
p
~ crsdit.to be~taken in accounting for actual' usage patterns'such as occupancy
.. tise . The external dose factors provided on Table 5 were derived from Table ]
I E-2 'of :NUREC/CR-5510 f(Re ference 3) . 10 iI sa ~ ' acmew anan rpm _
f i Table 5 Dry Soil Maximum Concentration Values Radionuclides Soil Concentration PCi/kg (eaual to 25 area /vr) Cr-51 1.51E+05 Mn-54 5.50E+03
- Fe-59 3.83E+03 Co-58 4.70E+03
-CO-60 1.82E+03 Zn-65 7.85E+03
.Zr 6.18E43 Ag-110m 1.66E+03
.Sb-124 2.51E+03 Cs-134 2.95E+03' Cs-137 8.13EM3 Ce-141 7.85E+04 Ce-144 8.75EM4 Assumptions include infinite planar distribution, uniform depth distribution to 15 cm, soil density at 1.625E+06 ge/m3, external q l
direct dose pathway only with a 100% occupancy factor. i i L. I l I I l l i i 1 11 Page F-21 ______ Op&ms D @an 844/97 _ __
/
l 3.2 Administrative Procedure Requirements: l l'
. Dry silt mat.erial shall be dispersed using typical agricultural dry bulk curface spreading practices only in approved disposal areas on site.
-C:splete records of each disposal will be maintained. These records will
' include the concentration'of radionuclides detected in the silt, an estimate
.ef the total volume of silt disposed of, the total radioactivity in each disposal' operation as well as the total accumulated on each disposal plot at ths time of the spreading, the plot on which the silt was applied, and the recults of any dose calculations or maximum allowable accumulated activity datsrminations. required to demonstrate that the dose limits imposed on these 1:nd spreading operations have not been exceeded. The determination of the 1 totsi radioactivity. and dose calculations shall also. include 'all past septic w:ste and silt disposal operations that placed low level radioactive materi-al en the det,ignated disposal plots.
Th9 periodic disposal of silt on each of the approved land spreading areas will be limited to within the same established dose and radioactivity crite-ric that have been approved for septic. waste disposal. C:ncentration limits that are applied to the. disposal of earthen type mate-riels (dry' soil) shall restrict the placement of small volumes of material that have relatively high concentrations of radioactivity such that direct
.cxptsure could not exceed'a small proportion (254) of the annual dose limits to members of the public that is contained in 10 CFR Part 20.1301.
Any farmer leasing land used for the disposal of silt deposits will be notified of the applicable restrictions placed on the site due to the land (cprsading of low level contaminated material. These restrictions are the
'came as' detailed for septic waste spreading as given in Reference 1.
l 12
I f
~4.0 EVALUATION-OF ENVIRONMENTAL IMPACTS:
4.1 Site Characteristics g- --Tha designated disposal sites consist-of two fields located on the Vermont
~.Ycnkes Nuclear Power Plant site. Both fields are on the plant property, 1within the~ site boundary security fence.- Site A contains an approximate
.. etn-acre parcel:of land centered approximately 2,000 feet northwest of the
-Racetor Building. Site B consist of approximately two acres and is centered approximately 1,500 feet south of the Reactor Building. These are the same
<lcad parcels approved by the'NRC.for the land disposal of septic waste, and crs' described in detail in Reference 1 along with-the boundary restrictions fer the placement of contaminated material.
Radiological assessments of septic waste disposal have determined that a single-two-acre plot would.be sufficient for!the routine disposal of that _ waste stream over a' 20 year period without exceeding the' dose criteria to a .
~
maximum exposed individual or~ inadvertent' intruder. 'As a result, the ten-ccrs field to the northwest can be divided into five disposal plots, with tha-two-acre site at the' south end of the' plant site providing e sixth plot. It.is therefore concluded that there is sufficient space within thc'aiready cyproved disposal plots to accommodate additional material from the cooling tcwsr. basins along with the septic waste without the likelihood of exceeding tha approved dose limit criteria. Since the residual' organic and inorganic solids associated with river sedi-
. ment (silt) are similar ~ to the sand and residual organic material remaining
.cfter decomposition of septic waste that is re.aoved form the plant's septic tanks,;the conclusions of'no significant environmental (non-radiological)
Limp:ct associated _with the disposal of' septic waste are not chana,ed by the
- cddition of'another earthen. type material, namely silt. )
-4.2 Ra'diolorical Imoact:
'Tha amount of cooling ,tcwer silt, in combination with any septic waste
'dieposals,;will be procedurally controlled ~ to insure doses are maintained within the prior approved limits'-(Reference 1). These limits are based on 13 D4tsn12fl[idunmMh2 - --
- past NRC proposed guidance (described in AIF/NESP-037, August 1986). The I
dose criteria require that the maximally exposed member of the general public receive a dose less than 1 mrem / year to the whole body or any organ dua to the disposed material, and less than 5 mrem / year to the whole body or any organ of an inadvertent intruder. To assess the doses received by the maximally exposed individual and inad-vertent intruder resulting from silt spreading, the same pathway modeling, assumptions, and dose calculation methods as approved for septic disposal are used. These dose models implement the methodologies and dose conversion fcctors as provided in Regulatory Guide 1.109 (Reference 2). Six potential pathways have been identified and include: (a) Standing on contaminated ground, (b) Inhalation of resuspended radioactivity, (c) Ingestion of leafy vegetables, (d) Ingestion of stored vegetables, (f) Ingestion of meat, and (g) Ingestion cf cow's milk Based on the septic waste evaluations, the liquid pathway was determined to be insignificant. Both the maximum individual and inadvertent intruder are assumed to exposed to these pathways with difference between them related to occupancy time. The basic assumptions used in the radiological analyses include: (a) Exposure to ground contamination and resuspended radioactivity is for a period of 104 hours per year during the Vermont Yankee active control of the disposal sites, and continuous thereafter. The 104 hour interval is representative of a farmer's time spend on a plot of land (4 hours per week for 6 months). (b) For the purpose of projecting and illustrating the magnitude of dose impacts over the remaining life of the plant, it is assumed that the current concentration levels of activity detected in silt remain 14
2 I N k
?
constant. Table 1 indicates the measured radioactivity levels for _I Cobalt-60 and Cesium-137 first noted in silt material. k 1* (c) The maximum radiation source corresponds to the accumulation of E radioactive matcrial on a single plot (two acre) within the approved j disposal sites over a period of 13 operating cycles. This extends = over the next 18 years until after the operating license expires in ['3 2012. The initial application (referenced to ' June, 1995) consists of U 14,000 cubic feet of silt collected in 1993 along with the first periodic clean out of the tower basins that adds an additional 4,000 -
'] , cubic feet. All subsequent applications of 4,000 cubic feet occur at "
18 month intervals. 2
,A e
(d) For the analysis of the radiological impact during the Vermont ' Yankee active control of the disposal sites, no plowing is assumed to N take place and all dispersed radioactive material remains on the surface, forming a source of unshielded direct radiation. _r_ (e) No radioactive material is dispersed directly on crops for human 4 or animal consumption. Crop contamination is only through root up- - take. 3 m_g 1 (f) The deposition on crops of suspended radioactivity is insignifi-cantly small.
