Text

Effluent & Waste Disposal Annual Rept 1995
	ML20108D028
Person / Time
Site:	Seabrook
Issue date:	12/31/1995
From:	; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	;
Shared Package
ML20108D026	List: ML20108D023; ML20108D028; ML20108D037; ML20108D045;
References
	NUDOCS 9605070250
	Download: ML20108D028 (251)
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l

Supplementallnformation 1995 l Facility: Seabrook Station Unit 1 Licensee: North Atlantic Energy Service Corporation

1. Regulatorv Limits A. Gaseous Effluents l

a. 5.0 mrad per quarter gamma air dose.

b. 10.0 mrad per quarter beta air dose.

c. 7.5 mrem per quarter to any orga:

B. Liquid Effluents

a. 1.5 mrem per quarter total body.

b. 5 mrem per quarter to any organ. l

2. hiaximum Permissible Concentrations Provide the MPC's used in determining allowable releases rates or concentrations.

a. Fission and activation gases: 1MPC

b. lodines: 1 MPC

c. Particulates, half-lives > 8 days: 1 MPC l

d. Liquid effluents: 1 MPC i 1

3. Average Energy l Not applicable.

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l 9605070250 960501 PDR ADOCK 05000443 R PDR

4. Measurements and Annroximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

a. Fission and activation gases: Determined by gamma spectroscopy. Total error is based on stack flow error, analytical error and calculated sampling error.

b. Iodines: Determined by collection on charcoal with subsequent gamma spectroscopy analysis. Total error is based on stack flow error, analytical error and calculated sampling error.

c. Particulates: Determined by collection on fixed filter with subsequent gamma spectroscopy analysis. Strontium is determined by composite analysis of filters by liquid scintillation, gross alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on stack flow error, analytical error and calculated sampling error.

d. Liquid Efiluents: Determined by gamma spectroscopy. A composite sample is analyzed for strontium by liquid scintillation, tritium by liquid scintillation, alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on the volume discharge error and analytical error.

5. Batch Releases Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.

a. Liquid l

1. Number of batch releases: 158

2. Total time for batch releases: 29780 minutes ,

3. Maximum time period for batch release: 755 minutes

4. Average time period for batch release: 188 minutes

5. Minimum time period for batch release: 66 minutes

6. Average stream flow during periods of release of effluent into a flowing stream: 1.54E06 liters per minute

b. Gaseous

1. Number of batch releases: 74

2. Total time for batch releases: 45000 minutes i

3. Maximum time period for batch release: 5119 minutes

4. Average time period for batch release: 608 minutes

5. Minimum time period for batch release: 0.5 minutes

6. Abnormal Releases

a. Liquid 1

1

1. Number of releases: 0

2. Total activity releases: N/A

b. Gaseous

1. Numberofreleases: 0

2. Total activity releases: N/A

TABLE 1A

-EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Quarter Quarter Est. Total 1 2 3 4 Error, %

A. Fission and activation gases

1. Total releases C1 1.43E-01 1.84E-01 4. 00i OI'6. 6 9E 01 1.70E+01l

2. Average release rate uctisec 1.84E-02 2.35E-02 5.03E-02 1.1.9E-01 for period

3. Percent of applicable % 2.84E-03 2.86E-02 3.12E-02 1.10E-01 Technical Specification limit B. Iodines

1. Total release C1 ND ND ND ND 1.50E+01l

2. Average release rate ucaisec N/A N/A N/A N/A for period

3. Percent of applicable % N/A N/A N/A N/A Technical specification limit C. Particulates

1. Total release Ci ND 7.93E-04 ND 1.81E-03 1.80E+01l

2. Average release rate uCais*c N/A 1.010-04 N/A 2.28E-04 for period

3. Percent of applicable t 1. 4 5E- 02 3.64E-02 2.33E-03 6.21E-01 Technical Specification limit

3. Gross alpha radioactivity Ci ND ND ND ND D. Tritium

1. Total release Ci 4.35E-02 4.54E-02 8.66E-02 4.76E+00 1.60E+01j

2. Average release rate uCat**c 5.59E-03 5.77E-03 1.09E-L2 5.99E-01 for period

3. Percent of applicable % 1.45E-02 3.64E-02 2.33E-03 6.21E-01 Technical specification limit l

?

'{

6 TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1995)

GASEOUS EFFLUENTS-ELEVATED RELRASES CONTINUOUS Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4 i

1. Fission and activation gases argon-41 Ci ND ND ND ND krypton-85 Ci ND ND ND ND krypton-85m Ci ND ND ND ND krypton-87 Ci ND ND ND ND krypton-88 Ci ND ND ND ND xenon-133 Ci ND ND ND ND xenon-135 Ci ND ND ND ND xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND l Ci C1 unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND

2. Iodines iodine-131 Ci ND ND ND ND iodine-133 Ci ND ND ND ND iodine-135 Ci ND ND ND ND Total for period Ci ND ND ND ND

3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND cobalt-58 Ci ND ND ND 1.63E-03 cobalt-60 Ci ND ND ND 4.32E-05 chromium-51 Ci ND ND ND 9.75E-05 manganese-54 Ci ND ND ND 5.08E-06 niobium-95 C1 ND ND ND 3.13E-05 iron-59 Ci ND ND ND 4.91E-06 unidentified Ci ND ND ID ND Total for period Ci ND ND ND 1.81E-03 l

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_ _ - - _ _ _ . - . _ _ , . ._ _ _ . - - . . - . _ - . - _ _- - = . - . _ .. -

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1995)

GASEOUS EFFLUENTS-ELEVATED RELEASES BATCH Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 4

1. Fission and activation gases argon-41 C1 1.13E-01 1.60E-01 3.34E-01 6.07E-01 krypton 95 Ci ND ND ND ND kryptor.2 35m Ci ND 1.98E-04 1.65E-03 2.04E-03 )

krypton-87 Ci ND 4.67E-04 3.25E-03 7.39E-03 krypton-88 Ci ND 4.91E-04 3.46E-03 3.45E-03 xenon-133 Ci 2.74E-02 1.39E-02 3.44E-02 1.36E-01 xenon-135 C1 2.70E-03 7.38E-03 1.02E-02 1.90E-02 l xenon-135m Ci ND 3.79E-04 4.53E-03 1.33E-02 I 1

xenon-138 Ci ND 1.56E-03 8.01E-03 ND l Ci C1 1 l

unidentified Ci ND ND ND ND l

Total for period C1 1.43E-01 1.84E-01 4.00E-01 8.69E-01 i I

l

2. Iodines 1 iodine-131 Ci ND ND ND 10 iodine-133 Ci ND ND ND ND l

iodine-135 Ci ND ND ND ND Total for period Ci ND ND ND ND l

3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND

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

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TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1995) i GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS Nuclides Released Unit

{

Quarter Quarter Quarter Quarter 1 2 3 4

1. Fission and activation gases argon-41 Ci ND ND ND ND krypton-85 Ci ND ND ND ND krypton-85m Ci ND ND ND ND krypton-87 Ci ND ND ND ND ,

krypton-88 Ci ND ND ND ND I j xenon-133 Ci ND ND ND ND xenon-135 C1 ND ND ND ND xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND Ci C1 1 l unidentified Ci ND ND ND ND ;

Total for period Ci ND ND ND ND

2. Iodines j iodine-131 Ci ND ND ND ND

) iodine-133 Ci ND ND ND ND iodine-135 Ci ND ND ND ND Total for period Ci ND ND ND ND

3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-137 C1 ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND l

cobalt-58 Ci ND ND ND 2.15E-07 Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND 2.15E-07 1

l

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1995)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 3 $ 4

1. Fission and activation gases argon-41 Ci ND ND ND ND krypton-85 Ci ND ND ND ND krypton-85m Ci ND ND ND ND krypton-87 Ci ND 10 ND ND krypton-88 Ci ND ND ND ND xenon-133 Ci ND ND ND ND xenon-135 Ci ND ND ND 10 xenon-135m Ci ND ND ND ND xenon-138 Ci ND ND ND ND Ci Ci unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND

2. Iodines iodine-131 Ci ND ND ND ND iodine-133 Ci ND ND ND ND iodine-135 Ci ND ND ND ND Total for period Ci ND ND ND ND

3. Particulates strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND l

~

cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND 10 barium-lanthanum-140 C1 ND ND ND ND cobalt-60 Ci ND 7,93E-04 ND ND Ci unidentified Ci ND ND ND ND Total for period Ci ND 7.938-04 ND ND

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l TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS l EATCH MODE l

l l

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND i cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND 3.94E-06 ND iodine-131 Ci 4.92E-05 2.95E-05 ND ND iodine -13 3 Ci 1.35E-05 1.64E-05 ND ND cobalt-57 Ci ND ND 4.22E-06 5.11E-05 cobalt-58 Ci 9.67E-04 8.52E-04 2.03E-03 8.05E-03 cobalt-60 Ci 3.89E-04 4.73E-04 5.18E-04 1.28E-03 chromium-51 Ci ND 4.03E-05 6.00E-05 8.68E-04 iron-55 Ci 4.62E-03 5.12E-03 4.78E-03 6.34E-03 iron-59 Ci ND ND ND 1.92E-05 zinc-65 Ci ND ND ND ND manganese-54 Ci 5.49E-05 6.06E-05 4.03E-05 2.14E-04 zirconium-niobium-95 Ci ND ND 1.13E-05 2.69E-06 molybdenum-99 Ci ND ND ND ND technetium-99m Ci 2.93E-05 4.54E-05 ND ND barium-lanthanum-140 Ci ND ND ND ND cerium-141 Ci ND ND ND ND antimony-124 Ci ND ND ND 1.83E-03 antimony-125 Ci 4.63E-04 5.63E-03 3.92E-03 1.40E-02 bromine-82 Ci 3.41E-05 1.27E-05 ND ND Ci unidentified Ci ND ND ND ND l Total for period (above) l Ci l6.62E-03 l1.23E-02 l1.14E-02 l3.27E-02 l xenon-133 Ci ND ND ND ND xenon-135 Ci ND ND ND ND

l l

TABLE 2B l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS CONTINUOUS MODE 1 Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND iodine-131 Ci ND ND ND ND cobalt-58 Ci ND ND ND ND cobalt-60 Ci 3.94E-04 ND ND ND iron-59 Ci ND ND ND ND zinc-65 Ci ND ND ND ND manganese-54 C1 2.73E-05 ND ND 6.86E-06 chromium-51 Ci ND ND ND ND zirconium-niobium-95 Ci ND ND ND ND molybdenum-99 Ci ND ND ND ND technetium-99m Ci ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND

' cerium-141 Ci ND ND ND ND antimony-125 Ci ND ND ND 1.10E-05 Ci Ci C1 Ci unidentified Ci ND ND ND ND l Total for period (above)l Ci l 4.21E-04 l ND l

ND l 1.79E-05 l xenon-133 Ci PD ND ND ND xenon-135 Ci ND ND ND ND j l

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TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1995)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l

l A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) l 1995 Est. Total l 1. Type of Waste Unit Period Error, %

a. Spent resins, filter sludges, m' E evaporator bottoms, etc. Ci E E

b. Dry compressible waste, m' 1.89 E2 contaminated equip. etc. Ci 8.42 E-1 2.8 El

c. Irradiated components, control m' E rods, etc. Ci E ,E m' E

d. Other (describe) Ci E E 1

I

2. Estimate of major nuclide composition ^(by type of waste) a.

Ci

b. Mn 54 2% 1.68 E-2 Fe 55 63% 5.30 E-1 Co 58 5% 4.21 E-2 Co 60 13% 1.09 E-1 Ni 63 17% 1.43 E-1 c.

d.

3. Solid Waste Disposition Humber of Shipments Mode of Transportation Destination 8 Enclosed truck Envirocare, Clive, Utah

4. Class of Solid Waste: Class A l

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5. Type of Container: Strong Tight Container; 96 Cu. Ft. External, 90 Cu. Ft. Internal Volume l 6. Solidification Agent or Absorbent: None 1

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TABLE 3 ,

i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1995) '

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Trannportation Destination j 0

i l

I

l l APPENDIX A Off-Site Does Calculation Manual Reauirement: Technical Speci0 cation 6.13.2.b requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the Annual Radioactive Ef0uent Release Report for the period in which the change (s) was made effective. Changes made to the Radiological Environmental Monitoring Program (REMP) in accordance with Technical Specification 3.12.1 and 3.12.2 are to be included. i Resnonse: One revision of the ODCM was made during the reporting period. l I

Revision 15

1. Retn...s current terminology and reporting requirements as referenced by I other station documents.

2. ReDects elimination of unnecessary isotopic analyses for non gamma emitting isotopes in normally clean liquid and gas handling systems when no positive indication of contamination is identified by routine gamma isotopic !

measurements. This was a change to Part A, which was subsequently reviewed and approved by the NRC.

3. Correction of several typographical errors.

l Revision 15 of the ODCM was inadvertently included in the 1994 Efnuent i Release Report. Revision 14, the applicable revision for the 1994 Report, is l enclosed for completeness. Since Revision 15 has already been transmitted, it is )

not included in this report. ;

i

RMD CONTROL COPY !

i

OFFSITE DOSE CALCUIATION MANUAL * ;

(ODCM) *

j

- - - - 1

1. Does this manual / manual revision:

a. Make changes in the facility as described in the UFSAR? O Yes No

. b. Make changes in procedures as described in the UFSAR? O Yes kNo

.. c. Involve tests or experiments not described in

the UFSAR? O 'ses No j d. Involve changes to the existing Operating h .. e or require additional licent requiremsnes? O Yes No 1

l . 2. If any of the above questions are tnswered yn, a safety evaluation per

- -- ~ - - - procedure NM 11210 is required. (The individual performing this review shall have completed 10 CFR 50.59 training.)

j s PREPARED BY: J. T. LINVILLE, CHEMISTRY DEPARTMENT SUPERVISOR i SUBMITTED BY:

~'

W. B. LEIAND, CHEMISTRY' AND HEXLTH PHYSICS MANAGER DATE '

SORC REVIEW COMPLETED DURING MEETING NUMBER:

DATE:b !

i APPROVED BY: ///[rMr

IIAM 4/

M 'A. DIPR0 [ STATION MANAGER i

REVISION 14 -- EFFECTIVE: 05/31/94 I

DATE OF 1AST PERIODIC REVIEW: 1/1/93 i _ DATE NEXT PERIOD,I L REVIEW DUE- 1/1/95 l

SUPERSEDED .-

4 l

Nonn Atlantie Energy Senice Cor;uration l

, . - - _ - . - - . - - _ _ - _ . - . - _ . - - . - . . _ _ . - ~ . _ _ . . - . ~ - - - .-. ..

DTSCLAIMER OF RESPONSIBIfITY

.- l This document was prepared by Yankee Atomic Electric Company (" Yankee"). The ;

use of information contained in this document by anyone other than Yankee, or the :

Organization for which the document was prepared under contract, is not authorized l and, with respect to any unauthorized use, neither Yankee nor its officers, l directors, agents, or employees assume any obligation, responsibility, or liability or make any warranty or representation as to the accuracy or completeness of the !

material contained in this document.

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Page 1 of 1 ODCM Rev. 14

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i ABSTRACT i

l The Offsite Dose Calculation Manual (ODCM) is divided into two parts: (1) the in-plant Radiological Effluent Monitoring Program requirements for liquid and gas l

' sampling and analysis, along with the Radiological Environmental Monitoring Program !

requirements (Part A); and (2) approved methods to determine effluent monitor i setpoint values and esti; nates of doses and radionuclide concentrations occurring bevond the boundaries of Seabrook Station resulting from normal Station operation (Pc.t B). i 1

The sampling and analysis programs in Part A provide the inputs for the models of Part B in order to calculate offsite doses and radionuclide concentrations !

necessary to determine compliance with the dose and concentration requirements of :

the Station Technical Specification 3/4.11. The Radiological Environmental ,

Monitoring Program required by Technical Specification 3/4.12 and outlined within j this manual provides the means to determine that measurable concentrations of radioactive materials released as a result of the operation of Seabrook Station are ,

not significantly higher than expected. l l

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Page 1 of 1 ODCM Rev. 14 1

q TABLE OF CONTENTS _

k CONTENT 2691 !

PART A: RADIDIDCICAL EFFLUENT MONITORING PROGRAMS }

i

1.0 INTRODUCTION

A.1-1 '

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2.0 RESPONSIBILITIES FOR PART A A.2-1 3.0 LIQUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM A.3-1 4.0 CASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM A.4-1 .

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING A.5-1 5.1 SAMPLING AND ANALYSIS PROGRAM A.5-1 5.2 IAND USE CENSUS A.5 2 3 FART B: RADIOIDGICAL CALCULATIONAL METil0DS AND PARAMETERS

1.0 INTRODUCTION

B.1-1 1.1 RESPONSIBILITIES FOR PART B B.1-1 1.2

SUMMARY

OF METHODS, DOSE FACTORS, LIMITS, CONSTANTS, VARIABLES AND DEFINITIONS B.1-2

~

2.0 METHOD TO CALCUIATE OFF SITE LIQUID CONCENTRATIONS B.2 1 2.1 METHOD To DETERMINE 3F N ANDC/G B.2 *

SB 2.2 METHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE B.2-2 2.2.1 Waste Test Tanks B.2 2 2.2.2 Turbine Building Sump B.2-3 2.2.3 Steam Generator Blowdown Flash Tank B.2-3 2.2.4 Primary Component Cooling Water (PCCW) System B-2.3 5.0 OFF-SITE DOSE CALCUIATION METHODS B.3 1 3.1 INTRODUCTORY CONCEPTS B.3 3 3.2 METHOD TO CALCULATE TOTAL BODY DOSE FROM LIQUID RELEASES B.3 5 3.2.1 Method I B.3-5 3.2.2 Method II B.3-6 3.3 METHOD TO CALCULATE MAXIMUM ORGAN DOSE FROM LIQUID '

RELEASES B.3 7 3.3.1 Method I B.3 7 3.3.2 Method II B.3 8 Page 1 ODCM Rev. 14

,m _ -

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.i TABLE OF CONTENTS CONTENT PAGE PART B: RADICIDCICAL CAlfUIATIONAL METHODS AND PARAMETERS 3.0 0FF-SITE DOSE CALCULATION METHODS 3.4 METHOD TO CALCUIATE THE TOTAL BODY DOSE RATE FROM NOBLE CASES B.3 9 3.4.1 Method I B.3-10 3.4.2 Method II B.3 12 3.5 HETHOD TO CALCULATE THE SKIN DOSE RATE FROM NOBLE CASES B.3 13 3.5.1 Method I B.3 14 3.5.2 Method 11 B,3 17 3.6 METHOD TO CALCULATE THE CRITICAL ORGAN DOSE RATE FROM 10 DINES, TRITIUM AND PARTICULATES WITH Tuz CREATER THAN 8 DAYS B.3 18 3.6.1 Method I B.3 18 3.6.2 Method II B,3 22

~

~ ~~~ ~ ~

3.7 METHOD Td CAI2U1 ATE THE ' GAMMA AIk DOSE It0'M NOBLE'" ~~" ~

CASES B.3 23 3.7.1 Method I B.3 23 3.7.2 Method II B.3 25 3.8 METHOD TO CALCUIATE THE BETA AIR DOSE FROM NOBLE CASES B.3 26 3.8.1 Method I B.3 26 3.8.2 Method II B.3 29 3.9 METHOD TO CALCULATE THE CRITICAL ORGAN DOSE FROM 10 DINES, TRITIUM AND PARTICULATES B.3 30 3.9.1 Method I B.3 30 3 . 't . 2 Mithod 11 B,3 32 3.10 METHOD TO CALCULATE DIRECT DOSE FROM PLANT OPERATION B.3 34 3.10.1 Method B,3 34 3.11 DOSE PROJECTIONS B.3 35 3.11.1 Liquid Dose Projections B.3 35 3.11.2 Caseous Dose Projections B.3 36 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING l'ROGRAM B.4 1

....a am .m

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TABLE OF CONTENTS CONTENT FAGI PART B: RADIDIDCICAL CALCULATIONAL METil0DS AND PARAMETERS 5.0 SETPOINT DETERMINATIONS B.5-1 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS B.5-2 5.1.1 Liquid Waste Test Tank Monitor (RM 6509) B.5-2 5.1.2 Turbine Building Drains Liquid Effluent Monitor (RM 6521) B.5 5 5.1.3 Steam Generator Blowdown Liquid Sample Monitor (RM 6519) B.5-6 5.1.4 PCCW Head Tank Rate-of Change Alarm Setpoint B.5-7 n

5.2 CASEQUS EFFLUENT INSTRUMENTATION SETPOINTS B.5-9 5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528 1. 2 and 3) B.5 9

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6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWASTE TREATMENT SYSTEMS B.6 1

__ 7.0 BASES _FOR DOSE cal,CUIATION METHODS _ _ _ _ . . _ _ _ _. __ _... B_. 7_- 1.__ __

7.1 LIQUID RELEASE DOSE CALCULATIONS B.7 1 s ..

7.1.1 Dose to the Total Body B.7-5 7.1.2 Dose to the Critical Organ B.7-5

~

7.2 CASEOUS RELEASE DOSE CALCUIATIONS B.7-8 7.2.1 Total Body Dose Rate From Noble Cases B.7 8 7.2.2 Skin Dose Rate From Noble Cases B.7 10 7.2.3 Critical Organ Dose Rate From Iodines, Tritium and Particulates With Half Lives Creater Than Eight Days B.7-13 7.2.4 Camma Dose to Air F6cm Noble Cases B.7 15 7.2.5 Beta Dose to Air From Mohle Cases B.7-17 7.2.6 Dose to Critical Organ From Iodines. Tritiwn and Particulates With Half Lives Greater Than Eight Days B.7 19 7.2.7 Spetir.1 Receptor Caseous Release Dose Calculations B.7 21 7.3 RECEPTOR POINTS AND AVERACE ATMOSPilERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS B.7 35 7.3.1 Receptor Locations B.7-35 7.3.2 Scabrook Station Atmospheric Dispersion Model B.7-36 7.3.3 Average Atmospheric Dispersion Factors for Receptors B.7-36

( . m.. mh

TABLE OF CONTENTS CONTENT FAG.E FART B: RADIOIDGICAL CAIEUIATIONAL METil0DS AND PARAMETERS 8.0 BASES FOR LIQUID AND GASEOUS MONITOR SETPOINTS B.8 1 8.1 BASIS FOR THE LIQUID WASTE TEST TANK HONITOR SETPOINT B 8.1 8.2 BASIS FOR THE PLANT VENT WIDE RANGE CAS MONITOR SETPOINTS B.8 4 8.3 BASIS FOR PCCW HEAD TANK RATE-OF-CHANGE ALARM SETPOINT B.8 9 REFERENCES R1 APPENDIX A: DOSE CONVERSION FA': TORS A-1 m-Page 4 ODCM Rev., 14 . ,,

LIST nF TQJ,IS, NtHB EP, TITLE NSE PART A

! A.3 1 Radioactive Liquid Waste Sarepling and Analysis Program A.3-2 A.4 1 Radioactive Caseous Waste Sampling and Analysis Program A.4-2 A.5-1 Radiological Environmental Monitoring Program A.5 3 A.5 2 Detection Capabilities for Environmental Sample Analysis A.5-7 A53 Reporting Levels for Radioactivity Concentration in Environmental Samples A.5-10 PART B B.1 1 Summary of Radiological Effluent Technical Specifications and Implementing Equations B.1-3 I B.1-2

- Summary of Method I Equations to Calculate Unrestricted Area Liquid Concentrations B.1 6 B.1-3 Summary of Method I Equations to Calculate Off-Site Doses from Liquid Releases B.1 7 ___

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B.1 4 Summacy of Method I Equations to Calculate Dose Rates B.1-8 B.1-5 Summary of Method I Equations to Calculate Doses to Air

, from Noble Cases B.1 11

( .. B.1-6 Summary of Method I Equations to Calculate Dose to an Individual from Tritium, Iodine and Particulates B.1 13

[ B.1 7 Summary of Methods for Setpoint Determinations B.1 14 5 B.1 B Summary of Variables B.1 15 B.1-9 Definition of Terms B.1 22

B.1-10 Dose Factors Specific tor Seabrook Station for Noble Gas Releases B.1-23 B.1-ll Dose Factors Specific for Seabrook Station for Liipiid Releases B.1-24 B.1-12 Dose and Dose Rate Factors Specit'ic for Seabrook Station for lodines, Trititun and Particulate Releases B.1 25 B.1 13 Combined Skin Dose Factors Specific for Seabrook Station Special Receptors for Noble Gas Release B.1 26 B.1-14 Dose and Dose Rate Factors Specific for the Education Center

[ ior Iodine. Tritium, and Particulate Releases B.1-27 I

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,_...._........,..-----s

1 LIST OF TABLES - ,

NUMBER TITLE EAGE PART B (Continued) .,

B.1-15 Dose and Dose Rate Factors Specific for the " Rocks" for Iodine. Tritium, and Particulate Releases B.1-28 a

B.4 1 Radiological Environmental Monitoring Stations B.4-2 B.7 1 Usage Factors for Various Liquid Pathways at seabrook B.7 7 Station B.7 2 Environmental Parameters for Caseous Efi'luents at Seabrook Station B.7 32 B.7-1 Usage Factors for Various Caseous Pathwayn at Seabrook

- Station B.7-34 B.7 4 Seabrook Station Long Term Aver. age Dispersion Factors Primary Vent Stack B,7 39 B.7-5 Seabrook Station Long Term Average Dispersion Factors for ,

Special (On-Site) Receptors Prim.ary Vent Stack B.7-40 B.7-6 Seabrook Station Long Term Atmospheric Diffusion and Deposition Factors Ground-Level Release Pathway B.7 41 1

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t LIST OF EFFECTIVE PAGES

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i- Cover 14 B.1 14 14

? B.1-15 14 J Disclaimer 14 B.1-16 14 9f B.1 17 14 Abstract 14 B.1 18 14 N B.1 19 14 k TOC 1 - 4 14 B.1 20 14 ei B.1-21 14

[ List of Figures 14 B.1 22 14 TJ B.1-23 14 O List of Tables 1 14 B.1-24 14 m: 2 14 B.1-25 14 E B.1 26 14 A LOEP 1 - 2 14 B.1-27 14 r, '

~.. B.1 28 14 f3 A.1 1 10 h a B.2 1 12

{ A.2 1 4 B.2 2 12 B.2-3 12 b[- A. 3 1 4 f A.3-2 4 B.3 1 12 9; A.3 3 4 B.3-2 12 h A.3-4 4 B.3-3 12 L' A.3 5 4 B.3-4 12 A.3 6 4 B.3-5 f.[ , 14 B.3 6 14

{ A.4-1 4 B.3 7 14 d % A42 4 B.3-8 14 1, : A.4-3 4 B.3 9 14 1 '

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A.4 5 4 B.3-11 14 h- B.3-12 14

.3 - A.5-1 4 B.3-13 14 E A.5 2 4 B.3 14 14 E A.5 3 4 B.3-15 14 J A.5 4 4 B.3 16 14

? A.5 5 4 B.3 17 14 k A.5 6 4 B.3-18 (j A.5 7 4 B,3 19 14 14 A.5 8 4 B.3-20 14 r@i A.5 9 4 B.3-21 14

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[ B.3-23 14 B.1-1 14 B.3 24 14 B.1 2 14 B.3 25 14 B.1 3 4 B.3 26 14 l B.1-4 12 B.3-27 14

B.1 5 4 B,3 28 14 B.1 6 8 B,1 29 14

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14 B.3 30 B . 't 31 14 14 B.1 9 14 B,3 32 14 B.1-10 14 B.3 33 14 B.1 11 14 B.1-34 14 B.1 12 14 B.1-15 14 B.1 13 14 B.3-36 14 Parp 1 ODCM Rev. 14

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B.3-37 14 B 7 26 14 B.7 27 14 B.4 1 9 B 7 28, 14 B.4-2 11 B,7 79) 14 B.4 3 4 B 7-30* 14 B.4 4 11 B.7 31! 14 B.4-5 9 B.7 32- 14 B.4 6 9 B.733j 14 B.4 7 8 B. 7 341 14 B.4-8 8 B.7 35 14 B.4 9 8 B 7-36 14 B.4 10 11 B,7 37 14 B.7 38 14 B.5-1 7 B.7 14 B.5 2 4 B740 14 B.5-3 8 B.7-41 14 B.5-4 4 .

B.5 5 10 B,g.1 4 B.5-6 to B,g.y '{ 4 B.5-7 10 B.8-3 4 B.5 8 10 B g.4 8 B 5-9 7 B,g.$ 4 B.5-10 7 B.8-6 7

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I 1 I

PART A l

RADIOLOGICAL EFFLUENT MONITORING PROGRAMS I.0 INTRODUCTION 1

1 The purpose of Part A of the ODCM (Off-Site Oose Calculation Manual) is I to describe the sampling and analysis programs conducted by the Station which ;

provides input to the models in Part B for calculating liquid and gaseous effluent concentrations, monitor setpoints, and off-site doses. The results of Part B calculations are used to determine compliance with the concentration and dose requirements of Technical $pecification 3/4.11.

The Radiological Environmental Monitoring Program required as a minimum l to be conducted (per Technical Specification 3/4.12) is described in Part A, with the identification of current locations of sampling stations being utilized to meet the program requirements listed in Part B. The information obtained from the conduct of the Radiological Environmental Monitoring Program provides data on measurable levels of radiation and radioactive materials in the environment necessary to evaluate the relationship between quantities of radioactive materials released in effluents and resultant radiation doses to individuals fecm principal pathways of exposure. The data developed in the j surveillance and monitoring programs described in Part A to the 00CM provide a I means to confirm that measurable concentrations of radioactive materials released as a result of Seabrook Station operations are not significantly higher than expected based on the dose models in Part B.

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A.1-1 l

4626R 00CM Rev. 10

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2.0 RES90NSiSTLITTES FOR PART a All changes to Part A of the 00CM shall be reviewed and approved by t..e Station Operations Review Committee (50RC) and the Nuclear Regulatory Commission prior to implementation.

It shall be the responsibility of the Station Manager to ensure that

~

the 00CM is used in the performance of the surveillance requirements and administrative controls of the appropriate portions of the Technical Specifications.

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I A.2-1 J

CDCM Rev. 4

3.0 LIOUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table. A.3-1 for Seabrook Unit 1. The results of the radioactive analysis shall be used as appropriate with the methodology of l Part B of the 00CM to assure that the concentrations of liquid effluents at the point of release from the multiport diffuser of the circulating water system are maintained within the limits of Technical Specification 3.11.1.1 for Unit 1.

Radioactive Gffluent information for liquids obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part B to demonstrate compliance with the dose objectives and surveillar.ce requirements of Technical Specifications 3/4.11.1.2, 3/4.11.1.3, and 3/4.11.4.

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A.3-1 ODCM Rev. 4

TABLE A.3-1 Radioactive Liquid Waste Sampling and Analysis Program Lower Limit Liquid Minimum Type of of Detection Release Sampling Analysis Activity (LLD) (1) ,

(uct/ mil Freauency Frequency Analysis Type P P Principal Gamma A. Liquid 5x10-7 Radwaste Each Batch Each Batch Emitters (3)

Test Tanks 1x10-6 I-131 (Batch Dissolved and 1x10-5 ,

Release)(2) P M '

One Batch /M Entrained Gases (Ganuma Emitters)

T w

M(4) H-3 lx10-5 ;

b P Each Batch Composite '

1

' Gross Alpha 1x10-7 Q(4) Sr-B9, Sr-90 5x10-8 P

Each Batch Composite i Fe-55 1x10-6 W Principal Gansna t B. Turbine Bu11 ding W 5x10-7 Sump Effluent (B) Grab Sample Emitters (3)

I-131 1x10-6 o ,.

g -

(Continuous '

M Dissolved and '

= Release (5) W 1x10-5 Grab Sample Entrained Gases

,I (Gamma Emitters) c- j I

') i

T_ABLE A.3-1 Radleactive Liquid Waste Sampling and Analysis Program (continued)

Lower Limit Liquid Minimum Type of of Detection Release Sampling Analysis Activity (LLD) (1)

Type Frequency Frequency Analysis fact /ml)

W M H-3 1x10-5 Grab Sample Gross Alpha 1x10-7 W Q Sr-89, Sr-90 5x10-8 Grab S w le 1x10-6 Fe-55

? '

" W W Principal Gamma C. Steam Generator [mitters(3) 5x10-7 Blowdown Flash Grab Sample Tank (6)(8) I-131 1x10-6 (Continuous M Dissolved and 1x10-5 Release)(5) W Grab Sample Entrained Gases (Gamma Emitters)

M H-3 1x10-5 bl i Grab Sample 1x10-7 o Gross Alpha 8

r . _ _ _

Sr-89, Sr-90 5x10-8 2

W Q

' Grab Sample 1x10-6 Ie-55

~^

O

. . _ _ _ . . _ _ . . _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ . . _ _ _ - _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . a

TABLE A.3-1 Radioactive Lieuid Waste Sampling and Analysis Program (continued)

Lower Limit Liquid Minimum Type of of Detection Release Sampling Analysis Activity (LLD) (1).

Type Frequency Frequency Analysis fuct/ mil ,

t O. Service Water (I) W W Principa) Gamma '

Grab Sample Emitterst3) 5x10-7 I-131 1x10-6 W M Dissolved and Grab Sample Entrained Gases 1x10-5 '

(Gamma Emitters)

W M H-3 1x10-5

> Grab Sample Gross Alpha 1x10-7 L

E W Q Sr-89, Sr-90 5x10-8 Grab Sample Fe-55 1x10-6 i

P - Prior to 01scharge W - Weekly M - Monthly 4 - Quarterly g

0 n

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TABLE A.3-1 Notations (I)The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net i count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s b LLD = 6 i

E x V x 2.22 x 10 x Y x exp (-Act)

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), ,

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegra' tion),

Y = the sample size (units of mass or volume),

2.22 x 10-6 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, h = the radioactive decay constant for the particular radionuclide (s-l),and at = the elapsed time between the midpoint of sample collection and the time of counting (s). -

i Typical values of E, Y, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an i oriori (before the fact) limit representing the capability of a measurement system and not as l an g costeriori (after the fact) limit for a particular measurement.

(2)A batch release is the discharge of liquid wastes of a rcrete volume.

i Prior to sampling for analyses, each batch shall be isolated, and then i thoroughly mixed to assure representative sampling.

A.3-5 ODCM Rev. 4

TABLE A.3-1 Notations (Continued)

(3)The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4. Isotopes which are not detected should be reported a "not detected." Values determined to be below detectable levels are not used in dose calculations.

(4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5)A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., f rom a volume of a system that has an input flow during the continuous release.

(6) Sampling and analysis is oaly required when Steam Generator Blowdown is directed to the discharge transition structure. ,

(7) Principal gamma emitters shall be analyzed weekly in Service Water.

Sample and analysis requirements for dissolved and entrained gases, tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gama emitters exceeds the LLD.

The following are additional sampling and analysis requirements:

a. PCCW sampled and analyzed weekly for principal gamma emitters.

b. Sample Service Water System (SWS) daily for principal gamma emitters whenever primary component cooling water (PCCW) activity exceeds )

1x10-3 uC/cc. ,

c. With the PCCW System radiation monitor inoperablie, sample PCCW and SWS daily for principal gama emitters.

d. With a confirmed PCCW/SWS leak and PCCW activity in excess of 1x10-4 uC/ce, sample SWS every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for principal gamma emitters.

e. The setpoint on the PCCW head tank liquid rate-of-change alarm will be set to ensure that its sensitivity to detect a PCCW/SWS leak is equal to oc greater than that of an SWS radiation monitor located in the unit's ambined SWS discharge, with an LLD of 1x10-b uC/cc. If this i sensitivity cannot be achieved, the SWS will be sampled once every 12 l hours. l (8)lf the Turbine Building Sump (Steam Generator Blowdown Flash Tank) l isolate due to high concentration of radioactivity, that liquid stream will l be sampled and analyzed for Iodine-131 and principal gama emitters prior to release. l A.3-6 ODCM Rev. 4

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4.0 GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table. A.4-1 for Seabrook Unit 1. The results of the radioactive analyses shall be used as appropriate with the methodologies of Part B of the 00CM to assure that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site bouridary are within ,the limits of Technical Specification 3.11.2.1 for Unit 1.

Radioactive effluent information for gaseous wastes obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part 8 to demonstrate compliance with the dose objectives and surveillance requirements of Technical Specifications 3/4.11.2.2, 3/4.11.2.3, 3/4.11.2.4, and 3/4.11.4.

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4 A.4-1 ODCM Rev. 4

TABLE A.4-1 Radioactive Gaseous Waste Sampling -

and Analysis Program Minimum Type of Lower Limit Gaseous of Detection (l)

Release Sampilng Analysis Activity Frequency Frequency Analysis (LLD) (uC1/cci Type M Principal Ganna Emitters (2) 1x10-4

1. Plant Vent M(3)(4)

Grab Sample H-3 1x10-6

~

w(6) g_;33 1 x10-12 Continuous (5)

Charcoal Sample

? Principal Ganna Emitters (2) jxio-11 Continuous (5) w(6)

[ Particulate Sample M Gross Alpha 1x10-Il Continuous (5)

Composite Particulate Sample Sr-89, Sr-90 1x10-Il Continuous (5) Q Composite Particulate '

Sample 9 :

E Principal Ganna Emitters 1x10-4 M(7) M(7) f 2. Condenser Air e Removal Exhaust Grab Sample 1x10-6 11 - 3

TABLE A.4-1 Radioactive Gaseous Waste Sampling and Analysis Program (continued) .

Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection (l)

Type Frequency Frequency Analysis (LLD) (uC1/cc)

3. Gland Steam Continuous W Principal Ganna Emitters (2) j xio-11 Packing Ex.hauster Particulate Sample Continuous W I-131 lx10-12

- Charcoal Sample Continuous M Gross Alpha 1x10-Il

[ Composite Particulate Sample 1 Continuous Q Sr-89, Sr-90 1x10-Il Composite Particulate Sample

4. Containment P(3) P Principal Ganna Emitters (2) 1x10-4 8 Purge Each Purge Grab Each Purge Sample H-3 (oxide) lx10-6 9

5'

?

V e

TABLE A.4-1 Notations -

(1)The LLD is defined, for purposes of these specifications, as the sma?lest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percen't probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s b ,

l LLD = 6 E x V x 2.22 x 10 x Y x exp (-Aat)

Where:

LLD = the "a priori' lower limit of detection (microcurie per unit l mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 10-6 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (s-l), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an g oriori (before the fact) limit representing the capability of a measurement system and not as an i costeriori (after the f act) limit for a particular measurement.

A.4-4 ODCM Rev. 4

TABLE A.4-1 Radioactive Gaseous Waste Sampling and Analysis Program (continued)

Notations

(

}The principal gamma emitte'rs for which the LLD specification applies includes the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135,.and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144, in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report in accordance with Technical Specificatica 6.8.1.4 Isotopes which are not detected should be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations.

(

Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period unless; 1) analysis shows that the DOSE EQUIVALENT I-131 concentrations in the primary coolant has not increased more than a factor of 3; and 2) the noble gas activity monitor for the plant vent has not increased by more than a factor of 3. For containment purge, requirements l apply only when purge is in operation.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(

}The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation I

made in accordance with Technical Specifications 3.11.2.1, 3.11.2.2, and l 3.11.2.3. l (6) Samples shall be changed at least once per seven (7) days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least seven (7) days following each shutdown, startup..or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one-hour period {

and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples l collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be l increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

(7) Samples shall be taken prior to start-up cf condenser air removal system when there have been indications of a primary to e?condary leak.

A.4-5 ODCM Rev. 4

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Samoline and Analysis Program The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of members of the public resulting from station ;

operation. This monitoring program is required by Technical l Specification 3.12.1. The monitoring program implementsSection IV.B.2 of !

Appendix I to 10CFR, Part 50, and thereby supplements the radiological l I

effluent monitoiing program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways which have been incorporated into Part 8 of the 00CM.

The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

In accordance with Technical Specification surveillance requirements, 4.12.1, sampling and analyses shall be conducted as specified in Table A.5-1 for locations shown in Section 4 of Part 8 to the 00CM. Detection capability requirements, and reporting levels for radioactivity concentrations in environmental samples are shown on Tables A.5-2 and A.5-3, respectively.

