ML20101M341

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Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters,1991,Including Annual Radiological Impact on Man for 1991
ML20101M341
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 12/31/1991
From: Tremblay L
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-92-75, NUDOCS 9207080183
Download: ML20101M341 (44)
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Text

.

g ' VERMONT YANKEE iNUCLEAR POWER CORPORATION

) Ferry Road, Brattleboro, VT 05301-7002 7 ,

(V ENGINEERING OFFICE Seu MAtN $ TTEET BOL Tort M A Ot 740

<sa num June 30,1992 BVY 92 - 75 United States Nuclear Regulatory Commission A*ITN: Document Control Desk Washington, DC 20555

References:

a. License No. DPR-28 (Docket No. 50-271)
b. _ letter, VYNPC to USNRC, BVY 92-25, dated February 28,1992

Subject:

Supplemental Effluent and Waste Disposal Semiannual Report Br Third and Founh

- Quaners,1991 Including Annual Radiological Impact on Man for 1991 for Vermont Yankee Nuclear Power Station.

Dear Sir:

By Reference (b), Vermont Yankee submitted the Effluent and Waste Dis msal Semiannual Report for the Third and Fourth Quarters,1991. At that time, Vermont Yan cee committed to submit the annual dose summary to man for 1991 in a supplemental report pursuant to Technical Specification 6.7.C.1.b. Accordingly, enclosed please find one copy of the subject report.

_ The enclosed supplemental wport contains the 1991 radiological impact on man information,  ;

as well as all of the effluent and r aste disposal totals for the third and fourth quarters of 1991 as previously submitted in Reference (b); therefore, the enclosed supplemental report may be fully substituted for the report submittd by Reference (b).

We trust that the enclosed information is satisfactory; however, should you have any questions, please contact this office.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION NNWC .

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Leonard A. Tremblay, Jr.

Senior Licensing Engineer

' cc: USNRC Region 1 Administrator USNRC Resident Inspector- VYNPS USNRC Project Manager - VYNPS

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I I SUPPLEMENTAL EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, FOR THIRD AND FOURTH QUARTERS, 1991 INCLUDING ANNUAL RADIOLOGILAL IMPACT ON MAN FOR 1991 I

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l Vermont Yankee Nuclear Power Station 8792R I

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ER141A In the Vermont Yankee Effluent and Waste Disposal Semiannual Report covering the third and fourth quarters of 1991 the following corrections should be made:

I. None.

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IABLE_0E_f0NIENIS

- 11 '

Eage ERRATA........................................................... 11

1.0 INTRODUCTION

..................................................... 1 2.0 METEOROLOGICAL DATA.............................................. 2 3.0 DOSE ASSESSMENT.......................................... ....... 3 g

5 3.1 Doses From Liquid Effluents................................ 3 ,

3.2 Doses From Noble Gases..................................... 3 3.3 Doses from Iodine-131, Iodine-133. Tritium and

'I Radionucliden in Particulate Form With Half-Lives Greater Than 8 Days................................................ 3 3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation.................................................. 5 3.5 Doses From On-Site Disposal of Septic Waste................ 7 REFEBENCES....................................................... 8 TABLES........................................................... 9 APPENDIX A - SUPPLEMENTAL INFORMATION.......... ....................... A-1 AP P ENDIX B - LI QU I D HO LDUP TANKS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1 APPENDIX C - RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION........................................... C-1 APPENDIX D - RADI0 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION........................................... D-1 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. . . . . . . . . . . . . E-1 AP P ENDIX F - LAND U S E C EN S US . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F-1 APPENDIX G - PROCESS CONTROL PR0 GRAM............................... .. G-1 APPENDIX H - 0FF-SITE DOSE CALCULATION MANUAL.......................... H-1 APPENDIX I - RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TR EAIM ENT S YS TEM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I-1

-=l APPENDIX J - ON-SITE DISPOSAL OF SEPTIC WASTE.......................... J-1

-111-8792R

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LI!iT OF TABLES Numher Iille hge 1A Gaseous Effluents - Summation Of All Releases 9 1B Gaseous Effluents - Elevated Releases 10 10 Gaseous Effluents - Ground 1,evel Releases 11 1D Gaseous Effluents - Nonroutine Releases 12 2A Liquid Effluents - Summation Of All Releases 13 2B Liquid-Effluents - Nonroutine Releases 14 3 Solid Waste and Irradiated Fuel Shipments 15 I 4 Maximum Otf-Site Doses and Do , Cnmmitments to Mc bers of the Public 16-17 SA to $11 Annual Summary of Upper Level Joint Frequency Distribution 18-25 I

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VERMONT YANKEE NUCLEAR POWER STATION SEMIANNUAL EFFLUENT RELEASE REPORT JULY - DECEMBER 1991

1.0 INTRODUCTION

_l W- 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 for both liquids and gases. Table 4 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 1991, including direct rose from fixed station sources. Tables SA through 5H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the li-month period, January to December 1991. Radioactive effluents reported in the Semiannual Effluent Report covering the first six I months of the year were used to determine the resulting doses for the first half of 1991.

I 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 I 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 I- actual m asured meteorological data recorded during the reporting period.

As required by Technical Specificatica 6.7.C.1.b. thic 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, a:.3, as a result, no dose assessments are required.

Assessment of radiation doses (including direct radiation) to the likely most exposed real member (s) of the public for the calendar year for the purposes of demonstrating conformance with 40CFR190, " Environmental Radiation Protection Standards for Nuclear Power Operations," are also required to be 8792R

included in this report if the con .tions indicated in Technical Specification _3.8.M.1, " Total Doss," 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 ciring the year, no additional radiation dose assessments are required.

All calculated dose estimates for this reporting period are wel? below the dose criteria o' 10 CFR Part 50, Appendix 1.

Appendices B through 11 indicate the status of reportable items per the requirements of Technical Specifications 6.7.C.1 and 6.14.A.

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2.0 METEOR 0LOGICALDATA I 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 derieed for all receptor points from the site meteorological record for eact. quarter using a rtraight-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 mocel as described in " Meteorology and Atomic Energy - 1968" (Reference 2) was used to generate deposition factors, assuming a constant deposicion velocity of 0.01 m/sec for all stack (elevated) releases. Turbine hall roof vents are considered as ground level release points with relative deposition rates determine: from Regulatory Guide 1.111 Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.

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g-3.0 DQSE ASSESS!92(T I 3.1 Doseslto2_LiquidJffluents There were no routine or accidental off-site liquid releases from Vermont Yankee during 1991. As a result, no receiving water exposure pathways

-I :ould contribute to any whole body or organ doses to individuals in unrestricted areas.

I 3.2 Doses From Noble Cages I Technical Specif3 cation 3.8.F.1 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, I Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification 3.8.F.1 assures that the releases of radioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."

Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, and nearest resident in each of the I sixteen principle compass directions, as well as the point of highest off-site ground level air concentration of radioactive materials, .ad for each of the milk animal locations located within five miles of the plant.

3.3 Doses From Iodine-13L. Tritium andladionuclides in Particulatelo.mlillt llalf-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 rad;onuclides in I

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_4-8792R

particulate form with half-lives greater than 8 days (hereafter called iodines and particulates) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix 1 (7.5 mrem per quarter, and 15 mrem per year). By implementing the requirements of 10 CFR Part 50, Appendix I, Technical Specification . ..G.1 assures that the releases of iodines and particulates in gaseous effluents I will be kept "as low as is reasonably achievable."

l Exposure pathways that could exist as a result of the release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surf ace, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary anm 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 I Annual 1.and Use Census as required by Technical Specification 3.9.D.1.

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 erfluents and included the assumption that the inhalation, vegetable garden, I and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor.

It is assumed that milk and meat animals are f ree 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 cf the iodine deposited from gaseous effluent is in elemental form (1 2) and is available for uptake (see p. 26, Reference 3).

I During the-first and fourth quarters, the milk animals are assumed to receive only stored feed.

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The resultant organ doses were c'etermined af ter adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bone, liver, kidney, thyroid, lung and skin for adults, teenagers, children and infants. The maximum estimated quarterly and annual organ doses to any age group due to iodines and particulates at any of

_g the off-site receptor locations are reported in Table 4. These estimated 5 organ doses are well below the 10 CFR Part 50, Appendix I dose criteria of Technical Specification 3.8.G.I. l I 3.4 Whole-Body Do s e a_in.Jnresiti c t e d_Ar e as_froct]ite c1.ladi a tion I 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)

I see any significant direct radiation.

High Pressure Ionization Chamber (HPIC) measurements have been made in the plaat 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 I 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.

I The other sources of dose, including direct radiation and skyshine, to I the site boundary are from low level radioactive waste 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.

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The estimated direct radiation dose f rom all major sources con.bined 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.

3.5 Dates From On-Site Disp.osal_ol Seplit., Waste I

Off-Site Dose Calculational Manual, Appendix B, roquires that all applications of septage within the approved designated disposal areas be limited to ensure the dose to a maximally-exposed individual be maintained at I less, than 1 mrem / year to the whole body and any organ, and the dose to the inadvertent intruder 'e maintained at less than 5 mrem / year. The projected i dose from on-site disposals of septic waste is given in Appendix J.

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s. .w a a - > - , s - - - s. ,a--. ..,.- . - . _ -. ,.n - _,,

- REFERENCES

, 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. Nucleac Regulatory Commission. Office l of Standards Development, March 1976.

2. Meteorology and Atomic Energy, 1968, Section 5-3.2.2, " Cloud Depletion",

pg. 204. U. S. Atomic Energy Commission, July 1968.

3. 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 1", U. S. Nuclear Regulatory Commission.

Office of Standards Development, Revision 1, October 1977.

I

!l 4. W. M. Lowder, P. D. Raft, and G. dePlanque Burke, " Determination of N-16 l 5 Gamma Radiation Fields at BWR Nuclear Power Stations", !!ealth and Saf ety Laboratory, Energy Research and Development Administration, Report No.

305, May 1976.

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IARLE la Vermont _ Yankee Ef fluent andjiante Dispo.saLSrmiannuaLRepori i I Ihird and_.fo.urth_Quarlers4._1191 Gaseous __ Effluents - Sumatlon_oLAlLRelcates Unit Quarter Quarter Est. Total 3 4 Erro L%

A. Fission and Activation Gases

1. Total release Ci 2.76E+02 1 1HEt03 LQQE+02 I 2. Average _telease rate for period
3. Percent cL.I.c c h . S pe c . limit (1) uCilsee 3 11E3D1 1.14_EiOO 1.48E+02_

4.fdEtDQ_

B. Iodines

1. T91al_ lodine-131 Ci__ l 53E:02 t .3 .09E._Q2 25,0PEtD1___

I 2. Averagg_rglease_rg1_e__fpr_pgriod

3. Percent of Tech. Spec. limit (2) uCi/1gc 1.95E-03 1, DIET 01 3.R3E-03_

92 40E+00 C. Particulates

1. Particulates with T-1/2 > 8 days C1 3J 2E-03 1.09E-02 ;LQDE+01 I 2. Average release ra u for period
3. P ArcenI_.nLle_ch,_SptL11mi_t 4,_.GInsa_ alpha _radinaclivity uCi/sec Ci 4.31E-04 (3.)

1.14E-06 1.37E-03 (3) 3.74E-Q6._

I D. Tritium I 1. Total release

2. Average release rata for period
3. Percent of Tc.ch,_Epec. limit Ci uCi/see 1,34E+01 2.34E+00 (3) 1.laE+01 1.46E10D (3)

__;L.QDE QL_

I (1) Technical Specification 3.b.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 form.

(3) Per Technical Specification 3.8.G.1, dese contribution from Tritium and i

particulates are included with I-131 above in Part B.

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IABLE_LB Y.enannt_lankee EEluent and Waale_ Disposal.lemiannual_Repstt Ihird and Fourth Ouartir L 1211 Gaseous _E dlMents - Elc.Yatedl Rlease (1)

Con (innaug_ngde Batsh_fiode I Nuclides_ Released Enit._ Quarter 3

Quarter 4

Quarter 3

Quarter 4

1. Fission Caggs I_ Krypton-85 Ci ND ND Krypl.Qn.E5m Ci 1,HQEtQO 4. 99EtQ_Q _

Krypton-87 _ _Ci I hrvp_t.on-38 Xenon-133 Ci C1 8.93E+0Q_

5. 9.QEiQ0 1.59E+00 2.94E+Q1 LE1E Q1 4.Q4E+00

___ Xenon-135 Ci &,29EtqQ 2 dlEt0L I _.__.2enon-135;n

___ Xenon-138 ci Ci 4A2E101___L10EiD 2 2 031 Q2__ 7. 8 7Et0L I Unidentified Total _LQI_P.eIlod Ci fi__,11hE 02 1.04E 03 2.a_.ladine s

... Iodine-131 C1 1.53E-02 2.14E-02

__._ lodine-133 _Ci SJ2E-Q2 9.Q2E-Q2 _

Indine-135 Ci 9.62E-Q2 1.2SE-01 Total for period Ci 1.66E-01 2,AQE-Q1

3. Particulalef _ __

Ci 1.74E-03 I

Strontium-89 ___S.68E-0!3 Stront.ium-90 Ci 5.7bE_Q6 2.82E-05 Cesium-134 Ci ND 4.06E-06 Cesium-137 Ci 1.91E-05 4.23E-05 i

I Barium-EaLthanum-140

__Ce riu:q.1A1_

C1 C1 2,_4 2E--0 3 1 33E-05 J 15E-03 1.9BE-04 (1) There were no batch mode gaseous releases for this reporting period.