~{
+
(g) Pathway data and usage factors used in the analysis are the same - as those used in the plant's ODCM assessment of off-site radiological iy~ impact from routine releases, with the exception that the f'raction of f stored vegetables grown on the contaminated land was conservatively h[ increased from 0.76 to 1.0 (at present no vegetable crops for human ;; consumption are grown on any of the approved disposal plots). 3 , (h) It is conservatively assumed that Vermont Yankee relinquishes .h m control of the disposal sited after the operating license expires in j 2012. (i.e., the source term accumulated on a single 2 acre disposal y plot applies also for the inadvertent intruder) . M _S 15 _-'-$ T' T
t (i) For the analysis of the impact after Vermont Yankee control of the site is relinquished, the radioactive material is plowed under and forms a uniform mix with the top six inc'es h of soil; but nonetheless, undergoes resuspension in air at the same rate as the unplowed surface contamination. For direct ground plane exposure the self shielding due to the six inch plow layer reduces the surface dose rate by about a factor of four. The dose models and methods used to generate deposition values and accumu. , 12ted activity over the operating life of the plant are documents in Attach-meze 2 to Reference 1. Based on the measured concentrations and silt volumes noted in Section 2.0 above, the total radioactivity that remains on the dicposal plots after the operating license expires is estimated on Table 6. l l Table 6 Proiected Radioactivity Builduo Due To Silt Spreadinc l j i Nuclide Contribution from Accumulation from 13 Total Remainin5 initial 14,000 ft3 cycles at 4,000 ft3/ea. in year 2013 (uci). (uci) (uci) j 1 l Cobalt.60 3.2 61.9 65.1
'cosium-137 104.9 500.5 605.4 l
Th2 calculated potential radiation exposure following the spreading of all cilt' material anticipated-to be generated through the remainder of the cparating license on a single two acre plot is provides on Table 7. 16 m_ m nn m nonnoun FAs FW
Table 7 Dose Imnact Due to Continued Sciendine to End of License Disnosal Site Access Radiation Exnosure Individual /Orcan Controlled by VYNPS 0.228 mrem /yr adult /whole body (max. exposed individual) 0.820 mrem /yr max. child / bone Uncontrolled by VYNPS 1.46 mrem /yr adult /whole body (inadvertent intruder after 2.41 mrem /yr max. child / bone license termination) The individual pathway contributions to the total dose due to continued silt spreading are shown on Table 8: Table 8 Pathwav-Denendent critical Ornan Doses Maximally exposed Inadvertent Intruder Individual / Organ Critical Individual / Organ (Child / Bone) (Child / Bone) Pathway (mrem /vear) (mrem /ve'ari Cround Irradiation 0.0474 0.957 Inhalation 0.00814 0.685 Stored Vegetables 0.528 0.528 Leafy vegetables 0.0265 0.0265 Milk Ingestion 0.201 0.201 Heat Ingestion 0.00833 0.00833 Total: 0.82 2.41 17 _m__.- mo m. . e .u m re_ rea,
In addition, the isotopic breakdown of the critical organ doses listed above (Table 8) for the two detected radionuclides is seen to.be: Table 9 , Isotonic Breakdown of Maximum Radiation Exposures Radioactivity Dose Percent of Description Isotone (uCi/2 acres) (mrem /vr) total During control Cs-137 605.4 0.805 98.2 of disposal siter Co-60 65.1 0.0144 1.8 Max organ: -------- child / bone 0.82 Termination of Cs-137 605.4 2.12 88.0 disposal site Co-60 65.1 0.29 12.0 Max. organ: -------- child / bone 2.41 For comparison to the total dose calculated assuming the continued disposal of silt removed fram the tower basins through the end of the operating license, the dose from just the original 14,000 cubic feet collected is shown on Table 10. 18 Revision .2.1 Date 8/14/97 Page F 28
Table 10 Dose Imoset Due to sincie (14.000ft3) Silt Screadine Disovsal Site Access Radiation Exoosure Individual /Orean Controlled by VYNPS 0.064 mrem /yr adult /whole body (max. exposed individual 0.219 mrem /yr max. child / bone in 1995) Uncontrolled by VYNPS 0.224 mrem /yr adult /whole body (inadvertent intruder after 0.393 mrem /yr max. child / bone license termination) Table 10 shows that the application of the silt material initially collected (14,000 cubic feet) accounts for abo se 27 percent of the maximum individual organ dose during the control period as compared to the scenario of contin-ued periodic silt spreading over the balti.ca of the operating license. This illustrates that dose impacts from the material currently collected are well below the acceptance criteria of limiting the dose from any rwo acre plot to no more than 1 mrem / year during the control period, and d mrem / year after termination of the license, and is expected to remain below the a'c ceptance criteria throughout plant life. If unexpected buildup of radioactivity in future silt clean out operations vere to ' occur, the option for use of alter-nate disposal plots remains available to ensure that the impact from any single two acre plot stays within the acceptance criteria. Also of interest are derived dose conversion factors which provide a means of ensuring that septic and silt disposal operations remain within the pre-scribed. radiological guidelines noted above. The critical organ (vorst case), and whole body dose factors for all pathways on a per acre bases are 19 __ m_ _ e en
given on Table 11 for periods during Vermont Yankee control of the disposal site, and on Table 12 for post control periods associated with the inadvert-ent intruder scenario. The dose conversion factors have been expanded to include other potential radionuclides beyond the original five that were addressed in Reference 1. This provides a means to assess other nuclides if future disposal operations identify additional radionuclides not previously observed. The development of these additional nuclide dose conversion factors utilize the same modeling and pathway assumptions as used to derive the factors for the original five radionuclides identified in septic waste. The models for these site and pathway specific dose factors are those in Regulatory Guide 1.100 (Reference 2), and are described in detail in Attach-ment II to Reference 1. R 20 Revision 21 Date R/14/97 Pace F-30__....
- t Table 11 i
All-Pathway Critical Orman / Whole Body Dose Conversion Factors Durine Vermont Yankee Control of Discosal Sites ! Nuclide , Individual / Organ Critical Organ Whole Body L Dose Factor Dose Factor ! (arem/yr per uCi/ acre) Cr-51 Teen / Lung 1.14E-05' 5.76E-06 Hn-54 ' Adult /GI-Ill 3.75E-04 1.93E-04 Fo-55. Child / Bone 6.45E-06 1.06E-06 i: Faa 59- . Teen /Inng 4.61E 2.13E-04 l' Co-581 ' Teen / lung- 3.27E-04 2.01E-04 Co-60 ' Teen / Lung- % 7.17E-04 5.31E-04
.In-65. Child / Liver -1.64E 1.03E-02 g Zr-95: Teen / lung 4.47E-04 1.34E-04
+
.Ag110m: Teen /CI-Ill 1.32E-02 6,24E-04 Sb-124: Teen / Lung- 8.34E-04 3.56E 04
'Cs-134: Child / Liver. 3.18E-03 1.28E-03 p Cs-137 Child / Bone 2.66E-03 7.02E-04
-Caa141; Teen / Lung 1.54E-04 1.50E-05 Ca-144? ? Teen / Lung 6.00E-04 2.44E-05 1
21 w_ u & mmnma m___ mm
Table 12 All-Pathway Critical Orcan / Whole Body Dose Conversion Factors Post Vermont Yankee Control of Disnosal Sites (Inadvertent Intruder) - Nuclide Individual / Organ Critical Organ Whole Body Dose Factor Dose Factor (mrem /yr per uCi/ acre) Cr-51 Teen / Lung 5.89E-04 1.19E-04 Kn-54 Teen / Lung 1.02E-02 3.12E-03 Fe-55 Teen / Lung 3.50E-04 2.27E-05 Fe-59 Teen /Inng 2.55E-02 4.43E-03 Co-58 Teen / lung 1.59E-02 3.72E-03 Co-60 Teen / Lung 3.19E-02 9.09E-03 Zn-65 Child / Liver 1.89E-02 1.25E-02 Zr-95 Teen / lung 2.93E-02 2.99E-03 Ag110m Teen / Lung 3.59E-02 9.53E-03 Sb-124 Teen /Lang 4.73E-02 7.04E-03 Cs-134 Child / Liver 1.21E-02 9.36E-03 Cs-137 Child / Bone 6.98E-03 3.85E-03 Ce-141 Teen / Lung 1.21E-02 3.44E-04 Ce-144 Teen /Lnng 5.00E-02 1.52E-03 22 Revision .2.1 Date S44/97 Page F-32
I f 5.0 PADIATION PROTECTION: The disposal operation of silt material from the cooling tower basins will follow the applicable Vermont Yankee procedures to maintain doses as low as reesonable achievable and within the specific dose criteria as previously approved for septic waste disposal (Reference 1),
6.0 SONCWSIONS
Silt collected from the cooling tower basins is an earthen type material that is similar in characteristics to septic waste residual solids with re-spect to the radiological pathway behavior and modeling, and can be disposed through on site land spreading on the same disposal plots as previously evaluated and approved for septic waste disposal. The radiological assess-ment of low level contaminated silt shows that the projected dose from the on site periodic spreading of this material will have no significant dose impset to members of the public and can be maintained below the approved dose limitations already in-place for septic waste. 23 Revision .21 Date 8/l4/97 Page F-33
7.0 REFERENCES
(1) Vermont Yankee 00OM, Appendix B; " Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site at Vermont Yankee". (Included NRC approval letter dated August 30, 1989, VY request for approval date June 28, 1989 with Attachments I and II) (2) USNRC Regulatory Guide 1.109, Rev. 1; " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", date October 1977. (3) NUREC/CR-5512, Vol. 1, " Residual Radioactive Contamination From Decom-missioning", Final Report, date October, 1992. file: vsilt. mss 24 Revision .21 Date R/14/97 Page F-34
i APPENDIX G MAXIMUM PERMISSIBLE CONCENTRATIONS (MPCs) IN AIR AND WATER AB0VE NATURAL BACKGROUND TAKEN FROM 10CFR20.1 TO 20.602. APPENDIX B Revision 21 Date 08/14/97 G-1
APPENDIX G With the implementation of the revised Part 20 to Title 10 of .the Code of Federal Regulations (10CFR20.1001-20.2401), the Maximum Permissible Concentrations (MPCs) that were part of the old 10CFR20 were replaced by a new Appendix B to 10CFR20 for the limits that apply to effluents released to unrestricted areas. However. MPC values were also used and accepted as licensing conditions for the control of radioactive materials in situations other than those directly covered by the requirements of the regulations. One example is the on-site disposal of septic waste which used the MPC values as one criteria of acceptability for land spreading. Appendix B to the ODCM references 10CFR20.1-20.601 Appendix B MPCs as concent' ration criteria for this
' disposal option.