It should be noted that Technical Specification 3.12.1.C requires that if milk or fresh leafy vegetable samples are unavailable from one or more sample locations required by the REMP, new specific locations for obtaining replacement samples (if available) shall be added to the REMP within 30 days, and the specific locations, from which the samples are unavailable may then be deleted f rom the monitoring program. In this context, the term unavailable means that samples are no longer available to be collected now or in the f1ture for reasons such as the permission from the owner te collect the samples has been withdrawn or he has gone out of business, thus causing the permanent lose of the sample location.

A . 5 -1 ODCM Rev. 4

5.2 Land Use Census As part of the Radiological Environmental Monitoring Program, Technical Specification 3/4.12.2 requires that a land use census be conducted annually during growing season to identify within a distance of 8 km the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m producing broad leaf vegetation. -

The land use census ensures that changes in the use of area beyond the site boundary are identified, and appropriate modifications to the monitoring program and dose assessment models are made, if necessary. This census satisfies the requirements of Section IV.3.3 of Appendix I to 10CFR Part 50.

For the purpose of conducting the land use census as required by Technical Specification 4.12.2, station personnel should determine what survey methods will provide the necessary results considering the type of information to be collected and the use to which it will be put, such as the location of potential milk animal pathway for use in routine dose calculations. Land use census results shall be obtained by using a survey method, or combination of methods, which may include, but are not limited to, door-to-door surveys (i.e., roadside identification of locations), aerial surveys, or by consulting local agricultural authorities.

Technical Specification 3.12.2.b requires that new locations identified from the census that yield a calculated dose of dose commitment 20 percent ,

greater than'at a location from which samples are currently being obtained be added within 30 days to the REMP. These new locations required to be added to the sampling program shall only be those from which permission from the owner to collect samples can be obtained and sufficient sample volune is available.

A.5-2 ODCM Rev. 4

TABLE A.5-1 Radiological Envirer.s:stal Monitoring Program l

Number of Representative Exposure Pathway Samples and Sampling and Type and frequency a

Sample Locations Collection Frequency of Analysis and/or Sample 40 routine monitoring stations Quarterly. Gamma dose quarterly.

1. DIRECT RADIAT10Nb with two or more dosimeters placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; -

An outer ring of stations, one in cach meteorological sector, generally in the 6 to 8-km range

? from the site; y

The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and control locations.

2. AIRBORNE Samples from five locationsd: Continuous sampler Radiciodine Cannister:

Radiotodine and operation with sample Particulates collection weekly, or 1-131 analysis weekly.

Three samples from close to the three SITE 8OUNDARY locations, more frequently if required by dust Particulate Sampler:

in different sectors, of high o loading. ,

8 calculated long-term average '

Gross beta radioactivity

ground-level D/Q. analysis following filter x change C-2 One sample from the vicinity of Gamma isotopic analysis e

~

a community having the highest of composite (by location)

' calculated long-term average i quarterly.

ground-level D/Q.

TABLE A.5-1 -

(Continued)

Number of Representative Exposore Pathway Samples and a Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

3. WATERBORNE i One sample in the discharge area. Monthly grab sample. Gama isotopic analysis *

a. Surface monthly. Composite for One sample from a control location. ,

tritium analysis quarterly.

One sample from area with existing Sem1 annually. Gama isotopic analysis e

> b. Sediment from semiannually.

from or potential recreational value.

L shoreline

4. INGESTION Samples from milking animals in Semimonthly when Gama isotopic e and I-131

a. Milk milking animals are on analysis on each sample.

three locations within 5 km .

distance having the highest dose pasture, monthly at potential. If their are none, other times.

then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.f n One sample from milking animals

at a control location, as for

o ext.mple, 15-30 km distant and 0

in the least prevalent wind direction.

e O

_____.__._-._-__.________-_--___--___._-----_____-.---.__--__._.u_ .----___s

i i

TABLE A.5-1 Radioloalcal Environmental Monitoring Program (Continued) l Exposure Pathway Number of Representative Sgsples Sampling and Type and Frequency and/or Sample and Sample Locations Collection Frequency of Analysis [

4

b. Fish and One sample of each of three commer- Sample in season, or Gamma isotopic analysis

Invertebrates cially and recreationally important semiannually if they on edible portions. y species in vicinity of plant are not seasonal. '

discharge area. t One sample of similar species in ,

areas not influenced by plant i

>- discharge. I on :

Oi c. Food Products Samples of three (if practical) Honthly, when Gamma isotopic" and I-131 ~ i different kinds of broad leaf available, analysis. !

vegetationE grown nearest each of

{

two different off-site locations >

of highest predicted long-term '

average ground-level D/Q if milk I sampling is not performed. '

I One sample of each of ths similar Monthly, when Gamma isotopic

and I-131 broad leaf vegetationE grown at available. analysis, i a control location, as for example 15-30 km distant in the laast prevalent wind direction, if allk . I sampling is not performed. i O

{

a: -

E I

.# i s~

. - . . . _ . -. . -- , - .. ._- , - - - - _ . . , , . - - . . . . . _ m ., .- . - - . , - _ . _ _ ..

. TABLE A.5-1 (Continued)

Table Notation a) Specific parameters of distance and direction sector f rom the centerline of the Unit I reactor, and additional description where pertinent, shall be provided for each and every sample location in Table B.4-1 in the 00CM, Part B. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling It is schedule shall be documented in the Annual recognized that, at times, it may not be possible or Radiological Environmental Operating Report.

practicable to continue to obtain samples of the medie of choice at the most desired location or time.

In these instances suitable alternative media and locations may be chosen for the p' icular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location (s), if available, for obtaining replacement samples in the next Semlannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the 00CM reflecting the new location (s).

Y' b)

A thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

c) Airborne particulate sample filters shall be analyzed for grossIfbeta radioactivity gross beta activity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in air or particulate more af ter sampilng to allow for radon and thoron dauchter decay.

samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

d) Optimal air sampling locations are based not only on D/Q but on factors such as population in the area, year-round access to the site, and availability of power.

e)

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

o lhe dose shall be calculated for the maximum organ and age group, using the methodology and parameters h f) in the 00CH, Part B.

g) If broad leaf vegetation is unavailable, other vegetation will be sampled.

v O'

_ . _ _ _ _ m . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ __ _ _ _ _ _ - _ _

TABLE A.5-2 Detection Capah111 ties for Environmental Sample Analysis a f,g Lower Limit of Detection (LLD)b Fish and Invertebrates Milk Food Products Sediment Water AirborneParticglate (DCi/kg) (pC1/kg. wet) (DCi/kg. dry)

Analysis (pC1/kg) or Gas (pC1/m ) (pC1/kg. wet)

Gross Beta 4 0.01 H-3 3,000 15 130 .

Hn-54 30 260 re-59 Co-58, 60 15 130 3

30 260 Zn-65 Z r-Nb-95 ISC 608 1-131 15 0.07 1 130 15 60 150 Cs-134 15 0.05 150 18 80 180 Cs-137 18 0.06 15c,d 15c,d Ba-La-140 8

9 V

_._____.___.______________.._______._______._____.___.__..._____________._____.m. _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ .

TABLE A.5-2 (Continued)

Table Notation a) This list.does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b) The LLD is defined, for purposes of these specifications, as the. smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a 'real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s

E V

2.22

Y exp(-Aat) hhere:

LLO is the *a priori" lower limit of detection as defined above, as picocuries per unit mass or volume; 4.66 is a constant derived from the Kalpha and Kb eta values for the 95% confidence level; sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute; E is the counting efficiency, as counts per disintegration; Y is the sample size in units of mass or volume:

2.22 is the number of disintegrations per minute per picoeurie; '

l Y is the fractional radiochemical yield, when applicable; l h is the radioactive decay constant for the particular radionuclide as per second; and

~

At for environmental samples is the elapsed time between sample collection and time of counting, as seconds. !

l Typical values of E,'V, Y, and At should be used in the calculation.

In calculating the LLO for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., Potassium-40 in milk samples). ,

A.5-8 i ODCM Rev. 4

TABLE A.5-2 (Continued) .

It should be recognized that the LLD is defined as an 1 oriori (before the '

fact) limit representing the capability of a measurement system and not as an g Dosteriori (af ter the f8Ct) limit for a particular measurement. This '

does not preclude the calculation of an a costeriori LLD for a particular measurement based upon the actual parameters for the sample in question and appropriate decay correction parameters such as decay while sampling and during analysis. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally '

background fluctuations, unavoidable small sample sizes, the presence of interf ering nuclides, or other uncontrollable circumstances may render these LLns unachievable. In such cases, the contributing f actors shall be identified and described in the Annual Radio 1cgical Environmental Operating Report.

c) Parent only.

d) The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an eight-day period following collection. The calculation shall be predicated on the normal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample would have decayed to an l insignificant amount (at least 3.6% of its original value). The '

ingrowth equations will assume that the supported La-140 &ctivity at the time of collection is zero.

e) Broad leaf vegetation only, f) If the measured concentration minus the three standard deviation l uncertainty is found to exceed the specified LLD, the sample does not have to be analyzed to meet the specified LLD.

g) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with recommendations of Regulatory Guide 4.13, Revision 1, July 1977.

A.5-9 ODCM Rev. 4

i i

TABLE A.5-3 ReDorting levels for Radioactivity Concentrations in Environmental Samples Fish and ,

Water AirborneParticglate Invertebrates Milk Food Products Analysis (DC1/ke) or Gas (DC1/m ) (DC1/kG. Wet) (DCl/kg) (DCl/kG. Wet)

H-3 30,000 ,

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400*

o 100 0.9 3 100**

I-131 10 1,000 60 1,000 Cs-134 30 20 2,000 70 2,000 Cs-137 50 200* 300*

Ba-La-140 O

n

Parent only.

x *a Broad leaf vegetation only.

E

?

Y

i l

SEABROOK STATION ODCM PART B RADIOLOGICAL CALCULATIONAL HETHODS AND PARAMETERS l

l R12\86

1.0 INTRODUCTION

Part B of the ODCH (Off-Site Oose Calculation Manual) provides formal 1 and approved methods for the calculation of off-site concentration, off site doses and effluent monitor setpoints, and indicates the locations of environmental monitoring stations in order to comply with the Seabrook Station Radiological Effluent Technical Specifications (RETS), Sections 3/4.3.3.9, 3/4.3.3.10, and 3/4.11, as well as the REHP detailed in Part A of the manual.

The ODCH forms the basis for station procedures which document the off-site doses due to station operation which are used to show compliance with the numerical guides for design objectives of Section !! of Appendix ! to 10CFR Part 50. The methods contained herein follow accepted NRC guidance, inless otherwise noted in the text.

1.1 Resoonsibilities for Part B n

,, All changes to Part B of the ODCH shall be reviewed and approved by the Station Operations Review Committee (50RC) in accordance with Technical Specification 6.13 prior to implementation._ Changes made to Part B shall be_

submitted to the Commission for their information in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.

, . It shall be the responsibility of the Station Hanager to ensure that the ODCH is used in the performance of in plant surveillance requirements and administrative controls of the appropriate portions of the Technical Specifications, and Effluent Control Program detailed in Part A of the manual.

The Woduc+5on Or.iccs he;cc shall be responsible to ensure that the Radiological Environmental Monitoring Program described in Section 4 of Part B is implemented in accordance with Technical Specification 3/4.12 and Part A of this manual.

l In addition to off site dose calculations for the demonstration of l compliance with Technical Specification dose limits at and beyond the site l boundary.10CFR20.1302 requires that compliance with the dose limits for l Individual members of the public (100 mrem /yr total effective dose equivalent) l be demonstrated in controlled areas on site. Demonstration of compliance with l the dose limits to members of the public in controlled areas is implemented l per Radiation Protection Department Procedures, and 1.i outside the scope of l

Executive Director - Nuclear Production R12\86 B.1 1 ODCM Rey. 14

l the ODCH. However, calculations performed in accordance with the ODCM can be j l used as one indicator of the need to perform an assessment of exposure to j l members of the public within the site boundary. Since external direct l exposure pathways are already subject to routine exposure rate surveys and l

l measurements, only the inhalation pathway need be assessed. The accumulated

' l critical organ dose at the site boundary, as calculated per ODCM Sections 3.9 4

and 3.11, can be used as an indicator of when additional assessments of f ll on site exposure to members of the public is advisable (see Section 3 l Off-site critical organ doses from station effluents should not, however, be l the only indicator of potential on site doses.

i 1.2 Summary of Methods. Dose Factors. Limits. Constants. Variables and j Definitions b'

This section summarizes the Method I dose equations which are used as \

j the primary means of demonstrating compliance with RETS. The concentration and setpoint methods are identified in Table B.1-2 through Table B.1 7. Where

{ more refined dose calculations are needed, the use of Method !! dose l determinations are described in Sections 3.2 through 3.9 and 3.11. The dose j

factors used in the equations are in Tables B.1-10 through B.1 14 and the j

Regulatory Limits are summarized in Table B.1 1.

)

The variables and special definitions used in this ODCH Part B. are in l Tables B.1-B and B.1 9. l i

i

! 1 1

J 1

i i

l

] R12\86 B.1 2 4 ODCM Rev.14 1

1 w

g TABLE B.1-1 Summary of Radiological Effluent Technical Specifications and Imolementino Eauations (1)

Technical SDecification Cstecory Method I limit 3.11.1.1 Liquid Effluent Total FEaction of Eq. 2-1 1 1.0 Concentration MPC Excluding Noble Gases Total Noble Gas Eq. 2-2 1 2 x 10'd pC1/mi Concentration 3.11.1.2 Liquid Effluent Total Body Dose Eq. 3-1 1 1.5 mrem in a qtr.

00se 1 3.0 mrem in a yr.

Organ Dose Eq. 3-2 1 5 mrem in a qtr.

T 1 10 mrem in a yr.

w 3.11.1.3 Liquid Radwaste Total Body Dose Eq. 3-1 1 0.06 mrem in a mo.

Treatment Operability Organ Dose Eq. 3-2 1 0.2 mrem in a mo.

3.11.2.1 Gaseous Effluents Total Body Dose Rate Eq. 3-3 1 500 mrem /yr.

Dose Rate from Noble Gases ,

Skin 00se Rate Eq. 3-4 1 3000 mrem /yr.

from Noble Gases Organ Dose Rate Eq. 3-5 1 1500 mrem /yr.

from I-131. I-133.

Tritium and o Particulates with y T1/2 > 8 Days

?

t m TABLE 8.1-1

$$ (Continued) 6 o.

Summary of Radioloalcal Effluent Technical Specifications and Implementina Eauations t i

(1)

Technical Specification Cate'aory Method I Limit 3.11.2.2 Gaseous Effluents Gamma Air Dose from Eq. 3-6 1 5 mrad in a qtr. !

Dose from Noble Noble Gases j Gases ji 10 mrad in a yr. '

Beta Air Dose from Eq. 3-7 1 10 mrad in a qtr.

Noble Gases 1 20 mrad in a yr. !

l 3.11.2.3 Gaseous Effluents Organ Dose from Eq. 3-8 1 7.5 arer.In a qtr.

Dose from I-131 Iodines. Tritium and o' I-133. Tritium. Particulates with 1 15 mrem in a yr.

and Particulates T1/2 > 8 Days 3.11.2.4 Ventilation Organ Dose Eq. 3-8 1 0.3 arem in a mo.

Exhaust Treatment 3.11.4 Total Dose (from Total Body Dose Footnote (2). 1 25 mrem in a yr.

All Sources) 1 Organ Dose 1 25 arem in a yr. .

Thyroid Dose 175 mrea in a yr.

3.3.3.9 Liquid Effluent l

Monitor Setpoint Liquid Waste Test Alarm Setpoint Eq. 5-1 T.S. 3.11.1.1 i f %

x Tank Monitor E?

l l -

)

l I

=- TABLE B.1-1

[3 (Continued) co Summary of Radioloolcal Effluent Technical Specifications and implementina Eaustions (1)

. Technical Specification Cate'cory Method I limit 3.3.3.10 Gaseous Effluent Monitor Setpoint Plant Vent Alarm / Trip Setpoint Eq. 5-9 T.S. 3.11.2.1 Wide Range Gas for Total Body Dose (Total Body)

Monitors Rate

~

Alarm / Trip Setpoint Eq. 5-10 T.S. 3.11.2.1 for Skin Dose Rate (Skin)

T w

(1) More accurate methods may be available (see subsequent chapters).

(2) Technical Specification 3.11.4.a requires this evaluation only if twice the limit of equations 3-1. 3-2, 3-12, 3-15 or 3-18 is reached. If this occurs a Method Il calculation. using actual release point parameters with annual average or concurrent meteorology and identified pathways for a real individual, shall be made.

8 9

n

{

TABLE B.1-2 Summary of Method i Ecuations to Calculate Unrestricted Area Liouid Concentrations Equation Number Category Equation 2-1 Total Fraction of MPC in C I F,ENG , y Liquids. Except Noble Gases 2-2 Total Activity of Dissolved NG and Entrained Noble Gases pg f pCi ' i from all Station Sources 1

' ml

's 2E-04 t

i i

i I

l

[

ODCM Rev. 8 R12\86 B.1-6

TABLE B.1-3 Sumary of Method i Ecuations to Calculate Off-bite Doses from Llould Releases

-Ecuation Number Catecory Ecuation 3-1 Total Body Dose D tb(mrem)=kfOgDFL itb 3-2 Maximum 4 Organ Dose D,o(mrem)=kfOgDFL imo i

l 1

l l

\

l l

l I

i ODCM Rev. 4 i

l R12\B6 B.1-7

, ) *; '

.) -)

/

~'?

s,mi .;C

, TABLE B.1-4 Summary of Method i Ecuations to' Calculate Oose Rates Equation Receptor Releasg Number location

Heicht_ Ecuation Category e 3-3a 05 E Otb(e) = 0.85

E (og

DFB )

R e Fro N '

Gases 3-3b 05 G i Otb(s) - 3.4

Et (0

DFBi )

I 3-3c EC E Othttet " 0.0015

E (og

DFBs) t G Ottt(s) = 0.0074

E (Os

DFBg) l 3-3d EC 1

Othtte) = 0.038

E (Og

OFBq) I 3-3e R E t

3-3f R G OtbR(g) - 0.2

E (0,

DFB ) l 1

f 8

05 - Off-Site. EC - Education Center. R - The " Rocks" l b

E - Elevated. G - Ground 1

6 t ,

l g TABLE B.1-4 h Summary of Method i Ecuations to Calculate Dose Rates es (Continued)

Equation Receptor Releasg Category Number location

Heiaht Ecuation i.

a 05 E Osting,3 - (4 DPue))

e es 3 4b 05 G 0 ting,3 - E (og . DF'ig,3) l

[

3-4c EC E Oskintres " 0.0014 . E (Og . DF' igg,3)

[ 8 i

k 3.4d EC G 0,tingg,3 - 0.0014 . E (Og . DF' igg,3) 4 !

3-4e R E Dskinate) - 0.0076 . E (Os

DF' tate >)

t 3-4f R G Oskinato) - 0.0076 . E (og . DF' gag,3) 1

]

E 9 '

k *05 - Off-Site. EC - Education Center, R - The " Rocks" D

E - Elevated. G - Ground L'

(E P

i

. : I t m TABLE B.1-4

Summary of Method i Ecuations to Calculate Dose Rates Equation Receptor Releasg .

Category Number location

Heloht i Ecuation Critical Organ Dose Rate From I-131. Oog.c - E (Os

DFG'icog.3) l I-133. H-3. and 3.Sa 05 E :

Particulate With Tu2 >8 Days i

3.5b 05 G Ocorgi - E (Os

DFG'tcots)) l 4

3.Sc EC E Oc otte1 -0.0014 . E (0, . OFG'icotte)) l i

i

?

3.5d EC G ocotte) -0.0014 . E (0, . DFG'icotts)) l

{

o ,

t 3.Se R E Oc onte) -0.0076 . E (0, . DFG*tconce)) !

8 l ._.. _

3.Sf R G bconggi -0.0076 . E (0, e DFG'icong,3) s 8

6 c i i

I *05 - Off-Site. EC - Education Center. R = The " Rocks" b

i E - Elevated. G - Ground 5 . . . _ _ . .

2 j ; .i 1 :

1 m TARLE B.1-5 I

Summary of Method I Ecuations to Calculate Doses to Air From Noble Gases Equation Receptor Releasg Category Number Location

Heloht Ecuation I

Gs 3.6a 05 E 'D trie) - 3.2E-07

t4.275 E (Os

DF[)

! N

' l

! 3.6b 05 G D[g,gg, - 1.6E-06

t-o.293 * [(Og

DF[) l

i k

~

3.6c EC E DJ,,gg,3 - 4.9E-10

t4.252 . E (0

DF[) l 1

3

ee 3.6d EC G D t rt(gi - 4.4E-09 . t-o.321. E (Og DF[] l L

3.6e R E D trate, - 5.1E-09 e t-o.155 E (Os

DF[)

l 3.6f R G DJ,,ng,3 - 4.1E-08 + t-o.ro4 E (Os DF[) l t

i E

L I

l To

'05 - Off-Site. EC - Education Center R = The " Rocks" b

E - Elevated. G - Ground

. . 1 k

TABt.E B.1-5 g

Summary of Method i Eaustions to Calculate Doses to Air From Noble Gases h

m (Continued) i untion Receptor Releasg Ecuation Category Ehumber I.oca t i on* Heloht t 3.7a 05 E l 0,8,g,3 - 4.1E-07

t-0 3

E (Di

DFf) 5 l

fygm fe a s t 3.7b 05 G l Dfirg,3 - 6.0E-06 t-0 33' . E (Os DFf) l l Of,,gg,3 - 1.8E-09 . t-0 35

E (0

DFf) l 3.7c EC E t

3.7d EC G Dfirtto) - 2.4E-08 . t-0 347 . E (Og . DFf) l b 3,7e R E Oft rate) - 3.9E-08

t-0.249 . E (0,

DFf)

D'tratg> - 4.6E-07 t-0 287 . E (Og

DFf) _

3.7f R G a i

8 i 9 i E 8 05 - Off-Site. EC - Education Center, R - The Rocks" l

? b E - Elevated. G - Ground

E.

t .

! t t

$ l

. . ) ' '

. / 1 TABLE B.1-6 g

~

Summary of Method i Ecuations to Calculate "h Dose to an Individual from Tritium. Iodine and Particulates Equation Receptor Release Number loca ti on' Height" Ecuation Citecory Dose to Critical De ,g,3 = 14.8 = t-o.297 . E (0i . OFGic,g,3) l Organ From lodines* 3.8a 05 E '

' I Tritium, and Particulates D cog,3 = 17.7 . t-8 338 . E (Og . DFGie g,3) l 3.8b 05 G t 3.8c EC E D cotte) - 3.3E-02 = t-0 3" Et (0, DFGt cottel) l

[

u

% m.

Ocotte) - 3.3E-2 . t-0 387

E (Og

DFGic gg,3) 3'.8d EC G i wwe O conte) - 7.3E-02 t-o.24s . E (Og

DFG cong,3) i 3.8e R E i D contgi - 8.6E-02 . t-o.267 E (0i.DFGicoatg))

3.8f R G t 3<

-s The " Rocks" 1 'CS - Off-Site EC = Education Center.

S E - Elevated. G = Ground

TABLE B.1-7 Summary of Methods for Setooint Determinations Equation Number Category I Ecuation 51 Licuid Effluents:

Liquid Waste Test 0F f

Tank Monitor setpoint ( ,) )- ,

1 0F min i "I (RM 6509) ;

. I 5 23 ggggggaliapf RCset(gph) - 1x100 SWF h

, Gaseous Effluents:

Plant Vent Wide Range Gas '

~

Monitors (RM-6528 1, 2. 3) 55 Total Body g 5,88 l

S6I~ Siii R 3000 skin (pC1/sec) l I

i i

l J

R12\B6 B 1 14. ODCM Rev. 14

._ ...h

I TABLE B.1 8 Summary of Variables variable Definition Units ma

- Concentration at point of discharge and pC1/ml C 11 entrained noble gas *1" in liquid pathways from all station sources na

- Total activity of all dissolved and pCi 1 entrained noble gases in liquid pathways ,j from all station sources C,, - Concentration of radionuclide 'i' at the pCi point of liquid discharge ml Cg Concentration of radionuclide "i" pCi/mi C,, - Concentration, exclusive of noble gases, of pCI radionuclide "i" from tank *p' at point of ml discharge C,, = Concentration of radionuclide 'i' in pCi/ml mixture at the monitor g- - -

D air

. --- Off site beta dose to air due to noble mrad

(*) gases in elevated release l' O*p ir(9)

- Off site beta dose to air due to noble gas in ground level release mrad l

D*p

- Beta dose to air at Education Center due to mrad ire (*) noble gases in elevated release l O p -

Beta dose to air at Education Center due to mrad l atrt(9) noble gases in ground level release l p D atrate)

Beta dose to air at " Rocks" due to noble mrad l gases in elevated release l O p = Beta dose to air at

Rocks" due to noble mrad I atra(9) gases in ground level release

- Off-site gamma dose to air due to noble mrad D*yir(')

l gases in elevated release l

- Off-site gamma dose to air due to noble mrad D*y l ir(9) gases in ground level release 1

Dy Gamma dose to air at Education Center due mrad I strEte) to noble gases in elevated release l

Gamma dose to air at Education Center due mrad D*yirE(9) to noble gases in ground level release l

l Gamma dose to air at

Rocks" due to noble mrad D*yi'R(*)

l gases in elevated release

" = --'-" "

R12\86 __ _ _ _ .

_ . , _ B h15 - .

~

TABLE B.1 8 (Continued)

Summary of Variables 3

Variable Definition Units Dy Gamma dose to air at " Rocks

due to noble mrac etrafel gases in ground level release l 0,,g,3 - Critical organ dose from an elevated mrem l release to an off site receptor 0,,g,3 - Critical organ dose from a ground level mrem release to an off site receptor l- D,,gg,3 - Critical organ dose from an elevated mrem l release to a receptor at the Education 7 Center 1 O cotto)

- Critical organ dose from a ground level mrem l release to a receptor at the Education

'l Center D,,gg,3 - Critical organ dose from an elevated mrem release to a receptor at the " Rocks"

.l ~ ' D,,a g gj ~

Critical organ dose from a ground level mrem release to a receptor at the " Rocks

Dd -

Direct dose mrem Dy Gamma dose to air. corrected for finite mrad

. finite Cloud D., -

Dose to the maximum organ irrem 5

0 - ' Dose to skin from beta and gamma mrem D

tb Dose to the total body mrem DF -

Dilution factor ratio D F,, , -

Minimum allowable dilution factor ratio

=

l DF'i Composite skin dose factor for off site mrem sec/pCl yr receptor l

DF 1E

- Composite skin dose factor for Education mrem sec/ptt-yr Center l DF ia

- Composite skin dose factor for the " Rocks

mrem sec/pCi-yr DFB, - Total body gamma dose factor for nuclide mrem 3

1* (Table 6.1-10) pC1 -y r DFB, -

Composite total body dose factor mrem 3 pC i -y r l

TABLE 8.1 8 (Continued)

Summary of variables Variable Definition Units DFL ith - Site-specific, total body dose factor for a mrem I liquid release of nuclide *i* (Table B.1- pct 1

11) i DFLj, -

Site specific, maximum organ dose factor mrem 1 for a liquid release of nuclide "i" (Table pct i

B.1-11) i

) l DFB igog,3 -

Site specific, critical organ dose factor mrem /pCi -

l for an elevated gaseous release of nuclide

i' (Table B.1 12)

[ DFG,,,g,3 -

Site-specific critical organ dose factor mrem /pCi l for a ground level release of nuclide "i"

'l (Table B.1-12)

DFG icoE(e)

Education Center-specific critical organ mrem /pCi dose factor for an elevated release of nuclide "i" (Tabic B.1-14) l DFG icot(s)

Education Center-specific critical organ mrem /pCi

-l dose factor for a ground level release of l nuclide "i" (Table B.1-14) l D F G,,,, g ,3 -

The " Rocks" specific critical organ dose mrem /pCi

'[ factor for an elevated release of nuclide l *i' (Table B.1-15)

DFGje,ggg3 -

The " Rocks"-specific critical dose factor mrem /pCi for a ground level release of nuclide "i" l (Table B.1-15) y DFG ico(*)

Site specific critical organ dose rate mrem-sec factor for an elevated gaseous release of pCi-yr nuclide "i" (Table B.1-12)

DFG Site-specific critical organ dose rate mrem-s ec ico(9) factor for a ground level release of C i-y r nuclide "i" (Table B.1 12)

DFG Education Center specific critical organ mrem-sec icottel dose rate factor for an elevated release of pCi -y r I,

nuclide "i" (Table 3.1 14)

DFG teoE(g) ucadon Cenespecide cMcal organ mrem-sec dose rate factor for a ground level release pC i-y r l of nuclide "i" (Table B.1-14)

DFG The " Rocks" specific critical organ dose mrem-sec icoRie) rate factor for an elevated release of pci-y r

} nuclide *1" (Table B.1 15)

,1 .l L . . a . . .. . _ .. . . . . .. . . . . . .. 0@lfh, A . . __

TABLE B.1 8 k (Continued) j Summary of Variables Variable Definition '

Units OFG icoR(g)

The " Rocks" specific critical organ dose mrem-sec rate factor for a ground level release of pc t .y p nurlide *1" (Table B.1 15)

DFS, -

Beta skin dose factor for neclide "i" mrem-m 3 (Table B.1 10) pC1 -yr i

D F', -

Combined skin dose factor for nt.clidt' *i" mrem-m 3 (Table B.1-10) pCi-y r 7 0Fy Gamma air dose factor for nuclide "i" mrad-m3 8

(Table B.1-10) pC i-y r Beta air dose factor for nuclide "i" D

0F i mrad-m3 (Table 8.1-10) pCi -y r 6('I Critical organ dose rate to an off-site mrem receptor due to elevated release of yr iodines, tritium, and particulates

] gcots)

Critical organ dose rate to an off-site mrem

j. . receptor due to ground level release of yr

] todines, tritium, and particulates l

0*

U 'I Critical organ dose rate to a receptor at mrem the Education Center due to an elevated yr release of iodines, tritium, and j particulates j c**"'I Critical organ dose rate to a receptor at mrem the Education Center due to a ground level yr release of iodines, tritium, and i

[ particulates 4 g**"I'3 Critical organ dose rate to a receptor at mrem the " Rocks" due to an elevated release of yr Q iodines, tritium, and particulates c**"I9)

Critical organ dose rate to a receptor at mrem the" Rocks"duetoagroundleveljrelease yr of iodines, tritium, and particulates

. 4 l 0 # "I'I Skin dose rate to an off site receptor due mrem l to noble gases in an elevated release yr

}

R12\86 9

TABLE B.1-8 (Continued)

Summary of Variables Variable Definition Units l g"i"(8I 5

Skin dose rate to an off site receptor due mrem l to noble gases in a ground level release yr gkint(e) s Skin dose rate to a receptor at the mrem Education Center due to noble gases in an yr elevated release gkinna) s Skin dose rate to a receptor at the mrem Education Center due to noble gases in a yr ground level release

~ gk'"I S

Skin dose rate to a receptor at the " Rocks" mrem due to noble gases in an elevated release yr g"i"'(83 5

Skin dose rate to a receptor at the " Rocks" mrem due to noble gases in a ground level yr release l gtb(e) Total body dose rate to an off-site mrem l receptor due to noble gases in an elevated yr

-.{ release

- Total body dose rate to an off site g**(83 mrem receptor due to noble gases in a ground yr

( level release l g* * "' I Total body dose rate to a receptor at the mrem l Education Center due to noble gases in an yr l elevated release l g" ' I Total body dose rate to a receptor at the mrem l Education Center due to noble gases in a yr j ground level release l gtbR(e)

Total body dose rate to a receptor at the mrem l . Rocks" due to noble gases in an elevated yr l release g"(8I Total body dose rate to a receptor at the mrem

" Rocks" due to noble gases in a ground yr

.. level release 0/0 -

Deposition factor for dry deposition of 1 elemental radiolodines and other p particulates F

d Flow rate out of discharge tunnel gpm or ft 3 /sec F. -

Flow rate past liquid waste test tank gpm monitor

.R12\86 _ _ _ ...... . ... _ a n_1 1n .

TABLE B.1 8 (Continued)

Summare of Variobles fariable Definition Units F - Flow rate past plant vent monitor cc set f: 3 f: 2 f:

3 Fraction of total MPC associated with Paths Dimensionless f4 1, 2, 3. and 4 F1 tna - Total fraction of MPC in liquid pathways Dimensionless (excluding noble gases)

HPC, - Maximum permissible concentration for pCi s radionuclide *1" (10CFR20, Appendix B, cc Table 2, Column 2)

~

Og =

Release to the environment for radionuclide curies, or

i" pcuries 0,

Release rate to the environment for pCi/sec

. radionuclide "1" R ,tp gng = Liquid monitor response for the limiting pCl/mi concentration at the point of discharge R sun -

Response of the noble gas monitor to cpm, or pCl/sec

. limiting total body dose rate

. R tb

- Response of the noble gas monitor to cpm. or pCi/sec limiting total body dose rate'

- Shielding factor Sr Dimensionless 5, -

Detector counting efficiency from the gas monitor calibration com or mR/hr Ci-cc pCi/cc S,, -

Detector counting efficiency for noble gas cpm 1- or mR/hr pCi-cc pCi/cc Si -

Detector counting efficiency from the eps liquid monitor calibration pci/ml SH -

Detector counting efficiency for cps j

radionuclide "t* pCi/ml l X/0 -

Average long term undepleted atmospheric sec l dispersion factor (Tables B.7 4, B.7 5, and ,3 l B.7 6) l (X/0]y -

Effective long term average gamma sec atmospheric dispersion factor ,3 l (Tables B.7-4 B.7-5, and B.7 6)

_ .a M as

.~ _. - . _ ___ - - _ _ _ _ __

i TABLE B.1 8 (Continued)

Summary of Variables Variable Definition 3hii

tt SWF = Service Water System flow rate gph PCC - Primary component cooling water measured pCi/ml (decay corrected) gross radioactivity concentration .

t = Unitiess factor which adjusts the value of Dimensionless atmospheric dispersion factors for elevated or ground-level releases with a total release duration of t hours l

l R12\86 B.1-21 ODCM Rev. 14

TABLE B.1-9 Definition of Terms, Critical Receptor - A hypothetical or real individual whose location and behavior cause him or her to receive a dose greater than any other possible real individual.

E211 - As used in Regulatory Guide 1.109, the term " dose," when applied to individuals, is used instead of the more precise term " dose, equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition or radioactivity, the term " dose." as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. The dose is measured in mrem to tissue or mrad to air.

Dose Rate - The rate for a specific averaging time (i.e., exposure period) of dose accumulation, licuid Radweste Treatment System - The components or subsystems which comprise i the available treatment system as shown in Figure B.6-1.

j 1

i R12\86 B.1-22 ODCM Rev.14

{

l l

\

} *

'o l

i y TABLE B.1-10 l

~ :

6 Dose Factors SDecific for Seabrook Statf ori for Noble Gas Releases l

Combined Skin Combined Skin Dose Factor for ! Dose Factor for Gamma Total Body --Beta Skin Dose Elevated Release Ground Level Beta Air Dose Gamma Air Dose Dose Factor Factor Points l Release Points Factor! Factor Radio- "~"' "~"' '

~'** ~'*C ~"'

nuclide Dra8 ( "'*i-yr pc ) Drs8 ( "'c*i-yr p ) DFg (a) ("'e'"i p yr ) .lDF ( "'*"i-yr pc ) DFf ("p#*ci-yr] DF{ ( mrad-s*

pci-yr g

Ar-41 8.84 E-03 2.69E 03 1.09E-02 6.22E 02 3.28E-03 9.30E-03 Kr-83m 7.56E-08 -----

1.81E-05 7.33E-05 2.88E-04 1.93E-05 Kr-85m 1.17E-03 1.46E-03 2.35E 03 1.93E 02 1.97E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.IIE-03 1.35E-02 1.95E-03 1.72E-05 Kr 87 5.92E-03 9.73E-03 1.38E-02 1.21E-01 1.03E-02 6.17E-03 Kr 88 1.47E 02 2.37E-03 1.62E 02 8.15E 02 2.93E-03 1.52E-02 Kr-89 1.66E-02 1.01E-02 2.45E-02 1.67E-01 1.06E-02 1.73E-02 Kr-90 1.56E-02 7.29E 03 2.13E 02 1.35E-01 7.83E-03 1.63E-02 Xe-131m 9.15E 05 4.76E 04 5.37E 04 5.35E-03 1.IIE-03 1.56E-04 Xe-133m 2.51E-04 9.94 E- 04 1.12E-03 1.12E 02 1.48E-03 3.27E-04 Xe 133 2.94E-04 3.06E-04 5.83E 04 i 4.40E-03 1.05E-03 3.53E-04 U Xe 135m 3.12E-03 7.llE-04 3.74E-03 1.99E-02 7.39E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 3.33E-03 2.59E 02 2.46E-03 1.92E 03 Xe-137 1.42E-03 1.22E-02 1.14E-02 i 1.28E 01 1.27E-02 1.51E-03 Xe-138 8.83E 03 4.13E 03 1.20E-02 ; 7.63E-02 4.75E-03 9.21E-03 i

i l

8.84E 8.84 x 10'3 ;

I h

9 2

, . . . _ . - . . . . - . - ~ - - - . .

. ...wr-------------~~

i VABLE B.1 11 Dose Factors Specific for Seabrook Station for Liould Releases l Total Body Maximum Organ Oose Factor Dose Factor mrem Radionuclide OFLitb Iuci ) DFL4 ,o (, mrem) g, H3 3.02E-13 3.0ZE 13 Na-24 1.38E 10 1.42E 10 Cr 51 1.83E-11 1.48E 09 Mn-54 5.15E 09 2.68E-08 Fe 55 1.26E 08 7.67E-08 Fe 59 8.74E 08 6.66E 07 Co 58 2.46E-09 1.40E 08 Co 60 6.15E 08 9.22E-08 2n 65 2.73E-07 5.49E 07 Br-83 1.30E 14 1.89E-14 Rb 86 4.1GE-10 -6.96E-10 Sr 89 2.17E-10 7.59E 09 Sr 90 3.22E 08 1.31E-07 Nb-95 5.25E-10 1.58E-06 Mo 99 3.72E 11 2.67E 10 Tc-99m 5.22E-13

.__Ag 110m _ ___.

1.95E-12

-1.01E - - - - - -- -6;40E 07 ~ ~ --

Sb-124 1.71E 09 9.89E-09 Sb 125 6.28E 09 8.31E 09 Te-127m 7.07E-08

- 1.81E-06 Te 127 3.53E-10 9.54E 08 Te 129m 1.54E 07

~

3.46E-06 Te 129 7.02E-14 1.05E-13 Te 131m 3.16E 08 2.94E-06 Te 132 9.06E 08 3.80E-06 1-130 2.75E-11 I 131 3.17E-09 2.30E 10 1.00E-07 1-132 6.28E 11 6.36E-11 1 133 3.85E 11 1 134 1.15E-08 1.19E 12 1.41E 12 1-135 5.33E-11 Cs-134 4.69E 10 3.24E 08 3.56E 08 Cs-136 2.47E 09 3.27E-09 Cs-137 3.58E-08 4.03E 08 Ba 140 1.70E-10 La-140 3.49E 09 1.07E 10 4.14E-0B Ce-141 3.85E 11 Ce 144 9.31E 09 1.96E 10 6.46E 08 Other* 3.12E 08 1.58E 06*

Dose factors to be used in Method I calculatien for any "other* detected gamma emitting radionuclide which is not included in the above list.

R12\86 ,

8.1-24.

