ML20077G976
| ML20077G976 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1990 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20077G973 | List: |
| References | |
| NUDOCS 9107030291 | |
| Download: ML20077G976 (41) | |
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VEllTi(>NT YAN K EE NI'(:l E Ai! P(iW Ell (l()ltl'OllATION YERil()NT YANKEE Ni'(:1.EAlt P(IWEli STATION VEltN(IN. VI:lDi().NT ',: 4
E . 1 I I I SUPPLEMENTAL EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR I THIRD AND FOURTH QUARTERG, 1990 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN FOR 1990 I
'I
- I l
1
..-...N...,-..... \
g 8792R i
' EEFAIA In the Verrnont Yankee Ef fluent and Waste Disposal Semiannual Report covering the first and second quarters of 1990, the following corrections should be made:
None. 1 1 1 I 1 l l I I I l 3 8792R
IABLt OF CONIENIS EAEC 11 ERRATA........................................................... 1
1.0 INTRODUCTION
2 2.0 METEOROLOGICAL DATA.............................................. 3 3.0 DOSS ASSESSMTNT.................................................. 3 3.1 Doses From Liquid Effluents................................ 3 3.2 Doses From Noble Gases..................................... 3.3 Doses from Iodine-131 Iodine-133. Tritium and Radionuclides in Particulate Form With Half-Lives Greater 3 Than 8 Days................................................ ' I 3.4 3.5 Whole Body Doses in Unrestricted Areas From Direct Radiation.................................................. Doses From On-Site Disposal of Septic Waste................ 5 7 8 REFERENCES....................................................... 9 TABLES........................................................... A-1 APPENDIX A - SUPPLEMENTAL INFORMATION.................................. B-1 APPENDIX B - LIQUID HOLDUP TANKS....................................... APPENDIX C - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION........................................... C-1 APPENDIX D - RADI0 ACTIVE GASEOUS EFFLUENT MONITORING ' INSTRUMENTATION........................................... D-1 I APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. . . . . . . . . . . . . E-1 F-1 APPENDIX F - LAND USE CENSUS........................................... APPENDIX G - PROCLCS CONTROL PR0 GRAM................................... G-1 H-1 APPENDIX H - 0FF-SITE DOSE CALCULATION MANUAL. . . . . . . . . . . . . . . . . . . . . . . . . . APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TRt.AIMENT SYSTEMS......................................... I-l APPENDIX J - ON-SITE DISPOSAL OF SEPTIC WASTE.......................... J-1 I I I 8792R
-lii-l l
l
3
- L 2,IST OF TABLES Numiter Ilile EAge I
1A Gaseous Effluents - Summation Of All Releases 9 1B Gaseous Effluents - Elevated Releases 10 1C Gasenus Ef fluents - Ground Level Releases 11 1D Gaseous Effluents - NonreutJne Releases 12 2A Liquid Effluents - Summation Of All Releases 13 2B Liquid Effluents - Nonroutine Releases 14 3 Solid Waste and Irradiated Fuel Shipments 15 4 Maximum Off-Site Doses and Dose Commitments to Members of the Public 16-17 5A to 511 Annual Summary of Upper Level Joint Frequency Distribution 18-25 I I 1 I l 4 i I
-iv-8792R l
l
, VERMONT YANKEE F OLEAR POWER STATION SEMIANNUAL EFFLUENT RELEASE REPORT JULY - DECEMBErs 1990 1 1.0 1RIBODUC.Il0N 1 Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste for the second six months of the year, with data summarized on a quarterly basis. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous g l effluents released during the year 1990. Tables 5A through 5H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 1990. Radioactive effluents reported in the Semiannual Effluent Report covering the first six months of the year were used to determine the resulting doses for the first half of 1990. As required by Technical Specification 6.7.C.1 dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the " Vermont Yankee Nuclear Power Station Off-Site Dose Calculation Manual" (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 1) and actual measured meteorological data recorded during the reporting period. As required by Technical Specification 6.7.C.1.b, this report shall also include an assessment of the radiation doses from radioactive effluents to member (s) of the public due to allowed recreational activities inside the site boundary during the year. However, for this reporting period no recreational activities inside the site boundary were permitted, and, as a result, no dose assessments are required. Assessment of radiation doses (including direct radiation) to the likely most exposed real member (s) of the public for the calend.r year for the purposes of demonstrating conformance with 40CFR190 " Environmental Radiation l Protection Standards for Nuclear Power Operations," are also required to be 8792R
included in this report if the conditions indicated in Technical Specification 3.8.M.1, " Total Dose," have been exceeded during the year. Since the conditions indicated in the action statement under Technical Specification 3.8.M.2 were not entered into during the year, no additional radiation dose assessments are required. ( All calculated dose estimates for this reporting period are well below the dose criteria of 10 CFR Part 50, Appendix I. Appendices B through 11 indicate the status of reportable items per the I requirements of Technical Specifications 6.7.C.1 and 6.14.A. I l l I 1 I I I I I 8792R I
I 2.0 t1EIEORQ1011 CAL _ 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 require:nents 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 cach quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 1). A source depletion model as described in " Meteorology and Atomic Energy - 1968" (Reference 2) was used to generate deposition factors, assuming a constant deposition velocity of 0.01 m/sec. Changes in terrain elevations in the site environment were also factored into the meteorological i models. I I I i 1 I I 8792R
3.0 DOSE ASSES 2iE2iI 3.1 Dascadro;n LiquisLIffluents There were no routine or accidental liquid releases f rom Vermont Yankee during 1990. As a result, no receiving water exposure pathways could contribute to any whole body or organ doses to individuals in unrestricted areas. 3.2 Dnges Frogdlobig_Saggs 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 etfluents from the alte to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing the requirements of 10 CFR Part-50, Appendix I, Technical Specification 3.S.F.1 assures that the releases of radioactive noble geses in gaseous effluents will be kept "as low as is reasonably achievable." Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, and nearest resident in each of the sixteen principle compass directions, as well as the point of highest off-site ground level air concentration of radioactive materials, and for each of the milk animal locations located within five miles of the plant. 3.3 Doses From Iodine-131. Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days Technical Specification 3.8.G.1 limits the organ dose to a member of the public from iodine-131, iodine-133, tritium and radionuclides in
-4_
8792R l 1
I particulate form with half-lives greater than 8 days (hereafter called fodines and particulates) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I (7.5 mrem per quarter, and 15 mrem per year). By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.8.G.1 assures that the releases of iodines and particulates in gaseous effluents 4 will be kept "as low as is reasonably achievable."