With the final publication of the revised 10CFR20.1001-20.2401, the original MPC taDies of the old 10CFR20 are no longer in print. As such, this appendix to the ODCM is added to provide a reference source for the MPC values contained in the original Appendix B to 10CFR20.1-20.601 for those conditions that still refer to these requirements. Revision 21 Date 08/14/97 G-2
Appendix G I Maximum Permissible Concentrations (MPC's) (From 19CFR20.1 to 20.602, Appendix B) 1 1 APPENOtX B TO ff 20.1-20.602---CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL. BACKGROUND (See footnotes at end of Appendix B1 tsotope
- Table i Table it Element (atomic number) Col. 2-g , _g Col.1-Air Col.2-4Ci/mQ gyyf%) ( Ci/mt)
*fh Actinium (89) - Ac 227 S 2 x to-" 6 x 10" 8xto-" 2 x 10" 1
3 x 10* " 9 x 10** 9 x 10* " 3 x 10*
- A 228- S 8 x 10" 3 x 10*
- 3 x 10*
- 9 x 10" I 2 x 10-8 3 x 10" 6 x 10* " 9 x 10*
- Amerwism (95) Am 241 S 6 x 10-" 1 x 10" 2 x 10* " 4 x 10" I 1 x 10-" 8 x 10"
- 4 x 10*" 3 x 10*
- Am 242m- . S 6 x 10-" 1 x to'* 2 x 10- ** 4 x 10**
I 3 x 10*" 3 x10-8 9 x10"8 9x10" Am 242 S 4 x 10" 4 x 10-8 1 x10" 1x10" l 5 x 10*
- 4 x 10-8 2 x10." 1 x10*
- Am 243 S 6 x 10-" 1 x10" 2 x 10* " 4 x10" 1 1 x 10* " 8 x 10-* 4x10*" 3 x10-8 Am 244 - S 4 x 10-* 1x10" 1 x 10*' 5 x 10-8 Antirr.ony 1 2x10" 1 x10" 8 x 10-' 5 x10's Sb 122 S 2x10" 8 x 10" 6 x10" 3 x 10*
- 1 1 x 10-' 8 x 10-* 6 x 10-' 3 x 10*
- Sb 124 S 2 x 10-' 7x 10*
- 5x 10" 2 x10" I 2 x10-8 7 x 10** 7 x 10-" 2x10" Sb 125 S 5 x to-' 3 x10'8 2x10" 1 x10" 1 3 x10*
- 3 x 10*
- 9x 10-" 1 x 10" Argort(18) A 37 Sub8
_ 6 x 10.s gxion A 41 Sub 2x10-8 Arsenic (33) 4 x10** As 73 S 2 x 10** 1 x10-s 7 x10" 5x10" 1 4 x 10*' 1 x 10*8 1 x 10 *
- 5x10" As 74 S 3 x10" 2x10-s 4 x 10-* 5 x 10**
1 1x10** 2x10*8 4 x 10*
- 5 x10-*
As 76 S 1 x 10-' 6 x10*
- 4 x10" 2x10" i 1 x 10" 6x10" 3x10" 2x10-8 As 77- S 5 x 10-' 2 x10-s 2x10" 8 x10" l 4 x 10-' 2x10-s 1x10" 8 x10" Astatine (85) At 211 S 7 x t o-' 5 x 10-' 2 x 10* " 2x10-8 I 3 x 10*
- 2x10-8 1 x 10-*
Barium ($$) 7 x10*
- Ba 131 S 1 x 10-8 5 x 10-8 4 x to" 2x10" l 4 x 10* ' 5 x 10** 1 x10*
- 2 x 10-*
Ba 140 S 1 x 10-' 8 x 10** 4 x10" 3 x10" 8 4 x 10-8 7x 10" 1 x10" 2x 10-* Berketium (97) . Bk 249 $ 9 x 10* " 2 x10-8 3 x 10-" 6 x10" 1 1 x 10* ' 2 x 10-8 4 x 10** 6 x 10*
- Bk 250 S 1x10" 6 x 10-s 5 x 10" 2 x 10" I 1 x 10" 6 x 10" 4 x 10*
- 2 x 10" BerytWm (4) Be 7 . .~ S 6 x 10-* 5 x 10-8 2 x 10-' 2x 10" i 1 x 10*
- 5x10" 4 x to" 2 x 10" Bismutn (53) . Si 206 - S 2 x to" 4 x 10" 1 x 10" 6 x 10" 1 1x10" 1 x 10" 5 x 10" 4 x 10" Bi 207- . S 2 x 10" 2 x 10" 6 x 10" 6 x 10" 1 1 x 10" 2 x 10" 5x10-" 6 x 10" Bi 210.. S 6 x 10" 1xto' 2x10-" 4 x to' 8/I4/97 g.isn 2 D* Page G-3
~ ~ ~ ~ '
Nuclear Regulatory Commission Pt. 20 [ff 20.1-20.602), App. 8 APPENDfX 8 TO (( 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABovE NATURAL, BACKGROUND-Continued (See footnotes at end of Appenda B] Isotope
- Table i Table il Dement (atomic number) Col. 2-g g , Col. 2-40") 40 i) 40 *I 4 t) 1 6 x 10" 1 x 10 8 2 x 10-
- 4 x 10" Bi 212.... S 1 x 10" 1 x 10" 3 x 10" 4 x 10" l 2 x 10-' 1 x 10- 8 7 x 10*
- 4 x 10-
- Bromine (35). Br 82... S 1 x 10** 6 x to" 4 x to" 3 x 10" I 2 x 10* ' 1 x 10- 8 6 x 10*
- 4 x 10*
- Cadmium (48) Cd 10f S 5 x 10" 5x to-8 2x to" 2x 10" I 7 x 10" 5 x 10" 3 x 10" 2 x 10" Cd1'5m S 4 x 10" 7x 10" 1 x 10" 3 x 10" l 4 x 10*
- 7 x 10-
- 1 x 10-' 3 x 10-
- Cd 115 - S 2x 10" 8 x 10" 1 x 10- 8 3 x 10" I 2 x 10" 1 x 10-s 6 x 10" Caksum (20) 4' x 10" Ca n5 S 3 x to" 3 x 10*
- 1 x 10" 9 x 10" I 1 x 10" 5x10" 4 x 10" 2 x 10" Ca 47 S 2 x 10-' 1 x 10- 8 6 x 10-* 5 x 10-
- 1 2 x 10" 1 x 10- 8 6 x 10" 3 x 10" Calrfomium (98) Cf245 S 2 x 10"' 1 x 10*
- 5 x to"* 4 x 10" i 1 x 10-" 7 x 10" 3 x 10"8 Q 250 2 x 10" S 5 x 10-" 4 x 10" 2 x 10"' 1 x 10" I 1x10"* 7x 10" 3 x 10"' 3 x 10" Cf 251 S 2 x 10-" 1 x10" 6 x 10"* 4 x 10-8 1 1 x 10* " 8 x 10" 3 x 10"8 3 x 10-*
0 252 S 6 x 10* " 2 x 10-* 2 x 10"' 7 x 10-* I 3 x10-" 2 x 10" 1x10-" 7 x 10-* 0 253 S 8 x 10-" 4 x 10" 3 x 10-" 1 x 10-* I 8 x 10* " 4 x 10-8 3 x 10-" O 254 1 x 10-* S 5 x 10-" 4 x 10-* 2 x 10"8 1 x10" l 5 x10"8 4 x to-* 2 x 10* a 1 x 10" Carbon (6) C 14 S 4 x t o-* 2 x 10-8 1 x to-' 8 x 10-* (CO.) Sub 5 x 10-8 1 x 10** Ceriurn (58) Ce 141 S 4 x10" 3 x10" 2 x10" 9 x to-* 1 2 x 10-' 3 x10-s 5 x 10** 9x10-8 Ce 143 S 3 x10" 1 x 10" 9 x 10" 4 x 10" l 2 x10" 1 x 10-8 7 x 10" 4 x 10-8 Ce 144 S 1 x 10" 3 x10" 3 x 10-" 1 x 10" l 6 x 10" 3 x 10" 2 x 10-" Cesium (55) Cs 131 1 x 10" S 1x10" 7 x10" 4 x 10" 2 x10-i 3 x10-8 3 x 10-8 1 x 10" Cs 134m 9 x 10-* S 4 x 10- 5 2 x10" 1 x 10-* 6 x 10-8 1 6 x10-8 3 x 10-8 2 x 10-' 1 x 10-s Cs 134 S 4 x 10" 3 x 10" 1 x 10" 9 x 10" i 1 x10-e 1 x 10-8 4 x 10"* Cs 135 S 4 x10" 5 x 10*' 3 x10" 2 x10" 1 x 10-* I 9 x10-8 7 x10" Cs 13G S 3 x 10*
- 2 x10" 4 x 10-' 2 x 10-8 1 x 10" 9 x10" 1 2 x 10" 2x10-8 6 x 10-
- 6x 10" Cs 137 S 6 x 10" 4 x 10" 2 x10" 2 x 10-*
1 1 x10" 1 x108 5 x 10-" 4 x10" CNorine (17) CI36 S 4 x 10" 2x10 8 1 x 10" 0x10" i 2 x10*
- 2 x 10*
- 6 x 10* "
0 38 6 x 10-* S 3 x10-8 1 x 10-8 9 x 10" i 4 x 10" 2 x 10-* 1 x 10" 7 x 10*
- 4 x 10" Chromium (24) . Cr 51 S 1 x 10" 5 x 10" 3