ND - Not detected at the plant stack.

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I IABLE_10 EtrmanLYanker j 1

Ef.fluenLansL.Wa tte_ Dispos al_Semiannuallernr1 Ibird an.d Ecurth Quarters _lM1 Gateaus Effluents - Ground l tYfl leleasts(2) l CDn.t inuoua_liode _ Jalch Jode Nurli0ea_ Released Unit Quarter Quarter Quatter Quarter 3 4 3 4

1. Fissien Gases I Krypton-85 hryplon-83m Krypton-87 Ci

_Qi Ci ED 6J 2E-01 3.92E+00 Krvoton-88 Qi 2dQE QD

__Zenon-133 Ci 5 J4 E-01

__ Xenon-l35 C i_. 3dBEt00 _

Xenon-135m Ci ld3Et01 Xenon-138 C1 . lt031t02.

Unidentified Ci Tolal_.for_pgrind Ci _lt331iO2

2. Iodines (

I Iodine-131 Iodine-133 Iodine-135 Ci

_Qi Q.1.

91 10E-03

4. 76E-0_2 6.39E-02 Tolal_for period Ci 1,21E-01
3. Par 11rulates(2)

Strontium-89 11 1.01E-03 .

Strontium--90 C1 1.42E-05 Cesium-134 Ci ND Cesium-137 Ci ND Barium-lan1hanum-140 Ci 2.08E-Q3 I_ Cerium-141 _

Ci 8 92E45

. (1) There were no batch mode gaseous releases for this reparting period.

(2) -Effluent sampling of the turbine roof ventilators as a ground level release point was initiated at the beginning of the fourth quarter 1991.

ND - Not detected at the Turbine Building roof.

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1 IM LE_.lD Vermont._ Yankee Eff.luent and Waste Disposal _ Semiannual _ Report Ih11 Land _EcuttlLQuatters__1911 Dastnus.lffluentri - Nonroutincleleases l

I There were no nonroutine or accidental gaseous releases during the third or fourth l

quarters of 1991. ]

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6 mmm V.erogat Yanke.e E fLluenLansLWasielispor aLSemiannue LRepor3 Third and Fourth Ouar1 HS_ljl91 LLquisLECfinents_ __ Summation..sf All Relenses I

I There were no off-site liquid releases during the third or fourth quarters of 1991.

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IAELL2B VermonWan.kee EiflunL Andlanle_Di spo s aLSemiannuaLAc ro tt Third _and_fnututQuartera_1991 na LiquiLEffluents_- Jonroutineleleases

.. g There were no nonroutine or accidental off-site releases during the third or fourth quarters of 1991.

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ZABLE 3 I Vermont _Xankee Efflutni_andJnteliaposaLSemiannuaLRepori Etird_and_ fourth _ Quarters ._1291 S211_d_ Waste and_ Irradiated _EueLShipmenta A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel):

_Jnil___ 6-Month Est. Total

__feriod Error. %

-, 1. Type of Waste

~

a. Spent resins, filter sludges, evaporator m3 2.90E+01 bottoms. etc. _Ci 1.55E+02 1 7.5E+01 I b. Dry compressible vaste, contaminated eanipment__etc.
c. Irradiated components, control rods, m3 C

m 4.89E+01

_.l.11E R1 8.13E+00

+ 7.5E+01 etc. 01 1,80E+05 1 7.5E+01

2. Estimate of Major Nuclide Composition (By Type of Waste):

I a. Cobalt-60 Zine-65 fgsium-137

% 1 3 E+01 1.70E+01 1,M E+01 Cesium-137 Cealum-134 Jick11-63_

% 4,00E10D__

% 2.40E100

%_LHOE-01 I Iron-55 Iodine-131 Xenon-131m

% 1.1QE101

%__1_,D3Et01

% 8.3QE+00

e. _fobalt-60 IIon.-55 Nicks 1_h3

%_LJ2E S1__

%_buGEt00_

% 4.00E-01 Cesium-134  % 6.70E+00  %

.I Barimq-14_0  % 5.20E+00 Lanthanum-140 % 5.201 00 Nickel-63  % L301t00  %

I b. Iron-55 Cohalt-60 Zine-65

% 5.76E+01

% 1.14EtQ1

% 6J0E+00 Manganese-M % 4.801100  %

3. Solid Waste Disposition:

Number ol_ Shipments Mo.deJLIransporlation Des 11 nation 13 Truck Barnwell , SC 1 Truck Richland ,13 B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information l_' i) Class of solid waste containers shipped: 46 A (unstable), 2A, 4B, SC

2) Types of containers used: 46 Strong-tight Containers, 6 Type A, 5 Type B
3) Solidification agent or absorbent: None

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BMJL4 Yerment_Yanker Ef fluent and Waste Disposal Semiannual Reporj; Third and Fourth Ouarters. 1991 tiaximup* Of f-Site Doses and Dose Cosgitments to Members of the Public Dose (mrem)***

ist 2nd 3rd 4th

-I Source Liquid Effluents (a)

Guarter Quartf:r_

Ouarter Quarter Year **

Airborne Effluents Iodines and Particulates 1.04E-02 4.81E-01 7.95E-01 2.07E-01 1.49E+00 (1) (2) (2) (6)

Noble Gases 7.04E-02 5.74E-02 2.37E-02 2.66E-01 4.18E-01 I

Beta Air (mrad) (3) (4) (4) (7)

Gamma Air 1. 36 E--01 1.34E-01 5.69E-02 2.33E-01 5.56E-01 i (mrad) (5) (5) (5) (5)

Whole Body Dose from 3.96E+00 E64E+00 3.78E+00 4.14E+00 1.55E,01 I-I- Facility Direct Radiation (mrem)**** D I *" Maximum" means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.

I **" Maximum" dose for the year is the sum of the maximirr doses for each quarter.

This results in a conservative yectly dose estimate, but still well within the u

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.

I (1) Child / Thyroid, hv-2900 meters.

(2) Infant / Thyroid, SSE 5100 meters.

(3)- hN-2900 meters.

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. _ . . . .. .- ~. . . = _ ..

I IldLE_4 (Continued) l (4) WNW-2400 meters.

. I' (5) S-400 meters.

.(6) Child / Thyroid, E-500 meters.

(7) E-500 meters.

I (a) There were no' liquid releases during this reporting period.

I I  :

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L-I E 8792R I.