- Exposure pathways that could exist as a result of the release of
.: iodines and particulates to the atmosphere include external irradiation from
- 3 activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principle compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent
) Annual Land Use Census as required by Technical Specification 3.9.D. i Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, the meat pathway was assumed to , exist at each milk animal location. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor. It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. I 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 j limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I ) and is available for uptake (see p. 26, Reference 4).
2 During the first and fourth quarters, the milk animals are assumed to receive only stored feed. lI e,m
- q
- I
I 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 ;roup due to iodines and particulates at any of the off-site receptor locations are reported in Table 4. These estimated organ doses are well below the 10 CFR Part 50, Appendix I dose criteria of Technical Specification 3.8.G.I. .I 3.4 lihole-Body Doses in Unrestricted Areas From Dirert._Radidion 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 effecta 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 crea in order to estimete the direct radiation from the station. The chamber was located at a point along the west site boundary which has been determin.= to receive the maximum direct radiation from the plant. Using i 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 (Ref erence 5) for radiation fields resulting f rom N-16 photons. The other sources of dose, including direct radiation and skyshine, to the site boundary are from low level radioactive vaste stored in the north warehouse and the low level waste storage pad facility. The annual dose is based on dose rate measurements in these two storage facilities and determined at the same most restrictive site boundary dose location as that for N-16 shine from the Turbine Building. 8792R l
The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed on Table 4 for each quarter. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any structure. F 3.5 Des ts2rm_On-Sli eJis po s aL.af_S eplicJ asic Off-Site Dose Calculational Manual, Appendix B, requires that all
- I applications of septage 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 f rom on-site disposals of septic waste is given in Appendix J.
I I I l I I 8792R
EEEERENCES
- 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.
l
- 2. Meteorology and Atomic Energy, 1968, Section 5-3.2.2, " Cloud Depletion",
pg. 204. U. S. Atomic Energy Commission, July 1968.
- 3. C. A. Pelletier, and J. D. Zimbrick, " Kinetics of Environmental Radioiodine Transport Through the Milk-Food Chain", Environmental Surveillance in the Vicinity of Nuclear Facilities Charles D. Thomas Publishers, Springfield, Illinois, 1970.
- 4. Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", U. S. Nuclear Regulatory Commission.
Office of Standards Development, Revision 1, October 1977.
- 5. W. M. Lowder, P. D. Raft, and G. dePlanque Burke, " Determination of N-16 Gamma Radiation Fields at BWR Nuclear Power Stations", Health and Safety Laboratory, Energy Research and Development Administration, Report No.
305, May 1976. 8792R
IABIL.lA
- Ytroontiankee Ei tiue ntandJiasitJi s p o s a LS emiannua LRe port Ibird and_Fanrih duarleIA d D D Gaseous _Efilutata._ __Sumation_of_ALLReleases J
__l'ait Quarter Quarter Est. Total 3 4 EtIgr3_.1 _ A. Fisolon and Activation Gases __.L_TelaLIelease ci 1 1hEiO3 7.33Et02 21. 00E +D L_. _ _2t_ Average _. release _ rain _for_.ter.iod _ _ucilses 1.5 bit 02 SEEt01_ I 3. l'qrcent oL. Itch. Spec. limit (1) % _ i dQE+00 2 11E100 B. lodines
- 1. Tota Ligdine-131 Ci 3.52E-02 4 &h03 5.00E+01
- 2. Average _Icita12_IAle l01_per10d_ _uQilsec biBI-Q3 t 5.16E E 1 __ 3 l erteat_sf_ Inch,_Sper _11 mil (2) % 2<21EiD1 2.79E-01 C. ?articulaten
___14_.f ar.ticulates._Eith T-1/ 2 > 8 days ci 4 331-Q3. __ 3,33E-03 mLDDI+QL._ h AY.CInge raleAae__IAte ior oeriod utiLgee 5.79E-04 4.24E-04
- 3. Percent of Tech. Spic. limit 1 (3) (3) 4._.GU 4 11_ alpha _IAdican11Y11y Ci 2.9BE-05 1.91E-06 I
D. Tritium
- 1. TclaLJ.ticale Cf. LkSE1Q1 2 32E+01 25.00E+0_1_
_2 t_.Avtrar ormitaat_ rate _for_parloL__.n31aec 3 AlEiOO . 3.67E+00 Percr.tLntlechi Sper,_ limit I (3) (3) (1) Technical Specification 3.8.F.1.a for gamma air dose. l (2) Technical Specification 3.8.G.1 for dose from I-131, 1-133, Tritium, and l radionuclides in particulate form. (3) Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulates are included with I-131 above ia Part B. 1 ND Not Detected. 3792R
d
'MLE_.1 B EtramLYautec Elliuent and3a ain__ Diar ad al_SiminunuaLEe v er.t ThirLand_ fourth.. Quarter 1*_1220 Onatons._Eliluents - Elevattd_Reltate (1)
Continuous _Made Batch _11cde Euclidta_ER1gaggd Unit _ Quarter Quarter Quarter Quarter 3 4 3 4 L._Einsion,_Gasts Kryplon-85 Ci ND ND _
.___XIyplgn-85m Ci 1.60E+01, 7.11E100 Krypton-87 Ci 5.65E+01 2,181tD1
__ Krypton-SS Ci (31EiO1 1.19E101 _ ._ __._ Xenon-133 Ci 2.92E+01 3.76Et00 ___ Xenon.135 Ci 7.03E+01 2.01E401 Xenna-135m Ci 2.00E+02 1., 21 E + 0 2 ___Ztnen-138 Ci 8112E102 5.82E102 Ci _ Unidentifled Ci TalaLLcI_pg riod C1 1.24E+03 7 . 8 3 E + 0 2__,__ 2._lodines_ ___ Iodina-111 C1 3.' -Q2 4tD5E-03 Iodine-133 Ci 4.7BE-02 1.20E-02 Indine-135 Ci 6.44E-02 4.89E-02 TotaLlor_E.crind C1 1.47E-01 1.01E-01 3m_ Ear.ticultte s Strontium-89 C1 1.82E-03 1.74E-03 Strontium nD C1 2 . 8 8 E--0 5 1.92E-05 Cesium-134 Ci S_allE-QL 7.69 E06 Cesium-L3]_ Ci 5d6E-05 2. 50E03 Barium-Lanthanum-140 Ci 2d2E-Q3 1.281-Q3. Manganese-54 Ci 2.96E-05 Bi ihE-05 lint.-65 Ci 5 . 0.61-Q 5 1.35E-05 Cohalt-58 Ci UD 6.87E-06 Cohalt-60 Ci 2.69E-04 1,7M-D4 Iron-59 Ci ND 2.54E-05 Ceriutn-141 Ci ND 2.89E-06 (1) There were no batch mode gaseous releases for this, reporting period. ND - Not detected at the plant stack. 8792R
IMLLLC Vermoot_Jankee ELiluentand_liattt_Dispaal_fiemiannual_hepart IttirLand_f.our.ttL9aarlera_1210 { Ganeoua_ Elliuents - Grnand Level Releas.es Tuere were no routine sneasured ground level continuous or batch inode gaseous releases during the third or fourth quarters of 1990. I I I I I I l 8792R
E TABLE ID ytrment Yan}u ELLluenLAnd_Wasiells psaaLSemlannuaLRepnrt I Third and_JguttlLQunI.tgrs_191Q Gase.ouLEf flutnis - RouroutinLAtitaats I There were no nonroutine or accidental gaseous release;; durlng the third or fourth quarters of 1990. I I I I I I 5 8792R
~ TABLE 2A YarmonLYankte h ((Unnt and Wag.tg_ Disposal SemiannuaLPernri Third ani.Inutlh. Quarters 1933 Liquid Ef flutDlJL. . SDIZLation_Df Al1 Releagga I There were no liquid releases during the third or fourth quarters of 1990.
