Text

Effluent & Waste Disposal Annual Rept 1994
	ML20082R289
Person / Time
Site:	Seabrook
Issue date:	12/31/1994
From:	; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	;
Shared Package
ML20082R237	List: ML20082R234; ML20082R289; ML20082R297;
References
	NUDOCS 9505020032
	Download: ML20082R289 (268)
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. _ . _ . .

North Atlantic April 28,1995 ENCLOSURE i TO NYN-95038 l

l 9505020032 950428 PDR ADOCK 05000443 R PDR

Page 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ;

Supplemental Information 1994 Facility: Seabrook Station Unit 1 Licensee: North Atlantic Energy ,

Service Corporation'

l. Reculatory Limits A. Gaseous Effluents

a. 5.0 mrad per quarter gamma air dose.

b. 10.0 mrad per quarter beta air dose.

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c. 7.5 mrem per quarter to any organ.

B. Liquid Efiluents l l

a. 1.5 mrem per quarter total body.

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b. 5 mrem per quarter to any organ. I 1

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

a. Fission and activation gases: 1 MPC

b. lodines: 1 MPC

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

d. Liquid effluents: 1 MPC

3. Averace Enerny ,

Not applicable.

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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. I

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.

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

5. Batch Releases l

Provide the following infonnation relating to batch releases of radioactive materials in liquid and gaseous effluents. j l

a. Liquid I. Number of batch releases: 160

2. Total time for batch releases: 37144 minutes

3. Maximum time period for batch release: 9300 minutes

4. Average time period for batch release: 232 minutes

5. Minimum time period for batch release: 45 minutes

6. Average stream flow during periods of release of effluent into a flowing stream:

1.48E06 liters per minute 1

b. Gaseous i

1. Number of batch releases: 53

2. Total time for batch releases: 17137 minutes

3. Maximum time period for batch release: 2976 minutes

4. Average time period for batch release: 323 minutes

5. Minimum time period for batch release: 0.3 minutes

6. Abnormal Releases

a. Liquid

1. Number of releases: 0

2. Total activity releases: N/A

b. Gaseous

1. Number of releases: 0

2. Total activity releases: N/A

TABLE 1A EFFLUENT AND NASTE DISPOSAL ANNUAL REPORT 1994 GASEOUS EFFLUENTS-SUlOLATION OF ALL RELEASES Unit Quart e r Quarter Quarter Quarter Ket. Total 1 2 3 4 Error, 4 A. Fission and activation gases

1. Total releases Ci 3.215-02 3.678-01 2.12E-02 2.49E-02 1.70E*01 l

2. Average release rate for period 4.138-03 4.67E 04 2.67E.03 3.13E-03

3. Percent et applicable Technical Specification 4 limit 1.53E-03 8.788-06 4.42E-04 3.42I-03 B. Iodines

1. Totsi release C1 ND ND ND ND 1.50Ee01 l

2. Aveiase r.l.a.e rate for period N/A N/A N/A N/A J, Percent of appiscacle Technical Specification t limit N/A N/A N/A N/A C. PartiCulates

1. Total release C1 1.758-05 2.678-04 5.30E 05 9.53E-06 1.80E+01 l

2. Average release rate for period 2.25E-04 3.40E-05 6.415 06 1.20E-06

3. forcent of applicable Technical Specification i limit 1.73E-03 7.80E-02 2.11E 02 1.198 02 D. Tr3 tium

1. Total release C1 4.448-02 2.12I.00 1.BOE 01 1.17E-02 1.60E+01 l

2. Average release rate for period 5.71E 03 2.70E-01 2.278-02 1.47E-03 J. Percent of app 14 cable Technical specification t limit 1.733-03 7.80E-02 2.11E-02 1.19E-02

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GAS GROUND TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1994)

GASEOUS EFFLUENTS-GROUY') LEVEL RELEASES CONTINUOUS Nuclides Released Unit

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 C1 ND ND ND ND krypton-88 Ci ND ND ND ND xenon-133 C1 ND ND ND ND xenon-135 Ci ND ND ND hT 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 C1 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-57 Ci ND 2.40E-08 ND ND cobalt-58 Ci 3.81E-07 1.39E-05 ND ND cobalt-60 Ci ND 1.95E-07 ND ND l manganese-54 Ci 2.92E-08 2.27E-07 ND ND Ci unidentified Ci ND ND ND ND Total for period Ci 4.10E-07 1.43E-05 0.00E+00 0.00E+00 Page 1

GAS GROUND TABLE 1B EFFLUENT AND WADTE DISPOSAL ANNUAL REPORT.(1994)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH Nuclides Released Unit 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 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 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 l 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 1.60E-07 ND cobalt-60 Ci ND ND 1.42E-06 ND Ci unidentified Ci ND ND ND ND Total for period Ci ND ND 1.58E-06 ND l

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TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1994)

GASEOUS EFFLUENTS-ELEVATED RELEASES CON 7INUOUS )

Nuclides Released Unit 1 2 3 4

1. Fission and activation gases argon-41 Ci ND ND ND ND i krypton-85 Ci ND ND ND ND l krypton-85m Ci ND ND ND ND krypton-87 Ci ND ND ND ND krypton-88 Ci ND ND 10 ND xenon-133 Ci ND ND ND ND xenon-135 Ci ND ND ND ND xenon-135m Ci ND ND ND ND j xenon-138 Ci ND ND ND ND l

C1 Ci l unidentified Ci ND ND ND ND Total for period Ci ND ND ND ND

2. Iodines iodine-131 l Ci ND ND ND ND iodine-133 i Ci ND ND ND ND l

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

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

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cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND l barium-lanthanum-240 Ci ND ND ND ND cobalt-57 Ci ND 4.97E-07 ND ND cobalt-58 Ci 1.71E-05 1.80E-04 3.88E-05 4.73E-06 cobaltJM Ci ND 2.17E-05 7.74E-06 4.80E-06 chromium-51 Ci ND 3.98E-05 ND ND manganese-54 Ci ND 8.57E-06 1.09E-06 ND niobium-95 C1 ND 2.88E-06 1.74E-06 ND Ci unidentified Ci ND ND ND ND Total for period C1 1.71E-05 2.53E-04 4.94E-05 9.53E-06

'l TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1994)

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

1. Fission and activation gases argon-41 C1 2.40E-03 ND 2.02E-02 1.40E-02 krypton-85 Ci ND ND ND ND krypton-85m Ci 2.83E-03 ND ND 2.90E-04 krypton-87 Ci 1.01E-04 ND ND 5.89E-04 krypton-88 C1 4.53E-04 ND ND 6.71E-04 xenon-133 Ci 3.33E-03 3.67E-03 5.31E-05 1.38E-03 xenon-135 Ci 6.92E-03 ND 9.70E-04 2.64E-03 xenon-135m C1 1.61E-02 ND ND 4.10E-03 xenon-138 Ci ND ND ND 1.20E-03 Ci Ci unidentified Ci ND Nr ND ND Total for period Ci 3.21E-02 3.67E-03 2.12E-02 2.49E-02

2. Iodines iodine-13A 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 cecium-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 NO ND ND 1 Total for period Ci ND ND ND ND l

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TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, %

A. Fission and activation products

1. Total releases C1 1.45E-02 1.65E-02 4.14E-02 1.74E-02 6.00E+00 l

2. Average diluted concentration during period uCi/ml 7.23E-11 1.74E-10 2.10E-10 7.61E-11

3. Percent of applicable limit t 2.24E-02 2.16E-02 3.54E-02 1.87E-02 B. Tritium

1. Total release Ci 5.74E+02 3.59E+01 6.98E+01 7.77E+01 8.00E+00

2. Average diluted concentration during period uC1/ml 2.87E-06 3.79E-07 3.54E-07 3.39E-07

3. Percent of applicable limit % 2.24E-02 2.16E-02 3.54E-02 1.87E-02 C. Dissolved and entrained gases

1. Total release Ci ND ND ND ND 1.90E+01

2. Average diluted concentration during period il 1 N/A N/A N/A N/A

3. Percent of applicable limit % N/A N/A N/A N/A D. Gross alpha radioactivity

1. Total release Ci ND ND ND ND 1.00E+01 E. Volume of waste released (prior to dil liters 4.56E+07 1.12E+07 2.97E+07 2.95E+07 1.30E+00 F. Volume of dilution water used during p liters 2.00E+11 9.46E+10 1.97E+11 2.29E+11 9.00E+00

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 LIQUID EFFLUENTS CONTINUOUS MODE Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 strontium-89 C1 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 ND ND ND ND 1ron-59 Ci ND ND ND ND zinc-65 Ci ND ND ND ND manganese-54 Ci ND ND ND ND chromium-51 Ci ND ND ND ND zirconium-niobium-95 Ci ND ND ND 1D molybdenum-99 Ci ND ND ND ND technetium-99m Ci ND ND 71D ND barium-lanthanum-140 Ci ND ND ND ND cerium-141 Ci ND ND ND ND Ci ci

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Ci

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C1 Ci unidentified Ci ND ND ND ND l Total for period (above)l Ci l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l xenon-133 Ci ND ND ND ND xenon-135 Ci ND ND ND ND

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TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 LIQUID EFFLUENTS BATCH MODE 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 5.05E-06 7.67E-04 ND ND iodine-131 Ci 3.96E-06 ND ND ND iodine-133 Ci 3.22E-05 7.23E-06 ND ND

cobalt-57 Ci ND ND 8.61E-06 ND cobalt-58 Ci 4.59E-03 6.20E-03 5.79E-03 1.63E-03 cobalt-60 Ci 8.27E-04 4.40E-04 1.04E-03 2.80E-04 chromium-51 Ci 1.19E-04 1.26E-04 5.33E-04 4.67E-05 iron-55 Ci 4.51E-03 2.83E-03 1.82E-02 1.22E-02 iron-59 Ci 5.46E-05 9.10E-05 9.03E-05 1.02E-05 zinc-65 Ci ND ND ND ND manganese-54 Ci 1.55E-04 8.15E-04 2.80E-04 7.82E-05 chromium-51 Ci ND ND 10 ND zirconium-niobium-95 Ci 1.71E-05 9.80E-06 8.37E-05 5.99E-06 niobium di Ci ND ND 6.21E-06 ND molybdenun. 99 Ci ND ND ND ND technetium-99m Ci 6.18E-06 2.75E-06 2.69E-05 8.64E-06 barium-lanthanum-140 Ci ND ND ND ND cerium 14i Ci ND ND ND ND sodium-24 Ci ND ND 5.41E-05 ND antimony-124 Ci 3.00E-04 4.86E-04 4.80E-04 2.83E-05 antimony-125 Ci 3.83E-03 4.70E-03 1.48E-02 3.13E-03 bromine-82 Ci ND ND. ND 6.76E-06 Ci unidentified Ci ND ND ND ND l Total for period (above)l Ci l 1.45E-02 l 1.65E-02 l 4.14E-02 l 1.74E-02 l xenon-133 Ci ND ND ND ND xenon 135 Ci ND ND ND ND

TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

Unit Reporting Est. Total

1. Type of waste NONE Period Error, %

a. Spent resins. filter sludges, evapora cr 0m 3 NONE bottoms. etc 0 C1

b. Dry compressible waste. contaminated 0m3 NONE equip, etc 0 C1

c. Irradiated components. control rods etc 0m3 NONE O Ci

d. Other (described) Om3 NONE 0 Ci

" stimate of major r x lide composition (hy te e of waste) !

a. N/A

b. i l

C.

d.

3. Solid Waste Disposition NJmbor of Shiomonts Mode of Transportation Destination NONE B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Modo of Transportation Destination NONE

APPENDIX A Off-Site Dose Calculation Manual Reauirement: Technical Specification 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 Effluent 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.

Response: One revision of the ODCM was made during the reporting period.

Revision 14 RETS - A release elevation adjustment tenn, which was omitted on a previous revision was placed back into Method I calculations. This revision added trigger points for IIcalth Physics evaluations oflimiting doses to individual members of the public in controlled areas on site.

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IN FO RdVI ATIO RMD CONTROL COPY #

h *******************

OFFSITE DOSE CAI4'UIATION *

gg, . O *. *

MANUAL

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(ODCM) *

1. Does this manual / manual revision:

a. Make changes in the facility as described in ,the ,, ' /

UFSAR? O Yes TNo

b. Make changes in procedures as described in the g UFSAR? - LE Yes;;. O Np

c. Involve tests or experiments not described in -

the UFSAR? , O Yesa No

d. Involve changes to the existing Operating License. 9 or require additional license requirements? ' , C Yes;} _ Np

2. If any of the above questions are answereti yes,. a . safety,evaluac, ion;per o procedure NM 11210 is required. (The individual performing..this review ~

shall have completed 10 CFR 50.59 training.)

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

t

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W.B.LELAND, CHEMISTRY'ANDHEALTH} PHYSICS 1 MANAGER DA'fE [r ~ ^

SORC REVIEW COMPLETED DURING MEETING NUMBER: kh DATE[ / m.-.M/ . . - .d '" i APPROVED BY: h N / D

^D 'Aff-

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W. A. DIPROFD, STATION MANAGER : ,

REVISION 15 -- EFFECTIEE: 1-5 ]

DATE OF LAST PERIODIC REVIEW: 12/.21/94 DATE NEXT PERIODIC REVIEW DUE:, 12/21/96 North Atlantie Energy Service Corporatism

i DISCLAIMER OF RESPONSIBILITY 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 and, with resoect to any unauthorized use, neither Yankee nor its officers, 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

ABSTRACT 4

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 sampling and analysis, along with the Radiological Environmental Monitoring Program requirements (Part A); and (2) approved methods to determine effluent monitor setpoint values and estimates of doses and radionuclide concentrations occurring beyond the boundaries of Seabrook Station resulting from normal Station operation (Part B).

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 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.

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Page 1 of 1 ODCM Rev. 14

g TABLE OF CONTENTS J

CONTENT ZMiE PART A: RADIOIDGICAL EFFIRENT NONITORING PROGRAMS

1.0 INTRODUCTION

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

PART B: RADIOIDGICAL CAIEUIATIONAL METHODS AND PARAMETERS l I

1.0 INTRODUCTION

B.1-1 1.1 RESPONSIBILITIES FT)R 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 .

l 2.1 METHOD TO DETERMINE Fino AND C 53 2 B.2-1 l 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 3.0 0FF-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 CALCUIATE 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. 15

I TABLE OF CONTENTS CONTENT IAGE PART B: RADIGIACICAL CAIEUIATIORIAL METHODS AND PARAMETERS 3.0 0FF-SITE DOSE CALCULATION METHODS 3.4 METHOD TO CALCUIATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES B.3-9 3.4.1 Method I B.3 10 3.4.2 Method II B.3-12 3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES 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 IODINES, TRITIUM AND PARTICUIATES WITH Tu2 GREATER ;

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 TO CALCUIATE THE GAMMA AIR DOSE FROM NOBLE GASES B.3-23 1

3.7.1 Method I B.3-23 j 3.7.2 Method II B.3-25 1 3.8 METHOD TO CALCULATE THE BETA AIR DOSE FROM NOBLE CASES B.3-26 1 3.8.1 Method I B.3-26 3.8.2 Method II B.3-29 3.9 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE FROM IODINES, TRITIUM AND PARTICUIATES B.3-30 3.9.1 Method I B.3-30 3.9.2 Method II B.3 32 3.10 METHOD TO CALCUIATE DIRECT DOSE FROM PIANT 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 Gaseous Dose Projections B 3-36 l 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B.4 1 Page 2 ODCM Rev. 15 l

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TABLE OF CONTENTS CONTENT pgd; PART B: RADIOLOGICAL CAIEULATIONAL MEIBODS AND PARAMETERS 5.0 SETPOINT DETERMINATIONS B.5-1 5.1 LIQUID EFFLUFNT 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 l 5.1.3 Steam Generator Blowdown Liquid Sample Monitor l (RM-6519) B.5-6 )

5.1.4 PCCW Head Tank Rate-of-Change Alarm Setpoint B.5 7 l 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS B.5-9 5.2.1 Plant Vent Vide-Range Gas Monitors (RM-6528 1, 2 l and 3) B.5-9 6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWASTE TREATMENT SYSTEMS B.6-1 7.0 BASES FOR DOSE CALCULATION METHODS B.7-1 .

l 7.1 LIQUID RELEASE DOSE CALCUIATIONS B.7 1 7.1.1 Dose to the Total Body B.7-5 7.1.2 Dose to the critical Organ B.7-5 7.2 GASEOU's RELEASE DOSE CALCULATIONS B.7-8 .1

< 7.2.1 Total Body Dose Rate From Noble Gases B.7-8 7.2.2 Skin Dose Rate From Noble Gases B.7-10 7.2.3 Critical Organ Dose Rate From Iodines, Tritium and Particulates With' Half-Lives Greater Than l 1

Eight Days B.7-13 7.2.4 Gamma Dose to Air From Noble Gases B.7-15 7.2.5 Beta Dose to Air From Noble Cases B.7-17 7.2.6 Dose to Critical Organ From Iodines, Tritium and Particulates With Half-Lives Greater Than Eight Days B.7 19 7.2.7 Special Receptor Gaseous Release Dose Calculations B.7-21 l l

7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS l s

FOR IMPORTANT EXPOSURE PATHWAYS B.7-35 7.3.1 Receptor Locations B.7-35 7.3.2 Seabrook Station Atmospheric Dispersion Model B.7-36 7.3.3 Average Atmospheric Dispersion Factors for Receptors B.7-36 I

Page 3 ODCM Rev. 15 l

TABLE QF CONTENTS CONTENT EgiE PART B: RADIGIACICAL CA14UIATIONAL METHODS AND PARAMETERS 8.0 BASES FOR LIQUID AND CASEOUS MONITOR SETPOINTS B.8-1

=

8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT B.8.1 8.2 BASIS FOR THE PIANT VENT WIDE RANCE GAS MONITOR SETPOINTS B.8-4 4

83 BASIS FOR PCCW HEAD TANK RATE-OF-CHANCE ALARM SETPOINT B.8-9 REFERENCES R-1 APPENDIX A: DOSE CONVERSION FACTORS A1 l APPENDIX X: SORC APPROVED PART A REVISION AWAITING NRC REVIEW X-1 APPENDIX Y: 10 CFR 59.59 EVALUATION 94-267-01, REVISION 15 !

0FFSITE DOSE CALCUIATION MANUAL, 12-13-94. Y-1 '

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LIST OF TABLES b' UMBER TITLE f69.E PART A A.3-1 Radioactive Liquid Waste Sampling and Analysis Program A.3 2 A.4-1 Radioactive Gaseous 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 A.5-3 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 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 B.1 4 Summary 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 B.1 8 Summary of Variables B.1-15 B.1-9 Definition of Terms B.1-22 B.1 10 Dose Factors Specific for Seabrook Station for Noble Gas Releases B.1-23 B.1-ll Dose Factors Specific for Seabrook Station for Liquid Releases B.1-24 B.1 12 Dose and Dose Rate Factors Specific for Seabrook Station for Iodines, Tritium 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 Science and Nature Center for Iodine, Tritium, and Particulate Releases B.1 27 Page 1 of 2 ODCM Rev. 15

LIST OF TABLES i

I NUMBER TITLE EAQE PART B (Continued)

B.1-15 Dose and Dose Rate Factors Specific for the " Rocks" for ,

Iodine, Tritium, and Particulate Releases B.1-28 !

B.4 1 Radiological Environmental Monitoring Stations B.4-2 ,

i B.7 1 Usage Factors for Various Liquid Pathways at Seabrook B 7-7 l Station B.7-2 Environmental Parameters for Gaseous Effluents at Seabrook Station B.7-32 B.7 3 Usage Factors fo: Various Gaseous Pathways at Seabrook Station B.7 34 1 B.7-4 Seabrook Station Long-Term Average Dispersion Factors Primary Vent Stack B.7-39 B.7 5 Seabrook Station Long-Term Average Dispersion Factors for Special (On Site) Receptors Primary 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

Page 2 of 2 ODCM Rev. 15

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t. ' 14' cover 15 B.1-14 B.1-15 15 Disclaimer 14 B.1-16 15 B.1-17 15 Abstract 14- B.1-18 15 ,

B.1-19 15 TOC 1 - 4 15 B.1-20 14 B.1-21 14 List of Figures 14 B.1-22 14 B.1-23 15-List of Tables 1 15 B.1-24. 14 2 15 B.1-25 15' B.1-26 15 LOEP 1 - 3 15 B.1-27 15 B.1-28 15 A.1-1 10 B.2-1 12 A.2-1 4 B.2-2 12 ;

B.2-3 - 12 A.3-1 4 A.3-2 4 B.3-1 15 A.3-3 4 B.3 2 12 A.3-4 4 B.3-3 12

-A.3-5 4 B.3-4 12 i A.3-6 4 B.3-5 14 B.3-6 14 A.4-1 4 B.3-7 14 A.4-2 4 B.3-8 14 A.4-3 4 B.3-9 14 A.4-4 4 B.3-10 14 A.4-5 4 B.3-11 15 B.3-12 14 A.5 1 4 B.3-13 14 A.5-2 4 B.3-14 14 A.5-3 4 B.3-15 15 A.5-4 4 B.3-16 14 A.5-5 4 B.3-17 14 A.5-6 4 B.3-18 14 A.5-7 4 B.3-19 15 A.5-8 4 B.3-20 15 A.5-9 4 B.3-21 14 A.5 10 4 B.3-22 14 B.3-23 14 B.1-1 15 B.3-24 15 B.1-2 14 B.3-25 14 B.1-3 4 B.3-26 14 B.1-4 12 B.3-27 15 B.1-5 4 B.3-28 15 B.1-6 8 B.3-29 14 B.1-7 4 B.3-30 14 B.1-8 15 B.3-31 15 B.1-9 15 B.3-32 15 B.1-10 15 B.3-33 14 B.1-11 15 B.3-34 14 B.1 12 15 B.3-35 14 B.1-13 15 B.3-36 14 Page 1 ODCM Rev. 15

LIST OF EFFECTIVE PAGES nsa - ast nas - ast 18.3-37 14 B.7 26 15 B.7-27 .15

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- B.4-4' 11 B.7-31 14 B.4-5 15 B.7-32. 14 B.4-6 15 B.7-33 14 B.4-7 8 B.7-34 15 B.4-8 15 B.7-35 '14 B.4-9 8 B.7-36 14 B.4 10 11 B.7-37 15 B.7-38 15 _

B.5-1 7 B.7-39 14 B.5-2 4 B.7-40 14 B.5-3 8 B.7 41 15 B.5-4 4 B.5-5 10 B.8-1 4 B.5-6 10 B.8-2 4 B.5 7 10 B-8-3 4 B.5-8 10 B.8-4 8 B.5-9 7 B.8 5 4 B.5 10 7 B.8-6 7 B.5-11 7 B.8-7 7 B.5-12 7 B 8-8 7 B.5 7 B.8-9 7

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< B.7-3 12 A4 8 B.7-4 12 A-5 8 B.7-5 12 A-6 8 B.7-6 12 A-7 8 B.7-7 12 A-8 8 B.7-8 14 A-9 8 B.7-9 14 A-10 8 B.7-10 14 A-11 8

- B.7-11 14 A-12 8 B.7 12 14 A-13 8 B.7-13 14 A-14 8 B.7-14 14 A-15 8 B.7-15 14 A-16 8 B.7-16 14 A-17 8 B.7-17 14 A-18 8 B.7-18 14 A-19 8 5.7 19 14 B.7-20 14 X-1 15 B.7-21 15 X-2 15 B.7-22 15 X-3 15 B.7-23 15 X-4 15 B 7-24 15 X-5 15 B.7-25 15 X-6 15 Page 2 ODCM Rev. 15 W" w -,--rge-w.y -

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., _.1 .

PART A RADIOLOGICAL EFFLUENT MONITORING PROGRAMS

1.0 INTRODUCTION

The purpose of Part A of'the 00CM (Off-Site Dose Calculation Manual) is to describe the sampling and analysis programs conducted by the Station whicn 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 to t.e 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 quantitles of radioactive materials released in effluents and resultant radiation doses to individuals from principal pathways of exposure. The data developed in the ,

surveillance and monitoring programs described in Part A to the 00CM provide a !

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. l A.1-1 4626R ODCM Rev.10

2.3 RESPON5!B!LITIES FOR PART A All changes to Part A of the 00CM shall be reviewed and approved by :.e

Station Operations Review Committee (SORC) 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 recuirements and administrative controls of the appropriate portions of the Technical Specifications.

i I

l

)

A.2-1 00CM Rev. 4

-l 3.0 LIOUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive liquid wastes shall De 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 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 effluent information for liquids obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part E to demonstrate compliance with the dose objectives and surveillance requirements of Technical Specifications 3/4.11.1.2, 3/4.11.1.3, and 3/4.11.4.

9 A.3-1 ODCM Rev. 4 l l

)

4

TABLE A.3-1 Radioactive Llauld Waste Sampling and Anel sis Program Lower Limit Minimum Type of of Detection ,

Liquid Analysis Activity (LLD) (1)

Release Sampling Analysis (uci/ml)

Frecuency frequency Type P Principal Gamma P

A. Liquid Emitters (3) 5x10-7 Radwaste Each Batch Each Batch Test Tanks I-131 1x10-6 (Batch M Dissolved and "

lx10-5 Release)(2) P '

Entrained Cases One Batch /M (Gamma Emitters)

H-3 1x10-5 P M(4)

Each Batch Composite Gross Alpha lx10-7 g(4) Sr-89, Sr-90 5x10-8 p

Each Batch Composite Fe-55 lx10-6 W Principal 41auna Turbine Building W 5x10-7 B.

Grab Sample Emitters e Sump Effluent (8)

I ',31 lx10-6 o

R (Continuous M Dissolved and

= Release (5) W Entrained Gases lx10-5 Grab Sample

,E (Gamma Emitters) ,

h

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

l ll i]i D_-

n t o) ii1) 6 7 6 5 5 7 8 6 mt(l 5 7 8 - - - - - - -

- - 0 i c m -

0 0 0 0 0 0 0 0 0 0 Le)/ 1 1 1 1 1 1 1 x

tdt 1 1 1 x

1 x x x x x x x reL c x x 5 1 1 1 1 5 1 eDL u 1 1 5 1 w

of (l

Lo .

)

a ss _

m er _

m dse 0 0 a nat a 9 G) aGt a 9 3 i h m h p r

)t ddm p r a as eeE l S r ys l S pr vn A g f ti A li a ,

o r

oisvy 3

- s 9 5

i e ct 1 3

oam srm s

s 9

8 5

5 eil H s 8 5 nt 3 o - -

P o - - ii 1 st a r e pt a r e rm - i n r. - r s ycn r PE 1 DE( H G S I i TAA G S F s _

y l

a n

A d

n a

q )

1

- n d y 3

l e sc p u i

min A m in use myu M Q W M M Q E a t il q S n L nae B

A e o inr T t (c MAf s

a W

d i

u q

i e e e e e L e l l l l p

y l l p p p p e gc p m m nn m m m m a a v a a a a l WS i ie WS WS WS bS t l u pq WS b c b b a me ar b

a b

a a a r

a r

o SF r r r r G G i

G G G G d

a R

r oh )

t s aa s(

5 rl eF) u )'

n 8 oe en( us G w) na o6 ie e md( tl ds iae awk ne uep eon ti a oR C

ql y (

ieT StT LR C

? ".

oy =

E~

E lfIl

s TA8tE A.3-1 Radioactive Lieutd Waste Sampline and Analysis Program (continued)

Lower Limit Minimum Type of of Detection Liquid (LLO) (1)

Release Sampilng Analysis Activity Frequency Frequency Analysis luct/ml)

Ivoe W W Principal Gamma O. Service Water (I) Emitters (3) 5x10-7 Grab Sample l-131 1x10-6 W M 01ssolved and Entrained Gases 1x10-5 Grab Sample (Gamma Emitters)

M H-3 1x10-5 W

> Grab Sample 1x10-7 Gross Alpha Y

s-Sr-89. Sr-90 5x10-8 W Q Grab Sample 1x10-6 Fe-55 P - Prior to 01scharge W - Weekly M - Month 1y o Q - Quarterly 8

lr

,4 -

_ _ _ _ . _ _ _ _ _ _ _ _ __ _ - _ _ _ -, .- ___.________m_ _ _ ____ _ _ _ _ _ _ -

TABLE A.3-1 Notations (1)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 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 =

E x V x 2.22 x 106 x Y x exp (-hot)

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 t

minute).

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

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

2.22 x 10-6 = the number of disintegrations per minute per microcurie, l Y = the fractional radiochemical yield, when applicable, i

h = the radioactivc decay constant for the particular radionuclide !

(s-l),and I 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 i oriori (before the fact) limit representing the capability of a measurement system and not as an i costeriori (af ter the f act) limit for a particular measurement.

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

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

A.3-5 ODCM Rev. 4

i TABLE A.3-1 Notations (Continued)

(3)The principal gamma emitters for which the LLO specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, .

l Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that i only these nuclides are to be considered. .0ther gansna peaks that are f

identifiable, together with those of the above nuclides,'shall also be analyzed and reported in t.he Semiannual Radioactive Effluent Isotopes Release Report which are not in accordance with Technical Specification 6.8.1.4. i detected should be reported as "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, i

! (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.

t (6) Sampling and analysis is only required when Steam Generator 81owdown 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, l tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gamma emitters exceeds the LLD.

The following are additional sampling and analysis requirements:

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

I b. Sample Service Water System (SWS) daily for principal gamma emitters i whenever primary component cooling we.ter (PCCW) activity exceeds ,

1x10-3 uC/cc.

l

c. With the PCCW System radiation monitor inoperable, . sample PCCW and SWS '

daily for principal gamma emitters. :

r

d. With a confirmed PCCW/SWS leak and PCCW activity in excess of 1x10-4 uC/cc, 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 or greater than that of an SWS radiation monitor located If in the unit's combined SWS discharge, with an LLO of 1x10-b uC/cc. this ,

sensitivity cannot be achieved, the SWS will be sampled once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

f (8)lf the Turbine Building Sump (Steam Generator Blowdown Flash Tank) l isolate due to high concentration of radioactivity, that liquid stream will l

L be sampled and analyzed for lodine-131 and principal gamma emitters prior

' to release. A.3-6 ODCM Rev. 4

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 boundary are within ,the limits of Technical Specification 3.11.2.1 for Unit 1.

Radioactive effluent information for gaseous wastes obtained f rom 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 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.

I I

i A.4-1 ODCM Rev. 4

TA8tE A.4-1 Fadioactive Gaseous Waste Sampling and Analysis Program Minimum Type of Lower Limit Gaseous Analysis Activity of Detection (l)

Release Sampling Analysis (LLD) (uct/cc)

Frequency Frequency Type Principal Gamma Emitters (2) 1x10-4 M(3)(4) M

1. Plant Vent Grab Sample 1x10-6 ;

H-3 I _13j 1x10-12 Continuous (5) w(6)

Charcoal Sample

? g(6) Principal Gamma Emitters (2) 1x10-Il Continuous (5)

[ Particulate ,

Sample Gross Alpha 1x10-Il Continuous (5) M Composite Particulate Sample Sr-89, Sr-90 1x10-Il Continuous (5) Q Composite Particulate y Sample

r E Principal Gamma Emitters 5x10-4 M(7) M(7) f 2. Condenser Air Removal Exhaust Grab Sample 1x10-6 s- 11 - 3

_ _ . _ . - _ _ . - . _ _ _ . _ _ - - _ _ _ - - - _ _ . _ . _ _ - - _ - - _ . _ - _ - - _ _ - - - - - _ _ - - _ . - - - - - - _ _ - _ - - -a ._ - w ~

TABLE A.4-1 ,

Radioactive Gaseous Waste Sampling and Analysis Program (continued)

Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detect 19n(I)

Ivpe Frequency Frequency Analysis (LLO) (uC1/cc)

3. Gland Steam Continuous W Principal Gamma Emitters (2) 1x10-Il ;

Packing Exhauster Particulate Sample Continuous W I-131 1x10-12 Charcoal Sample

?

o Continuous M Gross Alpha Ix10-Il d,

Composite Particulate Sample I

Continuous Q Sr-89, Sr-90 lx10-Il Composite Particulate Sample Principal Gamma Emitters (2) 1x10-4

4. Containment P(3) P Purge Each Purge Grab Each Purge 8 lx10-6 Q Sample H-3 (oxide)

E

?

n a

TABLE A.4-1 Notations (1)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 percent a '

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

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

j 4.66 s b LLD =

E x V x 2.22 x 106 x Y x exp (-AAt) l 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 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, A = the radioactive decay constant for the particular radion!clide (s-1), and at = the elapsed time between the midpoint of sample colltetton and the time of counting (s).

Typical values of E. V, Y, and At should be used in the ealculation.

It should be recognized that the LLD is defined as an i 9I12rj, (before the fact) limit representing the capability of a measurement systism and not as an g nosteriori (af ter the f act) limit for a particular measurement.