4 x 10" 2 x 10" 2 x 10*
- 5 x 10" Bx10" 2 x 10" Cobatt (27). Co$7 S 3 x 10-* 2 x 10" 1 x 10" 5x10" 1
2 x 10" 1 x 10- 8 6 x 10" 4x10" Co S8m -- S 2 x 10" 6x10" 6 x 10" 3 x 10" l 9 x 10-
- 6 x 10" 3 x 10-' 2 x 10' Co $6.-- S 8 x 10' 4 x 10" 3 x 10" 1x10' 1 5 x 10-
- 3 x 10 8 2 x 10-
- 9 x 10-*
Co 60 S 3 x 10' 1 x 10 * { 1 x 10" 5 x 10 *
- I 9 x 10" 1 x 10 8 C w Ch. 3 /10 * ** 3 x 10-
- Co 64 S 2r.10-* 1 x 10 ' s 7 x 10" 3 x 10*
- Cunum (Hj ,
1 1 x 10-* 6 x10**f < < 10 " 2 x 10" Cm 242.. S 1 x to"* 7 y 10
- I 4 x 10- " 2 x 10' Revision .21 Date 8/l4/97 Pace G-4
Pt. 20 [@ 20.1-20.602), App. B 10 CFR Ch. I (1-1-93 Edition) APPENDIX B TO ff 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOvE NATURAL BACKGROUND-Continued (See footnotes at end of Appermin B) Isotope ' Table i Table ti Element (atoms number) g Col. 2-- g Col. 2- - (pCe !) N'M [ l} I 2 x 10-" 7 x 10-* 6 x 10-" 2 x 10-* Cm 243 S 6 x 10*" 1 x 10" 2 x 10* " 5 x 10*
- 1 1x10-" 7 x 10-
- 3 x 10* " 2 x 10-
- Cm 244 S 9 x 10-" 2 x 10*
- 3 x 10 * " 7 x 10*
- 1 1 x 10* " 8 x 10" 3 x 10-" 3 x 10" Cm 245 S 5x10"8 1 x 10" 2 x 10-" 4 x 10-8 1 1 x 10* " 8 x 10-* 4 x 10*" 3x10" Cm 246 S 5x10"8 1x10" 2 x 10- u 4 x 10" i 1 x 10-" 8 x 10-
- 4 x 10* " 3 x 10-*
Cm 247 5 5 x 10-" 1 x 10" 2 x 10-u e x 10" I 1 x 10* " 6 x 10" 4 x 10-" 2 x 10" Cm 24e S 6 x 10-" 1 x 10" 2 x 10*" 4 x 10" i 1 x 10* " 4 x 10- 6 4 x 10-" 1 x 10*
- Cm 249 S 1x10" 6 x 10-8 4 x 10' 2 x 10- s i 1 x 10" 6 x 10-8 4 x 10" 2 x 10" Dysprosium (66) Dy 165 S 3 x to" 1 x 10- 8 9 x 10" 4x10" 1 2 x10-8 1 x 10- 8 7 x 10" 4 x 10-*
Oy 166_._ S 2 x10" 1 x 10" 8 x 10" 4 x 10" 1 2 x10" 1 x10-s 7 x ion 4 x io-e Ensteinium (99) Es 253 S 8 x 10-" 7 x to" 3 x to-" 2 x to" l 6 x 10-" 7 x10" 2 x 10-" 2 x 10-8 Es 254m . S 5 x 10-* 5x10" 2 x 10-" 2x10" 1 6 x10-s $ x 10** 2 x 10-" 2 x 10*
- Es 254 S 2 x 10-" 4 x 10" 6 x 10"8 1 x 10-'
I 1 x 10-" 4 x10" 4 x to-u i x to-s Es 255_ S 5x10-" 8 x10" 2 x 10-" 3 x 10-* I 4 x10* " 8 x 10" 1 x 10-" 3 x 10-8 Erbium (68) & 169 S 6 x10" 3 x10" 2 x 10" 9 x10" 1 4 x10" 3 x 10-8 1 x 10" 9 x 10-8 Er 171 S 7 x 10-' 3 x10-8 2 x 10" 1 x 10** I 6 x10-8 3 x 10-8 2x10" 1x10" Europium (63) Eu 152 S 4 x 10" 2x10-8 1 x 10" 6 x 10" (T/2=92 tys) . . I 3 x10* 8 2 x 10-8 1 x 10" 6 x 10-
- Eu 152 S 1 x to-* 2 x to-8 4 x 10-" 8 x to" (T/2=13 yrs) I 2 x10" 2x10 s 6 x 10-" 8 x 10" Eu 154 , S 4 x10" 6 x 10" 1 x 10-" 2 x 10-*
I 7x 10-' 6x10" 2 x 10-" 2 x 10" Eu 155 S 0 x10*
- 6 x10-8 3 x 10-' 2 x 10-*
I 7x10 8 6 x 10-8 3 x 10*
- 2 x 10-
- Fermium (100) Fm 254 S 6 x10" 4 x to-8 2 x to" 1 x to" l 7 x10-8 4 x10" 2 x 10** 1 x 10-*
Fm 255 S 2 x10-* 1 x10-8 6 x 10-" 3 x 10" 1 1 x 10*
- 1 x10-8 4x10-" 3 x 10" Fm 256 S 3 x10" 3 x10-8 1 x 10* " 9 x10" 1 2x 10-' 3x10*8 6 x 10* " 9 x10" Fluonne (9)- F 18 S 6 x10 > 2 x 10-8 2 x 10" 8 x10-*
I 3 x 10*' 1 x 10-' 9 x 10-8 5 x 10-* GadoGnium (64) Gd 153 S 2 x10" 6 x 10-8 8 x 10" 2 x 10" l 9 x 10 " e x 10-' 3 x 10-' 2 x 10-
- Gd 159 S 3 x 10 2 x 10-8 2 x 10" 8 x 10" 6 4 x 10' ' 2 x10" 1 x 10" 8 x 10" Gamum (31) G: 72 S 2 x 10" 1 x 10-' 8 x 10" 4 x 10" I 2 x 10-' 1 x 10- s 6 x 10-
- 4 x 10" Germar6:m (32) Ge 71 - S 1 x 10- 5 x 10- 8 4 x 10" 2 x 10" 1 6 x 10-* 5x t0*' 2 x 10-' 2 x 10-8 Gold (79) Au 196 S 1 x 10" 5x10" 4 x 10" 2 x 10" l 6 x 10-' 4 x 10-8 2 x 10-
- 1 x 10-
- Au 198. S 3 x 10 2 x 10*
- 1 x 10*
- 5 x 10-
- 1 2 x t0-' 1 x 10 s exgo-, 5 x io .
Au 199 S 1 x 10-* 5 x 10' 8 43 10**i 2 v 10
- I 6 s 10 ' 4 x 10" 2 x 10
- Hafn.um U2).. ... Mt161. S 2 x 10" 3 3.10" l ax 10" 1x10" 7 x 10" 1
7 x 10-* 2 x 10-' 3 x 10 * ' 7x10-* Holmium (67) .. ... Ho 16G S 2 x 10-' 9 x 10" 7> to'* 3 x 10 *
- nyicinn n nare 8/14/97 Pace G-5
Nuclear Regulatory Commission Pt. 20 [@@ 20.1-20.602), App. B APPENDfx 8 TO ff 20.1-20.602-CONCENTRATIONS IN AIR AND WATER AeovE NATURAL BACKGROUND-Continued (See footnotes et end os Appendis 81 1sotope
- Table i Table ti Dement (atoms: number) g 3_gj Col. 2- Col. 2-g 3ag
( G/mg * (pCi/mQ ( Cs)b) g"oj'*h 1 2 x 10*' 9 x 10*
- 6 x 10-' 3 x 10" Hycrogen (1)- H3 S 5 x 10" 1 x to" 2 x 10" 3 x 10" i 5 x 10-* 1 x 10* ' 2 x 10-' 3 x 4 0*
- Sub 2 x 10-8 4 x 10" Indem (49) - in 113m S 8 x 10" 4 x 10" 3 x 10" 1 x 10*
- I 7 x 10" 4 x 10" 2 x 10* ' 1 x 10-
- In 114m S 1 x 10" 5 x 10" 4 x 10" 2 x to-*
I 2x 10" 5 x 10" 7 x 10-" 2 x 10" In 115m S 2 x 10-8 1 x 10* ' 8 x 10" 4 x 10" 1 2 x 10*
- 1 x 10* ' 6 x 10*
- 4 x 10-*
In 115 S 2 x 10" 3 x 10" 9 x 10" 9 x 10" 1 3 x 10** 3 x 10*
- 1 x 10" 9 x10" lodine (53) I 125 S 5 x 10" 4 x 10" 8x10"' 2 x 10" 1 2 x 10-' 6 x 10" 6 x 10-' 2 x 10" 1 126 S 8 x10" 9 x 10* "
5 x 10- 8 3 x 10" 1 3 x10" 3 x 10.s 1 x 10" 9 x 10" 1129- S 2x 10" 1 x 10" ? x 10-" 6 x 10" l 7 x 10-8 6 x 10-8 2 x 10-' 2 x 10" 1131 S 9 x 10" 6 x 10" 1x10*" 3 x10" l 3 x10" 2 x 10-8 1 x 10-8 6 x 10" 1132 S 2 x 10-' 2x 10-8 3 x 10-' 8 x 10" l 9 x 10-' 5 x 10-' 3 x 10-* 2 x 10" I133 S 3 x10" 2x 10" 4 x 10-" 1 x10-8 1 2 x 10-' 1 x10-a 7 x 10*
- 4 x10*:
1134 S 5 x 10" 4 x10-s 6 x10" 2x10 8 1 3 x 10-* 2 x10-8 1 x 10" 6 x 10" 1135 S 1 x 10-' 7 x 10-* 1x10" 4 x 10" l 4 x 10-' 2 x 10*