~
I I I I I I I 1 8792R
l 4 TABLE 2B Ettmont Yanttt ELiluent and Wam1Luisp.gsal. Semiatuiual_ RepgIl Ihird andlnur11LQuaricIa_.19.2D
- Liquisilfiluents - Nour.online_Reltaans l
l - There were no nonroutine or accidental releases during the third or fourth quarters i I f of 1990. !I I 4 l \I . I 1 lI l r I ' lI b !I lI lI 879D i 4 I
IABLL.3 YCImQat Yanket I L Efilu t n L_and_M A11cJ21g p g a a l S e m i ann ual.ltner t IllirLanLEcurih._QuaricIb_.1310 S oliji..M at t e._and._IIInd in Ltd_f.utl._Shipm cAls A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel): None (
~ ~
_j) nit 6-Month Est. Total
- _Ieriod Error. 3 _
- 1. Type of Waste
- a. Spent resins, filter sludges, evaporator m3 htLtomaun.LCL, C
- b. Dry compressible waste, contaminated m
______.cquipment _ tic.
- c. Irradiated components, control rods, .C{
m tig. Ci * *
- 2. Estimate of Major Nuclide Composition (By Type of Waste): *
- a. % %
X % l l I _ 1 % I
- 3. Solid Waste Disposition
- NumhcI_QL Shipmtats t'2dt_QL IranspSIIAkinn Dc_atinatiun B. I: radiated Fuel Shipments (Disposition): None C. Sur.ls'nental information *
- 1) Clas of solid waste containers shipped:
- 2) Types of containers used: *
- 3) Solidifiestion agent or absorbent: *
*Not applicable. No solid waste or irradiated fuel shipments during the third and the fourth que.rters of 1990.
8792R l
IABLE_3 U
} Eerm011LYADIee J
E filue n tand_Wa s t e_Ris po s a LS emi annualle va rl Ih1rd and_En.urth Quarlera d 92D Maximum *_O f f -S Lt e_Do s e s_and_Das elemilment a__ta tiembe rs_o Lthe_.tuhlic l Dose (mrem)*** 1st 2nd 3rd 4th I Ouarler Quarler . Quarter Quarler.. Year **
- _ Source Liquid Effluents (a) - - - -
Airborne Ef fluents lodines and Farticulates 2.42E-02 5.60E-01 1.66E+00 2.09E-02 2.27E400 (1) (2) (2) (1) Noble Gases Beta Air 1.13501 6.41E-02 1.11E-01 8.52E-02 3.73E-01 (mrad) (3) (3) (3) (3) Gamma Air 1.29E-01 3.18E-02 2.85E-01 1.06E-01 5.52E-01 (rnrad ) (4) (4) (5) (4) 2.87E+00 3.59E+00 1.43E+01 l Whole Body Dose from 3.74E+00 4.0$E+00 Facility Direct Radiation ( m r err ) * * *
- dge 'ypothetical Dose f rom 1.24E-02 On-Site Septic Waste Disposal 3
*" Maximum" means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.
**" Maximum" done for the year is the sum of the maximum doses for each quarter.
I This results in a conservative yearly dose estimate, but still well within the limits of 10CFR50.