A.4-4 ODCM Rev. 4

.n - .- - - .- - - . _ _ - - . _

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, 2n-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Co-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 Specification 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 33 and 2) *.he roble gas activity monitor for'the plant vent has not increased by more than a factor of 3. For containment purge, requirements apply only when purge is in operation.

(') 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 made in accordance with Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

( } 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 '

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 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 affluent activity has not increased more than a factor of 3.

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

A.4-5 ODCM Rev. 4 i

r v .- -, - . . - - -

.--r - - . . +. -- -- - ----

- . .= -- - .- -

0 l i l l

5.0 RA010 LOGICAL ENVIRONMENTAL MONITORING I 5.1 Samoline and Analysis Procram ;

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 Specification 3.12.1. The monitoring program implementsSection IV.B.2 of Appendix 1 to 10CFR, Part 50, and thereby supplements the radiological ef fluent monitoring 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 ODCM.

4 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 Detection capability f or locations shown in Section 4 of Part B to the 00CM.

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 from the monitoring program. In this context, the term unavailable means that samples are no longer available to be collected now or in the future for reasons such as the permission from the owner to 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

l l

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 sr . tors 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.

Foi 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.

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

i 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 volume-is available.

A.5-2 ODCM Rev. 4

1 TABLE A.5-1 Radiological Environmental Nonitoring Program l

Number of ,

Representative Samples and Sampling and Type and Frequency Exposure Pathway a Collection Frequency of Analysis and/or Sample Sample Locations Quarterly. Gamma dose quarterly.

40 routine monitoring stations b

1. DIRECT RADIATION 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

- each meteorological sector, generally in the 6 to 8-km range

? from the site; I -

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

locations.

2. AIRBORNE Continuous sampler Radiciodine Cannister:

Radiolodine and Samples from five locationsd : -

operation with sample Particulates collection weekly, or I-131 analysis weekly.

Three samples from close to the ;

three SITE BOUNDARY locations, more frequently if '

required by dust Particulate Sampler:

o in different sectors, of high ,

loading.

8 calculated long-term average Gross beta radioactivity

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

' a community having the highest of composite (by location) '

" calculated long-tenn average quarterly.

ground-level D/Q.

_ __ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _~ ..

TABLE A.5-1 (Continued)

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

Sample Locations Collection Frequency of Analysis and/or Sample One sample from a control location, as for example 15-30 km distant and in the least prevalent wind ;

direction.

3. WATER 80RNE One sample in the discharge area. Monthly grab sample. Gamma isotopic analysis'

a. Surface monthly. Composite for one sample from a control location.

tritium analysis quarterly.

One sample from area with existing Semiannually. Ganuna isotopic as..: lysis e i'

> b. Sediment from semiannually.

m from or potential recreational value.

L shoreline

4. INGESTION Samples from milking animals in Semimonthly when Gaauna isotopic' and I-131 I

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 o

8 One sample from milking animals i

at a control location, as for example,15-30 km distant and 3

in the least prevalent wind direction.

s~

. .m ___ . . -

a>

t TABLE A.5-1 l Radiological Environmental Monitoring Program j (Continued)

Exposure Pathway Number of Representative Sgeples Sampling and Type and Frequency and/or Sample and Sample Locations Collection Frequency of Analysis

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.

j species in vicinity.of plant are not seasonal.

discharge area.

One sample of similar species in areas not influenced by plant

>- discharge.

on On c. Food Products Samples of three (if practical) Honthly, when Gamma isotopic

and I-131 different kinds of broad leaf available. analysis.

4 vegetationE grown nearest each of two different off-site locations of highest predicted long-term average ground-level D/Q if milk sampling is not performed. !

One sample of each of the similar Monthly, when . Gamma isotopic

and 1-131 >

broad leaf vegetationE grown at available. analysis.

a control location, as for example 15-30 km distant in the least prevalent wind direction, if milk a. ,

sampling is not performed.

t O . . .

x

$4

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

TA8tE A.5-1 (Contimmed)

Table Notaties a) Specific parameters of distag'ce and directies sector from the centeritne of the Unit I reacter, and additlenal descriptica where,pertiment, shall be provided for each and every sample location la lable 0.4-1 la the SOCII. part 8. Deviatless are permitted from the required sampling schedule if specimens are unohtaleable due to circumstances such as hazardous conditless, seasonal unavailability and malfuncties of automatic samp11ag egulpment. If specimens are umebtainable due to sampilag egulpment malfuncties, effort shall be made to complete corrective acties prior to the end of the next sampling perled. All devlettens from the sampling schedule shall be documented la the AnnualIt is rec Radlelegical Envireemental Operatlag Report.

practicable te centinue te obtala samples of the media of chelte at the most desired locattaa er time.

In these lastances suitable alternative media med locations may be chosen for the particular pathway la l

questles and appropriate substitutions made within 30 days la the redlelegical environmental moulterla program. Identify the cause of the unavailability of samples for that pathway and identify the new f

location (s), if available, for obtainlag replacement samples la the ment samlannual Radleactive [f fluent Release Report and aise laclede la the report a revised figure (s) and table for the OSCM reflecting the new locatten(s).

Y b)

A therselumlaescent desimeter (TLS) is considered to be one phospher; two er more phosphers la a pack f *

! are considered as two er more desleeters.

c) Airborne particulate sample illiers shall be analyzed for gross beta redleactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or moreIf gross b t

after sampilag to allew for rades and theren daughter decay. samples is greater than

' performed en the individual samples.

l d) optimal air sampling locattens are based met sely en 3/4 but en facters such as populatlea la the a

' year-round access to the site, and availablitty of power.

Gamma lsetepic analysts means the identificatten and quaatlficatten of gauna-emittlag radienscli e) may be attrlhetable to the effluents from the facility.

o 1he dose shall be calculated for the maximum organ and age group, uslag the methodelegy and pa lf) in the eeCM. part 8.

,k g) " Sread leaf vegetation is unavailable, other vegetation will be sampled.

2-1 l IABLE lvsita f g getutige Casabilities i=.' favironmental Sassle Ana

=-

Lower Llatt of Betectien (LLO)b Sedleent ,

Fish and Nilk food Products isCI Aa. drvi Invertebrates faCthe) isC1/ke. wet)

Airbor,me'Particglate isCIAe. wett

! Mater .

er sas _isCIAe 1

/

_Aglysis (sCIAe1 l 0.01 4

Gross Deta .

3,000 130 Cl-3 15 260 Mn-54 30 130 Fe-59 15 260 Co-50, 60 y 30

$ In-65 #

15C 1 W

Ir-Mb-95 0.07 15 W

15 130 12 1-131 00 0.05 le 15 ISO Cs-134 0.06 15Ced 10 Cs-131 .

15Cd a 9 Sa-La-140 1

O r

s~

e ,.

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _._ _ _ _ _ _ _ e

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

TABLE A.5-2 (Continued)

Table Notation 1

~

I a) This list-does not mean that only these nuc1 ides 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. I I

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. l l

For a particular measurement system, which may include radiochemical

<- separation:

4.66 s b L D = E

V ' 2.22

Y

exp(-hat) l

. Where: 1 LLD 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; 3

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; s

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

Y is the fractional radiochemical yield, when applicable; F

h is the radioactive decay constant for the particular radionuclide as per second; and 6t for environmental samples is the elapsed' time'between sample collection and time of counting, as seconds.

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

In calculating the LLD 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 ODCM Rev. 4

TABLE A.5-2 (Continued)

It should be recognized that the LLO is defined as an 1 oriori (before the fact) limit representing the capability of a measurement system and notThis as an i nosteriori .(af ter the f act) limit for a particular measurement.

does not preclude the calculation of an g nosteriori LLO 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 f1'uctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

c) Parent only, d)

The Ba-140 LLO 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 anThe insignificant amount (at least 3.6% of its original value). ;

ingrowth equations will assume that the supported La-140 activity at the '

time of collection is zero.

< e) Broad leaf vegetation only.

If the measured concentration minus the three standard deviation.

f) uncertainty is found to exceed the specified LLO, the sample does not have to be analyzed to meet the specified LLO.

Required detection capabilities for thermoluminescent dosimeters used for l

, g) '

environmental measurements shall be in accordance with recommendations of Regulatory Guide 4.13. Revision 1, July 1977.

4 A.5-9 ODCM Rev. 4

L TABLE A.5-3 Reportine Levels for Radioactivity Concentrations in Environmental Samples 1

Fish and Water AirborneParticglate Invertebrates Milk - Food Products (pC1/ke) or Gas (pCl/m ) (DC1/ke. wet) (DC1/kg) (pC1/te. wet)

Analysis H-3 30,000 i 1,000 30,000 Mn-54 t 400 10,000 Fe-59 i

1,000 30,000 Co-58 300 10,000 Co-60 300 20,000

> Zn-65 Zr-Nb-95 400*

O 3 100**

1-131 100 0.9 1,000 60 1,000 Cs-134 30 10 2,000 10 2,000 Cs-137 50 20 300*

Ba-La-140 200*

k* Parent only.

- Broad leaf vegetation only.

k

... n , , ..

l I

i l

SEABROOK STATION ODCH PART B i RADIOLOGICAL CALCULATIONAL HETHODS AND PARAMETERS 4

R12\86

T ,

l-1

1.0 INTRODUCTION

~ ~

Part B of the ODCM'(Off-Site Oose Calculation Manual) provides formal

- . 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, j 3/4.3.3.10, and 3/4.11, as well as the REMP detailed in Part A of the manual. .;

The ODCM forms the basis for station procedures which document the off-site .,

doses due to station operation which are used to show compliance with the l numerical guides for design objectives of Section II of Appendix I to 10CFR Part 50. The methods contained herein follow accepted NRC guidance, ;

unless otherwise noted in the text. l 1.1 Responsibilities for Part 8 All changes to Part B of the ODCM shall be reviewed and approved by the .

,j Station Operation Review Committee (SORC) in accordance with Technical j Specification 6.13 prior to implementation. Changes made to Part B shall be submitted to the Commission for their information in the Annual Radioactive l Effluent Release Report for the period in which the change (s) was made effective.

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

The Executive Director - Nuclear Production shall be responsible to ensure l 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.

In addition to off-site dose calculations for the demonstration of compliance with Technical Specification dose limits at and beyond the site boundary, 10CFR20.1302 requires that compliance with the dose limits for !

individual members of the public (100 mres/yr total effective dose equivalent) i

- be demonstrated in controlled areas on-site. Demonstration of compliance with the dose limits to members of the public in controlled areas is implemented per He*1th Physics Department Procedures, and is outside the scope of l i

B.1-1 ODCM Rev. 15 l ]

l l

i

v ' w T"'T79

l the 00CM. However, calculations performed in accordance with the ODCM can be l used as one indicator of,the need to perform an assessment of exposure to 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 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 j and 3.11. can be used as an indicator of when additional assessments of l on site exposure to members of the public is advisable (see Section 3.11.2).

l Off-site critical organ doses from station effluents should not, however, be l the only indicator of potential on-site doses.

1.2 Summary of Methods. Dose Factors. Limits. Constants. Variables and Definitions This section summarizes the Method I dose equations which are used as 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 II dose determinations are described in Sections 3.2 through 3.9 and 3.11. The dose factors used in the equations are in Tables B.1-10 through B.1-14 and the Regulatory Limits are summarized in Table B.1-1.

The variables and special definitions used in this ODCM, Part B, are in Tables B.1 8 and B.1-9.

i I

R12\86 B.1 2 ODCM Rev.14

so TABLE B.1-1

$ Summary of Radioloalcal Effluent Technical Specifications and Isolementina Ecuations (1)

Technical Specification Category 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.

Dose 1 3.0 mres in a yr.

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

m 1 10 mrem in a yr.

h w

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

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

3.11.2.1 Gaseous Ef*1uents Total Body Dose Rate Eq. 3-3 1 500 mres/yr.

Dose Rate from Noble Gases-Skin Dose Rate Eq. 3-4 1 3000 ares /yr.

from Noble Gases Organ Dose Rate :Eq. 3-5 1 1500 mres/yr. ,

from I-131. I-133 Tritium and o Particulates with y Tuy > 8 Days E

'A I L

! - I i

TABLE B.1-1 3 (Continued) y

$ Summary of Radioloalcal Effluent Technical Specifications and Imolementino Ecuations Technical Soecification Category Method I Limit 3.11.2.2 Gaseous Effluents Gamma Air Dose from Eq. 3-6 I 5 mrad in a qtr.

Dose from Noble Noble Gases Gases i 10 mrad in a yr.

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

Noble Gases i 20 mrad in a yr.

3.11.2.3 Gaseous Effluents Organ Dose from Eq. 3-8 1 7.5 mrem in a qtr.

Oose from I-131 Iodines. Tritium and I-133. Tritium. Particulates with i 15 mrem in a yr.

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

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

All Sources)

Organ Dose 1 25 area in a yr.

Thyroid Dose 1 75 mrem in a yr.

3.3.3.9 Liquid Effluent Monitor Setpoint 8 Liquid Waste Test Alarm Setpoint Eq. 5-1 T.S. 3.11.1.1 9 Tank Monitor N

TABLE B.1-1 5 (Continued)

?

> g Summary of Radioloalcal Effluent Technical Specifications and Implementina Eauations Technical Specification Cate'aory Method I Limit 3.3.3.10 Gasecus Effluent Monitor Setpoint Alarm / Trip Setpoint Eq. 5-9 T.S. 3.11.2.1 Plant Vent (Tots 1 Body)

Wide Range Gas for Total Body Dose Monitors Rate Al' arm / Trip Setpoint Eq. 5-10 T.S. 3.11.2.1 for Skin Dose Rate (Skin) us (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 II calculation, using actual release point parameters with annual average or concurrent meteorology and identified pathways for a real individual, shall be made.

8

2 a'

A

TABLE B.1-2 Summary of Method i Ecuations to Calculate Unrestricted Area Liauid Concentrations Equation Number Category Equation 2-1 Total Fraction of MPC in E C8 Liquids. Except Noble Gases Fg "" = ] yg _s 1 2-2 Total Activity of Dissolved "

as i

and Entrained Noble Gases C

us ' Ci '

from all Station Sources 1

' ,1

's 2E-04 b

r 1

ODCH Rev. 8 l

R12\86 B.1-6

TABLE B.1-3

- Summary of Method 1 Eauations to Calculate off-site Doses from Liculd Releases Equation Number Category Ecuation 3-1 Total Body Dose Dtb(mrem) = k E Og DFLitb 1

3-2 Maximum Organ Dose 0,o(arem)=kf0{ DFL 4,o 5

t i

ODCM Rev. 4 R12\86 B.1-7

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

2 TABLE B.1-4 Sununary of Method I Ecuations to Calculate Dose Rates -

i Ecuation Receptor Releasg Cateaory I umber Location

Hetoht Eauation .

Total Body Dose Rate From Noble 3-3a 05 E 6thte) - 0.85 . E (oi . 0Fai)

Gases t 3-3b OS G. 6tbts) - 3.4 . E (Og DFB,)

1 a 3-3c EC E 6tbE(e) = 0.0015 . E (Og . OFB,)

t

=

3-3d EC G 6tbt g) = 0.0074 . E (0, . OFs,)

m 1 l 3-3e R E 6t ent.3 - 0.038 . E (di . DFBi )

1 3-3f R G 6tbats)

0.2 . E (O i. DFB,)

1 4

8 9

?

G l

l *05 - Off-Site. EC - Science & Nature Center, formally the Education Center. R = The " Rocks" b

E - Elevated. G = Ground i

i 3

.__ _ _ . , . - - . - ,- _ , - - - . - , , , . . _ . - , - . . . _ . , _ , _ . _ . ..- - - - - - - . . , _ , - ,A _ . - . - , . - - , , .-- - - - _ _ . ---_,s,,---,-- - - , . - - - _ . - - - . . ,,- .%. - - , - - . . -. _ - = . ,. _ . . . . . . __ . . . . . -

TABLE B.1-4 Sununary of Method I Eaustions to Calculate Dose Rates (Continued)

Ec uation Receptor Releasg Category n umber location' Heicht Ecuation Rate From 3-4a 05 E 03 king,3 - E (0,

DF',g 3)

SeG e 3-4b OS G 03kgng,3 - E (Og

DF'g g,3) 1 3-4c EC E OskinEte) = 0.0014 . E (0,

DF'ittei) 1 cn h 3.4d EC G OskinEts) = 0.0014 . 1E (0i e DF'iE(s))

e 3-4e R E 05tingg 3 =0.0076 + E (O i DF' gag,3) 1 3-4f R G 0,gt,gg,3=0.0076 E (Q i DF'ta(g))

t i

8 9

?

~

O

- *05 - Off-Site. EC - Science & Nature Center, formally the Education Center, R - The " Rocks" l bE - Elevated, G - Ground

7..

TABLE B.1-4 ,

Summary of Method I Ecuations-to Calculate Dose Rates l

Ec uation Receptor Releasg '

i Catecon P umber location

Selaht Ecuation

! Critical Organ Dose Rate From I-131, Ocog,3 - E (0, OFG'ie.g 3) 1-133. H-3, and 3.Sa 05 E $

Particulate With Tifg >8 Days 3.5b 05 G b c .<,3 - E (og . DFG',c g,3) j 1 i

3.Sc EC E ocotte) -0.0014 . E (og . DFG'icotte))

i i "

3.5d EC G Ocotte) =0.0014 . E (Og . DFG'icottg))

l t 3.5e R E Oconte) =0.0076 . E (0, . DFG'icentel) t 3.5f R G Ocontg> "0.0076 . E (0,

DFG'icontg))

1 8

9 a'

w 4 ui

. l805 - Off-Site EC - Science & Nature Center, formally the Education Center, R = The " Rocks" b E - Elevated, G = Ground

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

1 '.

l _

l l

TABLE B.1-5 Summary of Method I Ecuations to Calculate Doses to Air From Noble Gases Ec uation Receptor Releasg Category ) umber location

Hetaht Eaustton 3.6a 05 E D,Tir(e) = 3.2E-07

t4.275*E(O i

DF[)

NbfeG$s t 3.6b 05 G D[irg,3 - 1.6E-06

t-o.293 . E (0,

DF[)

i 3.6c EC E D trEte) = 4.9E-10

t-o.252

E (Oi

DF[)

1 co

' 3.6d ' EC G D trE(g) = 4.4E-09 + t-o.321

E (0,

DF[)

1

~

3.6e R E D t rR(e) = 5.1E-09

t4155

E (0,

DF[)

t t

3.6f R G D f rR(g) = 4.1E-08 + t-o.204

E (0, '* DF[)

i 8

9 E

J G

- *05 - Off-Site. EC - Science & Nature Center, formally the Education Center, R - The " Rocks" l bE - Elevated, G = Ground

-_.&___ _ . _ _ _ _ . _ _ _ - - _ - _ _ - s.- __,u_ w e - _ _ _ _ _ _ _ _ w - - - ,a4 m+ ww _ ewe 6 .,w 4 .+ e se , m w .. v. om,.w e

TABLE B.1-5 Sununary of Method i Ecuations to Calculate Doses to Air From Noble Gases 4 1

Kontinued)

Eguation Receptor Releasg )

Category Number location

Height Ecuation b$e a 3.7a 05 E D[iri,3 - 4.1E-07

t-0 3

E (0,

DFf) 3.7b 05 G Dfirts) = 6.0E-06 . t-0 31' . E (0, . DFf) 1 3.7c EC E DfirEte) = 1.8E-09 + t-0 35

E (0g

DFf)

1 m

3.7d EC G DfirE(g) - 2.4E-08 + t-0 347 . E (0, . DFf)

~

t 3.7e R E OftrR(e) = 3.9E-08 e t-0.249 + E (Og

DFf) 1 3.7f R G DfirR(g) = 4.6E-07 . t-0.267

E (Og

DFf) 1 8

2 1

?

G l805 - Off-Site. EC - Science & Nature Center, formally the Education Center. R - The " Rocks" b

E - Elevated. G - Ground

TABLE B.1-6 Summary of Method I Eaustions to Calculate Dose to an Individual from Tritium. Iodine and Particulates Equation Receptor Release Catecory Number location

Height h Eauation Dose to Critical Organ From lodines. 3.8a 05 E

- ('I ~ ~ *

i* '**('I' Tritium, and Particulates 3.8b OS G Dcoto) " 17 7

t' '

E (Gi

DFGicog,3) 1 P '

Dcotte) - 3.3E-02

t *0 3"

E (Og

DFGicogg 3) 5 w

3.8c EC E 1

D cogg,3 - 3.3E-2

t-0 347

E (0,

DFG coE(c))

3.8d. EC G

-1 1

3.8e R E Deong,3 - 7.3E-02

t-0.248 . E (0,

DFG copte)) i Oco2(g) - 8.6E-02

t-o.zs7

E (0,

DFGmp) g 3.8f R G 9

?*

G 8 05 - Off-Site, EC - Science & Nature Center, formally the Education Center, R = The " Rocks" l b

E - Elevated G - Ground i

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

f TABLE B.1 7 Sumary of Methods for Setooint Determinations

_ Equation Number Cateaory Ecuation 51 Liouid Effluents:

Liquid Waste Test DF Tank Monitor R

setpoint ( ufd )= f 1 DFmin IC "I (RM 6509)

,j i 5 23 gggg,gagy;p{- RCset(gph) - 1x108 , $gg , g Gaseous Effluents:

Plant Vent Wide Range Gas Monitors (RM 6528-1, 2. 3) 5-5 Total Body gtb (pci/sec) - 588 5-6 Skin Rskin (pCf/sec) - 3000 I

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

TABLE B.1-8 Summary of Variables Variable Definition Units NG

- Concentration at point of discharge and pC1/ml C 11 entrained noble gas "i" in liquid pathways from all station sources us - Total activity of all dissolved and pCi C1 entrained noble gases in liquid pathways ml from all station sources C,d

- Concentration of radionuclide "i" at the Ci point of liquid discharge ,)

C,

- Concentration of radionuclide "1" Ci/ml C,,

- Concentration, exclusive of noble gases, Ci of radionuclide "1" from tank "p" at m) point of discharge C, - Concentration of radionuclide "1" in Ci/ml mixture at the monitor p = Off-site beta dosa to air due to noble mrad Dair(e) gases in elevate ( release p - Off-site beta dose to air due to noble mrad D

air (s) gas in ground level release p - Beta dose to air at Scierce & Nature mrad l DairE(e) Center due to noble gases in elevated release p - Beta dose to air at Science & Nature mrad l D aire (g) Center due to noble gases in ground level release p - Beta dose to air at " Rocks" due to noble mrr,d D airR(e) gases in elevated release p - Beta dose to air at " Rocks" due to noble mrad D airR(g) gases in ground level release Oy

= Off-site gamma dose to air due te gok mrad airte) gases in elevated release Dy

- Off-site gamma dose to air due to ,/. e . mrad air (s) gases in ground level release

- Gamma dose to air at Science & Nature mrad l Dy air k i Center due to noble gases in elevated release

- Gamma dose to air at Science ' Nature mrad l Oy eire (g) Center due to noble gases in i Sund level release

- Gamma dose to air at " Rocks" due to mrad Dy airR(e) noble gases in elevated release B.1-15 ODCM Rev. 15 l

TABLE B.1-8 (Continued)

Summary of Variables Va riable Definition Units

- Gamma dose to air at " Rocks" due to mrad Dy noble gases in ground level release aire (s)

D eog,3 = Critical organ dose from an elevated mrem release to an off-site receptor D,,g,3

- Critical organ dose from a ground level mrem release to an off-site receptor D,,gg,3

- Critical organ dose from an elevated mrem release to a receptor at the Science &

Nature Center

- Critical organ dose from a ground level mrem DcoE(s) release to a receptor at the Science &

Nature Center Deong.) - Critical organ dose from an elevated mrem release to a receptor at the " Rocks" D - Critical organ dose from a ground level mrem eonto) release to a receptor at the " Rocks" l Dd = Direct dose mrem

- Gama dose to air, corrected for finite mrad D[inite cloud

- Dose to the maximum organ mrem D.

D 3 = Dose to skin from Deta and gamma mrem D tb - Dose to the total body mrem DF = Dilution factor ratio D F,, ,

- Minimum allowable dilution factor ratio

- - Composite skin dose factor for off-site mrem-sec/pCi-yr DF i receptor I

- - Composite skin dose factor for Science & mrem-sec/pci-yr

' DF it Nature Center

- - Composite skin dose factor for the mrem sec/pCi-yr DF 1R ' Rocks" DFB,

- Total body gamma dose factor for nuclide mrem 3

i" (Table B.1-10) pCi-yr DFB, - Composite total body dose factor ,7,,3 pCi-yr

-. a -

B.1-16 ODCM Rev. 15 l

l TABLE B.1-8 (Continued)

Summary of Variables

.i Variable Definition Units DFLi g - Site-specific, total body dose factor mrem for a liquid release of nuclide "i" Egg (Table B.1-11)

D F Lj,, = Site-specific, maximum organ dose f actor mrem for a liquid release of nuclide "1" 7 (Table B.1-11)

Site-specific, critical organ. dose D F B,,,g ,3

- mrem /pCi factor for an elevated gaseous release of nuclide "1" (Table B.1-12)

DFG, cog,3

- Site-specific critical organ dose factor mrem /pCi for a ground level- release of nuclide "i" (Table B.1-12)

DFG icoE(e) = Science & Nature Center-specific mrem /pCi l. !

critical organ dose factor for an elevated release of nuclide "i" (Table B.1-14)

DFG,coggg3

= Science & Nature Center-specific mrem /pCi l :

critical organ dose factor for a ground )

level release of nuclide "1" (Table B.1- J 14)

DFG,cogg,3

- The " Rocks"-specific critical organ dose mrem /pC1 ,

factor for an elevated release of l nuclide "i" (Table B.1-15) ]

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

= e-spec W e c M eal o man dose rate mrem-sec j DFG'eo(e) t factor for an elevated gaseous release pgj jp of nuclide "1" (Table B.1-12) 1

- = Site-specific critical organ dose rate mrem-sec !

DFG factor for a ground level release of ico(o) pCi-yr nuclide "i" (Table B.1-12)

> = Science & Nature Center-specific mrem-sec l DFG icoE(e) critical organ dose rate factor for an -

pCi-yr -

elevated release of nuclide "i" (Table B.1-14)

> = Science & Nature Center-specific mrem-sec l DFGicoE(s) critical organ dose rate factor for a Ci-y r ground level release of nuclide "1" (Table B.1-14)

- = e ocksNspecWe cMcal oman dose mrem-sec DFG icoR(e) rate factor for an elevated release of "g #'

nuclide "i" (Table B.1-15)

B.1-17 ODCM Rev. 15 l

-TABLE B.1 .

(Continued)

Summary of Variables Variable Definition in,i.t L

- - The " Rocks"-specific critical organ dose mrem-sec !

, DFG1coR(g) rate factor for a ground level release pCi-yr of nuclide "i" (Table B.1-15)

DFS,

= Beta = skin dose f actor for nuclide "1" , p ,,,3 - ;

(Table B.1-10) pg g ,, ,

, D F',

- Combined skin dose factor for nuclide ,7,,, 3 '

"i" (Table B.1-10) pCi-yr 0Fy

- Gamma air dose factor for nuclide "1" mrad 4 3 1 (Table B.1-10) pC1 -y r ;

a = Beta air dose factor for nuclide "i" mrad e 3 DFT (Table B.1-10) pCi-yr gco(e) -. Critical organ dose rate to an off-site mrem receptor due to elevated release of yr iodines, tritium, and particulates

- Critical organ dose rate to an off-site mrem g**(8) receptor due to ground level release of yr iodines, tritium, and particulates

- Critical organ dose rate to a receptor mrem g**E(*)

l at the Science & Nature Center due to an yr.

elevated. release of iodines, tritium, and particulates

= Critical organ dose rate to a receptor mrem gcoE(g) at the Science & Nature Center due to a l- yr ground level release of iodines, tritium, and particulates

- Critical organ dose rate to a receptor mrem gor c (e) at the " Rocks" due to an elevated yr-release of iodines, tritium, and particulates

- Critical organ dose rate to a receptor mrem gcoR(g) at the " Rocks" due to a ground level -;--

release of iodines, tritium, and "r

particulates

- Skin dose rate to an off-site receptor mrem )

g5 H"(*) due to noble gases in an elevated yr release B.1-18 ODCM Rev. 15 l

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

TABLE B.1-8 l

(Continued)

' Summary of Variables Variable ' Definition jln.ill,

- Skin dose rate to an off-site receptor mrem g5 ki"(9) due to noble gases in a ground level yr release

= Skin dose rate to a receptor at the mrem gskinE(e) l-CCience & Nature Center due to noble

yr gases in an elevated release

- Skin dose rate to a receptor at' the mrem l g skine (g) Science & Nature Center due to noble l- l gases in a ground level release l

- Skin dose rate to a receptor at the mrem g skinR(e) Rocks" due to noble gases in an yp elevated release ,

=

S.Rocks" kin dose rate to a receptor at the mrem g skinR(g) due to noble gases in a ground yp level release j

= Total body dose rate to an off-site mrem 6tb(e) receptor due to noble gases in an yr elevated release

= Total body dose rate to an off-site mrem gtb(g) receptor due to noble gases in a ground yr level release l

= Total body dose rate to a receptor at mrem gtbE(e)' '

the Science & Nature Center due to noble yr l l gases in an elevated release .l 6 tbE(g)

= Total body dose rate to a receptor at mrem the Science & Nature Center due to noble. yr l i gases in a ground level release '

- Total body dose rate to a receptor at mrem gtbR(e) the " Rocks" due to noble gases in an yr elevated release i 4

= Total body dose rate-to a receptor at mrem )

gtbR(g) the " Rocks" due to noble gases in a yp ground level release l D/0 - Deposition factor for dry deposition of' 1 elemental radioiodines and other 7 particulates Fd - Flow rate out of discharge tunnel gpm or ft 3/sec F, = Flow rate past liquid waste test tank gpm monitor B.1-19 00CM Rev. 15 l

l I TABLE B.1-8 (Continued)

Summary of Variables Variable Definition M ,

F

= Flow rate past plant vent monitor cc set Fraction of total MPC associated with Paths Dimensionless fg3 f2

f3; =

f4 1, 2, 3, and 4

- Total fraction of MPC in liquid pathways Dimensionless tus p1 (excluding n0ble gases)

MPC,

= Maximum permissible concentration for Ci radionuclide "i" (10CFR20, Appendix B, cc Table 2 Column 2) l curies, or Og

= Release to the environment for radionuclide "i" pcuries pCi/sec i

- Release rate to the environment ft,r gi radionuclide "i" Liquid monitor response for the limiting pCi/mi R,,,,,,,, =

concentration at the point of discharge Reun = Response of the noble gas monitor to cpm, or pCi/sec i limiting total body dose rate Rg = Response of the noble gas monitor to cpm or pCi/sec limiting total body dose rate

' = Shielding factor Dimensionless Sg - ,

- Detector counting efficiency from the gas cpm mR/hr ;

5' monitor calibration pCi-cc M ,

S,,

= Detector counting efficiency for noble gas cpm or mR/hr i pC1-cc ' pC1/cc S

= Detector counting efficiency from the cps

, i

' liquid monitor calibration C1/ml

= Detector counting efficiency for cos Sn radionuclide "i" Ci/ml X/0 = Average long term undepleted atmospheric sec

dispersion f actor (Tables B.7-4, B.7-5, and g B.7-6)

[X/037 = Effective long-term average gamma see atmospheric dispersion factor g (Tables B.7-4, B.7-5, and B.7-6)

B.1 20 ODCM Rev. 14 R12\86

TABLE B.1-8 (Continued)

Summary of Variables Variable Definition Units SWF = Service Water System flow rate gph PCC - Primary component cooling water measured Ci/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 T

R12\86 B.1-21 ODCH Rev. 14

TABLE B.1-9 i

Definition of Terms i

Critical ReceDtor - A hypothetical or real individual whcse location and behavior cause him or her to receive a dose greater than any other possible real individual.

D2sg - 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 coumitment 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.

Liould Radwaste Treatment System - The components or subsystems which comprise the available treatment system as shown in Figure B.6-1.