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TABLE S2 VERMONT YANKEE JAN91-DEC91 METEOROLOGICAL DATA JOINT FREOUEkCf OlsTRIBUTION 297.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = 14 WIND DIRECTION FR34 SPEED (MPH) N kWE WE eke E E3E SE SSE S SSW SW VSV W WWW WW kNW VRBL TOTAL I OALM (1)

(2)

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

C-3 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 8.33 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 8.33 (2) .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 I 47 (1)

I2) 8.33

.01 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

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

8.33

.01 1

B-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 3 (1) .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 25.00 .00 25.00 (2) .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .00 .04 t' 18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 3 I .00 25.00 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 25.00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .00 .04 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 2 0  ? j) 00 8.33 .00 16.67 .00 25.00 I (1) .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ~

(2) .00 00 .00 .00 W .00 .00 00 .00 .00 .00 .00 .00 .01 .00 .02 .00 .04 CT 24 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 0 1 (1) .C0 .P .N .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 8.33 .00 8.33 (2) .00 00 .00 .00 .s s .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 ALL SPEEDS 1 0 0 1 0 0 0 0 0 0 0 0 0 1 0 9 0 12 (1) 833 .00 .00 8.'s3 .00 .00 .00 .00 .00 .00 .00 .00 .00 8.33 .00 73.00 .00 100.00 (2) .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .11 .00 .14 I

.01 (1) PERCENT OF ALL 00CD OBSERVATIONS FOR THit PAGE (2)= PERCENT OF ALL 0000 CBSERVATIONS FOR THIS PER100 C= CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH)

I I

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TABLE SB f

VERMONT YAWKEE JAN91-DEC91 METEOROLOGICAL DA1 A J01ET FREQUENCY DISTRIBUTION 297.0 FT WIND CATA STABILITY CLASS B CLASS FREQLENCY (PERCENT) = .70 WIND DIRECTION FRCM SPEED (MPH) N WWE WE EEE E ESE SE $$E S SSW SV WSW W WW kW WWW VRBL TOTAL I CALM (1)

(2) 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00

.00

.00 0 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 C-3 0 1 1 0 0 1 1 0 0 0 0 0 0 0 0 0 0 4 (1) .00 1,69 1.49 .00 .00 1.69 1,69 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6.78 (2) .00 .01 .01 .00 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 47 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 0 4 (1) .00 .00 .00 .00 .00 6.78

-~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 .05

.00

.00 6.78

.05 8 12 2 0 0 0 0 0 2 2 0 0 0 0 1 0 0 18 0 25

I. (1)

(2) 3.39

.02

.00

.00

.00

.00

.00

.00

.00

.00

.00 3.39 3.39

.00 .02 .02

.00

.00

.00

.00

.00

.00

.00 1.69

.00 .01

.00

.00

.00 30.51

.00 .21

.00

.00 42.37

.30 13 18 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 6 0 8 (1) .00 .00 .00 .00 00 .00 .00 1.69 .00 .00 .00 .00 .00 .00 1.69 10.17 .00 13.56 I (2).

19-24 (1)

.00 4-6.78

.00 0

.00

.00

.00 0

.00 0

.00

.00 0

.00

.00 0

.00

.00

.00 0

.01 0

.00

.00 0

.00

.00 0

.00

.00

.00 0

.00 0

.00

.00 0

.00

.00 0

.00

.01 0

.07 to

.00 16.95

.00 0

.00

.10 14

23. 73 (2)- .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .12 .00 .17 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 3 0 4 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.69 .00 5.08 .00 6.78 I (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .04 .00 .05 ALL SPEEDS 6 1 1 0 0 1 3 3 0 0 0 0 1 1 1 41 0 59 (1) 10.17-1.69 1.69 .00 .00 1.69 5.08 5.08 .00 .00 .00 .00 1.69 1.69 1.69 69.49 .00 100.00 (2) .07 .01 .01 .00 .00 .01 .04 .04 .00 .00 .00 .00 .01 .01 .01 .49 .00 .70 (1)= PERCENT OF ALL COCO OSSERVATIONS FCR THIS PAGE (3)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERICO C= CALM (WIND SPEED LESS TRAN OR EQUAL TO .95 MPH)

I 1

I I I

g; I

TABLE SC VERMONT YAEKEE JAN91-DEC91 METEOROLOO! CAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 2.20 WIND DIRECTION FRCH SPEED (MPN) N NNE NE ENE E ESE SE SSE S SSV SV VSV V WW NV NNV VRBL TOTAL I CALM (1)

(2)

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.00

.00 0

.09

.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 I C-3 (1)

(2)

.00

.00 0

.54

.01 1

.00 0

.00 1.08

.02 2

.00

.00 0

.00

.00 0

.54

.01 1

.54

.01 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

2.70

.06 5

47 4 1 1 1 0 1 1 0 1 0 0 0 1 0 3 13 0 27 (1) 2.16 .54 .54 .54 .00 .54 .54 .00 .54 .00 .00 .00 .54 .00 1.62 7.05 .00 14.59 (2) .05 .01 .01 .01 .00 .01 .01 .00 .01 .00 .00 .00 .01 .00 .04 .15 .00 .32 8-12 8 3 0 1 1 5 2 13 6 0 0 1 1 5 20 0 69 (1) 4.32 1.62 .00 .54 .54 2.70 1.00 7.03 3.24 .00 .00 .54 .54 1.62 2.70 10.81 .00 37.30 (2) .10 .04 .00 .01 .01 .06 .02 .15 .07 .00 .00 .01 .01 .04 .0c .24 .00 .82 13-18 7 1 C 0 0 0 0 2 3 0 0 0 1 3 7 28 0 52 I (1) 3.78 .54 .00 .00 .00 .00 .00 1.08 1.62 .00 00 .00 .54 1.62 3.78 15.14 .00 28,11 (2) .08 .01 .00 .00 .00 .00 .00 .02 .64 .00 .00 .00 .01 .04 .08 .._ .00 .62 19-24 2 0 0 0 0 0 0 0 0 1 0 0 1 2 0 21 0 27 (1) .00 .00 .00 .00 .00 .00 .00 .00 .54 .00 .00 .54 1.03 .00 11.35 .00 14.59 I

1.08

.00 .00 .00 .00 .00 .00 .01 .00 .00 .01 .02 .00 .25 .00 .32 7 (2) .02 .00 .00 CT 24 1 0 0 0 0 0 0 0 0 0 0 0 0 1 0 3 0 5 (1) .54 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .54 .00 1.62 .00 2.70 I ALL SPEEDS (2) .01