***The numbered footnotes indicate the location of the dose receptor, age group, and organ, where appropriate.
**** Maximum receptor point, west site boundary, no resident present.
(1) Child / Bone. NW-2900 meters. (2) Infant / Thyroid, NW-4700 meters. I (3) hM-2900 meters. 8792R
I IABLL.h (Continued) (4) IN-550 meters. (5) 0-400 meters. (n) There were no liquid releases during this reporting period. I
;I I
- I I
I I . I I I I I I I 8792R l
I TABLE 5A I vtRMohi YAkttE JAW 90 0EC90 METEOROLOGICAL DATA J0lWT FREQUENCY OlsTRIBUTION
$1 ABILITY CLAll A CLAll FREQUENCY (PERCEWT) e ,09 297.0 FT VlWO DATA WIWO O!RECTION FROM SPEED (MPH) N kNE hE EhE E E$E $E $$E $ $$W SW VSW W WW WW kWV VR8L 101AL 0 0 0 I
CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C3 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 2 28,57 I (1) 14.29 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 14.29 .00 .00 (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 47 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 4 I (2) 8 12
.00 (1) 14.29 1
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00 0
.00
.00 14.29 1
.00
.00 0
.00
.00 0
.00 28.57 2
, (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 13 18 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0 0 2 (1) .00 .00 .00 .00 .00 .00 14.29 .00 .00 .00 .00 .00 .00 .00 14.29 .00 .00 28.57 (2) .00 .0. .00 . 00 .00 .00 .01 .00 .00 .00 .00 .30 .00 .00 .01 .00 .00 .02 I 19 24 (1) (2) 00
.00 0
.00
.06 0
.00
.00 0
.00 0
00
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00
.00 0
.00 0
.00 14.29
.01 1
.00
.00 0
14.29
.01 1
I 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 $ PEE 05 2 0 0 0 0 0 1 0 0 0 0 0 0 0 3 1 0 7 I (1) 28.57 (2) .02
.00
.00
.00
.00
.00
.00 (1): PERCENT OF ALL G010 OBSERVATIONS FOR THil PACE
.00
.00
.00 14.29
.00 .01
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 42.86 14.29
.00 .04 .01
.00 100.00
.00 .09 (2) PERCENT OF ALL 0000 OBSERVATIONS FOR THis PERIOD Cs CALM (WIWO $ PEED LESS THAN OR EQUAL 10 .60 MP'n)
I I I
.I
- TABLE fB 1 L VERMONT YAWKEE JAN90 0Et90 PETE0a0LocicAL DATA JolNT FREoVENCY DitTRIBU110W
??7.0 ft WlWD DATA $1ABILl;Y CLAtt B CLA$s FREQUENCY (PERCENT) = 40 Wlho DIRTCT10N fROM
$ PEE 0(MFM) W hht NE Eht E ESE SE $$E S $$V SW V5W W WV WW WWW VRill TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM 0 0 0 0 I (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 00
.00
.00
.00
.00
.00
.00
.00 0 0 0 0 0 0 0 0 0 0 1 0 1 c3 0 0 0 0 0
.00 3.13 .00 3.13 (1) .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 0
.00 0
.00 0
.00 0
.01 4
.00 0
.01 6
47 1 0 0 0 0 0 1 0 0 0 0 (1) 3.13 .00 .00 .00 .00 .00 3.13 .00 00 .00 .00 .00 .00 .00 .00 12.50 .00 18.75 (2) .01 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .07 .I B 12 2 0 0 0 0 0 1 2 0 0 0 0 0 0 0 1 0 6 (1) 6.25 .00 .00 .00 .00 .00 3.13 6.25 .00 .00 .00 .00 .01 .00 . ', J 3.13 .00 18.75 (2) .02 .00 .00 .00 .00 .00 .01 .02 .00 .00 .00 .00 .00 .00 . 30 .01 .00 .07 I 13 18 (1) 3.13 1
.00 0
.00 0
.00 0
.00 0
.00 0 0
.00 6.25 3.13 2 1
.00 0
.00 3.13 0 1 0
.00 9.38 3 0
.00 4.38 3
.00 0
34.38 11 (2) .01 .00 .00 .00 .00 .00 .00 .02 .01 .00 .00 .01 .00 .04 .00 .04 .00 14 0 0 0 0 4 2 0 2 0 8 1 19 24 (1) .00 0
.00 0
.00 0
.00 0
.00 0
.00 0
.00 0
.00 0
.00 .00 .00 00 12.50 6.25 .00 6.25 .00 25.00
.10 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .02 .00 .02 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 00
.00
.00
.00
.00 00
.00 00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 ALL SPEE0s 4 0 0 0 0 0 2 4 1 0 0 1 4 5 0 11 0 32 (1) 12.50 .00 .00 .00 .00 .00 6.25 12.50 3.13 .00 .00 3.13 12.50 15.63 .00 34.38 .00 100.00 l (2) .05 .00 .00 .00 .00 .00 .02 .05 .01 .00 .00 .01 .05 .06 .v0 .14 .00 40 (1)*PEttENT Of ALL 000) OBSERVA110NS FOR THIS PACE (2)*PERCEWT OF ALL 0000 OBSERVAi!Oh5 FOR THIS PERIOD Ca CALM (WIND $ PEED LESS THAN OR EQUAL 10 .60 MPH) l I
l
- TATILE SC i L V!RMONT YAALEE JAh90 CEC 90 METEOROLOGICAL DATA J0!NT FREQUENCY OlsTRituil0N
~
297.0 71 VINO D AT A $1A$1LITY CLA$$ C CLAS$ FREQUENCY (PERCENT) = 1.81 WINO O!RICT!JW FROM IPEED(MPH) N kht hE ENE E ESE SE $$E $ $$V $W WSW W VWW kJ WWW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