1 l

l l

l i

1 1

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

l l

1

TABLE B.1-10 Dose Factors Specific for Seabrook Station for Noble Gas Releases Combined Skin Combined Skin Dose Factor for Oose Factor for Gamma Total Body Beta Skin Dose Elevated Ground Level 8 eta Air Gamma Air Dose Oose Factor Factor Release Points Release Points 00se Factor Factor 8 8 Radio- garem-m") y g garam-m*) ,1(e) garem-seeg

,,W garem-sec 3 yggerad-m3 PCL-yr

,7gerad-m pCi-yr 3

nUCIlde pCi yr pCi yr pCi yr pCi yr l Ar-41 8.84E-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 1.11E-03 1.35E-02 1.95E 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 1.11E-03 1.56E-04 Xe-133m 2.51E-04 9.94E-04 1.12E-03 1.12E-02 1.48E-03 3.27E-04 0 2.94E-04 3.06E-04 5.83E-04 4.40E-03 1.05E-03 3.53E-04 Xe-133 3.36E-03 Xe-135m 3.12E-03 7.11E-04 3.74E-03 1.99E-02 7.39E-04 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 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 8.84E 8.84 x 10'3 8

9 (P

..___-..___s_u._. -_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - . _ - - _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _

TABLE B.1-11 Dose Factors Soecific for Seabrook Station Liouid khleases Total ~ Body Maximum Organ 00se Factor Oose factor Radionuclide OFLitb(lhf) DFL,o(ggf")

4

I H3 3.02E-13 3.02E-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 4.18E 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 1.952 12 Ag 110m 1.01E-08 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 I-130 2.75E-11 3.17E-09 I-131 2.30E-10 1.00E-07 1-132 6.28E-11 6.36E-11 i 1-133 3.85E-11 1.15E-08 1-134 1.19E-12 1.41E-12 1-135 5.33E 11 4.69E-10 Cs-134 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 3.49E-09 La-140 1.07E-10 4.14E-08 ,

Ce-141 3.85E-11 9.31E 09 f Ce 144 1.96E-10 6.46E-08 Other* 3.12E-08 1.58E-06*

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

R12\86 B.1-24 00CM Rev. 14

?

TABLE B.1-12' Dose and Dose Rate Factors Specific for Seabrook Station todines.Tritiumanhhar'ticulateReleases j

Critical Critical Organ Critical Organ- '

. Organ Oose Factor' Critical Organ Dose Factor for Ground Dose Rate Factor. Dose Rate Factor for Elevated Level Release- for Elevated .for Ground Level-Release Point Point : Release Point Release Point . <

nuciide "b** INI ""8'** INI *I [I- *I ndi H-3 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 6.88E+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-06 -3.63E+01 1.24E+02 Nb-95 2.01E-06 6.86E-06 6.40E+01 2.20E+02 ]

Mo 99 1.63E 1.10E-07 5.39E-01 3.56E+00 1.04E-05 9.62E+01 3.31E+02, Ru-103 3.03E-06 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 I-133 1.45E-06 5.72E-06 4.57E+01 1.80E+02 i 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+03 l l

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 i Ce-144 6.09E-06 2.09E-05 1.93E+02 6.62E+02 i Other* 4.09E-06 1.39E-05 1.29E+02' 4.38E+02

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

B.1-25 ODCM Rev. 15 l

- l TABLE B.1-13 i l Combined Skin Dose Rate Factors Soecific for Seabrook Station SDeCial ReCeDtorS for Noble Ga5 Release Science &

Nature Center Science &

Combined Skin Nature Center The " Rocks" Dose Rate Combined Skin The " Rocks" Combined Skin Factor for Dose Rate Combined Skin Dose Rate Factor Elevated Factor for. Dose Rate Factor for Release Ground Level for Elevated Ground Level Release Point Release Point Release Point Point g m.m.

Radio- pp$* g mem- e, ,y"* g mem-me ) DF8

( mrem-see) y"* pei-yr e) ,

nuclide pei-yr pei-yr pei-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-85m 3.84E-03 4.08E-02 3.16E-02 2.69E-01 l

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 l 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 l l

Kr-90 3.15E-02 2.64E-01 2.14E-01 1.64E+00 Xe-131m 9.52E-04 1.19E-02 8.96E-03 8.07E-02 Xe-133m 1.99E-03 2.48E-02 1.87E-02 1.68E-01 !

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 l (1) See Seabrook Station Technical Specification Figure 5.1-1.

B.1-26 ODCM Rev. 15

]

TABLE B,1-14 Dose and Dose Rate Factors Specific for the Science & Nature Center l for odine. Tritium. and Particulate Releases Critical Critical Organ Dose Organ Oose Factor for Factor for Critical Organ Critical Organ Elevated Ground Level Dose Rate Factor Dose Rate Factor Release Release for Elevated for Ground Level Point Point Release Point Release Point-nuclide NW EI N* EI #"" p5-yr #"

pS-yr H-3 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 1.39E-06 5.71E-06 6.24E+01 2.39E+02 Fe-59 3.09E-07 1.89E-06 1.29E+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 Zn-65 7.34E 07 3.19E-06 3.31Et01 1.33E+02 Sr-89 1.15E-07 1.61E-06 3.63E+00 5.08E+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 Nb-95 1.53E-07 9.35E-07 6.43E+00 3.53E+01 Mo-99 1.62E 00 1.92E-07 5.58E-01 6.21E+00 Ru-103 1.30E 07 8.64E-07 5.33E+00 3.19E+01 l 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 2.47E+01 3.41E+02 l-133 1.84E-07 2.56E-06 5.83E+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 8a-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 9.24E-06 1.02E+02 3.91E+02 8.1-27 00CM Rev. 15 l

t TABLE B.1-15 '

Dose and [iose Rate Factors S]ecific for the " Rocks" particulate Releases "or lotine. 'ritium. ano Critical Organ Critical Organ Dose Factor Critical Organ Critical Organ Dose Factor for Ground Dose Rate Factor Oose Rate Factor s for Elevated Level . for Elevated for Ground Level r Release Point Release Point Release Point Release Point l nuclide ""$='' Ih"I "'8=** INI "8=** I A

I "# *** I gYI '

8 H-3 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-06 3.18E-05 2.55E+02 1.31E+03 ;

Fe-59 1.74E-06 1.17E-05 6.78E+01 4.29E+02 Co-56 2.01E-06 1.25E-05 8.11E+01 4.79E+02 Co-50 8.83E-05 4.09E-04 3.97E+03 1.85E+04 Zn-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 l 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 Moo 99 1.50E-07 1.34E-06 4.92E+00 4.32E+01 Ru-103 7.74E-07 5.47E-06 2.95E+01 1.96E+02 Ag-110m 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 I-133 1.95E-06 1.83E-05 6.18E+01 5.77E+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.i9E+02 Ce-141 3.59E-07 3.14E-06 1.20E+01 1.02E+02 Ce-144 7.02E-06 6.46E-05 2.25E+02 2.05E+03 >

Other* 9.56E-06 5.09E-05 4.16E+02 2.12E+03 B.1-28 00CM Rev. 15

-l

2.0 METHOD TO CALCULATE OFF-SITE LIOUID CONCENTRATIONS Chapter 2 contains the basis for station procedures used to demonstrate 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 FjENG) at the point of discharge from the station to the environment (see Figure B.6-1). Fj ENC' is limited to less than or equal to one, i.e.,

FENG < 1, 1

The total concentration of all dissolved and entrained noble gases at the point of discharge from the multiport diffuser from all station sources combined, denotedi C "', is limited to 2E 04 pCi/ml, i .e.,

Ci "S 1 2E-04 Ci/ml.

2.1 Method to Determine F ENG andCy0 First, determine the total fraction of MPC (excluding noble gases), at the point of discharge from the station from all significant liquid sources denoted Fj I"8: and then separately determine the total concentration at the point of discharge of all dissolved and entrained noble gases from all station sources, denoted C i "', as follows:

ENG Cj o

I l- (2'l)

F) MPC g l

uci/ml (pci/mi) l and: ;

l NG NG C)

Cg j 1 2E-04 (2-2) f

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

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

l R12/86 B.2-1 ODCH Rev. 12 I

i l

I C,, -.~ Concentration at point o'f 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 !

discharge can be made). C , is determined by dividing the product of the measured ra,dionuclide concentration in liquid waste test tanks PCCW. steam generator blowdown, or other l effluent streams timec 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).

C U - Total concentration at point of discharge of all dissolved .

I and entrained noble gases in liquids from all station sources (pC1/ml)

Ch - Concentration at point of discharge of dissolved and entrained !

j noble (pCi/m yas

) "i" in liquids from all station sources

~

2.2 Method to Determine ~ Radionuclide Concentration for Each Lio'uid Effluent Source ;

2.2.1 Waste Test Tanks C,i is determined for each radionuclide detected from the activity in a 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 BR$ evaporator is substituting for the waste evaporator, and distillate from the Steam Generator Blowdown 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

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

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

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

Sampling of this potential source is normally done once per week for

- determining the radioactivity ' released to the environment (see Table A.3-1). j j

2.2.3 Steam Generator Blowdown Flash Tank j 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-I 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.

Steam generator blowdown is only subject to' sampling and analysis when i 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 Coolinc 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 redweste in-leakage. If leakage has been determined, the Service Water System j is sampled to determine if any release to the environment has occurred.

R12/86 B.2 3 ODCM Rev. 12

w d

3.0 0FF-SITE DOSE CALCULATION METHODS' 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 II) for use l when more refined results are needed. This chapter provides the methods, data, and reference material with which the operator can calculate the needed l

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doses, dose rates and setpoints. For the requirements to demonstrate l compliance with Technical Specification off-site dose limits, the contribution j from all measured ground level releases must be.added to the calculated . j 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. I I

Chapter 7.0.

The Annual Radioactive Effluent Release Report, to be. filed after 'l January 1 each year per Technical Specification 6.8.1.4, requires that-meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and j measurement, be used for determining the gaseous pathway doses. For ,

continuous release sources (i.e., plant vent, condenser air removal exhaust, and gland steam packing exhauster), concurrent qui.(erly' average meteorology will be used in the dose calculations 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 4 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.

a-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.

B.3-1 ODCM Rev. 15 l

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4 assumptions, or parameters given in Regulatory Guide 1.109. and not already identified in the bases,of the 00CH. will be explicitly described in the

effluent report, along with the bases for the deviation.

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1 unw B.3-2 ODCM Rev. 12 7y

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 eres, 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, refers only to the doses received during the actual time period of exposure to 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 arem is said to have been exposed to a dose rate of 10 mrem / year, even though the actual dose received in the year of exposure may be less than 10 mrem.

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 at any time are limited to the equivalent annual dose limits of

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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 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 quantities, related to off-site doses or dose rates that demonstrate compliance with the RETS.

Delta D, denoted AD, is the quantity calculated by the Chapter 3, Method I dose equations. It represents the conservative increment in dose.

The AD calculated by Method I equations is not necessarily the actual dose l

ames B.3-3 ODCM Rev. 12

received by a real individual, but usually provides an upper bound for a given release because of the conservative margin built into the dose factors and the selection and definition of critical receptors. The radionuclide specific dose factors in each Method I dose equation represent the greatest dose to any l 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 I individual is likely to receive. Method 11 allows for a more exact dose )

calculation for eact individual if necessary, j l

D dot, denoted 6, is the quantity calculated in the Chapter 3 dose rate 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 maximum off-site annual dose if the peak observed radioactivity '

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 the order of an hour or less, this approach then provides assurance that 10CFR20.106 limits will be met.

Each of the methods to calculate dose or dose rate are presented in the following subsections and are summarized in Chapter 1. Each dose type has two levels of complexity. Method I is the simplest and contains 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 Chapter 3 for the various exposure types. A detailed description of the methodology, assumptions, and input parameters to the dose models that are applied in each Method 11 calculation, if not already explicitly described in the ODCM, shall be docuanted and provided when this option is used for NRC reporting and Technical Specification dose compliance.

unu B.3-4 ODCM Rev. 12

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3.2 Method to Calculate the Total Body Dose from Liouid Releases ,

- Technical Specification 3.11.1.2 limits the total body dose commiteent ,

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 radwaste treatment when the total body dose est.imate ex: . is 0.06 area in any 31-day period. Technical i 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 liquid release from the station as it is simpler to execute and more 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 du.*ing the month. See Section 7.1.1 for basis.

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

Dtb = k ][ Qi DFLith 1

(mrem) = ( ) (pC1) rg where j l

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. ;

l anue B.3-5 ODCM Rev. 14

O, - 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 .

3 discharge from the multiport diffuser (in ft /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 Method 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 l 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 ege-dependent individual via all existing exposure pathways. Table B.7-1 ;

lists the usage factors of Method 11 calculations. As noted in Section 8.7.1, l 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 shoreline l 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).

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3.3 Method to Calculate Maximum Oroan Dose from Liould Releases Technical Specification 3.11.1.2 limits the maximum organ dose commitment to a Member of the Public from radioactive material in liquid effluents to 5 arem per quarter and 10 arem per year per unit. Technical Specification 3.11.1.3 requires liquid radwaste treatment when the maximum organ dose projected exceeds 0.2 mres in any 31 days (see Subsection 3.11 for dose projections). Technical Specification 3.11.4 limits the maximum organ dose commitment to any'real member of the public from all station sources (including liquids) to 25 area in a year except for the thyroid - which is limited to 75 arem 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:

. '. = k 0, OFL%

y (3-2) 3 (mrem) = ( ) (pC1) where DFL % - Site'-specific maximum organ dose factor (mrem /pCl) for a liquid release. It is the highest of the four age groups. See Table B.1-11.

unas B.3-7 ODCM Rev.14

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. 0, = Total activity'( C1) released for radionuclide "1". (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 3

discharge from the multiport diffuser (in ft /sec). For normal 3

operations with a cooling water flow of 918 ft /sec, K is equal to 1.

r. !

a .

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

F ,

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 I Method 11 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, ,

I and used in the derivation of th.e simplified Method I approach as described in l the Bases"section, are also applied to Method II assessments, except that l doses cal'culated to critical organs from radioactive 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 8.7-1 lists the usage factors for Method 11 calculations. As noted in Section i 8.7.1, 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 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).

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unas B.3-8 ODCM Rev.14 ,

3.4 Mythod 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 500 mrem / year. 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 O tb to a rate equivalent to no more than 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.

Method I applies at all release rates.

Use Method II if a more refined calculation of Ogg 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 dcse 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. )

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cnu B.3-9 ODCM Rev.14

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' 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:

I 0.85

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DFBg) (3-3a)

Otb(e) =

E (0 1 .

,, mrem , pCi-sec 'pCi ' arem e 3

- yr pCi-m 3 (sec , , pCi-yr , ,

where l O to - The off-site total body dose rate-(mres/yr) due to noble l gases in elevated effluent releases.

6, = the release rate at the station vents (pC1/sec). for each noble gas radionuclide, "i", shown in Table B.1-10, and 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 ground level effluent releases can be determined as follows:

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E (0:

DFB g ) (3-3b)

Otb(s) =

1 l 4

r 3 j 3

mrem e 3 mrem , pCi-sec ,p 'nci ' ,

yr pCi-e 3 , s sec, , pci-yr ,

I j.where l

l O tb - The total off-site body dose rate (mres/yr) due to noble l gases in elevated effluent releases, and l

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

i unu B.3-10 ODCM Rev.14

For the special on-site receptor locations, the Science & Nature Center l and the " Rocks," the total body dose rates due to noble gases in effluent discharges can be determined as follows:

For the Science & Nature Center, elevated effluent release: l 6tbE(e) = 0.0015 E (0 $e DFB,) (3-3c) t For the Science & Nature Center, ground level effluent release: l-6t3cc,) - 0.0074 E(og DFBi ) (3-3d) t For the " Rocks," elevated effluent release:

(3-3e) 6tbR(e) = 0.038 . tE (0$ e DFBt )

For the " Rocks," ground level effluent release:

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1 btbR(g) = 0.2 E (Og

DFBi ) (3-3f) t where DtbE(e)'btbE(g) btbR(e), and 6tbR = The total body dose rate (mrem /yr) at the Science & Nature Center and l the " Rocks," respectively, due to noble gases in gaseous discharges from elevated (e) and ground level (g) release points, and j l

0, and DFBi are as defined previously.

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

B.3-11 ODCM Rev. 15 l

1. Normal operations (nonemergency event), and

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

3.4.2 Method 11 Method II 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 ODCH. 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 II 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 gamum atmospheric dispersion 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.

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3.5 Method to Calculate the Skin Dose Rate from Noble Gases Technical Specification 3.11.2.1 limits the dose rate at any time to the skin from noble gases at any location at or beyond the site boundary to 3,000 mrem / year. 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 Osun 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 Osun 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 i 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.

l Use Method II if a more refined calculation of'6,un 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 7.2.2 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.

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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:

I Oskinte)= E (0,

DF,'g,3) l '

l (3-4a) mrem 'pCi ' ' mrem-sec '

yr sec, ( pCi -y r ,

where 1

l 0,ging,3 = the off-site skin dose rate (mrem /yr) due to noble gases in l

an effluent discharge from an elevated release point.

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l 0, - as defined previously, and I

l DF'g.) = the combined skin dose factor for elevated discharges (see l Table B.1-10).

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

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l Oskin(g) " E (01

DF'<,3)i (3-4b) i I

l where l

l 0,gioc,3 - The off-site skin dose rate (arem/yr) due to noble gases in l

an effluent discharge from a ground level release point, I

l Og - as defined previously, and I

l D F,' g ,3 = The combined skin dose factor for ground level discharges

] (see Table B.1-10).

unse B.3-14 ODCM Rev.14

For.an on-site receptor at the Science & Nature Center and elevated l release conditions, the skin dose rate due to noble gases is:

0,utng< 3 = 0.0014

E (Qi . DF'gc,3) t (3-4c) i where Ds unE(e)

= The skin dose rate (mrem /yr) at the Science & Nature . l Center due to noble gases in an elevated relea'se, 0, = as defined previously, and DF = the combined skin dose factor for elevated discharges Ete)

(see Table B.1-13).

't For an on-site receptor at the Science & Nature Center and ground level l release conditions. the skin dose rate due to noble gases is:

Os unE(g) = 0.0014 . E (0i . DF E(g)) (3-4d) i where Os unE(g) = the skin dose rate (mrem /yr) at the Science & Nature Center l due to noble gases in a ground level release.

Qi - as defined previously, and DF E(g) " The combined skin dose factor for ground level discharges (see Table B.1-13).

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

bskinR(e) = 0.0076 . E (oi

DF gg,3) (3-4e) 1 B.3-15 ODCM Rev. 15 l

l l where l

l Ostinac.)

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

l l Og - as defined previously, and l

l DF'gg.)

i

- The combined skin dose factor for elevated discharges (see l Table 8.1-13). '

j l

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

l i OstinR(g) - 0.0076 = (0,eDF'n(g)) i (3-4f) i

)

l 2 l where I

l 0 ginng,3 - the skin dose rate (arem/yr) at the " Rocks" due to noble l gases in a grounc level release, I .

l 01 - - as defined previously, and l

l DFj ag,3

- the combined skin dose factor for ground level discharges l (see Table 8.1-13).

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

1. Normal operations (nonemergency event), and

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

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- 3.5.2 Method 11 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 ODCM. The general equation (B-9) {

taken from Regulatory Guide 1.109, and used in the derivation of the l 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 I 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.

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3.6 Method to Calculate the Critical Orcan Dose Rate from iodines. Tritium and Particulates with T1/2 Greater Than 8 Days Technical Specification 3.11.2.1 limits the dose rate at any time to any 131 1, 133 , 3H and radionuclides in particulate form with half lives organ from 1 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 cont,inued release at the peak rate. By limiting De ,

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.

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

Use Method II if a more refined calculat'on 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 rate greater than the Technical Specification limit to determine if it had I i

actually been exceeded during a short time interval. See Section 7.2.3 for basis.

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: l 1

l Oe ,(,) -

(0

DFGico(e)I ,

l (mrem) , g pCi ) , g mrem-sec) yr sec pCi-yr l

l where l

l 0 cot.) - The off site critical organ dose rate (mrem /yr) due to l l

iodine, tritium, and particulates in an elevated l release, ,

l utsse B.3-18 ODCM Rev.14

Qy - the activity release rate at the station vents of radionuclide "i" in pCi/sec (i.e., total activity measured of radionuclide "i' averaged over the time period for which the filter / charcoal sample collector -

was in the effluent stream. For i = Sr89 or Sr90 use the best estimates, such as most recent measurements),

and DFG' geog ) = the site-specific critical organ dose rate factor

( arem-sec ) for an elevated gaseous release (see pC1 -y r Table B.1-12).

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

De g,3 = E (0, DFG' 3cog,3) (3-5b) 1 where 0,,g,) = the off-site critical organ dose rate (mrem /yr) due to iodine, tritium, and particulates in a ground level release.

. 0, = as defined previously, and D FG{,,g,3 - the site-specific critical organ dose rate factor for a ground leycl gaseous discharge (see Table B.1-12).

For an on site receptor at the Science & Nature Center and elevated l release conditions, the critical organ dose rate can be determined as:follows:

+

OcoE(e) = 0.0014 * }[(0, D FG,' cog g ,3 ) (3-Sc) '

1 B.3-19 ODCM Rev. 15 l r . . . _ - - , . ._ - _.

I l

I where Dc otte)

= The critical organ dose rate (mrem /yr) to a receptor ,

at the Science & Nature Center due to iodine, tritium,

'l and particulates in an elevated release, Dj - as defined previously, and

= the Science & Nature Center-specific critical organ l DFG'cotte) i dose rate factor for an elevated discharge (see Table B.1-14).

l For an on-site receptor at the Science & Nature Center and ground level release conditions, the critical organ dose rate is:

6cotto) = 0.0014 E (0 e$ DFG,'cogg,3) (3-5d) i where ,

0,,gc,3 - the critical organ dose rate (mrem /yr) to a receptor at the Science & Nature Center due to iodine, tritium, l

and particulates in a ground level release, Os

- as defined previously, and l OFGse gc,3

- the Science & Nature Center-specific critical organ dose rate factor for a ground level discharge (see Table B.1-14).

For an on-site receptor at the " Rocks" and elevated release conditions, the critical organ dose rate is:

0coR(e) = 0.0076 * { (0,

DFG,',,gg,3 ) (3-Se) 1 where l B.3-20 ODCM Rev. 15 i

6egge3 = The critical organ dose rate (mrem /yr) to a receptor l c at the " Rocks" due to iodine, tritium. and l

l particulates in an elevated release, l Og - as defined previously, and I .

l DFG ieong.3 = the " Rocks"-specific critical organ dose rate factor l

for an elevated discharge (see Table B.1-15).

l l

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

l l Ocontg) = 0.0076 E(0,

DFG'coR(s))

l (3-5f) 1 l where ,

I l Dn ea and Dj

= are as defined previously, and I ,

l DFG icon (g) = the " Rocks"-specific critical organ dose rate factor l

for a ground level discharge (see Table B.1-15).

l l Equations 3-53 through 3-5f can be applied under the following conditions (otherwise, justify Method I or consider Method II):

i

1. Normal operations (not emergency event), and

2. Tritium I-131 and particulate releases via monitored station j vents to the atmosphere. l l

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amu B.3-21 ODCM Rev. 14

3.6.2 Method II Method 11 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 OOCH (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 f actors in accordance with Sections 7.3.2 and 7.3.3 for the release point I (either ground level or vent stack) from which recorded effluents have been f 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.

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anue B.3-22 ODCM Rev. 14

i I

I 3.7 Method to Calculate the Gamma Air Dose 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. Dose evaluation is required at least once per 31 days.

Use Method I first to calculate the gasuna 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 l Technical Specification limit to determine if it had actually been exceeded.

See Section 7.2.4 for basis.

3.7.1 Method I j The general form of the gamma air dose equation.is:

l Dj,, = 3.17E-02 . [X/0]Ihr

t d e (0, e DFJ) (3-6)

9 f 1 pC1 -y r ' sec mrad-m 3 (mrad) = ,

m3 e( ) E(C1) pCi-yr ,

gpCi-sec, ,

g

[

where ,

07g ,is the gamma air dose.

i 3.17E-02 is the number of pCi per pCi divided by the number of second per year, l [X/0]{n, is the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months gamma atmospheric dispersion factor.

t is a unitiess factor which adjusts the 1-hour [X/037 value for a l release with a total duration of t hours, 0, is the total activity in pCi of each radionuclide "i" released to the atmosphere frown the station gaseous effluent release point during the period of interest, and unu B.3-23 ODCM Rev. 14

DFT i is the gamma dose factor to air for radionuclide "i" (see Table B.1-10).

Incorporating receptor location-specific atmospheric dispersion factors

([X/0F), 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 gamma air dose can be determined.

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

DJi,g,3- 3.2E-07

t 4 .275 E(0,

DFJ) (3-6a) 1 e s pCi-y r mead-m 3 (mrad) = *( )*E(pC1)

Ci-m3 , s pC1-yr ,

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

Dlirgg3- 1.6E-06

t4 .293

E(Oi e DFJ) (3-6b) 1 I I f S pCi-yr *( mrad-m 3 (mrad) = )

E( C1) pCi-yr ,

Ci-m3 , i l c. Science & Nature Center receptor; elevated release conditions:

Dlirgc.3 - 4.9E-10

t-o.252

E (Oi*DF7) (3-6c) 1 3

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

pCi-m 3 pCi-yr l d. Science & Nature Center receptor: ground level release conditions:

D trt(g) = 4.4E-09

t-o.321

E (Oi*OF[) (3 6d) 3 (mrad) = ( pCi-yr ) * ( ) E ( Ci e mrad-m pCi-m 3 pC i -y r )

l B.3-24 ODCM Rev. 15

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

l DltrR(e) = 5.1E-09

t-0155

E (Og

DF[) (3 6e) 3 (mrad) = ( pCiP) * ( ) E (pCi , mead-m )

pCi-e 3 pCi -yr

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

l D trR(g) = 4.1E 08

t-o.rN

E (Os

DF[) (3-6f) 1 3

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

Ci-m 3 pCi -y r Equations 3-6a through 3-6f can be applied under the following conditions (otherwise justify Method I or consider Method II): l I

1. Normal operations (nonemergency event), and

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

I I

3.7.2 Method 11 Method !! 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 i Section 7.2.4 are also applied to Method 11 assessments. Concurrent meteorology with the release period may be utilized for the genna atmospheric j 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 effluentt, have been discharged.

unu B.3 25 ODCM Rev. 14

1 1

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 f gases at any location at or beyond the site boundary to 10 mead in any quarter J and 20 mrad in any year per unit. Dose evaluation is required at least once per 31 days.

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

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:

l 0

Dair = 3.17 E-02 * (X/0)1hr

t *

E (Og

DFf) (3-7)

- , j 3

pCi-yr ' sec ,( ),p ,gg , mrad 4 (mrad) = ,

,pci -s ec , m 3 s pCi-yr ,

where .

08air is the beta air dose, 1

3.17E-02 is the number of pCi per pCi divided by the number of seconds per year, l

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. I l

Og is the total activity (pC1) 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) .

! una B.3-26 ODCH Rev.14 i

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: ,

Df,,g.) = 4.1E-7

t4*3

E (Os

DFf) (3-7a) 1 3

(mrad) = ( pCi-yr ) * ( ) ( Ci e arad-m )

pCi-e 3 pCi-yr

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

Dfirgo - 6.0E-06

t-0 3"

E (0,

DFf) (3-7b) t 3

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

pCi-m 3 pCi-yr

c. Science & Nature Center receptor; elevated release conditions: l DFf) (3 7c)

OfirE(e) = 1.8E-09

t-0 35

tE (Oi .

1 3

(mrad) = ( pCl-yr) * ( ) E (pCi e mead in )

pCi-e 3 pCi-yr ,

i B.3-27 ODCM Rev. 15 l )

I j d. Science & Nature Center receptor: ground-level release conditions: j (3-7d) !

DfirE(g) = 2.4E-08

t4 3d7

E (0,

DFf) t 3

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

mrad-m )

pCi-m 3 pC1 -yr

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

Ofirace) = 3.9E-08

t-o.20

E (Os

DFf) (3-7e) 3 (mrad) = ( pCi-yr ) * ( ) (pCi

mrad 4 )

pCi-m 3 pCi-yr

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

OfirR(g) = 4.6E-07

t4.267

E (0,

DFf) (3-7f) 1 3

(arad) = ( pCi-yr ) * ( ) ( Ci e mrad-a )

pCi-m 3 pCi-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.

i l B.3 28 ODCM Rev. 15

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 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'7.2.5 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.

l l

1 i

l l

l una B.3-29 ODCM Rev.14

I 3.9 Method to Calculate the Critical Orcan Oose from lodines. Tritium and Particulates 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 sources (including gaseous effluents) to 25 mrem in a year except for the thyroid, which is limited to 75 mrem in a year.

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

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

Use Method 11 if a more refined calculation of critical organ dose is l needed (i.e., Method I indicates the dose is greater than the limit). See )

Section 7.2.6 for basis. l 3.9.1 Method i l

l De , = (X/0)l$I /(X/0)l*,'I

t *

E (Qi DFG,e,) (3 8)

(mrem) = ( sec 3

)f( sec 3

)*( )

E (pCi) * ( "* )

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

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

l ( X /0)l*'I

, is the annual average depleted atmospheric dispersion, t** is a unitiess adjustment factor to account for a release with a total duration of t hours, unu B.3-30 00CM Rev.14

Os is the total activity' in pCi of radionuclide "i" released to the atmosphere during the ,oeriod of interest (for strontiums, use the most recent measurement), and DFG ic , is the site-specific critical organ dose f actor for radionuclide "i", see Tables B.1-12. B.1-14, and 8.1-15. (For each radionuclide, it is the age group and organ with the largest dose factor.)

Incorporating receptor location-specific atmospheric dispersion factors

((X/0)T and (X/0)[f) 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.

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

Dcog,3 = 14.8 . t-o.297 . E (0, . DFG eoci 3) (3-8a) 1 (mrem) =( ).( ) E (pCf a mrem) pC ).

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

Dcog,3 = 17.7 . t-0 3M e E(Oi DFGieocg>) (3-8b) 1 (mrem) = ( ).( ) E ( C1 e mrem) pC).

c. Science & Nature Center receptor; elevated release conditions: l Dcotte) = 3.3E-02

t-0** E (0, . DFGieoE(e)) (3-8c) 1 (mrem) = ( ).( ) E (pCf

meem) .

pC1 B.3 31 ODCM Rev. 15 l

t.

o

d. Science.& Nature' Center receptor: ground-level release conditions:

l-D cotto) " 3.3E-02

t ~0 "7

E (Os

DFG coE(g)) i (3 8d) ;

1

(: .l (mrem) = ( )*( ) E ~(kCi * )

l

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

)

Deonce) = 7.3E-02

t-0.24s * (Og

DFGicomtes) (3-8e)

(mrem) =( )*( ) E (pCi * )

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

De ong,3 = 8.6E-02

t4.267

E (Og

DFGje.ac,3) (3-8f) i 1

(mrem) = ( )*(- ) E (pCi * ) i Equations 3 8a through 3-8f can be applied under the following conditions (otherwise, justify Method I or consider Method !!):

1. Normal operations (nonemergency event),,

2. Iodine, 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 11 Method Il consists of the models, ir st 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, l B.3-32 00CM Rev. 15

i 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 l critical organ dose will consider the four age groups independently, and use a shielding factor (Sr) of 0.7 associated with residential structures.

1 l

I usuu B.3-33 ODCM Rev. 14

l 1

3.10 Method to Calculate Direct Dose from Plant Operation 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 (including direct radiation from station facilities) to 25 mrem in a calendar ,

year (except the thyroid, which is limited to 75 mrem). 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 boundary which are part of the >

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).

The dose determined from direct measurements or calculations will be 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 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.

anus B.3-34 ODCM Rev.14

3.11 Dose Projections Technical Specifications 3.11.1.3 and 3.11.2.4 require that appropriate portions of liquid 'and gaseous radwaste treatment systems, respectively, be used to reduce raoioactive 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 I 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 treatment systems or gaseous radwaste treatment systems are not being fully 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 Liouid Dose Proiections The 31-day liquid dose projections are calculated by the following:

Determine the total body Dtb and organ dose D (Equations 3-1 and (a) l 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 when the plant is l

shut down.

(b) Calculate the ratio (R g) of the total estimated volume of batch releases expected to be released for the projected pe'iod r to that actually released in the reference period.

Calculate the ratio (R 2) of the estimated gross primary coolant f (c) '

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, B.3-35 ODCM Rev. 14 unu

e r

(d) Determine'the projected dose from:

Total Body: Dtb er " Dtb . Rg . R 2

Max. Organ: D, ,, - D, , R3 . R 2

6 3.11.2 Gaseous Dose Projections ,

r For the gaseous radwaste treatment system, the 31-day dose projections are calculated by the following:

(a) Determine the gamma air dose D ir (Equation 3-6a), and the beta-air dose Dfir(Equation 3-7a) from the last typical 31 day 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 atmosphere over the next 31-days to the number of curies released in the l reference period on which the gamma and beta air doses are based. ;

If no differences between the reference period and the next 31 days can be identified, set R3 to 1. )

(c) Determine the projected dose from: ,

i Gamma Air: DJge,,=D tr . R3 -

l Beta Air: Ofir or = Dfi, . R 3 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:

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 j l Specification 3.11.2.4.c. (i .e., 0.3 mres 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 l

1 i

unu B.3-36 ODCM Rev. 14 j

_ . _ _ ~

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 i current determination of DE I-131 as the projected value if no .:

trend can be determined.