- 1 x 10-8 7 x 10" lid 5um (77) ir190 S 1 x 10-* 6 x 10-8 4 x10" 2 x10" 1 4 x 10*' 5 x 10-a 1 x 10-' 2xto" tr 192 S 1 x10" 1 x 10-8 4 x 10" 4 x 10" 1 3 x 10-' 1 x 10" 9 x 10"* 4 x 10" Ir 194 S 2 x10" 1 x 10-8 8 x 10-' 3 x10" i 2 x 10-' 9 x 10-* 5x 10" 3x10" Iron (26) -- Fe 55 S 9 x10" 2 x to-8 3 x10" 8 x10"
, i 1 x 10-* 7 x 10" 3 x 10" 2x10" Fe 59 S 1 x10" 2 x 10*
- 5x10" 6 x10" l 5 x 10-* 2x10-s 2 x 10" 5 x 10" Krypton (36) Kr85m Sub 6 x 10-*
1 x to" Kr85 Sub 1 x10" 3 x to" Kr 27- Sub 1 x 10-* 2 x10" Kr 88 Sub 1 x10-* 2x10-s Lonthanum (57) La 140 S 2 x 10-' 7 x 10" 5 x 10" 2 x 10-* 1 1x10" 7 x 10" 4x10" 2 x 10-8 Lead (82) Pb 203 S 3 x 10*
- 1 x10-8 9x 10" 4 x 10" I 2 x 10-* 1 x10-8 6 x 10" 4x10" Pb 210 S 1 x10-" 4 x 10-* 4 x 10"' 1 x 10" I 2 x 10-" 5 x 10-8 8 x 10"8 2 x10" Pb 212 S 2 x 10" 6 x10" 6x10-" 2 x 10" l 2x10" 5 x 10" 7 x 10"* 2 x10" Lutetium (71) Lu 177- S 6 x10" 3 x 10*
- 2 x 10-* 1x10" l 5 x 10-' 3 x 10-8 2 x 10-* 1 x 10" Marganese (25) Mn52 S 2 x to-' 1 x 10" 7 x 10" 3 x 10" I 1 x 10" 9x10" 5 x 10' 3 x 10" Mn54 S 4 x 10-' 4 x 10" 1 x 10" 1 x 10" 1 4 x 10" 3 x 10*
- 1 x 10" 1 x 10" Mn56 S 8 x 10" 4 x 10" 3 x 10" 1 x 10" i 5 x 10-' 3 x 10*
- 2 x 10*
- 1 x 10 *
- Meicury (80) Hg 197m S 7 x 10" 6 x 10. a 3 x 10" 2 x 10" l 8 x 10 * ' 5 x 10*
- 3 x 10-
- 2 x 10-*
Hg 197.. S 1 x 10" 9x10' 4 x 10" 3 x 10" 3 I 3 x 10" 1 x 10* ' 9 x 10" 5 x 10"
! Hg 203.. S 7 x 10" l
5x10" 2 x 10" 2 x 10" i 1 x 10* ' 3 x 10-' 4 x 10 ' 1 x 10 *
- anom - -^
Pt. 20 [@ 20.1-20.602], App. B 10 CFR Ch.1 (1-1-93 Edition) APPENOlX 6 TO {f 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued (See footnotes at end of Append.: 0) esotope 8 Table I Table ti Dement (atom.c nuncer) g Col. 2 - g ,,w Con 2-(pO/mt) j)[,) (pC./ml) g[gj[n Motybdenum (42) Mo 99 -- S 7x to-8 5 x 10- 8 3 x 10" 2 x 10" I 2 x 10" 1 x 10" 7 x 10" 4 x 10" Neodymium (60) Nd 14 4 - S 8x10*" 2 x 10- 8 3 x 10* " 7 x to'* I 3 x 10* " 2 x 10" 8 1 x 10* " 8 x 10" Nd 147 S 4 x 10* ' 2 x 10*
- 1 x 10-* 6 x 10-
- 1 2 x 10" 2 x 10 8 8 x 10" 6 x 10*
- Nd 149 S 2 x 10" 8 x 10-8 6 x 10" 3 x 10" 1 1 x 10" 8 x 10-8 5 x 10" 3 x 10" Neptunium (93) Np 237 S 4 x 10-" 9 x I0" 1 x 10-" 3 x 10**
I 1 x 10-" 9 x 10" 4 x 10"' 3 x 10" Np 239 S 8x10*8 4 x 10*
- 3 x 10" 1 x 10*
- i 7x10" 4x10' 2 x 10' 1 x 10" Nickel (26)- .. Ni 59. S 5 x 10" 6 x 10- 8 2 x 10" 2 x 10" l 8x10" 6 x 10" 3 x 10" 2 x 10- 8 Ni 63 S 6x10" 8 x 10" 2 x 10" 3 x 10* -
I 3 x 10" 2 x 10" 1 x 10" 7 x 10" Ni G5 S 9 x 10" 4 x 10" 3 x 10" 1 x 10" 1 5x10" 3 x10-8 2 x 10" 1 x 10" G6ob.um (Columbium)(41) ND 93m S 1 x 10" 1 x 10" 4 x 10" 4 x 10" I 2 x 10-8 1 x 13-8 5 x 10*' 4x10" N0 95 S 5 x to-8 3 x 10-8 2 x 10-* 1 x 10" i 1 x 10-8 3 x10*8 3 x10*8 1 x 10" Nb 97 S 6 x 10** 3 x 10-8 2 x .u * . 9 x 10" 1 5x 10" 3 x 10-8 2x 10" 9x10" Osmium 96) Os 185 S 5 x t o-8 2 x10-8 2 x 10" 7 x 10" I 5 x 10-' 2x 10" 2 x 10" 7 x 10*
- Os 191m S 2 x10-8 7 x 10" 6 x 10" 3 x 10-8 1 9 x 10*
- 7 x 10-s 3 x 10* 8 2 x 10* 8 Os 191 S 1 x10" 5 x 10" 4 x 10" 2x10" 1 4 x 10" 5 x10-8 1 x 10" 2 x 10" Os 193 S 4 x 10" 2 x 10-8 1x10" 6 x 10-8 1 3 x 10" 2x10 8 9 x 10" 5 x 10" Pattadium (46) Pd 103 S 1 x10" 1 x 10-8 5 x 10" 3 x 10" l 7X 10" 8 x 10-8 3 x 10*
- 3 x 10 *
- Pd 109 S 6 x10" 3 x 10" 2 x 10" 9 x 10" 1 4 x 10" 2 x 10-8 1 x 10" 7 x 10" Phosphorus (15) P 32 S 7 x10" 5 x 10" 2 x 10" txto" l 8 x 10*
- 7x 10" 3 x 10" 2 x 10*8 Plat;num 98) Pt191 S 8 x10" 4 x 10-* 3 x 10" 1 x 10" l 6 x10-8 3x 10-8 2x 10" 1x10" Pt 193m S 7x10" 3 x 10-8 2 x 10" 1 x 10-8 1 5 x10" 3 x 10" 2 x 10" 1 x 10* 8 Pt 193 . S 1 x 10-* 3 x 10" 4 x 10" 9 x 10" l 3 x10" 5 x to" 1 x 10-* 2 x 10*
- Pt 197m S 6x10" 3 x 10" 2 x 10" 1x10" l 5 x 10-8 3 x10" 2 x 10-' 9 x 10*
- Pt 197 . S 8 x10" 4 x t o-8 3 x 10" 1 x 10" 1 6 x10* 8 3 x 10-a 2 x 10- 8 1 x 10-
- Plutortium (S4) Pu 238. S 2 x 10"8 1x10" 7 x 10-" 5 x 10" 1 3 x 10-" 8 x 10" 1 x 10-" 3 x 10" Pu 239 S 2x10"8 1 x 10" 6 x 10- " 5 x 10" l 4 x 10-" 8 x 10" 1 x 10* " 3 x 10" Pu 240 S 2 x 10"8 1 x 10" 6 x 10* " 5 x 10" l 4x10-" 8 x 10' 1 x 10* " 3 x 10" Pu 241 S 9 x 10-" 7 x 10" 3 x 10- " 2 x 10" 8 4 x 10" 4 x 10" 1 x 10" ( 1 10 "
Pv 242.. S 2 x 10* " 1 x 10' 6 x 10- " I 5 x 10*
- I 4x10*" 9 x 10" 1 x 10* " ! 3 s10 "
l Pu 243 S 2 x 10" ty10" C e 10" l 3 s 10 " 1 2 x 10" 1 x 10" t 6 x 10 * ' 3x10-*
! Pw 244 S l 2 x 10- " 1 x 10" 6 x 10 ' 4w10
t : 3 x 10-" 3x10" 1 >. io-" ! i . io" Poion.um (64.. .., . . . , I' jN20 S i 5 x to"* I 2 x 10 * " 2 x 10" 6 x 10" 2 x 10- " ! 7 x io-" : 7 x '0" 3 10 "
Nuclear Regulatory Commission Pt. 20 {s@ 20.1-20.602], App. 8 APPENOlX 8 TO ff 20.1-20.602-CONCENTRATIONS IN Al4 AND WATER ABOVE NATURAL BACKGROUNO-Continued (See footnotes as end of Append. 81 isotope
- Taoie a Taose as E6ement (atom.c numbe<j g, Col 2- Cor 1-4 Cot 2 (FO'*0 ( o[En (#O#*0
( c'[$n
^
Potassium (19)- K4 2 ._ . . . - . . S 2 x 10" 7 x 10" 9 nr 10'8 3 x 10" 1 1 x 10 * ' 6 x 10 *
- 4 x 10 * ' 2 x 10 *
- Praseod tmouro (59) Pr 142... S 2 x 10* ' 9 x 10" 1 x 10" 3 x 10" s 2 x 10*
- 9 x 10'
- 5x10*' 3 x 10 *
- Pr 183. .. S 3x10" 1 x 10" 1 x 10" 5 x 10" 1 2 x 10 *
- tw10** 6 s to*' 5 x 10 *
- Promethium (61) Pm 14 7.. S 6 x 10" 6 x 10' 2 x 10" 2 x to" i 1 x 10 * ' 6 x 10*
- 3 x 10* ' 2 x 10 *
- Pm 149 S 3 x '10 * ' 1x10' 1 x 10" 4 x tD" 1 2 x 10*
- 1 x 10 s gxto-. 4gio-.
