Text

Rev 1.9 to ODCM, Chapters 11,12 & App F
	ML20116F381
Person / Time
Site:	Braidwood
Issue date:	06/30/1996
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-960630-01, PROC-960630-1, NUDOCS 9608060332
	Download: ML20116F381 (124)
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V X244 ALL Document Control Desk Director of Nuclear Reactor Regulation

. U.S. Nuclear Regulatory Commission Mail Station Pl-137

\ Washington, DC 20555 July 15, 1996 Attached is a revision to the Offsite Dose Calculation Manual, Braidwood Annex, Chapters 11 and 12, and Appendix F. Please update your manual as follows:

Remove:

Braidwood Chapter , Revision 1.8 Braidwood Chapter 12, Revision 1.8 Braidwood Appendix F, Revision 1.8 Insert:

Braidwood Chapter 11, Revision 1.9 Braidwood Chapter 12, Revision 1.9 Braidwood Appendix F, Revision 1.9 Please sign below indicating your manual has been updated and

%j; that your controlled copy number is correct.

Name Date Return to:

Comed Central Files 1400 Opus Place Downers Grove, IL 60515

-or-Central Files 4th Floor Downers Grove

!. NV b

d 9600060332 960630 PDR ADOCK 05000456 p PM O)

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, BRAIDWOOD Revision 19 June 1996 CHAPTER 11 1 l

BRAIDWOOD ANNEX INDEX Revision 1.9 l 1

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CRAIDWOOD Revision 19 i

June 1996 l CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table of Contents CHAPTER TITLE PAGE 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 LIST OF TABLES l

1 MUMBER TITLE PAGE

! 11-1 Radiological Environmental Monitoring Program 11-2 LIST OF FIGURES NUMBER TITLE PAGE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11.*

11-2 inner Ring TLD Locations 1' 11-3 Ingestion and Waterbome Exposure Pathway Sample Locations 1-I l

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BRAIDWOOD Revision 19 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i The radiological environmental monitoring program for the environs around Braidwood Station is given in Tab!e 11-1. ,

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Figures 11-1 through 11-3 show sampling and monitoring locations. . l l !

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BRAIDWOOD Revision 1.9 June 1996 Table 11-1 Radiological Environmental Monitoring Program

-Exposure Pathway l l Sampling or l Type and Frequency and/or Sample i Sample or Monitoring Locations a Collection Frequency i of Analysis i

_--------------------------------i -- : - - - - - - -

I I operation with particulate i Radioactive and l a. Indicators-Near Field l sample collection weekly, or l 1-131 analysis biweekly on Particulates l i BD-06, Godley,0.5 mi WSW (0.8 km M) li dust loading, and radioiodinemore i samples'. frequently if required by l BD-19, Nearsite NW,0.3 mi NW (0.5 km Q) l canister collection biweekly. l i BD-20, Nearsite N,0.6 mi N (1.0 km A) i i Earticulate Samo!er l BD-21, Nearsite NE,0.5 mi NE (0.8 km C) l l s e i Gross beta analysis following l b. Indicators-Far Field l l weekly filter change

and i 8 gamma isotopic analysis' l

i BD-02, Custer Park,5.0 mi E (8.0 km E) i i quarterly on composite filters l BD-04, Essex,4.8 mi SSE (7.7 km H) l l by locatbn on near field and i BD-05, Gardner,5.5 mi SW(8.8 km L) i i control samples'.

i i l i l i i c. Controls e i e i i e i 8 i BD-03, County Line Road, I i l 6.2 mi ESE (10.0 km F) l l g wasian'annema o.i t, t 9 o. -

O O O -

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() BRAI D Revision June 1996

Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway '

l l Sampling or Type and Frequency and/or Sample i Sample or Monitoring Locations Collection Frequency of Analysis l l 1 I i

~5 2 DireitMdiatIoE~~~~'[a. Indicators-Inner Ring [6uarterly T5anirda dose on eai.h TLD- - ~ ~

l i 8 quarterly.

l BD-101-3,0.5 mi N (0.8 km A) l l l

BD-101-4,0.5 mi N (0.8 km A) l l i BD-102-1,1.1 mi NNE (1.8 km B) i i l BD-102-2,1.1 mi NNE (1.8 km B) l l

BD-103-1,1.0 mi NE (1.6 km C) i BD-103-2,1.0 mi NE (1.6 km C) '

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s BD-104-1,0.7 mi ENE (1.1 km D) i i l BD-104-2,0.7 mi ENE (1.1 km D) l l 8

BD-105-1,2.2 mi E (3.5 km E) i e i BD-105-2,2.2 mi E (3.5 km E) ! l l BD-106-1,2.5 mi ESE (4.0 km F) l l i BD-106-2,2.5 mi ESE (4.0 km F) i l BD-107-1,3.2 mi SE (5.1 km G) l l t BD-107-2,3.2 mi SE (5.1 km G) i i l BD-108-1, 3.2 mi SSE (5.1 km H) l l BD-108-2,3.2 mi SSE (5.1 km H) i 8 l BD-109-1, 3.8 mi S (6.1 km J) l l l BD-109-2,3.8 mi S (6.1 km J) l l BD-110-1,2.8 mi SSW (4.5 km K) i i 8 l BD-110-2,2.8 mi SSW (4.5 km K) l l BD-111a-1,1.4 mi SW(2.2 km L) e i l BD-111a-2,1.4 mi SW(2.2 km L) ,' l 8 BD-112-1,0.7 mi WSW (1.1 km M) e i l BD-112-2,0.7 mi WSW (1.1 km M) l l BD-113a-1,0.5 mi W(0.8 km N) l l l BD-113a-2,0.5 mi W(0.8 km N) e i g wau2cmunnem ua,ca tti 's ua 11-3

BRAIDWOOD Rambn 1.9 June 1996 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway l l Sampling or Type and Frequency and/or Sample i Sample or Monitoring Locations i Collection Frequency of Analysis l

~-~liirect 2 Fiadi tIo-~~~~ a Indicators-Inner Ring (Cont'd) -~~---~~~~~~~~~--f~~~~-~~~~~~~-----~

e i 8 (Cont'd) l BD-114-1,0.4 mi WNW (0.6 km P) l l

,e BD-114-2,0.4 mi WNW(0.6 km P) l l BD-115-1,0.3 mi NW(0.5 km Q) i l BD-115-2,0.3 mi NW (0.5 km Q) l l i BD-116-1,0.4 mi NNW(0.6 km R) i i l BD-116-2,0.5 mi NNW (0.8 km R) l l t i i l b. Indicators-Outer Ring l l i e i l BD-201-1,4.2 mi N (6.8 km A) l l BD-201-2,4 2 mi N (6.8 km A) e i l

a BD-202-1,4.8 mi NNE (7.7 km B) i i l BD-202-2,4 8 mi NNE (7.7 km B) l l l i BD-203-1,4.9 mi NE (7.9 km C) i i

( l BD-203-2,4.9 mi NE (7.9 km C) l l BD-204-1,4.3 mi ENE (6.9 km D) i l BD-204-2,4.3 mi ENE (6.9 km D) l l BD-205-1,4.0 mi E (6.4 km E) l l l

i BD-205-2,4.0 mi E (6.4 km E) i i l BD-206-1,4.5 mi ESE (7.2 km F) l l l

t i BD-206-2,4.5 mi ESE (7.2 km F) i i l BD-207-1,4.5 mi SE (7.2 km G) l l BD-207-2,4.5 mi SE (7.2 km G) a l BD-208-1,4.5 mi SSE (7.2 km H) l l 8

BD-208-2,4.5 mi SSE (7.2 km H) e i l BD-209-1,4.8 mi S (7.7 km J) l l

! BD-209-2,4.8 mi S (7.7 km J) l l

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BRA Re?A June 1996 .

Table 11-1 (Cont'd)

Radiological Environmental Monitonng Program

-Exposure Pathway l l Sampimg or l Type and Frequency and/or Sample i Sample or Monitoring Locations a Collection Frequency i ofAnalysis I i e

- - - ---- i l ----------------- -----------------. i (Cont'd) I e i l BD-210-1,5.3 mi N (8.5 km K) l l BD-210-2, 5.3 mi N (8.5 km K) e i

! BD-211-1,4.8 mi SW(7.7 km L) ! . l l BD-211-2,4.8 mi SW(7.7 km L) l l BD-212-3, 5.0 mi WSW (8.0 km M) i i l BD-212-4, 5.0 mi WSW (8.0 km M) l l e BD-213-3,4.8 mi W (7.7 km N) e i l BD-213-4,4.8 mi W (7.7 km N) l l I BD-214-1,4.3 mi WNW (6.9 km P) e i l BD-214-2,4.3 mi WNW(6.9 km P) l l~

l BD-215-1,4.5 mi NW (7.2 km Q) l l BD-215-2,4.5 mi NW (7.2 km Q) i i l BD-216-1,4.0 mi NNW (6.4 km R) l l e BD-216-2,4.0 mi NNW (6.4 km R) i e s

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i e i l indicators l l

. I i l One at each of the airborne location given in part 1.a l l s and 1.b. i e i e i e i i e BD-305-1, Fossil Hunting Area,0.4 mi E (0.64 km i i lI E) l l BD-305-2, Braidwood Pond Access,1.0 mi E e s l (1.64 km E) l l BD-309 Braidwood Pond Access,2.7 mi S l l' l i (4.3 km J) i i J

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BRAIDWOOD Revision 1.9 June 1996 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program

' Exposure Pathway l l Sampling or l Type and Frequency and/or Sample i Sample or Monitoring Locations i Collection Frequency I of Analysis I i 1 I I I 2 Direct fiadiatIon ~~~~[c. Controls

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[~-------~~~~~-~--[-~~~~~---~~~~~~---

i (Cont'd) I l One at each airbome control location given in part l l 8

1.c. i i i I . I i i e

3. Waterbome l l l 1 I i

a. Ground /Well l a. Indicators l Quarterly l Gamma isotopic' and tntium a a i analysis quarterly.

l BD-13, Braidwood City Hall Well, l l 1.7 mi NNE (2.7 km B) i l l BD-34, Gibson Well,4.7 mi E (7.6 km E) l l l BD-35, Joly Well,4 7 mi E (7.6 km E) l l BD-36, Hutton Well,

7 mi E (7.6 km E) i l BD-37, Nurczyk Well,4.7 mi E (7.6 km E l l t i i

b. Drinkina Water l a. Indicator l Weekly composite samples

l Gross beta and gamma i I I isotopic analysis on monthly l BD-22, Wilmington 5.0 mi NE (8.0 km C) l l composite;intium analysis on l l l quarterly composite.

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c. Surface Water l a. Indicator l Weekly grab samples l Gross beta and gamma e i i isotopic analysis on monthly l BD-10, Kankakee River downstream of l l composite;intium analysis on i discharge,5.4 mi NE (8.7 km C) i i quarterly composite.