ODCM Rev. 14 ,

i s

TABLE 8.1 12 Dose and Dose Rate Factors Specific for Seabrook Station for Iodines. Tritium and Particulate Releases Critical Organ Critical Organ Critical Organ Critical Organ Dose Factor Dose Factor for Dose Rate Factor Dose Rate Factor for Elevated Ground Level fc" Elevated for Ground Level Release Point Release Point Release Point Release Point Radionuclide Dro w., ( "pci ) Dro w, ( "pei ) Dro c.,

'*"~' *

( "yr-pc*1 ) Dec' t,, ("'*"

yr-> c**1 )

H3 3.08E 10 3.76E 09 9.71E 03 1.19E 01 Cr 51 8.28E 09 2.89E 08 2.91E 01 1.01E+00 Mn 54 1.11E 06 3.79E 06 4.38E+01 1.50E+02

~

Fe 59 1.06E 06 3.65E 06 3.53E+01 1.21E+02 Co-58 5.56E 07 1.91E 06 2.00E+01 6.8SE+01

~'

Co 60 1.21E 05 4.12E 05 5.42E+02 1.85E+03 Zn 65 2.33E 06 7.93E-06 7.82E+01 2.66E+02 Sr-89 1.98E 05 6.73E 05 6.24E+02 2.12E+03 Sr-90 7.21E-04 2.47E 03 2.27E+04 7.79E+04

. . _ . - Zr>95- 1.10E 06 - - - 3.77E 3.63E+01 -

Id 4 E+02------

Nb 95 2.01E-06 6.86E-06 6.40E+01 2.20E+02 Mo 99 1.63E-08 1.10E 07 5.39E 01 3.56E+00 Ru 103 3.03E 06 1.04E-05 9.62E+01 3.31E+02 Ag 110m 5.02E 06 1.72E 05 1.80E+02 6.15E+02 Sb 124 1.83E-06 6.28E 06 6.15E+01 2.11E+02 1-131 1.47E 04 5.04E 04 4.64E+03 1.59E+04 1 133 1.45E 06 5.72E 06 4.57E+01 1.80E+02 Cs 134 5.62E 05 1.91E 04 1.81E+03 6.18E+03 Cs-137 5.47E-05 1.86E-04 1.79E+03 6.09E+09 Ba 140 1.55E 07 6.39E 07 5.01E+00 2.06E+01 Ce-141 2.65E-07 9.28E-07 8.45E+00 2.96E+01 Ce 144 6.09E 06 2.09E 05 1.93E+02 6.62E+02 Other* 4.09E 06 1.39E-05 1.29E+02 4.38E+02

'00se factors to be used in Method I calculations for any 'other" detected gamma emitting radionuclide which is not included in the above list.

1 R12\B6 B.1 25 ODCM Rev. 14

1 l

l l

TABLE 8.1-13 Combined Skin Oose Factors Specific for Seabrook Station Soecial Receptors"8 for Noble Gas Release Education Center Education Center The ' Rocks

The " Rocks

Combined Skin Combined Skin Combined Skin Combined Skin Oose Factor for Dose Factor for Oose Factor for Dose Factor for Elevated Release Ground Level Elevated Release Ground Level Point Release Point Point Release Point or , , (mrem-see: op"* g arem-see) DP'*'*8 ( seem-see myu w garem-seeI Radionuclide PC1-YK pei-yr pci-yr pci yr Ar 41 1.57E 02 1.17E 01 9.73E 02 6.99E 01 Kr 83m 2.35E 05 1.13E-04 1.07E 04 5.58E 04

. Kr 83m 3.84E 03 4.08E 02 3.16E 02 2.69E 01

, Kr 85 2.16E 03 3.09E 02 2.29E 02 2.15E 01 Kr 87 2.31E 02 2.60E 01 2.00E 01 1.74E+00 m

Kr 88 2.23E 02 1.44E 01 1.25E 01 8.18E 01

~

Kr 89 3.73E 02 3.34E 01 2.68E 01 2.12E+00 Kr 90 3.15E 02 2.64E 01 2.14E 01 1.64E+00

~ ~ ~~

Xe 131m ~~ ~9.52E 04 l'.19 E-02 ~'~ ~ 1 90E 03 ~ ~~ 8~ 47E'05 ~ ~ ~

Xe 133m 1.99E-03 2.48E 02 1.87E 02 1.68E 01

% s Xe-133 9.20E 04 9.11E-03 7.16E 03 5.92E 02

, Xe 135m 5.24E 03 3.61E 02 3.07E 02 2.11E 01

, Xe 135 5.32E 03 5.41E 02 4.23E 02 3.53E 01 Xe 137 2.14E 02 2.89E 01 2.16E 01 2.00E+00 Xe 138 1.78E-02 1.49E 01 1.21E 01 9.27E 01 m See Seabrook Station Technical Specification Figure 5.1 1.

R12\B6

. B.

_ _ . _ _ _ _ _ _ - - -- - - - - - - - - - - _; a foBLE 8.1 14 I

Cose and Dose Rate Factors $pectite for the Education Center for lodine. Tritium, and Pertteulate Peleases Critical Organ Oose Critical Organ Oose Critical Organ Dose Critical Organ Oose Factor for Elevated Factor for Ground Rate Factor for Rate Factor for Ground Release level Release Elevated Release Level Release Point Point P oi n'. Point

" C ** PC Radtonuclide H3 6.45E 11 9.27E 10 2.03E 03 2.92E 02 Cr 51 4.98E 09 2.88E 08 2.12E 01 1.11E+00 Mn 54 1.39L-06 5.71E 06 6.24E+01 2.39E+02 Fe 59 3.09E 07 1.89E 06 1.2)E+01 7.16E+01 Co 58 3.89E 07 2.10E 06 1.72E+01 8.26E+01

- Co 60 2.17E 05 8.03E 05 9.87E+02 3.63E+03 2n 65 7.34E 07 3.19E 06 3.31E+01 1.33E+02 Sr 89 1.15E 07 1.61E 06 3'.63E+00 5.08t+01

-~

Sr 90 5.14E 06 7.19E 05 1.62E+02 2.27E+03 Zr-95 3.38E 07 2.57E 06 1.35E+01 9.15E+01 Mb 95 1.53E 07 9.35E 07 6.43E+00 3.53E+01 Mo 99 ~' 1.62E 08 1.92E 07 5.58E 01 6.21E+00 Ru 103 1.30E 07 8.64E*07 5.33E+00 3.19E+01 Ag 110m 3.43E 06 1.54E 05 1.55E+02 6.34E+02 Sb 124 6.96E 07 4.46E 06 2.89E+01 1.67E+02 I 131 7.79E 07 1.08E 05 2.4fE+01 3.41E+02

. 1 133 1.84E-07 2.56E 06 5.e3E+00 8.11E+01 Cs 134 6.83E 06 2.53E 05 3.08E+02 1.14E+03 Cs 137 1.03E 05 3.81E 05 4.64E+02 1.72E*03 Ba 140 1.14E 07 1.42E 06 3.85E+00 4.54E+01 Ce 141 4.09E-08 4.51E 07 1.45E+00 1.48E+01 Ce 144 6.95E 07 9.11E 06 2.27E+01 2.90E+02 Other* 2.26E 06 9.24[ 06 1.02E+02 3.91E+02 R12\86 B.1 27 ODCM Rev.14 l

~

l

Tost ( 8.1 15 Dose and Cose Rate Factors $0*cific for the ' Rocks' for lodine. Trition, and Particulate Releases Critical Organ Critical organ Dose Critical Organ Critical Organ Oose Oose Factor Factor for Oose Rate Fsetor Rate Factor for for Elevated Ground Level for Elevated Ground Level Release Point Release Point Release Point Release Point

" *

P Radionutilde P H3 6.85E 10 6.45E 09 2.16E 02 2.03E 01 Cr 51 2.68E 08 1.75E 07 1.07E+00 6.53E+00 Mn 54 5.84E 05 3.18E 05 2.55E+02 1.31E+03 Fe 59 1.74E 06 1.17E 05 6.78E+01 4.29E+02 Co 58 2.01E 06 1.25E 05 8.11E+01 4.79E+02 Co 60 8.83E 05 4.09E 04 3.97E+03 1.85E+04

- In 65 3.23E 06 1.80E 05 1.37E+02 7.29E+02

., sr 89 1.23E 06 1.15E 05 3.88E+01 3.63E+02 Sr 90 5.48E 05 5.14E 04 1.73E+03 1.62E+04 Zr 95 2.22E-06 1.68E 05 8.14E+01 5.83E+02 Nb 95 8.59E 07 5.79E 06 3.37E+01 2.13E+02 Mo.99 1.50E 07- 1.34L 06 - 4.92E+00 . 4.32E+01 _.. .

- Ru 103 7.74E 07 5.47E-06 2.95E+01 1.96E+02 Ag 110s 1.54E 05 8.77E-05 6.47E+02 3.53E+03 Sb 124 4.04E 06 2.80E 05 1.56E+02 1.01E+03 I 131 8.27E 06 7.73E-05 2.61E+02 2.44E+03 1 133 1.95E 06 1.83E 05 6.18E+01 5.77t+02 Cs 134 2.78E 05 1.29E 04 1.25E+03 5.80E+03 Cs 137 4.19E 05 1.94E 04 1.89E+03 8.77E+03 Ba 140 1.10E 06 9.99E 06 3.56E+01 3.19E+02 Ce 141 3.59E 07 3.14E 06 1.20E+01 1.02E+02 Co 144 7.02E-06 6.46E 05 2.25E+02 2.05E+03 Other* 9.56E 06 5.09E 05 4.16t+02 2.12E+03 R12\86 B.1 28 ODCM Rev. 1

l 1 i

I 2.0 METHOD TO CALCULATE OFF-SITE LIOUID CONCENTRATIONS Chapter 2 contains the basis for station procedures used to demonstrate I compliance with Technical Specification 3.11.1.1, which limits the total fraction of MPC in liquid pathways, other than noble gases (denoted here as F3 E"G) at the point of discharge from the station to the environment (see ENG Figure B.6-1). F i is limited to less than or equal to one, i.e.,

FENG < g, 1

j The total concentration of all dissolved and entrained noble gases at I

the point of discharge from the multiport diffuser from all station sources combined, denotedi C "', is limited to 2E-04 pCi/ml, i.e.,

C "' 12E-04 Ci/ml.

i 2.1 Method to Determine F ENG andC!G First, determine the total fraction of MPC (excluding noble gases), at I the point of discharge from the station from all significant liquid sources denoted F3 ENG: and then separately determine the total concentration at the l point of discharge of all dissolved and entrained noble gases from all station sources, denoted C i "', as follows:

U ENG Di Fj - 1I i MPC i i 1. (2-1) p guCi/ml) pu /mi andt C - I h 1 2E-04 (2-2)

(pCi/ml) (pCi/ml ) ( Ci/ml) where:

F ENG - Total fraction of MPC in liquids, excluding noble gases, at the point of discharge from the multiport diffuser.

l l

R12/86 B.2-1 ODCM Rev. 12 l

1

I C,, -

Concentration at point of discharge from the multiport diffuser of radionuclide "i", except for dissolved and entrained noble gases from all tanks and other significant sources, p, from which a discharge may be made (including the waste test tanks and any other significant source from which a l discharge can be made). C is determined by dividing the product of the measured ra,,ionuclide d concentration in liquid waste test tanks, PCCW, steam generator blowdown or other effluent streams times their discharge flow rate by the total available dilution water flow rate of circulating and service water at the time of release (pCi/ml).

MPC, - Maximum permissible concentration of radionuclide "i" except for dissolved and entrained noble gases from 10CFR20, Appendix B, Table II, Column 2 (pCi/ml).

CgG - Total concentration at point of discharge of all dissolved and entrained noble gases in liquids from all station sources (pCf/ml)

Cyf - Concentration at point of discharge of dissolved and entrained noble gas "1" in liquids from all station sources (pCi /ml )

2.2 Method to Determine Radionuclide Concentration for Each Liouid Effluent Source 2.2.1 Waste Test Tanks i

C,i is determined for each radionuclide detected from the activity in a j representative grab sample of any of the waste test tanks and the predicted flow at the point of discharge.

~

The batch releases are normally made from two 25,000 gallon capacity ,

waste test tanks. These tanks normally hold liquid waste evaporator distillate. The waste test tanks can also contain other waste such as liquid taken directly from the floor drain tanks when that liquid does not require processing in the evaporator, distillate from the boron recovery evaporator when the BRS evaporator is substituting for the waste evaporator, and distillate from the Steam Gs carater Clowdown System evaporators and flash steam condensers when that system must discharge liquid off-site.

If testing indicates that purification of the waste test tank contents is required prior to release. the liquid can be circulated through the waste demineralizer and filter.

R12/86 B.2-2 ODCM Rev. 12 l

l l

The contents of the waste test tank may be reused in the Nuclear System if the sample test meets the purity requirements.

Prior to discharge, each waste test tank is analyzed for principal gamma emitters in accordance with the liquid sample and analysis program outlined in Part A to the ODCH.

l l

2.2.2 Turbine Buildino Sumo The Turbine Building sump collects leakage from the Turbine Building floor drains and discharges the liquid unprocessed to the circulating water system.

Sampling of this potential source is normally done once per week for l determining the radioactivity released to the environment (see Table A.3-1).

l 2.2.3 Steam Generator Blowdown Flash Tank l

The steam generator blowddwn evaporators normally proc'ess the liquid

~

from the steam generator blowdown flash tank when there is primary to secondary leakage. Distillate from the evaporators can be sent to the waste test tanks or recycled to the condensate system. When there is no primary to secondary leakage, flash tank liquid is processed through the steam generator blowdown demineralizers and returned to the secondary side. j Steam generator blowdown is only subject to sampling and analysis when all or part of the blowdown liquid is being discharged to the environment instead of the normal recycling process (see Table A.3-1).

2.2.4 Primary Component Coolina Water (PCCW) System The PCCW System is used to cool selected primary components.

The system is normally sampled weekly to determine if there is any radwaste in-leakage. If leakage has been determined, the Service Water System is sampled to determine if any release to the environment has occurred.

R12/86 B.2-3 ODCH Rev. 12 l

l l

l

3.0 0FF SITE DOSE CALCULATION METH005 Chapter 3 provides the basis for station procedures required to meet the Radiological Effluent Technical Specifications (RETS) dose and dose rate requirements contained in Section 3/4.11 of the station operating Technical Specifications. A simple, conservative method (called Method I) is listed in Tables B.1-2 to B.1-7 for each of the requirements of the RETS. Each of the Method I equations is presented in Sections 3.2 through 3.9. In addition, those sections include more sophisticated methods (called Method !!) for use when more refined results are needed. This chapter provides the methods, data, and reference material with which the operator can calculate the needed doses, dose rates and setpoints. For the requirements to demonstrate compilance with Technical Specification off-site dose limits, the contribution from all measured ground level releases must be added to the calculated contribution from the vent stack to determine the Station's total radiological

~

impact. The bases for the dose and dose rate equations are given in

. Chapter 7.0.

The Semiannual Radioactive Effluent Release Report to be filed after January-1-each year. per- Technical Specification.611.0_r.equires_that meteorological conditions concurrent with the time of release of radioactive l materials in gaseous effluents, as determined by sampling frequency and

' measurement, be used for determining the gaseous pathway doses. For continuous release sources (i.e., plant vent, condenser air removal exhaust. I and gland steam packing exhauster), concurrent quarterly average meteorology will be used in the dose calcul3tions along with the quarterly total radioactivity released. For batch releases or identifiable operational activities (i.e., containment purge or venting to atmosphere of the Waste Gas System), concurrent meteorology during the period of release will be used to determine dose if the total noble gas or iodine and particulates released in the batch exceeds five percent of the total quarterly radioactivity released from the unit: otherwise quarterly average meteorology will be applied.

Quarterly average meteorology will also be applied to batch releases if the hourly met data for the period of batch release is unavailable.

Dose assessment reports prepared in accordance with the requirements of the ODCM will include a statement indicating that the appropriate portions of Regulatory Guide 1.109 (as identified in the individual subsections of the ODCM for each class of effluent exposure) have been used to determine dose impact from station releases. Any deviation from the methodology, amu B.3 1 ODCM Rev. 12 . 4 r

..e.

1

! assumptions, or parameters given in Regulatory Guide 1.109 and not already identified in the bases of the ODCH will be explicitly described in the effluent report, along with the bases for the deviation.

l l

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t, i ..

4

s .

=

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1

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E

.l t

I amu B.3-2 . .

O ' .. ,

.i .

o e

J 9

.a F

^ '^ ^ ~ " ' ~ ~ ' " " ~ '

___._.._lZE__ ~'~[

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

3.1 Introductory Concents In part.-the Radiological Effluent Technical Specifications (RETS) limit dose or dose rate. The term " dose" for ingested or inhaled radioactivity means the dose commitment, measured in mres, which results from the exposure to radioactive materials that, because of uptake and deposition in the body, will continue to expose the body to radiation for some period of time after the source of radioactivity is stopped. The time frame over which the dose commitment is evaluated is 50 years. The phrases " annual dose" or dose in one year" then refers to the 50-year dose commitment resulting from exposure to one year's worth of releases. " Dose in a quarter" similarly means the 50-year dose commitment resulting from exposure to one quarter's releases. The term

" dose," with respect to external exposures, such as to noble gas clouds, l refers only to the doses received during the actual time period of exposure to l

the radioactivity released from the plant. Once the source of the

( radioactivity is removed, there is no longer any additional accumulation to the dose commitment.

" Dose rate" is the total dose or dose commitment divided by exposure period. For example, an individual who is exposed via the ingestion of milk for one year to radioactivity from plant gaseous effluents and receives a 50-year dose commitment of 10 mrem is said to have been exposed to a dose rate of 10 mres/ year, even though the actual dose received in the year of exposure j may be less than 10 mrem.

I In addition to limits on dose commitment, gaseous effluents from the station are also controlled so that the maximum or peak dose rates at the site boundary a't any time are limited to the equivalent annual dose limits of 10CFR, Part 20 to unrestricted areas (if it were assumed that the peak dose !

rates continued for one year). These dose rate limits provide reasonable j assurance that members of the public, either inside or outside the site .

boundary, will not be exposed to annual averaged concentrations exceeding the !

limits specified in Appendix B. Table II of 10CFR. Part 20 (10CFR20.106(a)). ;

The quantities AD and 0 are introduced to provide calculable I quantities, related to off-site doses or dose rates that demonstrate compliance with the RETS. l 1

Delta 0, denoted AD, is the quantity calculated by the Chapter 3.

Method I dose equations. It represents the conservative increment in dose.

The 40 calculated by Method I equations is not necessarily the actual dose amu B.3-3 ODCM Rev. 12

- . .- - . - - - ....- --- ---- -. . - - ~ . - . - - . . -- . . . -

l received by a real individual, but usually provides an upper bound for a given l release because of the conservative margin built into the dose factors and the l selection and definition of critical receptors. The radionuclide specific ;

dose factors in each Method I dose quation represent the greatest dose to any '

organ of any age group. (Organ dose is a function of age because organ mass '

and intake are functions of age.) The critical receptor assumed by " Method I" :

equations is then generally a hypothetical individual whose behavior - in terms of location and intake - results in a dose which is higher than any real individual is likely to receive. Method II allows for a more exact dose l

calculation for each individual if necessary. 1 D dot, denoted 0, is the quantity calculated in the Chapter 3 dose rg,t,3, i l equations. It is calculated using the station's effluent monitoring system reading and an annual or long-term average atmospheric dispersion factor. 0 l predicts the maximem off-site annual dose if the peak observed radioactivity l release rate from the plant stack continued for one entire year. Since peak release rates, or resulting dose rates, are usually of short time duration on i the order of an hour or less, this approach then provides assurance that :

10CFR20.106 limits will ba met. l l

Each of the methods to calculate dose or dose rate are presented in the I following subsections and are summarized in Chapter 1. Each dose type has two levels of complexity. Method I is the simplest and ccntains many conservative factors. Method II is a more realistic analysis which makes use of the models ;

in Regulatory Guide 1.109 (Revision 1), as noted in each subsection of j Chapter 3 for the various exposure types. A detailed description of the j methodology, assumptions, and input parameters to the doh models that are ;

applied in each Method Il calculation if not already explicitly described in !

the ODCM. shall be documented and provided when this option is used for NRC :

reporting and Technical Specification dose compliance. ,

l l

1 L

l 4

unu B.3-4 ODCM Rev. 12 !

i i

3.2 Method to Calculate the Total' Body Dose from Lieu 1d Releases Technical Specification 3.11.1.2 limits the total body dose commitment to a member of the public from radioactive material in liquid effluents to 1.5 mrem per quarter and 3 arem per year per unit. Technical Specification 3.11.1.3 requires liquid radweste treatment when the total body dose estimate exceeds 0.06 mrem in any 31-day period. Technical Specification 3.11.4 limits the total body dose commitment to any real member of the public from all station sources (including liquids) to 25 mrem in a year.

Use Method I first to calculate the maximum total body dose from a l

liquid release from the station as it is simpler to execute and more l conservative than Method II.

Use Method II if a more refined calculation of total body dose is needed, i.e.. Method I indicates the dose might be greater than the Technical Specification limits. , ,

To evaluate the total body dose, use Equation 3.1 to estimate the dose from the planned release and add this to the total body dose accumulated from prior releases during the month. See Section 7.1.1 for basis.

3.2.1 Method I The increment in total body dose from a liquid release is:

Otb = k E Og DFLith 1

(mrem) = ( ) (pCi) where DFl itb = Site-specific total body dose factor (mrem /pC1) for a liquid release. It is the highest of the four age groups. See Table B.1-11.

unu B.3-5 ODCM Rev. 14

O, - Total activity (pCi) released for radionuclide "i". (For strontiums, use the most recent measurement available.)

K = 918/Fd ; where Fd is the average (typically monthly average) dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft3 /sec). For normal operations with a cooling water flow of 918 ft 3/sec, K is equal to 1.

Equation 3-1 can be applied under the following conditions (otherwise, justify Method I or consider Method II):

1. Liquid releases via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone that corresponds to a factor of 10 dilution), and

2. Any continuous or ba,tch release over any time period.

3.2.2 Method II Me: hod II consists of the models, input data and assumptions (bioaccumulation factors, shore-width factor, dose conversion factors, and transport and buildup times) in Regulatory Guide 1.109. Rev.1 (Reference A),

except where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used ,in the derivation of the simplified Method I approach as described.in the Bases section, are also applied to Method II assessments, except that doses calculated to the whole body from radioactive effluents are evaluated for each of the four age groups to determine the maximum whole body dose of an age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors of Method II calculations. As noted in Section B.7.1.

the mixing ratio associated with the edge of the l'F surfact isotherm above the multiport diffuser may be used in Method II calculations for the shoreline exposure pathway. Aquatic food ingestion pathways shall limit credit taken for mixing zone dilution to the same value assumed in Method I (M, = 0.10).

unu B.3-6 00CM Rev. 14

3.3 Methodle Calculate Maximum Organ Oose from Licuid Releases Tech.iic31 Specification 3.11.1.2 limits the maximum organ dose commitment to a Member of the Public from radioactive material in liquid l effluents to 5 mrem per quarter and 10 mrem per year per unit. Technical l Specification 3.11.1.3 requires liquid radwaste treatment when the maximum organ dose projected exceeds 0.2 mrem in any 31 days (see Subsection 3.11 for dose projections). Technical Specification 3.11.4 limits the maximum organ da:e commitment to any real member of the public from all station sources (including liquids) to 25 mrem in a year except for the thyroid. which is licited to 75 mrem in a year.

Use Method I first to calculate the maximum organ dose from a liquid release to unrestricted areas (see Figure B.6-1) as it is simpler to execute and more conservative than Method II.

Use Method II if a more refined calculation of organ dose is needed.

i.e.. Method I indicates the dos,e may be greater than the limit.

Use Equation 3-2 to estimate the maximum organ dose from individual or combined liquid releases. See Section 7.1.2 for basis.

3.3.1 Method I The increment in maximum organ dose from a liquid release is:

,D,, = k E O g DFLi .,

1 (3-2)

"I'"

(mrem) = ( ) ( C1)

( MC ;. s I

where 0FL % - Site'-specific r'laximum organ dose factor (mrem /pCi) for a liquid release. It is the highest of the four age groups. See 4 Table B.1-11.

1 unu B.3-7 00CM Rev.14

~

0, - Total activity (pC1) released for radionuclide "i". (For strontiums, use the most recent measurement available.)

K = 918/Fd : where Fd is the average (typically monthly average) dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3/sec). For normal operations with a cooling water flow of 918 ft 3/sec, K is equal l to 1.

Equation 3-2 can be applied under the following conditions (otherwise, justify Method I or consider Method II):

1. Liquid releases via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone that corresponds to a factor of 10 dilution), and

2. Any continuous or batch release over any time period.

~

3.3.2 Method II Method !! consists of the models, input data and assumptions (bioaccumulation factors, shore-width factor, dose conversion factors, and transport and buildup times) in Regulatory Guide 1.109, Rev.1 (Reference A), i except where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used in the derivation of the simp 1tfied Method I approach as described in the Bases,"section, are also applied to Method II assessments, except that doses calculated to critical organs from radio:ctive effluents are evaluated for each of the four age groups to determine the maximum critical organ of an age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors for Method II calculations. As noted in Section B.7.1, the mixing ratio associated with the edge of the l'F surface isotherm above the multiport diffuser may be used in Method II calculations for the i shoreline exposure pathway. Aquatic food ingestion pathways shall limit credit taken for mixing zone dilution to the same value assumed in Method I (M, = 0.10).

i case B.3-8 ODCM Rev.14

1 i

l l

3.4 Method to Calculate the Total Body Dose Rate From Noble Gases Technical Specification 3.11.2.1 limits the dose rate at any time to the total body from noble gases at any location at or beyond the site boundary to l 500 mrem / year. The Technical Specification indirectly limits peak release l rates by limiting the dose rate that is predicted from continued release at l

the peak rate. By limiting 0 tb to a rate equivalent to no more than l 500 mrem / year, we assure that the total body dose accrued in any one year by any member of the general public is less than 500 mrem.

Use Method I first to calculate the Total Body Dose Rate from the peak l release rate via the station vents or ground level effluent release points. J Method I applies at all release rates.

Use Method II if a more refined calculation of O tb is desired by the station (i.e., use of actual release point parameters with annual or actual meteorology to obtain release-specific X/Os) or if Method I predicts a dose rate greater than the Technical' Specification limit to determine if it had actually been exceeded during a short time interval. See Section 7 2.1 for basis.

Compliance with the dose rate limits for noble gases are continuously ]

demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off site dose rate limit, or a value below it. Determinations of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded, or as required by the Action Statement (Technical Specification 3.3.3.10. Table 3.3-10) when the monitor is inoperable.

I ur.m B.3 9 00CM Rev.14 l

3.4.1 Method i l The Total Body Dose Rate to an off-site receptor due to noble gases in l effluents released via the plant vent can be determined as follows:

l 0,3c.3 - 0.85

E ('Og . DFBg) (3-3a) i r 3 f i mrem , pCi-sec 'pCi ' mrem-e 3 yr pCi-e 3 , s sec , , pci-yr , ;

where l O tb -

The off-site total body dose rate (mrem /yr) due to noble l gases in elevated effluent releases, di -

the release rate at the station vents (pCf/sec), for each noble gas radionuclide, "i", shown in Table B.1-10, and t

DFB, - total body gamma dose factor (see Table B.1-10).

l The Total Body Dose Rate (to an off-site receptor) due to noble gas in l gruund level effluent releases can be determined as follows:

l -

l Ot ng,3 - 3.4

E ('Og

DFBg) (3-3b) 1 r 3 r 5 mrem , pCi-sec pCi ' mrem-e 3 P

yr pCi-e 3 ,

(sec, , pct -yr ,

I l where l

l O tb = The total off-site body dose rate (arem/yr) due to noble '

l gases in elevated effluent releases, and l

l 6g and DFB, are as defined for Equation 3-3a.

unu B.3-10 ODCM Rev.14

s .

l For the special on site receptor locations, the Education Center and the k

l Rocks.* the total body dose rates due to noble gases in effluent discharges l can be determined as follows: __

l l For the Education Center, elevated effluent release: _

l l Otht(e) - 0.0015 (0, DFB ) (3-3c) ,

I l For the Education Center, ground level effluent release:

l l OsbE(g) = 0.0074 . (0, . DFBs ) (3 3d) l l For the " Rocks.* elevated effluent release:

I

._. l . . _ . 0genc.3.- 0.038 (0 PFBi ) (3-3e)

I l For the " Rocks," ground level effluent release:

_. l l, Otbarg) = 0.2 (Og . DFBi ) (3-3f) l l where l

l Dtbt(e). OtbE(g). OtbR(e), and Otbt -

The total body dose rate (mrem /yr) l at the Education Center and the l

Rocks " respectively, due to noble l gases in gaseous discharges from elevated (e) and ground level (g) l l release points, and I

1 0 and DFB, are as defined previously.

l l Equations 3 3a through 3-3f can be applied under the following l conditions (otherwise, justify Method I or consider Method II):

unu B.3 11 '

ODCM Rev.14

1. Normal operations (nonemergency eve,1t), and

2. Noble gas releases via any station ' vent to the atmosphere.

3.4.2 Method II Method 11 consists of the model and input data (whole body dose factors) in Regulatory Guide 1.109. Rev. 1 (Reference A), except where site specific data or assumptions have been identified in the ODCM. The general equation (B 8) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, is also applied to a Method !! assessment. No credit for a shielding factor (Sp) associated with residential structures is assumed. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion 3 factor identified in ODCM Equation 7-3 (Section 7.2.1), and determined as

~

indicated in Section 7.3.2 for the release point (either ground level or vent stack) from which recorded effluents have been discharged.

amu B.3 12 ODCM Rev. 14

..g V

?

3.5 Method to Calculate the Skin 00se Rate from Noble Gases Technical Specification 3.11.2.1 limits the dose rate at any time to the j skin from noble gases at any location at or beyond the site boundary to 3.000 mrem / year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at l the peak rate. By limiting 0, gin to a rate equivalent to no more than 3,000 mrem / year, we assure that the skin dose accrued in any one year by any member of the general public is less than 3,000 mrem. Since it can be expected that the peak release rate on which 0,gs, is derived would not be exceeded without corrective action being taken to lower it, the resultant average release rate over the year is expected to be considerably less than the peak release rate.

Use Method I first to calculate the Skin Dose Rate from peak release rate via station vents. Method I applies at all release rates.

Use Method II if a more refined calculation of '0 skin is desired by the station (i.e., use of actual release point parameters with annual or actual l meteorology to obtain release-specific X/Os) or if Method I predicts a dose rate greater th75, the Technical Specification limit to determine if it had actually been exceeded during a short time interval. See Section 7.2.2 for basis.

Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit, or a value below it. Determinations of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded.

a I

t I 4 i

I unu B.3-13 ODCM Rev. 14 i

I I

l l

1 3.5.1 Method I l For an off-site receptor and elevated effluent release, the Skin Dose l Rate due to noble gases is:

l Dskin(e) = E (0, e D F,' g ,3 )

l '

l (3-4a) mrem f

Ci ' fmrem-s ec '

yr sec, ( C i -y r ,

where 1

l Os ging.) - the off-site skin dose rate (mrera/yr) due to noble gases in l an effluent discharge from an elevated release point.

l .

l Og = as defined previously, and l

l D F,' g 3 - the combined skin dose factor for elevated discharges (see l Table B.1-10).

l l For an off-site receptor and ground level release, the skin dose rate l due to noble gases is:

I .

I Ostin(s) " E CO

DFjg,3) (3-4b) t l

l where l

l 0,gjog,3 - The off-site skin dose rate (mres/yr) due to noble gases in l an effluent discharge from a ground level release point.

l l 0 - as defined previously, and l

l DF,'g,3 - The combined skin dose factor for ground level discharges l (see Table B.1-10).

unu B.3 14 ODCH Rev.14

l For an on site receptor at the Education Center and elevated release l conditions, the skin dose rate due to noble gases is:

I

~

I OskinE(e) - 0.0014 . E (of a DF igg,3) (3 4c) l l where l

l OskinE(s)

The skin dose rate (mrem /yr) at the Education Center l due to noble gases in an elevated release.

I

,, l 0, -

as defined previously, and

- l

=

l DF'Ete) t the combined skin dose factor for elevated discharges l (see Table B.1-13).

l l For an on site receptor at the Education Center and ground level release l conditions, the skin dose rate due to noble gases is:

. l l OskinE(g) - 0.0014 . E (01 e DF'gg,3) g (3 4d) l l where l

l 0,gg,gg,3 - the skin dose rate (mrem /yr) at the Education Center due to j noble gases in a ground level release, I

l 0, -

as defined previously. and I

=

] 0F'E(s) t The combined skin dose factor for ground level discharges l (see Table B.1-13).

l l For an on-site receptor at the " Rocks" and elevated release conditions.

l the skin dose rate due to noble gases is:

l l Ostinate) = 0.0076 . E (Oi e DF,'ag,3) (3 4e) amsa B.3 15 00CM Rev.14

=-=--=--a..:,... . .. . -

l where l

D ikinate) =

l the skin dose rate at the " Rocks' due to noble gases in an l elevated release.

I l Og =

as defined previously, and l

=

l DF'Ete) t The combined skin dose factor for elevated discharges (see l Table B.1-13).

. I I

l For an on-site receptor at the " Rocks" and ground level release l conditions, the skin dose rate due to noble gases is:

I l OskinR(s) = 0.0076 (0g . DF,'agg3) (3-4f) l l where

%=

l

' =

I O skina(g) the skin dose rate (mrem /yr) at the " Rocks" due to noble l gases in a ground level release.

I l 0 -

as defined previously, and I

l DF,"ggg3 -

the combined skin dose factor for ground level discharges l (see Table B.1-13).

l l Equations 3 4a through 3 4f can be applied under the following l conditions (otherwise, justify Method I or consider Method II).

I

1. Normal operations (nonemergency event), and

{

j 2. Noble gas releases via any station vent to the atmosphere.

I l

- - B.3-16 0

3.5.2 Method il Method 11 consists of the model and input data (skin dose factors) in Regulatory Guide 1.109. Rev.1 (Reference A), except where site-specific data or assumptions have been identified in the 00CM. The general equation (B-9) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, is also applied to a Method 11 assessment, no credit for a shielding factor (Sp) associated with residential structures is assumed. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor and undepleted atmospheric dispersion factor identified in ODCM Equation 7 8 (Section 7.2.2). and determined as indicted in Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged.

1 uruu 8.3-17 ODCM Rev.14

3.6 Method to Calculate the Critical Oraan Oose Rate from Iodines. Tritium i and Particulates with T1/2 Greater Than 8 Days Technical Specification 3.11.2.1 limits the dose rate at any time to any organ from 1311 , 133I.3H and radionuclides in particulate form with half lives greater than 8 days to 1500 mrem / year to any organ. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at the peak rate. By limiting Oc, ,

to a rate equivalent to no more than 1500 mrem / year, we assure that the critical organ dose accrued in any one year by any member of the general public is less than 1500 mrem.

Use Method I first to calculate the Critical Organ Oose Rate from the peak release rate via the station vents. Method I applies at all release rates.

Use Method II if a more refined calculation of De , is desired by the station (i.e., use of actual release point parameters'with annual or actual meteorology to obtain release-specific X/Os) or if Method I predicts a dose i rate greater than the Technical Specification limit to determine if it had l actually been cxceeded during a short time interval. See Section 7.2.3 for l basis, j i

3.6.1 Method I l The-Critical Organ Dose Rate to an off-site receptor and elevated l release conditions can be determined as follows:

I l Oco(e)

" (3-Sa)

(0

DFGico(e))

I (mrem) , g pCi ) , g mrem-s ec )

yr sec Ci-y r I

l where l

l Ocog,3 - The off-site critical organ dose rate (mrem /yr) due to l iodine, tritium, and particulates in an elevated l release, nau B.3-18 00CM Rev. 14

- the activity release rate at the station vents of Og radionuclide "i" in pCi/sec (i.e., total activity measured of radionuclide 't" averaged over the time period for which the filter / charcoal sample collector l was in the effluent stream. For 1 - Sr89 or Sr90. use l the best estimates, such as most recent measurements).

l and l

l D FG',,, g ,3 - the site specific critical organ dose rate factor l ( mrem-sec ) for an elevated gaseous release (see pC t -y r l Table B.1 12).

l

, l For an off-site' receptor and ground level release, the critical organ l dose rate can be determined as follows:

l l Oco(g) " E (O DFG'co(s)) t t (3 5b) 1 l, - .

l where l

l Ocog,3 - the off site critical organ dose rate (mrem /yr) due to

, l iodine, tritium, and particulates in a ground level l release.

I l 0, - as defined previously, and I .

- the site specific critical organ dose rate factor for l OFG,c,gg3 l a ground level gaseous discharge (see Table B.1-12).

! l l Fcr an on-site receptor at the Education Center and elevated release l conditions, the critical organ dose rate can be determined as follows:

l l Deette) - 0.0014

E (0g DFGicoE(e)) (3 Sc) f unse B.3 19 00CH Rev. 14 s

T a

l where l

l 0,,gg,3 -

The critical organ dose rate (mrem /yr) to a receptor l at the Education Center due to lodine, tritium, and l particulates in an elevated release.

I l Os

- as defined previously, and I .

l OFG icotte) -

the Education Center-specific critical organ dose rate l factor for an elevated discharge (see Table B.1 14).

I l For an on-s'te receptor at the Education Center and ground level release

~'

l conditions, the critical organ dose rate is:

I l 0coE(g) - 0.0014

E (0,

OFG'coE(g))

i (3-5d)

. 1 1

, l where l

l O cotto) the critical organ dose rate (mrem /yr) to a receptor l at the Education Center due to todine. tritium, and particulates in a ground level release.

l I

l Oi -

as defined previously, and I .

l DFG ie,gg,3 -

the Education Center specific critical organ dose rate l factor for a ground level discharge (see Table l B.1 14).

l l For an on-site receptor at the " Rocks" and elevated release conditions.

l the critical organ dose rate is:

l l Oconte) = 0.0076

E(0,

DFG'c i ac.3) (3 Se) t l

l where unu B.3 20 ODCH Rev. 14 m

.e

l 1

i 1

i l 6eagg,3 -

The critical organ dose rate (mrem /yr) to a receptor l at the " Rocks" due to iodine, tritium, and l particulates in an elevated release.

l l Oi - as defined previously, and '

I l

I , i OFG icoate) = the " Rocks"-specific critical organ dose rate factor l ,

l for an elevated discharge (see Table B.115). j i

l For an on site receptor at the " Rocks" and ground level release l l conditions, the critical organ dose rate is: l 1

l 0conte) = 0.0076

E(0g

DFG'cong,3) i (3-Sf) 1 l

l where ,

I I j l De ,a and d i - are as defined previously. and I ,

l DFGie,pg,3 = the " Rocks"-specific critical organ dose rate factor l l for a ground level discharge (see Table B.1-15).

l l l Equations 3-Sa through 3-5f can be applied under the following l conditions (otherwise, justify Method I or consider Method II)- !

l i

1. Normal operations (not emergency event), and l 2. Tritium. I-131- and particulate releases via monitored station l vents to the atmosphere.

l i

I l

I amu B.3-21 00CM Rev. 14

F 3.6.2 Method if Method II consists of the models. input data and assumptions in Appendix C of Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the 00CH (see Tables B.7-2 and B.7-3). The critical organ dose rate will be determined based on the location (site boundary, nearest resident, or farm) of receptor pathways as identified in the most recent annual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk, and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. The maximum critical organ dose rates will consider the four age groups independently, and take no credit for a shielding factor (Sp) associated with residential structures.

unu B.3-22* ODCH Rev. 14

3.7 Method to Calculate the Gamma Air Oose from Noble Gases Technical Specification 3.11.2.2 limits the gamma dose to air from noble gases at any location at or beyond the site boundary to 5 mrad in any quarter and 10 mrad in any year per unit. Dos; evaluation is required at least once per 31 days.

Use Method I .*irst to calculate the gamma air dose from the station gaseous effluent releases during the period.

Use Method II if a more refined calculation is needed (i.e., use of actual release point parameter with annual or actual meteorology to obtain

~

release-specific X/Os), or if Method I predicts a dose greater than the s

Technical Specification limit to determine if it had actually been exceeded.

. See Section ).2.4 for basis.

3.7.1 Method i The general form of the gamma air dose equation is: ,

~. l Dl,, - 3.17E-02 e [X/0){hr

t"

E (0, a DF[) (3 6) i e , ' '

(mrad) =

pCi-yr ' sec mrad-m 3

, e( )

E(pC1)

,pc i -s e c , m3 ,

$ pCi-yr ,

where DY,i, is the gamma air dose.