Protoactinium (91) - Pa 230. S 2 x 10" 7 x 10' 6 x 10* " 2 x 10" l 8 x 10* " 7 x 10 *
- 3 x 10 * " 2 x 10*
- Pa 231.. S 1 x 10"8 3 x 10" 4 y 10"* 9 x 10" I 1 x 10 8 x 10' 4 x 10"8 2 x 10" Pa 233.. S 6 x 10" 4 x 10* 8 2 x 10' 1 x 10' l 2 x 10*
- 3 x 10- a 6 x 10 *
- 1 x 10 *
- Radsum (88) Ra 223 2 x 10" S 2 x 10' 6 x 10 * " 7 x 10' 4 2 x 10"' 1 x 10" 8 x 10"8 4 x 10 *
- Ra 224 S $ x iO" 7x10" 2 x 10* " 2 x 10*
- I 7 x 10* " 2 x 10*
- 2 x 10* " 5 x 10*
- Ra 226 S 3 x 10* " 4 x 10" 3 x 10"8 3x10" s i 5 x 10* " 9 x 10*
- 2 x 10* " 3 x 10*
- Ra 226 7 x 10* " 8 x 10" 2 x 10"8 I' 3 x 10*
- 4 x 10* " 7 x 10" 1x10"8 3 x 10" Radori(66) Art 220 S 3 x 10" 1 x 10**
An 222 s 3 x 10" 3 x 10" Rhenium (75) _ Re 183 S 3 x 10 *
- 2 x 10'8 9 x 10" 6x10" 1 2 x 10* ' 8 x 10.a 5 x 10" 3 x 10*
- Re 186 S 6 x 10" 3 x 10' 8 2 x 10" 9 x 10-1 2 x 10" 1 x 10'8 8 x 10" 5 x 10" Re 187 S 9 x 10" 7 x 10" 3 x 10"
' 3 x 10" 5 x '0" 4 x 10" 2 x 10" 2 x 10" Re 188 4 x 10 2x 10*
- 1 x 10" 6 x 10*
- I 2 x 10* ' 9 x 10*
- 6 x 10*' 3 x 10*
- Rho $um (45) .. Rh 103m S 8 x 10" 4x10" 3 x 10*
- 1 x 10" l 6 x 10*
- 3 x 10*
- 2 x 10*
- 1 x 10-8 Rh 105 S 8 x 10" 4 x 10** 3 x10" 1x10" l 5 x 10" 3x10" 2 x 10" '1 x 10" Butnum (37) Ab e6 S 3 x 10" 2x10" 1 x 10" 7 x 10" 4 7 x10** 7 x 10" 2 x 10" 2 x10" Rb 87 S 5x10" 3 x 10" 2 x 10" 1 x10" l 7x 10" 5 x10" 2 x 10" 2 x 10" Butherwum (44) Ru 97 S 2 x 10" 1 x 10* 8 8 x 10" 4x10" I 2 x 10*
- 1 x 10-8 6 x 10*
- 3 x 10*
- Ru t03 S $ x 10" 2 x 10" 2 x 10" 8 x 10" l 8 x 10" 2 x 10-s 3xto-o 8 x10" Ru t05 S 7x 10" 3 x10 s 2 x 10" 1 x 10" l 5 x 10" 3 x 10-a 2 x 10" 1 x 10" Ru 106 S 8x10" 4 x 10" 3 x 10" 1 x 10" l 6 x 10" 3 x 10" 2 x 10"' 1 x 10- 5 Samanum (62) -- Sm 14 7 . . .. S 7 x 10-" 2x10" 2 x 10"' 6 x 10*
- I 3 x 10"' 2 x 10" 9 x 10"8 7 x 10' Sm 151., S 6 x 10" 1 x 10" 2 x 10" 4 x 10" 4 1 x 10- 8 1 x 10- 8 5 x 10*
- 4 x 10*
- Sm 153.. S 5x10" 2 x to" 2 y 10" 8 x to" 1 4 x 10* ' 2 x 10*
- 1 x 10*
- 8 x 10 *
- Scandium (21L Sc 46.. S 2 x 10" 1 x to" 8 x 10" 4 x 10-
- i 2 x 10" 13: 10 ' 8 x 10"' 4 x 10" Sc 8 7 5 6 x 10" , 2 x 10" 2 > 10 " 9 e 10" i 5 x 10 * *
- 3 10'8 ?v10** 9v10**
l Sc -6 S 2A10 ' f.10I 6 10 " 3s 10 5 a i l s' .10 ' 6 10 5 < 10 " 3 k 10' Scienum 3: Se 75 . 1 x to" , 9 = to
- S I 4 ,: t o "
S. 10 '
; 1 1x10 E s10 4,10*' 3 x 10 *
- f t. _.
0 Pt. 20 [s 20.1-20.602}, App. 8 10 CFR Ch.1 (1-1-93 Edition) APPENDIX 8 TO (( 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUNO--Continued (See footnotes at end of Appendia 01 l l tsotope ' Table 1 Table 11 Element (atomic number) Col 1-Air Col. 2- co, g _g,, Col 2-(pCi/my d'$ 9 (pC /m0 g%'h Smcon (14) Si 31 S 6 x 10" 3 x to" 2 x to" 9 x 10" 1 1 x 10** 6 x 10- 8 3 x 10*' 2 x 10*
- Silver (47) Ag 105 S 6 x 10" 3 x 10" 2 x 10" 1 x 10" l 8 x 10" 3 x 10" 3 x 10" ! 1 x 10" Ag 110m - S 2 x 10" 9 x 10" 7 x 10" l 3 x 10*
- 1 1 x 10" 9 x 10" 3 x 10* " 3 x 10" Ag 111 S 3 x 10" 1 x 10- a 1 x 10" 4 x t0' I 2 x 10" 1 x 10 8 8x10" 4 x 10*
- Sodium (11) Na 22 S 2 x 10" 1 x 10' 8 6 x 10 *
- 4 x to-
- I 9 x 10*' 9 x 10*
- 3 x 10* " 3 x 10* *
' Na 24 S 1 x 10** 6 x 10- 8 4 x 10*
- 2 x 10*
- 1 1 x 10" 8 x 10" 5 x 10" 3 x 10" Strontium (38) Sr85m $ 4 x 10" 2 x 10" 1 x 10** 7 x 10" l 3 x 10*
- 2 x 10* ' 1 x 10*
- 7 x 10* 8 Sr85 S 2 x 10- 8 3 x 10* 8 8 x 10* ' 1 x 10**
1 1x10" 5x10" 4 x 10" 2 x 10" Sr 89. S 3 x 10" 3 x 10" 3 x 10* " 3 x 10" 1 4 x 10" 8 x 10" 1 x 10" 2 x 10" Sr 90 S 1 x 10" 1 x 10" 3 x 10"' 3 x 10" l 5 x 10*' 1 x 10*
- 2 x 10* " 4 x 10**
Sr 91 S 4 x 10" 2 x 10" 2 x 10" 7 x 10* 8 8 3 x 10*
- 1 x 10- 8 9 x 10" 5 x10* 8 Sr S2 S 4 x 10-8 2 x 10*
- 2 x10" 7 x10" 1 3 x 10" 2 x 10-8 1 x 10-s e;x ico Sulfur (16) S 35 S 3 x 10" 2 x 10*
- 9 x 10" 6 x 10* 8 8 3 x 10" 8 x10 s 9 x 10" 3 x 10" Tantatum (73) Ta 182 S 4 x 10" 1 x 10* 8 1 x 10" 4 x 10-a i 2 x 10*
- 1 x 10* 8 7 x 10* " 4 x10" Technetium (43) Tc 96m S 8 x 10*
- 4 x to" 3 x to-* 1 x 10*
- I 3 x 10** 3 x 10" 1 x 10** 1 x 10-8 Tc96 S 6 x 10' 3 x 10
- 8 2 x10" 1x10" I 2 x 10" 1 x 10- 8 8 x 10" 5 x 10" Tc S7m. . S 2 x 10" 1 x 10" 8 x 10" 4 x 10" i 2 x 10" 5 x 10-s 5 x 10" 2x 10" Tc S7 'S 1 x 10** 5 x 10" 4 x 10" 2 x 10* 8 1 3 x10" 2 x 10-s 1 x 10" 8 x 10" Tc 99m S 4 x 10" 2 x 10" 1 x 10" 6 x 10" i 1 x 10" 8 x 10-8 5x10" 3 x 10-8 Tc 99 S 2 x 10*
- 1 x 10*
- 7 x 10-8 3 x 10*
- 1 6 x 10" 5 x 10* 8 2 x 10" 2 x 10" Telturium (52) Te 125m S 4x10" 5 x 10*
- 1 x 10" 2xto" i 1 x 10" 3 x 10* 8 4 x 10" 1x10" Te 127m S 1 x 10" 2 x 10* 8 5 x 10" 6 x 10*
- I 4 x 10" 2 x 10" 1 x 10" 5 x 10*
- Te 127 S 2 x 10*
- 8 x 10-s 6 x 10* 8 3 x 10*
- I 9x10" 5 x 10-s 3 x 10" 2 x10" Te 129m S 8 x 10*
- 1 x 10" 3 x 10" 3 x 10* 8 1 3 x 10" 6 x 10" 1 x 10" 2 x 10" Te 129.. S 5 x 10*
- 2 x 10* 8 2 x 10" 8 x 10" 1 4 x 10** 2 x 10* 8 1 x 10* ' 8 x 10*
- Te 131m S 4 x 10" 2x10" 1 x 10" 6 x 10" i 2 x 10* ' 1 x 10* 8 6 x 10*' 4 x 10*
- Te 132. S 2 x 10* ' 9 x 10" 7 x 10*
- 3 x 10" 1 1 x 10" 6 x 10" 4 x 10*' 2 x 10" Ter0ium (65). Tb 160.. S 1x10" 1x10" 3 x 10" 4 x 10" 1 3 x 10*
- 1 x 10 *
- 1 x 10 * ' 4 x 10*
- Tha: tium (81) . . . Ti200.. S 3 x to" 1x10" 9 x 10 *
- 4 x 10" I 1 x 10" 7 x 10 *
- 4 x 10" 2x10" T1201 5 2 x 10" 9510** 7 x 10" .