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d. Control I a. Control i Weekly grab samples i Gross beta and gamma l ! l isotopic ananalysis' on l BD-25, Kankakee River upstream of l monthly composite; intium l

i discharge, 9 6 mi E (15 4 km E) I i analysis on quarterly 8 ' ' composite.

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G BRA OD Revisio.

June 1996 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway '

l l Samphng or Type and Frequency and/or Sample i Sample or Monitoring Locations i Collection Frequency e of Analysis i i I (Cont'd) 8 8

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e. Sediments l a. Indicators l Semiannually l Gamma isotopic analysis' I I i sem: annually.

l BD-10 Kankakee River downstream of l l i discharge,5.4 mi E (8.7 km C) i i I i i i a

4. Inaestion -

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a. Mih I a. Indicators i Biweekly: May through 8 Gamma isotopic' and 1-131 l l October; monthly: November l analysis

on each sample.

l BD-17. Halpin's Dairy,5.5 mi SSW(8.8 km K) l through April l i i i l b Controls l l I i l BD-18, Biros Farm,8.7 me W (14.0 km N) l l I i

b. Eish l a. Indicator l Two times annually l Gamma isotopic analysis on 8 8 8 edible portions i BD-28, Kankakee River in discharge i I l area,5.4 mi E (8.7 km E) l I I I l b. Control l l i i l BD-25, Kankakee River upstream of l l discharge area,9.6 mi E (15.4 km E) i e i i i e i i g > dvEm wme n te.s d I le n i d 11-7

BRAIDWOOD Revision 1.9 June 1996 Table 11-1 (Cont'd)

Radiological Environmental Monitonng Program

Exposure Pathway l l Sampling or l Type and Frequency and/or Sample i Sample or Monitoring Locations i Collection Frequency i of Analysis e i i

_._______________4,_______________________.________j-_________________}__________________.

4. Ingestion i i (Cont'd) I i i i i i e i

c. Food Products l a. Indicators l Anrually 8 Gamma isotopic analysis' on i i each sample.

l Two samples from each of the four major l l e quandrants within 6.2 miles of the station. i i i e i e i i Sample locations for food products may vary a i l based on availability and therefore are not l l required to be identified here but shall be taken. 8 i i i e i e i l i i i i ib Controls e i i i e i e i i Two samples within 9.3 to 18.6 miles of the i i l station. l l I e g Aa.odum. anne ta.s.a 11 r i ea.

O O O .

BRAI Revision June 1996 Far field samples are analyzed when near field results are inconsistent with previous measurements and the radioachvity is confirmed as having its origin in airbome effluents released from the station, or at the discretion of the Radiation Protechon Director.

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

Gamma isotopic analysis means the idenbfication and quanUfication of gamma emitbng radionuclides that may be attributable to the effluents from the station.

l-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.

Grab sample (s) shall be taken at the time of collechon if the compositor is not in service.

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.I 11-12

BRAIDWOOD Revision 1.9 June 1996 O

CHAPTER 12.0 SPECIAL NOTE The transfer of the Radiological Emuent Technical Specifications to the ODCM by Technical Specification, Amendment 35, dated April 13,1992, was approved by the Nuclear Regulatory Commission.

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l BRAIDWOOD Revision 19 ,

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a BRAIDWOOD Rtvision 1.9 June 1996 1

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 12.1 DEFINITIONS 12-4 1

12.2 INSTRUMENTATION 12-8

1. Radioactrve Liquid Effluent Monitoring instrumentation 12-8

2. Radioactive Gaseous Emuent Monitoring Instrumentation 12-13 12.3 LIQUID EFFLUENTS 12-20

1. Concentration 12 20

2. Dose 12-27

3. Liquid Radwaste Treatment System 12-29 12.4 GASEOUS EFFLUENTS 12 31

1. Dose Rate 12-31

2. Dose - Noble Gases 12-37 '

3. Dose - lodine-131 and 133, Tritium, and Radioactive Material in Particulate Form 12-39

4. Gaseous Radwaste Treatment System 12-41

5. Total Dose 12-43

6. Dose Limits for Members of the Public 12-45 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-46

1. Monitoring Program 12-46

2. Land Use Census 12-59 ,

3. Interlaboratory Comparison Program 12-60 l 12.6 REPORTING REQUIREMENTS l 12-61

1. Annual Radiological Environmental Operating Report 12-61

2. Annual Radioactrve Emuent Release Report 12-63

3. Offsite Dose Calculation Manual (ODCM) 12-64 ,

4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 12-65 O '

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CRAIDWOOD Revision 19

June 1996 ;

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE 12.0-1 Emuent Compliance Matrix 12-2 12.0.2 REMP Compliance Matrix 12-3 12.1-1 Frequency Notations 12-7 12.2-1 Radioactive Liquid Emuent Monitoring Instrumentation 12-9 12.2-2 Radioactive Liquid Emuent Monitoring Instrumentation Surveillance Requirements 12-11 12.2-3 Radioactive Gaseous Emuent Monitoring Instrumentation 12-14 12.2-4 Radioactive Gaseous Emuent Monitoring instrumentation Surveillance Requirements 12-17 12.3-1 Radioactive Liquid Waste Sampling and Analysis Program 12-22 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-33 12.5-1 Radiological Environmental Monitoring Program 12-49 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-55 i 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-56 g:Wabdcrmannextraad\12ri-9f. doc 12-iv

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, BRAIDWOOD Revision 19 l

June 1996 12.0 B&OLOGICAL EFFLUENT TECHNICAL STANDARDS i

( Chapter 12 of the Braidwood Station ODCM is a compliance of the various regulatory requirements, i

surveillance and bases, commitments and/or components of the radiological effluent and environmental monitoring programs for Braidwood Station. To assist in the understanding of the relationship betwoon effluent regulations, ODCM equations, RETS (Chapter 12 secton) and related Technical Specification requirements, Table 12.0-1 is a matrix which relates these various components. The Radiological Environmental Monitoring Program fundamental requirements are contained within this chapter with Braidwood specific informaton in Chapter 11 and with a supplemental matrix in Table 12.0-2.

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BRAIDWOOD Revision 19 -

June 1996 Table 12.0-1 EFFLUENT COMPLIANCE MATRIX l Regulation Dose Component Limit ODCM RETS Technical Equation Specification l

10 CFR 50 1. Gamma air dose and beta air dose due A-1 12.4.2 6.8.4.e.8 Appendix ! to airbome radioactivity in effluent A-2 plume.

a. Whole body and skin dose due to A-6 N/A N/A airtome radioactivity in effluent A-7 plume are reported only if certain gamma and beta air dose criteria are, exceeded.

2. CDE for all organs and all four age A-13 12.4.3 6.8.4.e.9 groups due to iodines and particulates in effluent plume. All pathways are considered.

3. CDE for all organs and all four age A-29 12.3.2 6.8.4.e.4 groups due to radioactivity in liquid effluents.

10 CFR 20 1. TEDE, totaling all deep dose equivalent A-38 12.4.6 6.8.4.e.3 components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airbome and liquid-bome). CDE evaluation is made for adult only using FGR 11 data base.

40 CFR 190 1. Whole body dose (DDE) due to direct A-35 12.4.5 6.8.4.e.10 (now by dose, ground and plume shine from all reference, sources at a station.

also part of '

10 CFR 20) 2. Organ doses (CDE) to an adult due to A-13 all pathways.

Technical

1. " Instantaneous" whole body (DDE), skin A-8 12.4.1 6.8.4.e.7 Specifications (SDE), and organ (CDE) dose rates to A-9 an adult due to radioactivity in airbome A-28 effluents. For the organ dose, only inhalation is considered.

2. " Instantaneous" concentration limits for A-32 12.3.1 6.8.4.e.2 '

liquid effluents. ,

i Technical ,

1. Radiological Effluent Release Report NA 12.6.2 6.9.1.7 Specifications ;

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CRAIDWOOD Revision 19 June 1996 Table 12.0-2 REMP COMPLIANCE MATRIX Regulation Dose Component Limit RETS Technical Specification 10 CFR 50 Implement environmental monitoring 12.5.1 6.8.4.f Appendix 1 program.

Section IV.B.2 1

Technical Land Use Census 12.5.2 6.8.4.f.2 Specifications Technical Interlaboratory Companson Program Specifications 12.5.3 6.8.4.f.3 l

l Technical Radiological Environmental Operating Report 12.6.1 6.9.1.6 Specifications l

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CRAIDWOOD Revision 19 ,

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12.0 RADIOLOGICAL ENVIRONMENTAL TECHNICAL STANDARDS 12.1 DEFINITIONS 12.1.1 Action shall be that which prescribes remedial measures required under designated conditions.

12.1.2 Analoo Channel Ooerational Test shall be the injection of a simulated signal into the f channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock l and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm interlock and/or Trip Setpoints such that the l

Setpoints are within the required range and accuracy. '

12.1.3 Channel Calibration shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CAllBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overtapping, or total channel steps such that the entire channel is calibrated.

12.1.4 Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, companson of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

12.1.5 Dioital Channel Ooerational Test shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to venfy OPERABILITY of alarm and/or trip functions.

l 12.1.6 Dese Eauivalent 1-131 shall be that connection of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table til of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites".

12.1.7 Freauency - Table 12.1-1 provides the definitions of various frequencies for which surveillance's, sampling, etc. are performed unless defined otherwise. The 25%

l variance shall not be applied to Operability Action Statements. The bases to Technicai Specification 4.0.2 provide clanfications to this requirement.

12.1.8 Member (s) of the Public means any individual except when that individual is receiving an occupational dose.

I 12.1.9 Occuoational Dose means the dose recerved by an individual in the course of I

employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and i'nlicensed sources of radiation, whether in the possession of the licensee or otner person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary j participation in medical research programs, or as a member of the public.

O g%abdcm\annextrad\12ri-9tdoc l

12-4 l l

i

. 1

. ORAIDWOOD R vision 19 June 1996 n 12.0 RADIOLOGICAL ENVIRONMENTAL TECHNICAL STANDARDS (Conti 12.1.10 Ooerable/Ocerability a system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

12.1.11 Ooerational Mode (i.e. Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2 of the Technical Specifications.

12.1.12 Process Control Program (PCP) shall contain the current formulas, sampling, analyses.

tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Pans 20,61,71 and State regulations, burial ground requirements, and other requirements goveming the disposal of radioactive wastes.

12.1.13 Purge / Purging shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to pur@

the confinement.

A 12.1.14 Rated Thermal Power shall be a total core heat transfer rate to the reactor coolant cf C 3411 MWt.

l 12.1.15 Site Boundarv shall be that line beyond which the land is neither owned, nor leased otherwise controlled by the licensee. '

12.1.16 Solidification shall be the conversion of wet wastes into a form that meets shipping a l burial ground requirements.

12.1.17 Source Check shall be the qualitative assessment of channel response when the '

channel sensor is exposed to a source of increased radioactivity.