.00 .00 .00 .00 .00 .00 .00 1 (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 .00 .00 .00 .00 .00 .00 .00 C3 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0 2 (1) .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .68 .00 .68 .00 1.37 I (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .01 .00 .01 .00 .02 4-7 2 2 1 0 2 0 2 1 1 0 1 1 0 1 1 7 0 22 (1) 1.37 1.37 68 .00 1.37 .00 1.37 .68 68 00 .68 .68 .00 .68 .68 4.79 .00 15.07 (2) .02 .02 .01 .00 .02 .00 .02 .01 .01 .00 .01 01 .00 .01 .01 .09 .00 .27 I 8 12 2 0 0 0 0 . 2 10 5 1 0 1 0 2 5 22 0 52 (1) 1.37 .00 00 .00 .00 1.P 1.37 6.85 3.42 .68 .00 .68 .00 1.37 3.42 15.07 00 35.62 (2) .02 .00 00 .00 .00 .02 .02 .12 .06 .01 .00 .01 .00 .02 .06 .27 .00 .64 I 13 18 (1) 1.37 2
.00 0
.00 0
.00 0
.00 0
.68 1 0
.00 2.74 6.85 4 10
.00 0
.00 0 1 7
.68 4.79 2.74 4 1
.(f. 11.64 17
.00 0
32.19 47 (2) .02 .00 .00 . 0C . .00 .01 .00 .05 .12 .00 .00 .01 .09 05 .01 .21 00 .58 0 20 l 19-24 (1) .00 0
.00 0
.00 0
.00 0
.00 0
.00 0
.00 0
.00 0
.65 1
0
.00 0 1 6
.68 4.11 1.37 2 0
.00 6.85 10
.00 13.70 (2) .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .01 .07 .02 .00 12 .00 .25 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 0 3 I (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 00
.00
.00
.00
.00
.00
.00
.00
.63
.01
.68
.01
.68
.01
.00
.00 2.05
.04 ALL $PEEDS 6 2 1 0 2 3 4 15 17 1 1 4 13 11 8 58 0 146 (1) 4.11 1.37 .68 .00 1.37 2.05 2.74 10.27 11.64 .68 .68 2.74 8.90 7.53 5.48 39.73 .00 100.00 l (2) .07 .02 .01 .00 .02 .04 .05 .19 .21 .01 .01 .05 .16 .14 .10 .72 .00 1.81 (1)sPERCENT OF ALL GOCO OB$ERVAfl0NS FOR TM1$ FAGE (2)sPERCENT OF ALL C000 OBSERVATIcht FOR TMll PitlCO Ca CALM (WIND $ PEE 0 LE$$ TKAN OR EDUAL 10 .60 MPM) l I
I I
W TABl.E 5D. [ VEEMOW1 YAktti JAW 90 DIC90 Mtit0ROLOGltAt DATA JolW1 f REQUtWCY Ols1RIBuil0W
- 297.0 FT WIND CAtt STABILITY CLAlt 0 CLASS FRt0VENCY (FERCINT) e 49.26 WIND C 'RIC110W FROM I 5 Fit 0(MPN) W kWE ht (ht t ist $t $$t S $$W SW VSW W VWW WW hWW VRBL 101At 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 .M .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I (2) .00 .00 .00 .00 .00 .(v .no .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C3 53 32 31 13 32 44 53 46 24 15 18 8 8 15 36 37 0 485 B (1) 1.33 .80 78 .83 .80 1.10 1.33 1.15 .60 .38 45 .20 .20 .38 .90 .93 .00 12.18 (2) .66 40 .38 41 40 .54 .66 .57 .30 .19 .22 10 .10 .19 45 4ti .00 6.00 g
47 75 42 23 27 48 91 159 114 77 25 9 10 13 F2 52 186 0 9 73 (1) 1.88 1.05 .58 .68 1.21 2.28 3.99 2.86 1.93 .63 .23 .25 .33 .55 1.31 4.67 .00 24.43 (2) ,93 .52 .28 .33 .59 1.13 1.97 1,41 .95 .31 .11 .12 .16 .27 .64 2.30 .00 12.03 I 8 12 148 23 7 8 28 29 74 132 182 38 21 31 51 114 58 204 0 1148 (1) 3.72 .58 18 .20 .70 . 73 1.86 3.31 4.5/ .95 .53 .78 1.28 2.86 1,46 3.12 .00 28,82 (2) 1.83 .28 .09 .10 .35 .36 .92 1.63 2.25 .47 .26 .38 .63 1.41 .72 2.52 .00 14.20 13 18 93 12 4 2 0 4 6 31 142 23 12 19 91 187 104 163 0 893 (1) 2.33 .30 10 .05 .00 .10 .15 78 3.57 .58 .30 48 2.28 4.69 2.61 4.09 .00 22.42 (2) 1.15 .15 .05 ,.02 .00 .05 .07 .38 1.76 .28 .15 .23 1.13 2.31 1.29 2.02 .00 11.04 19 24 24 3 0 0 0 1 0 5 59 1 1 2 23 M 56 120 0 383 1 (1) (2)
.60
.30
.08
.04
.00
.00
.00
.00
.00
.00
.03
.01
.00
.00 13 1.48
.06 .73
.03
.01
.03
.01
.05
.0'
.58 2.21 1.41 3.01
.28 1.09 .69 1,48
.00
.00 9.62 4.74 GT 24 4 1 0 0 0 0 0 4 6 1 0 0 3 28 15 39 0 101 (1) 10 .03 .00 .00 .00 .00 .00 .10 .15 .03 .00 .00 .08 .70 .38 .98 .00 2.54 I (2) .05 .01 .00 .00 .00 .00 .00 .05 .07 .01 .00 .00 .04 .35 .19 48 .00 1.25 ALL srtt0s 397 113 65 70 108 169 292 332 490 103 61 70 189 454 321 749 0 3983 (1) 9.97 2.64 1.63 1.76 2.71 4.24 7.33 8.34 12.30 2.59 1.53 1.76 4.75 11.40 8.06 18.80 .00 100.00 (2) 4.91 1.40 .80 .87 1.34 2.09 3.61 4.11 6.06 1.27 .75 .87 2.34 5.61 3.97 9.26 I .00 49.26 (1)*PtRCtWT OF ALL GOCO 085tRVAtlohl FOR THit PAGE (2):PERCELT OF ALL 0000 OB$tRVAfl0NS 708 THis PER100 Cs CALM (VlWD SPito LESS THAN OR EQUAL 10 .60 MPM) l I
I 21-
TABLE SE [ vitMOWT YAhKtt JAk90 CEC 90 Mtitot0LO0lCAL DATA J0lh1 F ALQUtWCY 01518!8Uil0W
~
297.0 FT VlWD CATA $1ABILlif CLAll t CLAll Ftt0UtWCY (P[tCthi) e 33.30 VlWD OlttCil0W FROM .I EFEED(MPN) W hht Et thf ( ($t 5t SSE $ $5W SW V5W W WWW WW kWW vaSL 101AL CALM 0 0 t' 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 I (2) .00 .00
.D0