3.17E-02 is the number of pCi per pCi divided by the number of second

) per year, l [X/0]}g, is the 1-hour gamma atmospheric dispersion factor, l

t'* is a unitiess factor which adjusts the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months [X/0]7 value for a release with a total duration of t hours, Os is the total activity in pCi of each radionuclide "i" released to the atmosphere from the station gaseous effluent release point <fering the period of interest, and unu B.3-23 COCH Rev. 14

D FY, is the gamma dose factor to air for radionuclide "1" (see Table 8.1-10).

Incorporating receptor location-specific atmospheric dispersion factors

([X/0]T), adjustment factors (t**) for elevatek and ground level effluent release conditions, and occupancy factors when applicable (see Section 7.2.7),

yields a series of equations by which the gamma air dose can be determined.

a. Maximum off site receptor location, elevated release conditions:

l .Dlirg,3- 3.2E-07

t o.275 e E(Og e DF[) (3-6a) i r s ' '

pC l-yr mead-m 3

' (mrad) =

3

.( ) E (pCl) pCi -m , s pC1-yr ,

b. Maximum off-site receptor location, ground level release conditions:

l Dl1rto)= 1.6E-06 e t -0.293 E(Og e DF[) (3 6b) r , ' '

(mrad) =

pCi-yr 3

.( )eE(Cl) mrad M i

,pc i -m , s pC1-yr ,

I c..- Education Center receptor; elevated release conditions.

l DltrEte) = 4.9E-10 e t-o.252 eE(Og DFj) (3 6c)

' i 3

(mrad) = ( pCi-yr ) * ( ) E (pCi e mead-m ) _

pCi-m 3 pCi-y r

d. Education Center receptor: ground level release conditions:

l Dltrt(s) = 4.4E-09 t-o.321 E (0, e DF[) (3-6d) t 3 ~

(mrad) = ( pCl-yr ) * ( ) E (pCi e mrad-m )

pCi-m 3 pC 1 -yr emu B.3 24 ODCM Rev. 14

4. f E5 -.

- - - - , - _ . _ . . _. -- - ._ .- . = _ _ - . -_

e. Receptor at the " Rocks": elevated release conditions:

l Dlirac.3 = 5.1E-09

t-o.155

E (Og

DF[) (3 6e) t ,

3 (mrad) = ( pCi-yr ) * ( ) E (pCi

erad-e )

pct.e 3 pC1 -y r

f. Receptor at the " Rocks"; ground-level release conditions:

l DlirR(g) = 4.1E-08

t4 *

E (Og

0F[) (3-6f) 1 3

(mrad) = ( pCi-yr ) * ( ) E (pCie mrad-e )

Ci-m3 pci-yr Equations 3-6a through 3-6f can be applied under the following conditions (otherwise justify Method I or consider Method II):

1. Normal operations (ncnemergency event), and

2. Noble gas releases via station vents to the atmosphere.

3.7.2 Method II Method Il consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptinns have been identified in the ODCH. The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section 7.2.4 are also applied to Method II assessments. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor identified in ODCM Equation 7-14, and determined as indicated in Section 7.3.2 for the release point (either ground level or vent stack) from which recorded effluents have been discharged.

unu B.3-25 ODCH Rev. 14

l 3.8 Method to Calculate the Beta Air Dose from Noble Gases !

Technical Specification 3.11.2.2 limits the beta dose to air from noble l gases at any location at or beyond the site boundary to 10 mrad in any quarter '

and 20 mrad in any year per unit. Oose evaluation is required at least once per 31 days.

Use Method I first to calculate the beta air dose from gaseous effluent releases during the period. Method I applies at all dose levels. )

Use Method II if a more refined calculation is needed (i.e., use of actual release point parameters with annual or actual meteorology to obtain release-specific X/Os) or if Method I predicts a dose greater than the Technical Specification limit to determine if it had actually been exceeded.

See Section 7.2.5 for basis.

3.8.1 Method i The general form of the be'ta air dose equation is:

8 (3-7) l Da1r = 3.17 E-02 * (X/0)1hr

t '*

E ( 0,

O F,8) pCi-yr ' sec 3 (mrad) = , *( )*E nCi

mrad-m (pCi-sec j m3 , s pCi-yr ,

where .

8 0,,, is the beta air dose, 3.17E 02 is the number of pCi per pCi divided by the number of seconds per year, i

l (X/0)1hr is the 1-hour undepleted atmospheric dispersion factor. l l t** is a unitiess factor which adjusts the 1-hour X/0 value for a release with a total duration of t hours.

O, is the total activity ( C1) of each radionuclide 'i' released to the atmosphere during the period of interest, and DF$ is the beta dose factor to air for radionuclide "i" (see Table B.1-10) .

unu B.3-26 00CM Rev.14

Incorporating receptor location specific atmospheric dispersion factor (X/0), adjustment factors (t**) for elevated and ground level effluent release conditions. and' occupancy factors when applicable (see Section 7.2.7) yields a series of equations by which the Beta Air Dose can be determined,

a. Maximum off site receptor location elevated release conditions:

l Ofirg,3 = 4.1E-7

t'0 3

E (Os

OFf) (3-7a) t 3

(mrad) = ( pC1-yr ) * ( ) ( Ci e mrad-m )

gCi-m 3 pCi -y r s

b. Maximum off-site receptor location. ground-level release conditions:

Oftrg,3 .6.0E-06

t-0 31'

E (Og

OF 8 l i )_ _

(3 7b)_._ __ _

. i

- 3 (mrad) = ( pCi-yr ) * ( ) E (pCi

narad-m )

3 pC1 -yr pCi-m

c. Education Center receptor: elevated release conditions:

l DfirE(e) = 1.8E-09

t-0 35

E, (0,

OFf) (3 7c) 3 (mrad) = ( pCl-yr ) * ( ) (pCi e mrad-m )

pCi-m 3 pCi-y r

'm** B.3 27 ODCM Rev. 14

_ . - _ .. - _ . . . . _ . _ . _ . . . _ _ . ._,-.;-. .-n------- -

('rL

d. Education Center receptor; ground level release conditions:

l Oftrt(g) = 2.4E-08

t4 387

E (0,

Of f) (3 7d) 3 (mrad) = ( pCi-yr ) * ( ) (pCi

mead-m )

pC1-m 3 pci-y r

e. Receptor at the " Rocks"; elevated release conditions:

l Ofgrac 3 = 3.9E-08

t-o.249

E (0,

Off) (3-7e)

> t

~

3 (mrad) = ( DCl-yr ) * ( ) E (pCi

mrad-m )

3 pci-yr pCi-m

f. Receptor at the " Rocks"; ground level release conditions:

, l OftrR(g) = 4.6E-07

t-0.267

E (Ot*Off) (3-7f) 1 3

(mrad) = ( pCi-yr ) * ( ) E (pCi

mrad-m )

pCi-m- pC1-yr Equations 3-7a through 3 7f can be applied under the following conditions (otherwise justify Method I or consider Method II):

1. Normal operations (nonemergency event), and

2. Noble gas releases via station vents to the atmosphere, s

ams: 8.3 28 00CM ev

l 3.8.2 Method II Method II consists of the models. input data (dose factors) and assumptions in Regulatory Guide 1.109. Rev.1 (Reference A). except where site-specific data or assumptions have been identified in the ODCM. The general equations (B 4 and B-5) taken from Regulatory Guide 1.109. and used in the derivation of the simplified Method I approach as described in the Bases Section 7.2.5. are also applied to Method II assessments. Concurrent meteorology with the release period may be utilized for the atmospheric dispersion factor identified in ODCM Equation 7-15. and determined, as indicated in Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged.

J unn 8.3-29 ODCM Rev.14

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

l 3.9 Method to Calculate the Critical Oraan Dose from Iodines. Tritium and l ParticulLtig, 4

Technical Specification 3.11.2.3 limits the critical organ dose to a member of the public from radioactive iodines, tritium, and particulates with

) half-lives greater than 8 days in gaseous effluents to 7.5 mrem per quarter i and 15 mrem per year per unit. Technical Specification 3.11.4 limits the l total body and organ dose to any real member of the public from all station ,

4 sources (including gaseous effluents) to 25 arem in a year except for the q thyroid, which is limited to 75 mrem in a year.

4

Use Method I first to calculate the critical organ dose from gaseous

effluent releases as it is simpler to execute and more conservative than Method II.

Use Method II if a more refined calculation of critical organ dose is

, needed (i.e., Method I indicates the dose is greater than the limit). See Section 7.2.6 for basis. ,

3.9.1 Method I l l De , = (X/0)Nfl /(X/0)$'I

t *

E (0 *i DFG ie ) (3-8) 1 (mrem) = ( 8'C )/( sec ) * ( )

E (pCi) * ( )

4 where i

De , is the critical organ dose from iodines, tritium, and particulates.

l l (X/0)$$I is the 1-hour depleted atmospheric dispersion factor.

l (X/0)N'I is the annual average depleted atmospheric dispersion.

t** is a unitiess adjustment factor to account for a release with a l total duration of t hours, l

4 s

j unu B.3-30 ODCM Rev.14 1

Og is the total activity in pCi of radionuclide "t* released to the atmosphere during the period of interest (for strontiums use the most recent measurement), and DFG ig , is the site specific critical organ dose factor for raotonuclide l *i", see Tables B.1 12 B.1 14, and 8.1 15. (For each radionuclide, it l 1s the age group and organ with the largest dose factor.)

l Incorporating receptor location-specific atmospheric dispersion factors l ((X/0)![ and (X/0)7') and adjustment factors (t**) for elevated and ground- "

level release conditions, and incorporating occupancy factors when applicable (see Section 7.2.7), yields a series of equations by which the critical organ dose can be determined.

"2L

. a. Maximum off-site receptor location, elevated release conditions:

4 "I e E (0< e DFG ,,g,3) l Oc c.3 = 14.8 e t (3 8a) i (mrem) = ( )e( ) E (pCi e ' pC1 ." )

N

b. Maximum off site receptor location, ground level release j conditions:

l Deogg3 = 17.7 e t4 31'

E (0, DFGie g,3) (3 8b) i (mrem) = ( ,

)e( ) E ( Ci e mrem) pCi

c. Education Center receptor: elevated release conditions:

l Ocogg 3 = 3.3E-02 e t-0 3 E(Og DFGicottel) (3 8c)

(mrem) = ( )( ) E (pCi e mrem) pC ).

l nrm B.3-31 *D,f

[ g O ,

d. Education Center receptor: ground-level release conditions:

l DcoE(s) = 3.3E-02

t-0 3'I

E (Og

DFG ic,gg,3) (3 8d)

(mrem) = ( )e( ) E (pC1 e mrem) pC1

e. Receptor at the ' Rocks"; elevated release conditions:

l Dcoat,3 - 7.3E-02 e t-o.24s

E (Os DFGtconte)) (3 8e)

(mrem) = ( )*( ) E (pci e W)

f. Receptor at the " Rocks *: ground-level release conditions:

l Dcoacg3 = 8.6E-02 e t-o.267

E(0, e DFG c acg3) (3-8f) t

~

(mrem) =( )*( ) E (pCi * * )

pC1 Equations 3-8a through 3 8f can be applied under the following conditinns (otherwise. justify Method I or consider Method !!):

1. Normal operations (nonemergency event),

2. lodine, tritium, and particulate releases via station vents to the atmosphere. and

3. Any continuous or batch release over any time period.

3.9.2 Method !!

Method !! consists of the models, input data and assumptions in ,

Appendix C of Regulatory Guide 1.109. Rev. 1 (Reference A), except where site specific data or assumptions have been identified in the ODCM (see Tables B.7-2 and B.7-3). The critical organ dose will be determined based on the location (site boundary nearest resident or farm) of receptor pathways.

urm B.3-32 ODCM Rev. 14 m

,y

as identified in the most recent annual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. The maximum critical organ dose will consider the four age groups independently, and use a shielding factor (Sp) of 0.7 associated with residential structures.

I l

I i

l l

\

! unu B.3-33 00CM Rev. 14 l

1

)

l I

l 1

3.10 Method to Calculate Direct Dose from Plant Ooeration #

i Technical Specification 3.11.4 restricts the dose to the whole body or ;

any organ to any member of the public from all uranium fuel cycle sources - l (including direct radiation from station facilities) to 25 mrem in a calendar i year (except the thyroid, which is limited to 75 mres). It should be noted that since there are no uranium fuel cycle facilities within 5 miles of the station, only station sources need be considered for determining compliance !

with Technical Specification 3.11.4.

3.10.1 Method The direct dose from the station will be determined by obtaining the dose from TLD locations situated on-site near potential sources of direct radiation, as well as those TLDs near the site boundaly which are part of the i environmental monitoring program, and subtracting out the dose contribution from background. Additional methods to calculate the direct dose may also be ,

used to supplement the TLD information, such as high pressure ion chamber .

measurements, or analytical desi'gn calculations of direct dose from identified sources (such as solid waste storage facilities). i The dose determined from direct measurements or calculations will be l related to the nearest real person off-site, as well as those individuals ;

on-site involved in activities at either the Education Center or the Rocks i boat landing, to assess the contribution of direct radiation to the total dose limits of Technical Specification 3.11.4 in conjunction with liquid and ,

gaseous effluents.

i 4

l

?

l l

l

)

l l

anum B.3-34. ODCM Rev. 14 )

3.11 Dose Projections Technical Specifications 3.11.1.3 and 2.11.2,4 require that appropriate portions of liquid 'and gaseous radwaste treatment systems, respectively, be used to reduce radioactive effluents when it is projected that the resulting dose (s) would exceed limits which represent small fractions of the "as low as reasonably achievable" criteria of Appendix ! to 10CFR Part 50. The surveillance requirements of these Technical Specifications state that dose projections be performed at least once per 31 days when the liquid radwaste 1 treatment systems or gaseous radwaste treatment systems are not being fully l utilized.

Since dose assessments are routinely performed at least once per 31 days to account for actual releases, the projected doses shall be determined by comparing the calculated dose from the last (typical of expected operations) completed 31-day period to the appropriate dose limit for use of radwaste equipment, adjusted if appropriate for known or expected differences between past operational parameters and those anticipated for the next 31 days.

3.11.1 Licuid Dose Projections The 31-day liquid dose projections are calculated by the following:

(a) Determine the total body Da and organ dose D. (Equations 3-1 and 3-2, respectively) for the last typical completed 31-day period.

The last typical 31-day period should be one without significant

.' dentified i operational differences from the period being projected to, such as full power operation vs. periods wnen the plant is shut down.

(b) Calculate the ratio (R g) of the total estimated volume of batch releases expected to be released for the projected period to that actually released in the reference period.

(c) Calculate the ratio (R 2) of the estimated gross primary coolant activity for the projected period to the average value in the reference period. Use the most recent value of primary coolant activity as the projected value if no trend in decreasing or increasing levels can be determined.

unu B.3-35 00CM Rev. 14

)

i (d) Determine the projected dose from:

! Total Bcdy: Dtb pr - Otb .R g .R 2 Max. Organ: D ,, - D . R3 .R 2 3.11.2 Gaseous Dose Projections l

For the gaseous radwaste treatment system, the 31-day dose projections are calculated by the following:

(a) Determine the gamma air dose DJ,, (Equation 3-6a), and the beta airdoseDfg,(Equation 3-7a)fromthelasttypical31-day I

operating period.

(b) Calculate the ratio (R )3 of anticipated number of curies of noble gas to be released from the hydrogen surge tank to the utmosphere over the next 31 days to the number of curies released in the reference period on which the gamma and beta air doses are based.

! If no differences between the reference period and the next 31 l

days can be identified, set R3 to 1.

(c) Determine the projected dose from:

Gamma Air: D[tr pr = Dlg, . R 3 l

Beta Air: Ofge p, = Ofg, . R 3 l l

l For the ventilation exhaust treatment system, the critical organ dose from iodines, tritium, and particulates are projected for the next 31 days by the following:

i l (a) Determine the critical organ dose De, (Equation 3-Ba) from the l last typical 31-day operating period. (If the limit of Technical l Specification 3.11.2.4.c. (i.e. 0.3 mrem in 31 days) is exceeded.

l the projected controlled area annual total effective dose l equivalent from all station sources should be assessed to assure 4

amu B.3-36 ODCM Rev. 14

i l

l that the 10CFR20.1301 dose limits to members of the public are not l exceeded.)*

(b) Calculate the ratio (R )4 of anticipated primary coolant dose equivalent I-131 for the next 31 days to the average dose equivalent I-131 level during the reference period. Use the most current determination of DE I 131 as the projected value if no trend can be determined.

(c) Calculate the ratio (R )S of anticipated primary system leakage rate to the average leakage rate during the reference period. Use the current value of the system leakage as an estimate of the anticipated rate for the next 31 days if no trend can be determined.

(d) Determine the projected dose from:

Critical Organ: D,,y-D,.R e 4 . R5 I

l Note: This action is based on the assumption that tritium is the controlling l nuc-lide for whole body exposures through the inhalation pathway.

l Ma'ximum annual average on-site X/0's for station effluent release l points are approximately 100 times the values used for the site l boundary dose calculations. However, the site boundary doses l calculated by the ODCM for iodines, tritium, and particulates with l half lives greater than 8 days, includes all potential off-site l exposure pathways. For tritium, the inhalation pathway only accounts l for 10% of the total dose contribution being calculated. As a result.

l if the monthly calculation indicates that the site boundary maximum l organ dose reached 0.3 mrem, the on-site maximum dose due to l inhalation would be approximately 3.0 mrem for this period. If this l were projected to continue for a year with a 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months occupan:y l factor applied, the projected inhalation whole body dose would be l approximately 8 mrem, or 8% of the 10CFR20.1301 limit. This is a l reasonable trigger value for the need to consider the dose l contribution from all station sources to members of the public in l controlled areas.

unas B.3-37 ODCM Rev. 14 l

l 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring stations are listed in Table B.4-1.

The locations of the stations with respect to the Seabrook Station are shown on the maps in Figures B.4-1 to B.4-6.

Direct radiation measurements are analyzed at the station. All other radiological analyses for environmental samples are performed at the Yankee Environmental Laboratory. The Laboratory participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for all the species and matrices routinely analyzed.

Pursuant to Specification 4.12.2, the land use census will be conducted 'during the growing season' at least once per 12 months. The growing season is defined, for the purposes of the land use census, as the period from June 1 to October 1.

The method to be used for conducting the census will consist of one or more of the following, as appropriates door-to-door survey, visual inspection from roadside, serial survey, or consulting with local agricultural authorities.

Technical Specification 6.8.1.3 requires that the results of the Radiological Environmental Monitoring Program be summarized in the Annual Radiological Environmental Operating Report 'in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, 1979.* The general table format will be used with cue exception and one clarification, as follows. The mean and range values will be based not upon detectable measurements only, as specified in the NRC Branch Technical Position, but upon all measurements. This will prevent the positive bias associated with the calculation of the mean and range based upon detectable measurements only. Secondly, the Lower Limit of Detection column will specify the LLD required by CDCM Table A.5-2 for that

~

radionuclide and sample medium.

B.4-1 CDCM Rev. 9

e TABLE B.4-1 Radiolooical Environmental Monitorino StationsI *)

Distance From Exposure Pathway Sample Location Unit 1 Direction from and/or Samole and Desionated Code Containment (km) the Plant

1. AIRBORNE (Particulate and Radiciodine)

AP/CF-01 PSNH Barge 2.7 r"E Landing Area AP/CF 02 Hampton Marina 2.7 E AP/CF-03 SW Boundary 0.8 SW AP/CF-04 W. Boundary 1.0 W AP/CF-05 Winnacunnet H.S.(b) 4.0 NNE AP/CF-06 Georgetown 24.0 SSW Substation (Control)

2. WATERBORNE

a. Surface WS-01 Hampton-Discharge Area 5.3 E WS-51 Ipswich Bay (Control) 16.9 SSE

b. Sediment SE-02 Hampton-Discharge Area th) 5.3 E SE-07 Hampton Beach 3.1 E SE-08 Seabrook Beach (*) 3.2 ESE SE-52 Ipswich Bay (Control)(b) 16.9 SSE SE-57 Plum Island Beach 15.9 SSE (Control)(b)

3. INGESTION

a. Milk TM 04 Salisbury. HA 5.2 SW TM-08 Hampton Falls, NH 4.3 NNW TM-15 Hampton Falls,(b) NH 7.0 MW l TM-16 Kensington. NH 7.7 WNW TM 20 Rowley, MA (Control) 16.3 S

b. Fish and InvertebratesI *I FH-03 Hampton - Discharge 4.5 ESE Area FH-53 Ipswi (Control) 16.4 SSE HA 04 Hampto. Di 'cha rge 5.5 E Area HA-54 Ipswich Bay (Control) 17.2 SSE MU-06 Hampton - Discharge 5.2 E Area MU-56 Ipswich Bay (Control) 17.4 SSE l B.4-2 ODCM Rev. 15

TABLE B.4-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING STATIONS (*)

Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Designated Code Containment (km? the Plant 4 DIRECT RADIATION TL-1 Brimmer's Lane, 1.1 N Hampton Falls TL-2 Landing Rd., Hampton 3.2 NNE TL-3 Glade Path. Hampton 3.1 NE Beach TL-4 Island Path, Hampton 2.4 ENE Beach TL-5 Harbor Rd., Hampton 2.7 E Beach TL-6 PSNH Barbe Landing 2.7 ESE

~7a TL-7 brces Rd., Seabrook 2.6 SE Beach TL-8 Farm Lane, Seabrook 1.1 SSE TL-9 Fann Lane, Seabrook 1.1 S TL-10 Site Boundary Fence 1.0 SEW TL-11 Site Boundary Fence 1.0 SW TL-12 Site Boundary Fence 1.0 WSW j TL-13 Inside Site Boundary 0.8 W !

TL-14 Trailer Park, Seabrook 1.1 WNW TL-15 Brimmer's Lane, 1.4 NW Hampton Falls TL-16 Brimmer's Lane, 1.1 NNW Hampton Falls TL-17 South Rd., N. Hampton 7.9 N TL-18 Mill Rd., N. Hampton 7.6 NNE TL-19 Appledore Ave., 7.9 NE N. Hampton TL-20 Ashworth Ave., 3.4 ENZ Hampton Beach TL-21 Route 1A, Seabrook 2.7 SE Beach TL-22 Cable Avu., 7.6 SSE Salisbury Beach TL-23 Ferry Rd., Salisbury 8.1 S TL-24 Ferry Lots Lane, 7.2 SEW Salisbury TL-25 Elm St., Amesbury 7.6 EW TL-26 Route 107A, Amesbury 8.1 WSW B.4-3 ODCM Rev. 4

TABLE B.4-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING S' .. ONS(*3 ,_

Distance From Exposure Pathway Sample Location Unit 1 Direction From l and/or Sample and Desinnated Code Containment (km) the Plant l TL-27 Highland St., 7.6 V l S. Hampton '

TL-28 Route 150. Kensington 7.9 WNW TL-29 Frying Pan Lane, 7.4 NW ;

Hampton Falls l TL-30 Route 101C, Hampton 7.9 NNW i TL-31 Alumni Drive, Hampton 4.0 NNE TL-32 Seabrook Elementary 1.9 S School TL-33 Dock Area, Newburyport 9.7 S TL-34 Bow St., Exeter 12.1 NW TL-35 Lincoln Ackerman 2.4 NNW School i TL-36 Route 97, Georgetown 22 SSW (Control)

TL-37 Plaistow, NH (Control) 26 WSW TL-38 Hampstead, NH (Control) '

29 W l TL-39 Fremont, NH (Control) 27 WNW TL-40 Newmarket. NH (Control) 24 NNW TL-41 Portsmouth, NH 21 NNE .

(Control)D3 l TL-42 Ipswich, )UL (Control)D3 27 SSE (a) Sample locations are shown on Figures B.4-1 to B.4-6.

(b) This sample location is not required by monitoring program defined in Part A of ODCM; program requirements specified in Part A do not apply to samples taken at this location.

(c) Samples will be collected pursuant to CDCM Table A.5-1. Samples are not I required from all stations listed during any sampling interval (FH = Fish:

HA = Lobsters: MU = Muscles). Table A.5-1 specifies that 'one sample of three commercially and recreationally important species' be collected in the vicinity of the plant discharge area, with similar species being collected at a control location. (This wording is consistent with the NRC Final Environmental Statement for Seabrook Station.) Since the discharge area is off-shore, there is a great number of fish species that could be considered commercially or recreationally important. Some are migratory (such as striped bass), making them less desirable as an indicator of plant-related radioactivity. Some pelagic species (such as herring and mackerel) tend to school and vs der i throughout a large area, sometimes making catches of significant sit difficult I to obtain. Since the collection of all species would be difficult at impossible, and would provide unnecessary redundancy in terms of moni $,cing important pathways to man, three fish and invertebrate species have been specified as a minimum requirement. Samples may incl 2de marine fauna such as lobsters, clams, mussels, and bottom-dwelling fish. such as flounder or hake.

Several similar species may be grouped together into one sample if sufficient sample mass for a single species is not available after a reasonable effort has been made (e.g., yellowtail flounder and winter flounder).

B.4-4 ODCM Rev. 11

FIGURE B.4-1 RADIOIDGICAL ENVIRONMENTAL MONITORING IACATIONS UTTHIN 4 KITAMETERS OF SEABROOK STATION N

h 1

\

~

b4 '

s. (4 i BROWNS RIVER

=, Mb u AP/CF-04 A AP/CF-03 A

/

-')

& s AP/CF-02 A HAMPTON HAR8OR L

HU QREEK AP/CF-01' A na --

E l__ SE-08 A

/

f

) \L g l[ o 0 500 1000 $ "

E METERS (p h

/ m B.4-5 ODCM Rev.15

FIGURE B.4-2 .-

RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS BETVEEN 4 KIIDMETERS AND 12 KILOMETERS FROM SEABROOK STATION e)

R,) 0 5 cc i w % ~

g KILOMETERS C

E

=

x N

S J RYE BEACH TM-09 A TM-15 A SEE ENLARGEMENT IN FIGURE B.4-1

_ _T _ _. e .^"Ic55 '

TM-16 A l

l a

l l e-- HAMPTON BEACH lASE-07 SEABROOK S ATION e 8 A% DISCHARGE SITE WS-01 SE-02 MU-06

, "*~ ~, e i FH-03 HA-04

\d -

lbSEABROOKBEACH 8 l'N. ,

,_ _ _'%,4 _ _ . . , .

TM-04 A SALISBURY BEACH b

l MERRig g g6 l l

O ATLANTIC OCEAN 4 I

B.4-6 ODCM Rev.15 l

l

I I

FIGURE 3.4 3 !

RADIOIDCICAL ENVIRONMENTAL MONITORINC IDCATIONS OUTSIDE 12 KILOMETERS OF SEAEROOK STATION {

0 5 10 15

!F .

I KILOMETERS ,

\\

YORK e

DURHAM e

\ NIhg ,'

NEWMARKET e ORTSHOUTHe

.g ND

, EPPING \,

\.

\ +\,*e

, #e 8

i e DES 8 N SEE ENLARGEMENT IN FIGURE i '

j B.4-2 --in i HAMPTON I I e I I I 3

SEABROOK STATION !