12.1.18 Thermal Power shall be the total core heat transfer rate to the reactor coolant.

12.1.19 Unrestricted Area means an area, access to which is neither limited nor controlled t.

the licensee. l 12.1.20 Vent!!ation Exhaust Treatment Svstem shall be any system designed and installed 'o reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

A g tabdentannextrad\12ri-9f doc 12-5

CRAIDWOOD Rsvision 19 -

June 1996 12.0 RADIOLOGICAL ENVIRONMENTAL TECHNICAL STANDARDS (Conti 12.1.21 Venting shall be any controlled process of discharging air or gas from a confinement I to maintain temperature, pressure, humidity, concentration or other operating l condition, in such a manner that replacement air or gas is not provided or required :

during VENTING. Vent, used in system names, does not imply a VENTING process. '

12.1.22 Waste Gas Holdua System shall be any system designed and installed to reduce l radioactive gaseous effluents by col!ecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the enviro 1 ment.

12.1.23 Definitions Peculiar to Estimating Dose to Members of the Public using the ODCM Computer Program.

a. ACTUAL - ACTUAL refers to using known release data to project the dose to members of the public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.

b. PROJECTED - PROJECTED refers to using known release data from the previous time period or esthnated release data to forecast a future dose to members of the public. This data is not incorporated into the database.

O l

I 12-6

4

. BRAIDWOOD Revision 1.9 June 1996 TABLE 12.1-1 FREQUENCY NOTATIONS

NOTATION FREQUENCY l l

S - Shiftly At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . I D - Daily At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W - Weekly At least once per 7 days.

M - Monthly At least once per 31 days. !

Q - Quarterly At least once per 92 days.

SA- Semiannually At least once per 184 days. :

A - Annually At least once per 366 days.

R - Refueling cycle At least once per 18 months (550 days).

S/U - Startup Prior to each reactor startup.

P - Prior Prior to each radioactive release.

, N.A. Not applicable. l i

l l

Each frequency requirement shall be performed within the specified time interval with the maximum allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be applied to Operability Action Statements. The bases to Technical Specification 4 0 2 .,

provide clarifications to this requirement. These frequency notations do not apply to the i Radiological Environmental Monitoring Program (REMP) as described in Secten 12.5. '

4 l

g:Wabdcmurmextrad12ri-9f.rbc 12-7 i

, - - , . - . . - - ., -. 1

- e BRAIDWOOD Revision 19 June 1996 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitonng Instrumentation Ooerability Reauirements 12.2.1. A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their Alarm / Trip Setpoints cet to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Acolicability: At all times Action

1. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

Surveil!ance Recuirements 12.2.1.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2 2.

Bases !

12.2.1.C The radioactive liquid effluent instrumentation is provided to monitor and control as applicable, the releases of radioactive materials in liquid effluents during actuai or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to i exceeding the limits of RETS. The OPERABILITY and use of this instrumentation l

is consistent with the requirements of General Design Criteria 60,63, and 64 of l Appendix A to 10 CFR Part 50.

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g:Waiodem\annexibraid\12ri-9f. doc 12-8

O i

CRAIDWOOD Revision 1.9 June 1996 TABLE 12.21 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release -

l a. Liquid Radwaste Effluent Line (ORE-PR001) 1 31

b. Fire and Oil Sump (ORE-PR005) 1 34

]

c. Condensate Polisher Sump Discharge (ORE,PR041) 1 34

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Essential Service Water

1) Unit 1 a) RCFC 1 A and 1C Outlet (1RE-PR002) 1 32 b) RCFC 18 and 1D Outlet (1RE-PR003) 1 32

2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) RCFC 2B and 2D Outlet (2RE-PR003) 1 32

b. Station Blowdown Line (ORE-PR010) 1 32

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (Loop-WX001) 1 33

b. Liquid Radwaste Effluent Low Flow Line (Loop-WX630) 1 33

c. Station Blowdown Line (Loop-CWO32) 1 33 D l V .

g:Wabdcmunnextrad12ri-9f doc 12-9

O CRAIDWOOD Rsvision 19

June 1996 TABLE 12.2-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Section 12.3 and

b. At least two technically quali*ied members of the facility staff independeritiy

.. . verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are coliected and analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1.

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirernent, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months du' ng actual releases. Pump performance curves generated in place may be used to estimate flow.

ACTION 34 - With the number of channels OPERABLE less than required by the Minimum C~ n annels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1:

a. At least once per 12 nours when the specific activity of the secondary coolant is praG inan 0.01 microcurie / gram DOSE EQUIVALENT l-131 of

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.

O giabdcm\annextragn12ri-9f. doc 12-10

Q ,Oi

v B D RevL/1.9 ,

June 1996 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CAllBRATION TEST TEST

1. Radioactwity Monitors Providing Alarm and Automabc Termnabon of Release

a. Liquid Radwaste Emuent Line (ORE-PR001) D P R(3) O(1) N.A.

b. Fire and Oil Sump Discharge (0RE-PR005) D M R(3) O(1) N.A.

c. Condensate Polisher Sump Discharge (ORE-PR041) D M R(3) O(1)* N.A.

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Essential Service Water

1) Unit 1 a) RCFC 1 A and 1C Outlet (1RE-PR002) D M R(3) O(2) N.A.

b) RCFC 18 and 1D Outlet (1RE-PR003) D M R(3) O(2) N.A.

2) Unit 2 a) RCFC 2A ano 2C Outlet (2RE-PR002) D M R(3) O(2) N.A.

b) RCFC 2B and 2D Outlet (2RE-PR0'33) D M R(3) O(2) NA

b. Station Blowdown Line (ORE-PR010) D M R(3) O(2) NA

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line (Loop-WX001) D(4) NA R N.A. O

b. Liquid Radwaste Emuent Low Flow Line (Loop 4VX630) D(4) N.A. R NA O c Stata,n Blowdv*n t .nc .t . l. v D(4) N.A R N.A. O 9 . wa n .. . _ ., 2 .

12-11

l BRAIDWOOD Rsvision 19 .

June 1996 TABLE 12.2-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS O

TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of ,

this pathway and control room alarm annunciation occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow. This is only applicable for ORE-PR001 and ORE-PR005 Monitor ORE-PR041 will not trip on loss of sample flow.

(2) The OlGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or i

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts er i monitor loss of power), or !

l

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended rav ,

of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

{

j J

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

2 g%abdcm\annextrad\12ri-9rdoc 12-12

. ERAIDWOOD Revision 1.9 June 1996 12.2.2 Radinactiva n== anus Effluent Monitorina Instrumentatinn Ooerabihtv Reauirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 12.4 are not exceeded The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Apphcabihty As shown in Table 12.2-3 Action-

1. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

2. With less than the minimum number of radioactive gaseous emuent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-3. Restore the inope,rable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Emuent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

Survaillance Raanirements 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall te demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURC -

CHECK, CHANNEL CAllBRATION and DIGITAL and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-4.

Bases 12.2.2.C The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluecm during actual or potential releases of gaseous emuents. The Alarm / Trip Setoc -

for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarmitrip will :=

prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Cntena -

63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show comphance with the gaseous effluent release requirements of Section 12.4 shall be such that concentrations as low as 1x10 "

uCi/cc are measurable.

g:Wabdcmbnnextrad12ri-9f doc 12-13

BRAIDWOOD Revision 1.9 June 1996 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Plant Vent Monitoring System- Unit 1

a. Noble Gas Activity Monitor Providing Alarm

1) High Range (1RE-PR028D) 1 39

2) Low Range (1REPR0280) 1 39

b. lodine Sampler (1RE-PR028C) 1 40

c. Particulate Sampler (1RE-PR028A) 1 40

d. Effluent System Flow Rate Measuring Device (LOOP-VA019) 1 36 e Sampier Flow Rate Measunng Device (1FT-PR165) 1 36

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Monitor Providing Alarm

1) High Range (2RE-PR028D) 1 39

2) Low Range (2RE-PR0288) 1 39

b. lodine Sampler (2RE-PR028C) 1 40

c. Particulate Sampler (2RE-PR028A) 1 40

d. Effluent System Flow Rate Measuring Device (LOOP-VA020) 1 36

e. Sampler Flow Rate Measunng Device (2FT PR165, 1 36 g #a ounam e. ma t. - a2 ,

O 9 0 .

BRA D Revis .9 June 1996 TABLE 12.2-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILIIX ACTION

3. Not Used.

4. Gas Decay Tank System

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (ORE-PR002A and 28) 2 35

5. Containment Purge System

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR0018) 1 37

b. lodine Sampler (RE-PR001C) 1 40

c. Particulate Sampler (RE-PR001A) 1 40 t

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Line (ORE-PR009 and RE-PR009) 2 41 8 4 12-15

BRAIDWOOD Revision 1.9 .

June 1996 TABLE 12.2-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS

At all times.

ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. Releases may continue via this pathway for up to 7 days provided real time monitoring of radioactive effluents released via this pathway is established.

ACTION 38 - Not used.

ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may contir .-

for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months anc these samples are analyzed for principle gamma emitters at an LLD as specified -

Table 12.4-1.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway ma, continue for up to 30 days provided samples are continuously collected with auxo e .

sampling equipment as required in Table 12.4-1.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continu e for up to 30 days provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , liquid grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1.

l l

1 g%abdcm\annextrad\12ri-9f doc 12-16

O a BR N D n Revh~.<1.9 June 1996 TABLE 12.2-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIC41TAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CALIBRATION TEST IS REQUIRED

1. Plant Vent Monitoring System - Unit 1

a. Noble Gas Activity Monitor-Providing Alarm

1) High Range (1RE-PR028D) D M R(3) O(2)

2) Low Range (1RE-PR028B) D M R(3) O(2) *

b. lodine Sampler (1RE-PR028C) D M

R(3) O(2) c Partculate Sampler (1RE-PR028A) D M R(3)

O(2)

d. Effluent System Flow Rate Measuring D N.A. R O

Device (LOOP-VA019)

e. Sampler Flow Rate Measuring Device D N.A. R O *

(1FT-PR165)

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Monitor-Providing Alarm

1) High Range (2RE-PR028D) D M R(3) O(2)

2) Low Range (2RE-PR028B) D M R(3) O(2) b lodine Sampler (2RE-PR028C) D M R(3)

O(2) 9 + a u2an onne. m.2 i . , i ., a.

12-17

BRAIDWOOD Revision 1.9 June 1996 TABLE 12.2-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CAllBRATION IEST IS REQUIRED

2. Plant Vent Monitoring System - Unit 2 (Continued)

c. Particulate Sampler (2RE-PR028C) D M R(3) O(2)

d. Effluent System Flow Rate Measuring D N.A. R Q

Device (LOOP-VA020)

e. Sampler Flow Rate Measuring Device D N.A. R O *

(2FT-PR165)

3. Not Used

4. Gas Decay Tank System

a. Noble Gas Activity Monitor P P R(3) Q(1)*

Providing Alarm and Automat.t Termination of Release (0RE-PR002A and 28)

5. Containment Purge System (

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR001B) D P R(3) O(2)

b. lodine Sampler (RE-PR001C) P P R(3) N.A. *

c. Particulate Sampler (RE-PR001A) P P R(3) N.A. *

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Line (0RE-PR009 and RE-PR009) D M R(3) O(1) 9 wausemanne.v .a t. o y o ,s O 'O O .