'22 (1) 11.89 3.24

.00 6

.00 1

.54 2.16

.00 4

.00 1

.00 6

00 4

.54 3.24 2.16 8.65 5.41

.00 16

.00 10

.00

.54 1

.00

.00 0

.00 1

.00 4

.01 9

.54 2.16 4.Bo 8.11 45.95

.00 15

.04 85

.00 0

.00 100.00

.06 185 (2) .26 .07 .01 .05 .01 .07 .05 .19 .12 .01 .00 .01 .05 .11 .18 1.01 .00 2.20 I 1) PERCENT OF ALL 000) OBSERVATIONS FOR THIS PAGE

((2)= PERCENT OF ALL COCO CBSERVATIONS FOR THIS PERIOD C= CALM .95 HFM) (W!kD SPEED LESS THAN OR I

I 1 I

g i

IABLE SD VERMONT YANKEE JAN91-DEC91 METEOROLOGICAL DATA J0!NT FREQUENCY DISTRIBUTION 297.0 ff WIND CATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 47.39 WIND DIRECTION TRCN SPEED (MPH) N NME NE ENE E ESE SE SSE S SSV SV WSW W WWV NV WNW VREL T0 7L CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0J (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C3 50 33 28 19 34 38 59 36 27 12 9 12 12 11 31 44 0 455 I- (1)

(2) 1.25

.59

.83

.39

.70

.33 48

.23

.85

.40

.95 1.48

.45 .70 90

.43

.68

.32

.30

.14

.23

.11

.30

.14

.30 14

.?8

.13

.78 1.10

.37 .52

.00

.00 11.42 5.41 47 101 38 24 27 41 73 145 140 77 31 18 11 22 26 45 170 0 989 I (1)

(2) 8-12 2.54 1.20 132

.95

.45 30

.60

.29 9

.68 1.03 1.83 3.64 3.51 1.93

.32 9

49 20

.87 1.72 1.67 41 79 129 194

.92

.78

.37 37

.45

.21 38

.28

.13 37

.55

.26

.65 1.13 4.27

.31 70 113

.54 2.02 60 193

.00

.00 0

24.82 11.77 1191 I (1)

(2) 13-18 3.31 1.57 169

.75

.36 39

.23

.11 8

.23

.11 2

.50 1.03 1.98 3.24 4.87

.24 5

.49 8

.94 1.53 2.31 5 10 71 93 44 25

.95 45 12

.93 1.76 2.84 1.51 4.84 44 16

.83 1.34 .71 2.30 85 156 108 229

.00

.00 0

29.89 14.17 948 (1) 4.24 .98 .20 .05 .13 .20 .13 .25 1.78 .63 .30 40 2.13 3.92 2.71 5.75 .00 23.80 I (2) 19 24 (1) 2.01 63 1.58 46 2

.05

.10 1

.03

.02 0

.00

.06

.00 0

.10

.00 0

.06

.08 3

.12

.05 2

.84 12

.30

.30 3

.08

.14 0

.00

.19 1.01 1.86 1.23 2.72 0

.00 29 50 46

.73 1.26 1.15 2.28 91

.00 0

.00 11.28 302 7.58 I (2)

GT 24 (1)

.75 21

.53

.02 0

.00

.01 0

.00

.00 0

.00

.00

.00 0

.00

.00 0

. 0 ".

.00 0

.02

.00 0

.14 0

.00

.04 0

.00

.00 0

.00

.00 0

.00

.34

.13 5

.59 12

.30

.55 1.08 16 45

.40 1.13

.00 0

.00 3.59 99 2.48 (2) .25 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .06 .14 .19 .54 .00 1.18 I ALL SPEEDS 536 142 70 57 100 160 291 317 381 108 77 76 223 368 306 772 (1) 13.45 3.56 1.76 1.43 2.51 4.02 7.30 7.96 9.56 2.71 1.93 1.91 5.60 9.24 7.68 19.38 6.38 1.69 .83 .92 0 3984

.00 100.00

.00 47.39 (2) .68 1.19 1.90 3.46 3.77 4.53 1.28 .90 2.65 4.38 3.64 9.18 I 1)= PERCENT OF ALL GOOD CBSERVATIONS FOR 1HIS PAGE

((2)sPERCENT of ALL GOCX) OSSERVATIONS FOR THIS PERICO Ca CALM .95 (JIND MPH) SPEED LESS THAN O E

g LI l'

I

. l 1

l TA8tE SE VERMONT YAAKEE JAh91 0EC91 METEOROLOGICAL DATA J0thi FREQUENCY 0181RIBU110N l

297.0 ff WIND DATA STABILITY CLASS E CLA$s FREQUENCY (PERCENf) e 33.21 WIND 0!RECil0N FROM

$ PEED (MPH) N kWE WE EWE E ESE SE $$E S $$W SW VSW V WNV NV kKf VRBL TOTAL CALM 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .04 .00 .00 .00 .00 .00 .00 .00 .04 .00 .07 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 .0C .02 I C3 (1)

(2) 87 1.03 52

.62 50

.59 43

.51 54

.64 69

.82 74 3.12 1.86 1,79 1.54 1.93 2.47 2.65 9.58

.88 44

.52 22

.79

.26 15

.54

.18 6

.21

.07 9

.32 11 16

.57

.19 18

.21 34

.64 1.22 2.53 40 72

.66 0

.00

.00 665 23.82 7.91 47 180 19 8 15 19 40 140 143 70 24 16 19 19 21 51 243 0 1027 (1) 6.45 .68 .29 .54 .68 1.43 5.01 5.12 2.51 .86 .57 .68 .68 .75 1.83 8.70 .00 36.78 (2) 2.14 .23 .10 .18 .23 48 1.67 1.70 .83 .29 .19 .23 .23 .25 .61 2.89 .00 12.22 8 12 70 6. 2 1 1 8 36 98 88 36 15 M 40 54 45 209 J 725 (1) 2.51 .21 .07 .04 .04 .29 1.29 3.51 3.15 1.29 .54 .57 1.43 1.93 1.61 7.49 .00 25.97 (2) .83 .07 .02 .01 .01 ,10 43 1.17 1.05 .43 .18 .19 .48 .64 .54 2.49 .00 8.62 13 18 31 1 0 1 0 0 3 25 37 18 3 4 28 30 23 111 0 324 I (1)