KINGSTON e I

\E HAMPTON HARBOR I

SEABROOK,e I

' l L

~~~~~-

'N.-- DISCHARGE SITE e SALISBURY I j

e f-l~ANESBURY i e i PLAISTOW * , i 1 i

. / 1 e

' .-s #. # '- i i j Nif{'- .NEWBURYPORT e I

ATLANTIC OCEAN I

HAVERMILLe l

\

' , A SE-57

. 'I '

! PLUM ISLAND

. TM-20 FH-53 METHUEN e AP/CF-06 A A SE-52 A WS-51

LAWRENCE IPSWICH BAY IPSWICH e A MU-56 HA-54 a

GLOUCESTER B.4-7 ODCM Rev. 8

-. .. . . -= .

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

FIGURE B.4-4 DIRECT RADIATION MONITORING TACATIONS WITHIN 4 KIIAMETERS OF SEABROOK STATION e

NNW N NNE N

J _

A TL-2 NE Sg i

NW

\-35 A TL A TL-3 i

o e A TL-4 ENE TL-15 A TL-16 4 A TL-1 Q WNW TL-14 A SEABROOK g W TL-13 A TL-5 A

, g HAMPTON HARBOR t

TL-11 A H TS IS REEK -

TL-10 A TL-6 A

~

-8 A A y TL-9 - - -

ESE 8

A TL-7 5

TL-32 A d SW % u *

'Q $

/ 5 9 "

$ u$

0 500 1000 h METERS TL- 1 3 S SSE SE l

B.4-8 ODCM Rev. 15

FIGURE 5.4-5 l

i DIRECT RADIATION MONITORINC LOCATIONS BETJEEN 4 KILOMETF1tt AND 12 KILOMETERS TROM SEARROOK STATION N NNE

= N'NW Ei'

=i o s

KILCMETERS NW I NE l t N

A TL-34

! Miles \ d A RYE B UCH A TL-17 A TL-30 TL-18 A TL-19

[

l

\

A TL-29\

WW ,

\' ME SEE ENLARGEMENT IN FIGURE B.4-4

\. ~ h ~ A TL-31

~~ ~ ~~

A TL-28 NAMPT" .

SEA 8R00K STATION 5 i DISCHARGE SITE W A TL-27 l

, . - " * . , I j N.' , S GBRC0K B UCH

s. N -

n /

TL-26 i ,

, i /

- .e

,,,. I--- 9, -- .

/

WSW \

A -25

{k sA 58URY.8DCH TL-24 A TL-22 A)

\

TL-23 o s l

SE l MERRisc #* .

TL-33 A ATLANTIC CCIAN SW ssW s g sSE x l __

3.4 9 ODCM Rev. a 1

FIGURE B.4-6 DIRECT RADIATION MONITORING LOCATIONS OUTSIDE 12 KILOMETERS OF SEABROOK STATION -

NNW N 1, f NNE O $ 10 15 NW XILCMETIRS g YORX 8

ig Yf l CURHAM e s %, NE s TL-40 A '

NEWMARKET e PORT! MOUTH e ...

O EPPING fTL41

10Mflec/ .

/ \.

WNW FREMONT g

_, __1___

l

?f TL-398 e e DETER N I

SEI ENLAAGEMENT IN FIGUAE

' s HAMPTON e-

\ l

$~d8R00K STATION W

KINGSTCMe i

Nk gy,,oo, e a e e

i E j

l 7 O!5CHAAGE $1TE TL-38 A ..' /..$. . {

/~j Angsgggy e PLAISTC'4 e. , i/ i TL-37 A / I i EsE g.g *

/

. - . ,NJJ NEWEURh0RT .

ATLANTIC OC D N WSW l' xxygxxttte

[~~~~~~

, PLUM ISLAND

, . 4 , ,1, ETHUEN e TL-36 A 1

LAWRENCE IPSVICH 8AY [

IP!WICH e gTL-42 sW e GLOUCESTER ssW s ssE h \

B.4-10 CDCM Rev. 11

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

5.0 SETPOINT DETERMINATIONS i

Chapter 5 contains the methodology for the calculation of effluent monitor setpoints to implement the requirements of the radioactive effluent monitoring systems Technical Specifications 3.3.3.9 and 3.3.3.10 for liquids l gases, respectively. I Example setpoint calculations are provided for each of the required l

effluent monitors.

l l

l B.5-1 8686R 00CM Rev. 7 l

l l

5.1 Liquid Effluent Instrumentation Setpoints -

Technical Specification 3.3.3.9 requires that the radioactive liquid effluent instrumentation in Table 3.3-12 of the Technical Specifications have alarm setpoints in order to ensure that Technical Specification 3.11.I.1 is not exceeded. Technical Specification 3.11.1.1 limits the activity concentration in liquid effluents to the appropriate MPCs in 10CFR20 and a total noble gas MPC.

5.1.1 Licuid Waste Test Tank Monitor (RM-6509)

The liquid waste test tank effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 to the environment. It is also used to monitor discharges from various waste sumps to the environment.

5.1.1.1 Method to Determine the Setpoint of the Licuid Waste Test Tank Monitor (RM-6509)

The instrument response (pCi/ml) for the limiting concentration at the point of discharge is the setpoint, denoted Rsetpoint, and is determined as follows:

N setpoint

Il D C,g (5-1) min i (pC1/ml) ( ) ( )

(h) where:

F d

DF p - Dilution factor (dimensionless) (5-2) m F, - Flow rate past monitor (gpm)

F d - Flow rate out of discharge tunnel (gpm)

DFmin - Minimum allowable dilution factor (dimensionless)

B.5-2 '

8686R ODCM Rev. 4

f) -

1 - (f2+I 3

I 4); where fj is the fraction of the tott.1 contribution of MPC at the discharge point to be associated with the test tank effluent pathway and,2 f ' I3 '

and f 4 are the similar fractions for Turbine Building sump,

)

steam generator blowdown, and primary component cooling pathways, respecthely:

(f) +f2+I3+I4 I I}*

C ,y DF min " MPC g.

(5-3) g MPC g - MPC for radionuclide "1" from 10CFR20, Appendix 8. Table II, ,

Column 2 (pC1/ml). In the event that no activity is expected I to be discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MPC for an " unidentified" mixture given in 10CFR20, Appendix B, notes.

C,9 - Activity concentration of radionuclide "1" in mixture at the monitor (pC1/ml) !

i 5.1.1.2 Liquid Waste Test Tank, Monitor Setpoint Example The activity concentration of each radionuclide, C,g, in the waste test tank is determined by analysis of a representative grab sample obtained at the radwaste sample sink. This setpoint example is based on the following data:

1 C,3 (pCl/ml) MPCg (pC1/ml)

Cs-134 2.15E-05 9E-06 Cs-137 '7.48E-05 2E-05 Co-60 2.56E-05 3E-05 E C., . 2.iSE-05 7..u-05 2.5 2-05 . i. m -0.

1 guC1) ,(uC1) (uct) (uC1) mi mi mi ml B.5-3 8686R oDCM Rev. 8

- -__ ..- .- . .- _-_ _. - .-_._- .-. = _ _ - -- - - _-

DF - (5-3) min i i guCl-ml) ml-pC1 2.15E-05 7.48E-05 2.56E-05

" + + -

9E-06 2E-05 3E-05 8 guC1-al) guci-ml) guct-ml) mi-pCl mi-pCl mi-pC1 DFmln " 7 The minimum dilution factor, DFmin, needed to discharge the mixture of radionuclides in this example is 7. The release rate of the waste test tank is between 10 and 150 gpm. The circulating water discharge flow can vary from 10,500 to 412,000 gpm of dilution water. With the dilution flow taken as 412,000 gpm and the release rate from the waste test tank taken as 150 gpm, the DF is:

F d

DF =

p a .

(qpm) (5-4)

(gpm) 412,000 com 150 gpm

- 2750

. B.5-4 ODCM Rev. 4 8686R

Under these conditions, and with the fraction fj of total MPC to be associated with the test tank selected as 0.6, the setpoint of the 11guld radwaste discharge monitor is:

Rsetpoint " Il D "I in

$ ( )( ) uC1 mi (ml )

l 2 0

= 0.6 1.22E-04

( )( ) ( )

= 2.87E-02 pCl/ml or pC1/cc In this example, the alarm of the liquid radwaste discharge monitor should be set at 2.87E-02 pC1/cc above background.

5.1.2 Turbine Buildino Orains Llauld Effluent Monitor (RM-6521)

The Turbine Building drains 11guld effluent monitor continuously monitors the Turbine Building sump effluent line. The only sources to the Sump Effluent System are from the secondary steam system. Activity is expected in the Turbine Building Sump Effluent System only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, with reduced activity from decay and dilution.

The Turbine Building drains 11guld effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix 8 Table II, Column 2 to the environment. The alarm setpoint for this monitor will be determined using the same method as

~

that of the liquid waste test tank monitor if the total sump activity is l

B.5-5 l 8686R ODCH Rev.10

greater than 10 percent of MPC, as determined by the most recent grab sample isotopic analysis. If the total activity is less than 10 percent of MPC, the setpoints of RM-6521 are, calculated as follows:

High Trip Monitor (5-21)

Setpoint (pC1/ml) - f2 (DF') (1.0E-07 pC1/ml)

Circulating water flow rate (gem) where: OF' =

Flow rate pass-monitor (gpm) 1 1.0E-07 pC1/ml = most restrictive MPC value for an unidentified mixture given in 10CFR20, Appendix B, Note 3b.

f2 " 1 - (fl+f 3 + f 4); where the f values are described above.

In addition, a warning alarm setpoint can be determined by multiplying the high trip alarm point by an administratively selected fraction (as an example,.

0.25).

' ~

Harning Alarm High Trip (5-22)

Monitor Setpoint - (Monitor Setpoint) (0.25)

(pC1/ml) 5.1.3 Steam Generator Blowdown Liould Sample Monitor (RM-6519)

The steam generator blowdown liquid sample monitor is used to detect abnormal activity concentrations in the steam generator blowdown flash tank liquid discharge.

The alarm setpoint for the steam generator blowdown liquid sample conitor, when 11guld is to be discharged from the site, will be determined using the same approach as the Turbine Building drains 11guld effluent monitor. l l

For any liquid monitor, in the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint - -

l should be based on the most restrictive MPC for an " unidentified" mixture given in 10CFR20, Appendix B notes.

B.5-6 8686R ODCM Rev.10

l l

5.1.4 PCCW Head Tank Rate-of-Change Alarm Setpoint l

A rate-of-change alarm on the liquid level in the Primary Ccmponent l Cooling Water (PCCW) head tank will work in conjunction with the PCCW radiation monitor to alert the operator in the Main Control Room of a leak to the Service Water System from the PCCW System. For the rate-of-change alarm, i a setpoint is selected based on detection of an activity level equivalent to l 10~0 pC1/ml in the discharge of the Service Water System. The activity in I the PCCW is determined in accordance with the liquid sampling and analysis

program described in Part A, Table A.3-1 of the ODCM and is used to determine !

the setpoint. .

The rate-of-change alarm setpoint is calculated from:

i RC set = lx10-8 , ggp , PCC (g-23) ;

(N) hr uC1 (ml )

(gal) hr (m1 )

pC1 l where: ,

RC set

- The setpoint for the PCCW head tank rate-of-change alarm (in gallons per hour).

lx10-8 - The minimum detectable activity level in the Service I Hater System due to a PCCW to SWS leak (pC1/ml).

l SWF = Service Water System flow rate (in gallons per hour).

i PCC = Primary Component Cooling Water measured (decay corrected) gross radioactivity level (pCl/ml).

As an example, assume a PCCW activity concentration of lx10-5 pC1/ml . _

with a service water flow rate of only 80 percent of the normal flow of 21,000 gpm. The rate-of-change setpoint is then:

B.5-7

, 8686R 00CM Rev.10

I j

1

RCset - lx10-8 m -

1.0x106 gph (1/lx10-5 )

m -

RCset = 1000 gph 4

l As a result, for other PCCW activities, the RC set which would also relate to a detection of a minimum service water concentration of lx10-8 C1/ml can be found from:

1 1 h RCset " (5-24) 5.1.5 PCCW Radiation Monitor The PCCW radiation monitor will alert the operator in the Main Control Room of a leak to the PCCW System from a radioactively contaminated system.

The PCCW radiation monitor alarm is based on a trend of radiation levels in the PCCW System. The background radiation of the PCCW is determined by evaluating the radiation levels over a finite time period. The alert alarm setpoint is set at 1.5 x background, and the high alarm setpoint is set at 2 x background, per Technical Specification Table 3.3-6.

l l

B.5-8 8686R 00CM Rev.10

5.2 Gaseous Effluent Instrumentation Setpoints Technical Specification 3.3.3.10 requires that the radioactive gaseous effluent instrumentation in Table 3.3-13 of the Technical Specifications have their alarm setpoints set to insure that Technical Specification 3.11.2.1 is not exceeded.

5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528-1,2 and 3)

The plant vent wide-range gas monitors are shown on Figure B.6-2.

5.2.1.1 Method to Determine the Setpoint of the Plant Vent Wide Range Gas Monitors (RM-6528-1.2 and 3)

The maximum allowable setpoint for the plant vent wide-range gas i

monitor (readout response in pC1/sec) is set by limiting the off-site noble gas dose rate to the total body or to the skin, and is denoted R setpoint*

setpoint is the lesser of:

R R - 588 tb 0FB c

mr 3 pCi-sec ' I pCl-yr}

pC1/sec - (yrem-pCi-m 3 mrem-m and:

R skin - 3,000 0 5-6) pC1/sec - ("#'*) pCi yr yr (mrem sec) where:

R tb - Response of the monitor at the limiting total body dose rate (pC1/sec) 500 3 588 -

(mrem-uC1-m )

(1E+06) yr-pCi-sec (8.5E-07) 8666R B.5-9 ODCH Rev. 7

l l

i 500 = Limiting total body dose rate (mrem /yr) i e i 1E+06 = Number of pCl per pC1 (pCi/pCl) '

8.5E-07 = [X/QF, maximum off-site long-term average gamma atmospheric dispersion factor for primary vent stack releases (sec/m3 )

DFB e = Composite total body dose factor (mrem-m3 /pC1-yr) hj DFB, I

=

(5-7) hj i

Qg = The release rate of noble gas "1" in the mixture, for each noble gas identified in the off-gas (pC1/sec)

DFB g - Total body dose factor (see Table B.1-10) (mrem-m3 /pCl-yr)

R skin = Response of the monitor at the limiting skin dose rate (pC1/sec) 3,000 = Limiting skin dose rate (mrem /yr)

DF' = Composite skin dose factor (mrem-sec/pC1-yr) hi 0Fj I

(5-8) hg 1

0Fj - Combined skin dose factor (see Table B.1-10)

(mrem-sec/pCl-yr) l B.5-10 -

8686R 00CM Rev. 7

5.2.1.2 Plant Vent Wide Range Gas Monitor Setpoint Example The following setpoint example for the plant vent wide range gas monitors demonstrates the use of equations 5-5 and 5-6 for determining setpoints.

This setpoint example is based on the following data (see Table B.1-10 for DFBg and DFg ):

bg DFB g DFj 3

j (fCl) sec (mrem-m DCi-yr ) (mrem-sec) uCi-yr Xe-138 1.03E+04 8.83E-03 1.20E-02 Kr-87 4.73E+02 5.92E-03 1.38E-02 Kr-88 2.57E+02 1.47E-02 1.62E-02 Kr-85m 1.20E+02 1.17E-03 2.35E-03 Xe-135 3.70E+02 1.81E-03 3.33E-03 Xe-133 1.97E+01 2.94E-04 5.83E-04 h gDFB, I

DFB -

, (5-7)

Q9 1

hgDFB, - (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E-03) 1

+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)

+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) 3

- 9.83E+01 (pCi-mrem-m /sec-pCi-yr) hg - 1.03E+04 + 4.73E+02 + 2.57E+02 i

B.5-11 8686R ODCH Rev. 7

+

1.20E+02 + 3.70E+02 + 1.97E+01 e

= 1.15E+04 pC1/sec e

DFB -

9.83E+01 c 1.15E+04 3

- 8.52E-03 (mrem-m /pCl-yr) l Rtb = 588 DF8 (5-5)

- (588)

(8.52E-03) 6.90E+04 pC1/sec and next:

hg DFj DF' =

(5-8) bg i

hj DFj - (1.03E+04)(1.20E-02) + (4.73E+02)(1.38E-02) 1

+ (2.57E+02)(1.62E-02) + (1.20E+02)(2.35E-03)

+ (3.70E+02)(3.33E-03) + (1.97E+01)(6.83E-04)

= 1.38E+02 (pCl-mrem-sec/sec-pCl-yr) '

DF.

1.36E+02 g = 1.15E+04

- 1.18E-02 (arem-sec/pCl-yr)

Rskin - 3,000 0 5-6)

B.5-12 8686R ODCH Rev. 7

- (3,000)

(1.18E-02)

- 2.54E+05 pC1/sec The setpoint, Rsetpoint, is the lesser of R tb and R For the noble gas mixture in this example R skin.

tb is less than Rskin, indicating that the total body dose rate is more restrictive. Therefore, in this example the plant vent wide-range gas monitors should each be set at no more than 6.90E+04 pCi/sec above background, or at some administrative fraction of the above value.

In the event that no activity is expected to be released, or can be measured in the system to be vented, the gaseous monitor setpoint snould be based on Xe-133.

4 i

I I

l 2

B.5-13 8686R ODCM Rev. 7

6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWASTE TREATMENT SYSTEr45 Figure B.6-1 shows the liquid effluent streams, radiation monitors and the appropriate Liquid Radwaste Treatment System. Figure.B.6-2 shows the gaseous effluent streams, radiation monitors and the appropriate Gaseous Radwaste Treatment System. i For nore detailed information concerning the above, refer to the

. Seabrook Station Final Safety Analysis Report, Sections 11.2 (Liquid Waste System), 11.3 (Gaseous Waste System) and 11.5 (Process and Effluent Radiological Monitoring and Sampling System).

The turbine gland seal condenser exhaust is an unmonitored release path. The lodine and particulate gaseous releases will be determined by continuously sampling the turbine gland seal condenser exhaust. The noble gas releases will be determined by the noble gas released via the main condenser air evacuation exhaust and ratioing them to the turbine gland seal condenser exhaust by use of the flow rates. l l

l l

l B.6-1 8687R ODN Rn. 4

. l

O n MAKEUP STORAGE UNIT TANK PAB g e bh; E a

y-c "e e E-

@ _g -

g .. . )

<-- >; = '

1

, i l = .. . . ~ :- l =

1

.= ,

8

=

" I I

3 1 e i "

e'- i

-G ;

sysrau I l :

I d I

<ss > """

4- > l o ,. =.um. - o---

@ *==,m , @ = == m ..

=. .'.'"l"".,l=?.

Twent R.DS SunsP gewit. m.,t. fvs?IW ,

FIGURE B.6-1 Liquid Effluent Streams, Radiation Monitors, and Radwaste' Treatment System at Seabrook Station 8687R ODW Rev. 8

u e um CONTAINMENT " E E"*'"' ' cuRwo wocomo M00EONLY)

BUILDING VENTILATORS TVR8ht t ii VACUUM 37E4y SUILDhG { l l puup AE4CTOR GENERATOR EFFLUENT VACUUM TURe*E cou0ENSER

" ~

E l

/

CI GH3= ; !-[-

v v .

CONTAN MENT PURGE AIR

] l ans O

SLOWCOWN FLASM TANK 00 SASEOUS WASTE PROCESSho SYSTEM

[

d' W

TYPICAL OF THREE -", waste supuso Vsps? 4A

<* if j~

Y r p 'N I AFTER

" C00 lek l oRygR

. &.=m CHARCOAL SEDS '

l t COMPRESSOR 4

I ppuMARY l PRIMARY AUXIUARY aume VENT ,

SUILDm6 STACK

[\

]Q

- * ,uft -

7 SUILDmo N~b v U L. U AUXSJARY SUS.DMG VENT Am = w L10ENO , 7 C M . SEPA PLTER C . CHAACOAL FILTER RM . MADETION MONITOR FIGURE B.6-2 Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6-3 8687R ,

ODCM Rev. 8

_ _ _ _ _ . . ~ _-_ __.__.- . . _ _ _ _ _ _ . _ _ _ _. _ _ _ _ _ . .

7.0 BASES FOR DOSE CALCULATION METHODS 7.1 Liould Release Dose Calculations This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.

He'.had I may be used to show that the Technical Specifications which limit off-s'te total body dose from liquids (3.11.1.2 and 3.11.1.3) have been met for relenses over the appropriate periods. The quarterly and annual dose limits in Technical Specification 3.11.1.2 are based on the ALARA design objectives in 10CFR50, Appendix I Subsection II A. The minimum dose values noted in Technical Specification 3.11.1.3 are " appropriate fractions " as determined by the NRC, of the design objective to ensure that radwaste equipment is used as required to keep off-site doses AIARA.

Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I). The definition, below, of a single " critical receptor" (a hypothetical or real individual whose behavior results in a maximum potential dose) provides part of the conservative margin to the calculation of total body dose in Method I. Method II allows that actual individuals, associated with identifiable exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method II analysis for a critical receptor a'ssuming all principal pathways present instead of any real individual. That analysis was called the " base case:" it was then reduced to form Method I. The general equations used in the base case analysis are also used as the starting point in Method !! evaluations. The base case, the method of reduction, and the assumptions and data used are presented below.

The steps performed in the Meth0d I derivation follow. First, the dose impact to the critical receptor (in tte form of dose factors DFLith (mres/pC1)] for a unit activity release of each radioisotope in liquid effluents was derived. The base case analysis uses the general equations, methods, data and assumptions in Regulatory Guide 1.109 (Equations A-3 and A 7, Reference A). The liquid pathways contributing to an individual dose are due to consumption of fish and invertebrates, shoreline activities, and swimming and boating near the discharge point. A normal operating plant discharge flow rate of 918 ft /sec 3 was used with a mixing ratio of 0.10. The unar B.7-1 ODCM Rev. 12

A i--r -. 6 4,e-.,-- ---- - A --A b- -sA ---- - - - - - - - - + --==-hL m-J mixing ratio of 0.10 corresponds to the minimum expected prompt dilution or near field mixing zone created at the ccean surface directly above the multiport diffusers. (Credit for additional dilution to the outer edge of the prompt mixing zone which corresponds to the 1*F surface isotherm (mixing ratio

.025) can be applied in the Method 11 calculation for shoreline exposures oniy since the edge of this isotherm typically does not reach the shoreline receptor points during the tidal cycle. The mixing ratio for equatic food pathways in Method II assessments shall be limited to the same value (0.10) as applied in Method I for near-field mixing, or prompt dilution only.

The requirements for the determination of radiological impacts resulting from releases in liquid effluents is derived from 10CFR50. Appendix 1.

Section III.A.2 of Appendix I indicates that in making the assessment of doses to hypothetical receptors. "The Applicant may take account of any real phenomenon or factors actually affecting the estimate of radiation exposure.

including the characteristics of the plant modes of discharge of radioactive materials physical processes tending to attenuate the quantity of radioactive material to which an individual would be exposed, and the effects of averaging exposures over time during which determining factors may fluctuate." In ,

accessing the liquid exposure pathways that characterize Seabrook Station, the design and physical location of the Circulating Water Discharge System needs to be considered within the scope of Appendix I.

Seabrook utilizes an offshore submerged multiport diffuser discharger for rapid dissipation and mixing of thermal effluents in the ocean environment. The 22-port diffuser section of the Discharge System is located in approximately 50 to 60 feet of water with each nozzle 7 to 10 feet above the sea f'loor. Water is discharged in a generally eastward direction away from the shoreline through the multiport diffuser, beginning at a location over one mile cue east of Hampton Harbor inlet. This arrangement effectively prevents the discharge plume (at least to the 1 degree or 40 to 1 dilution isopleth) from impacting the shoreline over the tidal cycle.

Eleven riser shafts with two diffuser nozzles each form the diffuser and are spaced about 100 feet apart over a distance of about 1.000 feet. The diffusers are designed to maintain a high exit velocity of about 7.5 feet per second during power operations. Each nozzle is angled approximately 20 degrees up from the horizontal plane to prevent bottom scour. These high velocity jets passively entrain about ten volumes of fresh ocean water into the near field jet mixing region before the plume reaches the water surface.

This factor of 10 mixing occurs in a very narrow zone of less than 300 feet unir B.7-2 ODCM Rev. 12

1 l

l l

I j from the diffuser by the time the thermally buoyant plume reaches the ocean surface. This high rate of dilution occurs within about 70 seconds of discharge from the diffuser nozzles, i

! The design of the multiport diffuser to achieve a 10 to 1 dilution in j the near field jet plume, and a 40 to 1 dilution in the near mixing zone

associated with the 1 degree isotherm, has been verified by physical model i

tests (reference " Hydrothermal Studies of Bifurcated Diffuser Nozzles and j Thermal Backwashing - Seabrook Station," Alden Research Laboratories, 4 July 1977).

b l During shutdown periods, when the plant only requires service water

cooling flow, the high velocity jet mixing created by the normal circulating i water flow at the diffuser nozzles is reduced. However, mixing within the I

discharge tunnel water volume is significantly increased (factor of about 5) j due to the long transit time (approximately 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months ) for batch waste

discharged from the plant to travel the three miles through the 19-foot i diameter tunnels to the diffuser nozzles. Additional mixing of the thermally l buoyant effluent in the near field mixing zone assures that an equivalent

overall 10 to 1 dilution occurs by the time the plume reaches the ocean surface.

l

[ The dose assessment models utilized in the ODCM are taken from NRC Regulatory Guide 1.109. The liquid pathway equations include a parameter (M,)

to account for the mixing ratio (reciprocal of the dilution factor) of effluents in the environment at the point of exposure. Table 1, in Regulatory Guide 1.109r, defines the point of exposure to be the location that is articipate'd to be occupied during plant lifetime, or have potential land and water usage and food pathways as could actually exist during t:te term of plant operation. For Seabrook, the potable water and land irrigation pathways do not exist since saltwater is used as the receiving water body for the circulating water discharge. The three pathways that have been factored into the assessment models are shoreline exposures, ingestion of invertebrates, and fish ingestion.

With respect to shoreline exposures, both the mixing ratios of 0.1 and 0.025 are extremely conservative since the effluent plume which is discharged over one mile offshore never reaches the beach where this type of exposure could occur. Similarly, bottom dwelling invertebrates, either taken from mud flats near the shoreline or from the area of diffuser, are not exposed to the undiluted effluent plume. The shore area is beyond the reach of the surface unsi B.7-3 ODCM Rev. 12 i

i

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

plume of the discharge, and the design of the upward directed discharge nozzles along with the thermal buoyancy of the effluent, force the plume to quickly rise to the surface without affecting bottom organisms.

Consequentially, the only assumed exposure pathway which might be impacted by the near field plume of the circulating water discharge is finfish. However, the mixing ratio of 0.1 is very conservative because fish will avoid both the high exit velocity provided by the discharge nozzles and i the high thermal temperature difference between the water discharged from the diffuser and the ambient water temperature in the near field. In addition, the dilution factor of 10 is achieved within 70 seconds of discharge and j confined to a very small area, thus prohibiting any significant quantity of ]

fish from reaching equilibrium conditions with radioactivity concentrations !

created in the water environment. l The mixing ratio of 0.025, which corresponds to the 1 degree thermal near field mixing zone, is a more realistic assessment of the dilution to which finfish might be exposed. However, even this dilution credit is conservative since it neglects the plant's operational design which discharges radioactivity by batch mode. Batch discharges are on the order of only a few hours in duration several times per week and, thus, the maximum discharge concentrations are not maintained in the environment long enough to allow fish to reach equilibrium uptake concentrations as assumed in the dose assessment modeling. Not withstanding the above expected dilution credit afforded at the 1 degree isotherm, all Method II aquatic food pathway dose calculations shall conservatively assume credit for prompt dilution only with an M, = 0.10. When ;

dose impacts from the fish and invertebrate pathways are then added to the conservative dose impacts derived for shoreline exposures, the total I calculated dose is very unlikely to have underestimated the exposure to any real individual.

The recommended value for dilution of 1.0 given in NUREG 0133 is a simplistic assumption provided so that a single model could be used with any plant design and physical discharge arrangement. For plants that utilize a !

surface canal-type discharge structure where little entrainment mixing in the ;

environment occurs, a dilution factor of 1.0 is a reasonable assumption, '

However, in keeping with the guidance provided in Appendix I to 10CFR50, Seabrook has determine site-specific mixing ratios which factor in its plant ,

design. !

amn B.7-4 ODCM Rev. 12

1 l

The transit time used for the aquatic food pathway was 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and for shoreline activity 0.0 hours0 days 0 hours 0 weeks 0 months . Table B.7-1 outlines the human consumption and use factors used in the analysis. The resulting. site-specific total body dose factors appear in Table B.1-11. Appendix A provides an example of the j development of a Method I liquid dose conversion factor for site-specific !

conditions at Seabrook.

7.1.1 Dose to the Total Body l For any liquid release, during any period, the increment in total body dose from radionuclide "1" is: l ADtb - k Os DFLith (mrem) () (pCi) ""

$K (7-1) where:

DFL ith - Site-specific total body dose factor (mrem / Ci) for a liquid release. It is the highest of the four age groups. See Table B.1-11.

O, = Total activity ( Ci) released for radionuclide "i".

K = 918/Fd (dimensionless); where Fd is the average dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3/sec).

Method I is more conservative than Method II in the region of the Technical Specification limits because the dose factors DFL ith used in Method I were chosen for the base case to be the highest of the four age groups (adult, teen, child and infant) for that radionuclide. In effect each ;

radionuclide is conservatively represented by its own critical age group. I 7.1.2 Dose to the Critical Oroan The methods to calculate maximum organ dose parallel to the total body I dose methods (see Section 7.1.1).

unst B.7 5 ODCM Rev. 12

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

For each radionuclide, a dose factor (mrem / C1) was determined for each

of seven organs and four age groups. The largest of these was chosen to be the maximum organ dose factor (DFLi ,,) for that radionuclide. DFL i .,also includes the external dose contribution to the critical organ.

For any liquid release, during any period, the increment in dose from radionuclide "i" to the maximum organ is:

AD , - k Oi DFli .,

I7'2)

(mrem) () (pC1) ' mrem' pC1 l s ,

l 1

where: l DFL i , - Site-specific maximum organ dose factor (mrem / C1) for a liquid I release. See Table 8.1-11. l l

Oi - Total activity (gC1) released for radionuclide "i". ;

K - 918/Fd (dimensionless); where Fd is the average dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3 /sec).

i l

anur B.7-6 ODCH Rev. 12

TABLE B.7-1 Usage Factors for Various Liould Pathways at Seabrook Station (From Reference A. fable E-5*. except as noted. Zero where no pathway exists)

AGE VEG. LEAFY MILK MEAT FISH INVERT. POTABLE SHORELINE SWIMMING ** BOATING **

VEG. WATER (KG/YR) (KG/YR) (LITER /YR) (KG/YR) (K6/YR) (KG/YR) (LITER /YR) (HR/YR) (HR/YR) (HR/YR)

Adult 0.00 0.00 0.00 0.00 21.00 5.00 0.00 334.00*** 8.00 52.00 Teen 0.00 0.00 0.00 0.00 16.00 3.80 0.00 67.00 45.00 52.00 Child 0.00 0.00 0.00 0.00 6.90 1.70 0.00 14.00 28.00 29.00 Infant 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

Regulatory Guide 1.109.

- HERMES: "A Digital Computer Code for Estimating Regional Radiological Effects from Nuclear Power Industry." HEDL.

December 1971. Note, for Method 11 analyses, these pathways need not be evaluated since they represent only a small fraction of the total dose contribution associated with the other pathways.

- - Regional shoreline use associated with mudflats - Maine Yankee Atomic Power Station Environmental Report.

uner B.7-7 ODCM Rev. 12

7.2 Gaseous Release Dose Calculations ('

7.2.1 Total Body Dose Rate From Noble Gases This section serves: (1) to document the development of the Method I equation (2) to provide background information to Method I users, and (3) to I

identify the general equations, parameters and approaches to Method II-type dose rate assessments.

Method I may be used to show that the Technical Specification which i limits total body dose rate from noble gases released to the atmosphere 1

(Technical Specification 3.11.2.1) has been met for the peak noble gas release rate.

Method I was derived from general equation B-8 in Regulatory Guide l.109 as follows:

l b tb - 1E+06 [X/0]T h 0, DFB, (7-3) 1 I

e , t

l l 'arem' 'pCi' sec [pCf' mrem-m 3

t yr , (W, m3 ,(sec , pCi-yr ,

1 l where: ,

[X/0 7 = Maximum off-site receptor location long term average gamma atmospheric dispersion factor.

I i

6, = Release rate to the environment of noble gas "i" (pCi/sec).

DFB, = Gamma total body dose factor, mrem-e 3 . See Table B.1-10.

pCi-yr ,

(Regulatory Guide 1.109. Table B 1).

l Elevated and ground level gaseous effluent release points are addressed l

l separately through the use of specific (X/0]y. For an elevated gaseous l effluent release point and off-site receptor Equation 7-3 take;. the form:

amar B.7-8 ODCM Rev. 14

l Osb(e) - (1E+06) * (8.5E-07)

E (0g

DFBg) i r 3 e ,

' mrem' ,'pCi' , sec ,p pCi , mrem m 3 yr , pCi s m3 , s sec pC1 -yr ,

which reduces to:

6tb(e) = 0.85

E (Og

DFBg) (3-3a) 1 r 3 f i

' mrem' pCi-sec 'nCi ' mrem-m 3 g ,

, yr s Ci-m3 ,

,sec, pCi-yr ,

For a ground level gaseous effluent release point and off-site receptor.

Equation 7-3 takes the form:

6tt>(s) = (1E+06) * (3.4E-06)

E (0g

DFBq) 1 which reduces to:

l Otb(g) = 3.4

E (Og

DFBg )

' ' ' \

' mrem' ,rpCi-sec 'pCi ' mrem-m 3 (3-3b) '

p ,

t yr s Ci-m 3 , s sec, pCi-yr ,

The selection of critical receptor, outlined in Section 7.3 is inherent in the derived Method I, since the maximum expected off site long-term average

, l atmospheric dispersion factor is used. The sum of doses from both plant vent l stack and ground level releases must be considered for determination of Technical Specification compliance. Ali noble gases in Table B.1-10 should be considered.

A Method 11 analysis could include the use of actual concurrent meteorology to assess the dose rates as the result of a specific release.

unar B.7-9 ODCH Rev. 14

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

7.2.2 Skin Dose Rate From Noble Gases This section serves: (1) to document the development of the Method I equation (2) to provide background information to Method I users, and (3) to identify the general equations parameters and approaches to Method II-type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Only the differences are ,

presented here.

Method I may be used to show that the Technical Specification which limits skin dose rate from noble gases released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak noble gas release rate.

The annual skin dose limit is 3.000 mrem (from NBS Handbook 69.

Reference D, pages 5 and 6. is 30 rem /10). The factor of 10 reduction is to account for nonoccupational dose limits.

It is the skin dose commitment to the critical, or most limiting, off-site receptor assuming long-term site average meteorology and that the i release rate reading remains constant over the entire year. ;

l Method I was derived from the general equation B 9 in Regulatory :

Guide 1.109 as follows:

D s = 1.110}i, + 3.17E+04 Ef 0 [X/0]'DFS 1 i (7-4) e 3 r 3

'arem ' , ' mrem ' ' mrad ' 'pci-yr ' Ci see mrem-a 3 yr , mrad , , yr , ,Ci-sec , 37 m 3

, t pCi-yr ,

where:

1.11 - Average ratio of tissue to air absorption coefficients (will convert mrad in air to mrem in tissue).

DFS, = Beta skin dose factor for a semi-infinite cloud of radionuclide "i" which includes the attenuation by the outer

" dead" layer of the skin.

einer B.7-10 00CM Rev. 14

Dji, -

3.17E+04 E 0 [X/0] DFgY (7-5) s f %

' mrad ' ,

'pci -yr ' Ci mea d-<n 3

, yr , ,Ci-sec , (7)(sec) m3 ( pCi -y r ,

DF[

=

Gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i".

Now it is assumed for the definition of (X/07) from Reference 8 that:

DJ4,jt, - Dj,, [X/0]T/[X/0) (7-6) 1 8 l

'mra d ' , 'mra d ' sec m3

, yr , , yr j m3 , s sec, and 0 = 31.54 0, (7-7)

'C i ' , 'Ci -s ec ' 'pCi '

J7, Ci-yr , ,sec ,

so:

7 (7-8) 0,ign - 1.111E+06 [X/0]7 E og DF 1 i !

< 8

' mrem ', ' mrem ' 'pCi ' sec 'pCi ' mead-m 3 yr , , mrad,y7; m 3

,sec , , pci-yr ,

+1E+06 X/0 E 0, DFSg i

e 3

'pCi ' sec 'pci ' mrem-<n 3

,W , m 3 g sec,,

pC i -y r ,

1 l

caer 8.7-11 ODCM Rev. 14 i

r" l Substituting atmospheric dispersion factors for an elevated gaseous l effluent release point, Equation 7-8 takes the following form:

l l Dsting.3 = [1.11

IE+06

8.5E-07

E (Og

DF[)] + [1E+06

8.2E 07

E (Og

DFSg)]

1 1 l

l which yields:

I

! 03 gg c,3 = [0.94 E (Og

DF[)] + [0.82 E (Qt

DFS$ )] (7 4a)

' r

'

r 3 3 ypCi-sec mrem 3

' mrem' , p pCi , mrem m , pCi-sec p Ci , mrem m 3 5

yr s 3

Ci-m -mrad , (sec pCi-yr s pC1-m 3 (sec pCi-yr ,

I l defining:

I l DFg 'g,3 = 0.94 DF[ + 0.82 DFSg (7-10a) l Then the off-site skin dose rate equation for an elevated gaseous l effluent release point is:

I l

(3-4a) bskin(e) = E Og

DF ig ,3 1

' mrem'

, p 'kCi , mrem sec '

g yr , sec pCi-yr ,

l For an off-site receptor and a ground level gaseous effluent release l point. Equation 7-8 becomes:

I l Osts,c,3 = [1.11 1E+06 3.4E-06*E (Og *DF[)] + [1E+06 1.0E-05+E (Og *DFSg )]

t l which yields:

l I

es tgng,3 = [3.8 E (Og

DFI)] + [10 E (Oi

DFS,)]

1 i

-EOi [3.8 DF[ + 10 DFSg]

uzw B.7-12 ODCH Rev. 14

l defining:

l l DF,'g,3 = 3.8 DF[ + 10 DFS i (7-10b) l l Then the off-site skin dose rate equation for ground level g&seous l effluent release points is:

l l Ostin(g) = Og e DFjg,3 (3-4b)

The selection of critical receptor, outlined in Section 7.3, is inherent in the derived Method I as it is based on the determined maximum expected off-site atmospheric dispersion factors. All noble gases in Table B.1-10 must be considered.

7.2.3 Critical Orcan 00se Rate From Iodines. Tritium and Particulates With Half-Lives Greater Than Eight Days This section serves: (1) to document the development of the Method I equation. (2) to provide background information to Method I users, and (3) to identify the general equation's parameters and approached to Method II type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1.

Method I may be used to show that the Technical Specification which limits orgfn dose rate from iodines, tritium and radionuclides in particulate form with half liv.ts greater than 8 days released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak above mentioned release rates. The annual organ dose limit is 1500 mrem (from NBS Handbook 69.

Reference D, pages 5 and 6). It is evaluated by looking at the critical organ dose consnitment to the most limiting off-site receptor assuming long term site average meteorology.

l The equation for De , is derived from a form of Equation 3 8 in l Section 3.9 by applying the conversion factor, 3.154E+07 (sec/yr) and l converting 0 to 6 in pCi/sec:

I

)

l i

uru7 B.7-13 ODCM Rev.14

i r

I De, = 3.15E+07

E (0g DFGje ) (7-12) 1

' mrem' ,'sec' 'pCl' ,' mrem' ,

yr , yr , ,s e c j Ci ,

l Equation 7-12 is rewritten in the form:

De , = E (0 i* DFGje,)

Ma) 1

' ares ' ,p 'pci ' , 'arem-sec ' ,

yr j ,sec, , pCi -y r ,

where:

DFGi 'e, = 3.154E+07 e DFGje, UE

' mrem-sec ' 'sec'* 'arem' pCi -y r , " , y r , K, l The dose conversion factor, DFGje,, has been developed for both elevated l gaseous effluent release points and ground level gaseous effluent release l points (DFGje,g,3 and DFGje,gg3), respectively. These dose factors are used to l determine accumulated doses over extended periods and have been calculated l with the Shielding Factor (SF) for ground plane exposure set equal to 0.7, as l referenced ,1,n Regulatory Guide 1.109. In the case of the dose rate conversion l

l factors (DF.G' geog,3 and DFG'ie g,3), the dose conversion factors from which they l were derived were calculated with the Shielding Factor (SF) for ground plane l exposure set equal to 1.0. '

For an off-site receptor and elevated effluent release point, the critical organ dose rate equation is:

Oc ,g,3 = E (0, e DFG'ic g,3) (3-Sa) l 1

' mrem '

,p 'pci , mrem-sec '

yr , sec pCi -y r j For an off-site receptor and ground level effluent release point, the critical organ dose rate equation is: I l

um B.7-14 ODCM Rev. 14 1

l

.__ _ . _ . _ _ . _ _ _ _ . . _ = _ _ . _ ._ _ _._. _ . ~ . . _ _ . _ . __ . __ _ _ _ . _

i i

i

! l Ocots) = E (Qi = O FG'$ e g,3 ) (3-5b) t

' mrem ', 'pCi , mrem-sec '

yr , sec pCi -y r ,