. CRAIDWOOD Revision 1.9 June 1996 TABLE 12 2-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS At all times.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of

' this pathway and control room alarm annunciation occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow. Monitoring ORE-PR002A and 28 will not trip on loss of sample flow. This is only applicable for functional unit 6, ORE-PR009 and RE-009.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or l

c. Detector check source test failure, or I

d. Detector channel out-of-service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL Call 8 RATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL Call 8 RATION, sources that have been related to the initial calibration shall be used.

g-WabdemWmextrenn12ri 9 doc 12-19

CRAIDWOOD Revtsion 1.Q June 1996 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Ooerability Reauirements )

12.3.1. A The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x10" microcurie /ml total activity.

Acolicability: At all times Action

1. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

Surveillance Recuirements 12.3.1.1.B Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 12.3-1.

12.3.1.2.B The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of 12.3.1.A.

Bases 12.3.1.C This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values in Appendix B. Table 2, Column 2 to 10 CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result .n exposures within: (1) the Section ll.A design objectives of Accendix 1.10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301.

This section applies to the release of radioactive materials in liquid effluents from all units at the site.

gtabdcm\annerbrad\12ri-9. doc l

12-20

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CRAIDWOOD Revision 19 June 1996 12.3 LIQUID EFFLUENTS (Continued)

Bases The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

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g%abdcmunnexhaid\12ri-9. doc 12-21

GRAIDWOOD Revision 19 Juns 1996 TABLE 12 3-1 RADIOACTIVE LfOUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)*

(pCvml)

1. Batch Release P P Principal Gamma 5x10

Tanks

Each Batch Each Batch EmittersM l-131 1x10*

P M Dissolved and Entrained 1x10

One Batch /M gases (Gamma Emitters)

P M H-3 1x10' Each Batch Composite

Gross Alpha 1x10' P Q Sr-89, Sr 90 5x10' Each Batch Composite

Fe 55 1x10*

2. Continuous W Principal Gamma 510 ,

Rekases

Emitte#

Continuous

Composite m l-131 1 *. i

a. Circulating Water M M Dissotved and Entrained t:-

Blowdown Grab Sample Gases (Gamma ;

Emitters)*

b. Waste Water Treatment M H-3

Diwharge to Continuous

Composite

Circulating Water Discharge I

Gross Alpha '. !

c. Condensate Continuous

Q Sr-89. Sr-90 ti Polisher Sump Composite

Discharge Fe-55 i-i i

g:Wabdcyn\annextraid\12ri-9. doc 12-22

. BRAIDWOOD Revtsion 19 June 1996 TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION (LLD)("(pCi/ml) l 3. Continuous W') W') Principal Gamma 5x10

I Release") Grab Sample Emittersm Essential Service Water Reactor -

Containment l Fan Cooler '

l (RCFC) Outlet Line r

1 l-131 1x10' l

H-3 1x10' ,

1 M Dissolved and 1x10* l

, Entrained Gases i (Gamma Emihrs)m

4. Continuous O- Surge Tank None None Principal Garrma Emittersm Sn*- -i t

Vent-Component '

Cooling Water i Line (')

Dissolved and .

Entrained Gases (Gamma Emitters)*

4 l-131 *.'

{

lO .

g:*sbdomurmextrakh12r1-9 doc 12-23

O BRAIDWOOD Remsion 10 June 1996 TABLE 12 3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is defined, for purposes of these sections, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD = 4.66s3 E V 2.22 x 106 Y exp (-AAt)

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

s, = 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' = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec "), and at = the elasped time between the midpoint of sample collection and the time of counting (sec).

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

Altemative t i n Methodoloav An attemative methodolology for LLD determinaten follows and is similar to the above LLD equation:

(2.71 + 4.65VB)+ Decay LLD =

E q b Y t(2.22E06) 0 l g:Wabdcmunnexhaid\12ri-9 doc l

12-24 l

. CRAIDWOOD Revision 19 June 1996 >

TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS t

Where: i B = background sum (counts)

E = counting efficiency, (counts detected / disintegration's) -

q = sample quantity,(mass or volume) b = abundance,(if applicable)

Y = fracbonal radiochemical yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegration's per minute per microcurie 2.71 + 4.65VB = k8 + (2k V 2 V B), and k = 1.645.

(k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.)

Decay = e* [ ART /(1-e")) [AT,/1-e#,)], (if applicable)

A = radioactive decay constant, (units consistent with At, RT and T )

At = " delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent with 1)

RT= elapsed real time, or the duration of the sample count, (units consistent with A)

T = sample deposition time , or the duration of analyte collection onto the sample media, (units consistent with A)

The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the backgrov -

sum, utilizing the software's ability to perform decay corrections (i.e. during sample collecbon, from sample collection to start of analysis and during counting), this attemate method will result in a more accurate determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

O .

ghWkrnWmertraid\12ri-9. doc 12 25

CRAIDWOOD Revision 19 June 1996 TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM IAEl E NOTATIONS (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.

(3) 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.

(4) A continuous release is the discharge of liquid wastes of a nondi.screte volume, e.g., from a volume of a system that has an input flow during the continuous release.

(5) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously whenever the effluent stream is flowing. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(6) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and RE-PR003 indicates measured levels greater thatn 1x104 Ci/ml above background at any time during the week.

(7) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xre-135, and Xe-138 for dissolved and entrainec for principal gamma emitters. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, toghether with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report 1 June 1974.

(8) A continous release is the discharge of dissolved and entrained gaseous waste form a nondiscrete liquid volume.

i giabdemWnnextrad12ri-9. doc 12-26 l

, BRAIDWOOD Revision 19 June 1996 12.3.2 Dana O Ocarability Reauirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

2. During any calendar year to less than or equal to 3 mrems to the wnole body and to less than or equal to 10 mrems to any organ.

Apphcabihty. At all times.

Action

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Reauirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases 12.3.2.C This section is provided to implement the requirements of Sechons ll.A, lil.A and IV A c' Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Seebon ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV A of Appendix l to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters in the ODCM implement the requirements in Seebon Ill.A of Appendix 1 that conformance with the guides of Appendix I be shown t, calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantiacy underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in hquid effluents are consistent with the methodology provided in Regulatory Guide 1.109 " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1." Apol 1977.

O .

g%abdcm\ennextraid\12ri-9. doc 12-27

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

BRAIDWOOD Revision 19' June 1996 l 12.3.2 Dste(Continued)

Bases This section applies to the release of radioactive materials in liquid effluents from each reactor at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated i effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attnbuted to each unit to obtain the total releases per unit.

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g:Wabdomunnextrad12r19. doc 12-28

, BRAIDWOOD Revision 19 June 1996 12.3.3 Liouid Radwaste Treatment System Ooerability Reauirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

Acolicabilitv: At all times.

Action i

1. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

Surveillance Reauirements 12.3.3.1.8 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radwaste Treatment System is not being fully utilized.

12.3.3.2.8 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Sections 12.3.1.A and 12.3.2.A.

Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that this l

system will be available for use whenever liquid effluents require treatment pner to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of I

radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix I to 10 CFR Part 50.

l l

g%aiodem\annextrad\12ri-9. doc 12-29

v .

BRAIDWOOD Revision 19' June 1996 12.3.3 Liouid Radwaste Treatment System (Continued)

Bases The specified limits goveming the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.

This section applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations f, rom shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

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gva\odan\snnextrad12ri-9 doc 12-30

. BRAIDWOOD Revision 1.9 June 1996 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Ooerability Reauirements i

12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. For noble gases: less than or equal to a dose rate of 500 mrems/yr to the whole body and less than or equal to a dose rate of 3000 mrems/yr to the skin.

and

2. For lodine 131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

Acoliemhilitv: At all times.

Action

1. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s). j Surveillance Reauirements O 12.4.1.1.8 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM j

l 12.4.1.2.B The dose rate due to lodine 131 and 133, tritium, and all radionuclides in particulate l form with half-lives greater than 8 days in gaseous effluents shal1 be determined to t'e I within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1.

Bases 12.4.1.C This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annua.

dose limits of 10CFR20. These limits provide reasonable assurance that radioactwe material discharged in gaseous effluents will not result in the exposure of a MEMBER j OF THE PUBLIC exceeding the limits specified in 10CFR20.1301.

I

)

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gVabdcmiennextreed\12ri-9 doc 12-31

A BRAIDWOOD Revisiot: 19-June 1996 12.4 GASEOUS EFFLUENTS (Continued)

Bases @

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times the corresponding thyroid dose rate above background via the inhc!ation pathway to less than or equal to 1500 mrems/ year.

This section applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

O l

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g1Aabdcmunnextrad12ri 9. doc 12-32 l

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1 l

. CRAIDWOOD Revision 19 June 1996 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ,

LIQUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT OF ,

TYPE FREQUENCY ANALYSIS ANALYSIS (e) DETECTION l FREQUENCY (LLD)"'(pCi/cc) 1

1. Waste Gas P P Principal Gamma 1x10" Decay Tank Each Tank Each Tank Emitters (*)

Grab Sample

2. Containment P P Principal Gamma 1x10" Purge Each Purge (*) Each Purge ( ) Emitters (2)

Grab Sample H-3 1x10

3. Auxiliary Bldg. M(*) M Principal Gamma 1x10" Vent Stack Grab Sample Emitters (2)

(Unit 1 and 2) s H-3 1 x10

Continuous (*) W* l-131 1x10"'

Charcoal Sample I-133 1x10" Continuous (') Wm Principal Gamma 1x10 " '

Particulate Emitters (2)

Sample l Continuous (*) Q Gross Alpha 1x10'"

Composite Particulate ;

Sample Continuous (') Q Sr-89, Sr-90 1x10'"

Composite Particulate Sample .

Continuous 4 l

Noble Gas Noble Gases, Gross 1x10 Monitor Beta or Gamma 4

i .

l gtabdomunnextroed\12ri-9 doc 1 l

12-33

l BRAIDWOOD Revision 19 June 1996 TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of l

radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD = 4 fi6s.

E V 2.22 x 10" + Y exp (-Aat)

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

so= 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' = the number of disintegrations per minute per microcurie, 9 Y = the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuclide (sec "), and at = the elasped time between the midpoint of sample collection and the time of counting (sec).