3 x 10' l 9 x ic" 5s10-8 3 x 10" ! 2x10" T3202 S 63.10 ' 4 10**, 3 e 10" ; 1*10'* I 23.10*' 2 10-8. 8 10 " ; 7 x 10 ' TI M4 S 6 x 10- ' 3 x 10" l 2 s 10 " ! i w i0'
, 3xio-. 2 x io 8 ' 9 x io-" ' n io
- __ u u u n,_ 8/14/97 m_ __
- - _ - - - - - - - - - - - -- -- - - ' ~-~
t I l Nuclear Regulatory Commission Pt. 20 [f@ 20.1-20.602), App. B i APPEN0fX B TO (( 20.1-20.602-CONCENTRATIONS IN AIR AND WATER 'ABOVE NATURAL. l BACKGAOUNO-Continued (See footnotes al end of Apperds 8] l 1sotope
- Table I Table 11 Element (stomic number) Col 2-g g,,,9 Col.1- Ak Col. 2-(pCitmt)
*)* (pCstml) }*,j*
Thorium (90) Th 227 S 3 x 10- " 5x10" 1 x 10* " 2x to" I 2 x 10"* 5x10" 6 x 10"' 2 x 10" Th 228.- S 9 x 10-" 2 x 10" 3 x 10"' 7 x 10" 1 6 x 10-" 4 x 10" 2 x 10"* 1 x 10" Th 230- S 2x10-" 5 x 10" 8 x 10"* 2 x 10*
- 1 1 x 10*" 9 x t0-* 3 x 10- " 3 x 10 *
- Th231- S 1 x 10" 7x 10 5 x 10" 2 x 10" i 1 x 10*
- 7 x 10."a 4 x 10 *
- 2 x 10" Th 232 5 3 x 10-" 5 x 10-
- 1 x 10* " 2 x 10*
- I 3 x 10* " 1 x 10 ' 1x10-" 4 x 10" Th natural . S 6 x 10-" 6 x 10*
- 2 x 10-" 2 x 10-
- I 6 x 10-" 6 x 10*
- 2 x 10-" 2 x 10*
- Th 234 S 6 x 10-' 5 x 10-
- 2 x 10-' 2 x 10-
- I 3 x 10*
- 5 x 10-' 1 x 10-' 2 x 10-
- Thutium (69)- Tm 170 S 4 x 10" 1 x 10* 8 1 x 10" 5 x 10" 1 3 x 10-* 1 x 10" 1 x 10*
- 5 x 10*
- Tm 171 S 1 x 10" 1 x 10** 4 x 10" 5 x t0" 1 2 x 10-' 1 x 10-' 8 x 10-' 5x10" Tin (50) Sn 113 S 4x10" 2 x 10- 8 1 x 10" 9 x 10" 1 5 x 10" 2 x 10-8 2 x 10" 8 x t0" Sn 125 S 1x10" 5 x 10-* 4 x 10-' 2 x 10" l 8 x 10-* 5 x 10-* 3 x 10-'
Tungsteri(Wottram) F4) 2 x 10-* W 181 S 2 x t o-* 1xto" 8 x t o-* 4 x10" I 1 x10" 1x10" 4 x 10" 3 x 10*
- W 185 S 8 x10" 4 x 10-s 3 x 10-8 1 x 10' I 1 x10" 3 x 10-8 4 x 10" 1 x 10" W 187- S 4 x10" 2 x 10*- 2 x 10" 7 x 10" 1 3 x 10-' 2 x 10-8 1 x 10*
- 6x10" Uranium (32) U 230 S 3 x t o-" 1 x to-* 1 x 10-" 5 x 10**
1 1 x 10-" 1 x10" 4x10"' 5 x 10** U 232 S 1 x 10-" 8 x 10" 3 x 10"' 3 x10" l 3 x 10-" 8 x10" 9 x 10"8 3 x 10" U 233 S 5x10-" 2 x 10* " 9 x 10*
- 3 x 10" 1 1 x 10-" 9x 10" 4 x 10-u 3 x 10" U 234 S* 6 x 10-" 9 x 10-* 2 x 10-" 3 x 10" I 1 x 10-" 9x10" 4x10"8 3 x 10" U 235 S* 5 x10* " 8 x 10-* 2 x 10-" 3 x 10" I 1 x 10-" 8 x 10** 4x10-" 3 x10" U 236 S 6 x 10-" 1 x10 2 x 10-" 3 x 10*
- 1 1 x 10-" 1 x 10-s 4 x io-" 3 x 10".
U 238. S* 7x 10* " 1 x 10-8 3 x 10-" 4 x 10" I 1 x 10* " 1 x10.a 5 x 10"* U 240 4 x 10" S 2 x 10-' 1 x 10** e x 10-* 3 x 10-* I 2 x 10-' 1 x10-8 6 x 10" 3 x10" U rsaturat - S* 1 x 10-" 1x10 s 5x10"' 3 x10" I 1 x 10* " 1 x 10*
- 5x10"8 3 x 10-*
Vanadiurn (23) V 48 S 2 x 10 ' 6 x 10" 9 x 10*
- 3 x 10" 1 6 x 10" 8 x 10*
- 2 x 10" 3 x 10" Xenon (54) Xe 131m Sub 2 x 10" 4 x 10" Xe 133.- Sub 1 x 10
- 3 x 10" Xe 133m Sub 1 x to-* 3 x 10" Xe 135.. Sub d x 10**
Ytterbium 90) 1 x 10" .._..... Yb 175 .. ... .._ S 7 x 10-' 3 x 10" 2 x 10' 1x10" I 6 x 10" 3 x 10" 2 x 10' 1x10' Yttrium (39) Y 90.., S 1 x 10" 6 x 10" 4 x 10" 2 x 10" 1 1 x 10" 6 x 10' 3 x 10" 2 x 10' Y 91m. S 2 x 10-* 1 x 10" 8 x 10" 3 x 10- 8 1 2 x 10" 1 x 10-' 6 x 10 * ' 3x10-8 Y 91. S 4 x 10-' 8 x 10' 1 x 10 *
- 3 x 10" s 3 x 10" 6 x 10 *
- 1 10 ' 3 < 10 "
Y 92. S 4 x 10-' 2 >.10 *
- 1e10-* G,10
4 3 x 10- ' 2 x 10 *
- 1 x 10" 6 >.10" Y 93.. S 2 x 10"
- 8 x 10' 6 x 10" 3 x 10" t 1 x 10-' 8 x 10" S r.10" 3 >.10- *
---_ _ __ . ..c .: .: . u n .. R/14/07 ' ""
l Pt. 20 [{} 20.1-20.602], App. B 10 CFR Ch.1 (1-1-93 Edition) APPENDIX B TO {G 20.1-20 602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-COO (iOUed (see footnotes si end of Append.a 83 asotope
- Table i Table si i
Element (atomic number) Col.14ir Col. 2- Col 1-Ai, Cot 2-- b'U'"9 (pCe rnt) (# "U (pCe rnt) Zinc (30) 2n 65 S 1x10" 3 x 10- a 4 x 10" 1 x 10' l 6 x 10" 5x t0-s 2x t0" 2x10" Zn 69m. S 4 x 10" 2x10' 1 x 10" 7 x 10" 1 3 x 10" 2 x 10*
- 1 r.10" 6 x 10" Zn 69.. E 7 x 10" 5 x 10" 2 x 10" 2 x 10*
- I 9 x 10*
- 5 x 10*
- 3 x 10*
- 2 x 10*
- Zarcor*ium (40) 2r 93 $ 1 x 10" 2 x 10" 4 x 10" 8x10" 1 1 x 10* ' 2 x 10*
- 1 x 10*
- 8 x 10*
- Zr 95-- S I x 10" 2 x 10*
- 4 x 10" 6 x 10" l 3 x 10*
- 2 x 10* 8 1 x 10* ' 6 x 10*
- 2r97 S 1 x 10* ' 5 x 10*
- 4 x 10*' 2 x 10" l 9 x 10*
- 5 x 10-* 3 x 10*' 2 x 10*
- Any single radionuchde not ested above Sub 1 x 10*
- 3 x 10*
- with decay rnode other than alpha emissann or spontaneous fission and with radioactive haff-life less than 2 hours.