(2) 19 24 1.11

.37 5

.04

.0i 0

.00

.00 0

.04

.01 0

.00

.00 0

.00

.00 0

.11

.04 1

90 1.33

.30 1

44 8

.64

.21 1

.11

.04 0

.14 1.00 1.40

.05 2

.33 2

46 6

.82 3.98

.27 1.32 5 13

.00

.00 0

11.60 3.85 44 (1) .00 .00 .00 .00 .29 .04 .00 .07 .07 .18 .47 .00 I

.18 .00 .04 .04 .21 1.58 (2) .06 .00 .00 00 .00 .00 .01 .01 .10 .01 .00 02 .02 .07 .06 .15 .00 .52 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 3 0 5 (1) .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .04 .11 .00 .18 (2) .00 .00 .00 .00 .L0 .00 .00 .00 .00 .00 .00 00 .00 .01 .01 .04 .00 .06 ALL SPEEDS 3 73 78 60 60 .e. 117 254 312 225 94 40 50 105 139 159 652 0 2792 (1) 13.36 2.79 2.15 2.15 2.63 4.19 9.10 11.17 8.06 3.37 1.43 1.79 3.76 4.98 5.69 23.35 .00 100.00 (2) 4.44 .93 '1 .71 .88 1.39 3.02 3.71 2.68 1.12 48 .59 1.25 1.65 1.89 7.76 .00 33.21 I (1) PERCENT OF ALL C000 OBStavAt!0NS FOR THIS FACE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERs00 Ca CALM ,llND $ PEED LESS THAN OR EQUAL 70 .95 MPH)

, I E

I' TABLE 5F VERMONT f AkKEE JAN91 DEC91 METEOROLOGICAL DATA J0!bt FREQUENCY Ol81RIBuil0N 297.0 FT WIND DATA STABIL11T CLASS F CLASS FREQUEhCT (FERCEht) . 14.04 WIND DIRECil0N FA0H SFEE0(MPH) N NNE NE EFE E ESE SE $$E & SSW SW WSW W WW WW kWW VRBL TOTAL CALM 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 .08 .00 .00 .00 .08 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 C3 42 42 E3 25 38 36 47 37 27 19 10 8 12 14 22 37 0 441 (1) 3.56 3.56 2.12 2.12 3.22 3.05 3.98 3.14 2.29 1.61 .85 .68 1.02 1.19 1.86 3.14 .00 37.37 i (2) .50 .50 .30 .30 .45 .43 .56 .44 .32 .23 .12 .10 14 .17 .26 .44 .00 5.25 )

j 47 54 11 5 4 12 40 101 94 39 16 11 9 13 14 29 84 0 536 (1) 4.58 .93 42 .34 1.02 3.39 8.56 7.97 3.31 1.36 .93 .76 1.10 1.19 2.46 7.12 .00 45.42 !

(2) .64 .13 .06 .05 .14 48 1.20 1.12 46 .19 .13 .11 .15 .17 .34 1.00 .00 6.38 6 12 11 0 0 0 1 14 30 23 5 8 3 9 17 14 44 0 180 I

1 (1) .93 .08 .00 .00 .00 .08 1. i9 2.54 1.95 .42 .65 .25 .76 1.44 1.19 3.73 .00 15.25 (2) .13 01 .00 .00 .00 .01 17 .36 .27 .06 .10 .C4 .11 .20 .17 .52 .00 2.14 13 18 1 0 0 0 0 0 0 0 4 1 1 0 2 3 3 6 0 21 (1) .08 .00 00 .00 .00 .00 .00 .00 .34 .08 .08 .00 .17 .25 .25 .51 .00 1.78

.00 .00 .00 .00 .00 .00 .05 .00 .02 .04 .07 .00 l (2) .01 .00 .01 .01 .04 .25 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 .08 .00 .00 .00 .08 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 )

GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 108 54 30 29 50 77 162 161 93 41 30 20 36 50 68 171 0 1180 (1) 9.15 4.58 2.54 2.46 4.24 6.53 13.73 13.64 7.88 3.47 2.54 1.69 3.05 4.24 5.76 14.49 .00 100.00 (2) 1.28 .64 .36 .34 .59 .92 1.93 1.92 1.11 49 .36 .24 .43 .59 .81 2.03 .00 14.04 (1)sPERCENT OF ALL C000 OBSERVATIONS FOR THIS PACE (3)sPERCENT OF ALL GOOD OSSERVATIONS FOR THIS PERIOD Cs CALM (WIND SPEED LESS tdAN OR EQUAL 10 .95 MPH) l i

l l

l L

l

!I I

TABLE 5G YEs.MONT TANKEE JAN91.,EC91 METEOROLCGICAL DATA JOINT FEZ 3UENCY DISTRIBUTION 297.0 FT WIND DATA $1A81L11Y CLASS 0 CLASS fRIOUENCY (PERCENT) a 2.31 WIND DIRECIl0N IRCM SPEED (MPM) W NNE NE ENE E ESE SE SSJ S SSW SV WSW W kW NW kNW VRBL 101AL CALM 0 0 0 0 0 0 0 (i 0 0 0 0 0 0 0 0 0 C (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I C3 (1)

(2) 4 3 2,06 1.55 1.03 2.0G

.05 .04 .02 2

.03 4 1

.52 1.55

.01 .04 3

.01 1

.10 8

.06 5

.10 8

.52 4.12 2.58 4.12 2.06 2.58 1.03 1.55

.05 4

.06 5

.02 2

.04 3

.00 0

00

.52

.01 1

.00

.00 0 54 27.84

.64 47 5 2 1 1 1 5 11 16 8 6 6 3 7 10 5 4 0 91 (1) 2.58 1.03 .52 .52 .52 2.58 5.67 8.25 4.12 3.09 3.09 1.55 3.61 5.15 2.58 2.06 .00 46.91 (2) .06 .02 .01 .01 .01 .06 .13 .19 .10 .07 .07 .04 .08 .12 .06 .05 .00 1.08 B 12 4, 0 0 0 0 0 2 12 2 4 1 4 2 6 0 5 0 42 I (1)

(2) 2.06

.05

.00

.00

.00

.00 0

.00

.00 0

.00

.00 0

.00 1.03 6.19 1.03 2.06

.00 0

02 0

1 a.

0

.02 0

.05

.';2

.01 0

2.06 1.03 3,09

.05 0

.02 0

.07 1

.00 2.58

.00 2

.06 2

.00

.00 0

21.65

.50 6

13 18 0 0 1

.52 1.03 1.03 3.09 I (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .52 .00 .00 .00 .00 (2) .00 .00 .00 00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 .02 .02 .00 .07 19 24 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 (1) .00 00 .00 00 .00 .00 .00 .00 52 .00 .00 .00 .00 .00 .00 .00 .00 .52 -

(2) .00 .00 .00 00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00

.00 .00 .00 .00 .00 I (2) .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 13 5 3 5 2 8 14 36 16 19 11 12 11 20 7 12 0 194 (1) 6.70 2.58 1.55 2.58 1.03 4.12 7.22 18.56 8.25 9.79 5.67 6.19 5.67 10.31 3.61 6.19 .00 100.00 (2) .15 .06 .04 06 .02 10 .17 43 .19 .2.3 .13 .14 .13 .24 .08 .14 .00 2.31 (1)sPERCENT OF ALL 00CD OBSERVATIONS FOR THIS PACE (2) PERCENT OF ALL GOCD OBSERVATIONS FOR THit PERICD Cs CALM (WIND SPEED LESS ThAN OR EQUAL To .95 MPH)