i The selection of critical receptor, outlined in Section 7.3 is inherent i in Method I, as are the expected atmospheric dispersion factors.

In accordance with the Basis Statement 3/4.11.2.1 in NUREG-0472 and the d

base's section for the organ dose rate limit given for Technical Specification i 3.11.2.1, a Method II dose rate calculation, for compliance purposes, can be l based on restricting the inhalation pathway to a child's thyroid to less than 4 or equal to 1,500 mrem /yr. Concurrent meteorology with time of release may l also be used to assess compliance for a Method II calculation.

i j 7.2.4 Gamma Dose to Air From Noble Gases This section serves: (1) to document the development and conservative

! nature of Method I equations to provide background information to Method I I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.

Method I may be used to show that the Technical Specification 3.11.2.2 l l which limits off-site gamma air dose from gaseous effluents has been met for l releases over appropriate periods. This Technical Specification is based on j the objectiye in 10CFR50, Appendix 1. Subsection B.1, which limits the i estimated gamma air dose in off-site unrestricted areas.

NUREG/CR-2919 presents a methodology for determining atmospheric l dispersion factors (CHI /O values) for intermittent releases at user specified j receptor locations (intermittent releases being defined as releases with j durations between 1 and 8.760 hours0.0088 days 0.211 hours 0.00126 weeks 2.8918e-4 months ). The CHI /O values for intermittent j releases are determined by linearly interpolating (on a log-log basis) between j an hourly 15-percentile CHI /O value and an annual average CHI /O value as a j function of. release duration. This methodology has been adopted to produce a

} ret of time-dependent atmospheric dispersion factors for Method I calculations.

i For any noble gas release, in any. period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109 with the added assumption j that 0}htu - DY [X/0]Y/[X/0):

I ames B.7-15 ODCM Rev.14 1

1 4

ADl$r = 3.17E+4 [X/0]7 E Oi DF[

1

, , - 3 (7-14)

'pC I-y r ' sec mrad-m 3 (mrad) = (C1)

,Ci-sec, m 3 g pC i -y r ,

where:

(

3.17E+04 - Number of pCi per Ci divided by the number of seconds per year.

[X/Q]Y =

Annual average gamma atmospheric dispersion factor for the receptor location of interest.

Oi -

Number of curies of noble gas "i" released.

=

DF} Gamma air dose factor for a uniform semi-infinite cloud of radionuclide "1".

l Incorporating a unitiess release duration adjustment term t** (where "a" l is a constant and "t" is the total release duration in hours). and the conversion factor for Ci to kCi (to accommodate the use of a release rate 0 in pC1), and substituting the 1-hour gamma atmospheric dispersion factor in place of the annual average gamma atmospheric dispersion factor in Equation 7-14 leads to:

D}i, = 3.17E-02 e [X/Q]}hr

t d .Ei 0, e DFJ (3-6) r 3 f i sec 3 (mrad) = ' p C i -y r '

pCi-sec s m3

E Ci

mrad-m pCi-yr ,

, s For an elevated release. the equation used for an off-site receptor is:

f i l D a 7g r(e) = 3.17E-42 * [1.0E-05]

t-o.275 E 1 \

Oi e DF{s i

unir B.7-16 ODCM Rev.14 l i

l 1

l

l wt.fch leads to:

(3-6a)

DJg,g 3 - 3.2E-07

t4.275

E Qg

DF[

i f '

e 8 pCi-yr mead-m3 (mrad) = e pCi e 3

pC i -e , , pCi-yr ,

For a ground-level release, the equation used for an off-site receptor is:

f i 7

l 0,g r(g) - 3.17E-02 = [4.9E-05]

t-o.293 . E 0,

DFf i t s which leads to:

l (3-6b)

DJg,c,3 - 1.6E-06

t-4.293

E 0,

DFl t

, f '

e pCi-yr 3 (mrad) =

gCi e mrad-m 3

pCi-m , t pCi-yr ,

The major difference between Method I and Method II is that Method II would use actual or concurrent meteorology with a specific noble gas release spectrum to determine [X/0F rather than use the site's long-term average meteorological dispersion values.

7.2.5 Bet ~a Dose to Air From Noble Gases This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.

Method I may be used to show that Technical Specification 3.11.2.2, which limits off-site beta air dose from gaseous effluents, has been met for releases over appropriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated beta air dose in off-site unrestricted area locations.

For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109:

uns B.7 17 ODCM Rev. 14 l

l

)

\

ADfs, - 3.17E-02 X/0 E 05 DFf 1

1

, r 3 (7-15) l

' pCi-yr ' f sec mrad-m3 (mrad) = ( C1)

,pci-s ec j m3 ,

g pCi-yr ,

where:

DF{ = 8 eta air dose factors for a uniform semi-infinite cloud of l radionuclide "i".

Incorporating the term t into Equation 7-15 leads to:

l Dfi, - 3.17E-02 e X/0

t **

E 1 0:

DFf (3-7) t r i i (mrad) = ' pci-yr ' sec Ci e mrad-e3

,pci -s ec ,

ma

.()*E pCi -yr j i

Where X/Q = average 1-hour undepleted atmospheric dispersion factor.

For an elevated release, the equation used for an off site receptor is:

l Dfi,g 3 - 3.17E-02 e 1.3E-05

t43*E10g*DFf I 1 I

. 1 e 3 r 3 l sec (mrad) = ' p C i -y r ' pCi e mrad-m3 I

, *()*

( C1 -sec j m3 ,

, pCi-yr ,

which leads to:

Ofirg,3 - 4.1E-07

t43*E 0

DFf (3-7a) t r 3 f i pCi-yr mrad-m 3 (mrad) - *

()*E Ci e 3

pCi-m , s pCi-yr ,

For a ground-level release, the equation used for an off-site receptor is:

unst B.7-18 ODCM Rev. 14 l

! Oficc,3 - 3.17E-02 1.9E-04

t'0 318

E 0,

DFf (mrad) =

' pci-yr ' sec gCi e mrad-<n 3

(

pCi-sec j m 3 e() E g pC1-yr , l which leads to: l l Ofi,g,3 - 6.0E-06 e t-8 31'

E 0, e DFf (3-7b) t e 3 pCi-y r pCi e mra d-<n3 (mrad) = *

()*E 3

nCi-4n , s pC1-yr ,

7.2.6 Dose to Critical Orcan From Iodines. Tritium and Particulates With Half-Lives Greater Than Eiaht Days This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.

Method I may be used to show that the Technical Specifications which limit off-site organ dose from gases (3.11.2.3 and 3.11.4) have been met for releases over the appropriate periods. Technical Specification 3.11.2.3 is based on the ALARA objectives in 10CFR50, Appendix I, Subsection II C.

Technical $pecification 3.11.4 is based on Environmental Standards for Uranium Fuel Cycle in 40CFR190, which applies to direct radiation as well as liquid and gaseous effluents. These methods apply only to iodine, tritium, and particulates in gaseous effluent contribution.

Method I was developed such that "the actual exposure of an j individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix !). The use below of a single " critical receptor" provides part of I the conservative margin to the calculation of critical organ dose in Method I.

l Method II allows that actual individuals, associated with identifiable v exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method II analysis of a critical receptor assuming all j pathways present. That analysis was called the " base case *: it was then reduced to form Method I. The base case, the method of reduction, and the l assumptions and data used are presented below.

i 1

5 amo B.7-19 ODCM Rev.14 a

I l

The steps performed in the Method I derivation follow. First, the dose ,

impact to the critical receptor (in the form of dose factors DFG3e , l (mrem /pCi)] for a unit activity release of each iodine, tritium, and particulate radionuclide with half lives greater than eight days to gaseous effluents was derived. Six exposure pathways (ground plane, inhalation. l stored vegetables, leafy vegetables, milk, and meat ingestion) were assumed to exist at the site boundary (not over water or marsh areas) which exhibited the highest long-term X/0. Doses were then calculated to six organs (bone, liver, kidney, lung, GI-LLI, and thyroid), as well as for the whole body and skin for 1 four age groups (adult, teenager, child, and infant) due to the seven combined exposure pathways. For each radionuclide, the highest dose per unit activity release for any organ (or whole body) and age group was then selected to become the Method I site-specific dose factors. The base case, or Method I analysis, uses the general equations methods, data, and assumptions in Regulatory Guide 1.109 (Equation C-2 for doses resulting from direct exposure

'to contaminated ground plane: Equation C-4 for doses associated with-inhalation of all radionuclides to different organs of individuals of different age groups: and Equation C-13 for doses to organs of individuals in different age groups resulting from ingestion of radionuclides in produce, milk, meat, and leafy vegetables in Reference A). Tables B.7-2 and B.7-3 outline human consumption and environmental parameters used in the analysis, it is conservatively assumed that the critical receptor lives at the ' maximum off-site atmospheric dispersion factor location" as defined in Section 7.3. .

The resulting site-specific dose factors are for the maximum organ which combine the limiting age group with the highest dose factor for any organ with each nuclide. These critical organ, critical age dose factors are given in Table B.1-12. Appendix A provides an example of the development of Method I gaseous dose conversion factor for site-specific conditions at Seabrook.

For any iodine, tritium, and particulate gas release, during any period, the increment in dose from radionuclide "1" is:

ADie , - OjDFGje, (7-16) where DFGje, is the critical dose factor for radionuclide "i" and 0, is the activity of radionuclide "1" released in microcuries.

Applying this information, it follows that the general form for the critical organ dose equation is:

ams B.7-20 ODCH Rev. 14 i

l

i w;

! D,, - (X/0)l'd /(X/0)!'[

t -* * (0,*DFGie ) (3 8) 8'C / 8'C "I'*

mrem =

3

+() e E pCi + W ,

m m3 -

u s u s Substituting specific values associated with the maximum off site receptor location and elevated release condition yields:

l Dco(e) - (1.12E-05)/(7.55E-07)

t-o.297 (Og

DFG ic ,g,3)

-. which reduces to:

?

, l De g,3 - 14.8

t4 .297 * (0,* DFG ic g,3) (3 8a)

For the maximum off-site receptor location and ground level release

- conditions. the equation is:

,, l D co(g) - (1.71E-04)/(9.64E-06) e t-8 31' . h (0, DFGicoto))

~

which reduces to:

l Deo g g 3 - 17. 7

t -o .316 * (Oi

OFGie g,3) (3-8b) 7.2,7 Special Receptor Gaseous Release Oose Calculations Technical Specification 6.8.1.4 requires that the doses to individuals involved in recreational activities within the site boundary are to be determined and reported in the annual Semiannual Effluent Report, f The gaseous dose calculations for the special receptors parallel the bases of the gaseous dose rates and doses in Sections 7.2.1 through 7.2.5.

Only the differences are presented here. The special receptor XOs are given in Table B.7 5.

7.2.7.1 Total Body Dose Rate From Noble Gases Method I was derived from Regulatory Guide 1.109 as follows:

amor B.7 21 ODCM Rev. 14 PL

Dtb - 1E46 (X/0F OgDFBs (7 3)

General Equation (7-3) is then multiplied by an Occupancy Factor (OF) to account for the time an individual will be at the on-site receptor locations during the year. There are two special receptor locations on site. The .

Rocks" is a boat landing area which provides access to Browns River and Hampton Harbor. The Seabrook FSAR, Chapter 2.1. indicates little boating activity in either Browns River or nearby Hunts Island Creek has been observed ..

upon which to determine maximum or conservative usage factors for this on-site shoreline location. As a result, a default value for shoreline activity as provided in Regulatory Guide 1.109. Table E 5 for maximum individuals was utilized for determining the " Rocks" occupancy factor. The 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months / year corresponds to the usage factor for a teenager involved in shoreline recreation. This is the highest usage factor of all four age groups listed in

? Regulatory Guide 1.109, and has been used in the ODCH to reflect the maximum usage level irrespective of age.

Regulatory Guide 1.109 does not provide a maximum individual usage

- _ factor .f.or_ activities similar to those which would be associated with tne Seabrook Education Center. Therefore, the usage factor used in the ODCH for the Education Center reflects the observed usage patterns of visitors to the ,

facility. Individuals in the public who walk in to look at the exhibits on display and pick up available information stay approximately 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months each.

Tour groups who schedule visits to the facility stay approximately 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

For conservatism it was assumed that an individual in a tour group would return five times in a year, and stay 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months on each visit. These assumptions, when multiplied together, provide the occupancy factor of 12.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months / year used in the ODCH for public activities associated with the Education Center.

g l For the Education Center, and the " Rocks", the occupancy factors (OFs) are:

12.5 hrs /yP' Education Center - - 0.0014 g 8760 hrs /yr U)

The " Rocks. , 67 hrs /yr = 0.0076

) 8760 hrs /yr r

o U3 Taken from Seabrook Station Technical Specifications (Figure 5.1-1).

amar B.7 22 e ? ,. ; c s

["

, 4 9 -

6 .

4

substituting in.the annual average gamma X/Os:

[X/0]7 - 1.1E-06 sec/m3 (Education Center) for primary vent stack i

releases, j

l

- 5.3E-06 secm3 (Education Center) for ground level releases.

- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases.

l

]

- 2.6E-05 sec/m3 (The " Rocks") for ground level releases.

l and multiplying by:

OF - 0.0014 (Education Center)

= 0.0076 (The " Rocks")

- gives:

OtbEce) = 0.0015 . E (0i

OFB,) (mrem /yr) (3-3c) 1 . .

Ottt<g) = 0.0074 . E (0,

OFBg) (mrem /yr) ( 3-3d) 1

, OsbR(e) = 0.038 . E (og OFBi ) (mrem /yr) (3-3e) 1 OtbR(g) = 0.2 (Os

DFBi ) (mrem /yr) (3-3 f) where:

l tbE(el' btbE(g)* b tbR(e), and h tbR(g) = total body dose rates to an

} individual at the Education Center l and the " Rocks" (recreational l site), respectively, due to noble j gases in an elevated (e) and ground

(( l level (g) release.

I

_ l 6, and DFB, are as defined previously.

,- 7.2.7.2 Skin Oose Rate From Noble G8ses I =i j- Method I was derived from Equation (7-8):

03 n, = 1.111E+06 [X/0]Y E Og 0FJ + (7 8) e t

{' 1E+06 X/0 E 0 DFS, t

"' B.7 23 00C Rev . --

J e

F

i l substituting in the annual average gamma X/Os: 1 (X/0]Y - 1.1E-06 sec/m3 (Education Center) for primary vent stack releases.

l - 5.3E-06 sec/m3 (Education Center) for ground level release l points.

- 5.0E 06 sec/m3 (The " Rocks") for primary vent stack releases.

l - 2.6E 05 sec/m3 (The " Rocks") for ground level release points. -

l and the annual average undepidted X/Os:

i 3 X/0 - 1.6E 06 sec/m3 (Education Center) for primary vent stack releases.

~

l - 2.3E-05 sec/m3 (Education Center) for ground level release points.

- 1.7E 05 sec/m3 (The ' Rocks") for primary vent stack releases.

l l - 1.6E 04 sec/m3 (The ' Rocks") for ground level release points.

l and multiplying by: ,

OF - 0.0014 (Education Center)

- 0.0076 (The " Rocks")

g':ves:

0 kingc.3 = 0.0014 E O i (1.22 0Fl + 1.60 0FS,] for an elevated release point.

t O

skinE(g) = 0.0014 E 0, (5.88 0FJ + 23 0FS,] for a ground level release point.

O stinat.3 = 0.0076 E 0, (5.55 0FJ + 17.0 0FS $ ) for an elevated release point.

t O

skinagg3 = 0.0076 E iD (28.9 0FJ + 160 0FSg] for a ground level release point.

l and the equations can be written:

~

1 OskinE(e) = 0.0014 . E (0, . DFigg 3) (3-4c) emu B.7 24 00CH Rev. 14

~

4 l Oskint(g) = 0.0014 E (0, e DF 1'I(g)) (3 4d) l 0,gingg,3 = 0.0076 . E (0, . DF i'at.1) (3-de) i l Ostinatal = 01076 . E (og

DF 'ag,3) i (3-4f) s where:

l 6,gingg,3, 6,gingg,3, 6:unate), and 6,gs,ng,3 - the skin dose ra'.e (mrem /yr)

[

to an individual at the l

' Education Center and the l

Rocks", respectively, due

, l to noble gases in an i elevated (e) and ground i level (g) release, 1

l 6, - defined previously, and I . , , ,

DJigg 3 DF iggg3. DFing,3and DFigg,3 l -

the combined skin dose factors for l radionuclide "1" for the Education l Center and the " Rocks",

i respectively, for elevated (e) and i ground level (g) release points l

(see Table 6.1-13).

7.2.7.3 Critical Oroan Dose Rate From lodines. Tritium and Particulates With Half-Lives Greater Than Eloht Days The equations for 6,, are derived in the same manner as in Section 7.2.2. except that the occupancy factors are also included. Therefore:

l OcoE(e) = 0.0014

E (0, e DFG'coE(e)) i for an el?vated release. (3 Sc) l O cottg> = 0.0014 . E (0, e DFGje,gg,3) for a ground level release. (3-5d) l Ocettel = 0.0076 E (0, e DFG',,gg,3) i for an elevated release. (3-Se) nasar B.7 S ODCH Rev. 14 c.

l Oc ag,3 = 0.0076 E (og . DFG,'c,gg,3) for a ground level release. (3 5f) where:

l b cot (e)* b cot (g)* b coR(e),

and 6 c,gg,3 a the critical organ dose rates j

(mrem /yr) to an individual at the l Education Center and the " Rocks",

l respectively, due to lodine, l tritium, and particulates in j

elevated (e) and ground level (g) l releases, l

_ l 6: = as defined previously, and I , ,

5 , ,

l DFGicotte) DFGicotts) DFGicoR(e), and DFGicente) = the critical organ dose rate l

factors for radionuclide "1"

[

for the Education Center and "l

the " Rocks", respectively, for

[

elevated (e) and ground level

[

(g) release points (see _

l

%, Tables B.1 14 and B.1 15).

7.2.7.4 Gamma Dose to Air From Noble Gases

~

Hethod I was derived from Equation (3 6):

l DJir - 3.17E-02 [X/0]}hr

t"

E (Os

DF )

6 (3 6) where all terms of the equation are as defined previously.

Incorporating the specific 0F and the atmospheric dispersion factor, the gamma air dose equation for the Education Center for elevated releases:

l Diggg,3 = 3.17E-02 1.1E-05 t 0.252 0.0014 . E (0, . DF[)

1 which reduces to:

unsi B.7-26 ODCM Rev. 14

~_mJ _

! i ~

i l D trEte) = 4.9E-10 e t c.252

E (Og e DF[) (3 6c) r s ! %

pCi-y r (mrad) - .( )*I gCI e mead-m3 3

,pCi m , s pCi-yr ,

For ground-level relatses, the gamma air dose equation for the Education Center becomes:

l 0ltr(Ets) - 3.17E-02 e 1.0E-04 t 0.321

0.0014 . E (0, e DF[)

~'

which reduces to:

t 5 Djirgg,3 = 4.4E-09 e t 0.321 E (Og

DFJ) l (3 6d) t f I i

pCi-yr 3 (mrad) ,

3

( )*I nCi , mrad-m

,pCl-m , 5 pCi-yr ,

incorporating the specific 0F and atmospheric dispersion factors for the

" Rocks

yields the gamma air dose equation for elevated releases:

l Olt,gg,3 - 3.17E-02 e 2.1E-05 e t *0*I55

0.0076 E (0,

OF[)

which reduces to:

l Dltrate) = 5.1E-09 e t 155 e (0, e DF[) (3 6e) pCi-yr 3 (mrad) =

3

( )*I Ci , mrad m

,pCi m , ( pC1 yr ,

For ground-level releases, the gamma air dose equation for the " Rocks" becomes:

l DJirag,3 - 3.17E-02 e 1.7E-04 t 0.204

0.0076 . E (O i *OF[)

which reduces to:

unir B.7-27 ODCM Rev.14 WA.== .

p,

l l DIsrato) = 4.1E-08 e t o.204

E (0, eDF[) (3 6f)

, , r s pCi-yr (mrad) = .( )*I gCi e mead-m3 pCi-m3 , t pC i -y r ,

\

7.2.7.5 Beta Dose to Air From Noble Gases Method I was derived as described in Section 7.2.5. The general form of

. the dose equation is:

l 0[gr - 3.17E-02 e X/0 3 "j,*de t **

E (0, e DFf) (3-7)

~

where all terms in the equation are as defined in Section 7.2.5.

Incorporating the specific 0F and atmospheric dispersion factor for i elevated releases into Equation 3 7 yields the following beta dose equation for the Education Center: ,

l Dfg,gg,3 - 3.17E-02 e 4.0E-05 e t '0 35 0.0014 . E (Og . DFf)

~

which reduces to:

l Oftr[(e) - 1.8E-09 e t-o.35 E (Og

OFf) (3 7c) e y ! %

pCi-y r mrad-m 3 (mrad) = .( )*I nCi e

,pci-m3 , t pCi-yr ,

for ground-level releases, the beta air dose equation for the Education Center becomes:

l Ofirgt,3 - 3.17E-02

5.5E-04

t *0 387 e 0.0014 E (Og . DFf)

, t which reduces to:

amor 8.7 28 ODCM Rev. 14 s

?

._ s n..~

i l Ofi,gg,3 - 2.4E-08 e t *0 34'

E (0, e DFf) (3 7d) i

, f f

pCl-yr mrad <n 3 (mrad) - +( )*I pCi e Ci -<n3 j $

pCi-yr ,

Incorporating the specific 0F and atmospheric dispersion factors for the

" Rocks

yields the beta air dose equation for elevated releases:

l Ofirate) - 3.17E-02 e 1.6E-04 + t -o.ru e0.0076.E(0,eDFf) which reduces to:

l Ofirag,3 - 3.9E-08 e t-0.20

E (0, e DFf) (3-7e) i e , t n 3

(mrad) -

pCl-yr

.( )*I gCi e mrad-m pCi-m ,

a

( pCi-yr ,

for ground-level releases, the beta air dose equation for the ' Rocks" becomes:

l Dfirag,3 - 3.17E-02 e 1.9E-03 + t 0.267

0.0076 + E (0,

DFf) whici, reduros to:

l Dfi,gg,3 - 4.6E-07 e t *0 287 . E (0, e DFf) (3 7f) i f , f %

pu -yr pCi e mrad-m 3

(mrad) - .( )eI s

,pc i -m , t pCi-yr ,

7.2.7.6 Critical Oraan Oose From lodi'nes. Tritium and Particulates With Half-lives Greater Than E'cht Days Method I was derived as described in Section 7.2.3. The Critical Organ Dose equations for receptors at the Education Center and the " Rocks" were derived frem Equation 3 8. The following general equation incorporates (1) a amn B.7-29 ODCM Rev. 14 a n.h .m . .. .. .. _y

k

)

f ratio of the average 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months depleted atmospheric dispersion factor to the average annual depleted atmospheric dispersion factor. (11) the unitiess t**

term, and (iii) the OF:

l De , - (X/0)!'.d/(X/0)l'[

t **

OF e E (0,

DFG,e,)

i r 3 r 3 sec sec ,g ),( ) ,g 'pCi * *

(mrem) - g

,m 3

m3 , t PCi ,

Applying the Education Center-specific factors for elevated release conditions p.oduces the equation: '

~

l Dcogg,3 - (3.72E-Ob)/(1.56E-06) e t *0 388

0.0014

E (0i

OFGic,g,3)

-- i

. which reduces to:

l Dcon.3 - 3.3E-02 . t '0 3

E (0, DFGgeog,3) (3 8c)

.s . .. . . . . . . - . .

'O*

(mrem) - ( )*( )*I pCi e g pC). ,

For a ground level release, the equation for a raceptor at the Education

- Center is:

l Dcogg,3 - (5.21E-04)/(2.23E-05) . t'0 347

0.0014

E (0, DFGicots))

which reduces to:

l DooE(g) - 3.3E-02 e t *0 347 . E (Og

DFGicots)) (3 8d)

(mrem) - ( )*( )*I Ci * *

t mci ,

The specific Critical Organ Dose equation for a receptor at the " Rocks" under elevated release conditions is: l

'ut*' B.7-30 ODCM Rev. 14

\

. . . .. a .. imaa.a

I l

l l

l Dconce) = (1.54E-04)/(1.61E-05) e t o.248

0.0076 . E (0, e DFG $e g,3) t l

which reduces to: l l

l Deang 3 - 7.3E-02 e t 0.248

E (Oi eDFGicac 3) (3-8e) l (mrem) - ( )*( )eI pCi e r >

l 1

i For a ground-level release, the equation for a receptor at the " Rocks" is-l l Deonggj - (1.80E-03)/(1.59E-04) e t-0.267

0.0076 . E (O i e DFG$ cogg3) 1 which reduces to:

l Deong,3 - 8.6E-02

t -0.267 . E (Og

DFG $e <,3) (3-8f) 1 (mrem) - ( )e( )eI Ci e mrem' pCi ,

The special receptor equations can be applied under the following l conditions'Iotherwise, justify Method I or consider Method II):

1. Normal operations (nonemergency event).

2. Applicable radionuclide releases via the station vents to the atmosphere.

If Method I cannot be applied, or if the Method I dose exceeds this limit, or if a more refined calculation is required, then Method II may be !

applied. l 1

l l

unst B.7 31 ODCM Rev. 14

TABLE B.7-2 Environmental Parameters for Gaseous Effluents at Seabrook Station (Derived from Reference A)"

Vegetables Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored YV Agricultural Productivity (Kg/M2 ) 2. 2. 0.70 2. 0.70 2. 0.70 2.

P Soil Surface Density (KG/M2 ) 240. 240. 240. 240. 240. 240. 240. 240.

T Transport Time to User (HRS) 48. 48. 48. 48. 480. 480.

TB Soil Exposure Time UI (HRS) 131400. 131400. 131400. 131400. 131400. 131400. 131400. 131400 TF Crop Exposure Time to P!rme (HRS) 1440. 1440. 720. 1.440. 720. 1.440. 720. 1.440.

TH Holdup After Harvest (HRS) 1440. 24. O. 2160. O. 2160. O. 2160.

OF Animals Daily Feed (KG/ DAY) 50. 50. 6. 6. 50. 50.

FP Fraction of Year on Pasture t2) 0.50 0.50 0.50 FS Fraction Pasture when on I. 1. 1.

Pasture"I FG Fraction of Stored Veg. Grown in 0.76 Garden FL Fraction of Leafy Veg. Grown in 1.0 Garden FI Fraction Elemental Iodine - 0.5 H Absolute Humidity - 5.60"I (gm/m3 )

Regulatory Guide 1.109. Rev. I B.7-32 00CM Rev. 14 siner

\

) i l

TABLE B.7-2 (Continued)

Notes:

(1) For Method 11 dose / dose rate analyses of identified radioactivity releases of less than one year, the soll exposure time for that release may be set at 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months (1 year) for all pathways.

(2) For Method 11 dose / dose rate analyses performed for teleases occurring during the first or fourth calendar quarters, the fraction of time animals are assumed to be on pasture is zero (nongrowing season). For the second and third calendar quarters..the fraction of time on pasture (FP) will be set at 1.0. FP may also be adjusted for specific farm locations if this information is so identified and reported as part of the land use census.

(3) For Method 11 analyses, the fraction of pasture feed while on pasture may be set to less than 1.0 for specific farm locations if this information is so identified and reported as part of the land use census.

3 (4) For all Method 11 analyses, an absolute humidity value equal to 5.6 (gm/m ) shall be used to reflect conditions in the Northeast (

Reference:

Health Physics Journal, Vol. 39 (August). 1980: Page 318-320.

Pergammon Press).

1 einst B.7-33 ODCM Rev. 14 4

- = - - -

1 i.

TABLE B.7 3 Usage Factors for Various Gaseous Pathways at Seabrook Station (from Reference A, Table E-5)'

Maximum Receotor:

Age Leafy Group Vegetables Vegetables Milk Meat inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m3 /yr)

Adult 520.00 64.00 310.00 110.00 8000.00 Teen 630.00 42.00 400.00 65.00 8000.00 Child 520.00 26.00 330.00 41.00 3700.00

?

Infant 0.00 0.00 330.00 0.00 1400.00

~

~ ~ ~ ~ ~ ~ ~

~ ' ~ ' ~ ~ - - ' ~~~~

TU i~o' R cwa 5 Education Ce'ritel: ~ ~ ~

.. Age Leafy Group VeQetables Vegetables Milk Meat inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m3 /yr)

Adult 0.00 0.00 0.00 8000.00 8000.00 Teen 0.00 0.00 0.00 8000.00 8000.00 Child 0.00 0.00 0.00 3700.00 3700.00 Infant 0.00 0.00 0.00 1400.00 1400.00

Regulatory Guide 1.109 ams B.7-34. ODCM Rev. 14

I l

l l

7.3 Receptor Points and Averace Atmosoheric DisDersion Factors for important Exoosure Pathways l

The gaseous effluent dose equations (Hethod I) have been simplified by assuming an individual whose behavior and living habits inevitably lead to a

! higher dose than anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:

1. Direct exposure to contaminated air:

l l

2. Direct exposure to contaminated ground:

1 l 3. Inhalation of air:

1

4. Ingestion of vegetables:

5. Ingestion of goat's milk; and l

l

6. Ingestion of meat.

Section 7.3.1 details the selection of important off-site and on-site locations and receptors. Section 7.3.2 describes the atmospheric model used to convert meteorological data into atmospheric dispersion factors.

Section 7.3.3 presents the maximum atmospheric dispersion factors calculated at each of the off-site receptor locations.

7.3.1 Rece5 tor Locations The most limiting site boundary location in which individuals are, or likely to be located as a place of residence was assumed to be the receptor for all the gaseous pathways considered. This provides a conservative estimate of the dose to an individual from existing and potential gaseous pathways for the Method I analysis.

This point is the west sector. 974 meters from the center of the reactor units for undepleted, depleted, and gamma X/0 calculations, and the northwest l section, 914 meters for calculations with D/0 the dispersion parameter.

l The site boundary in the NNE through SE sectors is located over tidal marsh (e.g., over water), and consequently are not used as locations for determining maximum off-site receptors (Reference NUREG 0133).

unir B.7-35 ODCM Rev. 14 1

Two other locations (on-site) were analyzed for direct ground plane exposure and inhalation only. They are the " Rocks" (recreational site) and the Education Center shown on Figure 5.1-1 of the Technical Specifications.

7.3.2 Seabrook Station Atmosoheric Dispersion Nodel The time average atmospheric dispersion factors for use in both Method I and Method II are computed for routine releases using the AEOLUS 2 Computer Code (Reference B).

AEOLUS-2 produces the following average atmospheric dispersion factors for each location:

1. Undepleted X/0 dispersion factors for evaluating ground level concentrations of noble gases:

2. Depleted X/0 dispersion factors for evaluating ground level concentrations of iodines and particulates:

3. Gamma X/0 dispersion factors for evaluating samma dose rates from a sector averaged finite noble gas cloud (multiple energy undepleted source); and

4. D/0 deposition factors for evaluating dry deposition of elemental radiciodines and other particulates.

Gamma" dose rate is calculated throughout this ODCM using the finite cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E.

Section 7-5.2.5. That model is implemented through the definition of an effective gamma atmospheric dispersion factor. [X/07] (Reference B.

Section 6), and the replacement of X/0 in infinite cloud dose equations by the

[X/07).

7.3.3 Averace Atmosoheric Dispersion Factors for ReceDtors The calculation of Method I and Method II atmospheric diffusion factors (undepleted CHI /0 depleted CHI /0 D/0. and gamma CHI /O values) utilize a methodology generally consistent with US NRC Regulatory Guide 1.111 (Revision 1) criteria and the methodology for calculating routine release diffusion factors as represented by the X00000 computer code (NUREG/CR-2919).

The primary vent stack is treated as a " mixed-mode" release. as defined in Regulatory Guide 1.111. Effluents are considered to be part-time ground unst B.7-36 ODCM Rev.14

l l

l 1evel/part time elevated releases depending on the ratio of the primary vent stack effluent exist velocity relative to the speed of the prevailing wind.

All other release points (e.g., Turbine Building and Chemistry lab hoods) are considered ground level releases.

In addition, Regulatory Guide 1.111 discusses the concept that constant mean wind direction models like AEOLUS-2 do not describe spatial and temporal variations in airflow such as the recirculation of airflow which can occur during prolonged periods of atmospheric stagnation. For sites near large bodies of water like Seabrook, the onset and decay of sea breezes can also results in airflow reversals and curved trajectories. Consequently, Regulatory Guide 1.111 states that adjustments to constant mean wind direction model outputs may be necessary to account for such spatial and temporal j variations in air flow trajectories. Recirculation correction factors have been applied to the diffusion factors. The recirculation correction factors

, used are compatible to the " default open terrain" recirculation correction factors used by the X00000 computer code.

The relative deposition ratesi D/0 alues, were derived using the j --

rehtivrdeposittwrate ~turves"presunted 1r1tegutTrury Guidr~ 1.111 --- ' - -

(Revision 1). These curves provide estimates of deposition rates as a function of plume height, stability class, and plume travel distance.

, ReceDtor locations l

For ground level releases, the downwind location of "The Rocks" l (244m NE/ENE) and the Ed Center (406m SW) were taken as the distance from the i nearest point on the Unit 1 Administrative Building / Turbine Building complex.

!' For the site boundary, the minimum distances from the nearest point on the Administration Building / Turbine Building complex to the site boundary within a 45-degree sector centered on the compass direction of interest as measured from FSAR Figure 2.1-4A were used (with the exception that the

NNE NE ENE-E-ESE-SE site boundtry sectors were not evaluated because of their i over water locations).

For primary vent stack releases, the distances from the Unit 1 primary

! vent stack to "The Rocks" (244m NE) and the Ed Center (488m SW) as measured j from a recent site aerial photograph were used. For the site boundary the minimum distances from the Unit 1 primary vent stack to the site boundary within a 45 degree sector centered on the compass direction of interest as measured from FSAR Figure 2.1 4A were used (with the exception that the 1

i umi B.7 37 ODCM Rev. 14 1

e e NNE-NE ENE E ESE SE site boundary sectors were not evaluated because of their over water locations).

k Meteorolooical Data Bases For "The Rocks" and Ed Center receptors, the diffusion factors represent 5 six year averages during the time period January 1980 through December 1983 and January 1987 through December 1988 (with the exception that, because of low data recovery, April 1979 and May 1979 were substituted for April 1980 and May 1980). For the site boundary receptors, both six year average growing M season (April through September) and year-round (January through December) k diffusion factors were generated, with the higher of the two chosen to represent the site boundary.

k > The meteorological diffusion factor used in the development of the ODCM Hethod I dose models are summarized on Tables B.7 4 through B.7 6.

t -

- = +a--_ --,,

r 4

""" 8.7 38' ODCM Rev. 14 IN

TABLE B.7-4 l Seabrook Station Lono-Term Averace Discersion Factors l

Primary Vent Stack ;

1 l

1 Dose Rate to Individual Dose to Air Dose to j Critical Organ Total Body Skin Critical Organ Gamma Beta Thyroid i

e 3 - -

7.5E-07 - -

7.5 07 l X/0 depleted sec

]

s

t l

r ' -

8.2E-07 - -

8.2E-07 -

X/0 undepleted sec j 5,

u s l

r 1. 5 E -08**

1.5E-08 D/0 7 !

t s l r '

8.5E-07 8.5E-07 -

8.5E-07 - -

seC X/QT u* s 1

l

West site boundary, 974 meters from Containment Building

- Northwest site boundary, 914 meters from Containment Building unar B.7-39 ODCM Rev. 14 l

\

e TABLE B.7-5 l Seabrook Station Lono Term Average DisDersion Factors for Soecial (On-Site) ReceDtors Primary Vent Stack

__TDoseto Critical Dose Rate to Individual Dose to Air Organ Total Body Skin Critical Organ Gamma Beta Thyroid Education Center: *

(SW - 488 meters) 1.5E-06 - -

1.5 -06 X/0 depleted sec s s 1.6E 06 - -

1.6E-06 -

X/0 undepleted sec r

s 2.7E-08 - - -

0/0 s s f '

1.1E-06 1.1E-06 -

1.1E-06 - -

X/0y sec ]

m3 ,

l l

The " Rocks": -

(ENE - 244 meters)

P ' - -

1.6E-05 - -

1.6E-05 X/0 depleted sec u* s 1.7E-05 - -

1.7E-05 -

X/0 undepleted s s 1.1r.-07 - - -

D/0 u s 5.0E-06 5.0E-06 -

5.0E-06 - -

see X/07 r >

us B.7-40 ODCM Rev. 14 ,

I

i TABLE B.7 6 Seabrook Station l Long Term Atmospheric Diffusion and DeDosition Factors Ground level Release Pathway R E C E P T 0 R(*)

Diffusion Factor The Rocks Ed Center Off-Site l

, Undepleted CHI /0. sec/m 3 1.6 x 10 2.3 x 10 5 1.0 x 10

(244m ENE) (406m SW) (823m W)

- Depleted CHI /0. sec/m 3 1.5 x 10 2.1 x 10 5 9.4 x 10

(244m ENE) (406m SW) (823m W) 0/0. m 2 5.1 x 10*7 1.0 x 10'? 5.1 x 10.s (244m ENE) (406m SW) (823m W)

Gamma CHI /0. sec/m3 2.6 x 10 5.3 x 10 3.4 x 10

(244m ENE) (406m SW) (823m W) s (a)

The highest site boundary diffusion and deposition factors occurred during the April through September growing. season. Note that for the primary vent stack release pathway, none of the off site receptor diffusion and deposition factors (located at 0.25 mile increments beyond the site boundary) exceeded the site boundary diffusion and deposition factors.

~

'**' B.7 41 ODCM Rev. g4 a

8.0 BASES FOR LIOUID AND GASEOUS MONITOR SETPOINTS d

8.1 Basis for the licuid Waste Test Tank Monitor SetDoint The liquid waste test tank monitor setpoint must ensure that Specification 3.3.3.9 is not exceeded for the appropriate in-plant pathways.

The liquid waste test tank monitor is placed upstream of the major source of dilution flow.

The derivation of Equation 5-1 begins with the general equation for the response of a radiation monitor:

R =

C,9 S jj ( 8-1 )

i (cps) = (, ) (# )

where:

R = Response of the monitor (cps)

S)g

= Detector counting efficiency for radionuclide "i" (cps /(uct/ml))

C,3 = Activity concentration of radionuclide "i"'in mixture at the monitor (uci/ml)

The detector calibration procedure for the liquid waste test tank monitor at Seabrook Station establishes a counting ef ficiency by use of a known calibration source standard and a linearity response check. Therefore, in Equation 8-1 one may substitute S) for S)3, where S) is the detector counting efficiency determined from the calibration procedure. Therefore, Equation 8-1 becomes:

R = C g (8-2)

S) 1 (cps) = ( ) ( )

I 8.8-1 ODCM Rev. 4

The MPC for a given radionuclide must not be exceeded at the point of -

discharge. When a mixture of radionuclides is present,10CFR20 specifies that the concentration at the point of discharge shall be limited as follows:

d (8-3) p

<1 i i uC1-m1 Imi vci) -

where:

C - Activity concentration of radionuclide 'i' in the mixture at di the point of discharge (vC1/ml)

MPC g - MPC for radionuclide 'i' from 10CFR20 Appendix B, Table II, Column 2 (uC1/ml)

The activity concentration of radionuclide 'i' at the point of discharge is related to the activity concentration of radionuclide 'i' at the monitor as follows: .

(8-4)

C d1

=

C,, [Fd :

(mi ) * (mi ) ( gpm E) where: ,

C df = Activity concentration of radionuclide 'i' in the mixture at the point of discharge (uci/ml) l F, = Flow rate past monitor (gpm)

F = Flow rate out of discharge tunnel (gpm) d 8.8-2 ODCM Rev. 4

i l

Substituting the right half of Equation 8-4 for C d1 in Equation 8-3 and solving for F d/F, yields the minimum dilution factor needed to comply with j Equation 8-3' l

DFmin I 1 (8-5) g (gLm) guci-ml) gpm ml-pC1 l

where: ,

F d

- Flow rate out of discharge tunnel (gpm)

F, - Flow rate past monitor (gpm)

C,g - Activi,ty concentration'of radionuclide "1" in mixture at the monitor (pC1/ml)

MPCj - MPC for radionuclide "1" from 10CFR20, Appendix B, Table II, Column 2 (pC1/ml)

If F d/F,is less than DFmin, then the tank may not be discharged until either Fdor F,or both are adjusted such that:

F d

1 0F (8-5) 7-m min (EL")

gpm Usually Fd /F,is greater than DFmin (i.e., there is more dilution than necessary to comply with Equation 8-3). The response of the liquid waste test tank monitor at the setpoint is therefore:

Rsetpoint " Il 0 in "I

pCl ,( )( ) (cos-ml) (uCl) l - ml pC1 ml B.8-3 8689R ODcM Rev. 4

where jf is equal to the fraction of the total contribution of MPC at the discharge point to the environment to be associated with the test tank effluent pathway, such that the total sum of the fractions for the four 11guld discharge pathways is equal to or less than one (f) + f2+I*I4 3 I I'*

The monitoring system is designed to incorporate the detector efficiency, Sj , into its software. This results in an automatic readout in pC1/cc or pC1/mi for the monitor response. Since this procedure for converting cps to pC1/mi is inherently done by the system software, the monitor response setpoint can be calculated in terms of the total waste test ,

tank activity concentration in pC1/ml determined by the laboratory analysis.

Therefore, the setpoint calculation for the liquid waste test tank is:

R setpoint "I lD in (uCl) ( )g ) guCl) j ml mi i 8.2 Basi? for the Plant Vent Wide Range Gas Monitor Setpoints The setpoints of the plant vent wide range gas monitors must ensure that Technical Specification 3.11.2.1.a is not exceeded. Sections 3.4 and 3.5 show that Equations 3-3 and 3-4 are acceptable methods for determining compliance with that Technical Specification. Which equation.(i.e., dose to total body or skin) is more limiting depends on the noble gas mixture.