.00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 00 .00 .00 .00 .00 C3 70 50 50 45 42 62 SO 55 32 22 16 8 8 18 21 60 0 639 (1) 2.60 1.66 1.66 1.67 1.56 2.30 2.97 2.04 1.19 62 .59 .30 .30 .67 .78 2.23 00 23.73 (2) .87 .62 .62 .56 .52 .77 99 .68 40 .27 .20 .10 10 .22 .26 .74 00 7.90 47 125 19 5 14 15 60 209 134 87 23 17 14 22 23 46 176 0 989 (1) 4.64 .71 19 .52 .56 2.23 7.76 4.98 3.23 .85 .63 .52 .82 .85 1.71 6.54 00 36.72 (2) 1.55 .23 .06 .17 .19 .74 2.58 1,66 1.08 28 .21 .17 .27 .28 .57 2.18 .00 12.23 8 12 58 8 0 0 2 7 70 97 94 37 12 15 59 66 42 146 0 713 (1) 2.15 .30 .00 .00 .07 .26 2.60 3.60 3.49 1.37 45 .56 2.19 2.45 1.56 5.42 00 26.48 (2) .72 .10 .0J .00 .02 .09 .87 1.20 1.16 46 15 .19 .73 .52 .52 1.81 00 8.82 13 18 12 1 0 0 0 1 2 26 52 20 3 4 22 51 37 70 0 301 (1) .45 .04 .00 .00 .00 .04 .07 97 1.93 74 .11 15 .82 1.89 1.37 2.60 .00 11.18 (2) .15 .01 .00 00 , .00 .01 .C2 .32 .64 .25 .04 .05 .27 .63 46 .87 .00 3.72 19 24 2 0 0 0 0 0 0 2 0 4 2 1 3 5 3 17 0 48 (1) .07 .00 .00 .00 .00 .00 .00 .07 .33 .4 .07 . 04 11 .19 .11 .63 00 1.78 (2) .02 .00 .00 .00 .00 .00 .00 .02 .11 .05 .02 .01 .04 .06 .04 .21 .00 .59 GT 24 0 0 0 0 0 0 0 1 0 0 0 0 0 1 1 0 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .04 .00 .00 .00 .00 .00 .04 .04 .00 .00 .11 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .01 .01 .00 .00 .04 ALL SPitOS 267 78 55 59 59 130 361 315 274 106 50 62 114 164 150 469 0 2693 (1) 9.91 2.90 2.04 2.19 2.19 4.83 13.41 11.70 10.17 3.94 1.66 1.56 4.23 6.09 5.57 17.42 .00 100.00 (2) 3.30 .96 .68 .73 .73 1.61 4.46 3.90 3.39 1.31 .62 .52 1.41 2.03 1.66 5.80 .00 33.30 (1)* PERCENT OF ALL C000 OB$ttvATIONS FOR THl$ PACE (2)sithCENT OF ALL GOOD OS$tRVATIONS FOR THis PERIOD Ce CALM (WIND $Pt[0 Lit $ THAW OR EQUAL TO .60 kPH)
TABLE 5F L 1 vtRMoht T Autt JAh90 0tC90 Mtit080 LOGICAL DAT A J01NT FREQUtWCY Oltf RIBUTION 297.0 F' WIND DATA $1ABILITT CLAll F CLA$$ Ikt0VtWCY (PIRCthi) e 12.70 WIWO DIRttil0W FROM
$ttt0(MPH) N hbt ht [ht E ($1 $t $$t $ $$W $W vsw W LNW WW kWW VRBL TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C3 33 35 17 17 29 37 45 32 16 11 9 9 11 15 16 38 0 370 lg (1) 3,21 3.41 1. E.6 1.66 2.82 3 t,0 4.38 3.12 1.56 1.07 .88 .65 1.07 1.46 1.56 3.70 .00 36.03 (2) 41 43 .21 .21 .36 46 .56 40 .20 .14 .11 .11 14 19 .20 47 .00 4.58 47 32 5 3 7 16 35 99 77 31 12 6 16 22 18 25 58 0 462 m (1) 3.12 .49 .29 .68 1,56 3.41 9.64 7.50 3.02 1.'7 .58 1.56 2.14 1.75 2.43 5.65 .00 44.99 (2) 40 .06 .04 .09 .20 .43 1.22 .95 .38 .15 .07 .20 .27 .22 .31 .72 .00 5.71 8 12 2 0 0 1 0 1 29 27 16 6 6 7 10 14 10 51 0 180 (1) 19 .00 .00 10 .00 10 2.82 2.63 1.56 .58 .58 .68 .97 1.3A 97 4.97 .00 17.53 (2) .02 .00 .00 .01 00 .01 .36 .33 .20 .07 .07 .09 .12 ..t 12 .63 .00 2.23 B 13 18 1 0 0 0 0 0 0 0 3 3 0 1 0 2 2 3 0 15 2 (1) .10 .00 .00 .00 .00 .00 .00 .00 .29 .29 .0L 10 .00 19 .19 .29 .00 1,46 (2) .01 .00 .00 . 00. 00 .00 .00 .00 .04 .04 .t i .we .00 .02 .02 .04 .00 19 19 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .C1 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I (1)
(2)
.00
.00
.00
.00
.00
.00
.00
.00 00 00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00 00
.00 00
.00 ALL $ PEE 0$ 68 40 20 25 45 73 173 136 66 32 21 33 43 49 53 150 0" 1027 (1) 6.62 3.89 1.95 2.43 4.32 7.11 16.85 13.24 6.43 3.12 2.04 3.21 4.19 4.7' 5.16 14.61 .00 100.00 (2) .84 49 .25 .31 .56 .90 2.14 1.68 '.82 40 .26 41 .53 .61 .66 1.66 .00 12.70 (1NERCENT OF ALL GC"3) OB$tRVAfloks FOR THit FACE (2bFERCENT Of ALL C000 OB$tR\ATIOh5 FOR IMIS FER100 C= CALM (WINO $ PIED List THAW OR EQUAL 10 .60 MPM) l l
L mus [ VIRMONT YAkttt JAW 90+0tC90 MEtt0ROLOGlCAL DAT A J0thi f tt0V!WCT sllitlBUTIDW
~
297.0 ft Wik0 OATA $fABILiti CLAS$ 0 CLA$$ fat 0VtWCT (FitCENT)
- 2.45 WIND DIRECTION FRCN SPitD(MP ;) W kht hE (sit E ESE $( $$E $ $$W $W WSW W VWW WW kkW YRBL TOTAL 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 C3 6 2 3 2 5 4 6 4 2 1 3 1 1 2 4 7 0 53 (1) 3.03 1.01 1.52 1.01 2.53 2.02 3.03 2.02 1.01 51 1.52 .51 .51 1.01 2.02 3.54 .00 26.77 (2) .07 02 04 .02 ' .06 .05 .07 .05 .02 .01 . 