(c) Calculate the ratio (Rs) of anticipated primary system leakage rate to the average leakage rate during the reference period. Use .

the current voice of the fystem lenkage 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,, ,, - D,, . R 4

. R5 l

1

-1 J

l Note: This action is based on the assumption that tritium is the-controlling '

l nuclide for whole body exposures through the inhalation pathway.

l Maximum 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 00CM 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 arem, the on-site maximum dose due to l

inhalation would be approximately 3.0 arem 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 occupancy l factor applied, the projected inhalation whole body dose would be l approximately 8 aren, or 85 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.

sma B.3-37 ODCM Rev. 34

I l

l 4

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. )

I Direct radiation measurements are analyzed at the station. All other j radiological analyses for environmental samples are performed at the Yankee l 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 srtwing 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. I 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, aerial survey, or consulting with local agricultural authorities.

Technical Specification 6.8.1.3 requires that the results of the Radiological Environmental Monitoring Program be sununarized in the Annual Radiological Environmental Operating Report 'in the format of the table l's the Radiological Assessment Branch Tcchnical Position, Revision 1, 1979.' The general table forinat will be used with one 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 ODCM Table A.5-2 for that radionuclide and sample medium.

l l

l 1

l i

1 i

B.4 1 ODCM Rev. 9 l

l 1

. - . = ..

TABLE B.4-1 Radiolooical Environmental Monitorino Stations (*)

Distance From Exposure Pathway Sample f .dtion Unit 1 Direction From and/or SamDie and Desi3puisi Code Containment (km) the Plant

1. AIRBORNE (Particulace and Radiof fi:,> ,

AP/CF-01 PSNH D Te 2.7 ESE Landing Area AP/CF-02 Hampton'4aritto 2.7 E AP/CF-03 SW Boundbry 0.8 SW AP/CF-04 W. Boundar. 1.0 W AP/CF-05 Winnacunnet .J.(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 (b) 5.3 E <

SE-07 Hampton Beach 3.1 E SE-08 Seabrook Beach (b) 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, MA 5.2 SW TM-08 Hampton Falls, NH 4.3 NNW TM-15 Hampton Falls NH 7.0 NW TM-16 Kensington, NH(b) 7,7 yyy l

TM-20 Rowley, MA (Control) 16.3 5

b. Fish and Invertebrates ICI FH 03 Hampton - Discharge 4.5 ESE Area FH 53 Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Discharge 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 I B.4-2 00CM Rev. 15

TABLE B.4-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING STATIONS (*3 Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Desianated Code Containment (km) the Plant

4. DIRECT RADIATION TL-1 Brimmer's Lane, 1.1 N Hampton Falls TL-2 Landt;g Rd., Hampton 3.2 NNE

-- TL-; 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 Barge Landing 2.7 ESE Area TL-7 Cross Rd., Seabrook 2.6 SE Beach TL-8 Farm Lane, Seabrook 1.1 SSE TL-9 Farm Lane, Seabrook 1.1 S TL-10 Site Boundary Fence 1.0 SSW TL-11 Site Boundary Fence 1.0 SW TL-12 Site Boundary Fence 1.0 WSW 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 ENE Hampton Beach TL-21 Route 1A, Seabrook 2.7 SE Beach TL-22 Cable Ave., 7.6 SSE Salisbury Beach TL-23 Ferry Rd., Salisbury 8.1 S TL-24 Ferry Lots Lane, 7.2 S5W Salisbury TL-25 Elm St., Amesbury 7.6 SW TL-26 Route 107A, Amesbury 8.1 WSW B.4-3 ODCM Rev. 4

TABLE B.4 (continued). -

r RADIOLOGICAL ENVIRONMENTAL MONITORING.STATI0F$

W 4

Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Samole and Desienated Code Contain==nt (km) the Plant -

TL-27 Highland St., 7.6 W

S. Hampton -

TL-28 Route 150. Kensington 7.9 WNW

, TL-29 Frying Pan Lane, 7.4 NW Hampton Falls TL-30 Route 101C, Hampton 7.9 NNW Alumni Drive Hampton TL-31 4.0 NNE TL-32 Seabrook Elementary 1.9 S School TL-33 Dock Area, Newburyport 9.7 5 12.1 TL-34 Bow St., Exeter NW TL-35 Lincoln Ackerman 2.4 NNW School TL-36 Route 97, Georgetown 22 SSW ,

(Control)

TL-37 Plaistow, NE (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)M Ipswich, MA (Control)N 27 TL-42 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 ODCH: 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 !

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 oJ plant-related radioactivity. Some pelagic species (such as herring and mackerel) tend to school and wander _

)

throughout a large area, sometimes making catches of significant size difficult to obtain. Since the collection of all species would be difficult or l impossible, and would provide unnecessary redundancy in terms of monitoring important pathways to man, three fish and invertebrate species have been specified as a minimum requirement. Samples may include marine fauna such as lobsters, class, 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 RADIO 1DCICAL ENVIRONMENTAL MONITORING IDCATIONS WITHIN 4 KIIDtiETERS OF SFABROOK STATION

.l N

)

b l

Q v4 '

> n. Vf4 ry B RIVER ;

SEABROOK g f k AP/CF A AP/CF-03 A __

r# A L

H CREEK AP/CF-01'A a

SE-08 A

/ '

f

) \5 j?

g u 0 500 1000 $ "

h METERS

/ m B.4-5 ODcM Rev.15

FIGURE B.4-2 RADIO 1DGICAL ENVIRONMENTAL MONITORING IDCATIONS BETVEEN 4 KIIDMETERS AND 12 KILOMETERS FROM SEABROOK STATION R ,

0 5 K j W '" W H KILOMETERS t

8 E

8 s, '

N RYE BEACH TM-09 A ,,

TM-15 A SEE ENLARGEMENT IN FIGURE B.4-1

_ _T _ _ e .^Ic!?S I

TM-16 A l l l l e-- HAMPTON BEACH l l A SE-07 SEABROOK STATION a 1 A% DISCHARGE SITE ;

i WS-01 i SE-02 MU-06

. ~~~~ ~, i I FH-03 HA-04

\ -

/ l% SEA 8ROOKBEACH

,x, '

,___% , x . _ . ..

TM-04-A SALISBURY BEACH b

MERRIMAC NY O I ATLANTIC OCEAN B.4-6 ODCM Rev.15

TICURE B.4-3 RADIOll)CICAL ENVIRONMENTAL MONITORING TLCATIONS OUTSIDE 12 KILOMETERS OF SEARROOK STATION 1.

f .

0 5 10 15 I

KILOMETERS ,

YORK e

DURHAM e

.\ Ahty ,'

NEWMARKET e CRTSMOUTH e -.

' O

, EPPING \

t' 'g

),

-___q-__---____ ,

,[p\?.

i i SEE ENLARGEMENT IN FIGURE l '

8.4 > I I HAMPTON I e I t i 8 SEABROOK STATION l'

KINGSTON e \' HAMPTON HARBOR E --

l SEABROOK e

, ~~.-

N---

, N 'HARGE $1TE DISC i

I e SALISBU!tY

/ l'AMES8URY

e 8 PLAISTOW e / iy ,

l

/ 4 j

44h .NEWBURYPORT e ATLANTIC OCEAN

! HAVERHILLe

! , A SE-57

, , ,1, I PLUM ISLAND .

. TM-20 FH-53 HETHUEN e AP/CF-06 A A SE-52 A WS-51 e W RENCE IP5WICH BAY IPSWICH e A MU-56 HA-54

- l GLOUCESTER B.4-7 ODCM Rev. 8 e

l j

FIGURE B.4-4 DIRECT RADIATION MONITORING IACATIONS WITHIN 4 KIIDMETERS OF SEABROOK STATION r

NNW N NNE N

J A TL-2 NE

$6 i 8

NW NATL-35 V

A TL-3 4 Y o A TL-4 ENE A +

TL-15 A TL-16 47 A TL-1 #ff WNW TL-14 A R0WM VER SEABROOK g STATION gE W yt.g3 3 TL-5 A TL-12 A s J

TL-11 A H TS IS CREEK TL-10 A TL-6 A

~

-8 A A D

TL-9 ESE

/ $ A TL-7 5

TL-32 A d SW ==

85o 2

/ 0 500 1000 5

9 g

u h

f

TL 1 METERS tf SSW

'/

S SSE N

SE I

B.4 8 ODCM Rev.15

TICLTE B.4a5 DIRECT RADIATION MONITORING LOCATIONS BET.*EEN i

4 KILOMitin9 AND 12 KILOMETERS MOM SEAER00K STATION l i

N NNE

= N'NW '

0 $

E l'

\8

=i KILOMETERS

i 5

NW NE

$f N

A TL-34 5 Miles h J :

~~ A RYE BEACM TL-17 A A

TL-30 TL-13 A TL-19

[

\

A TL-29\

GE WW ,

\~

SEE ENLARGEMENT IN FIGURE 8.4-4 g~~

I A TL-28 i i

?' """

A TL-27 lw SEA 8 ROCK STATION s i DIS i

RGE SITE W

i i

k ,,.

- %., i N.' i SEABROOK BEACH TL-26 I'N. '-

, s

,1

s-- 9, - .

WSW f\ k SA $8URY.8EACH TL-22 TL-24 A A)

Q 4 SE sc %@ ,

TL-33 A 5 g

/ SW 5 SSE SSW CDcM Rev, a 3.4 9

FIGURE B.4-6 ,

DIRECT RADIATION MONITORING LOCATIONS OUTSIDE 12 KILOMETERS OF STARROOK STATION NNW N1,T NNE 0 5 10 15 gy KILOMETERS -

e YORK l

, , Q OURNAM e s NE, Riyh '

s TL-40 A

\ RAYMOND NEWMARKET e PORTSMOUTHe TL-41

.g e DPING 10 Miles -

e \

\,Ta WNW __

s- ENE FREMONT - I i i N TL-390 e e gXETER SEE ENLARGIMGT IN FIGURE , ;

I* ~'

s HAMPTON l -

SEA 8R00K STATION j.- *'

W KINGSTCge 8

NN =

I

r E

l Sun 00K .

I Kf.4 O!$ CHARGE SITE

,/ *j ,,'g3,ggy , o MM ,

PtAISTOW e. , i / i TL-37 A / i 8 EsE N.N =

l I

,' . - . #,dg},!-

NEWluRYPORT . ATLANTIC OC D N Wsw M4vERHItt e'

/

PLUM 15LANO

. , ,1 ETHUEN e TL-36 A e LAWR DCI !PSVICM SAY sE IP5VICH e 4TL-42 i sW ssW s ssEh.__ \

B.4-10 ODCM Rev. 11

- ~ ~

5.0 SETPOINT DETERMINATIONS Chapter 5 contains the methodology for the calculation of effluent .

monitor setpoints to implerent the requirements of the radioactive effluent i

- monitoring systems Technical Specifications 3.3.3.9 and 3.3.3.10 for ligulds gases, respectively. :

Example setpoint calculations are provided for each of the required effluent monitors.

J f

L B.5-1 8686R ODCM Rey, y

i 5.1 Llauld 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 3.11.1.1 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 Llauid 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 Liould Waste Test Tank Monitor (RM-6509)

The instrument response (pC1/ml) for the limiting concentration at the point of discharge is the setpoint, denoted Rsetpoint, and is determined as follows:

R setpoint " 1 0 mi ( ~1' min 1 (pCl/ml) ()() (h) where:

OF

=[F*

= Dilution factor (dimensionless) (5-2) 1 I

l F, = Flow rate past monitor (gpm) ,

I F

d

- Flow rate out of discharge tunnel (gpm) l DFmin - Minimum allowable dilution factor (dimensionless)

B.5-2 1 8686R ODCM Rev. 4 i

f) -

1 - (f2+# 3 + I4); where fj -is the fraction cf the total contribution of MPC at the discharge point to be

- associated with the' test tank effluent pathway and, 2f ' I '3 -

and f 4 are the similar fractions for Turbine Building sump, steam generator blowdown, and primary component cooling pathways, respectively: (f) + f2*I3+I4 I I}'

0F (5-3) min " M g.

MPC g - MPC for radionuclide "1" from 10CFR20, Appendix B. Table II, ,

Column 2 (pC1/ml). In the event'that no activity i: expected 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 ,g. - Activity concentration of radionuclide "1" in mixture at the monitor (pC1/mi) 5.1.1.2 Liauld 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 (pC1/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 1 C., . 2.iSE-05 . T.4.E-05 2.5 -05 . i.22E-04

<uC1) .guC1) <uC1) (uC1) mi ml al ml B.5-3 8686R

~

ODCM Rev. 8 b

(5-3)

DF min 9 guci-ml) mi-pC) 2.15E-05 7.48E-05 2.56E-05

" + + . r 9E-06 2E-05 3E-05 guci-al) guci-ml) guCl-ml) ml-pC1 mi-pC1 ml-pCi DFmin " 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:

DF = .

m

, e (5-4)

M (gpm) 412,000 com 150 gpm

- 2750 V>

- 8.5-4 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, tne setpoint of the liquid radwaste discharge monitor is:

Rsetpoint " Il D *I in mi

( )( ) ($)

ml 2750

- 0.6 1.22E-04

()() (h)

= 2.87E-02 pC1/ml or pCl/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 Building Drains Licuid Effluent Monitor (RM-6521)

The Turbine Building drains liquid 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 8.5-5 l 8686R 00CH Rev.10

I l

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 j I

setpoints of RM-6521 are, calculated as follows:

High Trip Monitor (5-21)

Setpoint (pC1/ml) - f2 (DF') (1.0E-07 pC1/ml)

Circulatino water flow rate (opm) where: DF' -

Flow rate pass-monitor (gpm) 1.0E-07 pCi/mi - most restrictive HPC value for an unidentified mixture given in 10CFR20, Appendix B Note 3b.

l 1

f2 =I- (f1+f 3 + f 4); where the f values i 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).

Warning Alarm g High Trip (5-22)

Monitor Setpoint Monitor Setpoint) (0.25)

(pC1/ml) 5.1.3 Steam Generator Blowdown Llauid 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 monitor, when liquid is to be discharged from the site, will be determined 3 using the same approach as the Turbine Building drains liquid effluent monitor.

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 - -

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

5.1.4 PCCW Head Tank Rate-of-Change Alarm Setpoint A rate-of-change alarm on the liquid level'in the Primary Component 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 l the Service Water System from the PCCW System. For the rate-of-change alarm, a setpoint .is selected based on detection of an activity level equivalent to 10-0 pCi/mi in the discharge of the Service Water System. The activity in the PCCW is determined in accordance with the liquid sampling and analysis program described in Part A, Table A.3-1 of the ODCH and is used to determine the setpoint. -

The rate-of-change alarm setpoint is calculated from:

(5-23)

RC set - 1x10~0SWF PCC 1

(hrN ) = (m$

l ) (N) hr (*Cl) p where: -

RC - The setpoint for the PCCW head tank rate-of-change set alarm (in gallons per hour).

lx10-8 - The minimum detectable activity level in the Service l Water System due to a PCCW to SWS leak (pCi/ml).

SWF = Service Water System flow rate (in gallons per hour).

PCC - Primary Component Cooling Water measured (decay corrected) gross radioactivity level (pC1/ml).

As an example, assume a PCCW activity concentration of 1x10-5 pC1/mi . _

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 ODCM Rev.10

RCset . 1x10 .

1.0x100 gph (1/lx10-5 )

RCset - 1000 gph 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:

RCset = (5-24) 1 l

5.1.5 PCCW Radiation Monitor l 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.

l 1

The PCCW radiation monitor alarm is based on a trend of radiation l 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.

B.5-8 8686R OOCH 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-Ranoe 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 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 DFB c

mr 3 pCi/sec = (yrem-uCi-m ( pC1-vr l pC1-sec } 3 l mrem-m and:

R skin = 3,000 (5-6) !

pCl/sec = (*#'*) YI yr (m" rem'~-s e e )

where:

(

R tb = Response of the monitor at the limiting total body dose rate (pC1/sec) 500 3 mrem-uC1-m (1E+06) yr-pCl-sec (8.5E-07) 8686R B.5-9 ODCM Rev. 7

l 500 - Limiting total body dose rate (mrem /yr)

IE+06 Number of pC1 per pC1'(pC1/pC1) 8.5E [X/Q]Y, maximum off-site long-term average gamma atmospheric dispersion factor for primary vent stack releases (sec/m3 )

^

'0FB c

- Composite total body dose factor (mrem-m3 /pC1-yr) hg DFB g I

- (5-7) bt i

hj - The release rate of noble gas "1" in the mixture, for each noble gas identified in the off-gas (pC1/sec)

DFB, - Total body dose factor (see Table B.1-10) (mrem-m3 /pCI-yr)

R skin

- Response of the monitor at the limiting skin dose rate (pC1/sec) 3,000 - Limiting skin dose rate (mrem /yr) l DF' = Composite skin dose factor (mrem-sec/pCi-yr) hg 0Fj I

- (5-8) .

hg i l DF' I

- Combined skin dose factor (see Table B.1-10)

(mrem-sec/pCl-yr) l l

B.5-10 8686R OOCH Rev. 7 l

l

I l

l 5.2.1.2 Plant Vent Wide Range Gas Monitor Setpoint Example i

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 ):

hi DFj DFB, 3 g (Q) sec 4 mrem-m )

oCi-vr (mrem-sec) pCi-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 hj OF8 g 0FB c

(5-7)

Q1 i

hg0FBg - (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 (pC1-mrem-m / set-pCl-yr) hg - 1.03E+04 + 4.73E+02 + 2.57E+02 i

B.5-11 8686R ODCM Rev. 7 i

I

+ 1.20E+02 +-3.70E+02 + 1.97E+01

- 1.15E+04-pCi/sec 9.83E+01 0O c

" 1.15E+04 s 3

!' - 8.52E-03 (mrem-m /pCl-yr) ,

Rtb = 588 DFB (5-5)

- (588) (8.52E-03)

- 5.90E+04 pCi/sec and next; hi DFj I

DF' - ,

(5-8) l 91 1

i hg 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 (pCi-mrem-sec/sec-pCI-yr) 1.36E+02 DF.g 1.15E+04 l

- 1.18E-02 (arem-sec/pCl-yr)

Rskin " 3' # D ~0' B.5-12 8686R 00CM Rev. 7

- (3.000) (1.18E-02)

- 2.54E+05 pCl/sec The setpoint, Rsetpoint, is the lesser of Rtb and R skin. For the noble gas mixture in this example R 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 should be based on Xe-133.

i l

l I

l B.5-13 8686R ODCM Rev. 7

6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION HONITORS AND RADWASTE TREATMENT SYSTEMS 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 appropriste Gaseous Radwaste Treatment System.

For more detailed information concerning the above, refer to the Seabrook Station Final Safety Analysis Report, Sections 11.2 (Liquid Haste System), 11.3 (Gaseous Haste 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 'oy 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.

B.6-1 ODCM Rev. 4 8687R

l l

O O i 1

1 MAKEUP STORAGE UNIT TANK PAB 3 lf 3 3

_ l

~

a y-c e

so - -

e =-

O 'G g .. )

<-- >; =

_ l ruasm I4 **** stam I m

I "

suono

' SErd Ewon. [ym I

systra I ,c I

1 l"

'a l l g [ t e =

I ,

Iemeuurno i

=. O c ,,,; 3_ = l 1

i :

I !

I h '

GE > -

6- >

e __ _,_ -.

@.--==, u._

@ an= =, _,,, m @ .a

=~

- .= m ...,

.Castf. den.710N w.ff t .

G = == = @ . cs ..m. ,

FIGURE B.6-1 L' auld Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station l

B.6-2 .

ODCM Rev. 8 I 8687R l

nm .=

CONTAINMENT

'g," '

cuRiha Hocono MODE ONLY)

BUILDING VENTRATOR$

TUR8ht VACubM eUECh0 PUMP

7FAV EFFLUEW AEACTOR GE.6TDA VACUUM

' ~

b b SE TUme*E CONDENSER j

= cI --0 .

h]-

u u .

CONTAhMENT PURGE AIR I

] l sw j

SLOWOOWN FLASM TAhit ogg CASE 0VS WASTE PROCESSWO SYS11M [

E I " waste SUN,06MG 4,

' ~

OUARD AFTER CooLE4 ,,,, I I 1

oRVER CHARCOALBEDS '

d l CoM,RES$om l l

I PRIMARY m uARy "" l VENT ,

AUXLIARY ,,,

sTACx eUanma l

- @" l l I

f% -

~ _ - 3

. ~" l L"* susono -E.

%.)

AUXElARY gua.DMG VENT AR LIGENO H M PA PETER C 04ARCOAL FLTER

((

RM RADuTION MONf70R FIGURE B.6-2 l Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6-3 ODCM Rev. 8 8687R ,

A e

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 j 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 .l limit off-site total body dose from liquids (3.11.1.2 and 3.11.1.3) have been met for releases 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, Appendly I Subsection II A. The minimum dose values noted in Technical Specification 3.11.1.3 are " appropriate fractions," as j

- determined by the NRC, of the design objective to ensure that radwaste equipment is used as required to keep off-site doses ALARA.

6 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 j with identifiable exposure pathways, be taken into account for any given j 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 i 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 II evaluations. The base case, the.

method of reduction, and the assumptions and data used are presented below.

l The steps performed in the Method I derivation follow. First, the dose impact to the critical receptor (in the form of dose factors DFLith (mres/pC1)] for a unit activity release of each radioisotope in liquid I 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 3/sec was used with a mixing ratio of 0.10. The mnu B.7 1 ODCM Rev. 12 1

I J

l r, -

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

l l

mixing ratio of 0.10 corresponds to the minimum expected prompt dilution or near-field mixing zone created at the ocean surf ace 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 only 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 Ill.A.2 of Appendix ! 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 1.

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 floor. Water is discharged in a generally eastward direction away

~

from the shoreline through the multiport diffuser, beginning at a location over one mile due east of Hampton Harbor inlet. This arrangement effectively prevents the discharge plume (at least to the 1 Ngree 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 B.7-2 ODCM Rev. 12 unir

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.

The design of the multiport diffuser to achieve a 10 to 1 dilution in 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 tests (reference " Hydrothermal Studies of Bifurcated Diffuser Nozzles and Thermal Backwashing - Seabrook Station," Alden Research Laboratories.

July 1977).

During shutdown periods, when the plant only requires service water cooling flow, the high velocity jet mixing created by the normal circulating water flow at the diffuser nozzles is reduced. However, mixing within the discharge tunnel water volume is significantly increased (factor of about 5) 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 diameter tunnels to the diffuser nozzles. Additional mixing of the thermally 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.

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 1.109, defines the point of exposure to be the location that is

~

anticipated to be occupied during plant lifetime, or have potential land and water usage and food pathways as could actually exist during the 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 otur B.7-3 ODCM Rev. 12

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 j 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 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 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 f modeling. Not withstanding the above expected dilution credit afforded at the i 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 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 f surface canal-type discharge structure where little entrainment mixing in the I environment occurs, a dilution f actor of 1.0 is a reasonable assumption.

However, in keeping with the guidance provided in Appendix 1 to 10CFR50.

Seabrook has determine site-specific mixing ratics which factor in its plant design.

amo B.7 4 ODCM Rev. 12 i

I

l

'1 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 l use factors used in the analysis. The resulting, site-specific, total body l dose factors appear in Table B.1-11. Appendix A provides an example of the development of a Method I liquid dose conversion factor for site-specific conditions at Seabrook.

l 7.1.1 Dose to the Total Body I

For any liquid release, during any period, the increment in total body dose from radionuclide "1" is: i aDtb = k Oi DFLith "I'" !

(mrem) () ( Ci)

M (7-1) l l

where:

DFl itb - 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.

Oi - Total activity ( C1) released for radionuclide "i".

K - 91B/Fd (dimensionless): wheredF 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 l

Technical Specification limits because the dose factors DFLith used in Method ! 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.

7.1.2 Dose to the Critical Organ The methods to calculate maximum organ dose parallel to the total body

~

dose methods (see Section 7.1.1).

unsi B.7 5 ODCM Rev. 12

For each radionuclide, a dose factor (mrem /pCi) was determined for each )

of seven organs and four age groups. The largest of these was chosen to be the maximum organ dose factor (DFL ,,) for that radionuclide.

g DFL t . also ;

includes the external dose contribution to the critical organ.

For any liquid release, during any prriod, the increment in dose from radionuclide "i" to the maximum organ is:

AD,, - k O g DF Lt .,

e 3 (7-2)

(mrem) () (pC1) where:

DFLt , - Site-specific maximum organ dose factor (mrem / C1) for a liquid release. See Table B.1-11.

Og - Total activity (pC1) released for radionuclide "i".

K - 918/F4 (dimensionless): whered F is the average dilution flow of the Circulating Water System at the point of discharge from 3

the multiport diffuser (in ft /sec).

1 I

unar B.7-6 ODCM Rev. 12

. . - . _ . . _ ____ . ._. . . . _ _ . - g, .,

TABLE 8.7-1 Usaae Factors for Various Liould Pathways at Seabrook Station ,

(From Reference A. Table 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) (KG/YR) (KG/YR) (LITER /YR) (HR/YR) (HR/YR) (HR/YR) i 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 I Infant 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I i

1

Regulatory Guide 1.109.

l

- HERMES: "A Digital Computer Code for Estimating Regional Radiological Effects from Nuclear Power Industry." HEDL.

December 1971. Note, for Method II 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.

8.7-7 OOCH Rev. 12 mner s__ .-___ o___-._m_.___.._-__._t_ _ _ _ _ _ _ _ _ - . _ _ _ - _ _ _ - - _ ___e '

a m- _ _ _ _ _ ._+- ___w - --

_ - _ w +' -d-' t---+1# a+ -e'd J e__

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

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 informativ to Method I users, and (3) to 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 limits total body 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.

Method I was derived from general equation B-8 in Regulatory Guide 1.109 as follows:

i 1 0s - IE46 (X/0F og0FBq (7-3) i

/ h

' mrem',,'pCi' sec 'pC1 ' mrem-m 3 s

yr s km 3 (sec , ( pci-yr ,

I where:

[X/0F - Maximum off site receptor location long term average gamma atmo:pheric dispersion factor.

I dj - Release rate to the environment of noble gas "i" (pCi/sec).

- Gamma total body dose factor, mrem-m 3 . See Table B.1-10.

DFBi y pCi-yr ,

(Regulatory Guide 1.109. Table B 1).

. l Elevated and ground level gaseous effluent release points are addressed l separately through the use of specific (X/0]T. For an elevated gaseous l effluent release point and off-site receptor. Equation 7 3 takes the form; amar B.7 8 ODCM Rev. 14 1

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

l Ot sc,3 - (1E+06) * (8.5E-07)

E (Og

DF8g) 1 f %

< s

' mrem ' " 'pci '

sec pCi

mrem-m 3 yr s k m3 , (sec pCi-yr ,

which reduces to:

0 3,3 - 0.85 . E (0, . DFBg ) (3 3a) ,

t '

r 3 3

' mrem' , pCi sec 'pCi ' mrem-m 3 p ,

yr s pCi-m 3 , u sec, g pCi-yr ,

For a ground level gaseous effluent release point and off-site receptor.

Equation 7-3 takes the-form:

Otb(g) - (1E+06) * (3.4E-06) = E (0g

DFB,)

t which reduces to:

l Otb(g) = 3.4

E (0,

DFB,)

i r * ' '

(3-3b)

' mrem' , pCi sec g 'pci ' , mrem-m 3 yr s pCi-m 3 ,

(sec, pCi-yr ,

ihe 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. All 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, unsi B.7-9 ODCM Rev. 14

1 l

-l 7.2.2 Skin Oose 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 release rate reading remains constant over the entire year.

Method I was derived from the general equation B-9 in Regulatory Guide 1.109 as follows: P D S - 1.11 D},,. + 3.17E44 0, [X/0TDFS, (7-4)

I i f 3

'pCi-yr ' mrem-m 3

' mrem ',, ' mrem ' ' mrad ' { sec yr , mrad, yr , C1-sec , yr m3 ,

g pC1-yr ,

where:

1.11 - Average ratio of tissue to air absorption coefficients (will convert mrad in air to mrem in tissue).

OFS, - Beta skin dose factor for a semi infinite cloud of radionuclide "1" which includes the attenuation by the outer

" dead

layer of the skin. .

ams: B.7 10 00CM Rev. 14

~

DJg, - 3.17E+04 E Og [X/03 DF i? (7-5) t f i

' mrad ' 'pci-yr ' Cl mrad-m 3

, yr ,

,Ci-sec , (F)g sec) m 3 ( pCi -y r ,

DF[

= Gamma air dose factor for a uniform semi-infinite cloud of radionuclide *1*.

Now it is assumed for the definition of (X/07) from Reference 8 that: l DJg,gg, - Dlg, [X/0]T/[X/0] (7-6) r 3 r

P ara d ' ,,

'mra d ' see m3 g yr , t yr , m3 , u sec, and Og - 31.54 Og (7-7)

'Ci ' , 'Ci-sec ' 'pci '

K, pC1 -yr , ,sec ,

so: 'l 7

(7-8) l

. 0,g'gn - 1.11 1E+06 [X/0]Y E 04

DF i i e , 1

' mrem ', ' mrem ' 'pC1 ' sec 'pCi ' mrad 3 3 t

yr , , mrad sEm 3

,sec , ( pci-yr ,

+1E+06 X/0 E 0 DFSg 4 i

r '

3

'pci ' sec 'pCi ' mrem-m 3 ,

k m 3 (sec , , pCi-yr ,

uns7 B.7-11 ODCM Rev. 14

l. Substituting atmospheric dispersion factors for an elevated gaseous l effluent release point. Equation 7 8 takes the following form:

l l 0,g,,c.3 = [1.11 1E+06 8.5E-07 . E (0i

DF[)] + [1E+06

8.2E 07 . E (Og . OFS,))

t t l

l which yields:

l I708}

! 0.ging,3 = [0.94 E (Og

DFJ)] + [0.82 (0,

DFSi )]

3 3

' mrem ' , pCi-sec-mrem p pC1 , mrem m . pCi-sec p pCi , mrem m g

yr s

3 pCi-m mrad , (sec pCi-yr , pC1-m 3 (sec pCi-yr ,

I l defining: ,

I l DFi 'g,3 = 0.94 DFl + 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)

Oskin(,) = E Og

DFig,3 1

' mrem' , ' Ci , mrem sec' g yr ,

, (sec Ci-yr ,

l For an off-site receptor and a ground level gaseous effluent release l point, Equation 7 8 becomes:

I l Osting,3 = [1.11*1E+06*3.4E-06eE (0,*DFJ)] + [1E+06+1.0E-05 E (0$*0FS$ )]

l which yields:

I I

(7 b)

Oskin(s) = [3.8 E (Og

OFJ)] + [10 E (Oi + DFSg))

i 1

=EOt [3.8 0F[ + 10 DFS,3 a m as B.7-12 ODCM Rev. 14

l defining:

l l OFi 'g,3 = 3.8 0F[ + 10 0FS i (7-10b) l l Then the off-site skin dose rate equation for ground level gaseous l effluent release points is:

l l Os unto) = E 0, e DF '<,3 i (3-4b) i 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 Oroan Dose Rate From Iodines Tritium and Particulates With Half-lives Greater Than Eicht Days l 1

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 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 lives 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 0, pages 5 and 6). It is evaluated by looking at the critical organ dose commitment to the most limiting off-site receptor assuming long-term site average meteorology.

l The equation for be , 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 Ci/sec:

amar B.7-13 ODCM Rev. 14 i

I Oc , = 3.15E+07

E (Os

DFG ico) (7 12)

' mrem' ,'sec' g 'pC1' ,' mrem'

( yr , ( yr , ,sec, Ci ,

l Equation 7-12 is rewritten in the form:

(7-12a)

Oc , = E (0,

OFG,),)

t

'pci ' , ' mrem-sec '

' mrem '

,p yr , sec, Ci-y r ,

where:

(7-13)

OFGi 'e, = 3.154E+07

DFG,c,

' mrem-sec ' , 'sec ' , ' mrem '

pCi -y r , yr , Ci ,

l The dose conversion factor. DFG ie ,. has been developed for both elevated l gaseous effluent release points and ground level gaseous effluent release l points (DFG,,,g,3 and DFGico(s)). 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 f actors (DF.G', cog,3 and DFG',,,c,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:

be,(e) = E (Og

OFG'gcog,3)

(3 Sa) 1

' mrem' , 'nci , mrem-sec '

yr sec Ci-y r

( , ,

For an off-site receptor and ground level effluent release point, the critical organ dose rate equation is:

uns' B.7-14 00CM Rev.14

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

l M

Oc <,3 - E - ( 0,

DFG'ge,<,3 )

~MM l

1 P

mrem '

, )g 'gCi , mrem-sec '

, t yr j sec pCi -y r ,

The selection of critical receptor, outlined in.Section 7.3 is inherent 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 base's section for the organ dose rate limit given for Technical Specification 3.11.2.1, a Method II dose rate calculation, for compliance purposes, can be based on restricting the inhalation pathway-to a child's thyroid to less than or equal to 1,500 mrem /yr. Concurrent meteorology with time of release may also be used to assess compliance for a Method II calculation.