Therefore, each equation must be considered separately. The derivations of Equations 5-5 and 5-6 begin with the general equation for the response R of a radiation monitor: 4 R - S C ,9

( 8-D gg (cpm) - (CD * ) (" )

cm

- B.8-4 oDCM Rev. 8 8689R

where: 1 l

R - Response of the instrument (cpm)

S gj - Detector counting efficiency for noble gas "1" (cpm /( C1/cm3 )) ;

i C,9 - Activity concentration of noble gas "1" in the mixture at the noble gas activity monitor (pCi/cm3)

C,g, the activity concentration of noble gas "1" at the noble gas activity monitor, may be expressed in terms of gO by dividing by F, the appropriate flow I rate. In the case of the plant vent noble gas activity monitors the appropriate flow rate is the plant vent flow rate.

I 1 C,g - hj T- (8-8)

! ($)-($)

c,3 sec (M) g,3 4

where: .

[ '

Qg - The release rate of noble gas "1" in the mixture, for each noble '

gas listed in Table B.1-10.

F - Appropriate flow rate (cm 3/sec)

Substituting the right half of Equation 8-8 into Equation 8-7 for C,3 yields:

R = 5 99 hg h (8-9) 1 (cpm) (C *) (h) ( )

cm i

As in the case before, for the liquid waste test tank monitor, the plant vent wide range gas monitor establishes the detector counting efficiency by use of a calibration source. Therefore, S can be substituted for S g gg

' 8.8-5 8689R ODCM Rev. 4

l l

l 1

in Equation 8-9, where S g is the detector counting efficiency determined from the calibration procedure. Therefore, Equation 8-9 becomes: '

R - S g h hi (8-10)

(cpm) = (9*]* ) ( ) ( )

Cm The total body dose rate due to noble gases is determined with Equation 3-3:

l b =

0.85

EL(R)

tb Qg DFB (3-3) 3 i

3 (mrem) yr

, (DCi-sec) ( ) (pg) gmrem-m )

3 Cl-m sec pCi-yr where:

b - total body dose rate (mrem /yr) tb .

t 0.85 - (1.0E+06) x (8.5E-07) (pCi-sec/pCl-m3 )

IE+06 - number of pCl per pCl (pCl/pCl) l 8.5E-07 - [X/Q]Y, maximum off-site average gamma atmospheric I dispersion factor (sec/m3 ) for primary vent stack releases EL(R)

- Release point correction factor - 1.0 for primary vent i

stack Qj - As defined above.

DFB - total body dose factor (see Table 8.1-10) t 3

(mrem-m /pCl-yr)

B.8-6 8689R ODCM Rev. 7

l A composite total body gamma dose factor, DFBc, may be defined such that:

DFB c h= g hj DFB j (8-11) {

3 3 mrem-m pC1-yr g) , (g) (mrem-m )

sec sec pCi-yr Solving Equation 8-11 for DFB g yields:

h j DFB j DFB =

e (5-7) l

[o,g i

Technical Specification 3.ll.2.1.a limits the dose rate to the total body from noble gases at any location at or beyond the site boundary to 500

, mrem /yr. By setting O equal to 500 mrem /yr and substituting DFB for DFB tb c g in Equation 3-3, one may solve for [ Q jat the limiting whole body noble gas dose rate: I 4

l hj= 588 DFB '

i C 3

(uC1) ,g mrem-uC1-m pCi-yr

sec yr-pCi-sec ) (mrem-m3 )

i Substituting this result for [ hj in Equation 8-10 yields Rtb, the response j of the monitor at the limiting' noble gas total body dose rate:

i R tb

- 588 S g h DFB g

3 (gp ,) , (mrem-uC1-m ) {c,,_c,3) (sec) (DCl-yr )

j yr-pCl-sec pCi g,3 3 mrem-m The skin dose rate due to noble gases is determined with Equation 3-4:

h - L(R)

DF g U-O skin Qg (mrem) ,( ) (Q) (mrem-sec) yr sec pCl-yr B.8-7 8689R ODCM Rev. 7

there:

EL(R) - 1.0 for primary vent stack release (dimensionless) -

bskin - Skin dose rate (mrem /yr) <

hy - As defined above.

DFj - Combined skin dose factor (see Table B.1-10) (mrem-sec/pCl-yr)

A composite combined skin dose factor, DF', may be defined such that:

DFj hg -

hy DFj (8-14) i i (mrem-sec) pCI-yr (g) , (dt,) (mrem-sec) sec sec pCl-yr Solving Equation 8-14 for DF' yields:

V-L Q, DFj I

DF' - ,

(5-8)

Li o, Technical Specification 3.11.2.1.a limits the dose rate to the skin from noble gases at any location at or beyond the site boundary to 3,000 mrem /yr.

By setting D skin equalto3,000 mrem /yrandsubstitutingDFjforDFjin Equation 3-4 one may solve for [ 0, at the limiting skin noble gas dose. rate: I i '

bg = 3,000 DF, (8 15) i C (61)1 uCl sec (mrem) yr (mrem sec y

yr Substituting this result for [ h in gEquation 8-10 yleids Rskin, the response I

of the monitor at the limiting noble gas skin dose rate:

B.8-8 '

8689R ODCM Rev. 7

Askin - 3,000 S g h 0 (8-16) 3 e set CE") mrem) yr gpCi om-cm ' ' i I mrem-sec uC1-yr '

Cm As with the liquid monitoring system, the gaseous monitoring system is also designed to incorporate the detector efficiency, S , into its g

software. The monitor also converts the response output to a release rate (pCl/sec) by using a real time stack flow rate measurement input. Therefore, multiplying by the stack flow rate measurement (F), the Equations 8-15 and 8-16 become:

R - 588 (5-5) tb 0FB g 3

C mr (p_C1) , (yrem-uC1-m (pCI-yr

) )

sec pCl-sec 3 mrem-m

- 3000 R

skin h. (5-6)

(uCl) ,(mrem) uC1 (mrem-yr sec yr -sec )

8.3 Basis for PCCW Head Tank Rate-of-Change Alarm Setpoint Tht PCCW head tank rate-of-change alarm will work in conjunction with the PCCW radiation monitor to alert the opcrator in the Main Control Room of a leak to the Service Water System from the PCCW System. For the rate-of-change alarm, a setpoint based on detection of an activity level of 10-8 Cl/cc in I the discharge of the Service Water System has been selected. This activity level was chosen because it is the minimum detectable level of a service water monitor if such a monitor were installed. The use of rate-of-change alarm with information obtained from the liquid sampling and analysis commitments described in Table A.3-1 of Part A ensure that potential releases from the B.8-9 8689R ODCM Rev. 7

. - _ . _ - . . . - . . _ . - . _ _ . - . = - . _ - _ . - _ . - . . - . _ . . .,

Service Water System are known. Sampling and analysis requirements for the Service Water System extend over various operating ranges with increased sampling and analysis at times when leakage from the PCCW to the service water is occurring and/or the activity level in the PCCW is high.

t l

l B.8-10 -

8689R 00CM Rev. 7

REFERENCES A. Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of. Evaluating Compliance with 10CFR50, Appendix I", U.S. Nuclear Regulatory Commission, Revision 1, October 1977.

B. Hamawi, J. N., "AEOLUS A Computer Code for the Determination of Continuous and Intermittent-Release Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents in Open-Terrain Sites, Coastal Sites, and Deep-River Valleys for Assessment of Ensuing Doses and Finite-Cloud Gamma Radiation Exposures," Entech Engineering, Inc., March 1988.

C. Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and ,

Dispersion of Gaseous Effluents 'n Routine Releases From Light-Water Cooled Reactors" U.S. Nuclear Regulatory Commission, March 1976. '

O. Natior.al Bureau of Standards, " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure", Handbook 69, June 5, 1959.

E. Slade, D. H., " Meteorology and Atomic Energy - 1968", USAEC, July 1968.

F. Seabrook Station Technical Specifications.

l R-1 8689R ODCM Rev. 7

i f

APPENDIX A I

I a

I DOSE CONVERSION FACTpRS

- A-1 ODCM Rev. 8 l

l e

l APPENDIX A Dose Conversion Factors j

I. Liquid Pathways - Seabrook Site Specific DCF's The models used to assess doses resulting from effluents into liquids is derived from Appendix A of Reg.

Guide 1.109. Since Seabrook is a salt water site, the assumed pathways of exposure taken from Reg Guide 1.109 are Aquatic foods - fish; Aquatic foodJ -invertebrates; and :

j dose from shoreline deposits (direct dose). No drinking water or irrigation pathways exist because of the salt water environme".t. In addition, expossures resulting from !

boatire; and swimming activities have been included for key radionuclides even though Reg. Guide 1.109 identifies these '

pathways as not contributing any significant contribution ,

to the total dose, and therefore does not provide dose l equations for them. For completeness, the swhnnkg and boating pathways have been includes using the dose models from the HERMES code (HEDL-TME-71-168, Dec.1971) , section G, Water Innersion.

The Method I dose conversion factors are derived by calculating the dose impact to individuals via the site :

specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by radionuclide are calculated for each of the 7 organs (including whole body) for each of the four age groups (adult, teen, child, and l infant). The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all the exposure pathways combined.

The list of dose factors in the ODCN then rcpresents a combination of different limiting organs and age groups which, when used to calculate a dose impact from a mix of radionuclides released in liquig effluents, gives a conservative dose since it combines the exposure to different organs and age groups as if there was a single critical organ-age group.

As an example of how the liquid dose conversion factors are developed, the following calculation for Co-60 is shown.

The critical organ / age group is selected based on the full assessment of all organs and age groups.

Factor for fish Ingestion:

The general equation for ingestion doses in RG 1.109 is eq. A-3.

U M -b t ap p p 1119.7- -

QB D e F

i ip alpj ,

The full assessment for the ODCM dose factors indicated that for i = co-60, the maximum dose l (arem/yr) is to the GI-LLI of an adult as the l target organ and age group, therefore: ODCM Rev. 8 A-2

~

l

U := 21 kg/yr adult usage factor for fish ap M := 0.1 mixing ratic for near field dilution p provided by submerged multiport diffuser, F := 918 cu. ft./sec effluent flow rate for cil.culating water system Q := 1.0 curies / year relased of CO-60 i assumed B := 100 equilibrium bioaccumulation factor ip for CO-60 in salt water fish, in liters /kg

-5 D := 4.02 10 area /pci, adult GI-LLI alpj ingestion dose factor from RG-1.109, table E-11.

-5 1 := 1.501 10 decay constant for CO-60 in 1/ hrs.

t := 24 time between releece and p ingestion, in hrs. l 1119.7 is the factor to convert from .

Ci/yr per ft3/sec to pCi/ liter. note .

that RG 1.103 uses 1100 as a rounded i approvination.

Therefore the dose from fish to adult GI-LLI is (mram/yr):

U M -1 t ap p p 1119.7- -Q B D e = 0.0103 F i ip alpj Factor for invertabrate ingestion:

Next, the dose from invertebrates to the adult GI-LLI is given by the same general equation but with the following variables changed:

A-3 *

, - - - - . - , y

kg/yr usage factor ,

U := 5 ap B := 1000 1/kg bioaccumulation factor ip all other variables the same as above therefore the dose from invertebrates is (arem/yr):

U M -1 t e, ap p p 1119.7- -Q B *D e = 0.0245 F i ip nipj Factor for shoreline direct dose:

The general equation for direct dose from shoreline deposits is taken from equation A-7 in RG-1.109 as (arem/yr):

U M W -1 t -1 t ap p p b 111970- -

Q TD e -

1-a ~

F i. aipj i

It is assumed that all internal organ doses also receive exposure from direct external sources, therefore each organ dose due to ingestion must have i and external component added. For the above equation, the site specific variables for an adult exposure to a 1 curie per year release of CO-60 are:

U := 334 hrs / year usage factor used for ;

assumed shoreline activities at ap Seabrook.

M := .1 mixing ratio for near field p dilution provided by the submerged multiport diffuser and assume to be extended to the beach continuously.

W := 0.5 shorevidth factor for ocean sites. dimensionless 'l A-4 ODCM Rev. 8

1

~

3 T := 1.923 10 radioactive half life in l

days for CO-60 j

-8 1 D ;- 1.70 10 cose factor for CO-60 due

aipj to deposits in sediments, units of (area /hr)/(pci/m2) l t: = 0. transit time to point of p exposure, hrs l t := 131400 period that sediment is b assumed to be exposed to j water contamination for long i term buildup, set at 15 .

j years for Method I DCF's <

l Q := 1.0 curies per year, co-60 i assumed 1

1 111970 conversion factor to convert i (Ci/yr)/(ft3/sec) to i pCi/ liter and account for

.the proportionality constant used in sediment model Therefore the dose to the whole body and each organ due to direct exposure to the shoreline (arem/yr) is:

U M -

W -1 t -X t ap p p b 111970- -Q TD e ,1 - e .

= 0.0573 F i aipj Direct dose due to Swi ning:

The dose due to inserzion in water (swining) is taken from the HERMES computer code. The original ODCM calculation was based on some preliminary dilution assumptions which gave a near field prompt dilution factor for the multiport diffuser of 8. For single unit operation with both service water and circulating water flow (412,000 gpm), a value on 10 is more realistic.

This surface area of the plume is restricted to a small area over the diffuser and does not touch the shoreline approx. 1 mile away. Since the over all impact from swi n ing is small when compared to the other exposure pathways, the original conservatism on dilution are kept here.

A-5 ODCM Rev. 8 m-- v- w ~w, ,- -

r w , - +

The dose from swimming is given by the following equation:

U 12 p 1.0 10 - -

Q DF (aram/yr)

F i in a i Where:

U := 45 hrs /yr, usage factor for '

p swimming for ==v4="= age 4 group (teen) from HERMES.

11 F := 6.56 10 liters /yr, estimated annual a dilution effluent flow in !

multiport diffuser ,

l Q := 1.0 c'uries/yr, assumed release i rate of nuclide i.

-6 DF := 4.6 10 mram-liters per hrs-pCi, dose l im factor for Co-60 for water immersion taken from HERMES.

12 ,

1.0 10 constant for pCi/Ci l i

Therefore the swimming dose for a 1 curia release of Co-60 is (aram/yr):

M i 12 p -5 1.0 10 U -

-Q DF = 3.155 10 !

p F i in a

i As can be seen, the contribution of the swinnalng dose ,is only about one 30000ths of the total of the i RG 1.109 pathways, and can be ignored in the case of Co-60. Similarly, the boating dose as given in .

.' HERMES is taken as half of the swimming dose,(and l

A-6 - ODCM Rev. 8

1 E

corrected for change in usage assumptions). The

resulting dose is found to be less than the swimming dose and can also therefore be discounted in this 4

Case.

a i

Total liquid Pathway dose

. l 1

The sum of the above liquid pathway doses can now be I added to give the total "av4== jndividual dose to ;

the critical organ (adult-GI-IIK) for Co-60. This ; I gives: i i

l l l

! 0.0103 + 0.0245 + 0.0573 = 0.0921 area /yr l l

4

. Since the internal doses *given by the RG-1.109 i methods actually are 50 yr dose commitments resulting from one year exposure to the quantity of activity assumed to be released into the water, and the direct dose represents the dose received for the period assumed to be exposed to the pathway, and the activity release was taken as a unit quantity (i.e. Q= 1 Ci), the above total liquid pathway dose can be stated as site specific committed dose factor in aram/Ci released. For Method I in the 000(, the critical organ dose factor is seen to be 0.0921 mren/Ci, as shown above. The value reported on Table B.1-11 (9.22 E-08 ares /uci) was generated by a computational routine which gives rise to the round-off difference between it and the above avample. The whole body site specific dose factor for the ODCM was calculated in the same way treating the whole body as a separate organ.

i i

l g7 ODCM Rev. 8 e

l II. Gaseous Pathways - Seabrook Site Specific DCF's The models used to' assess doses resulting from gaseous effluents in the form of iodines, tritium, and particulates are derived from Appendix C of Reg. Guide 1.109. For Seabrook, it is assumed that at the off site location which exhibits ,

minimum atmospheric dilution for plant releases the following

~

i exposure pathways exist: inhalation, ground plane, ingestion of i goats milk, meat, stored vegetables, and leafy vegetables.

The Method I dose and dose rate factors are derived by calculating the dose impact to all age group individuals via the site specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by nuclide are calculated for ,

each of 7 organs ( including the whole body) for each of the 4 agei groups. The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the ,

age groups for all exposure pathways combined. The list of dose '

factors in the ODCM then represents a combination of different limiting organs and age groups which, when used to calculate the dose impact from a mix of radionuclides released into the atmosphere, gives a conservative dose since it combines the exposure to different organs and age groups as if they were for all the same critical organ-age group.

As an example of how the gaseous particulate dose factors are l developed, the following calculation for Mn-54 is shown. The critical organ / age group for Mn-54 was selected gazed on a full assessment of all organ and age group combinations. For elevated releases from the plant vent stack to the maximum site boundary i (max. dose point due to meteorology), the critical organ and age group for Mn-54 was determined to be the GI-LLI for the adult.

PART A: Inhalation Dose Contibution:

1 The general equations for inhalation doses in RG 1.109 are eq. C-3, and C-4 which together give:

4 "X' 3.17 10 R - - -

Q DFA =D a ,Q i ija ja Where for the cass of Mn-54 releases, the variables above are defined as:

4

, 3.17 10 is the number of PCi/Ci divided by j the number of second per year l I !

A-8 ODCM Rev. 8 I

4 1

R := 8000 tho brG2 thing rato for cga group a j a (adults) in m'3 /yr.

X -7

- = 7.5 10 the long term average depleted Q atmospheric dispersion factor, in

sec/m"3, at the maximum exposure point off site. (S.B.)

l Q := 1 the release rate of nuclide i to the

i atmosphere in Ci/yr

-6 DFA := 9.67 10 the inhalation dose factor for j ija nuclide 1 (Mn-54), organ j (GI-LLI) ,

and age group a (adult) taken from' RG 1.109, table E-7, in arem/pci

inhaled.

Therefore, the inhalation dose to the maximum potential off site individual is given as:

q .

4 Y

3.17 10 R - -

-Q DFA = 0.00184 mram/yr per Ci i a .q i ija j PART B: Ground Plane Direct Dose Contribution:

1

[ The general equations for ground plane external direct dose in RG 1.109 are equations C-1 an1 C-2 which together give the dose DG as:

-1 t i b 12 'D' 1-e 8760 1.0 10 S - - -

Q - =DFG ,

F ,Q i 1 ij !

i i l

i Where for the case of Mn-54 releases, the variables in the above equation are defined as:

1 A-9

ODCM Rev. 8 l

12 1.0 10 is tha number of pCi per Ci S := 0.7 the shielding factor provided by F- residential structures (dimensionless) for use in calculation accumulated doses over time. Note that for determination of dose rate factors (i.e. instantaneous dose rates) the shielding factor is set equal to 1.0, or in affect no credit for dose reduction is taken for determination of dose rates at points in time.

D -8

- = 1.5 10 the long term average relative Q deposition factor at the maximum site ,

boundary location, in 1/m*2 <

1 := 0.8105 is the radiological decay constant for i Mn-54 (nuclide i in this case) in 1/yr.

t := 15 is the time in years over which b accumulation is evaluated ( approx.

midpoint of plant operating life)

-9 DFG := 5.80 10 external dose factor to the whole ij or any internal organ j, for body,ing stand on contaminated ground from Mn-54 (RG 1.109 Table E-6) in area /hr per pCi/m"2 l

Q := 1.0 is the unit release quantity assur.ed i for each nuclide i, in Ci/yr.

8760 is the number of hours in a year Therefore, the contribution to the total dose made by exposure to i the ground plane at the maximum off site exposure location for Mn-54 is given as:

l

-1 t i b 12 'D' 1-e DFG = 0.658 mram 8760 1.0 10 S - -

-Q -

per F ,Q, i 1 ij i yr per Ci gn ,

ODcM Rev. 8

4 PART C: Ing::cticn Dono Contribution:

As an initial step to determining the dose contribution from ingestion of milk, meat, stored vegetables, and leafy vegetables, we must first calculate the radionuclide concentration in forage, produce, and leafy vegetables resulting from atmospheric tranfers of the activity to the surface of the vegetation and onto the soil for root uptake. For all radiciodines and particulate nuclides (except tritium and C-14),

the concentration of nuclide i in and on the vegetation at a point of interest can be calculated using R.G. 1.109 equations C-5 and C-6, which combined gives:

i 4

e a

-1

X .t t "

~'

Ei e i b -1 t

8 D 1-e 1-e i h 1.14 10 - -

-Q -

r- +B -

e

,Q i Y 1 iv P1 v Ei i 1

4 PART C.1: Concentration in Produce (stored vegetables)

For the case of Mn-54 released in air emissions to the maximum site boundary, the concentration of Mn in produce grown in the hypothetical garden at that location can be calculated from the above equation where the variables are defined as:

8 1.14 10 is the number of pCi per Ci divided by the number of hours in a year (8760).

D -8

- = 1.5 10 is the relative deposition factor, in 1/m2, at the maximum exposure point off Q

- site (S. B.)

o := 1 the release rate of nuclide i to the i atmosphere in ci/yr r := 0.2 fraction of deposited activity retained on crops, leafy vegetables, or pasture

grass (1.0 for iodines) 4 A-ll ODCM Rev. 8

. l X := 0.00219 offectivo removal rato constant for l I

El Mn-54 from crops dua to decay and weathering, in hr-1 !

t := 131400. soil exposure time to depositicn, in

b. (equal to 16 yrs, or aid plant life)

Y := 2.0 agricultural productivity (yeild) for v produce, in kg/m-2

-2 B := 2.9 10 concentration factor for uptake of iv Mn-54 from soil by edible parts of crops in pci/kg (wat weight) per pCi/kg dry soil ..

-5 1 := 9.252 10 radioactive decay constant for Mn-54, i in hrs-1 P := 240. effective surface density of soil. in kg/m2 t := 1440. crop holdup time after harvest and h before ingestion, in hrs .

t := 1440. crop exposure time to plume, in hrs II Therefore, the concentration of Mn-54 in stored vegetables produced at the location of maximum deposition for a unit activity release is given as: ,

i

-% .g -% .t Ei e i b -1 t ,

a 'D' 1-e 1-e i h 1.14 10 - -

-Q -

r- +B - e = 67.379

.Q i Y 1 iv P1 v Ei i '

~

pCi/kg PART C.2: Imafy Vegetable Concentration:

For leafy vegetables, the above equation is repeated with the value for t.h, crop holdup time after harvest is changed from 1440 hrs to 24 hrs, i.e'.:

ODCM Rev. 8 8 A-12 v - - - - - __ - - + - -

_ _ _ _ _ _ _ . _ _ _ _ = _- - - __.__

t := 24 crop holdup time after harvest, in hrs.

h Therefore the concentration of Mn-54 in leafy vegetables at the maximum deposition point due to a unit activity release is given as:

-L

~

.t -% .g Ei e i b -1 t 8 'D' 1-e 1-e i h 1.14 10 - -

-Q -

r- +B -

e = 76.811

.Q, i Y 1 iv P1 v Ei i '

gi/kg PART C.3.a: Animal Feed Concentration (pasture): C P

Next, we can repeat the above calculation to determine the concentration of Mn-54 in pasture grass used as animal feed. This will allow for the determination of dose contribution from milk and meat.

For pasture grass, all the above variables remain the same except for : ,

1 i

Y := 0.70 for agricultural productivity of pasture j v grasses, kg/m2 l t := 720. for grass exposure time to plume, hrs a

t := 0.0 for holdup time after harvest h

Using these variables in the above equation gives the concentration in pasture grass as:

-1 .t -1 t Ei e i b -1 t 8 'D' 1-e 1-e i h 1.14 10 - - -Q -

r- +B - e = 179.227

.Q, i Y 1 iv P1 v Ei i .

pCi/kg A-13 ODCM Rev. 8

~

PART C.3.b: Animal Feed Concentration (stored feed): C s .

For stored feed that would be given to goats, or meat animals, the average concentration would be calculated by changing the following variables in the above calculation to:

Y := 2.0 agricultural productivity for stored feed v

t := 1440. feed crop exposure time to plume in hrs /

e t := 2160. feed crop holdup time after harvest, hrs h

Putting these values back into tha above equation gives the concentration in stored animal feed (goat and meat animal) of Mn-54 for a unit activity release to the maximum exposure point.

_A .t -1 t Ei e i b -1 t 8 "D' 1-a 1-e i h 1.14 10 - -

-Q -

r- +B -

e = 63.037

.Q i Y 1 iv P1 v Ei i ~

pCi/kg PART C.3.c.: Concentration in Goat's Milk: C m

The Mn-54 concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated from RG 1.109 general equation C-10 as:

-1 t i f F 1C -Q e = conc. in milk, pCi/litar ,

a v F i A-14 ODCM Rev. 8

whoro tho variabics aro dafined as:

-4 F := 2.5 10 average fraction of animal's daily a intake of Mn-54 which appears in each liter of milk', in days / liter j I

Q := 6.0 amount of feed consumed by a goat i F per day, in kg/ day (50 kg/d for

naeat) i t := 2.0 average transport time of activity j f from feed into milk and to receptor,, ,

in days.

-3 i 1: = 2.22 10 decay constant of Mn-54 ,in days-1

! i 4

i h

I In addition, the C.v term for the concentration of a nuclide in i the animal's feed is given from RG 1.109 general equation C-11 as:

a

~1 - f C = f f C + C +f -

1-f C l p p. s p s, s v p a . .

4 4

where the following equals:

{

1 I

j f := 0.5 fraction of the year that animals p graze on pasture i

f := 1.0 fraction of daily feed that is j s pasture grass when the animal grazes i

on pasture i C := 179.227 concentration of Mn-54 in pasture p grass as calculated from above, 1

Pci/kg i

C := 63.037 concentration of Mn-54 in stored

< s feed as calculated from above, in 1

Pci/kg i

i f Therefore, the concentration in the total animal's feed is estimated to be :

A-15 -

ODCM Rev. 8

~

f f C. + 'l - f C +f -

'l - f ' C = 121.132 P O P . P. 8 P . G. s PCi/kg -

When this value of 121.132 is put back into the above general equation for nuclide concentration in milk, we get:

[C := 121.132 pCi/kg ]

v and

-1 t #

i f F C -Q e = 0.181 pCi/ liter of a v F Mn-54 in goats milk PART C.3.d. : Concentration in Meat: C f

Similar to milk, the concenkration of the nuclide in animal meat is calculated. RG 1.109 general equation C-12 is given as:

-1 t i s' C = F C Q e f f v F l Here the variables are set as:

-4 F := 8.0 10 fraction of animals daily intake of f Mn-54 which appears it, each kg of flesh, in days /kg Q := 50.0 animal's daily feed intake, in F kg/ day t := 20.0 average time from slaughter to a consumption, in days C := 121.132 concentration on Mn-54 in animal's v feed, same as calculated above for goat, in pCi/kg Therefore, the concentration of Mn-54 in animal meat is calculated to be:

i A-16

- On Rn. 8

-1 t i s F C -Q e = 4.635 pCi/kg in meat f v F- ,

for Mn-54 PART D: DOSE FROM INGESTION OF FOODS PRODUCED 'AT MAXIMUM IOCATION Now that we have calculated the concentration of Mn-54 in milk, ,

meat, leafy vegetables, and stored vegetables produced at a i location of maximum air deposition, the resulting dose to any organ j and age group a can be calculated from the following ,

general equation C-13 taken from RG 1.109: i

~

DFI -

'U f C +U C +U C +U f *C :

ija , va g v ma a Fa f La 1 L, l 1

For Mn-54 set equal to 1, we find that from the evaluation of all organs for all age groups for combination of all exposure pathways, the adults GI-III is the critical age group / organ.

Therefore, the variables in the above dose equation can be defined as:

-5 DFI := 1.40 10 ingestion dose factor for ija adults /GI-LLI for Mn-54, in mram/pci ingested (RG 1.109, Table E-11)

U := 520.0 vegetable ingestion rates for va adults, kg/yr f := 0.76 fraction of stored vegetables g grown in the garden f := 1.0 fraction of leafy vegetables 1 grown in the garden U := 310.0 milk ingestion rate for ma adults, liter /yr-A-17 .

ODN Rn. 8

U := 110.0 mest 'ng:ntion i rato for Fa cdulto, kg/yr U := 64.0 leafy. vegetable ingestion La rate for adults, kg/yr C := 67.379 concentration of Mn-54 in

> v stored vegetables, in pCi/kg (from above)

C := 0.181 concentration of Mn-54 in a milk, in pCi/ liter (from above) l C := 4.635 concentration of Mn-54 in f meat, in pCi/kg (from above)

C := 76.811 concentration of Mn-54 in L leafy vegetables, in pCi/kg (from above)

The dose from the combination of ingestion pathways for this example is calculated by substituting the above listed variables back into the ingestion dose equation: , l DFI -

'O f C +U C +U C +U f C = 0.4495 <

ija , va g v ma m Fa f La 1 L, mrem-

/yr per Ci By breaking the above dose equation down into the different pathways which combine to give the total ingestion dese, we can see the individual dose contribution made by each exposure pathway.

Therefore, we have:

Dose for ingestion DFI U *f C = 0.373 of stored vegetables ija va g v Dose for ingestion -4 of goat's milk DFI U C = 7.855 10 ija ma m A-18 ODCM Rev. 8

j . -

b .

l Dose for ingestion DFI U C = 0.00714 l of meat ija Fa. f !

l l

1 Dose for ingestion DFI U f C = 0.0688 of leafy vegetables ija la 1 L l

1 PART E: TOTAL DOSE FROM ALL EXPOSURE PATHWAY l

i The total dose from all exposure pathways assumed to be present at l the maximum receptor location can be found by simply adding the

individual pathway doses calculated above. Since all the calculations above assumed a unit activity release from the plant

! vent stack, the combined dose can be stated as dose factor per unit i activity released. This then demonstrates the development of the i Seabrook ODCM Method I dose factors for gaseous release of 4

prf'?c.alates from the vent stack.

Inhalation dose (Part A) 0.00184 mram/yr per Ci

)

4 Ground plane dose (Part B) 0.658 mram/yr per Ci 1

2 i I Ingestion dose total (Part D) 0.449 mram/yr per Ci l i

j l Total dose all pathways 1.11 mrem /yr per ci j (critical organ is GI-LLI of an adult for Mn-54) .

l i

A-19 -

ODCM Rev. 8 h -- ,

1 APPENDIX B l

l Process Control Program Reauirement: Technical Specification 6.12.2.a requires that licensee initiated changes to the Process Control Program be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change (s) were made.

Resnonse: No changes were made to the Process Control Program during the reporting period.

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APPENDIX C Radioactive Liould EfHuent Monitoring Instrumentation Reauirements: Radioactive Liquid Effluent Monitoring Instrumentation channels are required to be operable in accordance witn Technical Specification 3.3.3.9.b. With less than the minimum number of channels operable for 30 days, Technical Specification 3.3.3.9.b requires an explanation for the delay in correcting the inoperability in the next Annual Effluent Release Report in accordance with Technical Specification 6.8.1.4.

1 Resnonse: A review of the Action Statement Status tracking system for the period from January 1,1995 to December 31,1995 indicated Tech Spec 3.3.3.9 was never entered for more than 30 consecutive days.

i

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r l APPENDIX D 1

Radioactive Gaseous Effluent Monitoring Instrumentation Reauirements: Radioactive Gaseous Effluent Monitoring Instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.10.b. With less than the minimum number of channels operable for 30 days, Technical Specification 3.3.3.10.b requires an explanation for the delay in correcting the inoperability in the next Annual Effluent Release Report it, accordance with Technical Specification 6.8.1.4.

Resoonse: A review of the Action Statement Status tracking system for the period from January 1,1995 to December 31,1995 indicated Tech Spec 3.3.3.10 was never entered for more than 30 consecutive days.

Per Tech. Clarification TS-056, the condenser offgas monitor (1-RM-RM-6505) must be tracked for out-of-service time. This monitor was out of service from 8/17/95 through 9/28/95 per work request 95W002006.

l APPENDIX E l

Liould Holdun Tanks Reauirement: Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any temporary unprotected outdoor tank. With the quantity of radioactive material in any temporary unprotected outdoor tank exceeding the limits of Technical Specifications 3.11.1.4, a description of the events leading in this condition is required in the next Annual Effluent Release Report pursuant to Technical Specification 6.8.1.4.

Resnonse: There were no outside temporary tanks utilized for the storage of radioactive material during the reporting period.

1

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APPENDIX F Radwaste Treatment Systems l Reauirement: Technical Specification 6.14.1.a requires that licensee initiated changes to the Radwaste Treatment Systems (liquid, gaseous, and solid) be submitted to the Commission in the Annual Radioactive Effluent Release Repon for the period in which the change was made.

l Resoonse: During 1995, a vendor-supplied demineralizer skid, as previously identified in the Updated Final Safety Analysis Report (UFSAR), was placed into permanent operation to treat liquid radioactive waste. Prior to establishing the permanent configuration for the demineralizer skid, waste liquid was processed by a skid mounted demineralizer installed under a temporary plant modification. The information required by Technical Specification 6.14.1 is included in Design Coordination Report 91-32, which was reviewed and approved by SORC. I Further changes will be made to the UFSAR to reflect the permanent piping connections used by the vendo -supplied skid upon full implementation of j Design Coordination Report 91-32. l i

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l APPENDIX G j Unolanned Releases Reauirement: Technical Specification 6.8.1.4 requires that the Annual Radioactive Effluent Release Report include a list and description of unplanned releases of l radioactive materials in gaseous and liquid effluents made during the reporting j period from the site to UNRESTRICTED AREAS. l Response: There were no utiplanned releases of radioactive materials from the site to UNRESTRICTED AREAS during the reporting period.

l 1

ENCLOSURE 2 TO NYN-96032 4

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l SEABROOE JAN95-DEC95 MRT DATA JOIKT FREQUENCY DISTRIBUTION (210*FOCrr TOWER) 43.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = 1.47 WIND DIRECTION FROM i

SPEED (MPH) N HNE WE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL l

CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .0. .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .0L .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 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 4-1 0 0 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 2.38 .00 .00 .00 .00 .00 2.38 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .00 .00 .00 .00 .00 .04 8+12 0 0 0 5 1 3 36 10 0 9 13 14 6 2 1 0 0 100 (1) .00 .00 .00 3.97 79 2.38 28.57 7.94 .00 7.14 10.32 11.11 4.76 1.59 .79 .00 .00 79.37 (2) .00 .00 .00 .06 .01 .04 .42 .12 .00 .11 .15 .16 .07 .02 .01 .00 .00 1.17 13-18 1 0 0 3 3 1 1 1 0 2 3 1 1 3 2 1 0 23 (1) 79 .00 .00 2.38 2.18 .79 .79 .79 .00 1.59 2.38 .79 .79 2.38 1.59 .79 .00 18.25 (2) .01 .00 .00 .04 .04 .01 .01 .01 .00 .02 .04 .01 .01 .04 .02 .01 .00 .27 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 1 0 0 8 4 4 37 11 0 11 16 18 7 5 3 1 0 126 (1) .79 .00 .00 6.35 3.17 3.17 29.37 8.73 .00 8.73 12.70 14.29 5.56 3.97 2.38 .79 .00 100.00 (2) .01 .00 .00 .09 .05 .05 .43 .13 .00 .13 .19 .21 .08 .06 .04 .01 .00 1.47 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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SEABROOK JAN95-DEC95 MET DATA JOINT FREQUENCY DISTPIBUTION (210-F00T TOWEit) 43.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = 3.35 WIND DIRECTION FROM SPEED (MPH) W NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRSL TDTAL CALM 0 0 0 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,

I C-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,

I 4-7 0 0 0 0 1 1 2 3 0 1 2 11 4 4 1 3 0 33 I (1) .00 .00 .00 .00 .35 .35 .70 1.05 .00 .35 70 3.83 1.39 1.39 .35 1.05 .00 11.50 l (2) .00 .00 .00 .00 .01 .01 .02 .04 .00 .01 .02 .13 .05 .05 .01 .04 .00 .39 8-12 1 2 2 11 8 14 47 12 1 6 14 23 9 16 10 1 0 177 (1) .35 .70 70 3.83 2.79 4.88 16.38 4.18 .35 2,09 4.88 8.01 3.14 5.57 3.48 .35 .00 61.67 (2) .01 .02 .02 .13 .09 .16 .55 .14 .01 .07 .16 .27 .11 .19 .12 .01 .00 2.07 13-18 1 0 3 8 3 1 4 2 1 0 10 3 6 12 14 0 0 68 i (1) .35 .00 1.05 2.79 1.05 .35 1.39 .70 .35 .00 3.48 1.05 2.09 4.18 4.88 .00 .00 23.69 l (2) .01 .00 .04 .09 .04 .01 .05 .02 .01 .00 .12 .04 .07 .14 .16 .00 .00 .79 j 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 2 ( 1 0 9 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .70 2.09 -35 .00 3.14 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .07 .01 .00 .11 ,

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 2 2 5 19 12 16 53 17 2 7 26 37 19 34 31 5 0 287 (1) .70 .70 1.74 6.62 4.18 5.57 18.47 5.92 .70 2.44 9.06 12.89 6.62 11.85 10.80 1.74 .00 100.00 (2) .02 .02 .06 .22 .14 .19 .62 .20 .02 .08 .30 .43 .22 .40 .36 .06 .00 3.35 (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)ePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH) l l

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SEABROOK JAN95-DEC95 MET DATA JOIsrf FESQUENCY DISTRIBUTION (210* FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 5.71 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESI SE SSE S SSW SW NSW W WNW NW NNW VRBL TOT.SL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 2 (1) .00 .00 .20 .00 .00 .00 .00 .00 00 .00 .20 .00 .00 .00 .00 .00 .00 .41 (2) .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .02 4-7 2 1 2 1 9 4 2 3 3 1 6 6 7 14 9 2 0 72 (1) .41 .20 .41 .20 1.84 .82 .41 .61 .61 .20 1.23 1.23 1.43 2.86 1.84 .41 .00 14.72 (2) .02 401 .0J .01 .11 .05 .02 .04 .04 .01 .07 .07 .00 .16 .11 .02 .00 .84 0-12 5 1 1 24 31 31 27 21 5 8 25 31 36 36 27 3 0 312 (1) 1.02 .20 .20 4.91 6.34 6.34 5.52 4.29 1.02 1.64 5.11 6.34 7.36 7.36 5.52 .61 .00 63.80 (2) .06 .01 .01 .28 .36 .36 .32 .25 .06 .09 .29 .36 42 .42 .32 .04 .00 3.64 13 18 1 0 2 2 3 1 0 1 0 1 7 6 13 30 24 1 0 92 (1) .20 .00 .41 .41 .61 .20 .00 .20 .00 .20 1.43 1.23 2.66 6.13 4.91 .20 .00 18.01 (2) .01 .00 .02 .02 .04 .01 .00 .01 .00 .01 .08 .07 .15 .35 .28 .01 .00 1.07 19 34 0 . 0 0 0 0 0 0 0 0 0 0 1 3 2 5 0 0 11 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .20 .61 .41 1.02 .00 .00 2.25 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .04 .02 .06 .00 .00 .13 0 0 0 0 0 0 0 0 0 0 07 24 0 0 0 0 0 0 0 0

.00 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 -. 0 0 ALL SPEEDS 8 2 6 27 43 36 29 25 8 to 39 44 59 82 65 6 0 489 (1) 1.64 .41 1.23 5.52 0.79 7.36 5.93 5.11 1.64 2.04 7.98 9.00 12.07 16.77 13.29 1.23 .00 100.00 (2) .09 .02 .07 .32 .50 .42 .34 .29 .09 .12 .46 .51 .69 ,96 .76 .07 .00 5.71 (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)ePERCENT OF ALL OOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) l

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.m ,- m.- , < w , , . - . - -- ~. -

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SEABROOK JAN95-DEC95 MET DATA JOIF1' FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCEK!') = 44.72 NIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSN SW WSW W NNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 2 (11 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 03 .03 .00 .00 .00 .00 .00 .05 (2)' .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 00 .00 .00 .02 C-3 28 21 14 18 10 7 11 11 29 14 18 16 13 12 21 25 0 268 (1) .73 .55 .37 .47 .26 .18 .29 .29 .76 .37 .47 .42 .34 .31 .55 .65 .00 7.00 l (2) .33 .25 .26 .21 .12 .08 .13 .13 .34 .36 .21 .19 .15 .14 .25 .29 .00 3.13 1

4-7 134 65 79 76 -99 71 99 113 82 68 62 78 89 122 126 147 0 1510 (1) 3.50 1.70 2.06 1.98 2.58 1.85 2.58 2.95 2.14 1.77 1.62 2.04 2.32 3.18 3.29 3.84 .00 39.42 (2) 1.56 .76 .92 .89 1.16 .83 1.16 1.32 .96 .79 .72 .91 1.04 1.42 1.47 1.72 .00 17.63