04 .01 .01 .02 .05 .09 .00 .66 4T 7 1 0 t 3 8 12 14 9 2 7 3 2 8 5 11 0 94 (1) 3.54 .51 .00 1.01 1.52 4.04 6.06 7.07 4.55 1.01 3.54 1.52 1.01 4.04 2.53 5.56 .00 47.47 (2) .09 .01 .00 .02 .04 .10 .15 .17 .11 .02 .09 .04 .02 .10 .06 .14 .00 1.16 8 12 0 0 0 1 0 1 8 10 4 0 3 0 6 5 1 6 0 45 (1) .00 .00 .00 .51 .00 .51 4.04 5.05 2.02 00 1.52 .00 3.03 2.53 .51 3.03 .00 22.73 (2) .00 .00 .00 .01 .00 .01 .10 .12 .05 .00 .04 .00 .07 .06 .01 .07 .00 .56 13 18 0 0 0 0 0 0 0 0 0 0 0 0 0 3 2 1 0 6 (1) .00 .00 .00 .00 00 .00 .00 .00 .00 00 .00 .00 .00 1.52 1.01 .51 .00 3.03 (2) .00 .00 .00 ,00 .00 .00 .00 .00 .00 00 .00 .00 .00 . D4 .02 .01 .00 .07 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 G1 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 $PEEDS 13 3 3 5 8 13 26 28 15 3 13 4 9 18 12 25 0 198 (1) 6.57 1.52 1.52 2.53 4.04 6.57 13.13 14.14 7.58 1.52 4.57 2.02 4.55 9.09 6.06 12.63 .00 100.00 (2) .16 .04 .04 .06 .10 .16 .32 .35 .19 .04 16 .05 .11 .22 .15 .31 .00 2.45 (1):FERCENT OF ALL 0000 085tRVAT10h5 FOR THis PAGE (2)sPERCtWT OF ALL GOCO 085tRVAfl0NS FOR THit PERIOD Cs CALM (WIWD $PtED LE$$ THAN OR (0UAL 10 .60 MPM)
- TABLESli 1 vtRMDNY YAhttt JAh90 CIC90 MET (0E0 LOGICAL DATA JOINT FREQUthtY DISTRIBUTION 297.0 F1 WIND CATA STA81 Lily CLAtt ALL CL Ast F Rt0UtWCY (PIRCtWT) = 100.00 WINO OlktC110N FROM
$PEtC(MPM) N kht kt th! E ESE SE S$t $ $$W $W WIW W WWW WW kWW VRBL TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM 0 0 0
.00 .00 .00 .00 .00 .00 .00 .00 I (1)
(2)
.00
.00
.00
.00 00 00
.0L
.00
.00
.00 00
.00
.00
.00
.00
.00
.00
.00 00
.00 .00 .00 .00 .00 .00 .00 .00 .00 C3 163 119 101 97 1C8 147 164 137 74 49 46 26 28 51 78 144 0 1552 (1) 2.02 1.47 1.25 1.20 1.34 1,82 2.28 1.69 .92 61 .57 .32 .35 .63 96 1.78 .00 19.19 I (2) 2.02 1.47 1.25 1.20 1.34 1.82 2.28 1.69 .92 .61 .57 .32 .35 .63 .96 1.78 .00 19.19 47 242 69 32 50 64 194 482 340 205 62 40 44 59 72 129 442 0 2546 (1) 2.99 .85 .f 0 .62 1.04 2.40 5.96 4.20 2.54 77 49 .54 .73 .89 1.60 5.47 .00 31.49 (2) 2.99 .25 40 .62 1.04 2.40 5.96 4.20 2.54 .77 49 .54 . 73 .89 1.60 5.47 .00 31.49 I 8 12 213 31 7 10 30 40 164 278 301 82 42 54 126 201 117 430 0 2146 (1) 2.63 .38 .09 .12 .37 49 2.28 3.44 3.72 1.01 .52 .67 1.56 2.49 1.45 5.32 .00 26.54 (2) 2.63 .38 .09 .12 .37 49 2.28 3.44 3.72 1.01 .52 .67 1.56 2.49 1.45 5.32 .00 26.54 5 13 18 109 13 4 2 0 6 9 63 208 46 15 26 120 250 147 257 0 1275 (1) 1.35 .16 .05 .02 .00 .07 .11 78 2.57 .57 .19 .32 1.48 3.09 1.82 3.18 .00 15.77 (2) 1.35 16 .05 02 .00 .07 .11 .78 2.57 .57 .19 .32 1.48 3.09 1.82 3.18 .00 15.77 19 24 26 3 0 0 0 1 0 7 69 5 3 4 36 97 59 150 0 460 (1) .32 .04 .00 .00 .00 .01 .00 09 .85 .06 .04 .05 45 1.20 . 73 1.66 .00 5.69 (2) .32 .04 .00 .00 .00 .01 .00 .09 .85 .06 .04 .03 45 1.20 .73 1.66 .00 5.69 01 24 4 1 0 0 0 0 0 5 6 1 0 0 3 30 17 40 0 107 I (1)
(2)
.05
.05
.01
.01
.00
.00
.00
.00
.00
.00
.00
.00
.00
.00
.06
.06
.07
.07
.01
.01 00
.00
.00
.00
.04
.04
.37 37
.21
.21
.49 49
.00
.00 1.32 1.32 ALL $Pttos 757 236 144 159 272 368 859 830 663 245 146 154 372 701 547 1463 0 8086 (1) 9.36 2.92 1.78 1.97 2.75 4.20 10.62 10.26 10.67 3.03 1.81 1.90 4.60 8.67 6.76 18.09 .00 100.00 l (2) 9.36 2.92 1.78 1.97 2.75 4.80 10.62 10.26 10.67 3.03 1.81 1.90 4.60 8.67 6.76 18.09 .00 100.00 (1)*PERCtWT OF ALL C000 OB$tRVA110hl FC4 THit PACE (2)* PERCENT OF ALL GCCO OB5tRVA110ks FOR THit PERIOD Co CALM (Wik0 EPEED Litt THAN OR 10UAL 10 .60 MPH) l I
I l
.u.
p APPUiDIX A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information { Third and Fourth Quarters, 1990 Facility: Vermont Yankee _Hucitar Power Station Licent.eet VcImont_lankeithucitar..forcr corocration 1A. Technical Specification Limits - Dose and Dose Rate Ie chnic a LS p e cific ation_and_C at e go ry Limit 1 a. Noble Gaggs 3.8.E.1 Total body dose rate 500 mrem /yr 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Gansna air dose 5 n. rad 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 I 3.8.F.1 Beta air dose 20 mrad in a year
- b. Iod ine-1112_ladine-133. _ Trit 11EILand_ Radionuclides in Particulate Form With flalf-Lives Grcaler Than 8 Days 3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose . 15 mrem in a year l
- c. Liquida 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 mrem in a year 3.8.B.1 Organ dose 5 mrem in a qua-ter 3.8.B.1 ?rgan dose 10 mrem in a year A-1 S 8792R
2A. Technical Specification Limits - Concentration [ Ic chnic a LS p e c if ic ali citandlate goIS Limit
~
- a. Hohlt linacs No MPC limits I b. lodine-131. losiine-133. Tritium _And RadionuclidcL_in _ P a r t iculate.J.cIs .llith i Kalf-LiYtS_GItater Than 8_Da16! No MPC limits
- c. Liquid 5 3.8.A.1 Total iraction of MPC excluding noble gases (10CTR20, Appendix B.