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 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 which limits off-site gamma air dose from gaseous effluents has been met for releases over appropriate periods. This Technical Specification is based on the objecti,ye in 10CFR50. Appendix I, Subsection 8.1, which limits the estimated gamma air dose in off-site unrestricted areas.

NUREG/CR-2919 presents a methodology for determining atmospheric dispersion factors (CHI /O values) for intermittent releases at user. specified receptor locations (intermittent releases being defined as releases with 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 releases are determined by linearly interpolating (on a log log basis) between an hourly 15-percentile CHI /O value and an annual average CHI /O value as a function of release duration. This methodology has been adopted to produce a set of time dependent atmospheric dispersion factors for Method I calculations.

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 that D}inite - DY [X/0]Y/[X/0):

unsi B.7-15 ODCM Rev.14

ADjgr = 3.17E4 [X/0]T E Og DFJ 1

y , e 3 (7-14)

'pCi-y r ' sec mrad-m 3 (mrad) - (C1)

,C1-sec j m 3 y pCi-yr , ,

where:

3.17E+04 - Number of pCi per Ci divided by the number of seconds per year.

[X/0]Y - Annual average gamma atmospheric dispersion factor for the receptor location of interest.

Og - Number of curies of noble gas "1" released.

DF}

- Gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i".

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 pCi (to accommodate the use of a release rate 0 in pC1), and substituting the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months gamma atmospheric dispersion f actor in place of the annual average gamma atmospheric dispersion factor in Equation 7-14 leads to:

d D}g, - 3.17E-02 [X/0]}hr

t . Ei Og

DFJ (3-6) e f 5 3

' pCi -y r ' sec 3 (mrad) = ,

E pCi e mead-m y

pCi-sec j m3 ( pC1-yr ,

For an elevated release, the equation used for an off-site receptor is:

e ,

T l 0,g r(e) - 3.17E-02 * [1.0E-05]

t 4.275

E Og

DFf 1 ( s unw B.7-16 ODCM Rev.14 l

1

i 1

l which leads to:

l (3-6a)

Djg,g,3 - 3.2E-07

t-o.275

E Q

DF[

t 1

< 3 1

, 3 3

pCi-yr (mrad) - *E nCi

mrad-m pC1-yr ,

pCi-m3 , s For a ground-level release, the equation used for an off-site receptor is:

7 Og

DF l D,g r(g) - 3.17E-02 * [4.9E-05]

t-8 #'3

E which leads to:

l (3-6b)

D[geg,3 - 1.6E-06

t-o.293

E Q

DFJ I 1

f i 3

pCi-y r gCi e mrad-m (mrad) - =

,pci-m ,

2

, 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/0]T 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 i users, and (2) to identify the general equations, parameters and approaches to i Method Il 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 j the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated beta air dose in off-site unrestricted area locations. l l

For any noble gas release, in any period, the increment in dose is taken ,

I from Equations B 4 and B-5 of Regulat'ory Guide 1.109:

mm B.7-17 ODCM Rev. 14 I

1 ADfir - 3.17E-02 X/0 E Og DFf 1

< 3 (7-15)

(mrad) -

pCi-yr ' ,sec (pCi) mrad-m3 3 , p C 1 -y r ,

pC1 -sec , m ,

. where:

DF{ - Beta air dose factors for a uniform semi-infinite cloud of radionuclide "i*.

Incorporating the term t** into Equation 7-15 leads to:

Df,, - 3.17E-02

X/0

t-*

E 0

DFf (3-7) i r 3 i

(mrad) . ' pCi-yr ' sec mrad-m3

()*E Ci e

,pci-sec s m3 ,

, pC1 -yr ,

Where X/0 - average 1-hour undepleted atmospheric dispersion factor.

For an elevated release, the equation used for an off site receptor is:

Oftr(e) - 3.17E-02 e 1.3E-05

t-0 3

E,0,

DFf f 3 r 3 pCi-yr ' sec pCi e mrad-a 3

(mrad) - ,

()*E y

pCi-s ec s m3 ( pCi-yr ,

which leads to: ,

Dfirg,3 - 4.1E-07

td'3

E 0,

DFf (3-7a) ~I t

f i 3

pCl-yr (mrad) - *()*E Ci

mrad-m pCi-m3 , ( pCi-yr , '

For a ground level release, the equation used for an off site receptor is:

uns: B.7-18 ODCM Rev. 14 m _ -

3 y - _ ,

l Dfirgg3 - 3.17E-02 = 1.9E-04 . t-0 318

E [0g . DFh

(

(mrad) = p i-yr 1, '

,pci -s ec j [sec*()*[

, gCi e mrad-m3 pC 1 -yr j

=

which leads to:

l 0[i,g,3 - 6.0E-06 e t -0 318

Qg

OFh (3-7b)

, , e ,

(mrad) = p i-yr Cl-m3 j *()*E nCi e mead-m3 pC1-yr j

(

7.2.6 Dose to Half-lives Critical Greater Oroan Then Efoht Days _

From iodines. Tritium es With and Particulat This section serves: (1) nature of Method I equations to provide background information tt Method II-type dose assessments. users, andoapproaches Method I (2) to identify to the gener limit off-site organ dose from gasesa ons releases over the appropriate periods. .

(3.11.2.3 which and 3 11 ave been met for based on the ALARA objectives in 10CFR50. Appendix ITechnical Specification 3 Technical specification 3.11.4 is based on Environmental St. Subsection II C.

Fuel Cycleeffluents.

and gaseous in 40CFR190, which applies to direct radiatio andards for Uranium particulates in gaseous effluent contribution.These , and methods apply o individual ... is unlikely to be substantiallyMethod I was deve Appendix I).

underestimated" (10CFR50 the conservative margin to the calculationpart ofofcritical oThe us i Method II allows that actual individuals, associated with irgan dose in Method I.

dentifiable Method I was based on a Method II analysis of a criticale pathways present.

In fact.

I reduced to form Method I.That analysis was called the " base case"; it was thenrecepto assumptions and data used are presented below.The base case. the method j um B.7-19 ODCM Rev. 14

L l First, the dose 1 The steps performed in the Method I derivation fol ow.

f impact to the critical receptor [in the form h iodine, tritium,of and dose f actors DFGge, (mrem /pCi)] for a unit activity release of eac h eight days to gaseous particulate radionuclide with half lives greater t anSix exposure pathw effluents was derived.

stored vegetables, leafy vegetables, milk, and meat ingess) which exhibited the exist at the site boundary (not over water or marsh areaDoses we highest long term X/0.

kidney, lung, GI-LLI, and thyroid), as well as forthe the seven w ocombined four age groups (adult, teenager,aschild, then selected to and inf ant) due toFor ea exposure pathways.

release for any organ (or whole body) and age group wThe base case, or Method I become the Method I site specific dose factors. ptions in analysis, uses the general equations methods, li from direct data,exposure and assum Regulatory Guide 1.109 (Equation C 2 for doses resu t ngEquation C-4

'to contaminated ground plane: f individuals of inhalation of all radionuclides to different lidesorgans in produce,oand Equation C-13 different age groups:

different age groups resulting from ingestion of radionucTables B.7-2 and 8.7-3 m'?k, meat, and leafy vegetables in Reference A).d in the analysis.

outline human consumption and environmental parameters uselives at the " maxi It is conservatively assumed that the critical receptor d in Section 7.3.

off site atmospheric dispersion f actor location" as define organ which i

The resulting site-specific dose factors are for the max mumfor any organ w in combine the limiting age group with the highest thod I dose f actor each nuclide. Appendix A provides an example of the development of Meditions Table B.1 12.

gaseous dose conversion factor for site-specific con period, For any iodine, tritium, and particulate gas release, during any "1" is:

the increment in dose from radionuclide (7-16)

AD,c, - 0,0FG,c, "i" and 0, is the where DFG,c, is the critical dose factor for radionuclide released in microcuries.

activity of radionuclide "1" l form for the Applying this information, it fol')ws that the genera critical organ dose equation is:

14 ODCM Rev.

B.7-20 am:1

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

! Dfi,g,3 - 3.17E-02 e 1.9E-04

t-0 31'

E 0,

DFf (arad) =

' pci-yr ' , ~sec *()e C1 e mrad-m 3

,pci-sec , T m g pC1-yr ,

which leads to:

l Dfi,c,3 - 6.0E-06

t-8 31'

QeDFf i

(3-7b)-

pCi-yr mead-m 3 (mrad) - *()*E Ci e 3

(pCi-m , , pC1-yr , .

7.2.6 Dose to Critical Oroan From lodines, Tritium and Particulates With Half-Lives Greater Than Eicht 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 Il-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 1. Subsection'II C.

Technical Specification 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 actbst exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50.

Appendix I). The use below of a single " critical receptor" provides part of the conservative margin to the calculation of critical organ 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 of a critical receptor assuming all )

pathways present. That analysis was called the " base case"; it was then I reduced to form Method I. The base case, the method of reduction, and the assumptions and data used are presented below.

unw B.7-19 ODCM Rev. 14

The steps performed in the Method I derivation follow. First, the dose ,

impact to the critical receptor [in the form of dose factors DFG je, (mres/ Cl)] 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, 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 f highest long-term X/0. Doses were then calculated to six organs (bone, liver, f kidney, lung, GI-LLI, and thyroid), as well as for the whole body and skin for {

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 sita-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 l'

inhalation of all radionuclides to different organs of individuals of I

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 "Itaximum off site atmospheric dispersion f actor 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 f actors are given in Table B.1-12. Appendix A provides an example of the development of Method I gaseous dose conversion f actor for site specific conditions at Seabrook.

For any iodine, tritium, and particulate gas release, during any period, the increment in dose from radionuclide "i' is:

ADie, - 0,0FGico (7-16) 1 where DFG,,, is the critical dose factor for radionuclide "i" and 0, is the

, activity of radionuclide "1" released in microcuries.

1 Applying this information, it follows that the general form for the

, critical organ dose equation is:

4 amor B.7 20, ODCH Rev. 14

De , - ( X/0)fl) /( X/0)[ . t -* * (0,.DFGico) (3-8) r % < '

seC seC mrem = g

,() , { 'pgg , mrem'

,m 3

m3 s pC) ,

Substituting specific values associated with the maximum off-site receptor location and elevated release condition yields:

Deog,3 - (1.12E-05)/(7.55E-07)

t 4 .297 (gt ,gpgieo( ))

which reduces to:

Dec.,33 = 14.8

t -o.297 * (Og

DFGicog,3) (3-8a)

For the maximum off-site receptor location and ground-level release conditions, the equation is:

Deo(s) - (1.71E-04)/(9.64E-06)

t-0 318 (0, *DFG%)

which reduces to:

Deo(s) - 17.7

t -0 318 * (Oi DFG ie g,3) (3 8b) 7.2.7 Special ReceDtor Gaseous Release Dose 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 Radioactive Effluent Release Report. l-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 X0s 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:

B.7 21 ODCM Rev. 15 l

(7-3)

Otb - 1E+06 [X/0]Y t}[ 0 $DFB i 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 l Hampton Harbor. The Seabrook Station UFSAR, 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 def ault vclue 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 ftctor of all four age groups listed in Regulatory Guide 1.109, and has been used in the 00CM to reflect the Caximum usagt level irrespective of age.

Regulatory Guide 1.109 does no?. provide a maximum individual usage factor for activities similar to thoae which would be associated with the l Seabrook Station Science & Nature Ct.nter. Therefore, the usage factor used in j the DDCM for the Science & Nature 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 approxinutely 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 tines 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 ODCM for public activities associated l with the Science & Nature Center.

For the Scicnce & Nature Center, and the " Rocks", the occupancy factors l

(Ofs) are:

l 12.5 hrs /yr 3 .0014 0

Science & Nature Center - 8760 hrslyr 67 hrs /yr il)

- 0.0076 The " Rocks" - 8760 hrs /yr

0) Taken from Seabrook Station Technical Specifications (Figure 5.1-1).

B.7-22 ODCM Rev. 15 l

a substituting in the annual average gamma X/Os:

(X/0F - 1.1E-06 sec/m3 (Science & Nature Center) for primary vent stack l' I releases.

- 5.3E-06 seem3 (Science & Nature Center) for ground level l f releases. .

- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases. .

- 2.6E-05 sec/m3 (The " Rocks") for ground level releases, and multiplying by:

OF = 0.0014 (Science & Nature Center) l

- 0.0076 (The " Rocks") !

i gives:

dtbE(e) = 0.0015

E (0,

DFBj) (mrem /yr) (3-3c) 1 OtbE(g) = 0.0074 E (0g DFBj) (mrem /yr) (3-3d) t Desace> = 0.038 e E (0, . orb,) (mrem /yr) (3-3e) i OtbR(g) = 0.2 E (0g

DFB$ ) (mrem /yr) (3-3f) i where: ,

b tbE(e)* b tbE(g)* b tbR(e). 8Dd b tbR(g) = total body dose rates to an individual at the Science & Nature l Center and the " Rocks" (recreational site), respectively, due to noble gases in an elevated (e) and ground level (g) release.

6, and DFB, are as defined previously.

7.2.7.2 Skin Dose Rate From Noble Gases Method I was derived from Equation (7-8):

Dag, = 1.111E+06 [X/0F E O iDFJ + (7 8) i 1E+06 X/0 E Qg 0FSg B.7-23 ODCM Rev. 15 l

i substituting in the annual average gamma X/Os: -

lL

[X/037 - 1.1E-06 sec/m3 (Science & Nature Center) for primary vent stack releases.

l

- 5.3E-06 sec/m3 (Science & Nature Center) for ground level I release points.

4

- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases.

- 2.6E-05 sec/m3 (The " Rocks") for ground level release points.

and the annual average undeoleted X/Os:

l. X/0 - 1.6E-06 sec/m3 (Science & Nature Center) for primary vent stack releases.

l

- 2.3E-05 sec/m3 (Science & Nature Center) for ground level release points.

- 1.7E-05 sec/m3 (The " Rocks") for primary vent stack releases.

- 1.6E-04 sec/m3 (The " Rocks") for ground level release points.

and multiplying by:

l OF - 0.0014 (Science & Nature Center)

- 0.0076 (The " Rocks")

gives:

i 0 guigg,3 = 0.0014 ][ Os [1.22 0FJ + 1.60 0FS i ) for an elevated release point.

1 OskuiE(g) = 0.0014 }[ 0, [5.88 DF[ + 23 DFS ) for a ground level release point.

1 1

0,ginnt.) = 0.0076 ][ Oi [5.55 DFJ + 17.0 0FS i ] for an elevated release point.

1 Oskinntg> = 0.0076 0, [28.9 DFJ + 160 DFS,) for a ground level release point. 1 and the equations can be written: DskinE(e) = 0.0014 . E (0, . DF 'Ete)) i (3-4c) 1 l B.7-24 ODCM Rev. 15 ; l l

6,ginggg) = 0.0014 . E (Os . DF 'E(g)) t (3-4d) i 6,ginng,3 = 0.0076

E (Os . DF,'ag,3) (2-4e) 1

                                            ~
     ' 6skinR(g) = 0.0076 . E (Oi . DF $ng,3)                                              (3-4f) i where:                                                                                                     3 b skinE(e)* b skinE(g)' b skinR(e), and 6skinR(g) - the skin dose rate (mrem /yr) to an individual at the                        ,

Science & Nature Center and l the " Rocks", respectively, due to noble gases in an elevated (e) and ground level (g) release, 6 - defined previously, and 4

                                                 -  the combined skin dose' factors for                   I DF'Ete),

1 DF'E(g), 1 DF'ag,3and i DF{ng,3 radionuclide "i" for the Science & -l Nature Center and the " Rocks", l ,

                                               ,     respectively, for elevated (e) and ground level (g) release points                      ,

(see Table B.1-13). 7.2.7.3 Critical Orcan Dose Rate From lodines. Tritium and Particulates With Half-lives Great 6r Than Eicht Days The equations for 6,c are derived in the same manner as in Section 7.2.2, except that the occupancy factors are also included. Therefore: DcoEte) = 0.0014

E (og (3-Sc)

DFGicoE(e)) for an elevated release. i OcoE(g) = 0.0014

E (0, . DFG coE(g)) for a ground level release. (3-5d) 1 DeoR(e) = 0.0076 . E (0, . DFG,'cong,3) for an elevated release. (3-Se) i l B.7-25 ODCM Rev. 15 l

Deonto) = 0.0076 . E (0, . DFG coR(9)) for a ground level release. (3-5f) I 1 where: 6 coE(e)- b eoE(g)* eor b (e), and'6coR(g) - the critical organ dose rates i (mrem /yr) to an individual at the l Science & Nature Center and the {

                                                             " Rocks", respectively, due to                           !

iodine, tritium, and particulates in elevated (e) and ground level (g) releases, 6, - as defined previously, and DFG coEte), DFG'coE(g). i DFG e ag,3, and DFG,'cong,3 - the critical organ dose rate factors for radionuclide "1" l for the Science & Nature Center and the " Rocks", respectively, for elevated (e) and ground level (g) release points (see Tables B.1-14 and B.1-15). 7.2.7.4 Gamma Dose to Air From Noble Gases Method I was derived from Equation (3-6): Dji,. - 3.17E-02 * [X/0]}hr

t **
E (Qi
DF[) (3-6) 1 where all terms of the equation are as defined previously.

Incorporating the specific 0F and the atmospheric dispersion factor, the gamma l air dose equation for the Science & Nature Center for elevated releases: 0 trE(e) - 3.17E-02 e 1.1E-05 t -0.2s2

0.0014 * (0,eDF[)

which reduces to: B.7-26 ODCM Rev. 15 l

9 i

l (3-6c) D trE(e) = 4.9E-10

t o.252 . tE (Os
DFJ) f 7 pCi-yr mrad-m 3 (mrad) - * ( )*I Ci e 3

pCi -m , s PCi"1' s For ground-level releases. the gamma air dose equation for the Science & l . f Nature Center becomes: l D f r(E(g) - 3.17E-02

1.0E-04 t 0.321
0.0014 . E (0,
DFJ) which reduces to:

D ire (g) = 4.4E-09 t 0.321

E (Os
DFI) (3-6d) 1 f 3 r 3 pCi-yr * ( )*I mrad-m 3 (mrad) - Ci e 3

pCi-m , ( pCi-yr , Incorporating the specific 0F and atmospheric dispersion factors for the

 " Rocks" yields the gamma air dose equation for elevated releases:

D irpie) - 3.17E-02

2.1E-05
t 0.155
0.0076
E (Oi
DFJ) which reduces to: ,

(3-6e) D irR(e) = 5.1E-09

t -o.155 * (0,
DFJ)

                                              #                  h f         %

pCi-yr * ( )*I mead-m 3 (mrad) - Ci e pCi-m3 , t pCi-yr , j For ground-level releases. the gamma air dose equation fcr the " Rocks" becomes:

        . DJf ra(g) - 3.17E-02 e 1.7E-04 t 0.204

0.0076 . E (0,
DFJ) 1 which reduces to:

B.7-27 ODCM Rev. 15 l l 1

l DItrR(g) = 4.1E-08 t.o.204 E (0, .0F[) (3-6f) 1

                                                 ~#                 4                                     i r          3 3

pCi-y r pCi + mrad-e (mrad) - . ( )I

                        ,pci-m ,3 s

pCi-yr , 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: , Dfic = 3.17E-02 e X/0 3 "jr*No t **

E (0,
DFf) (3-7) 1 where all terms in the equation are as defined in Section 7.2.5. -

Incorporating the specific 0F and atmospheric dispersion factor for elevated releases into Equation 3-7 yields the following beta dose equation [ for the Science & Nature Center: Ofirgc 3 - 3.17E-02 e 4.0E-05 e t ~0 35 0.0014

E (0,
DFf) which reduces to:

0,fgrgc.) = 1.8E-09 . t 0.35

E (0,
DFf) (3-7c) 1 pCi-yr * ( ).I pCi
mrad M (mrad) =

pCi-m , 3 g pCi-yr , l For ground-level releases, the beta air dose equation for the Science & Nature Center becomes: Dff rE(g) - 3.17E-02

5.5E-04 t "0 347 0.0014
E (0,
DFf) which reduces to:

B.7-28 ODCM Rev. 15 l

[ D[1rt(g) - 2.4E-08

t *0 347 * (0,*DFf) (3-7d) e s 3

(mrad) = p i-y r

                                                                          * ( )*I    Ci , mead-m
                                       ,pCi-m 3
                                                                       ,          5 pci-yr ,

Incorporating the specific 0F and atmospheric dispersion factors for the

   " Rocks" yields the beta air dose equation for elevated releases:

DftrR(e) - 3.17E-02

1.6E-04
t-o.249
0.0076 E (Og
DFf) 1 which reduces to:

Off rR(e) - 3.9E-08

t o.249 E (0g
DFf) (3-7e) 1 f i r 3 pCi-yr mead-m 3 (mrad) = * ( )*I pCi e pCi-m ,

3 t pCi-yr , For ground-level releases, the beta air dose equation for the " Rocks" becomes: DfirR(g) = 3.17E-02 * .1.9E-03

t 0.267
0.0076
E (Oi*DFf) 1 which reduces to:

DfirR(g) - 4.6E-07

t o.267 E (Os
DFf) (3-7f) 1.

                                           ,                            3 r                 3 3

pCi-yr * ( )*I pCi e mead-m (mrad)=

                                          , C i -m ,

3 y pC1-yr , 7.2.7.6 Critical Oroan Oose From lodines. Tritium and Particulates With Half-Lives Greater Than Eicht Days Method I was derived as described in Section 7.2.3. The Critical Organ Dose equations for receptors at the Science & Nature Center and the " Rocks" l were derived from Equation 3-8. The following general equation incorporates (i) a B.7-29 ODCM Rev. 15 l

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

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

l

                                                                                                                     .1
                                                                                                                       )
        . ratio of the average 1-hour depleted atmospheric dispersion f actor to the aven ge. annual depleted atmospheric dispersion factor (ii) the unitiess t**

term, and (iii) the OF: ) [ De , - (X/0)f*[/(X/0)j'/'

t **
OF e E (0,
DFGico) f if i sec /

(mrem) - ,

                                             .()*( )*I pCi

l u s s s

    - l Applying the Science & Nature Center-specific factors for elevated release conditions produces the equation:

I ~ De .gg,3 - (3.72E-05)/(1.56E-06) e t *0 M8

0.0014 . E (0,
DFGje.g.))

t . which reduces to: 1 De .gg 3 - 3.3E-02

t *0 M'
E (0,
DFG ie g 3) (3-8c) i (mrem) = ( )*( )*I pCi
Y r s l For a ground-level release, the equation for a receptor at the Science &

l Nature Center is-De gc,3 - (5.21E-04)/(2.23E-05) e t"0 M7

0.0014 E (0,
DFGge (,3) ,

t which reduces to: , T D cot (s) - 3.3E-02 o' t ~0 M7

E (Os
DFGje,cg3) (3-8d) 1 l

arem' (mrem) - ( )*( )*I pCi e pC1 The specific Critical Organ Dose equation for a receptor at the " Rocks" under elevated release conditions is:

B.7-30 ODCM Rev. 15 l

 --       -                                                                                                            \

l- Deong.3 = (1.54E-04)/(1.61E-05) e' t o.24s e 0.0076 . E (0, = DFG,,,c.3) 1 , 1 which reduces to: Dconce) = 7.3E-02

t 0.244 . E (0,
DFG,coc.3) (3-8e) l

  -l                                         1 (mrem) = (    )*( )*I pCi e i

For a ground-level release, the equation for a receptor at the " Rocks" is: l D con (s) = (1.80E-03)/(1.59E-04)

t o.267
0.0076. (Oi* e DFGi e c,3) which reduces to:

l De ong,3 - 8.6E-02

t o.267 * (0,*DFG%) (3 8f)

(mrem) = ( )*( )*I Ci e u s The special receptor equations can be applied under the following conditions l1otherwise, 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. , ODCM Rev. 14 i anur B.7 31 i e

TABLE B.7-2 Environmental Parameters for Gaseous Effluents at Seabrook Station (Derived from Reference A)" Vegetables Cow Milk Goat Milk Meat-Stored Leafy Pasture Stored Pasture Stored Pasture Stored Variable (Kg/M2 ) 2. 2. 0.70 2. 0.70 2. 0.70 2. YV Agricultural Productivity 240. 240. 240.- 240. 240. P Soll Surface Density (KG/M2 ) 240. 240. 240.

48. 48. 48. 48. 480. 480.

T Transport Time to User (HRS) 131400. 131400. 131400. 131400. 131400. 131400 TB Soil Exposure Time UI (HRS) 131400. 131400. 1440. 1440. 720. 1.440. 720. 1.440. 720. l.440. TF Crop Exposure Time to Plume (HRS) 1440. 24. O. 2160. O. 2160. O. 2160. TH Holdup After Harvest (HRS)

50. 50. 6. 6. 50. 50.

OF Animals Daily Feed (KG/ DAY) 0.50 0.50 0.50 FP Fraction of Year on Pasture (2)

1. 1. 1.

FS Fraction Pasture when on Pasture U3 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 HI (ge/m3 )

Regulatory Guide 1.109, Rev. I 8.7-32 00CM Rev. 14 -

airui

TABLE 8.7-2 (Continued) NJtes: (1) For Method 11 dose / dose rate analys'er. of identified radioactivity releases of less than one year, the soll exposure time for that release may be set at 8760 hours (1 year) for all pathways. (2) For Method 11 dose / dose rate analyses performed for releases 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 pssture feed while on pasture may be set to less than 1.0 for specific farm locations if this information is so identified and seported as part of the land use census. 3 (4) For all Method 11 analyses, an absolute humidity value equal to 5.6 (ge/m ) shall be used to reflect conditions in the Northeast (

Reference:

Health Physics Journal, Vol. 39 (August), 1980: Page 318-320 Pergammon Press). B.7-33 ODCH Rev. 14 einn

l l TABLE B.7-3 Usaae Factors for Various Gaseous Pathways at Seabrook Station (f rom Reference A. Table E-5)" Maximum Receptor:

     -Age                       Leafy Vegetables    Vecetables         Milk            M        Inhalation piqup, (kg/yr)        (1/yr)         (kg/yr)       (m 3 /yr)

(kg/yr) 520.00 64.00 310.00 110.00 8000.00 Adult 630.00 42.00 400.00 65.00 8000.00 Teen 520.00 26.00 330.00 41.00 3700.00 Child 0.00 0.00 330.00 0.00 1400.00 Infant l The " Rocks" and Science & Nature Center: Age Leafy gegyp, Veaetables Vecetables Milk Meat inhalation (kg/yr) (1/yr) (kg/yr) (m3 /yr) (kg/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 l l l i

Regulatory Guide 1.109 B.7-34 ODCM Rev. 15 l

4 J b. A 1 + +- JcS,.a a w - * .a e 7.3 Receptor Points and Averace Atmosoheric Discersion Factors for Imoortant Exoosure Pathways The gaseous effluent dose equations (Method I) have been simplified by assuming an individual whose behavior and living habits inevitably lead to a l higher dose than anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered: I

1. Direct exposure to contaminated air:

i

2. Direct exposure to contaminated ground; '

i

3. Inhalation of air: I i

4. Ingestion of vegetables:

5. Ingestion of goat's afik: and

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 section, 914 meters for calculations with D/0 the dispersion parameter. The site boundary in the NME through SE sectors is located over tidal ) marsh (e.g.. over water), and consequently are not used as locations for I determining maximum off-site receptors (Reference NUREG 0133). amar B.7-35 ODCM Rev. 14 l 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 DisDersion Model The time average atmospheric dispersion factors for use in both Method I and Method 11 are computed for routine releases using the AE0LUS-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 gamma dose rates from a sector averaged finite noble Jas cloud (multiple energy undepleted source); and

4. D/0 deposition factors for evaluating dry deposition of elemental I

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. I Section 7-5.2.5. That model is implemented through the definition of an l effective gamma atmospheric dispersion factor [X/07) (Reference B. l Section 6), and the replacement of X/0 in infinite cloud dose equations by the l [X/07). 7.3.3 Average 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 XOOD00 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 amar B.7-36 ODCM Rev.14

l level /part-time elevated releases depending on the ratio of the primary vent i 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 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 X00D00 computer code, t The relative deposition rates. D/0 values, were derived using the relative deposition rate curves presented in Regulatory Guide 1.111 (Revision 1). These curves provide estimates of deposition rates as a function of plume height, stability class, and plume travel distance. , i ReceDtor locations For ground-level releases, the downwind location of "The Rocks" (244m NE/ENE) and the Science & Nature Center (406m SW) were taken as the j distance from the nearest point on the Unit 1 Administrative Building / Turbine l I 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 UFSAR Figure 2.1-4A were used (with the exception l ) that the NNE-NE-ENE E-ESE-SE site boundary sectors were not evaluated because of their over-water locations). f For primary vent stack releases, the distances from the Unit 1 primary vent stack to "The Rocks" (244m NE) and the Science & Nature Center (488m SW) l as measured from a recent site aerial photograph were used. For the site l boundary, the minimum distances from the Unit 1 primary vent stack to the site ) ( boandary within a 45-degree sector centered on the compass direction of interest as measured from UFSAR Figure 2.1-4A were used (with the exception l l that the B.7 37 ODCM Rev. 15 l

I l l I NNE NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their j over water locations). Meteorolooical Data Bases l For "The Rocks" and Science & Nature Center receptors, the diffusion factors represent 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 season (April through September) and year-round (January through December) diffusion factors were generated, with the higher of the two chosen to represent the site boundary. The meteorological diffusion factor used in the development of the ODCM Method I dose models are summarized on Tables B.7-4 through B.7-6. l l I B.7-38 ODCH Rev. 15 l

I I TABLE B.7-4

j. Seabrook Station Lono Term Average Discersion Factors Primary Vent Stack Dose Rate to Individual Dose to Air Dose to I Critical f Organ l Total Body Skin Critical Organ Gamma Beta Thyroid l 7.5E-07 - -

7.5 07 sec X/0 depleted

                       <*      s                                                                                          l r      *        -

8.2E-07 - - 8.2E 07 - X/0 undepleted sec s* > 1 f ' - - 1.5E-08** - - 1.5E-08 D/0

           <       s l

f ' 8.5E-07 8.5E-07 - 8.5E-07 - - - y/QT sec . 3 (m , ) I I l .

West site boundary, 974 meters from Containment Building

    ** Northwest site boundary, 914 meters from Containment Building amar                                                    B.7-39                                         ODCM Rev. 14

TABLE B,7-5 I l Seabrook Station tono Term Averace Discersion Factors for Soecial (On-Site) Receotors Primary Vent St#ck Dose to 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 - - 1.5E-06 X/0 depleted sec

                         <        s 1.6E-06             -             -

1.6E 06 - see X/0 undepleted m3 ,

          '      1                               -               -

2.7E-08 - - - D/0 l

          \      s 1

P ' 1.1E-06 1.1E-06 - 1.1E-06 - - 1 sec j X/0y I g m3 , The " Rocks": (ENE 244 meters) f - - 1.6E 05 - - 1.6E-05 X/0 depleted sec' (* s f 3 - 1.7E-05 - - 1.7E 05 - j sec X/0 undepleted

                                <*       s 1.1E-07             -         -        -

D/0

          .r       s 5.0E-06         5.0E-06                -

5.0E-06 - - X/07 sec' s s am*7 B.7-40 ODCM Rev. 14

l l l i TABLE B.7-6 l Seabrook Station I Lono-Term Atmosoheric Diffusion and Oeoosition Factors Ground-Level Release Pathway l R E C E P T 0 R(*) Diffusion Factor The Rocks Science & Nature Off-Site l l Center Undepleted CH1/0. 1.6 x 10'd 2.3 x 10'5 1.0 x 10 5 ) sec/m 3 (244m ENE) (406m SW) (823m W) Depleted CHI /0. 1.5 x 10'd 2.1 x 10~5 9.4 x 10 sec/m 3 (244m ENE) (406m SW) (823m W) D/0. m 2 5.1 x 10~7 1.0 x 10*7 5.1 x 10 s (244m ENE) (406m SW) (823m W) Gama CHI /0 sec/m 3 2.6 x 10-5 5.3 x 10 3.4 x 10 (244m ENE) (406m SW) (823m W) (*) 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 f actors (located at 0.25 mile increments beyond the site boundary) exceeded the site boundary diffusion and deposition factors. B.7 41 00CM 9ev. 15 l

          , ,.., , , . . . ,   =--am** * * " ' * * * * ~* * *' '

B . l.