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TABLE 53 VER OWT YAkKEE JAW 91 DEC91 ME1EOROLOGICAL DATA J0thi FREQUEW;Y DISTRIBuil0N 297.0 FT WIND DAT A 51ABILiff CLASS ALL CLASS FRioVEWCY (PERT [N1) = 100.00 WIND DIR[tfl0N FROM SPEED (MPM) W kNE h! [NE E ESE $[ SSE $ SSW SW WSW W WWW WW Nww vtBL TOTAL CALM 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 1 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .01 .00 .01 . 0') .04 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .01 .00 .01 .00 .04 I C-3 (1)

(2) 183 132 106 2.18 1.57 1.26 1.12 1.51 1.75 2.18 1.5'J 2.18 1.57 1.26 1.12 1.51 1.75 2.18 1.50 94 127 147 183 126 81

.96

.96

.64

.64 54

.34

.34 29 34

.40 40 42

.? D

.50 46 87 154

.55 '. 03 1.83

.55 1.03 1.83

.00

.00 0 if25 19.33 19.33 I 4r (i)

(2) 345 4.10 4.10 71

.84

.64 39 46 46

.57

.57 48 73 159 398 393 1 95

.87 1.89 4. 7.1 4.68 2.32

.87 1.89 4.73 4.68 2.02

.92

.92 77

.61

.61 51 42

.50

.50

.74 62

.74 71 133 518

.84 1.58 6.16

.84 1.58 6.16

.00

.00 0 2675 31.82 31.82 6 17 227 40 11 11 22 55 135 284 313 82 62 61 123 193 124 492 0 2235 (1) 2.70 48 .13 .13 .26 .65 1.61 3.38 3.72 .98 .74 73 1.46 2.30 1,48 5.85 .00 26.59 (2) 2.70 48 .13 .13 .26 .65 1.61 3.33 3.72 98 .74 .73 1.46 2.30 1.48 5.85 .00 26.59 13 18 208 41 8 3 5 3 8 38 115 45 16 20 116 202 144 385 0 1362 I 19 24 (1)

(2) 2.47 2.47 74

.49

.49 2

.10

.10 1

404

.04 0

.06

.06 0

.10

.10 0

10

.10 4

.45 1.37 45 1.37 3 21

.54

.54 5

.19

.19 0

.24 1.38 2.40 1.71 4.58

.24 1.38 2.40 1.71 4.58 2 32 60 51 137

.00

.00 0

16.20 16.20 392 (1) .M .02 .01 .00 .00 .00 .05 .04 .25 .06 .00 .02 .38 .71 .61 1,63 .00 4.66 (2) .88 .02 .01 .00 .00 .00 .05 .04 .25 .06 .00 .02 .38 .71 .61 1.63 .00 4.66 GT 24 22 0 0 0 0 0 0 0 0 0 0 0 5 15 17 55 0 114 (1) .26 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .06 .18 .20 .65 .00 1.36 I (2) .26 .00 .00 .Du ALL SPEEDS 1059 286 165 156 227 369 728 845 725 263 158 159 380 588 556 1742

.00 (1) 12.60 3.40 1.96 1.86 2.70 4.39 8.66 10.05 8.62 3.13 1.88 1.89 4.52 7.00 A.61 20.72

.00 .00 .00 .00 .00 .00 .00 .06 .18 .20 .65 .00 0

.00 100.00 1.36 8406 i

(2) 12.60 3.40 1.96 1.85 2.70 4.39 8.66 10.05 8.62 3.13 1.88 1.89 4.52 7.00 6.61 20.72 .00 100.00 (1) PERCELT OF ALL :;000 OBSERVAfl0NS FOR THIS PAGE (2)=PERCEhi 0F ALL C0CD OBSERVATIONS FOR THis PERICD Ca CALM (VlWD SPEED LESS THAN OR EQUAL 10 .95 MPH)

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APPENDIX A y I EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT

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f I Supplemental Information $

Third and Fourth Quarters, 1991 Facility: Vermont Yankne_ Nuclear _forer_Etation I Licensee: Vermont Janker.Euclear_ foyer _ Corporation  !

I 1A. Technical Specification Limits - Dose and Dose Rate Ic chnic aLSpe c ific a tion _and_Ca tegory Limit

a. Noble _ Gases 3.8.E.1 I 3.8.E.1 Total body dose rate Skin dose rate 500 mrem /yr 3000 mrem /yr
3. 8. F.1 Gamma air dose 5 mrad in a quarter I 3.8.F.1 Canana 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. lo din e-1314_lo dine-133.._Irit iunt an dla d i on u c li d e s in_fAr_titula Le_Eorm_Ri.th_llalf -LiYan GrenLer_Ihan_B_DayE 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 I c. Liguida I 3.8.B.1 Total body dose 1.5 mrem in a quarter I

3.8 3.1 Total body dose 3 mrem in a year 3.8.B.1 Organ dose 5 mree in a quarter 3.8.B.1 Organ dose 10 mrem in a year A-1 8792R I

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W 2A. Technical Specification Limits - Concentration

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a. Noble _ Gases No MPC limits
b. Indine:13 L_1cdine-t31_lritinntand Radionucl id e s _in _1'ar ti cula t e_fo rnt Wit h lla1L-Liv e s_Ste at e r_Ihan_8_ Days : No MFC limits
c. Liquids 3.8.A.1 Total fraction of MPC I excluding noble gases (10CTR20 Appendix B.

Table II, Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 uC1/cc

3. Average Energy Provided below are the average energy (E) of the radionuclide mixture in i releases of fission and activation gases, if applicable,
a. Average gamma energy: 3rd Quarter 1.11E+00 McV/ dis 4th Quarter 1.12E+00 MeV/ dis (
b. Average beta energy: Not Applicable
4. Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or approximate the total I radioactivity in effluents and the methods used to determine radionuclide composition.

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a. Fission and Activation Gases I Continuous stack monitors monitor gross Noble Gas radic, activity released from the plant stack. Total Noble Gas release rates are calculated using this monitc,r. On days the monitor shows less than detectable release of fission gases, a zero releane is considered.

I To determine the isotopic breakdown of the release, sampics are taken of the Steam Jet Air Ejector, which is the source gas for the releases. These samples are analyzed by gamma spectroscopy to determine the isotopic composition. The isotopic composition is then proportioned to the gross releases determined from the stack These are

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monitor to quantify the individual 1setopic releases.

I indicated in Table 1B and the totals of Table 1A. O Beginning in the fourth quarter of 1991, grab samples were obtained I from the Turbine Building roof vents. Only Xe-135 was detected in these samples. The remainder of the gases indicater were calculated by ratioing the indicated Xe-135 to the other gases using the Steam Jet Air Ejector camples as mentioned above. These results are indicated in Table 1C and the totals of Table 1A.