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

Altemate t t n Methodoloov An altemate methogolody for LLD determination follows and is similar to the above LLD equation:

)

l (2.71 + 4.65VB) Decay l LLD =

l E q b Y t (2.22E06) l

. O g%sbdcm\annextraid\12ri-9. doc 12-34

, CRAIDWOOD Revision 19 June 1996 t

D' TABLE 12.41 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 2

TABLE NOTATIONS Where:

B = background sum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity, (mass or volume) b = abundance, (if applicable)

, Y = fractional radiochemical yeild or collection efficiency, (if applicable) t = count time (minutes)

! 2.22E06 = number of disintegrations per minute per microcurie 2

(2.71 + 4.65VB) = k + (2k V 2 V B), and k = 1.645.

, (k=value of the t statistic from the single-tailed t distribution at a significance leve-v of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concludirg that the nuclide present when it is not or that the nuclide is not present when it s Decay = e"[1-e"))[AT /1-e")],(if applicable)

A = radioactive decay constant, (unhits consistent with At, RT and T )

At = " delta t", or the elapsed time between sample collection or the midpoint of samp'e collection and the time the count is started, depending on the type of sample, (units consistent with A)

RT = elapsed real time, or the duration of the sample count, (units consistent with A)

Ta = sample deposition time, or the duration of analyte collection onto the sample media, (unit consistent with A)

The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. dunng sample collection, from sample collection to start of analysis and during counting), this alternate method will result in a more accurae determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit and not as an after the O fact limit for a particular measurement.

g Wabdcrn\annextraid\12ri-9. doc 12 35

BRAIDWOOD Revision 13 June 1996 O

TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (2) The principal gamma emitters for which the LLD specification applies 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, Co-60, Zn-65, Mo-99,1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in 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 Radioactive Effluent Release Report pursuant to Section 12.6.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

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

(5) Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) 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 Sections 12 A 12.4.2.A and 12.4.3.A.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within a timeframe necessary to meet the applicable lower limits of detection, but not to exceed 48 hot. -

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 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POW 1 ~

within a 1-hour period and analyses shall be completed within a timeframe necessary to meet -

applicable lower limits of detection, but not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . When samples collected for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 l-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the not e gas monitor shows that effluent activity has not increased more than a factor of 3.

. O g%siodem\annextread\12ri-9. doc 12-36

. BRAIDWOOD Revision 19 June 1996 12.4.2 Dose - Noble Gases

)

O Ooerability Reauirements 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

2. During any calendar year: Less than or equal to 10 mrads for gamma radiation and I less than or equal to 20 mrads for beta radiation.

Apohcabihty At all times.

Action i

1. With the calculated air dose from radioactive noble gases in gaseous effluents l exceeding any of the above limits, prepare and submit to the Commission within 30 '

days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the ]

cause(s) for exceeding the limit (s) and defines the corrective actions that have been l taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Survadlance Raouirements O 12.4.2.8 Cumulative dose contributions for the current calendar quarter and the current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases 12.4.2.C This section is provided to implement the requirements of Sections 11.8, Ill.A and IV A cf Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV A ,

of Appendix ! to assure that the releases of radioactive materialin gaseous effluents to '

. area at or beyond the SITE BOUNDARY will be kept "as low as is reasonable '

achievable." The Surveillance Requirements implement the requirements in Section ,

Ill.A of Appendix 1 that conformance with the guides of Appendix i be shown by ,

calculational procedures based on models and data such that the actual expocure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

b v .

g%sbdcm\annextraid\12ri 9. doc '

12-37

1 CRAIDWOOD Revision 1*9 l June 1996 12.4.2 Dese - Noble Gases (Continued) 1ases i

The dose calculation methodology and parameters established in the ODCM for

{

calculating the doses due to the actual release rates of radioactive materials in gaseous )

effluents are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluati1g Compliance with 10 CFR Part 50, Appendix I" Revision 1 October 1977 and Reputatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmorpheric conditions.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e g., flow rates and radioactivity concentrations, or, if not practicable, the treated ,

ef'auent releases may be allocated equally to each of the radioactive waste producing !

units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O O

g%abdcm\annextrad\12ri-9 doc 12-38

l

, CRAIDWOOD Revision 19 June 1996 12.4.3 Dose -lodine I-131 and 133. Tritium. and Radioactive Materialin Particulate Form I

l Ooerability Reauirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from lodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. During any calendar quarter Less than or equal to 7.5 mrems to any organ, and

2. During any calendar year Less than or equal to 15 mrems to any organ.

Aeolit shility: At all times.

Action

1. With the calculated dose from the release of lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 da,is, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent l

releases will be in compliance with the above limits. I Surveillance Reauirements

,0

(,/ 12.4.3.B Cumulative dose contributions for the current calendar quarter and the current calendar year for lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 3 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases 12.4.3.C This section is provided to implement the requirements of Sections ll.C. Ill.A and IV A cf 4 :. acix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section 11 C P Appendix 1. The ACTION statements provide the required operating flexibility and at the u e time implement the guides set forth in Section IV.A of Appendix I to assure that the releases :'

radioactive materialin gaseous effluents to areas at or beyond the SITE BOUNDARY a a & ect "as low as is reasonable achievable." The ODCM calculational methods specified in tre Surveillance Requirements implement the requirements in Section Ill.A of Appendix I tnat conformance with the guides of Appendix l be shown by calculational procedures based r models and data, such that the actual exposure of a MEMBER OF THE PUBLIC througn appropriate pathways is unlikely to be substantially underestimated.

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g tabocmunnextraad\12r1-9 doc 12-39

o BRAIDWOOD Remsion 1,9 June 1996 12.4.3 Ogse (Cont:nued)

Bases The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine ,

Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR l Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.111,

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1)individualinhalation of airbome radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animal's graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions.

e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units shanng the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systerns are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

gtaiodem\ annex \ breed \12ri-9 doc 12-40

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

i ERAIDWOOD Revision 1.9 !

June 1996 .

12.4.4 Gaseous Radwaste Treatment System 4

Ooerability Reauirements l

12.4.4.A l The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS i HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems j shall be used to reduce releases of radioactivity when the projected doses in 31 days ;

due to gaseous affluent releases, from each unit, to areas at and beyond the SITE ;

BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) meet or ;

exceed Technical Specifications and/or code of Federal Regulation limits.

j Appirabihty' At all times.

Action

. 1, With radioactive gaseous waste being discharged without treatment and in l

excess of limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the ;

following information:

{

a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

Survaillance Ranuirements l 4

12.4.4.1.8 Doses due to gaseous releases from each unit to areas at and beyond the SITE

BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radweste Treatment Systems are not being fully utilized. !

12.4.4.2.B The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 and 12.4.2 or 12.4.3.

Bases 12.4.4.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION I EXHAUST TREATMENT SYSTEM ensures that the system will be available for use ;

whenever gaseous effluents require treatment prior to release to the environment. ;

l I

l 1

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g%sWdemunnextraad\12ri-9 doc 12-41

\

CRAIDWOOD Revision 19 June 1996 12.4.4 Gaseous Radwaste Treatment System (Continued)

Bases The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the Gaseous Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section li.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions.

e g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

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g%abdcm\annextrad12ri-9 doc 12-42

)

CRAIDWOOD Revision 19 l June 1996 12.4.5 Total Dose

\ Ooerability Reauirements l 12.4.5. A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Acoliemhilitv: At all times.

Action 1

1. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2,12.4.2, or 12 4 3.

l calculations should be made including direct radiation contnbutions from the units l and from outside storage tanks to determine whether the ateve limits of Section l 12.4.5.A have been exceeded. If such is the case, prepare a 5d submit to the Commission within 30 days, pursuant to Technical Specificatic n 6.9.2, a Special I

Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for l achieving conformance with the above limits. This Special Report, as defined in 'O CFR 20.2203, shall include an ana!ysis that estimates the radiation exposure (ce sei to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the i release (s) covered by this report. It shall also describe levels of radiation ara

! O concentration of radioactive materialinvolved, and the cause of the exposure -

(gb or concentrations. If the estimated dose (s) exceeds the above limits, and if "-

release condition resulting in violation of 40 CFR Part 190 has not already t~

corrected, the Special Report shall include a request for a variance in accc< .

l with the provisions of 40 CFR Part 190. Submittal of the report is considere ,

l timely request, and a variance is granted until staff action on the request s

! complete.

I Surveillance Reauirements I

l 12.4.5.1.A Cumulative dose contributions from liquid and gaseous effluents shall be determmm i accordance with Sections 12.3.2,12 4 2. and 12.4.3, and in accordance with the methodology and parameters in the ODCM.

12.4.5.2.8 Cumulative dose contnbutions from direct radiation from the units and from radwav-I storage tanks shall be determined in accordance with the methodology and pararv-the ODCM. This requirement is applicab e only under conditions set forth in ACTh *.

Section 12.4.5.A.

D V ,

, g Wa\odem\annextraed\12ri-9. doc 12-43

CRAIDWOOD Revision 19 June 1996

]

12.4.5 Total Dose (Continued)

Bases 12.4.5.C This section is provided to meet the dose limitations of 40 CFR Part 190 that have )

been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the (

preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from I other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius i

of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is I

estimated to exceed the requirements of 40 CFR Part 190, tne Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individualis not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

O gVa\odem\annexibraid\12ri-9. doc 12-44

, CRAIDWOOD Revision 19 t 12.4.6 Dose Limits for Members of the Public Ooerability Reauirements l 12.4.6.A The licensee shall conduct operations such that the TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 mrem in a year. In addition, the dose in any unrestricted area from external sources does not exceed 2 mrem in any one hour. The Effluents Program shall implement monitoring, sampling and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and ;

parameters in the ODCM.

Apohcabthty At all times.

AGil0Il

1. If the calculated dose from the release or exposure of radiation meets or exceeds the 100 mrem / year limit for the MEMBER OF THE PUBLIC, prepare and submit a report the Commission in accordance with 10CFR20.2203.

2. If the dose in any unrestricted area from extemal sources of radiation meets or exceeds the in any one hour limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Commission in accordance with l

10CFR20.2203.

Surveillance Rannirements -

4 12.4.6.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to determire '

p compliance with the 100 mrem / year limit in accordance with the ODCM. In addition l

Q evaluate and/or determine if direct radiation exposures exceed 2 mrom in any hour in unrestncted areas. ;

Bases 12.4.6.C This secten applies to direct exposure of radioactive materials as well as radioacta- i materials released in gaseous and liquid effluents.10CFR20.1301 sets forth the 1: ,

mrem / year dose limit to members of the public; 2 mrom in any one hour limit in the I unrestncted area; and reiterates that the licensee is also required to meet the '

40CFR190 standards.10CFR20.1302 provides optons to determine compliance te 10CFR20.1301. Compliance to the above operability requirement is based on 10CFR20,40CFR190 and Braidwood Station Technical Specifications. )

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I g%aiodemiannextraid\12ri-9. doc i

12-45

i BRAIDWOOD Revtsion 1 @

June 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i 12.5.1 Monitorina Proaram Operability Reauirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Acolicability: At all times.