, 4-12 50 25 85 86 103 130 68 52 44 56 124 121 147 191 190 56 0 '1528 I

(1) 1.31 .65 2.22 2.24 2.69 3.39 1.77 1.36 1.15 1,46 3.24 3.16 3.84 4.99 4.96 1.46 .00 39.89 (2) .58 .29 .99 1.00 1.30 1.52 .79 .61 .51 .65 1.45 1.41 1.72 2.23 2.22 .65 .00 17.84 ;

. 13a18 1 7 49 27 4 12 5 15 8 11 34 20 48 104 94 8 0 447 l (1) .03 .18 1.28 .70 .10 .31 .13 .39 .21 .29 .89 .52 1.25 2.71 2.45 .21 .00 11.67 (2) .01 08 .57 .32 .05 .14 06 .18 .09 13 .40 .23 .56 1.21 1.10 .09 .00 5.22 19-24 0 0 10 11 1 1 4 1 0 0 2 1 5 12 to 0 0 58 (1) .00 .00 .26 .29 .03 .03 .10 .03 .00 .00 .05 .03 .13 .31 .26 .00 .00 1.51 (2) .00 .00 .12 .13 .01 .01 .05 .01 .00 .00 .02 .01 .06 .14 .12 .00 .00 .68 07 24 0 0 4 7 5 0 0 0 0 0 0 1 0 1 0 0 0 18 (1) .00 00 .10 .18 .13 .00 .00 .00 .00 .00 .00 .03 .00 .03 .00 .00 .00 .47 i (2) .00 .00 .05 .08 .06 .00 .00 .00 .00 .00 .00 .01 .00 .01 .00 .00 .00 .21 !

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! ALL SPEEDS 213 118 241 225 222 221 187 192 163 149 241 238 302 442 441 236 0 3831 l (1) 5.56 3.08 6.2* 5.87 5.79 5.77 4.88 5.01 4.25 3.89 6.29 6.21 7.88 11.54 11.51 6.16 .00 100.00 ;

(2) 2.49 1 38 2.91 2.63 2.59 2.58 2.18 3.24 1.90 1.74 2.81 2.78 3.53 5.16 5.15 2.75 .00 44.72 _

(1)oPERCENT OF ALL COOD OBSERVATIONS FOR THIS PAGE '

l- (2)oPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD l r

C CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) '

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SEABROOK JAN95-DEC95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 28,66 l o WIND DIRECTION FROM l

SPEED (MPH) N NNE NE ENE E' ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 1 0 0 0 2 0 0 0 0 1 1 1 3 1 0 10 (1) .00 .00 .04 .00 .00 .00 .08 .00 .00 .00 .00 .04 .0. .04 .12 .04 .00 .41 (2) .00 .00 .01 .00 .00 .00 .02 .00 .00 .00 .00 .01 .01 .01 .04 .01 .00 .12 C-3 27 17 19 21 22 8 9 14 26 26 39 33 37 59 39 32 0 428 (1) 1.10 .59 .77 .86 .90 .33 .37 .57 1.06 1.06 1.59 1.34 1.51 2.40 1.59 1.30 .00 17.43 (2) .32 .20 .22 .25 .26 .09 .31 .16 .30 .30 .46 .39 .43 .69 .46 .37 .00 5.00 4-7 73 30 27 28 33 27 27 56 63 66 103 163 181 193 164 89 0 1323 (1) 2.97 1.22 1.10 1.14 1.34 1.10 1.10 2.28 2.57 2.69 4.20 6.64 7.37 7.86 6.68 3.63 .00 53.89 (2) .85 .35 .32 .33 .39 .32 .32 .65 .74 .77 1.20 1.90 2.11 2.25 1.91 1.04 .00 15.44 0-12 54 4 5 5 15 13 6 15 16 20 55 121 73 83 65 29 0 579 (1) 2.20 .16 .30 .20 .61 .53 .24 .61 .65 .81 2.24 4.93 2.97 3.38 2.65 1.18 .00 23.58 (2) .63 .05 .06 .06 .38 .25 .07 .28 .19 .23 .64 1.41 .85 .97 .76 .34 .00 6.76 13-18 2 0 0 0 3 4 1 3 2 8 2 1 4 34 25 1 0 90 (1) .08 .00 .00 .00 .12 .36 .04 .12 .08 .33 .08 .04 .16 1.38 1.02 .04 .00 3.67 (2) .02 .00 .00 .00 .04 .05 .01 .04 .02 .09 .02 .01 .05 .40 .29 .01 .00 1.05 19 24 0 0 1 1 2 1 0 1 1 0 0 1 0 7 6 0 0 21 (1) .00 .00 .04 .04 .08 .04 .00 .04 .04 .00 .00 .04 .00 .29 .24 .00 .00 .86 (2) .00 .00 .01 .01 .02 01 .00 .01 .01 .00 .00 .01 .00 .08 .07 .00 .00 .25 GT 24 0 0 0 2 2 0 0 0 0 0 0 0 0 0 0 0 0 4 ti) .00 .00 .00 .08 .08 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .16 (2) .00 .00 .00 .02 .02 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .05 ALL SPEEDS 156 51 53 57 77 53 45 89 108 120 199 320 296 377 302 152 0 2455 (1) 6.35 2.08 2.16 2.32 3.14 2.16 1.83 3.63 4.40 4.89 8.11 13.03 12.06 15.36 12.30 6.19 .00 100.00 (2) 1.82 .60 .62 .67 .90 .62 .53 1.04 1.26 1.40 2.32 3.74 3.46 4.40 3.53 1.77 .00 28.66 (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS FAGE (2). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS FERIOD Ce CALM (WIND SPEED LESS TRAN OR EQUAL TO .95 MPH) l l

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&EASROOK JAN95-DEC95 MBT DATA JOINT FREQUENCY DISTRIBUTION (210-FOCr!' TOWER) 43.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT)

8.60 WIND DIRECTION FROM SPEED (MFH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 1 0 0 3 0 0 1 0 0 0 0 1 1 1 2 1 0 11 (1) .14 .00 .00 .41 .00 .00 .14 .00 .00 .00 .00 .14 .14 .14 .27 .14 .00 1.49 (2) .01 .00 .00 .04 .00 .00 .01 .00 .00 .00 .00 .01 .01 .01 .02 .01 .00 .13 C-3 8 5 13 13 10 3 5 3 10 27 35 38 61 60 33 17 0 341 (1) 1.09 .68 1.76 1.76 1.36 .41 .68 .41 1.36 3.66 4.75 5.16 8.28 8.14 4.48 2.31 .00 46.27 (2) .09 .06 .15 .15 .12 .04 .06 .04 .12 .32 .41 .44 .71 .70 .39 .20 .00 3.98 4-7 4 3 2 2 7 1 5 4 8 8 41 62 66 63 74 23 0 373 (1) .54 .41 .27 .27 .95 .14 .68 .54 1.09 1.09 5.56 8.41 8.96 8.55 10.04 3.12 .00 50.61 (2) .05 .04 .02 .02 .08 .01 .06 .05 .09 .09 .48 .72 .77 .74 .86 .27 .00 4.35 8-12 0 0 0 1 1 0 2 0 0 0 0 3 3 0 1 1 0 12 (1) .00 .00 .00 .14 .14 .00 .27 .00 .00 .00 .00 .41 .41 .00 .14 .14 .00 1.63 (2) .00 .00 .00 .01 .01 .00 .02 .00 .00 .00 .00 .04 .04 .00 .01 .01 .00 .14 13-18 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 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .30 .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 13 8 15 19 18 4 13 7 18 35 76 104 131 124 110 42 0 737 (1) 1.76 1.09 2.04 2.58 2.44 .54 1.76 .95 2.44 4.75 10.31 14.11 17.77 16.82 14.93 5.70 .00 100.00 (2) .15 .09 .38 .22 .21 .05 .15 .08 .21 .41 .89 1.21 1.53 1.45 1.28 .49 .00 0.60 i 1

(1)oPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3)oPERCENT OF ALL GOOD CBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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SEABROOK JAN95-DEC95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 7.49 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 2 0 0 1 0 0 0 1 0 0 0 1 4 1 1 3 0 14 (1) .31 .00 .00 .16 .00 .00 .00 .16 .00 .00 .00 .16 .62 .16 .16 .47 .00 2.18 (2) .02 .00 .00 .01 .00 .00 .00 .01 .00 .00 .00 .01 .05 .01 .01 .04 .00 .16 C-3 4 11 4 4 5 4 5 2 4 7 24 70 105 130 49 14 0 442 (1) .62 1.71 .62 .62 .78 .62 .78 .31 .62 1.09 3.74 10.90 16.36 20.25 7.63 2.18 .00 68.85 (2) .05 .13 .05 .05 .06 .05 .06 .02 .05 .08 .28 .82 1.23 1.52 .57 .16 .00 5.16 4-7 4 2 0 0 4 2 0 0 2 3 16 23 39 57 27 6 0 185 (1) .62 .31 .00 .00 .62 .31 .00 .00 .31 .47 2.49 3.58 6.07 8.88 4.21 .93 .00 28.82 (2) .05 .02 .00 .00 .05 .02 .00 .00 .02 .04 .19 .27 .46 .67 .32 .07 .00 2.16 8 12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,00 .16 .00 .00 .16 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .01 13-18 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 19 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 10 13 4 5 9 6 5 3 6 10 40 94 148 188 78 23 0 642 (1) 1.56 2.02 .62 78 1.40 .93 .78 .47 .93 1.56 6.23 14.64 23.05 29.28 12.15 3.58 .00 100.00 (2) .12 .15 .05 .06 .11 .07 .06 .04 .07 .22 .47 1.10 1.73 2.19 .91 .27 .00 7.49 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2) PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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I SEABROOK JAN95-DEC95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM I

SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWW NW NNW VRBL TOTAL l CALM 3 0 1 4 0 0 3 1 0 0 1 4 6 3 6 5 0 37 (1) .04 .00 .01 .05 .00 .00 .04 .01 400 .00 .01 .05 .07 .04 .07 .06 .00 .43 (2) .04 .00 .01 .05 .00 .00 .04 .01 .00 .00 .01 .05 .07 .04 .07 .06 .00 .43 C 67 54 51 56 47 22 30 30 69 74 117 157 216 261 142 88 0 1481 (1) .78 .63 .60 .65 .55 .26 .35 .35 481 .86 1.37 1.83 2.52 3.05 1.66 1.03 .00 17.29 l

(2) .78 .63 .60 .65 .55 .26 .35 .35 .81 .86 1.37 1.83 2.52 3.05 1.66 1.03 .00 17.29 4-7 217 101 110 107 153 106 135 179 158 147 230 346 386 453 401 270 0 3499 (1) 2.53 1.18 1.28 1.25 1.79 1.24 1.58 2.09 1.84 1,72 2.68 4.04 4.51 5.29 4.68 3.15 .00 40.04 (2) 2.53 1.18 1.28 1.25 1.79 1.24 1.58 2.09 1.84 1.72 2.68 4.04 4.51 5.29 4.58 3.15 .00 40.84 0-12 110 32 93 132 159 191 186 110 66 99 231 313 274 328 295 90 0 2709 (1) 1.28 .37 1.09 1.54 1.86 2.23 2.17 1.28 .77 1.16 2.70 3.65 3.20 3.83 3.44 1.05 .00 31.62 (2) 1.28 .37 1.09 1.54 1.86 2.23 2.17 1.28 .77 1.15 2.70 3.65 3.20 3.83 3.44 1.05 .00 31.62 13-18 6 -7 54 40 16 19 11 22 11 22 56 31 72 183 159 11 0 720 (1) .07 .08 .53. .47 .19 .22 .13 .26 .13 .26 .65 .36 .84 2.14 1.86 .13 .00 8.40 (2) .07 .08 .63 .47 .19 .22 .13 26 .13 .26 .65 .36 .84 2.14 1.86 .13 .00 8.40 19-24 0 0 11 12 3 2 4 2 1 0 2 3 8 23 27 1 0 99 (1) .00 .00 .13 .14 .04 .02 .05 .02 .01 .00 .02 .04 .09 .27 .32 .01 . 00 1.16 (2) .00 .00 .13 .34 .04 .02 .05 .02 .01 .00 .02 .04 .09 .27 .32 .01 .00 1.16 GT 24 0 0 4 9 7 0 0 0 0 0 0 1 0 1- 0 0 0 22 (1) .00 .00 .05 .11 .08 ,00 .00 .00 .00 .00 .00 .01 .00 .01 .00 .00 .00 ,26 (2) .00 .00 .05 .11 .00 . 00 .00 .00 .00 .00 00 .01 .00 .01 .00 .00 .00 .26 ALL SPEEDS 403 194 324 360 385 340 369 344 305 342 637 855 962 1252 1030 465 0 8567 (1) 4.70 2.26 3.78 4.20 4.49 3.97 4.31 4.02 3.56 3.99 7.44 9.98 11.23 14.61 12.02 5.43 .00 100.00 (2) 4.70 2.26 3.78 4.20 4.49 3.97 4.31 4.02 3.56 3.99 7.44 9.95 11.23 14.51 12.02 5.43 .00 100.00 (llePERCENT OF ALL COOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

SEABROOE JAN95-DEC95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 209.0 FT WINP DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = 1.47 WIND DIRECTION F' M SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W NNW NW NNW VRBL 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 C-3 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 4-7 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .79 .79 .00 .00 .00 .00 .00 1.59 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .00 .00 .02 0-12 0 0 1 2 1 3 19 3 0 4 4 9 1 1 0 0 0 48 (1) .00 .00 .79 1.59 .79 2.38 15.08 2.38 .00 3.17 3.17 7.14 .79 .79 .00 .00 .00 38.10 (2) .00 .00 .01 .02 .01 .04 .21 .04 .00 .05 .05 .11 ., 01 .01 .00 .00 .00 .56 13-18 0 0 3 3 4 1 11 12 0 5 9 8 4 4 1 0 0 66 (1) .00 .00 2.38 2.38 3,17 .79 8.73 9.52 .00 4.76 7.14 6.35 3.17 3.17 .79 .00 .00 52.38 (2) .00 .00 .04 .04 .05 .01 .13 .14 .00 .07 .11 .09 .05 .05 .01 .00 .00 .77 19-24 2 0 0 0 0 0 1 0 0 0 2 1 0 2 2 0 0 10 '

(1) 1.59 .00 .00 .00 .00 .00 .19 .00 .00 .00 1.59 .79 .00 1,59 1.59 .00 .00 7.94 (2) .02 .00 .00 .00 .00 .00 .01 .00 .00 .00 .02 .01 .00 .02 .02 .00 .00 .12 )

0 0 0 0 0 0 0 0 0 0 0 GT 24 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 2 0 4 5 5 4 31 15 0 10 16 19 5 7 3 0 0 126 (1) 1.59 .00 3.17 3.97 3.97 3.17 24.60 11.90 .00 7.94 12.70 15.08 3.97 5.56 2.38 .00 .00 100.00 (2) .02 .00 .05 .06 .06 .05 .36 .18 .00 .22 .19 .22 .06 .08 .04 .00 .00 1.47 (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C. CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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i SEABROOE JAN95-DEC95 MRT DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 209.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) e 3.36 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W NNW WW NNW VRBL 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 .LO (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0a .00 C-3 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 4-7 1 0 0 1 1 0 1 1 0 0 2 6 1 1 2 0 0 17 (18 .35 .00 .00 .35 .35 .00 .35 .35 .00 .00 .70 2.09 .35 .35 .70 .00 .00 5.92 (2) .01 .00 .00 .01 .01 .00 .01 .01 .00 .00 .02 .07 .01 .01 .02 .00 .00 .20 0-12 1 2 1 9 5 8 32 8 1 5 5 14 9 12 6 1 0 119 (1) .35 .70 .35 3.14 1.74 2.79 11.15 2.79 .35 1.74 1.74 4.88 3.14 4.18 2,09 .35 .00 41.46 (2) .01 .02 .01 .11 .06 .09 .37 .09 .01 .06 .06 .16 .11 .14 .07 .01 .00 1.39 4 13-18 1 1 4 10 3 2 16 14 0 3 14 10 10 17 8 1 0 114 (1) .35 .35 1.39 3.48 1.05 .70 5.57 4.88 .00 1.05 4.88 3.48 3.48 5.92 2.79 .35 .00 39.72 (2) .01 .01 .05 .12 .04 .02 .19 .16 .00 .04 .26 .12 .22 .20 .09 .01 .00 1.33 19-24 0 0 3 0 0 0 0 2 1 0 5 3 2 8 5 0 0 29 (1) .00 .00 1.05 .00 .00 .00 .00 .70 .35 .00 1.74 1.05 .70 2.79 1.74 .00 .00 10.10 (2) .00 .00 .04 .00 .00 .00 .00 .02 .01 .00 .06 .04 .02 .09 .06 .00 .00 .34

. GT 24 0 0 0 0 0 0 0 0 0 0 0 0 1 2 4 1 0 8 l (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .35 .70 1.39 .35 .00 2.79 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .02 .05 .01 .00 .09 ALL SPEEDS 3 3 8 20 9 10 49 25 2 8 26 33 23 40 25 3 0 287 (1) 1.05 1.05 2.79 6.97 3.14 3.48 17.07 8.71 .70 2.79 9.06 11.50 8.01 13.94 8.71 1.05 .00 100.00 (2) .04 .04 .09 .23 .11 .12 .57 .29 .02 .09 .30 .39 .27 .47 .29 .04 .00 3.36 (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2). PERCENT OF ALL OOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) i I

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SEABROOK JAN95.DEC95 NET DATA JOINT FREQUENCY DISTRIBUTION (210*FOCrf TOWER) $

1 209.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 5.72 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE dE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CAIJE O O O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 $

(1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l

.00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 00 .00 .00 . .00 .00 i

C-3 0 0' 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 2 i (1) .00 .00 .20 .00 .00 .00 .00 .00 .00 .00 .20 .00 .00 .00 .00 .00 .00 .41 (2) .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .02 ,

f 4*7 4 2 0 2 6 3 3 1 0 2 5 3 5 8 ) 1 0 48 !

(1) .82 .41 .00 .41 1.23 .61 .61 .20 .00 .41 1.02 .61 1.02 1.64 .61 .20 .00 9.82 (2) .05 .02 400 .02 .07 .04 .04 .01 .00 02 .06 .04 .06 .09 .04 .01 .00 .56 8 12 3 1 0 25 30 17 28 16 5 4 12 22 19 23 12 2 0 227 I (1) .61 .20 1.64 5.11.6.13 3.48 5.73 3.27 1.02 .82 2.45 4.50 3.89 4.70 2.45 .41 .00 46.42 (2) .04 .01 .09 .29 .35 .20 .33 .19 .06 .05 .14 .26 .22 .27 .14 02 .00 2.65

]

13 18 2 0 2 4 3 2 1 5 3 6 14 13 30 45 26 0 0 162 (1) .41 .00 .41 .82 .61 .41 1.43 1.02 .61 1.23 2.86 2.66 6.13 9.20 5.32 .. 00 .00. 33.13 (2) .02 .00 .02 .05 .04 .02 .08 .06 .04 .07 .16 .15 .35 .53 .30 .00 .00 1.89 ,2 l'

19 24 1 0 0 0 0 0 0 1 0 3 2 2 10 15 6 0 0 40 (1) .30 .00 .00 .00 .00 .00 .00 .20 .00 .61 .41 .41 2.04 3.07 1.23 .00 .00 8.18 (2) .01 .00 .00 .00 .00 .00 .00 .01 .00 .14 .02 .02 .12 .18 .07 .00 .00 .47 GT 24 0 0 0 0 0 0 0 0 0 0 0 2 2 3 2 1 0 10 I (1) .00 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .41 .41 .61 .41 .20 .00 2.04 (2) .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .02 .02 .04 .02 .01 .00 .12 ALL SPEEDS 10 3 11 31 39 22 38 23 8 15- 34 42 66 94 49 4 0 489 (1) 2.04 .61 2.25 6.34 7.98 4.50 7.77 4.70 1.64 3.07 6.95 8.59 13.50 19.22 10.02 .82 .00 100.00 (2) .12 .04 .13 .36 .46 .26 .44 .27 .09 .18 .40 .49 .77 1.10 .57 .05 .00 5.72 (1)ePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)ePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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e SEASROOE JAN95-DEC95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWE8t) '

809.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 44.77 WIND DIRECTION FROM

$PRED(MrH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W NNW NW NNW VRBL 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 C-3 12 15 9 17 9 4 6 4 7 13 9 9 10 8 10 17 0 159 (1) .31 .39 .24 .44 .24 .10 .16 .10 .18 .34 .24 .24 .26 .21 .26 .44 .00 4.15 (2) - .14 .18 .11 .20 .11 .05 .07 .05 .08 .15 .11 .31 .12 .09 .12 .30 .00 1.86 4-7 90 56 38 54 70 54 81 63 54 36 39 27 38 43 58 10 0 871 (1) 2.35 1,46 ,99 1.41 1.83 1.41 2.12 1.65 1,41 .94 1.02 .71 .99 1.12 1.51 1.83 .00 22.75 (2) 1.05 .65 .44 .63 .82 .63 .95 .74 .63 .42 .46 .32 .44 .50 -. 6 8 .82 .00 10.18 P-12 136 75 67 77 70 110 98 96 65 65 96 99 91 130 129 111 0 1515 (1) 3.55 1.96 1.75 2.01 1.83 2.87 2.56 2.51 1.70 1.70 2.51 2.59 2.38 3.40 3.37 2.90 .00 39.57 (2) 1.59 .88 78 .90 .82 1.29 1.15 1.12 .76 76 1.12 1.16 1.06 1.52 1.51 1.30 .00 17.71 13-18 22 35 67 29 6 19 19 38 34 43 91 64 117 195 148 19 0 946 (1) .57 .91 1.75 .76 .16 .50 .50 .99 .89 1.12 2.38 1.67 3.06 5.09 3.87 .50 .00 24.71 (2) .26 .41 .78 .34 07 .22 .22 .44 .40 .50 1.06 .75 ,1.37 2.28 1,73 .22 .00 11.06 19 24 4 8 23 8 1 5 3 11 7 9 23 1 32 59 38 2 0 239 (1) .10 .21 .60 .21 .03 .13 .08 .29 .18 .21 .60 .28 .84 1.54 .99 .05 .00 6.24 (2) .05 .09 .27 .09 .01 .06 .04 .13 .08 .09 .27 .08 .37 .69 .44 .02 .00 2.79 GT 24 0' 1 18 10 6 5 7 3 0 0 2 2 13 18 12 2 0 99 (1) .00 .03 .47 .26 .16 .13 .18 .08 .00 .00 .05 .05 .34 .47 .31 .05 .00 2.59 (2) .00 . 01 .21 .22 .07 .06 .08 .04 .00 .00 .02 .02 .15 .21 .14 .02 .00 1.16 ALL SPEEDS 264 190 222 195 162 197 214 215 167 165 460 208 301 453 395 221 0 3829 (1) 6.89 4.96 5.80 5.09 4.23 5.14 5.59 5.62 4.36 4.31 6.79 5.43 7.86 11.83 10.32 5.17 .00 100.00 (2) 3.09 2.22 2.60 2.28 1.89 2.30 2.50 2.51 1.95 1.!* 3.04 2,43 3.52 5.30 4.62 2.58 .00 44.77 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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SEABROOK JAN95-DEC,95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) ,

809.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 28.67 i WIND DIRECTION FROM ,

1 SPEED (MPH) N WNE NE ENE E ESE SE SSE S SSW SW WSW W WWW WW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L til .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

^

C-3 7 5 5 2 6 9 5 14 7 9 8 11 5 7 4 2 0 106 (1) .29 .20 .20 .08 .24 .37 .20 .57 .29 .37 .33 .45 .20 .29 .16 .08 .00 4.32 >

(2) .00 .06 .06 .02 .07 .11 06 .16 .08 .11 .09 .13 .06 .08 .05 .02 .00 1.24 l 4-7 43 22 22 23 19 24 37 28 33 26 23 23 26 29 51 27 0 456 !

(1) 1.75 .90 .90 .94 .77 .98 1.51 1.14 1.35 1.06 . 94 . ,94 1.06 1.18 2.00 1.10 .00 18.60 (2) .50 .26 .26 .27 .22 .28 .43 .33 .39 .30 .27 .27 .30 .34 .60 .32 .00 5.33 ;

8-12 122 22 29 16 11 10 15 45 65 74 122 100 115 169 119 115 0 1149 +

(1) 4.98 .90 1.18 .65 .45 .41 .61 1.84 2.65 3.02 4.98 4.00 4.69 6.09 4.85 4.69 .00 46.86 (2) 1.43 .26 .34 .19 .13 .12 .18 .53 .76 '.87 1.43 1.17 1.34 1.98 1.39 1.34 .00 13.43 4 i

13-18 27 9 6 1 4 3 5 15 17 27 65 143 111 117 71 7 0 628 (1) 1.10 .37 .24 404 .16 .12 .20 .61 .69 1.10 2.65 5.03 4.53 4.77 2.90 .29 .00 25.61 !

(2) .32 .11 .07 .01 .05 .04 .06 .18 .30 .32 ,76 1.67 1.30 1.37 483 .08 .00 7.34 19-24 6 2 1 0 2 3 1 1 1 7 3 3 8 34 12 2 0 86 f (1) .24 .08 .04 .00 .08 .12 .04 .04 .04 .29 .12 .22 .33 1.39 .49 .08 .00 3.51 (2) .07 .02 .01 .00 .02 .04 .01 .01 401 .08 .04 .04 .09 .40 .14 .02 .00 1.01 GT 24 0 0 0 3 5 1 1 1 1 1 0 1 0 9 4 0 0 27 i (1) .00 .00 .00 .12 .20 .04 .04 .04 .04 .04 00 .04 .00 . .37 .16 .00 .00 1.10 l (2) .00 .00 .00 .04 .06 .01 .01 .01 .01 .01 .00 .01 .00 .11 .05 .00 .00 .32 l 1

ALL SPEEDS 205 60 63 45 47 50 64 104 124 144 221 281 265 365 261 153 0 2452 (1) 8.36 2.45 2.57 1.84 1.92 2.04 2.61 4.24 5.06 5.07 9.01 11.46 10.01 14.89 10.64 6.24 .00 100.00 (2) 2.40 .70 .74 .53 .55 .58 .75 1.22 1.45 1.68 2.58 3.29 3.10 4.27 3.05 1.79 .00 28.67 (1)oPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3) PERCEFF OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Co CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) i i

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l SEABROOK JAN95-DEC95 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOCT TOWER) 209.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 0.61 WIND DIRECTION FROM CPEED(MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W KNW NW NNW VRBL 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 0 4 4 6 1 1 2 1 2 3 2 2 3 0 6 2 0 39 (1) .00 .54 .54 .82 .14 .14 .27 .14 .27 41 .27 .27 .41 .00 .82 .27 .00 5.30 (2) .00 .05 .05 .07 .01 .01 .02 .01 .02 .04 .02 .02 .04 .00 .07 02 .00 .46 47 6 9 6 5 3 6 8 13 14 21 12 11 14 15 6 8 0 157 (1) .82 1.22 .82 .68 .41 .82 1.09 1,77 1.90 2.85 1.63 1.49 1.90 2.04 .82 1.09 .00 21.23 (2) .07 .11 .07 .06 .04 .07 .09 .15 .16 .25 .14 .13 .16 .18 .07 .09 .00 1.84 4-12 30 7 3 3 5 0 3 13 21 46 44 34 33 55 51 36 0 384 (1) 4.08 .95 .41 .41 .68 .00 .41 1.77 2.85 6.25 5.98 4.62 4.48 7.47 6.93 4.89 .00 52.17 (2) .35 .08 .04 .04 .06 .00 .04 .15 .25 .54 .51 .40 .39 .64 .60 .42 .00 4.49 13-18 10 1 1 0 1 0 0 3 3 3 16 36 31 22 12 16 0 155 (1) 1.36 .14 .14 .00 .14 .00 .00 .41 .41 .41 2.17 4.89 4.21 2.99 1.63 2.17 .00 21.06 (2) .12 .01 .01 .00 .01 .00 .00 .04 .04 .04 .19 .42 .36 .26 .14 .19 .00 1.81 19-24 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .24 .00 .00 .00 .00 .00 .00 .00 .00 .00 .14 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 OT 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 46 21 14 14 10 7 13 31 40 73 74 83 81 92 75 62 0 736 (1) 6.25 2.85 1.90 1.90 1.36 .95 1.77 4.21 5.43 9.92 10.05 11.28 11.01 17.50 10.19 8.42 .00 100.00 (2) .54 .25 .16 .16 .22 .08 .15 .36 .47 .85 .87 .97 .95 1.08 .88 .72 .00 8.61 (1)= PERCENT OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2) PERCENT OF ALL GOOD OBSERVATIONS FOR THIS FERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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SEABROOE JAN95-DEC95 MET DATA JOINT FREQtJENCY DISTRIBUTION (210-FOOT TOWER) 809.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) e 7,41 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE 'S SSW SW WSW W WNW NW NNW VRBL 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 C-3 0 0 2 1 2 4 4 2 3 4 7 5 4 2 2 4 0 46 (1) .00 .00 .32 .16 .32 .63 .63 .32 .47 .63 1.10 .79 .63 .32 .32 .63 .00 7.26 (2) .00 .00 .02 .01 .02 .05 .05 .02 .04 .05 .08 .06 .05 .02 .02 .05 .00 .54 4-7 17 4 11 3 3 5 7 9 12 20 26 24 18 23 30 18 0 230 (1) 2.68 .63 1.74 .47 .47 .79 1.10 1,42 1.89 3.15 4.10 3.79 2.84 3 63 4.73 2.84 .00 36.28 (2) .20 .05 .13 .04 .04 .06 .08 .11 .14 .23 .30 .28 .21 .27 .35 .21 .00 2.69 8-12 22 4 2 3 4 0 2 11 17 18 33 29 31 41 30 37 0 284 (1) 3.47 .63 .32 .47 .63 .00 .32 1.74 2.68 2.84 5.21 4.57 4.89 6.47 4.73 5.84 .00 44.79 (21- .26 .05 .02 ,04 .05 .00 .02 .13 .20 .21 .39 .34 .36 .48 .35 .43 .00 3.32 13-18 5 3 0 0 0 0 0 1 3 4 8 15 13 11 6 5 0 74 (1) .79 .47 .00 .00 .00 .00 .00 .16 .47 .63 1.26 2.37 2.05 1.74 .95 .79 .00 11.67 (2) .06 .04 .00 .00 .00 .00 .00 .01 04 .05 .09 .18 .15 .13 .07 .06 .00 .87 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (3) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0- 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 44 11 15 7 9 9 13 23 35 46 74 73 66 77 68 64 0 634 (1) 6.94 1.14 2.37 1.10 1.42 1.42 2.05 3.63 5.52 7.26 11.67 11.51 10.41 12.15 10.73 10.09 .00 100.00 (2) .51 .13 .18 .08 .11 .31 .15 .27 .41 .54 .87 .85 .77 .90 .80 .75 .00 7.41 (1) PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (3) PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND EPEED LESS THAN OR EQUAL TO .95 MPH) l l

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SEABROOE JAN95 DEC95 MET DATA JOINT FREQUENCY DISTRIBUTIDW (210-FDOT TOWER) ;

209.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL 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 i (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 19 24 21 26 18 18 17 21 19 29 27 27 ' 22 17 22 25 0 352 (1) .22 .28 .25 .30 .21 .21 .20 .25 .22 .34 .32 .32 .26 .20 .26 .29 .00 4.12 l i

(2) .22 .28 .25 .30 .21 .21 .20 .25 .22 .34 .32 .32 .26 .20 .26 .29 .00 4.12

]

4-7 161 93 77 84 102 92 137 115 113 105 108 95 102 119 130 124 0 1781

.(1) 1.88 1.09 .90 1.03 1.19 1.08 1.60 1.34 1.32 1.23 1.26 1.11 1.19 1.39 1.75 1.45 .00 20.82 (2) 1.88 1.09 .90 1.03 1.19 1.08 1.60 1.34 1.32 1.23 1.26 1.11 1.19 1.39 1.75 1.45 .00 20.82 8-12 114 til 111 135 126 148 197 192 174 216 316 307 299 431 347 302 0 3726 i (1) 3.67 1.30 1.30 1.58 1.47 1.73 2.30 2.24 2.03 2.53 3.69 3.59 3.50 '5.04 4.06- 3.53 .00 43.56 (2) 3.67 1.30 1.30 1,58 1.47 1.73 2.30 2.24 2.03 2.53 3.69 3.59 3.50 5.04 4.06 3.53 .00 43.56 13-18 67 49 83 47 21 27 58 88 60. 92 217 289 316 411 272 40 0 2145 (1) .78 .57 497 .55 .25 .32 .68 1.03 .70 1.08 2.54 3.38 3.69 4.81 3.18 .56 .00 25.08 (2) .78 .57 .97 .55 .25 .32 .68 1.03 .70 1.08 2.54 3.38 3.69 4.81 3.18 .56 .00 25.08 l 19-24 13 10 27 8 3 8 5 16 9 18 35 16 52 118 63 4 0 405 (1) .15 .12 .32 .09 .04 .09 .06 .19 .11 ,21 .41 .19 .61 1.38 .74 .05 .00 4.74 (2) .15 .12 .32 .09 .04 .09 .06 .19 .11 .21 .41 .19 .61 1.38 .74 .05 .00 4.74 GT 24 0 1 18 13 11 6 8 4- 1 1 2 5 16 32 22 4 0 144 (1) .00 .01 .21 .15 .13 .07 .09 .05 .01 .01 .02 .06 .19 .37 .26 .05 .00 1.68 (2) .00 .01 .31 .15 .13 .07 .09 .05 01 .01 .02 .06 .19 .37 .26 .05 .00 1.68 ALL SPEEDS 574 288 337 317 281 299 422 436 376 461 705 739 807 1128 876 507 0 8553 (1) 6.71 3.37 3.94 3.71 3.29 3.50 4.93 5.10 4.40 5.39 8.24 8.64 9.44 13.19 10.24 5.93 .00 100.00 (2) 6.71 3.37 3.94 3.71 3.29 3.50 4.93 5.10 4.40 5.39 8.24 8.64 9.44 13.19 10.24 5.93 .00 100.00 (1). PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) l l

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e ENCLOSURE 3 TO NYN-96032 i

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i Seabrook Station l Supplemental Effluent Release Report Radiological Impact Assessment for 1995 I. Summary Doses resulting from liquid and gaseous effluents from Seabrook Station during 1995 were calculated in accordance with Method II as defined in the I Station Offsite Dose Calculation Manual (CDCM). The calculational methods used follow the models in Regulatory Guide 1.109. The calculations included !

maximum whole body doses and organ doses from all liquid releases, maximum offsite organ doses resulting from airborne iodines, tritium and particulate '

radionuclides, and maximum offsite beta air and gamma air doses from airborne noble gases. Doses were also calculated for the special receptor locations inside the site boundary: the Science and Nature Center and the " Rocks". In j addition, the direct dose from plant operation was calculated. These doses from effluent releases and direct shine during 1995 are summarized in Table A. l The calculated maximum annual total body dose and the maximum organ dose from liquid effluents each represent 0.02% of the annual dose limits established by Technical Specification 3.11.1.2 (3 mrem total body and 10 mrem organ). The calculated annual maximum dose from airborne iodine, tritium and particulate radionuclides for offsite receptor locations represents 0.02% of the dose limit established by Technical Specification 3.11.2.3 (15 mrem organ), whereas the calculated maximum annual beta air and gamma air doses from airborne noble gases for offsite receptor locations represent, respectively 0.001% and 0.005% of the dose limits established by Technical Specification 3.11.2.2 (20 mrad beta air and 10 mrad gamma air). The calculated annual beta air and gamma air doses from airborne noble gases for the Science and Nature Center were 0.0000004% and 0.000001% of the limits in Technical Specification 3.11.2.2. Whereas for the " Rocks" the annual doses were 0.0001% and 0.0002% of the limits in Technical Specification 3.11.2.2.

The calculated annual doses from airborne iodines, tritium and particulate radionuclides at the Science & Nature Center and the " Rocks" were, respectively 0.002% and 0.05% of the limits in Technical Specification 3.11.2.3.

The sum of the maximum whole body doses from all exposure pathways for the liquid and gaseous effluents, plus the direct whole body dose from station operation. was 3.2E-3 mrem to a hypothetical individual. This whole body dose represents 0.01% of the annual whole body dose limit (25 mrem) for a member of the public as set forth in 40CFR190. and demonstrates compliance with that nuun code. The maximum organ dose from all exposure pathways including direct dose was 5.1E-3 mrem. This represents 0.02% of the annual organ dose limit of 25 mrem, as set forth in 40CFR190.

mun

11. Method for Calculating the Total Body and Maximum Organ Doses Resultino from Liauid Releases The computer code IDLE, which is consistent with the models in Regulatory Guide 1.109 (Reference 1), was used to calculate the total body and organ doses resulting from liquid effluents from Seabrook Station. The general equations A-3. A-4, A-5, A-6 and A-7 from Regulatory Guide 1.109 are applied in IDLE. The total body doses and the organ doses are evaluated for each of the four age groups (i.e., infant, child, teen and adult) to determine the maximum total body dose and maximum organ dose via all existing exposure pathways (i.e., fish and aquatic invertebrate ingestion, and shoreline exposure) to an age-dependent individual. The values for the various factors considered in equations A-3 through A-7 have been taken from Regulatory Guide 1.109 and the Station Offsite Dose Calculation Manual (0DCM) (Reference 2).

The specific values used for the usage factor (Uap), mixing ratio (Mp ),

bioaccumulation factor (Bjp), dose factors (Daipj), transit time (tp ),

transfer constant from water to sediment (Kc), exposure time for sediment or soil (t ),b and shore width factor (W) are provided by the reference sources as summarized in Table B. The ficw rate of the liquid effluent (F) and the radionuclide activities (0 )5 are measured specifically prior to each liquid release. The values for half lives for radionuclides (Tj ) and their radioactive decay constants (Aj) have been taken from Kocher (Reference 3).

The exposure pathways considered in the calculations of total body and maximum organ doses resulting from liquid discharges from Seabrook Station have been limited to ingestion of aquatic foods and exposure to shoreline deposits. The dose calculations do not include the ingestion of potable water and irrigated vegetation as potential exposure pathways because the liquid effluents from the plant are discharged into salt water.

Table A presents the calculated liquid pathway doses for each calendar !

quarter and also the total for the year.

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i nuun III. Method for Calculating the Ghmma and Beta Air Doses from Noble Gases The computer codes AIRAD and AE0LUS 2 (Mod 06) were used for the calculation of both the gamma and beta air doses resulting from noble gases present in gaseous effluents released from Seabrook Station. The features and use of AEOLUS 2 for the calculation of atmospheric dispersion factors (i.e.,

Chi /0 f actors) from recorded meteorological data (i.e., meteorological data measurements taken during the time of the release) are described in section B.7.3.2 of Seabrook's ODCM. Meteorological dispersion factors concurrent with periods of batch gas releases are calculated along with the values for quarterly average dispersion f actors. The atmospheric dispersion factors calculated using AEOLUS 2 were, in turn, used in the gamma and beta air dose calculations by AIRAD. AIRAD is consistent with the models presented in Regulatory Guide 1.109, general equations B-4 and B-5. The values for the dose factors, DFJ and DF 3, have been taken from Table 8-1 in Regulatory 0

Guide 1,109.

Table A lists the calc;1ated air doses for each calendar quarter, and the total for the year.

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IV. Method for Calculatino the Critical Orqan Cose Resultino from lodines.

Tritium and Particulates with T uz Greater than 8 Days in Gaseous Releases 4

)

The computer codes AE0LUS 2 (Mod 06) and ATMODOS were used for the calculation of the organ doses resulting from iodines, tritium and particulates with half-lives greater than 8 days present in gaseous effluents released from Seabrook Station. The features and use of AEOLUS 2 for the j calculation of atmospteric dispersion factors (i.e., Chi /0 factors) from recorded meteorological data (i.e., meteorological data measurements taken l during the time of the release) are described in section B.7.3.2 of Seabrook's 1 ODCM. Meteorological dispersion factors concurrent with periods of batch gas l releases were calculated along with the values for quarterly average dispersion factors. The atmospheric dispersion factors calculated using AE0LUS 2 were, in turn, used in the dose calculations by ATMOD05. ATMODOS calculates the organ doses ( i.e., dose to bone, liver, kidney, lung, lower large intestine, total body, and skin) due to the presence of radionuclides other than noble gases in gaseous effluents, and is consistent with the models l

presented in Appendix C of Regulatory Guide 1.109. The pathways considered in i the dose calculations are the ground plane, inhalation, and ingestion of stored vegetables, fresh garden vegetables, milk and meat. The critical organ dose is determined for the offsite location (e.g., site boundary, nearest resident or farm) of receptor pathways as identified in the most recent annual land use census. The total body dose contributions via the ground plane and inhalation pathways as calculated by ATMODOS have also been included in the total body dose estimates for the special receptor locations inside the site boundary. Equations C-1 through C-13 are applied in the ATMODOS calculation of the critical organ doses. The input data and assumptions are those provided in Appendix C of Regulatory Guide 1.109, except where site-specific data and assumptions have been identified in Tables B.7-2 and B.7-3 of Seabrook's ODCM. These two ODCM tables provide the options for special conditions, depending on the type of receptor being evaluated at a specific location, that are to be applied in Method.II calculations. The receptor type controls the exposure pathways for calculational purposes. The receptor types used in the dose calculations were a resident receptor (which considered the ground plane, inhalation and vegetable ingestion exposure pathways), a milk receptor (which considered'the ground plane, inhalation, vegetable and milk ingestion exposure pathways) and a boundary and radius receptor (both of which considered the ground plane and inhalation exposure pathways). The resident l and milk receptor locations for the various sector were based on the 1995 land use census data for Seabrook Station (Table D). The radius receptor locations 1

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nzuo l were applied at several distances in each sector to insure that the location l

cf .htonaximum doses were not overlooked.

Depletion of the plume during transport is considered by AE0LUS 2 in the <

calculations of atmospheric dispersion f actors (e.g., calculation of [.(/0]D), l A shielding factor (Sp) of 0.7 is applied for residential structures. The source for the values of the various factors used in equations C-1 through l

C-13 are summarized in Table C.

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V. REFERENCES

1. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR Part 50.

Appendix I. Reg. Guide 1.109. Rev 1, Oct. 1977.

2. Station Offsite Dose Calculation Manual, Rev 15.

3. Kocher D.C., Dose-Rate Conversion Factors for Exposure to Photons and Electrons Health Physics, Vol . 45, No. 3. Sept.1983.

orurt _ _ _

TABLE A Seabrook Station Effluent and Waste Disposal Semiannual Report 1995 Maximum (a) Off-Site Doses and Dose Commitments to Members of the Public Dose (mrem)(b) l 1st l 2nd 3rd 4th Quarter Quarter Quarter Quarter Year (c) l Liquid Effluents:

Total Body Dose 9.4E-05 8.1E-05 1.0E-04 4.0E-04 6.8E-04

! (1) (2) (1) (2)

Organ Dose 4.2E-04 3.2E-04 4.1E-04 1.2E-03 2.4E-03 (3) (3) (3) (3)

Airborne Effluents:

Organ Dose from Iodines, 2.4E-04 1.1E-04 1.8E-05 2.0E-03 2.4E-03 Tritium, and Particulates (4) (5) (6)

(7)

Noble Gases Beta Air 1.9E-05 2.2E-05 9.6E-05 9.2E-05 2.3E-04 (mrad) (8) (9) (10) (11) i Gamma 3.3E-05 4.3E-05 2.3E-04 1.7E-04 4.8E-04 i

Air (8) (12) (10) (11)

(mrad) i Doses (mrem) at Receptor Locations Inside Site Boundary (d).

L Science and Nature Center (SW, l 488m):

Beta Air Dose (mrad) 7.0E-08 ---

7.8E-09 ---

7.8E-08 Gamma Air Dose (mrad) 9.6E-08 ---

4.8E-08 ---

1.4E-07 Organ Dose (mrem) 4.5E-06 ---

1.0E-06 2.4E-04 2.4E-04 (13) (14) (15)

The " Rocks" (NE/ENE. 244m):

Beta Air Dose (mrad) 1.9E-06 7.7E-06 2.9E-06 1.5E-05 2.8E-05 Gamma Air Dose (mrad) 1.6E-06 4.0E-06 2.5E-06 9.3E-06 1.7E-05 l Organ Dose (mrem) 5.8E-05 9.2E-04 4.0E-05 6.1E-03 7.1E-03 (13) (13) (13) (15) l DirectDogg)FromPlant 0 i Operation I

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NOTES:

(a) " Maximum means the largest fraction of corresponding 10CFR50, Appendix I, dose design objective.

(b) The numbered footnotes indicate the age group, organ, and location (compass sector and distance from stack in meters) of the dose receptor, where appropriate.

(1) Child (2) Adult (3) Bone of a Child (4) Liver. Kidney, Lung, GI-LLI, Thyroid, and Whole Body of a Child, N-1000 (5) GI-LLI of a Teen NW-1000 (6) Liver, Kidney, Lung. GI-LLI, Thyroid, and Whole Body of a Child, NW-1000 (7) GI-LLI of a Child, S-1000 (8) SW-1000 (9) ENE-2276 (10) SE-2276 (11) ESE-2276 (12) NNW-775 (13) Liver, Kidney, Lung, GI-LLI, Thyroid, and Whole Body of a Teen (14) Liver, Kidney, Lung, GI-LLI, Thyroid, and Whole Body of an Adult and Teen (15) Lung of a Teen 1

(c) " Maximum" dose for the year is the sum of the maximum doses for each quarter. This reruits in a conservative yearly dose estimate, but still well within the limits of 10CFR50.

(d) For each special receptor location, the whole body and organ doses calculated for the airborne effluent releases were adjusted by the occupancy factor provided in Seabrook's ODCM (i.e., 0.0014 for the Science and Nature Center and 0.0076 for the'" Rocks"),

(e) Only station sources are considered since there are no other facilities within five miles of Seabrook Station. 1995 data for the closest off-site environmental TLD locations in each sector (as listed in Table B.4-1 of Seabrook's ODCM) were compared to preoperation data from 1986-1988 for the same locations. No statistical difference which could be attributed to station sources was identified.

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i TABLE B Sources of the Values of Factors Used in Liquid Dose Equations >

Factor Source U,p Table B.7 1, Station ODCM l

Mp Section B.7.1. Station ODCM (value-0.1 for l aquatic foods and 0.025 for shoreline)

B,p Table A-1, Reg. Guide 1.109 l D,ip) Tables E-11 through E-14, R.G. 1.109 tp Section B.7.1, Station ODCM K

c Reg. Guide 1.109 ;

tb Reg. Guide 1.109 W Table A-2, Reg. Guide 1.109 (value-0.5)

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TABLE C Sources of Values for the Factors Used in Dose Equations for Gaseous Releases Factor Source tb Reg. Guide 1.109 13 Kocher (Reference 3)

DFG 33 Table E-6, Reg. Guide 1.109

[X/0]D Calculated by AE0LUS 2 (Mod 5)

R, Table B.7-3, Station ODCM DFA 33, Tables E-7 through E-10, R.G.1.109 di Reg. Guide 1.109 P,t e,th and Y, Table B.7-2, Station 00CM r Table E-15. Reg. Guide 1.109 B jy Table E-1, Reg. Guide 1.109 p Reg. Guide 1.109 H Table B 7-2, Station ODCM F, Tables E-1 and E-2. R.G. 1.109 0F Table E-3, Reg. Guide 1.109 tf Reg. Guide 1.109 f, Table B.7-2 Station ODCM f

3 Table B.7-2. Station ODCM F

f Table E-1, Reg. Guide 1.109 t, Table E-15. Reg. Guide 1.109 DF13 ), Tables E-11 through E-14, R.G.1.109 V'a V, Table B.7-3. Station ODCM Table B.7-3, Station ODCM U ,' , U ,L f 9'f1 Reg. Guide 1.109 og Calculated by AE0LUS 2 (Mod 5)

( Table E-15. Reg. Guide 1.109 Or Table E-3, Reg. Guide 1.109 mun

(.

TABLE D

' Receptor Locations

for Seabrook Station Milk Animal Nearest Nearest within 5 Mi Resident Garden Radius Sector mile (km) mile (km) mile (km)

N 0.6 (1.0) 2.6 (4.2) ---

NNE- 2.0 (3.2) 2.0 (3.2) ---

NE 1.5 (2.4) 2.0 (3.2) ---

ENE 1.5'(2.4) --- ---

E 1.6 (2.6) --- ---

ESE; 1.5 (2.4) --- ---

SE 1.5 (2.4) --- ---

SSE 0.6 (1.0) --- ---

S 0.6 (1.0) 0.7 (1.1) ---

SSW 0.6 (1.0) 0.8 (1.3) ---

SW 0.6 (1.0) 0.8 (1.3) 3.2 (5.2)

WSW 0.7 (1.1) --- ---

W 0.6 (1.0) 0.7 (1.1) ---

WNW 0.6 (1.0) 1.0 (1.6) 3.8 (6.1) 4.8 (7.7)

NW 0.6 (1.0) 0.7 (1.1) 4.4 (7.1)

NNW 0.7 (1.1) 0.7 (1.1) 3.4 (5.5)

Locations based on 1995 Land Use Census.

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ENCLOSURE 4 TO NYN-96032 4

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ML20108D028

Contents

Text

1.0 INTRODUCTION

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

Reference:

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ML20108D028

Text

1.0 INTRODUCTION

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

Reference:

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