    '._                      u

4,

!./..r...g 7,- g .-

                 ..j. -

l 0-l 'i e-o g-4 i ., l-1. 4 4. e 6 i: 4 I '. e-

t s 8.0 BASES FOR LIOUID AND GASEOUS MONITOR SETPOINTS 8.1 Basis for the Licuid Waste Test Tank Monitor Setooint 3 The liquid waste test tank monitor.setpoint must ensure that Specification 3.3.3.9 is not exceeded for the appropriate in-plant pathways. l 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:

S)q ( 8-1) R C,g 1 (eps) = (, ) (*" ) where: R = Response of the monitor (cps) S)g

                             = Detector counting efficiency for radionuclide "i"                            ;

i (cps /(vC1/ml)) C,9

                              = Activity concentration of radionuclide "i"~in mixture at.

the monitor (vCi/ml) The detector calibration procedure for the liquid waste test tank monitor at Seabrook Station establishes a counting efficiency by'use of a known calibration source standard and a linearity response check. Therefore, in Equation 8-1 one may substitute S) for S)q, where S) is the detector counting efficiency determined from the calibration procedure. Therefore. Equation 8-1 becomes: R = C ,4

                                                                                                   .(8-2)

S) 1 (cps) = (# ) (, ) 8.8-1 ODCM Rev. 4

i

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: . (8-3) PC 11 i i i uC1-m1 Imi wC1) o where: C - Activity concentration of radionuclide "i" in the mixture at i di the point-of discharge (wC1/ml) I MPC j = MPC for radionuclide 'i' from 10CFR20, Appendix 8 Table II, l Column 2 (sc i/ml) l The activity concentration of radionuclide 'i' at the point of discharge is related to the activity concentration of radionuclide "1".at the monitor as follows: F C = p E (8-4) di C ,3 d EE1 EE1 (mi ) , (m1 ) (125) gpm where: . d C di = Activity concentration of radionuclide 'i' in the mixture at the point of discharge (vC1/ml) F, = Flow rate past monitor (gpm) 2 F = Flow rate out of discharge tunnel (gpm) d 8.8-2 ODCM Rev. 4

1 '_ 1 i Substituting the right half of Equation 8-4'for Cdi in Equation 8-3 and l solving for Fd/F, yields the minimum dilution factor needed to comply with , l Equation 8-3: i F C ,g DF 1 (8-5) mini {d g MPC g i ggp _m) guCl-ml) gpm ml-pCi i i where: , I F - Flow rate out of discharge tunnel (gpm) d F, - Flow rate past monitor (gpm) C,g - Activity concentration'of radionuclide "1" in mixture at the J monitor (pC1/ml) MPCj - MPC for radionuclide "1" from 10CFR20, Appendix 8. Table'II, Column 2 (pC1/ml) If F d/F,is less than DFain, then the tank may not be discharged until either Fd or F,or both are adjusted such that: F d (8-5) 1 DF 7-m ain (E) 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: R setpoint " I l D in "I uCi ,( )< ) geos-ml) (uct) ml pCi ml B.8-3 8689R oDCM Rev. 4

where fj 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+#+I4 3 I I I The monitoring system is designed to incorporate the detector efficiency, Sj , into its software. This results in an automatic readout in pCi/cc or pC1/ml for the monitor response. Since this procedure for converting cps to pC1/ml 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 11guld waste test tank is:

                                                                      *I lD setpoint                                                         in

( )( ) ("m'l ) ("m'l ) 8.2 Basis 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.ll.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: ( 8-D R - S gg C,g (cpm) = (CD*-#* pC1

                                                                                                ) ($)

c ,3

                 -                                                                                                     B.8-4 oDCM Rev. 8 8689R
                   - - ' - - - ~-                                   -             _ _ _ . _ _         _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

there:

                   -R      - Response of the instrument (cpm) 599 .- Detector counting efficiency for noble gas "i" (cpm /(pC1/cm3 ))

C,9 - Activity concentration of noble gas "1" in the mixture at the noble gas activity monitor (pC1/cm3 ) C,g, the activity concentration of noble gas "1" at the noble gas activity , monitor, may be expressed in terms of gQ by dividing by F, the appropriate flow rate. In the case of the plant vent noble gas activity monitors the appropriate flow rate is the plant vent flow rate. C,g - hg h (8-8)~ (cme3 - ( e'C (m> S cm 3 where: Q, - The release rate of noble gas "1" in the mixture, for each noble gas listed in Table B.1-10. 4 F - Appropriate flow rate (cm 3/sec) Substituting the right half of Equation 8-8 into Equation 8-7 for C,g yields: R - S 99 hg h (8-9) (cpm) (C }( }( ) C cm As in the case before, for the 11guld waste test tank monitor, the plant vent wide range gas monitor establishes the detector counting efficiency by use of a calibration source. Therefore, 5 can be substituted for S 9g ; 9 8689R M Rev. 4 I

           -in Equation 8-9,'where Sg is the detector. counting efficiency determined from the calibration procedure. Therefore Equation 8-9 becomes:

R - S g h hg (8-10) 3 (cpm) = (cp m) (3,c) ( ) Cm The total body. dose rate due to noble gases is determined with Equation 3-3: l l b - 0.85

EL(R)
tb Og DF8 9

(3-3)

i 3

(mrem) , <pC1-sec) ( ) (p_C1 C ) (mrem-m yr C1-m 3 sec pCi-yr ) where: l D tb. - total body dose rate (mrem /yr) l 0.85 - (1.0E+06) x (8.5E-07) (pCl-sec/pCi-m3 ) IE+06 - number of pC1 per pC1'(pC1/pCI) l 8.5E-07 - [X/Q)Y, maximum off-site average gamma atmospheric f dispersion factor (sec/m3 ) for primary vent stack releases EL(R) - Release point correction factor - 1.0 for primary vent stack I

                      .                                                                                                                                                      l' Qg                                   - As defined above.

I DFB g - total body dose factor (see Table B.1-10) 3 (mrem-m /pci-yr) 8.8-6 8689R OOCH Rev. 7 l

A composite total body gamma dose factor, DFBc, may be defined such that: DFB c i 1 DFB; (8-11) i 1 l 3 3 mrem-m pCi-yr (Q) sec

                                            ,       gg) mrem-m )

sec pCl-yr Solving Equation 8-11 for DFB c yields: h gDFB g i DFB c

(5-7) l 01 l 1 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 settirg D tb equal to 500 mrem /yr and substituting DFB for DFB g in Equation 3-3, ont may solve for [ Qg at the limiting whole body noble gas I dose rate: h-3 588 DFB (8-12) 1 C (Q) sec mrem-uCi-13

                       , (yr-pC1-sec          ) (pCi-yr3) mr m m Substituting this result for [ hg in Equation 8-10 yields Rtb, the response i

of the monitor at the limiting noble gas total body dose rate: R tb

                    =           588             S g        h            DFB g

(8-13) 3 3 (cpm) = (mrem-uCi-m }com-cm } (see) (DCi-yr ) p-pC1-sec pC1 3 3 cm mrem-m The skin dose rate due to noble gases is determined with Equation 3-4: b skin

                      - EUR)

Qj DF 3

(3-4) (mrem) , ( ) (uCl) garem-sec) yr sec pCi-yr B.8-7 8689R ODCM Rev. 7

r where: a EL(R) - 1.0 for primary vent stack release (dimensionless) bskin - Skin dose rate-(mrem /yr) h, As defined above. DFj Combined skin dose factor (see Table B.1-10) (crem-sec/pCi-yr) Acompositecombinedskindosefactor,DFj,maybedefinedsuchthat: DFj hg - hj DFj (8-14) i i gmrem-sec) (uC1) , ggCl) gmrem-sec) pCi-yr sec sec pCi-yr SolvingEquation8-14forDFjyields: T. L O DFj g DF' - ' (5-8) L o, i Technical Specification 3.ll.2.1.a limits the dose rate to the skin I from noble gases at any location at or beyond the site boundary to 3,000 mrem /yr. l By setting D equalto3,000 mrem /yrandsubstitutingDF;forDFjin skin Equation 3-4 one may solve for [ Og at the limiting skin noble gas dose rate: I h,=3,000 DF. (8-15) I c l ggQl.) (mremy g uCl-yr )

                                'sec                   yr       mrem-sec l                       Substituting this result for [ h .ingEquation 8-10 yields Rskin, the response I

of the monitor at the limiting noble gas skin dose rate. i B.8-8 8689R ODCH Rev. 7 . I I

O Rskin - 3,000 5 h (8-16) i 9 3 pCl ICP*) (mrem) yr (cpm-cm pC1 ' <sec' 3 (mrem-yr -sec } Cm As with the 11guld monitoring system, the gaseous monitoring system is also designed to incorporate the detector efficiency, 5 , into its 9 software. The monitor also converts the response output to a release rate ( CI/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 b6come: R - 588 tb DFB c 3 (gCi)l , (mrem-pC1-m ) <pci-yr ) sec yr-pC1-sec 3 ; mrem-m 1 l R skin

                       -   000       h,                                          (5-6)

C (gC1) , (mrem) pCl-yr I see yr gmrem-sec) 8.3 Basis for PCCW Head Tank Rate-of-Change Alarm Setpoint The PCCW head tank rate-of-change alarm 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, a setpoint based on detection of an activity level of 10-8pC1/cc in the discharge of 'he 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 j 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. E h 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, l October 1977. B. Hamawl, 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. D. National 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 i l l l l l R-1 8689R ODCM Rev. 7

APPENDIX A e DOSE CONVERSION FACTORS

    .               A-1              ODCM Rev. 8
                                                            )

APPENDIX A Dose Conversion Factors f 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. Gince Seabrook is a salt water site, the - , assumed pathways of exposure taken from Reg Guide 1.109 are I Aquatic foods - fish; Aquatic foods -invertebrates; and dose from shoreline deposits (direct dose). No drinking.. water or irrigation pathwas exist because of the salt water environment. In ad~ Aon, exposures resulting from boating and swinnning activ.tties 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 provida dose equations for them. For completeness, the swinnning and I boating pathways have been includes using the dose models from the HERMES code (HEDL-THE-71-168, Dec.1971) , section G, Water Immersion. The' Method I dose conversion factors are derived by l calculating the dose impact to individuals via the site l specific pathways for a unit activity release (1 curie per l 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 < 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 ODCM then represents a combination of different limiting organs and age groups ' which, when used to calculate a done impact from a mix of radionuclides released in liquid affluents, 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 alp-) , The full assessment for the ODCM dose factors indicated that for i = co-60, the maximum dose l (aram/yr) is to the GI-LLI of an adult as the target organ and age group, therefore: ODCM Rev. 8 A-2

 -a          -                             . .-

U := 21 kg/yr adult usage factor for fish ap M := 0.1 mixing ratio for near field dilution p provided by submerged multiport ' diffuser. F := 918 cu. ft./sec effluent flow rate for circulating 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 F
                                                -5 D             := 4.02 10                   mrea/pci, adult GI-III 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 release and p ingestion, in hrs. 1119.7 is the factor to convert from Ci/yr per ft3/sec to pCi/ liter. nota . that RG 1.109 uses 1100 as a rounded approximation. Therefore the dose from fish to adult GI-III is (area /yr): , U M -1 t ap p p 1119.7- -Q B D e = 0.0103 F i. ip alpj i 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: ODCM Rev. 8 A-3 - a y + e -r-- -

                                        ,_2.,        .-- ,

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 ; ap p p 1119.7- -Q B D *e = 0.0245 F i ip alpj t' 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 - e . F '

i. alpj 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 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 ap assumed shoreline activities at seabrook. M := .1 miving 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 ODCH Rev. 8

    ,    4   .                       a                          ,.       _  .~.-         . ,. -

7 I' 3 T := 1.923 10 radioactive half life in days for Co-60.

                                           -8 D         := 1.70 10           dose factor for CO-60 due aipj'                        to deposits in sediments, units of (arem/hr)/(pci/m2) t     := 0.                    transit time to point of p                            exposure, hrs t     := 131400                period that, sediment is b                             assumed to be exposed to water contamination for long term buildup, set at 15                        ,

years for Method I DCF's i Q := 1.0 curies per year, Co-60 i assumed 111970 conversion factor to convert (Ci/yr)/(ft3/sec) to 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 -1 t ap p p b TD e ,1 - e = 0.0573 111970- - Q . F i aipj Direct dose due to Swinunkg: The dose due to immersion in water (swimming) 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 gra), 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 swimming is small when w M to the other exposure pathways, the original conservatism on dilution are kept here. A-5 ODCM Rev. 8 I I

The dose from swinaning is given by the following equation: U 12 p 1.0 10 - - Q DF (area /yr) j F .i im ; a i l i i a Where: l 1 U := 45 hrs /yr, usage factor for , i p swinnning for =v4== age - s i group (toen) from HIl20ES. 11 F := 6.56 10 liters /yr, estimated annual l a dilution affluent flow in multiport diffuser Q := 1.0 ' curies /yr, assumed release i rate of nuclide i.

                                                                     -6 i

DF := 4.6 10 arem-liters per hrs-pci,' dose im factor for Co-60 for water insersion taken from HERMES. ! l I 12 1.O.10 constant for pCi/Ci Therefore the swinnning dose for a 1 curia release of co-60 is (arem/yr): M 12 p -5 .j 1.0 10 U - - Q DF = 3.155 10 p F i in a As can be seen, the contribution of the swinuming dose,is only about one 30000ths of the total of the 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 swinuning dose,(and I         l A-6           -                     ODCH Rev. 8 l
 ,c.,

v. - - - ,-7 ,, w , e -

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

corrected for change in usage assumptions). The resulting does is'found to be less than the swimming dose and can also therefore be discounted in this case. Total liquid Pathway dose: The sum of the above liquid pathway doses can now be added to give the total navim m individual dose to the critical organ (adult-GI-LLI) for Co-60. This 4 gives: 0.0103 + 0.0245 + 0.0573 = 0.0921 mram/yr Since the internal doses'given by the RG-1.109 , methods actually are 50 yr dosa 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. @ 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 ODCM, the critical organ dose factor is seen to be 0.0921 aren/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 example. The whole body site specific dose factor for the ODCM was calculated in the sano way treating the whole body as a separate organ. e A-7 OM Rn. 8 4 c....- , , - -.

i II. Gaseous Pathways - Seabrook Site Specific DCF's l The models used to' assess doses resulting from gaseous affluents in the form of iodines, tritium, and particulates For Seabrook, are derived from Appendix C of Reg. Guide 1.109. it is assumed that at the off site location which exhibits minimum atmospheric dilution for plant releases the following-exposure pathways exist: inhalation, ground plane, ingestion of goats milk, meat, stored vegetables, and leafy vegetables. The Meth'od 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 age / 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 developed, the following calculation for Mn-54 is shown. The critical organ / age group for Mn-54 was selected gased on a full assessment of all organ and age group combinations. For elevated releases from the plant vent stack to the maximum site boundary (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: 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 i Where for the case of Mn-54 releases, the variables above j are defined as: 4 3.17 10 is the number of pCi/Ci divided by the number of second per year l 1 1 l A-8 ODCH Rev. 8

R := 8000 tha breathing rate for ags group a a (Edults) in n"3 /yr. X ~7 the long term average depleted

                  - = 7. 5 10 Q                                                atmospheric dispersion factor, in sec/m"3, at the ==v4==                      exposure point off site.(S.B.)

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 ija                                  nuclide 1 (Mn-54), organ j (GI-LLI) ,

and age group a (adult) taken from' RG 1.109, table E-7, in area /pci inhaled. Therefore, the inhalation dose to the maximum potential off site individual is given as: 4 Y 3.17 10 R - -

                                                          -Q.        DFA              = 0.00184              mram/yr per Ci a       ,q    i             ija l

PART B: Ground Plane Direct Dose Contribution: The general equations for ground plane external direct dose in RG 1.109 are equations C-1 and C-2 which together give the dose DG as: i

                                                                                                      -1      t i   b              ,

12 'D' 1-e 1 8760 1.0 10 S - - - Q - DFG

                                                                                  '                   A                    ij F       ,Q                  i i                       i Where for the case of Mn-54 releases, the variables in the above equation are defined as:

I A-9

ODCM Rev. 8

12 1.0 10 io ths number of PCi per Ci S := 0.7 the shielding factor provided by

            .F -                         residential structures (dimensionleso) for use in calculation ac&=" lated doces 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 rav4="= 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 mres/hr per pCi/m"2 Q        := 1.0                is the unit release quantity assumed 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 the ground plane at the maximum off site exposure location for Mn-54 is given as:

                                                      -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 F per Ci On Rw. 8 A-10 . l l

r PART C Ingestion Dose Crntributions 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: , _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

                             ,,q      l'            Y     1              iv       PX v     Ei                        i    ,

l l I PART O.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: 1 8 1.14 10 is the number of pCi per Ci divided by the number of hours in a year (8700) . i D -8

                       - = 1.5 10                       is the relative deposition factor, in l

Q 1/m2, at the maximum exposure point off site (S. B.)

! Q := 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) A-11 ODCM Rev. 8

1- = 0.00219 Cffectiva removal rate constant for El Mn-54 from crops dua to decay and weathering, in hr-1 t := 131400. soil exposure time to deposition, in b (equal to 15 yrs, or uid plant life) Y := 2.0 agricultural productivity (yelld) 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 l                                     1      := 9.252 10            radioactive decay constant for Mn-54, i                            in hrs-1 i

P := 240. effective surface density of soil. in kg/m2 t := 1440. crop holdup time after harvest and l h before ingestion, in hrs ! t := 1440. crop exposure time to plume, in hrs e Therefore, the concentration of Mn-54 in stored vegetables produced at the location of maximum deposition for a unit activity release is given as: _A .t -1 t Ei e i b -1 t 8 'D' 1-e 1-e i h

                                                                                +B      -                       e           = 67.379 1.14 10 -      -
                                            -Q   -

r-

                                        .Q     i             Y     1               iv               P1 v     Ei                                 i     '
                                                   ~

Wi/4 PART C.2: Imafy Vegetable Concentration: 1 ' For leafy vegetables, the above equation is repeated with the value for t.h, crop holdup time after harvest in changed from 1440 hrs * ' to 24 hrs, i.e'.: ODCH Rev. 8 A-12

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:

                                                                                           ~                                 !

_x .t -1 t Ei e i b -1 t 8 "D' 1-e 1-e i h

                         -Q    -

r- +B - e = 76.811 1.14 10 -

                   ,Q       i              Y     1               iv          P1 v     Ei                             i         ,

pCi/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 : , [ Y := 0.70 for agricultural productivity of pasture v grasses, kg/m2 l t := 720. for grass exposure time to plume, hrs ; j e t := 0.0 for holdup time after harvest h Using these variables ir, the above equation gives the concentration in pasture grass as: _x .e _x .e Ei e i b -1 t 8 'D' 1-e 1-e i h

                                                               +B       -                          e            = 179.227 1.14 10 -       -
                           -Q    -

r-

                      ,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 e:.op exposure time to pluma 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. _1 .t -1 t Ei e i b -1 t 8 "D' 1-e 1-e i h r- +B - *e = 53.037 1.14 10 - -

                      -Q     -
                 ,Q       i                Y    1                 iv          P1 v     Ei                                 i pCi/kg PART C.3.c.:            Concentration in Goat's Milk:                       C a

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    iC     -

Q *e = conc. in milk, pCi/litar a v F

                                                                    .                                                                  l A-14                                             ODCM Rev. 8                 !

I

           "-M                 -m--..-

whnro tha variables cre d3 fined cc:

                               -4 F     := 2.5 10         average fraction of animal's daily                  1 I

m intake of Mn-54 which appears in each litar of milk', in days / liter Q := 6.0 amount of feed consumed by a goat i F per day, in kg/ day (50 kg/d for meat) 1 t := 2.0 average transport time of activity , f from feed into milk and to receptor,, in days..

                                 -3 1     := 2.22 10        decay constant of Mn-54 ,in days-1 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: C = f f C + '1 - f ' C +t -

                                                           '1 - f     C v          p     a    p    .

p. s p . s. 's where the following equals:

i f := 0.5 fraction of the year that animals p graze on pasture f := 1.0 fraction of daily feed that is a pasture grass when the animal grazes on pasture C := 179.227 concentration of Mn-54 in pasture p grass as calculated from above, PCi/kg C := 63.037 concentration of Mn-54 in stored s ised as calculated frca above, in pCi/kg Therefore, the concentration in the total animal's feed is . estimated to be : l A-15

ODCM Rev. 8

-r.y

1

                                                                                                               ~
                     -f       f     aC     + 'l - f              C           +f       *
                                                                                        'l - f       -

C = 121.132 l O P P. O P D. D P . PCi/kg 1 I When this value of 121.132 is put back into the above general l equation for nuclide concentration in milk, we get: (C := 121.132 pC1/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 concentration 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           w 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 in each kg of flesh, in days /kg Q      := 50.0                 animal's daily feed intake, in F                            kg/hy                                                           ,

t := 20.0 average time from slaughter to a consumption, in days C := 121.132 concentration on Mn-54 in animal's 4 y feed, same as calculated above for , goat, in PCi/kg ~ Therefore, the concentration of Mn-54 in animal meat is calculated to be: n

                                                                                -                         OW     Rp. 8 A-16 m   -                                                 , ,            .;n~       w

   .                                      =    -                        .   -   -   . - __

l

                                                                                                           " i4
                                             -1     t i    s F   *C       -Q        e             = 4.635           pCi/kg in meat                    ;

I f v F- , for Mn-54 . PART D: DOSE FROM INGESTION OF FOODS PRODUCED AT MAXIMUM IDCATION

Now that we have calculated the concentration of Mn-54 in milk, leafy vegetables, and stored vegetables produced at a m at, locat ion of maximum air deposition, the resulting dose to any organ j and age group a can be calculated from the following ,

J general equation C-13 taken from RG 1.109: l

DFI -

                               'U       f     *C     +U        C     +U       C   +U          f   C           i 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-LLI 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 arem/pci ingested (RG 1.109, Table E-11)

U := 520.0 vegetable ingestion rates for va adults, kg/yr i 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' i ODCM Rev. 8 A-17 .

U := 110.0 . meat'ingrtiknratofor Fa adults, 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: , DFI -

                                                              "U                           -

f C +U C +U C +U f C = 0.4495 ija . va g v ma a Fa f La 1 L, arem-

                                                                                                                                                                                                       /yr:

per

                                                                                                                                                                                                      -Ci By breaking the above dose equation down into the different pathways which combine to give the total ingestion dose, we can see i

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 a ! A-18 ODCH Rev. 8 e

Dose for ingestion DFI U C = 0.00714 of meat ija Fa. f Dose for ingestion DFI *U f C = 0.0688 of leafy vegetables ija La 1 L PART E: TOTAL DOSE FROM ALL EXPOSURE PATHWAY The total dose from all exposure pathways assumed to be present at 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 activity released. This then demonstrates the development of the Seabrook ODCM Method I dose factors for gaseous release of particulates from the vent stack. Inhalation dose (Part A) 0.00184 mres/yr per Ci Ground plane dose (Part B) 0.658 mram/yr per Ci Ingestion dose total (Part D) 0.449 mram/yr per Ci Total dose all pathways 1.11 arem/yr per C1 (critical organ is GI-LLI of an adult for Mn-54) l l l A-19

ODCM Rev. 8 l

l

l-r l l APPENDIX X: SORC APPROVED PART A REVISION AVAITING NRC REVIEV, i X1 ODCM Rev.15

2.0 RESPONSI81LITIES FOR PART A All changes to Part A of the ODCM shall be reviewed and approved by the Station Operation Review Committee (50RC) and the Nuclear Regulatory l Commission prior to implementation. It shall be the responsibility of the Station Manager to ensure that the ODCM is used in the performance of the surveillance requirements and administrative controls of the appropriate portions of the Technical Specifications. X-2 00CM Rev. 15 [

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

TABLE A.3-1 Radioactive Liould Waste Sampline and Analysis Procram (continued) E Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD) Liquid Release' Type Frequency Frequency Analysis (I) (ucl/ml) y H-3 1x10~5 M Grab Sample Gross Alpha 1x10'? W Sr-89. Sr-90 5x10 s I Grab Sample 0 (9) C. Steam Generator Principal Gamma 5x10 7 Blowdown Flash W Emitters ts 7 Tankt sus) Grab Sample I-131 1x10'5 w (Continuous Dissolved and Release)(5) H Entrained Gases 1x10'5 ra ample (Gamma Emitters) g H-3 1x10*5 M Grab Sample Gross Alpha 1x10*7 g Sr-89. . 9 5x10 s l Grab Sample 0 (9) Fe-55 1x10'5' o 2 to f , G

l

                                .                                                                      l

.I TABLE A;3a Notations (Continued) (33 The principal gamma emitters for which the LLD specification applies include the following radionuclides: : Mn 54, Fe-59 Co-58. Co-60, In 65, Mo-99, Cs 134. Cs-137. Ce-141, and Ce 144. This~1ist 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 Annual Radioactive Effluent Release Report in           l accordance with Technical Specification 6.8.1.4. . Isotopes'which are not detected should be reported as "not detected." L Values determined to be below detectable levels are not used in dose calculations.

H) 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. :from a volume of a system that has an input flow during the continuous release. (6) Sampling and analysis is only required when Steam Generator 810wdown is directed to the discharge transition structure. U3 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 gamma 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 inoperable, sample PCCW and ,

SWS daily for principal gamma esitters. 4

d. With a confirmed PCCW/SWS leak and PCCW activity in excess of 1x10 uC/cc, sample SWS every 12 hours 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 or greater than that of an SWS radiation monitor, located in the unit's combined SWS discharge, with an LLD of 1x10 a uC/cc. If this sensitivity cannot be achieved, the SWS will be sampled once every 12 hours.

(a) If the Turbine Building Sump (Steam Generator Blowdown Flash Tank) isolate due to high concentration of radioactivity, that liquid stream will be sampled and analyzed for. Iodine-131 and principal gamma emitters prior to release. X-4 ODCM Rev. 15 l I

TABLE A.3-1 Notations (Continued) jN Ouarterly composite analysis requirements shall only be required when l analysis for principal gamma emitters indicate positive radioactivity, l 1 i j l! X-5 00CH Rev. 15 l

TABLE A.4-1 Radioactive Gaseous Waste Samoling and Analysts Procram (continued) Hinimum LowerLimi},pf Sampling Analysis Type of Activity Detection Gaseous Release Type Frequency Frequency Analysis (LLO) (uCi/cc)

3. Gland Steam W Principa),pamma Packing Continuous Particulate Emitters 1x10'II Exhauster Sample Continuous II 1x10-12 Charcoa Sample H Gross Alpha Continuous p[j@ osl , 1x10'll Sample O Sr-89, Sr-90 4 Continuous pfj$$l,{, 1x10'll Sample (8) !

4. Containment p(3) Principal2) Gamma 1x10'8 Purge Each Purge Grab Each Purge Sample H 3 (oxide) 1x10

8 9 N'

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

TABLE A.4-1 Notations , (Continued) l (2) The principal gamma emitters for which the ' LD specifications applies 1 include 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 Cg,-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 Annual Radioactive Effluent Release Report in accordance with .l , Technical Specification 6.8.1.4. Isotopes which are not detected may be reported as "not detected." Values determined to be below detectable ; levels are not used in dose calculations. (33 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 t increased more than a factor of 3: 2) the noble gas activity monitor for ; the plant vent has not increased by more than a factor of 3. For , containment purge, requirements apply only when purge is in operation. , (8) Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. (5) 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 made in accordance with Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3. (6) Samples shall be changed at least once pt. seven (7) days and analyses shall be completed within 48 hours after cr.uging, or after removal from sampler. Sampling shall also be performed an. least once per 24 hours ; for at least seven (7) days following each shutdown, startup, or THERMAL j POWER change exceeding 15 percent of RATED THERMAL POWER within a- ' one-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement i does not apply if; 1) snalysis 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. ! U3 Samples shall be taken prior to start-up of condenser air- removal system when there have been indications of a primary to secondary leak. (s) Quarterly composite analysis requirements shall only be required when l analysis for principal gamma emitters indicate positive radioactivity. l X-7 ODCM Rev. 15 l l

APPENDIX Y: 1 1 10 CFR 50.59 EVALUATION 94 267-01, REVISION 15 0FFSITE DOSE CALCUIATION MANUAL, 12-13-94. l l l l Y-1 ODCM Rev.15

l l 10 CFR 50.59 EVALUATION I i "b7~b[ SNEET OF

2. TITLE: movlston 15 of felte Dose Calculation Manual (CDCM)

J. T. Linville DATE: 12/13/94

3. INITIATOR:

4. DETERMINATION OF SAFETY EVALUATION APPL'CAstLITY a

Does the proposed changet A. Make changes in the facility as described in the UFSAR? [ } YES [X1 NO

3. Make changes in prococksres as described in the UFSAR? (X) YES [ ] NO C. Involve tests or experiments not described in the UFSAR? I } YES [X) NO BAS 15 (s w rting information is required for each question; attach additional peces as necessary):

SEE ATTACHED l C Check this block if the answers to Questions 4A, 48 and 4C are No and a Safety Evaluation is being performed r for conservatism.

5. OPERATING LICENSE l

Does the proposed change require a change to the existing Operating License (including the ' Technical Specifications) or are additional Operating License requirements needed7 ( 3 Yt3 [X1 NO 3d15 (supporting infonastion is required for each question; attach additional pages as necessary): c l SEE ATTACHED l l

6. REVIEWS ENGINEERING REVIEW INDEPJJiDENT REVIEW

                                      -                          REVIEWER i   REVIEW R DATE                /    N                                    DATE            /t   !/4/4,4 q    n 4

NAMM FORM 11210A Rev, 13 Page 1 of 2 W2 ODCM Rev. 15

j

10 CFR 50.59 EVALtlATION (Continued) 1 IRSSER

7. SAFETT EVALUAfl0N These cyaestions shalt be answered if any question in block 4 or 5 la answered YES.

A. Will the probability of an accident previously evaluated in the UFSAR be increased? [ ] YES [X] NO B. Witt the consequences of an accident previously evaluated in the UFSAR be increased? [ ] YES [X} NO IDENTIFICATION C. Will the probability of a antimction of equipment leportant to safety be increased? [ ] YES [X] NO

0. Wllt the consequences of a malfunction of equipment important to safety be increased? [ } YES [X1 NO E. Wilt the possibility of an accident of a different type than any previously evaluated [ ] YES [X3 NO ;

in the UFSAR be created? F. Will the possibility of a malfunction of a different type than any previously evaluated [ } YES [X) No in the UFSAR be created? G. Wilt the margin of safety as defined in the bests for any technical specification be [ ] YES [X] NO reduced? BRIEF

SUMMARY

AND BAS!$ (supporting information is required for each cyaestion; attach' additional pages as necessary): SEE ATTACHED SORC REVIEW NSARC REVIEW 8. MEETING S 9h IEETING S DATE /2~M' DATE NOkbt.oAI) STATIOhiMANAGER APPROVAL NSARC CHAIRMAN CONCURRENCE NAMM FORM 11210A Page 2 of 2 Rev. 13 M ODCM Rev. 15

SAFETY EVALUATION FOR Omnt; DOSE CALCULATION MANUAL - REV.15 i l EXECUTIVE

SUMMARY

i

1. Reference to the " Education Center" has been updated to reflect the current designation of this facility as the " Science and Nature Center".

2. Reference to the " Semiannual Radioactive Effluent Release Report" is changed to the " Annual Radioactive Release Report" This admuustrative update reflects a recent amendment to the Technical Specifications that allowed the plant to change the frequency of effluent report submittals to the NRC

from semi-annual to annual

3. The designations of " Executive Director-Nuclear Production" and " Health Physics Department" have replaced outdated designations of " Production Services Manager" and " Radiation Protection Department".

1

4. Typographical corrections in Tables B.1-10, B.1 13, and S.1-15 are made in response to a QA audit '

finding. These adnunistrative changes have no functional impact on the use of the information contained in the tables. However, a typographical error in the exponent for the critical organ dose rate factor for ground level releases was identified for Cs-137 (6.09E+09) on Table B.1-12, and is corrected to the value of 6.09E+03. It was determined the the; error did not impact past calculations and was in the conservative direction if it were to have been applied in estimating dose.