Action

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 12.6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person / business who participates in this program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered, if the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person / business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sarnpling schedule will be desenbec in the Annual Radiological Environmental Operating Report.

2. With the level of radioactivity as the result of plant effluents in an environmer' e sampling medium at a specified location exceeding the reporting levels of Tat -

12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Spe Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the pote annual dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in tiie sampling medium, this repe shall be submitted if:

concentration (1) , concentration (2) + ...>1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 12.5-2 are detected and are tre result of plant effluents, this report shall be submitted if the potential annual dose

to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. Th6 report is not required if the measured level of radioactivity was not the result s plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report requiree by Section 12.6.1.

"The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

{ }

g%sbdcrmannextrekn12ri-9. doc 12-46 1 I

. CRAIDWOOD Revision 19 June 1996

'12.5 RADIOLOGICAL ENVIRONMENTAL MON!TORING PROGRAM _ (Continued)

3. If the sample type or sampling location (s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable attemative sampling media for the pathway of interest and/or specific sampling locetions for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Prepare and submit a controlled version of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.

Surveillance Reauirements 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides '

representative measurements of radiation and of radioactive materials in those f exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station O operation. This monitoring program implementsSection IV.B.2 of Appendix i to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring l program is provided by the Radiological Assessment Branch Technical Position on '

Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program ,

changes may be initiated based on operational experience. l The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 l are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact lim t for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem. 40. 586-g3 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

l l

g:WawdomwmentranM2ri-9. doc 12-47 J

BRAIDWOOD Revision 1.9 June 1996 e

12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

ID[eroretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking.

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g.Wabdcmunnextraid\12ri-9. doc 12-48

BRA D Revision 1.9

June 1996 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

1. Airbome Samples from a total of eight locations: Continuous sampler operation Radiciodine Canister Radioiodine and with partculate sample collection 1-131 analysis biweekly Particulates a. Indicator- Near Field weekly (or more frequently if on near field samples and required due to dust loading), control.<2)

Four samples from locations within 4 km (2.5 mi) and radioiodine canister in different sectors. collection biweekly. Particulate Samoler Gross beta analysis

b. Indicator- Far Field followinglweekly filter change and gamma Three additional locations within 4 to 10 km (2.5 isotopic analysis")

to 6.2 mi) in different sectors. quarterly on composite filters by location on near

c. Control field samples and control.8 One sample from a control location within 10 to l 30 km (6.2 to 18.6 mi). 4 g e a o3cm annt.1:aa tr . ,1, 12-49 1

C'RAIDWOOD Revision 1.9 June 1996 l TABLE 12.5-1(Continued) l l

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

2. Direct Forty routine monitonng stations either with a Quarterly Gamma dose on each Radiation

thermoluminescent dosimeter (TLD) or with one TLD quarterly.

instrument for measuring dose rate continuously, l placed as follows:

a. Indicator-Inner Ring l (100 Series TLD)

One in each meteorological sector, in the general area of the SITE BOUNDARY (0.1 to 3.8 miles);

b. Indicator- Outer Ring (200 Series TLD)

One in each meteorological sector, within 6.1 to 10 km (3.8 to 6.2 mi); and

c. Other One at each Airtome location given in part 1.a.

and 1.b.

The balance of the TLDs to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access.

(300 Series TLD) g4 mannextrauh12rl-9 doc I

i q BRA Revision 1.9 %

i June 1996 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS i 2 Direct d. Control Quarterly Gamma dose on each Radiation"(Cont'd) TLD quarterly.

One at each Airborne control location given in part 1.c .

3. Waterbome a. Indicator Quarterly Gamma isotopic"3and

a. Ground / Well intium analysis quarterly.

Samples from two sources only if likely to be affected."

b. Drinkingm 7

a. Indcator Weekly grab samples. Gross beta and gamma l isotopic analyses"8 on l One Sample from each community drinking monthly composite; ;

water supply that could be affected by the tntium analysis on ;

station discharge within 10 km (6.2 mi) quadedy composite. j downstream of discharge. I

c. Surface If no community water supply (Drinking Water) Weekly grab samples. Gross beta and gamma !

Water

exists within 10 km downstream of discharge isotopic analyses"3 on y then surface water sampling shall be performed monthly composite; intium analysis on . l

a. Indcator quarterly composite.

One sample downstream

d. Control a. Coritrol Weekly grab samples. Grou beta and gamma l Sample

isotopic analyses"8 on !

One surface sample upstream of discharge monthly composite; !

intium analysis on quarterly composite. ,

g wawcmunnenwaet2n-9 aoc 12-51 ,.

BRAIDWOOD Revision 1.9 June 1996 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDIOR SAMPLE AND SAMPLE LOCATIONSm FREQUENCY FREQUENCY OF ANALYSIS

e. Sediment a. Indicator Semiannually. Gamma isotopic At least one sample from downstream

area ,

within 10 km (6.2 mi).

4. Ingestion a. Indicator Biweekly

when animals are on Gamma isotopic

and pasture (May through October), 1-131"* analysis on each

a. Milk

Samples from milking animals from a monthly at other times sample.

maximum of three locations within 10 km (6.2 (November through April).

mi) distance.

b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi).

b. Fish a. !ndicator Two times annually. Gamma isotopic analysis

on edible Representative samples of commercially and portions c

recreational!y important species in discharge j area.

b. Control Representative samples of commercially and recreationally important species in control locations upstream of discharge.

g wa nnexeraea2r b9 aoc 12 '

o V

a BRA N D Revision 1.9 DV June 1996 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS"3 FREQUENCY FREQUENCY OF ANALYSIS

c. Food Products a. Indicator Annually Gamma isotopic")

analysis on each sample.

Two representative samples from the principal food pathways grown in each of four major quadrants within 10 km (6.2 mi):

At least one root vegetable sample"4 Atleast one broad leaf vegetable (or vegetation)ou b Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi).

g *amennannexaaiduzo 9 um 12-53

BRAIDWOOD Revtsbn 19 '

June 1996 .

TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every i

sample location in Table 12.5-1 of the ODCM Station Annexes. Refer to NUREG-0133, l

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." l October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. l (2) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its

)

origin in airbome effluents from the station, or at the discretion of the Radiation Protection l Director.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta j activity in air particulate samples is greater than 10 times the yearly niean of control samples, gamma isotopic analysis shall be performed on the individual samples. '

(4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

The 40 locations is not an absolute number. The number of direct radiation monitoring j

stations may be reduced according to geographical limitations; e.g., if a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) The " downstream" sample shall be taken in an area beyond but near the mixing zone.

The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence.

(8) If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all mdk sampling may be discontinued.

(9) Biweekly refers to every two weeks.

(10) 1-131 analysis means the analytical separation and counting procedure are specific for l this radionuclide. ,

! i (11) One sample shall consist of a volume /weignt of sample large enough to fill contractor '

specified container. I g;)kaiodem\annexibraid\12r1-9.do 12-54

BRA D Revision 1.9 June 1996

TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCill) OR GASES (pCi/m') (pCi/kg, wet) (pCill) (pCi/kg, wet)

H-3 20,000W Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2* 0.9 3 100 i

Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

(2) If no drinking water pathway exists. a value of 20 pCi/l may be used

_ - - - _ _ _ _ _ _ _ _ _ - _ . . - - _ - . _ - . _ . . - _ _ . _ _ - - . _ - _ _ _ - _ - - - - _ _ . - - . - - _ - - - - - - _ - _ - . - _ ~---+: -

BRAIDWOOD Revision 1.9 June 1996 TABLE 1? 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS")

LOWER LIMIT OF DETECTION (LLD)M'3 WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/I) OR GASES (pCi/m') (pCi/kg. wet) (pCill) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 1000 H-3 200 Mn-54 15 130 Fe-59 30 260 Co-58.60 15 130 Zn-65 30 260 Zr-Nb-95 15 l-131r> 1/15") 0.07 100 0.5/50' 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 ' 18 80 180 Ba-Lc-140 15 -

15 l

~

BRAIDWOOD Revision 1.9 June 1996 v TABLE 12.5-3 (Continued) I DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended 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.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive materialin a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:

4.66 S, + 3/t, ,

LLD =

(E) (V)(2.22) (Y) (exp (-ut))

i 4.66 S.

q LLD -

Q (E)(V)(2.22)(Y)(exp (-ut))

l Where: 4.66 S n 3/t, t LLD = the "a priori" Minimum Detectable Concentration (picoCuries per unit mass or volume), j so = the standard deviation of the background counting rate or of the counting rate of a blank sar : - s ,

appropriate (counts per minute), ,

l

= JTotalCounts !

l ts ,

E = the counting efficiency (counts per disintegration).

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

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec"),

g?a\odem\ennextraed\12ri 9 doc 12-57

v .

BRAIDWOOD Revision 19 June 1996 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS to = counting time of the background or blank (minutes), and At = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).

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

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contnbuting factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(4)lf no drinking water pathway exists, the value of 15 pCi/l may be used.

(5) A value of 0.5 pCi/l shall be used when the animals are on pasture (May through October) and a value of 5 pCi/l shall be used at all other times (November through April).

(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide.

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CRAIDWOOD Revision 19 ,

June 1996 a

12.5.2 Land Use Census Ooerability Reauirements >

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12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the i

d location in each of the 16 meteorological sectors

of the nearest milk animal, the nearest ;

residence **, and an enumeration of livestock. For dose calculation, a garden will be assumed at

the nearest residence.

i Aophcabihty At all times.

Action 4 i

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose !

4 commitment, via the same exposure pathway 20% greater than at a location from which i samples are currently being obtained in accordance with Section 12.5.1, add the new l

location (s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11. The sampling location (s), excluding the control location, having the lowest j calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from

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this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling

locations.

. *This requirement may be reduced according to geographical limitations; e.g. at a lake site P

where some sector's will be over water. !

- The nearest industrial facility shall also be documented if closer than the nearest residence Surveillance Reauirements 12.5.2.8 The Land Use Census shall be conducted during the growing season, between June 1 and 0; ber l

1, at least once per 12 months using that information that will provide the best results. such as rn ;

a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The resu is :f 3 the Land Use Census shall be included in the Annual Radiological Environmental Operatirg l Report.

Amane 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the 5. T '

BOUNDARY are identified and that modifications to the Radiological Environmental Mon.te' q Program given in the ODCM are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50 M annual garden census will not be required since the licensee will assume that there is a garcen at the nearest residence in each sector for dose calculations.

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CRAIDWOOD Revision 19 j

June 1996 l 12.5.3 Interfaboratory Comoarison Procram i Ooerabihtv Recuirements 12.5.3. A Analyses shall be performed on radioactive materials supplied as part of an ;

interlaboratory Comparison Program that correspond to samples required by Table l

12.5-1. j 1

Acolicabilitv: At all times.