Table II. Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 uCi/cc
- 3. Average Energy Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.
- a. Average gamma energy: 3rd Quarter 1.04E+00 MeV/ dis I 4th Quarter 1.12E+00 MeV/ dis
- b. Average beta energy: Not Applicable
- 4. Measurements and Approximations of Total Radioactivity Frovided below are the methods used to seasure or approximate the total radioactivity in offluents and the methods used to determine radionuclide composition.
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- a. Fission and Activation Gases Stack-continuous monitors normally show less than de'; table releases of fission and activation gases. Therefore, to determine t.- level of releases, gas grab samples are drawn at the stack monthly or when the noble gas monitors show an increcse. The grab samples are analyzed by gamma spectroscopy to determine the isotopic composition and resultant release rate. The error involved in these steps may be approximately 1100 percent.
- b. lodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters
{ and cartridge are removed weekly (if releases are less than 4 percent of the Tech Spec limit), or daily (if they are greater than 4 percent of the limit), and are analyzed for radiciodine 131, 132, 133, 134, and 135. The error involved in these steps may be approximately 150 percent,
- c. Part.iculates The particulate filters uescribed in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately 150 percent.
- d. Liquid Effluents Radioactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liqu d effluents i released. For each batch, station records are retained of the total activity (mci) released, concentration (uCi/ml) of gross A-3 8792R
radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.
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Each batch of radioactive liquid effluent released is analyzed for gross gamma end gamma isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch. released during a month, is also analyzed for tritium, SR-89, I SR-90, gross beta and gross alpha radioactivity, in addition to gamma spectroscopy. There were no liquid releases during the reporting period. I 5. Batch Releases I a. Liquid There were no routine liquid batch releases during the reporting period.
- b. Gaseous l There were no routine gaseous batch releases during the reporting ,
period.
- 6. Abnormal Releases
- a. Liquid There were no nonroutine liquid releases during the reporting period.
- b. Gaseous There were no nonroutine gaseous releases during the reporting period.
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~ APPENDIX B F LIQUID HOLDUP TANKS L r Requirement.: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report per Technical Specification 6.7.C.1. Respanic The limits of Technical Specification 3.8.D.1 were not exceeded durinE this reporting period. I I l l l l l l l B-1 8792R I
APPU4 DIX C RADIOACTIVE LIQUID ETTLUENT MONITORING INSTRUMENTATION [~ Requirement: Radioactive liquid ef fluent monit oring instrumentation channels L 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, en explanation in the next Semiannual Effluent Release Report of the reason (s) f or delay in correcting the inoperability are required per Technical Specification 6.7.C.1. I Respcnne: Since the requirements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid effluent monitoring !*strumentation were met for this reporting period, no response is t w . ired. I I I I I I I l C-1 8792R l L .
API'D4 DIX D RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRlHDiTATION ( Requirement: Radioactive gaseous effluent monitvring instrumentation channels { are required to be operable in accordance with Technical Specifisation Table 3.9.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status I within 30 days pur suant to Note 5 of Table 3.9.2, an explanation in the next Semiannual Effluent Release Report of the reasen(s) for the deley in correcting the inoperability is required per Technical Specification 6.7.C.1. I Responsct Since the requirements of Technical Specification Table 3.9.2 governing the operability of radioactive gaseous ef fluent monitoring instrumentation were met for this reporting period, no response is required. l I I I
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APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirfmtat The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.9.C. With milk - samples no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3, Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Reports (1) identif y the cause(s) of the sample (s) no longer being available. (2) identify the new location (s) for obtaining availabic replacement samples and (3) include revised ODCM figure (s) and table (s) reflecting the new location (s). Responst: All required milk samples were available during this reporting period. l l l l l l l e.1 l 8792R I l
- APPDiDIX F INiD USE CENSUS Requir.cment : A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a location (s) whica yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in i Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report. Ecsponses No locations were identified by the 1990 land use census that would yield at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to Technical Specification 4.8.G.I. I I I I i 1 . I I F-1 8792R l
APPUiDIX G PROCESS CONTROL PROGRAM ~ Requirement: Technical Specification 6.12.A.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) .i was made. Respnnse: There was no licensee initiated change (s) to the Process Control Program during this reporting period. I I I I I I I I I I G-1 8792R
W APPENDIX 11 0FF-SITE DOSE CALCU1ATION MANUAL ~ Requitetoent: Technical Specification 6.13.A.1 requires that licensee initiated changes to tt Off-Site Dose Calculation Manual (ODCM) I be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made eifective. Response: There were no licensee-initiated changes to the off-alte Dose Calculation Manual during this reporting period. I I l l l 1 i l l l 11 - 1 8792R I
l APPENDIX I l I RADI0 ACTIVE LIQUID, GASEOUS, AND $0 LIP WASIL 4., nM4ENT SYSTEMS i Reguirement: Technical Specification 6.14.A requires that licensee initiated rnajor changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual 4 Radioactive Ef fluent Release Report for the period in which the evsluation was reviewed by the Plant 'peration Review Cennittee. Restsnart There vere no licensee initiateu major changes to the i radioactive waste systems (liquid, gasetu., sad solid) during f this reporting period. I .I I I i
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m APPENDIX J ON-SITE DISPOSAL LF SEPTIC WASTE I Rc_quirmment: Off-Site Dose Calculational Manual Appendix B requires that the dose impact <'ue to on-site disposal of septic waste during the reporting year and from previous years be reported to the i Commission in the Semiannual Radioactive Effluent Report filed I after January 1, if disposals occur during the reporting year. F1822nic: There were two on-site disposals of ceptic waste during the reporting year. The total volume of septage spresd was approximately 19,000 gallons, with all detected radioactivity contained in the solid fraction. The average solids content of the waste was 12.7 wt. %. The total. activity spread during 1990 I on the 1.9 acres (southern) on-site disposal plot was: RuC1).de Activity (Ci} Mn-54 3.21E-7 Co-60 1.12E-5 3 l Zn-65 7.73E-7 Cs-137 1.04E-6 Ce-141 2.28E-7 The projected hypothetical dose from on-site disposals of septic I waste is 1.24E-02 mrem / year. This dose was calculgted according to the model and the assumptions of Off-Site Dose Calculational Manual, Appenaix B. I I J-1 8792R
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