Any single radionuclides not listed above 3 x 10" 9 x 10" 1 x 10" 3 x 10* * . .. with decay mode other than alpha emissaon or spontaneous f;ssion and with radioactive half-Me greater than 2 hours. Any single radionuclides ret listed 6x10ns 4 x 10" 2 x 10"* 3 x 10" above, which decays by afpha errns-sion or spontaneous fission.
'Solubic (S); Insoluble (1).
'"Sub" means that values gWen are for submersion in a semisphencalinfmite cloud of airbome material.
'These radon concentrat,ons are appropriate for protection from radon-222 combined with its short-Iked daughters.
Mematrvely. the value in Table I may be seplaced try one-third (%) "woriung levet." (A "morking lever is defined as any combination of shor14rved radon-222 daughters. polonium-218. lead-214. bismuth 214 and polonium-214. in one liter of air, without regard to.the degree of equilibrium, that will result in the uttamate ensssion of 1.3 x10' MeV of alpha particle energy.) The Tabnn 11 value may be replaced by one-thirueth (%.) of t " working Tevel" The limit on radon-222 concentrations in restricted areas may be based ort an annual average. .
'For soluble rnixtures of U-238. U-234 and U-235 in air chemical toxicity may be the Emiting factor. If the percent by weight. enrichment) of U-235 is dess than 5. the concentration value for a 40-Nnr workweek. Table 1. is 0.2 milligrams uranium per cubic rneter of air average. For any ervichmsnt the product of the sverage concentration and time of exposure dun ~ng a 4%our workweek shalt not exceed 6 x10" SA pCi-hr/mt, where SA is the speoKic activtty of the uranium inhaled. The conceritration value for Tab 6e it is 0.007 milligrams uransurn per cubic meter of air. The spearic activity for natural uranium is 6.77x10" curies per gram U. The specific actrvity for other mixtures of U-238. U-235 and U-234. If not known. shall be:
SA=3.6x10" curies / gram U U<lepleted SA=(0.4 +0.38 E+0 0034 E ') 10** E E 0.72 where E is the percentage by weight of U-235. expressed as percent NOTC in any case where there is a mucture in air or water of more than one radionuclides. the bmiting values for purposes of this Appendcx should be determined as follows:
- 1. If the identity and concentration of eacts rad onuclide in the mixture are knowit the 6miting values should be derived as tohows Determir.e, for eacts rad.onuci.de in the mixture, the ratio between the quantity present in the rnixture and the kmit othennse established in Appendix B for the speof.c radionuctice when ret in a mixture. The sum of such ratios for all the radionucredes in the mixture may set exceed "1" (i.e ** unity") ~
EamPLt.: If radionuclides A. B. and C are present in concentrations C,. C., and Cc. and if the applicable MPC's, are MPC py MPC and MfT.c tasactively, then the concentrations shall be hmited so that the following relationship exists.
%IMPC.)+ (C./MPC.)+(Cc/MPCc) "i1 4 ef either the identity or the concentration of any rad onuchde in the mixture is not known, the kmit.ng values for purposes of Appendix 6 shall be:
- a. For purposes of Table 1. Col 1-6 x 10"
- b. For purposes of Table I. Cot 2-4 x 10'
- c. For purposes of Table 41. Col 1-2 x 10'"
- d. For purposes of Table 11, Col. 2-3 x 10"
- 3. If any of the cond.t.ons specif.ed below are met, the corresponding values speched below may be used in heu of those spec fied en paragraph 2 above
- a. If the edentity of each vaa.onuchoe in the mature es known but the concentration of one or more of the radionuct des in the eniature as not known the concentrat.on lim.t for the m.m1vre is the hm.t specified en Appendra S" for the rad.onucl.oc in the
- maniure haven; the lowest Concentrat.Cn serrkt or
- b. If the edentty ot each rac.orwchoe m the mistuve es not knowr), (301 at as knowre that CC'Ta n fa3.onucl.ces sDecst.ed en appendis "6" are not present en the m,ature. the Concentral.on bmat for the morture is the IOwest Concentrat.on s.mit spec.f.ed in Append s "B'* for any rad.OnvCbCe wh.Ch es not known to be absent from the mrture or m idon 9: nate 8/I4/97 Pm G.H
J l
\
Nuclear Regulatory Commission Pt. 20 [{ 20.1-20.602), App. C
\
Taele i Taoie la
- c. Element fatom.c number) and isotope Col 1-
, Cot 2--
Col 1- Cot. 2-.- p g, Water Aer (pO/ Water mg ("O"'I '"O bO#'"U af it is known that Sr 90, t 125. I 126. I 129. I 131 (I 133. Tab.e 11 only), Po 210. Po 210. At 211. Ra 223. Ra 224. Ra 226. Ac 227. Ra 228. Th 230. Pa l 231. Th 232. Th.nat. Cm 248. Cf 254 and Fm 256 are not present. S x 10" 3 x 10" if k is known that Sr 90. I 125. I 126. I 129 (t 131. I 133, Table 18 only). PD 280. Po 210. Ra 223. Ra 226. Ra 228. Pa 231. Th.nat. Cm 248. Cf 254, and Fm 256 are not present _ _ 6 x 10" 2 x 10" If 4 is known that Sr 90. I 129 (1 125. I 126. I 131. Table it only). Pb 210. Ra 226. Ra 228. Cm 248. and Cf 254 are not present 2 x 10" . 6 x to" If k h known that (I 129. Tabte II only). Ra 226. and Ra 228 are not present .. 3 x 10*
- 1 x 10" If a h known that alpha. emitters and Sr 90. I 129. PD 210. Ac 227. Ra 228 Pa 230. Pu 241. and Ok 249 are not present-- 3 x 10" . . . . . 1 x 10"'
if k is known that alpha.eminers and Pb 210, Ac 227. Ra 228. and Pu 241 are not present . _ 3 x 10"* . 1 x 10* " If M is known that alpha.en.itters and Ac 227 are not present 3 x 10* " 1 x 10"8 ff A is known that Ac 227. Th 230. Pa 231. Pu 238. Pu 239. Pu 240. Pu 242 Pu 244.Cm 248. Cf 249 and Cf 251 are not presen' 3 x 10* " . 1 x 10* "
- 4. If a mixture of radionuclides consists of uranium and as daughters in ore dust prior to chemical separation of the uranium from the ore, the vatues specifed below may be used for uranium and its daughters through radium-226. instead of those from persgraphs 1,2. or 3 above.
- a. For purposes of Table 1. Col.1-1x10*" pG/mt gross alpha acJvity; or 5x10*" pO/mi natural uranium or 75 micrograms per cubic meter of air natural uranium.
- b. For p' urposes of Table 11. Col.1-3 x 10o: pG/mi gross alpha actMty: 2 x 10"8pG/rni natural uranium; or 3 micrograms per cubic meter of air natural uranium.
- 5. For purposes of this note, a radionuclides may be considered as not present in a mixture if (a) the ratio c? the concer.trabon of that radionuchde in the trwture (CJ to the concentratkm hmit for that rad.onuchde speofied irt Table h of Apperv.1ix 'V" (M/CJ does not exceed cormdered as not present ii. the mirture does.not (i.e.exceed C./MPC.51/10)
% 1.e and (b) the sum of such rateos for att the radionuclides (C,/MFQC,/M/% + 5 %).
Revision 2d Date Page G-12
APPENDIX I 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 Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee. Response: There were no licensee-initiated major changes to the radioactive waste systems during this reporting period. ommacums I-l
APPENDIX J l ON-SITE DISPOSAL OF SEPTIC WASTE AND COOLING TOWER SILT l l Requirement: Off-Site Dose Calculational Manual, Appendices B and F requires that the dose impact due to on-site disposal of septic waste and the cooling tower silt during the reporting year and from previous years be reported to the Commission in the Annual Radioactive Effluent Report if disposals occur during the reporting year. VYNPC will report in the Annual Radiological Effluent Release Report a list of the radionuclides present and the total radioactivity associated with the on site disposal activities at Vermont Yankee. Resnonse: There was one on-site disposal of septic waste during the reporting year. The total volume of the septage spread was approximately 10,600 gallons. The total activity spread on the 1.9 acres (southern) on-site disposal field during 1997 and from previous years was: Nuclide Activity (Ci) Mn-54 2.47E-07 Co-60 1.17E-05 Zn-65 1.90E-08 Cs-137 2.51E-06 The projected hypothetical dose from on-site disposals of septic waste is 8.16E-03 mrem /yr. This dose was calculated according to the model and the assumptions of Off-Site Dose Calculational Manual, Appendix B. mmuana J-l}}