Action

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

Surveillance Reauirements 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.3.C The requirement for participation in an Inte" boratory Comparison Program is provided to ensure that independent checks on the i ecision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the l l quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

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~l BRAIDWOOD Revision 1.9 l June 1996

\

12.6 REPORTING REQUIREMENTS !

12.6.1 Annual Radiolnaie=1 Environmental Ooeratina Reoort* I Routine Annual Radiological Environmental Operating Report covering the operation of ,

the Unit (s) during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements ;

taken during the period pursuant to the locations specified in the tables and figures in ;

Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch ;

Technical Position, Revision 1, November 1979. In the event that some individual results ,

are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

l The reports shall also include the following: a summary description of the Radiological O Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11,1-1; discussion of environmental :

sample measurements that exceed the reporting levels of Table 12.5-2 but are not the i result of plant effluents. discussion of all analyses in which the LLD required by Table !

12.5-3 was not achievable; result of the Land Use Census required by Section 12.5 2. an !

the results of the licensee participation in an interiaboratory Comparison Program and tre :

corrective actions being taken if the specified program is not being performed as requireo by Section 12.5.3. l t

A single submittal may be made for a multiple unit station. I i

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1241

BRAIDWOOD Rsvision 19 June 1996 12.6 REPORTING REQU1HEMENTS (Cont'd) 12.6.1 Annual Radiological Environmental Ooeratina Reoort (Cont'd)

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourty meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distnbutions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from,the Unit or Station during tne previous calendar year. This report shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation, for the previous calander year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."

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BRAIDWOOD Revision 19 June 1996 N 12.6 REPORTING REQUIREMENTS (Continued) 12.6.2 Annual Radioactive Effluent Release Reoort" Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year operation shall be submitted prior to May 1 of the following year.

The Annual Radioactive Effluent Release Reports shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g, cement, urea formaldehyde).

The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to areas beyond the site boundary of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluerit Release Reports shallinclude any changes made dunng the reporting period to the PCP, as well as any major changes to Liquid, Gaseous or Sota e

N Radwaste Treatment Systems, pursuant to Section 12.6.3.

The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2 2 respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively "A single submittal may be made for a multiple unit station The submittal should como.m .

those sections that are common to a!I units at the station; however, for units with separate radwaste systems, the submittal shall spect'y the releases of radioactive material from eaca unit.

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BRAIDWOOD Rsvision 19 June 1996 12.6 REPORTING REOUIREMENTE (Continued) l 12.6.3 Offsite Dose Calculation Manual (ODCM) l l

12.6.3.1 The ODCM shall be approved by the Commission pnor to initial implementation.

12.6.3.2 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2. This documentation shall contain:

1. Sufficient information to support the change together with the appropiate analyses or evaluations justifying the changes (s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20,160,40 CFR Part 190,10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the Onsite Review and I nvestigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and investigative Function.

c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM or updated pages if the Commission retains a controlled copy.

If an entire copy of the ODCM is submitted, it shall be submitted as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the date (e.g., month / year) the change was implemented.

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BRAIDWOOD Revision 1.9 June 1996 12.6 REPORTING REQUIREMENTS (Continued) 12.6.4 Mgor Changes to Licuid and Gaseous Radwaste Treatment Systems *

- Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4) An evaluation of the change which shows the predicted releases of radioactive matenais in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those preve estimated in the License application and amendments thereto; i

6) A comparison of the predicted releases of radioactive materials, in liquid and gasec .

effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change

8) Documentation of the fact that the change was reviewed and found acceptable b, Onsite Review and investigative Function.

b. Shall become effechve upon review and acceptance by the Onsite Review and Investigative Function.

Licensees may Eoose to submit the information called for in this section as part of the annual FSAR update.

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. BRAIDWOOD Revision 1.9 June 1996 APPENDIX F BRAIDWOOD ANNEXINDEX REVISION 1.9 l

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BPAIDWOOD Revision 1.9 -

June 1996 APPENDIX F STATION SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 TABLE OF CONTENTS PAGE

~ F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 O 1 I

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BRAIDWOOD Revision 1.9 June 1996 O APPENDIX F LIST OF TABLES NUMBER TITLE PAGE F.1 Aquatic Environmental Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 ' Average Wind Speeds F-5 F-5 X/O and D/O Maxima At or Beyond the Unrestricted Area Boundary F-6 F-Sa X/O and D/Q Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/O at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors .

Based on 1 cm Depth at the Unrestricted Area Boundary for Selected Nuclides F-9 F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F-24 Supplemental Tables A Mixed Mode Jaint Frequency Distribution Table Summaries - 203 and 34 Foot Elevation Data F-39

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class B Ground Level Joint Frequency Distribution Table Summaries F-43

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class

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BRAIDWOOD Revision 1.9 .

June 1996 APPENDIX F LIST OF FIGURES NUMBER TITLE PAGE F-1 Unrestricted Area Boundary F-45 F-2 Restricted Area Boundary p_4g i

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. 1 BRAIDWOOD Revision 1.9 June 1996 O APPENDIX F STATION-SPECIFIC DATA FC R BRAIDWOOD UNITS 1 AND:!

F.1 INTRODUCTION This appendix contains data relevant to the Braidwood site. Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment.

F.2 REFERENCES

1. Sargent & Lundy, Nuclear Analysis and Technology Division Braidwood Calculation No.

ATD-0149 Revisions 0,1,2, and 3,3/30/95 for Braidwood.

2. " Assessment of the impact of Liquid Radioactive Effluents from Braidwood Station on Proposed Public Water intakes at Wilmington, Illinois", J.C. Golden NSEP, January 1990. 1

3. ' Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite ,

Dose Calculations," NUS Corporation,1988. ;

4. ' Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group,1992.

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BRAIDWOOD Revision 1.9 -

June 1996 Table F-1 4 Aquatic Environment Dose Parameters I

General informatiDD There is no irrigation ocurring on the Kankakee River downstream of the station.

Recreation includes one or more of the following: boating, waterskiing, swimming, and sport fishing.

Downstream dams are within 50 miles of the station. One is located on the Kankakee. The other is the lilinois River at Dresden Island, Marseilles and Starved Rock. The Kankakee River flows into the Illinois River about 12 river miles downstream of the station.

This is based on information in Figure 2.1-13 of the Braidwood Environmental Report and in Section 2.4.1.1 and Figure 2.4-2 of the LaSalle Environmental Report.

Water and Fish Incestion Parameters Parameter

Value U", water usage, Uhr 0.042 U', fish consumption, kg/hr 2.4E-3 1/M*,1/M' O.25,1.0 F*,cfs 3950 F',cfs 5.63E3 t', hr" 24.0 t*, hr' 3.0 Limits on Radioactivity in Unorotected Outdoor Tanks8 Outside Temporary Tank 5 10 Ci' (per Technical Specification 3.11.1.4)

The parameters are defined in Section A.2.1 of Appendix A.

t'(hr) = 24 hr (all stations) for the fish ingestion pathway

t* (hr) = 3 hr (distance nearest potable water intake. to Wilmington, is 4 river miles downstream; a flow rate of 1.4 mph is assumed)

' See Section A.2.4 of Appendix A.

Tritium and dissolved or entrained noble gases are excluded from this limit. l a

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a; BRAIDWOOD Revision 1.9 June 1996 l Table F-2 Station Characteristics STATION: Braidwood LOCATION: Braceville, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)

1) Release Height = m 2) Diameter = m Exit Speed = ms" d

3) 4) Heat Content Kcal s )

CHARACTERISTICS OF VENT STACK RELEASE POINT

1) Release Height = 60.66 m* 2) Diameter = _.2JQ_.m

3) Exit Speed = 11.0 ms"*

CHARACTERISTICS OF GROUND LEVEL RELEASE !

1) Release Height = 0 m I

2) Building Factor (D) = 60.6 m' ,

METEOROLOGICAL DATA l AJ2D_ft Tower is Located .521mEE.of vent stack release point i Tower Data Used in Calculations Wind Speed Differential i Release Point and Direebon Temperature l i

Elevated (NA) (NA) j Vent 203 ft 199-30 ft Ground 34 ft 199-30 ft l

I Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections !

B.3 through B.6 of Appendix B.

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BRAIDWOOD Revision 1.9

June 1996 Table F-3 Critical Ranges Unrestricted Area Restricted Area Nearest Dairy Farm Boundary

Boundary Nearest Resident" within 5 Miles

Direction (m) (m) (m) (m)

N 610 305 800 None NNE 914 265 2800 None NE 792 299 1100 None ENE 701 361 1200 None E 1036 355 1200 None ESE 2713 425 3500 None SE 3414 448 4300 None SSE 3444 540 5300 None S 4633 530 6700 None SSW 975 540 2000 None SVV 632 632 600 None WSW 555 555 800 None VV 518 500 600 None WNW 503 434 600 None NVV 495 428 600 None NNW 510 442 600 None See Updated Final Safety Analysis Report Table 2.1-1a and Environmental Report. Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B 6 of Appendix B.

1995 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.

1995 annual milch animal census, by Teledyne isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters.

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BRAIDWOOD Revision 1.9 June 1996 Table F-4 Average Wind Speeds Average Wind Speed (m/sec)'

Downwind Direction Elevated" Mixed Mode Ground Level" N 7.6 6.0 4.7 NNE 7.5 5.8 4.4 NE 6.1 5.3 3.9 ENE -

6.2 5.2 3.7 E 6.6 5.4 4.0 ESE 6.8 5.6 4.3 SE 6.2 5.3 3.9 SSE 5.8 5.2 4.1 S 5.5 4.9 3.6 SSW 5.5 5.0 3.7

( SW 5.3 4.8 3.3 WSW 4.7 4.2 2.4 W 5.4 4.4 2.2 WNW 6.0 4.6 2.4 NW 6.0 4.8 3.1 NNW 6.8 5.4 3.9 l

l Based on Braidwood site meteorological data, January 1978 through December 1987. Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 of Appendix B.

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The elevated and ground level values are provided for reference purposes only. Routine dose calet4ations t are performed using the mixed mode values. '

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BRAIDWOOD Revision 1.9 June 1996 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Sewalnd mised nede(vent) mete ee ere m d Levet meteese Strection mediu. x/e medlue 9/e endlus xte Sie (meters) (sec/m**3) (meters) (1/w'*2) (meters) (sec/w'*3) (1/eF*2) u 610. 1.141E-M ele. 1.MM-08 ele. 4.644E G6 3.355E-00 NME 914. 5.076E-0T 914. T.02M-M 914. 1.703E-06 1.302E-08 GE 792. 2.990E-07 792. 4.274E-09 792. 1.730E 06 1.092E-OS ESE M1. 4.201E-0T 701. 4.900E-M Mt. 2.1F4E-06 1.310E 08 E 1936. 3.104E ST 1936. 3.700E-09 1936. 1.505E 06 0.551E 09 ESE 2T13. 1.M5E-ST 2T13. 1.1ME-09 2T13. 3.990E-0T 1.MOE-09 st 3414. T.575E-08 3414. T.225E 10 3414. 2.75FE-0T 1.000E 09 ssE 3444, 4.020E SE 3444, 6.345E-10 3444, s 2.145E-0F 1.015E-09 4633. 4.06M-8B 4633, 2.644E-10 4633. 1.749E-0T 4.520E-10 seu 9F5. 1.925E-0T 975. 2.M 3E 09 9F5.

su 1.333E-06 6.701E 09 632. 5.153E-0T 632. 5.400E-09 632. 3.405E-816 1.4ME-8B usu 555. T.021E-0T 555. 4.550E-09 555.