5. Table B.4-1 has been updated to reflect recent changes in the location of milk sampling stations listed as part of the Radiological Environmental Monitoring Program. This is due to the loss of Station TM-10 (Hampton Falls), and its replacement with a new sampling location, station TM-16 (Kensington). In addition, the location of the TLD site designated TL-30 has been deternuned to be )

on Route 27, and replaces the former location designation of Route 101C, which had been the old roadway route number originally indicated on local maps. Table A.3-1, " Radioactive Liquid Waste Samplirig and Analysis Program" is proposed to be amended ( 6. by stipulating that quarterly activity analyses for Sr-89, Sr-90, and Fe-55 in Turbine Building Sump and Steam Generator Blowdown discharges would only be made when one or more weekly analyses i for principal gamma emitters indicates positive activity. These three nuclides represent a small l fraction of any expected contanunation event, which would be dominated by gamma emitting ) radionuclides. Without the detectable presence of such gamma emitters in waste samples, it is judged I l unreasonable that any of these other radionuclides would be present and detectable above the required LLD's. This change does not impact the ability to project offsite doses since the reduction in the l number of isotopic analyses only is concerned with those composite samples that have no indication of any contamination, and therefore, no contribution to any offsite dose. i I

7. Table A.4-1, " Radioactive Gaseous Waste Sampling and Analysis Program" is proposed to be l amended by stipulating that quarterly activity analysis for Sr-89 and Sr-90 in the Gland Steam Packing Exhauster discharge would only be made when one or more of the weekly particulate analysis for principal gamma emitters indicates positive activity. These non-gamma radionuclides represent a small fraction of any expected contmimtion event, which would be dominated by principal gamma l

emitters. Without the detectable presence of such gamma emitters in waste samples, it is judged unreasonable that any of these other radionuclides would be present and detectable above the required ( LLD's. This change does not impact the ability to project offsite doses since the reduction in the l number of isotopic analyses only is concerned with those composite samples that have no indication of any contammation and, therefore, no contribution to offsite dose. Revision 15 will implement items 1-5 following SORC approval and manual issue. The affected pages for l items 6 and 7 will be held following SORC approval for NRC review. The changes in items 6 and 7 are to ( PART A of the ODCM and require NRC review and concurrence prior to implementation. l l Y-4 ODCM Rev. 15 l

4.0 DETERMINATION OF SAFETY EVALUATION APPLICABILITY l

4A. Make changes in the facihty as described in the UFSAR? NO 1 i The correction of typo sapidcal errors, sampling locations, incorrect ground level release factor, and changes to the analysis tables in Part A of the ODCM do not change the physical facility as described l in Sections 1.9, 2.3, 3.1.6.1,11.1,11.1.5,11.2,11.3,11.5.2.2 or in 15.7.3.2. 4B. Make changes to picess as described in the UFSAR7 YES Section 11.5.2.2 of the UFSAR discusses the use of the Station Offsite Dose Calculation Manual (ODCM) for the purposes of alann setpoints for the effluent radiation monitors. This revision to the ODCM changes the analysis protocol for certam release points listed in Part A of the ODCM. ~ 4C. Involves tests or exp Ae not described in the UFSAR? NO This change to the ODCM does not change the models or calculations in the ODrM but modifie.. .s requirements for when certam analyses are performed for certam effluent pathways that are not normally considered radioactive. The change does not involve a test or expon.sst not described in the UFSAR. 5.0 OPERATING LICENSE 1 NO ; The Techment Specifications require the ODCM to implement calculation procedures using models j and specified parameters to ensure the acmal exposure to a member of the public through appropriate pathways is unlikely to be substantially underestimated. The ability of the ODCM to successfully i satisfy these requirements is not affected by the changes in Revision 15. The attached table shows the ! I relationship between the principal gamma emmers and the beta emitters both in primary coolant and secondary coolant under the UFSAR assumptions of 0.12% clad defects and a simultaneous 100 lb/ day prunary to secondary leak. Additionally, the capability for the Seabrook Station effluent program to detect the gamma emitters and beta enutters for both liquids and gases. In all cases the data shows that if there are no principal gamma enutters detected in either the Turbine Buildmg Sump, the Steam Generator Blowdown, or the Gland Steam Packmg Exhauster, it is judged l unreasonable that any of these other radionuclides would be present and detectable above the required LLD's. Regulatory Gmde 1.21, Measurmg, Evaluating, and Reportmg Radioactivity in Solid Wastes and Releases of Radioactive Matenals in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, permits the use of ratios between routmely measured radionuclides and certam radionuclides which have no gamma rays and weak beta radiation for the purposes of actually ; quannfying the radionuclides which are the beta emitters. In this case, Revision 15 utilizes this concept only for the tngger to perform the beta analyses for the purposes of quantification rather than for quantification.

7. SAFETY EVALUATION A. Will the probability of an accident previously evaluated in the UFSAR be increased?

NO

                                                                                                             "* U Y-5

Revision 15 of the ODCM addresses typographical corrections and introduces a screening process which only requires beta emitter analyses when principal gamma emitters are detected for certain effluent pathways that are not normally radioactive. 'Ibese changes are passive in nature dealing with analytical routines and have no effect on the probability of an accident previously evaluated in the UFSAR. B. Will the consequences of an accident previously evaluated in the UFSAR be increased? NO 1 i The correction of typographical errors and the introduction of a screening process using the detection of principal gamma emitters to trigger beta analyses for effluent pathways that are not normally radioactive does not have any effect on the consequences of an accident previously evaluated in the UFSAR. l C. Will the probability of a malfunction of equipment important to safety be increased? NO l l I The revision to provide corrections for typographical errors and to provide a screening process using the detection of principal gamma emitters to indicate the need for beta analyses on effluent pathways I normally not considered radioactive does not change the effluent monitor setpoint methodology. Therefore, it does not affect the probability of a malfunction of equipment important to safety. l l D. Will the consequences of a malfunction of equipment important to safety be increased? . NO The ODCM methodology is passive with regard to plant equipment malfunctions. The changes made in Revision 15 to the ODCM for typographical error = and to introduce a screening mechanism using the detection of principal gamma emitters to trigger beta analyses for certain effluent pathways normally not considered radioactive does not increase the consequences of a malfunction of equipment important to safety. E. Will the possibility of an accident of a different type than any previously evaluated in the UFSAR be created? NO The ODCM methodology is used to evaluate the effect of the release of radioactive emissions from the plant. This methodology involves sampling, analysis, and calculations which is passive with regard to the operation of the plant. Revision 15 to the ODCM which corrects typographical errors and creates a screening mechanism using the detection of principal gamma emitters to trigger beta analyses for certain effluent pathways normally not considered radioactive does not create de possibility of an accident of a different type than previously evaluated in the UFSAR. F. Will the possibility of a malfunction of a different type than previously evaluated in the UFSAR be created? NO The ODCM methodology used to evaluate the effects of radioactive releases from the plant is passive with regard to the operation of the plant. The methodology involves sampling, laboratory analyses, and calculations. Revision 15 to the ODCM which corrects typographical errors and allows for a screening mechanism using the detection of principal gamma emitters as a trigger for beta analyses Y-6 ODCM Rev. 15

for certain emuent pathways normally not considered radioacave does not create the possibility of a malfunction of a different type than previously evaluated in the UFSAR. .G. Will the margin of safety as defined in the basis for any Tachnieml Specification be reduced? i NO The bases for Technical Specifications 3/4.11.1, Liquid Emuents, 3/4.11.2, Gaseous Emuents, and 3/4.11.4, Total Dose, implement the requirements of Ma adix I to 10 CFR Part 50. The ODCM dose calculation math adalogy and pm m; implement calculational procedures based on models and data to ensure the acmal exposure to a member of the public through appropriate pathways is unlikely to be substantially under==a==+d Revision 15 to the ODCM which corrects typographical errors and allows for a screening procedure employing the detection of principal gamma emitters to trigger beta analyses for certain emuent pathways not normally considered radioactive does not change the Es. The revision does not eliminate beta analyses for certam :i present ODCM models or y-emuent pathways not normally considered radioactive. The attached table shows that if there are no principal gamma emitters detactad on these pathways, it is judged unreasonable tha. any of these oth radionuclides would be present and detectable above the required LLD's. Therefore, tte screenmg mathadalogy in Revision 15 to the ODCM employing the detection of principal ramma emitters as a , trigger for beta analyses on certain emuent pathways normally not considered radioactive does not reduce the accuracy or reliability of dos: calculations or setpoint determmations and thus does not reduce the margin of safety as defined 3.n the basis of Technical Specifications. l I i l I i l l l 1 Y-7 ODCM Rev. 15

k Offsite Dose Calculation Manual Rev.15 10 CFR 50.59 Evaluation Reactor Coolant Reactor Coolant Secondary ODCM Required Typical Liquid ODCM Required Typical Gaseous Activity (uCi/ml) Corrosion Product Coolant Activity Liquid Effluent Effluent Sample Gaseous Effluent Effluent Sample - Nuclide 0.12% Clad Activity (uCl/ml) (uCl/ml) Sample LLD MDA (uCl/ml) Sample LLD Gamma MDA Defects Note 1 Note 1 Note 1 and 2 (uCi/ml) (uCl/cc) (uCl/cc) Sr-89 3.50E-04 4.91E-08 5.00E-08 3.90E-08 1.00E-11 1.40E-13 Sr-90 1.00E-05 1.20E-09 5.00E-08 2.00E-08 1.00E-11 3.80E-14 Sr-91 6.50E-04 3.81 E-08 1.20E-07 Mo-99 8.40E-02 9.88E-06 5.00E-07 2.72E-07 1.00E-11 1.73E-13 Tc-99m 4.80E-02 2.24E-05 3.61E-08 l-131 2.70E-01 3.33E-05 1.00E-06 3.10E-08 1.00E-12 1.90E-14 Cs-134 2.50E-02 2.88E-06 5.00E-07 3.01E-08 1.00E-11 1.27E-14 Cs-137 1.80E-02 1.92E-06 5.00E-07 3.73E-08 1.00E-11 9.50E-15 Ce-144 3.30E-05 4.82E-09 5.00E-07 2.28E-07 1.00E-11 5.45E-14 I 1.60E-02 1.71 E-06 5.00E-07 3.35E-08 1.00E-11 1.16E-14 ce Co-58 Co.60 2.00E-03 2.18E-07 5.00E-07 1.84E-08 1.00E-11 8.72E-15 Mn-54 3.10E-04 4.82E-08 5.00E-07 4.67E-08 1.00E-11 9.01E-15 Fe-55 1.60E-03 1.68E-07 1.00E-06 3.00E-07 Fe-59 1.00E-03 1.23E-07 5.00E-07 6.64E-08 1.00E-11 1.82E-14 Note 1: These values taken from Updated FSAR Section 11.1. Tables 11.1-1 and 11.1-4. Note 2: Based on 0.12% Cladding Defects and 100 lbs/ day pdmary to secondary leakage (per Note 1 in Table 11.1-4). ! O x >

Page 1 i l

APPENDIX B Process Control Procram 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. Response: No changes were made to the Process Control Program during the reporting period. 1 1 l I l 1 i l

i i APPEMOIX C Radioactive Liouid Effluent Monitoring Instrumentation Reauirement: Radioactive Liquid Effluent Monitoring Instrumentation channels are required to be

operable in accordance with 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 that an explanation for the delay in correcting the inoperability be provided -

the next Annual Effluent Release Report in accordance with Technical Specification 6.8.1.4. t Response: A review of the Action Statement Status tracking system for the period from January . 1,1994 to December 31,1994 indicated Technical Specification 3.3.3.9 was entered for more than 30 consecutive days during the reporting period. April 15 to September 8, both rate of change monitors were out of service due to the implementation of the new main plant computer (90DCR0001).

                    . May 10 to July 8, PCCW A train radiation monitor was out of service duo to PCCW train A outage (planned outage pins retubing effort).

I

i i l 1

      ....-,w    ,_   ,,        ,    .--              2.-_.                             ,                          1

APPENDIX D Radioactive G scous Efnuent Monitorina Instrumentation Reauirement: 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 that an explanation for the delay in correcting the inoperability be provided in the next Annual Efiluent Release Report in accordance with Technical Specification 6.8.1.4. Response: A review of the Action Statement Status tracking system archive indicated Technical Specification 3.3.3.10 was never entered for more than 30 consecutive days during the reporting period. 1 l l l i I

r-

APPENDIX E I.iauid Holdup 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 Specification 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. Response: There were no outside temporary tanks utilized for the storage of radioactive material during the reporting period. i

V y l l APPENDIX F Radwaste Treatment Systems l Requirement: 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 Report for the period in which the change was made. Response: There were no major changes made to Radwaste Treatment Systems during the reporting period. 1 I l l l 1 l

r APPENDIX G Unnlanned Releases Re31girement: Technical Specification 6,8.1.4 requires that the Annual Radioactive Effluent Release } i Report include a list and description of unplanned releases of radioactive materials in gaseous and liquid effluents made during the reporting period from the site to UNRESTRICTED AREAS. Response: There were no unplanned releases of radioactive materials from the site to UNRESTRICTED AREAS during the reporting period. I l

U I l l North Atlantic April 28,1995 1 l ENCLOSURE 2 TO NYN-95038 J i l l l 1 l l i l 1

(J

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I l I l 1 SEABROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 FT WIN 0 DATA STASILITY CLASS A CLASS FREQUENCY (PERCENT) = 1.87 WIND O!RECTION FROM SPEED (MPM) h NME NE ENE E ESE SE $$E S SSW SW WSW W WNW NW NNW VRSL 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 47 0 0 0 0 0 0 4 0 0 0 4 3 4 0 0 0 0 15 (1) .00 .00 .00 .00 .00 .00 2.47 .00 .00 .00 2.47 1.85 2.47 .00 .00 .00 .00 9.26 (2) .00 .00 .00 .00 .00 .00 .05 .00 .00 .00 .05 .03 .05 . 00 - .00 .00 .00 .17 l 8 12 1 . 0 1 0 2 5 ' 30 15 0 5 14 17 8- 7 ~3 0 0 108 (1) .62 .00 .62 .00 1.23 3.09 18.52 9.26 .00 3.09 8.64 10.49 4.94 4.32 1.85^ .00 .00 66.67 (2) .01 .00 .01 .00 .02 .06 .35 .17 .00 .06 .16 .20 .09 .08 .03 .00 .00 1.25 13 18 0 0 0 0 0 1 6 2 0 0 8 7 4 6 2 1 0 37 , (1) .00 .00 .00 .00 .00 .62 3.70 1.23 .00 .00 4.94 4.32 2.47 3.70 1.23 .62 .00 22.84 (2) .00 .00 .00 .00 .00 .01 .07 .02 .00 .00 .09 .08 .05 .07 .02 .01 .00 .43 19 24 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 .62 .62 .00 .00 .00 .00 .00 1.23-(2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .00 .00 .02 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 1 0 2 6 40 17 0 5 27 28 16 13 5 1 0 162

                      -(1)    .62    .00 .62    .00 1.23 3.70 24.69 10.49        .00 3.09 16.67 17.28 9.88 8.02 3.09            .62  .00 100.00 (2)    .01    .00 .01    .00    .02  .07    46    .20     .00   .06      .31    .32   .19   .15     .06  .01  .00     1.87 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIN 0 SPEED LESS THAN OR EQUAL TO .95 MPH)                                                                                       .
                                                                                                                                                           -s
                                                                                          .r...      ~     ,             .       .       --

n - -

f I 1 SEASROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 FT WIND DATA STABILITY CLASS 8 CLASS FREQUENCY (PERCENT) = 3.07 WIND DIRECTION FROM , l SPEED (MPM) N NNE NE ENE E ESE SE SSE $ SSW SW WSW W WNW NW NNW VR8L 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 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 47 0 1 0 1 0 0 7 1 0 4 5 4 6 2 1 0 0 32 (1) .00 .38 .00 .38 .00 .00 2.64 .38 .00 1.51 1.89 1,51 2.26 .75 .38 .00 .00 12.08 (2) .00 .01 .00 .01 .00 .00 .08 .01 .00 .05 .06 .05 .07 .02 .01 .00 .00 .37 8 12 3 0 1 10 2 6 18 9 6 13 13 19 20 15 8 0 0 143 (1) 1.13 .00 .38 3.77 .75 2.26 6.79 3.40 2.26 4.91 4.91 7.17 7.55 5.66 3.02 .00 .00 53.% (2) .03 .00 .01 .12 .02 .07 .21 .10 .07 .15 .15 .22 .23 .17 .09 .00 .00 1.65 13 18 0 0 0 2 2 2 0 0 1 2 13 12 12 16 19 1 0 82 (1) .00 .00 .00 .75 .75 .75 .00 .00 .38 .75 4.91 4.53 4.53 6.04 7.17 .38 .00 30.94 (2) .00 .00 .00 .02 .02 .02 .00 .00 .01 .02 .15 .14 .14 .19 .22 .01 .00 .95 19-24 0 0 0 0 0 0 0 0 0 0 0 0 1 4 3 0- 0 8 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .38 1.51 1.13 .00 .00 3.02 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .05 .03 .00 .00 .09 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 3 1 1 13 4 8 25 10 7 19 31 35 39 37 31 1 0 265 (1) 1.13 .38 .38 4.91 1.51 3.02 9.43 3.77 2.64 7.17 11.70 13.21 14.72 13. % 11.70 .38 .00 100.00 (2) .03 .01 .01 .15 .05 .09 .29 .12 .08 .22 .36 .41 .45 .43 .36 .01 .00 3.07 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)sPERCENT OF ALL COCO 06SERVAfl0NS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) i l I l l

I

                                                           .c SEASROOK JAN94 DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 FT WIND DATA          STABILITY CLASS C                    CLASS FREQUENCY (PERCENT) =   4.80 WIND DIRECTION FROM SPEED (MPH)       N NNE      NE ENE        E ESE        SE SSE           S SSW      SW WSW       W WWW    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       0   0     0      0      0       1        1     1     1     0     0     0     0   1    0      0        5 (1)    .00   .00   .00  .00    .00    .00     .24      .24   .24    .24  .00   .00   .00   .00  .24  .00   .00   1.20 (2)    .00   .00   .00  .00    .00    .00     .01      .01   .01    .01  .00   .00   .00   .00  .01  .00   .00    .06 47       4       1   1     0      3      3       7        3     5     4     7    12   16      8   5    2      0     81 (1)    .%    .24   .24  .00    .72    .72 1.69         .72 1.20     .% 1.69 2.89 3.86 1.93 1.20      .48   .00  19.52 (2)    .05   .01   .01  .00    .03    .03     .08      .03   .06    .05  .08   .14   .19    .09 .06  .02   .00    .94 8-12      2       2   3     9     15     12      16        9     4     2    26    22   22     40  25    4      0   213 (1)     48    48   .72 2.17 3.61 2.89 3.86 2.17              .96     48 6.27 5.30 5.30 9.64 6.02     .%    .00  51.33 (2)    .02   .02   .03  .10    .17    .14     .19      .10   .05    .02  .30   .25   .25     46 .29  .05   .00   2.46 13 18      0       0   5     1      0      1       0        0     1     1    11    12   13     32  23    2      0   102 (1)    .00   .00 1.20   .24    .00    .24     .00      .00   .24    .24 2.65 2.89 3.13 7.71 5.54     .48   .00  24.58 (2)    .00   .00   .06  .01    .00    .01     .00      .00   .01    .01  .13   .14   .15    .37 .27  .02   .00   1.18 19-24      0       0   0     0      0      0       0        0     0      1    0     1     1     7   4    0      0     14 (1)    .00   .00   .00  .00    .00    .00     .00      .00   .00    .24  .00   .24   .24 1.69   .96  .00   .00   3.37 (2)    .00   .00   .00  .00    .00    .00     .00      .00   .00    .01  .00   .01   .01    .08 .05  .00   .00     .16                 )

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 l ALL SPEEDS 6 3 9 10 18 16 24 13 11 9 44 47 52 87 58 8 0 415 (1) 1.45 .72 2.17 2.41 4.34 3.86 5.78 3.13 2.65 2.1710.6011.3312.53 20.M 13,98 1.93 .0C 100.00 (2) .07 .03 .10 .12 .21 .19 .28 .15 .13 .10 .51 .54 .60 1.01 .67 .09 .00 4.80 l l l (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THit PAGE (2)sPERCENT OF ALL C000 08 SERVAT 10NS FOR THis PERIOD l C= CALM (WINO SPEED LESS THAN OR EQUAL To .95 MPH) i l

. . ~ ,, l l I l

l

l SEAS 400K JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) l l 43.0 FT WINO DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 47.38 l WIND DIRECTION FROM l I SPEED (MPM) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWW WW NNW VRBL TOTAL CALM 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 (1) .00 .02 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 (2) .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 C-3 13 22 8 12 8 5 3 10 11 13 8 10 28 23 20 20 0 214 (1) .32 .54 .20 .29 .20 .12 .07 .24 .27 .32 .20 .24 .68 .56 .49 .49 .00 5.23 (2) .15 .25 .09 .14 .09 .06 .03 .12 .13 .15 .09 .12 .32 .27 .23 .23 .00 2.48 47 113 54 52 76 113 66 74 76 67 66 105 113 160 118 151 141 0 1545 (1) 2.76 1.32 1.27 1.86 2.76 1.61 1.81 1.86 1.64 1.61 2.56 2.76 3.91 2.88 3.69 3.44 .00 37.74 (2) 1.31 .62 .60 .88 1.31 .76 .86 .88 .78 .76 1.22 1.31 1.85 1.37 1.75 1.63 .00 17.88 , I 8 12 108 43 44 119 100 56 50 32 23 99 191 147 133 229 184 69 0 1627 (1) 2.64 1.05 1.07 2.91 2.44 1.37 1.22 .78 .56 2.42 4.67 3.59 3.25 5.59 4.49 1.69 .00 39.74 (2) 1.25 .50 .51 1.38 1.16 .65 .58 .37 .27 1.15 2.21 1.70 1.54 2.65 2.13 .80 .00 18.83 13 18 6 15 32 20 10 1 2 0 4 27 49 35 50 201 137 10 0 599 (1) .15 .37 .78 49 .24 .02 .05 .00 .10 .66 1.20 .85 1.22 4.91 3.35 .24 .00 14.63 (2) .07 .17 .37 .23 .12 .01 .02 .00 .05 .31 .57 .41 .58 2.33 1.59 .12 .00 6.93 19 24 0 3 9 10 4 8 0 0 0 2 0 0 1 35 29 0 0 101 (1) .00 .07 .22 .24 .10 .20 .00 .00 .00 .05 .00 .00 .02 .85 .71 .00 .00 2.47 (2) .00 .03 .10 .12 .05 .09 .00 .00 .00 .02 .00 .00 .01 .41 .34 .00 .00 1.17 GT 24 0 0 2 1 0 0 0 0 0 0 0 0 0 4 0 0 0' 7 (1) .00 .00 .05 .02 .00 .00 .00 .00 .00 .00 .00 .00 .00 .10 .00 .00 .00 .17 (2) .00 .00 .02 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .00 .00 .08 ALL SPEEDS 240' 138 147 238 235 136 129 118 105 207 353 305 3 72 610 521 240 0 4094 (1) 5.86 3.37 3.59 5.81 5.74 3.32 3.15 2.88 2.56 5.06 8.62 7.45 9.09 14.90 12.73 5.86 .00 100.00 (2) 2.78 1.60 1.70 2.75 2.72 1.57 1.49 1.37 1.22 2.40 4.09 3.53 4.31 7.06 6.03 2.78 .00 47.38 (1)aPERCENT OF ALL G000 OBSERVATIONS FOR THIS PAGE (2)sPERCENT OF ALL GOOD 08SERVAfl0NS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

SEABR000: JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 28.56 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 1 0 1 0 0 0 1 0 0 0 2 0 1 0 0 0 6 (1) .00 .04 .00 .04 .00 .00 .00 .04 .00 .00 .00 .08 .00 .04 .00 .00 .00 .24 (2) .00 .01 .00 .01 .00 .00 .00 .01 .00 .00 .00 .02 .00 .01 .00 .00 .00 .07 C-3 25 13 24 27 26 10 13 8 24 24 42 35 67 45 48 22 0 453 (1) 1.01 .53 .97 1.09 1.05 .41 .53 .32 .97 .97 1.70 1.42 2.71 1.82 1.94 .89 .00 18.35 (2) .29 .15 .28 .31 .30 .12 .15 .09 .28 .28 49 .41 .78 .52 .56 .25 .00 5.24 47 31 16 36 40 47 17 27 42 42 77 138 290 227 1 95 120 50 0 1395 (1) 1.26 .65 1.46 1.62 1.90 .69 1.09 1.70 1.70 3.12 5.59 11.75 9.20 7.90 4.86 2.03 .00 56.52 (2) .36 .19 42 46 .54 .20 .31 .49 .49 .89 1.60 3.36 2.63 2.26 1,39 .58 . 00 - 16.14 8-12 12 3 18 9 14 6 7 10 6 18 103 131 71 1 04 - 27 14 0 553 (1) .49 .12 .73 .36 .57 .24 .28 41 .24 .73 4.17 5.31 2.88 4.21 1.09 .57 .00 22.41 ) (2) .14 .03 .21 .10 .16 .07 ' .08 .12 .07 .Z1 1.19 1.52 .82 1.20 .31 .16 .00 6.40 13 18 0 9 4 4 2 2 0 0 7 1 4 2 4 9 5 0 0 53 (1) .00 .36 .16 .16 .08 .08 .00 .00 .28 .04 .16 .08 .16 .36 .20 .00 .00 2.15 (2) .00 .10 .05 .05 .02 .02 .00 .00 .08 .01 .05 .02 .05 .10 .06 .00 .00 .61 19-24 0 2 1 0 0 1 0 0 0 0 0 0 0 0 0 0 0 4 (1) .00 .08 .04 .00 .00 .04 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .16 (2) .00 .02 .01 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 GT 24 0 0 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 (1) 00 .00 .16 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .16 (2) .00 .00 .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 ALL SPEEDS 68 44 87 81 89 36 47 61 79 120 287 460 369 354 200 86 0 2468 l (1) 2.76 1.78 3.53 3.28 3.61 1.46 1.90 2.47 3.20 4.86 11.63 18.64 14.95 14.34 8.10 3.48 .00 100.00 (2) .79 .51 1.01 .94 1.03 .42 .54 .71 .91 1.39 3.32 5.32 4.27 4.10 2.31 1.00 .00 28.56 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR TH!$ PAGE (3)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD I C= CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH)

      - 4 4

I 5 f I SEASROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 7.65 WINO DIRECTION FROM SPEED (MPN)- N NNE NE ENE E EEE SE SSE S SSW SW WSW W WNW NW NNW VRSL TOTAL ; CALM 1 0 0 0 0 0 0 0 1 0 1 1 0 0 0 1 0 5 (1) .15 .00 .00 .00 .00 .00 .00 .00 .15 .00 .15 .15 .00 .00 .00 .15 .00 .76 (2) .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01- .01 .00 .00 .00 .01 .00 .06 4 6 18 55 0 295 i C-3 9 5 9 10 15 3 8 24 31 61 23 ' 14 (1) 1.36 .76 1.36 1.51 2.27 .61 .91 .45 1.21 2.72 3.63 4.69 8.32 9.23 3.48 2.12 .00 . 44.63 (2) .10 .06 .10 .12 .17 .05 .07 .03 .09 .21 .28 .36 .64 .71 .27 .16 .00 3.41 i 47 4 1 0 6 12 4 3 1 6 14 34- 77 68 53 47 11 0 341 (1) .61 .15 .00 .91 1.82 .61 45 .15 .91 2.12 5.14 11.65 10.29 8.02 7.11 1.66 .00 51.59 (2) .05 .01 .00 .07 .14 .05 .03 .01 .07 .16 .39 .89 .79 .61 .54 .13 .00 3.95 , 8 12 0 0 0 0 5 2 2 0 0 0 0 3 1 0 2 2 0 17 (1) .00 .00 .00 .00 .76 .30 .30 .00 .00 .00 .00 .45 .15 .00 .30 .30 - .00 2.57 (2) .00 .00 .00 .00 .06 .02 .02 .00- .00 .00 .00 .03 .01 .00 .02 .02 .00 .20 1 1 13 18 0 0 0 0 0 0 0 0 0' 1 0 0 0 0 1 1 0 3 /

                      -(1)         .00   .00  .00           .00   .00    .00       .00     .00    .00       .15    .00     .00                  .00     .00           .15    .15    .00             .45 (2)      .00   .00   .00          .00   .00 - .00        .00     .00    .00       .01    .00     .00                  .00     .00           .01    .01    .00             .03 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            14    6     9            16     32    10-       11      4     15               59 112 124 114                                      73     29          0       661 (1)     2.12   .91 1.36 2.42 4.84 1.51 1.66                      .61 2.27 4.99     33 ~ 8.93 16.94 18.76 17.25 11.04                                       .004.39    100.00 (2)      .16   .07   .10          .19   .37    .12       .13     .05    .17       .38    .68 1.30 1.44 1.32                                  .84    .34    .00          7.65 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 4-                                                                                                                                                                                                         ;

1-A 4

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r k SEAEROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 6.67 WIND DIRECTION FROM SPEED (MPN) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWW NW NNW VRBL TOTAL CALM 0 0 0 1 0 1 1 0 0 0 1 0 1 0 0 0 0 5 (1) .00 .00 .00 .17 .00 .17 .17 .00 .00 .00 .17 .00 .17 .00 .00 .00 .00 .87 (2) .00 .00 .00 .01 .00 .01 .01 .00 .00 .00 .01 .00 .01 .00 .00 .00 .00 .06 C-3 5 5 8 9 7 2 1 2 2 8 27 69 124 88 43 7 0 407 (1) .87 .87 1.39 1.56 1.22 .35 .17 .35 .35 1.39 4.69 11.98 21.53 15.28 7.47 1.22 .00 70.66 (2) .06 .06 .09 .10 .08 .02 .01 .02 .02 .09 .31 .80 1.44 1.02 .50 .08 .00 4.71 4-7 2 0 0 0 2 0 1 0 0 2 8 22 26 52 41 4. 0 160 (1) .35 .00 .00 .00 .35 .00 .17 .00 .00 .35 1.39 3.82 4.51 9.03 7.12 .69 .00 27.78 (2) .02 .00 .00 .00 .02 .00 .01 .00 .00 .02 .09 .25 .30 .60 .47 .05 .00 1.85 8 12 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .17 .00 .00 - .00 .00 .00 00 .00 .00 .17 (2) .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .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 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 2 (1) .17 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .17 .00 .35 (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .02 GT 24 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 (1) .17 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .17 (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 ALL SPEEDS 9 5 8 10 9 3 3 2 3 10 36 91 151 140 84 12 0 576 (1) 1.56 .87 1.39 1.74 1.56 .52 .52 .35 .52 1.74 6.25 15.80 26.22 24.31 14.58 2.08 .00 100.00 (2) .10 .06 .09 .12 .10 .03 .03 .02 .03 .12 .42 1.05 1.75 1.62 .97 .14 .00 6.67 (1)= PERCENT OF ALL GOOO OBSERVATIONS FOR THIS PAGE (?)= PERCENT OF ALL 0000 OSSERVATIONS FOR THIS PER!a0 C= CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPM) 1 l l l I l i l j i i