I The error involved in these steps may be approximately 1100 percent.

b. Iodines ,

Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. Beginning in the fourth quarter of 1991, continuous particulate and charcoal samples were also taken at the Turbine Building roof vents. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135.

I The error involved in these steps may be approximately 150 percent.

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I c. Particulates I The particulate filters described in b. abovc etc also counted for particulate radioactivity. The error involved in this sample is g

5 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 liquid ef f luents released. For each batch, station records are retained of the -

total activity (mC1) released, concentration (uCi/ml) of gross I radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.

Each batch of radioactive liquid effluent released is analyzed for gross gamma and gamma isotopic radioactivity. A montitly prepartional composite sample, comprising an aliquot of each batch released during a month, is also enalyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition to I gamma spectroscopy.

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There were no liquid releases during the reporting period.

5. Batch Releases
a. Liquid There were no routine liquid batch releases during the reporting I period.

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b. Gaseous s,-

I There were no routine gaseous Satch releases during the reporting Yb c

period.

6. Abnormal Releases
a. Liquid I There were no nonroutine liquid releases during the reporting b ng period.
b. Gaseous There were no nonroutine gaseous releases during the reporting I period.

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I APPENDIX B I LIQUID HOLDUP TANKS Requiremeni: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive mater 2a1 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.

hespont.e:

I The limits of Technical Specification 3.8.').1 werc not exceeded during this reporting period.

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APFDiDIX C I RADI0 ACTIVE LIQUID EFFLUD4T MONITORING INSTRUMuiTATION 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 Semiannual Effluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7,C.1. -

I Response: Since the requirements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid ef fluent monitoring instrumentation were met for this reporting period, no response is required.

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I' APPENDIX D I RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION I Requirsment: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical I Specification Table 3.9.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Seminnnual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per

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Technical Specification 6.7.C.1.

I Resppase: 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.

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g.. APPENDIX E I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement: The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.9.C. With milk samples no longer available from one or more of the sampic lo;ations required by Technical Specification Tabic 3.9.3, Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Report:

(1) identify the cause(s) of the sample (s) no longer being available, (2) identify the new location (s) for obtaining -

available replacement samples and (3) include revised ODCM figure (s) and table (s) reficcting the new location (s).

Etapange: The dairy farm at Station m-16/TC-16 went out of business and was sold at auction in July of 1991. A substitute location was chosen to replace it, and the first samples were collected there in July of 1991. The new milk and cattle feed sampling location is designated 2 -15 and TC-15 (for milk and cattle feed, respectively). These changes were rnade to the ODCM as Revision 11.

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APPENDIX F 1R4D USE CENSUS I Resultemeltt : A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a I location (s) which yields at least a 20 percent greater dose or dose commitment than the velues currently being calculated ir.

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.

Resp.cnic: No locations were identified by the 1991 land use census that would yield at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant I to Technical Specification 4.8.G.I.

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APPENDIX G I PROCESS CONTROL PROGGet Requirement: Technical Specification 6.12.A.1 rejuires that licensee initiated chc.nges to the Process Control Program (PCP) be I. submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was :nade.

flegypan.c : The Process Control Program was revised to include the following paragraph at the end of Section 3.0 during this reporting period:

I " Vendor supplied or temporary methods of processing resins may be used in lieu of the above process provided that the vendor or I 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 Supervisor prior to implementation."

I This change did not reduce the overall conformance of the dewatered spent resins / filter media waste product to existing criteria for solid waste shipments and dispocal. It allows the I use of qualified vendor supplied or temporary methods of processing resins.

The rerised PCP was included with the Semiannual Radiological Effluent and Waste Disposal Report filed with the NRC on February 28, 1992 for the report period covering the third and fourth quarters of 1991.

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ApfENDIX H OFF-SITE DOSE CALCULATION MANUAL l i

Reguirement: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dosc Calculation Manual (ODCM) be submitted to the Connission in the Semiannual Radioactive l Effluent Release Report for the period in which the change (a) was made effective.

1 Response: There were two revisions to the Off-Site Dose Calculation Manual during this reporting period:

I 1. The dairy farm et Station 1N-16/TC-16 went out of busineos and was sold at auction in July of 1991. A substitute location was chosen tu replace it, and the first samples were collected there in July of 1991. The new milk and cattle feed sampling location is designated 1M-15 and TC-15 (for milk and cattle feed, respectively). These changes were made to the ODCM as Revision 11. They will not reduce the accuracy or reliability of dose calculations or setpoint de te mina tions . Change pages to the ODCM (Revisions 11 and I 12) were submitted with the Semiannual Radiological Ef fluent and Waste Disposal Report which was filed with the NRC on February 28, 1992 for the reporting period covering the third and fourth quarters of 1991.

I 2. The Off-Site Dose Calculation Manual was emended ta include Method 1 off-site dose calculati ns for a ground level release f rom the Turbine Building roof vents. Method I dose model assumptions are conservative. They assume a ground level release receptor point at the site boundary with the maximum atmospheric dispersion factors. At this location all pessible pathways are assumed to exist (e . g. , g round 1

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APPDiDIX 11 (Continued) 0FF-SITE DOSE CALCUIATION MANUAL plane, inhalation, garden, milk, and meat). These changes I were made to the ODCM as Revision 12. This revision provides a method for integrating the measured releases from the Turbine Building through the roof vents into the total release calculation for the plant. It will not reduce the accuracy or reliability of dose calculations or setpoint determinations. Change pages to the ODCM (Revisions 11 and

12) were submitted with the Semiannual Radiological Effluent and Waste Disposal Report which was filed with the NRC on February 28, 1992 for the reporting period covering the I third and fourth quarters of 1991.

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APP 2JiDIX 1 RAD *0 ACTIVE LIQUID GASEOUS, AND SOLID k'AETE TRFlsINENT SYSTD1S Resninment: Technical Specification 6.14.A requires that licensee initiated g major changes to the radioactive waste systerns (liquid, gaseous.

E and solid) be reported to the Conunission in the Semiannual Radioactive Effluent Release Report for the period in which .ae evaluation was reviewed by the Plant Operation Review Conunittee.

w Respons.c There were no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and rolid) during I this reporting period.

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APPENDIX J I ON-SITE DISPOSAL OF SEPTIC WASTE I Esquirrmettt: Off-Site Dose Calculational Manual Append h B requires that the dose impact due to on-site disposal of septic waste during the g

E reporting year and from previous years be reported to tio Commission in the Semiannual Radioactive Effluent Report filed after January 1, if disposaic occur during the reporting year.

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reporting year.

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