SEA 8 ROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 43.0 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 WWW NW NNW VRBL TOTAL CALM 1 2 0 2 0 1 1 1 1 0 2 3 1 1 0 1 0 17 (1) .01 .02 .00 .02 .00 .01 .01 .01 .01 .00 .02 .03 .01 .01 .00 .01 .00 .20 (2) .01 .02 .00 .02 .00 .01 .01 .01 .01 .00 .02 .03 .01 .01 .00 .01 .00 .20 C3 52 45 49 58 56 21 24 24 46 64 101 145 274 217 135 63 0 1374 (1) .60 .52 .57 .67 .65 .24 .28 .28 .53 .74 1.17 1.68 3.17 2.51 1.56 .73 .00 15.90 (2) .60 .52 .57 .67 .65 .24 .28 .28 .53 .74 1.17 1.68 3.17 2.51 1.56 .73 .00 15.90 47 154 73 89 123 177 90 123 123 120 167 301 521 507 428 365 208 0 3569 (1) 1.78 .84 1.03 1.42 2.05 1.04 1.42 1.42 1.39 1.93 3.48 6.03 5.87 4.95 4.22 2.41 00 41.30 (2) 1.78 .84 1.03 1.42 2.05 1.04 1.42 1.42 1.39 1.93 3.48 6.03 5.87 4.95 4.22 2.41 .00 41.30 8 12 126 48 67 147 138 87 123 75 40 137 347 339 255 395 249 89 0 2662 (1) 1.46 .56 .78 1.70 1.60 1.01 1.42 .87 .46 1.59 4.02 3.92 2.95 4.57 2.88 1.03 .00 30.81 (2) 1.46 .56 .78 1.70 1.60 1.01 1.42 .87 46 1.59 4.02 3.92 2.95 4.57 2.88 1.03 .00 30.81 13 18 6 24 41 27 14 7 8 2 13 32 85 68 83 264 187 15 0 876 (1) .07 .28 .47 .31 .16 .08 .09 .02 .15 .37 .98 .79 .% 3.06 2.16 .17 .00 10.14 (2) .07 .28 .47 .31 .16 .08 .09 .02 .15 .37 .98 .79 .96 3.06 2.16 .17 .00 10.14 19-24 1 5 10 10 4 9 0 0 0 3 1 2 3 46 36 1 0 131 (1) .01 .06 .12 .12 .05 .10 .00 .00 .00 .03 .01 02 .03 .53 42 .01 .00 1.52 (2) .01 .06 .12 .12 .05 .10 .00 .00 .00 .03 .01 .02 .03 .53 .42 .01 .00 1.52 l GT 24 1 0 6 1 0 0 0 0 0 0 0 0 0 4 0 0 0 12 l (1) .01 .00 .07 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .00 .00 .14 l (2) .01 .00 .07 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .00 .00 .14 ALL SPEEDS 341 197 262 368 389 215 279 225 220 403 837 1078 1123 1355 9 72 377 0 8641 (1) 3.95 2.28 3.03 4.26 4.50 2.49 3.23 2.60 2.55 4.66 9.69 12.48 13.00 15.68 11.25 4.36 .00 100.00 (2) 3.95 2.28 3.03 4.26 4.50 2.49 3.23 2.60 2.55 4.66 9.69 12.48 13.00 15.68 11.25 4.36 .00 100.00 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE l (2)= PERCENT OF ALL C000 06SERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

l 1 l J I ( I i SEASR00K JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210 F00T TOWER) 209.0 FT WIND DATA STA81LITY CLASS A CLASS FREQUENCY (PERCENT) = 1.88 r WIND DIRECTION FROM SPEED (MPM) N NME NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VR8L 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 .0C .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 47 0 0 0 0 0 0 2 0 0 0 2 1 0 0 0 0 0 5 (1) .00 .00 00 .00 .00 .00 1.23 .00 .00 .00 1.23 .62 .00 .00 .00 .00 .00 3.09 (2) .00 .00 .00 .00 .00 .00 .02 .00 .00 .00 .02 .01 .00 .00 .00 .00 .00 .06 8-12 .2 0 0 0 2 1 21 3 0 1 4 to 6 2 1 0 'O - 53 (1) 1.23 .00 .00 .00 1.23 .62 12.% 1.85 .00 .62 2.47 6.17 3.70 1.23 .62 .00 .00 32.72 (2) .02 .00 .00 .00 .D2 .01 .24 .03 .00 .01 .05 .12 .07 .02 .01 .00 .00 .61 13 18 0 1 0 0 0 4 17 10 0 4 16 12 9 9 2 0 0 84 (1) .00 .62 .00 .00 .00 2.47 10.49 6.17 .00 2.47 9.88 7.41 5.56 5.56 1.23 .00 .00 51.85 (2) .00 .01 .00 .00 .00 .05 .20 .12 .00 .05 .19 .14 .10 .10 - .02 .00 .00 .97 19-24 0 0 0 0 0 0 3 2 0 0 5 4 2 2 2 0 0 20 i (1) .00 .00 .00 .00 .00 .00 1.85 1.23 .00 .00 3.09 2.47 1.23 1.23 1.23 .00 .00 12.35 (2) .00 .00 .00 .00 .00 .00 .03 .02 .00 .00 .06 .05 .02 .02 .02 .00 .00 .23 , CT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 f (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 2 1 0 0 2 5 43 15 0 5 27 27 17 13 5 0 0 162 (1) 1.23 .62 .00 .00 1.23 3.09 26.54 9.26 .00 3.09 16.67 16.67 10.49 - 8.02 3.09 .00 .00 100.00 (2) .02 .01 .00 .00 .02 .06 .50 .17 .00 .06 .31 .31 .20 .15 .06 .00 .00 1.88 (1)= PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PAGE (2)= PERCENT or ALL 000D OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 1 l v w - , - - - , w- 3 w

s. 1 SEA 8R00K JAN94 0EC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210 F00T TOWER) 209.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = 3.07 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE $ 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 C3 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 1 0 0- 4 2 4 5 0 0 0 0 . 16 (1) .00 .00 .00 .00 .00 .00 .38 .00 .00 1.51 .75 1.51 1.89 .00 .00 .00 .00 6.04 (2) .00 00 .00 .00 .00 .00 .01 .00 .00 .05 .02 .05 .06 .00 .00 .00 .00 .19 8 12 1 1 1 7 1 4 17 11 3 9 9 12 to 7 2 0 0 95 (1) .38 .38 .38 2.64 .38 1.51 6.42 4.15 1.13 3.40 3.40 4.53 3.77 2.64 .75 .00 .00 35.85 (2) .01 .01 .01 .08 .01 .05 .20 .13 .03 .10 .10 .14 .12 .08 .02 .00 .00 1.10 13-18 2 0 1 5 4 2 3 5 3 7 16 12 15 21 17 1 0 114 (1) .75 .00 .38 1.89 1.51 .75 1.13 1.89 1.13 2.64 6.04 4.53 5.66 7.92 6.42 .38 .00 43.02 l (2) .02 .00 .01 .06 .05 .02 .03 .06 .03 .08 .19 .14 .17 .24 .20 .01 .00 1.32 19-24 0 0 0 0 0 0 0 0 0 0 7 7 7 7 4 0 0 32 { (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 2.64 2.64 2.64 2.64 1.51 .00 .00 12.08 i (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .08 .08 .08 .08 .05 .00 .00 .37 ! GT 24 0 0 0 0 0 0 0 0 0 0 0 0 1 3 4 0 0 8 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .38 1.13 1.51 .00 .00 3.02 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .01 .03 .05 .00 .30 .09 ALL SPEEDS 3 1 2 12 5 6 21 16 6 20 34 35 38 38 27 1 0 265 1 (1) 1.13 .38 .75 4.53 1.89 2.26 7.92 6.04 2.26 7.55 12.83 13.21 14.34 14.34 10.19 .38 .00 100.00 (2) .03 .01 .02 .14 .06 .07 .24 .19 .07 .23 .39 .41 .44 44 .31 .01 .00 3.07 l (1)= PERCENT OF ALL GOOD 06SERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PERIOD , C= CALM (WINO SPEED LESS THAN OR EQUAL TO .95 MPH) j l l

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

t SEASROOK JAN94 DEC94 MET DATA JolNT FREQUENCY 0!$TRIBUTION (210-F00T TCMER) 209.0 FT WINO DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 4.80 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE $$E S $$W SW WSW W WNW NW NNW VR8L 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 0 0 0 0 2 0 0 0 1 0 0 0 1 0 1 0 5 (1) .00 .00 00 .00 .00 48 .00 .00 .00 .24 .00 . 00 .00 .24 .00 .24 .00 1.20 (2) .00 .00 .00 .00 .00 .02 .00 .00 .00 .01 .00 . 00 .00 .01 .00 .01 .00 .06 4-7 1 0 1 0 2 2 0 2 1 2 7 8 7 2 0 2 0 37 (1) .24 .00 .24 .00 .48 48 .00 .48 .24' 48 1.69 1.93 1.69 .48 .00 48 .00 8.92 (2) .01 .00 .01 .00 .02 .02 .00 .02 .01 .02 .08 . 09 .08 .02 .00 .02 .00 .43 8 12 2 2 3 7 12 12 11 16 4 0 17 11 24 19 8 4 0 152 (1) .48 48 .72 1.69 2.89 2.89 2.65 3.86 .96 .00 4.10 2.65 5.78 4.58 1.93 .96 .00 36.63 (2) .02 .02 .03 .08 .14 .14 .13 .19 .05 .00 .20 . 13 .28 .22 .09 .05 .00 1.76 13 18 2 2 6 3 3 1 5 3 3 2 18 14 17 45 27 1 0 152 (1) .48 .48 1.45 .72 .72 .24 1.20 .72 .72 48 4.34 3.37 4.10 10.84 6.51 .24 .00 36.63 (2) .02 .02 .07 .03 .03 .01 .06 .03 .03 .02 .21 . 16 .20 .52 .31 .01 .00 1.76 19 24 0 0 0- 0 0 0 0 0 0 2 7 10 7 18 9 1 0 54 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .48 1.69. 2.41 1.69 4.34 2.17 .24 .00 13.01 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .08 . 12 .08 .21 .10 .01 .00 .63 GT 24 0 0 0 0 0 0 0 0 0 1 ~0 1 1 7 5 0 0 15 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .24 .00 . 24 ..24 1.69 1.20 .00 .00 3.61 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 . 01 .01 .08 .06 .00 .00 .17 ALL SPEEDS 5 4 10 10 17 17 16 21 8 8 49 44 56 92 49 9 0 415 (1) 1.20 .96 2.41 2.41 4.10 4.10 3.86.5.06 1.93 1.93 11.81 10.60 13.49 22.17 11.81 2.17 .00 100.00 (2) .06 .05 .12 .12 .20 .20 .19 .24 .09 .09 .57 . 51 .65 1.07 .57 .10 . 00 . 4.80 (1)= PERCENT OF ALL GOOD 06SERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH) l v a V wrww- ,m - - 'y

[ ] I . .. SEAS 400K JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 209.0 FT WINO DATA STA81LITY CLASS 0 CLASS FREQUENCY (PERCENT) = 47.40 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S $$W SW WSW W WNW NW NNW VR8L TOTAL CALN 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 12 8 10 4 6 5 7 5 9 3 5 4 11 10 13 11 0 123 (1) .29 .20 .24 .10 .15 .12 .17 .12 .22 .07 .12 .10 .27 .24 .32 .27 .00 3.00 (2) .14 .09 .12 .05 .07 .06 .08 .06 .10 .03 .06 .05 .13 .12 .15 .13 .00 1.42 4-7 70 44 33 50 68 71 50 40 46 27 40 47 67 56 70 66 0 845 (1) 1.71 1.07 .81 1.22 1.66 1.73 1.22 .98 1.12 .66 .98 1.15 1.64 1.37 1.71 1.61 .00 20.64 (2) .81 .51 .38 .58 .79 .82 .58 .46 .53 .31 46 .54 .78 .65 .81 .76 .00 9. 78 8 12 136 53 58 104 78 63 61 67 42 74 136 til 126 135 125 85 0 1454 (1) 3.32 1.29 1.42 2.54 1.91 1.54 1.49 1.64 1.03 1.81 3.32 2.71 3.08 3.30 3.05 2.08 .00 35.52 (2) 1.57 .61 .67 1.20 .90 .73 .71 .78 .49 .86 1.57 1.29 1.46 1.56 1.45 .98 .00 16.83 13 18 90 42 32 34 12 7 16 20 14 84 1 75 87 127 213 1 72 28 0 1153 (1) 2.20 1.03 .78 .83 .29 .17 .59 .49 .34 2.05 4.27 2.13 3.10 5.20 4.20 .68 .00 28.16 (2) 1.04 49 .37 .39 .14 .08 .19 .23 .16 .97 2.03 1.01 1.47 2.47 1.99 .32 .00 13.35 , i 19 24 10 16 19 12 8 0 1 4 1 14 24 21 44 142 77 2 0 395 l (1) .24 .39 .46 .29 .20 .00 .02 .10 .02 .34 .59 .51 1.07 3.47 1.88 .05 .00 9.65 (2) .12 .19 .22 .14 .09 .00 .01 .05 .01 .16 .28 .24 .51 1.64 .89 .02 .00 4.57 GT 24 0 10 11 7 1 9 0 0 0 2 0 0 8 46 29 1 0 124 (1) .00 .24 .27 .17 .02 .22 .00 .00 .00 .05 .00 .00 .20 1.12 .71 .02 .00 3.03 i (2) .00 .12 .13 .08 .01 .10 .00 .00 .00 .02 .00 .00 .09 .53 .34 .01 .00 1.44 ' l 4LL SPEEDS 318 1 73 163 211 173 155 135 136 112 204 380 2 70 383 602 486 193 0 4094 i (1) 7.77 4.23 3.98 5.15 4.23 3.79 3.30 3.32 2.74 4.98 9.28 6.60 9.36 14.70 11.87 4.71 .00 100.00 I (2) 3.68 2.00 1.89 2.44 2.00 1.79 1.56 1.57 1.30 2.36 4.40 3.13 4.43 6.97 5.63 2.23 .00 47.40 (1)aPERCENT OF ALL C000 OSSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PERIOD i C= CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH) l l 1 1 1

F~L l SEA 8R00C JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210 F00T TOWER) 209.0 FT VINO DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 28.53 WIND DIRECTION FROM I SPEE0(MPN) N NNE NE ENE E ESE SE SSE $ SSW SW WSW W WWW NW NNW VRSL -TOTAL CALM 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 2 (1) .00 .04 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .00 .08 (2) . C.0 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .02 C-3 7 8 9 6 5 7 6 5 8 3 11 6 4 4 3 7 0 99 (1) .28 .32 .37 .24 .20 .28 .24 .20 .32 .12 .45 .24 .16 .16 .12 .28 .00 4.02 (2) .08 .09 .10 .07 .06 .08 .07 .06 .09 .03 .13 .07 .05 .05 .03 .08 .00 1.15 4-7 34 21 29 32 24 37 32 17 21 22 29 32 27 35 32 19 0 443 (1) 1.38 .85 1.18 1.30 .97 1.50 1.30 .69 .85 .89 1.18 1.30 1.10 1.42 1.30 .77 .00 17.98 (2) .39 .24 .34 .37 .28 .43 .37 .20 .24 .25 .34 .37 .31 .41 .37 .22 .00 5.13 8-12 50 25 22 20 12 12 24 33 52 76 156 174 146 153 114 40 0 1109 - (1) 2.03 1.01 .89 .81 .49 .49 .97 1.34 2.11 3.08 6.33 7.06 5.93 6.21 4.63 1.62 .00 45.01 (2) .58 .29 .25 .23 .14 .14 .28 .38 .60 .88 1.81 2.01 1.69 1.77 1.32 .46 .00 12.84 13-18 30 8 9 9 2 1 2 13 9 18 146 153 120 1 72 39 12 0 743 (1) 1.22 .32 .37 .37 .08 .04 .08 .53 .37 .73 5.93 6.21 4.87 6.98 1.58 .49 .00 30.15 (2) .35 .09 .10 .10 .02 .01 .02 .15 .10 .21 1.69 1.77 1.39 1.99 .45 .14 .00 8.60 19 24 0 3 2 0 0 3 0 1 8 2 6 4 7 13 5 0 0 54 (1) .00 .12 .08 .00 .00 .12 .00 .04 .32 .08 .24 .16 .28 .53 .20 .00 .00 2.19 (2) .00 .03 .02 .00 .00 .03 .00 .01 .09 .02 .07 .00 .08 .15 .06 .00 .00 .63 GT 24 0 8 4 0 0 1 0 0 0 0 0 0 0 1 0 0 0 14 (1) .00 .32 .16 .00 .00 .04 .00 .00 .00 .00 .00 .00 .00 .04 .00 .00 .00 .57 (2) .00 .09 .05 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .16 ALL SPEEDS 121 74 75 67 43 61 64 69 98 121 348 369 304 378 193 79 0 2464 (1) 4.91 3.00 3.04 2.72 1.75 2.48 2.60 2.80 3.98 4.91 14.12 14.98 12.34 15.34 7.83 3.21 .00 100.00 (2) 1.40 .86 .87 .78 .50 .71 .74 .80 1.13 1.40 4.03 4.27 3.52 4.38 2.23 .91 .00 28.53 (1) PERCENT OF ALL GOOO OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL G000 OBSERVATIONS FOR THIS PERICO Ca CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPH) i l l l l l l

SEA 8400K JAN94 0EC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F00T TOWER) 209.0 FT WINO DATA STA8!LITY CLASS F CLASS FREQUENCY (PERCENT) = 7.65 WIko O!RECTION FROM SPEED (MPM) N NNE NE ENE E ESE SE SSE $ SSW SW WSW W WNW NW NNW VRSL 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 1 2 4 0 2 1 2 2 0 0 1 3 1 2 4 3 0 28 (1) .15 .30 .61 .00 .30 .15 .30 .30 .00 .00 .15 .45 .15 .30 .61 .45 .00 4.24 (2) .01 .02 .05 .00 .02 .01 .02 .02 .00 .00 .01 .03 .01 .02 .05 .03 .00 .32 47 7 4 12 3 6 5 6 14 16 13 19 11 8 9 4 3 0 140 (1) 1.06 .61 1.82 .45 .91 .76 .91 2.12 2.42 1.97 2.87 1.66 1.21 1.36 .61 .45 .00 21.18 (2) .D8 .05 .14 .03 .07 .06 .07 .16 .19 .15 .22 .13 .09 .10 .05 .03 .00 1.62 8-12 21 7 6 3 4 2 4 7 14 20 47 56 50 54 50 22 0 367 (1) 3.18 1.06 .91 45 .61 .30 .61 1.06 2.12 3.03 7.11 8.47 7.56 8.17 7.56 3.33 .00 55.52 (2) .24 .08 .07 .03 .05 .02 .05 .08 .16 .23 .54 .65 .58 .63 .58 .25 .00 4.25 13 18 11 4 2 0 0 0 0 1 0 6 14 24 21 17 19 5 0 124 (1) 1.66 .61 .30 .00 .00 .00 .00 .15 .00 .91 2.12 3.63 3.18 2.57 2.87 .76 .00 18.76 (2) .13 .05 .02 .00 .00 .00 .00 .01 .00 .07 .16 .28 .24 .20 .22 .06 .00 1.44 19 24 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .15 .00 .00 .00 .15 .00 .30 (2) .00 .00 .00 .00 .00 .00 .00 .00 ' .00 .00 .00 .01 .00 .00 .00 .01 .00 .02 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 40 17 24 6 12 8 12 24 30 39 81 95 80 82 77 34 0 661 (1) 6.05 2.57 3.63 .91 1.82 1.21 1.82 3.63 4.54 5.90 12.25 14.37 12.10 12.41 11.65 5.14 .00 100.00 (2) .46 .20 .28 .07 .14 .09 .14 .28 .35 .45 .94 1.10 .93 .95 .89 .39 .00 7.65 (1)* PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD 08SERVAfl0NS FOR THIS PERIOD Cs CALM (WIND SPEED LESS THAN OR EQUAL To .95 MPM)

'd l 1 i SEABROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210 F00T TOWER) 209.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 6.67 WIND DIRECTION FROM . 1 SPEED (MPN) N NNE NE ENE E ESE SE SSE S $$W SW WSW W WWW NW NNW VR8L TOTAL l 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 5 1 0 3 0 0 1 2 5 3 4 4 4 3 4 3 0 42 (1) .87 .17 .00 .52 .00 .00 .17 .35 .87 .52 .69 69 .69 .52 .69 .52 .00 7.29 (2) .06 .01 .00 .03 .00 .00 .01 .02 .06 .03 .05 .05 .05 .03 .05 .03 .00 49 47 16 4 4 5 3 0 5 3 22 16 15 17 26 17 18 9 0 180 (1) 2.78 .69 .69 .87 .52 .00 .87 .52 3.82 2.78 2.60 2.95 4.51 2.95 3.13 1.56 .00 31.25 (2) .19 .05 .05 .06 .03 .00 .06 .03 .25 .19 .17 .20 .30 .20 .21 .10 .00 2.08 4 7 19 35 31 46 37 33 25 0 2 72 i 8-12 20 9 3 0 1 1 1 (1) 3.47 1.56 .52 .00 .17 .17 .17 .69 1.22 3.30 6.08 5.38 7.99 6.42 5.73 4.34 .00 47.22 l

                              .10        .00         .01    .01    .05    .08   .22    41  .36   .53   .43  .38  .29  .00     3.15   j (2)    .23        .03         .01 13 18       10     1   0     1      0     0     0      0       0     5    3     6     9    11  15    17    0       78 (1)   1.74   .17  .00   .17   .00   .00    .00    .00    .00   .87  .52 1.04 1.56 1.91 2.60 2.95     .00    13.54 (2)    .12   .01  .00   .01   .00   .00    .00    .00    .00   .06  .03   .07     10   .13 .17  .20  .00       90 19 24        1     0   0     0      0     0     0      0       1     0    0     0     0     0    0    0    0        2 (1)    .17   .00  .00   .00   .00   .00    .00    .00    .17   .00  .00   .00   .00    .00 .00  .00   .00     .35 (2)    .01   .00  .00   .00   .00   .00    .00    .00    .01   .00  .00   .00   .00    .00 .00   .00  .00     .02 OT 24        1     0   0     0      0     0     0       0      0     0    0     0     0     0    0    1    0        2 (1)    .17   .00  .00   .00   .00    .00   .00    .00     .00  .00  .00   .00   .00    .00 .00  .17   .00     .35 (2)    .01   .00  .00   .00   .00     00   .00    .00     .00   .00  .00   .00  .00    .00 .00   .01  .00     .02 ALL SPEEDS       53     15   7     9      4     1     7      9      35    43   57    58    85    68   70   55    0     576 (1)   9.20 2.60 1.22 1.56      .69   .17 1.22

56 6.08 7.47 9.90 10.07 14.76 11.81 12.15 9.55 .00 100.00 (2) .61 .17 .08 .10 .05 .01 .08 .i; .41 .50 .66 .67 .98 .79 .81 .64 .00 6.67 (1)=PERCCNT OF ALL 0000 OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL 0000 OBSERVATIONS FOR THIS PERIOD C= CALM (WINO SPEED LESS THAN OR EQUAL To .95 MPH)

I

y SEASROOK JAN94-DEC94 MET DATA JOINT FREQUENCY DISTRIBUTION (210-F007 TOWER) 209.0 FT WINO DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WINO DIRECTION FROM

      $ PEED (MPH)        N NNE     NE ENE        E ESE       SE $$E         S SSW      SW WSW      W WWW      NW NNW VR8L TOTAL CALM        0      1    0     0     0     0      0     0       0      0    0     0    0     0     0     1    0           2 ,

(1) .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .02 (2) .00 01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .02 C3 25 19 23 13 13 15 16 14 22 10 21 17 20 20 24 25 0 297 (1) .29 .22 .27 .15 .15 .17 .19 .16 .25 .12 .24 .20 .23 .23 .28 .29 .00 3.44 (2) .29 .22 .27 .15 .15 .17 .19 .16 .25 .12 .24 .20 .23 .23 .28 .29 .00 3.44 4-7 128 73 79 90 103 115 96 76 106 84 114 120 140 119 124 99 0 1666 (1) 1.48 .85 .91 1.04 1.19 1.33 1.11 .88 1.23 .97 1.32 1.39 1.62 1.38 1.44 1.15 .00 19.29 (2) 1.48 .85 .91 1.04 1.19 1.33 1.11 .88 1.23 .97 1.32 1.39 1.62 1.38 1.44 1.15 .00 19.29 6-12 232 97 93 141 110 95 139 141 122 199 404 405 408 407 333 176 0 3502 (1) 2.69 1.12 1.08 1.63 1.27 1.10 1.61 1.63 1.41 2.30 4.68 4.69 4.72 4.71 3.86 2.04 .00 40.55 (2) 2.69 1.12 1.08 1.63 1.27 1.10 1.61 1.63 1.41 2.30 4.68 4.69 4.72 4.71 3.66 2.04 .00 40.55

13 18 145 58 50 52 21 15 43 52 29 126 388 308 318 488 291 64 0 2448 (1) 1.68 .67 .58 .60 .24 .17 .50 .60 .34 1.46 4.49 3.57 3.68 5.65 3.37 .74 .00 28.34 '

(2) 1.68 .67 .58 .60 .24 .17 .50 .60 .34 1.46 4.49 3.57 3.68 5.65 3.37 .74 .00 28.34 19-24 11 19 21 12 8 3 4 7 10 18 49 47 67 182 97 4 0 559 (1) .13 .22 .24 .14 .09 .03 .05 .08 .12 .21 .57 .54 73 2.11 1.12 .05 .00 6.47 (2) .13 .22 .24 .14 .09 .03 .05 .08 .12 .21 .57 .54 .78 2.11 1.12 .05 .00 6.47 4 GT 24 1 18 15 7 1 10 0 0 0 3 0 1 10 57 38 2 0 163 (1) .01 .21 .17 .08 .01 .12 .00 .00 .00 .03 .00 .01 .12 .66 .44 .02 .00 1.89 . 1 (2) .01 .21 .17 .08 .01 .12 .00 .00 .00 .03 .00 .01 .12 .66 44 .02 .00 1.89 ALL SPEEDS 542 285 281 315 256 253 298 290 289 440 976 896 963 1273 907 371 0 8637 (1) 6.28 3.30 3.25 3.65 2.96 2.93 3.45 3.36 3.35 5.09 11.30 10.40 11.15 14.74 10.50 4.30 .00 100.00 (2) 6.28 3.30 3.25 3.65 2.96 2.93 3.45 3.36 3.35 5.09 11.30 10.40 11.15 14.74 10.50 4.30 .00 100.00 (1)aPERCENT OF ALL GOCD OBSERVATIONS FOR THIS PACE (2)ePERCENT OF ALL GOOO OBSERVATIONS FOR THl$ PERIOD C= CALM (WINO SPEED LESS THAN OR EQUAL TO .95 MPH) l

r .q.

1: - 1 i North Atlantic April 28,1995 l l j I l l l l ENCLOSURE 3 TO NYN-95038 l l l l i 1 i l l l l l 1 i

F 4 Seabrook Station Supplemental Effluent Release Report Radiological Impact Assessment for 1994 I. Summary Doses resulting from liquid and gaseous effluents from Seabrook Station during 1994 were calculated in accordance with Method 11 as defined in the Station Offsite Dose Calculation Manual (ODCM). 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 off organ doses resulting from airborne iodines, tritium and particulate rad 0:.uclides, 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 addition, the direct dose from plant operation was calculated. These doses from effluent releases and direct shine during 1994 are summarized in Table A. The calculated maximum annual total body dose and the maximum organ dose from liquid effluents each represent 0.03% 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 0.009% 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. 0.0002% and 0.0008% 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 0.00001% and 0.00003% of the limits in Technical Specification 3.11.2.2, Whereas for the " Rocks" the annual doses were 0.0003% and 0.0004% 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, 0.000003% and 0.0007% 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 2.2E-1 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 amn p

 .                                                                                     l l

l the public as set forth in 40CFR190. and demonstrates compliance with that code. The maximum organ dose from all exposure pathways including direct dose was 4.6E-3 mrem. This represents 0.02% of the annual organ dose limit of 25 mrem, as set forth in 40CFR190. I ama3 r II. Method for Calculating the Total Body and Maximum Organ Doses Resulting 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 (ODCM) (Reference 2). The specific values used for the usage f actor (U,p), mixing ratio (Mp ), bioaccumulation factor (Bip), dose factors (0,,pj), transit time (tp ), transfer constant f rom water to sediment (K c ), 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 flow rate of the liquid effluent (F) and the radionuclide activities (0 3 ) are measured specifically prior to each liquid release. The values for half lives for radionuclides (Tg ) and their radioactive decay constants ( A ) have been taken from Kocher (Reference 3). g 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 e nosure 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, nias 4 111. Method for Calculating the Gamma and Beta Air Doses from Noble Gases The computer codes AIRAD and AEOLUS 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 AE0LUS 2 for the calculation of atmospheric dispersion factors (i.e.. Chi /0 factors) from recorded meteorological data (i.e., meteorological data I measurements taken during the time of the release) are described in section 8.7.3.2 of Seabrook's ODCM. Meteorological dispersion factors concurrent with periods of batch gas releases are calculated along with the values for quarterly average dispersion factors. 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 DFf have been taken from Table B-1 in Regulatory Guide 1.109. Table A lists the calculated air doses for each calendar quarter, and the total for the year, nnn ,

r. .

IV. Method for Calculatina the Critical Organ Dose Resulting from lodines. Tritium and Particulates with T U2 Greater than 8 Days in Gaseous Releases The computer codes AEOLUS 2 (Mod 06) and ATM000s 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 AE0LUS 2 for the calculation of atmospheric dispersion factors (i.e., Chi /0 factors) 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 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 ATMODOS. ATM0005 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 nresented in Appendix C of Regulatory Guide 1.109. The pathways considered in the dose calculations are the ground plane, inhalation, cnd 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 ATM0 DOS 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 alculation 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 0DCM 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 !! 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 j and milk receptor locations for the various sector were based on the 1993 land I use census data for Seabrook Station (Table D). The radius receptor locations nru3 -S-l ^

were applied at several distances in each sector to insure that the location of the maximum doses were not overlooked. Depletion of the plume during tran3 port is considered by AE0LUS 2 in the calculations of atmospheric dispersion factors (e.g., calculation of [X/0]D), A shielding factor (S F ) of 0.7 is applied for residential structures The source for the values of the various factors used in equations C-1 through C-13 are summarized in Table C. alh81 t V. REFERENCES , i

1. Calculation of Annual Doses to Man from Routine Releases of Reactor ,

Effluents for the Purposes of Evaluating Compliance with 10CFR Part 50, f Appendix 1, Reg. Guide 1.109, Rev 1, Oct. 1977. l

2. Station Offsite Dose Calculation Mant.al, Rev 15.

3. Kocher, D.C., Dose-Rate Conversion Factors for Exposure to Photons and Electrons, Health Physics, Vol. 45, No. 3, ept. 1983.

I 1 I Ritsal ry TABLE A Seabrook Station Effluent and Waste Disposal Semiannual Report 1994 Maximum (8) Off-Site Doses and Dose Commitments to Members of the Public Dose (mrem)(b) 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year k) Liquid Effluents: Total Body Dose 2.2E-04 1.4E-04 2.5E-04 1.5E-04 7.6E-04 (2) (2) (1) (1) Organ Dose 4.2E-04 5.8E-04 1.3E-03 8.4E-04 3.1E-03 (4) (4) (3) (3) Airborne Effluents: Organ Dose from Iodines. 2.3E-05 1.2E-03 1.2E-04 4.5E-05 1.4E-03 Tritium. and Particulates (5) (6) (6) (7) Noble Gases Beta Air 3.9E-06 1.2E-07 2.0E-06 2.5E-05 3.1E-05 (mrad) (8) (9) (10) (11) Gamma 7.4E-06 3.9E-08 7.5E-06 6.8E-05 8.3E-05 Air (8) (9) (12) (11) (mrad) Doses (mrem) at Receptor Locations Inside Site Boundary (0: Science and Nature Center (SW. 488m): --- --- 2.2E-06 --- 2.2E 06 Beta Air Oose (mrad) --- --- 2.9E-06 --- 2.9E-06 Gamma Air Dose (mrad) --- 3.3E-07 1.6E-07 --- 4.9E-07 Organ Dose (mrem) (13) (13) The " Rocks" (NE/ENE. 244m): Beta Air Dose (mrad) 5.0E-06 3.1E-06 4.2E-05 --- 5.0E-05 Gamma Air Oose (mrad) 4.4E-06 6.6E-07 3.2E-05 --- 3.7E-05 Organ Dose (mrem) 4.6E 07 1.4E-05 4.8E-06 1.5E-06 2.1E-05 (13) (13) (13) (13) Direct Dose From Plant 0 Operation") nun 1

pr 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 (cor. pass sector and distance from stack in meters) of the dose receptor, where appropriate. (1) Child , (2) Adult (3) Child / Bone (4) Adult /GI-LLI (5) Child /GI-LLI, ESE-2414 (6) Child /GI-LLI, WSW-1127 (7) Child /GI-LLI, SE-2414 (8) ESE-2276 (9) NE-2276 (10) N 914 (11) WNW-930 (12) SSE-914 (13) Teen / Lung (c) " Maximum" dose for the year is the sum of the maximum doses for each quarter. This results in a conservative yearly dose estimate, but still well within the limits of 10CFR50. ' (d) For each special receptor location, the whole body and organ doses i calculated for the airborne effluent releases were adjusted by the l occupancy factor provided in Seabrook's 00CM (i.e., 0.0014 for the i 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. 1994 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 j 1986-1988 for the same locations. No statistical difference which could I be attributed to station sources was identified. nun E-

1 TABLE B Sources of the Values ' ' tors Used in Liquid Dose Equations

                                 ..w Factor                       Source V,,    Table B.7-1, Station ODCM Mp    Section B.7.1. Station ODCM (value-0.1 for aquatic foods and 0.025 for shoreline)

B ig Table A-1, Reg. Guide 1.109 . 0,,p3 Tables E-11 through E-14. R.G. 1.109 tp Section B.7.1, Station ODCH K e Reg. Guide 1.109 tb Reg. Guide 1.109 W Table A-2, Reg. Guide 1.109 (value-0.5)

.=

3 nun p 1 TABLE C Sources of Values for the Factors Used in Dose Equations for Gaseous Releases Factor. Source t b Reg. Guide 1.109 A, Kocher (Reference 3) DFG ij Table E-6, Reg. Guide 1.109 [X/0]D Calculated by AE0LUS 2 (Mod 5) R. Table B.7-3, Station 00CM Tables E-7 through E-10 R.G.1.109 OFAs ). di Reg. Guide 1.109 P,t ,t h 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 tr Reg. Guide 1.109 f, Table B.7-2. Station ODCM f Table B.7-2, Station ODCM 3 F f Table E-1, Reg. Guide 1.109 t, Table E-15 Reg. Guide 1.109 DFI,3, Tables E-11 through E-14 R.G.1.109 U*,Um aMe B.7 3. Madon 000 U[, Uh

                                    '   'I'  '      *"   "

f9'f1 Reg. Guide 1.109 j og Calculated by AEOLUS 2 (Mod 5) l ( Table E 15, Reg. Guide 1.109 f Or Table E-3, Reg. Guide 1.109 amn ! i

1 TABLE D Receptor Locations

for Seabrook Station l

l 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) --- -- 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) 0.7 (1.1) -- S 0.6 (1.0) 0.8 (1.3) l SSW 0.6 (1.0) 0.8 (1.3) --- I SW 0.6 (1.0) 0.8 (1.3) 3.2 (5.2) l WSW 0.7 (1.1) 0.7 (1.1) --- l W 0.6 (1.0) 0.7 (1.1) l WNW 0.6 (1.0) 1.0 (1.6) 3.0 (4.8) 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) , 1

Locations based on 1994 Land Use Census, amn j}}

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