W 5.471E-06 1.053E-8B 510. 8.901E-0T 510. 5.0ME-09 510. 5.902E-06 1.830E 8B lana 503. 1.0TFE-M 503. 6.100E-09 503. 6.472E-06 1.913E 8B NW 495. 1.001E-06 495. 0.650E-09 495. 5.501E-06 2.53FE-05 NuW 510. 1.090E-06 510. 1.105E-00 510. 5.421E 06 3.02EE-05 Braidwood Site Meteorological Data 1/78 - 12/87

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Note: Based on Reference 1 of Section F.2 and the formulas in Sectons B.3 and B.4 of Appendix B.

X/Q is used for beta skin, and inhalaton dose pathways. See Sec,tions A.1.2, A.1.3, and A.1.4.2 of Apprendix A.

D/O is used for produce and leafy vegetable pathways. Section A.1.4 of Appendix A.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest XIQ or D/O at or beyond the unrestricted area boundary (UAB) 9 , a .. - . 4 .. .

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O CRAIAD Reviza 1.9 .

June 1996 Table F-Sa X/O and D/Q Maxirna at or Beyond the Restricted Area Boundary Seemwind Mlaed Mode (Vent) Detease Grourul Levet telease tirectlen Sedlue M/4 Sedlus 9/8 Sedlue N/0 t/e (meters) (secteF*3) (asters) (1/aP*2) (aeters) (sectuP*3) (1/eF*2)

N 305. 3.764E-N 305. 4.NGE-08 305. 1.551E-05 9.62FE-08 uut N5. 3.041E-06 265. 3.055E-08 265. 1.445E-05 9.310E 08 NE 299. 1.412E-06 299. 1.473E-OS 299. 0.027E- M 4.092E-00 ENE 361. 1.N5E-06 341. 1.130E-OS 341. 6.706E-06 3.452E-OS E 355. 1.669E-N 355. 1.590E-08 355. 0.9FSE- N 4.411E 08 Est 425. 1.264E-06 425. 1.67M-08 425. 7.012E- M 4.132E-OS sf 448. 1.056E-N 440. 1.2ME-08. 445. 4.269E-M 3.1TFE-OS ssE 540. 5.596E-07 540. S.639E 09 540. 3.6T3E- N 2.25GE-OS S 538. 6.166E-0T 530. 5.425E-09 530. 4.5F6E-06 1.F45E-OS SW 540. 4.441E 07 540. 6.000E-09 540. 3.423E-06 1.740E-08 W 432. 5.153E-0T 632. 5.400E-09 432. 3.405E-06 1.494E-08 WSW 555. T.02tE-07 555. 4.55GE-09 555. 5.4 TIE-06 1.053E-08 W 500. 9.431E-0T 500. 5.209E-09 500. 4.NSE-M 1.932E-08 nand 434. 1.304E-06 434. T.394E-09 434. 0.341E-06 2.3e9E-08 W 428. 1.381E-06 428. 1.050E-08 424. 7.070E- M 3.170E-08

NW 442. 1.300E-06 442. 1.444E-OS 442. 6.SFSE N 3.T64E-08 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/O or DiQ at or beyond the restricted area boundary (RAB).

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l BRAIDWOOD Revision 1.9 June 1996 Table F-6 D/O at the Nearest Milk Cow and Meat Animal Locations within 5 miles

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Downwind Nearest Milk Cow D/O (1/m"2) Nearest Meat Animal D/O (1/m"2)

Direction Radius Mixed Ground Release Radius Mixed Ground (meters) Release (meters) Release Release N 8000 2.694E-10 4.083E-10 4100 8.404E-10 1.347E- 09 !

NNE 8000 2.158E-10 3.221E-10 8000 2.158E-10 3.221E-10 NE 8000 1.333E-10 2.015E-10 8000 1.333E-10 2.015E-10 ENE 8000 1.305E-10 1.987E-10 5300 2.604E-10 4.153E-10 E 8000 1.614E-10 2.447E-10 3700 5.792E-10 9.701E-10 l

, ESE 8000 1.962E-10 2.874E-10 3700 7.121E-10 1.134E- 09 l SE 8000 1.779E-10 2.395E-10 4300 4.998E-10 7.250E-10 l SSE 8000 1.591E-10 2.270E-10 6600 2.218E-10 3.226E-10 l S 8000 1.074E-10 1.704E-10 8000 1.074E-10 1.704E-10 SSW 8000 1.172E-10 1.757E-10 8000 1.172E-10 1.757E-10 SW 8000 1.417E-10 1.921E-10 7200 1.695E-10 2.326E-10 WSW 8000 1.143E-10 1.943E-10 6100 1.800E-10 3.169E-10 W 8000 9.700E-11 1.724E-10 4600 2.423E-10 4.659E-10 WNW 8000 9.286E-11 1.723E-10 8000 9.286E-11 1.723E-10' NW 8000 1.255E-10 2.228E-10 8000 1.255E-10 2.228E-10 NNW 8000 1.639E-10 2.781E-10 8000 1.639E-10 2.781E-10 Braidwood Site Meteorological Data 1/78 - 12/87 O O O .

BRAI OD -

Revision 1.9 June 1996 Table F-7 Maxinem Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Aree Ex--r i for Kr-83m Soarwiruf unrestricted Mined Mode (Vent) Reteese Groemd Level Reteese Strection Aree Seemd Redlue V VSAR Redius G ESAR (motore) (meters) (ared/yr)/(ist/sec) (meters) (ared/yr)/(ucl/sec) a 610. 610 1.455E-M 1.09FE-M 610. 5.33M- M 4.021E- M NME 914. 914 6.375E-05 4.002E-05 914. 2.125E- M 1.602E-M NE 792. 792. 3.020E-05 2.00dE-05 792. 2.00FE-M 1.513E-M ENE M1. 701. 5.294E-05 3.992E 05 701. 2.575E-M 1.M1E-M E 1934. 10M. 3. M3E-05 2.792E-05 1934. 1.F10E- M 1.295E- M Est 2713. 2T13. 1.129E-05 0.514E M 2F13. 3.F92E-05 2.059E-05 SE 3414. 3414. T.009E- M 5.345E-06 3414. 2.141E-05 1.414E-05 ssE 3444. 3444. 6.M7E-M 4.559E 06 3444. 1.790E 05 1.35dE-05 3 4633. 4633. 3.224E M 2.431E-06 4633. 9.260E-06 6.900E-06 ssu 975. 9F5. 2.363E-05 1.702E-05 975. 1.444E-M 1.000E-M su 632. 632. 5.930E-05 4.472E-05 632. 3.6ME-M 2.70dE-M Wsu 555. 555. 0.469E 05 4.30$E-05 555. 5.M2E-M 4.400E-M W 510. 510. 9.99fE-05 T.4F1E-05 510. 6.292E-M 4.744E M Wuw 503. 503. 1.205E-M 9.003E-05 503. 6.653E M 5.01dE-M Inf 495. 495. 1.242E-M 9.366E 05 495. 6.06dE M 4.5T4E M

~

muu 510. 510. 1.322E-M 9.90fE-05 510 6.144E-M 4.633E-M GRA10 MOOD SITE IETEGROLOelCAL MTA 1/F0 - 12/ST Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

Routine dose calculations are performed using mixed mode (vent) release data.

tesenoa.=mw.2eie i-s

BRAIDWOOD Revision 1.9 June 1996 i

Table F-7 (Continued) '

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 con Depth at the Unrestricted Area inn f- i for Kr-85m

Deesmind unrestricted Mined Nede(Vent) Release tremultevet telease Directlen Aree Sound Radius V WBAE Radius S Esas (meters) (meters) (are#rr)/(uct/sec) (meters) (are#yr)/(uct/sec) '

N 610, 410. 9.909E-M 9.590E-M 610 2.731E-93 2.614E-93 uut 914. 914, 4.979E-M 4.705E-M 914 HE 792. 792. 1.222E-03 1.171E-93 3.418E-M 3.481E-M 792. 1.1T3E-03 1.124E-03 EME M1. 791. 4.45M M 4.200E-M 791.

E 1934. 1934. 1.363E 83 1.305E-83 3.452E-M 3.320E-M 1834. 1.0ZM 03 9.809E-M Est 2713. 2713. 1.220E- M 1.174E-M 2713. 3.051E M 2.930E M st 3414. 3414. 8.179E 05 T.ST4E-05 3414. i SsE 3444. 3444. 1.970E-M 1.893E-M '

4.950E-05 4.700E-05 3444. 1.634E-M 1.5ME-M 8 4633 4633. 4.000E 05 3.851E-05 4433, 1.051E- M 1.010E- M ssu 975. 975. 2.413E M 2.32M M '

su 9F5. 9.963E-M S.400E-M 632. 632. 5.199E-M 4.999E-M 432 usu 555. 555. 1.909E-03 1.905E-83 u 4.70FE M 6.444E-M 555 3.061E-83 2.929E-83 514. 518. 6.900E-M 6.632E-M 518.

unu 503. 503. 3.001E-03 2.MFE 85 T.511E-M T.294E-M 503. 3.126E-83 2.900E-83 i

mu 495. 495. 8.39dE M 8.059E- M 495

meu 510. 510. 2.915E-93 2.700E-83 9.823E-M 8.462E- M 510 3.091E-83 2.95M -83 00A18vDe SITE BETEBROSICAL DATA 1/78 - 12/07 I

i .

i i

l s .

t CRA OD. ,

i Revision 1.9 June 1996 Table F-7 (Continued) i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area t _ r_y for Kr-85 i

i l

Soestwind therestricted Mined flode(Went) Beteese Ground Levet Selease Directlen Aree Bened Bedlue V VSAS Bedlue 8 GSAR teeters) (meters) (ared/yr)/(isl/sec) (meters) (ared/rr)/(acl/sec) a alt. ele. 1.125E 95 1.000E-85 auf 914, ele. 2.90dE 95 2.aSOE-85 914. 5.M1E-06 5.4T4E-M 914.

NE 792. 792. 1.344E-95 1.300E-05 4.192E- M 4.953E- M M2. 1.311E 05 1.26 M-95 ENE 791. 701. 5.15GE-06 4.900E-06 701.

E 1834. 1954. 1.44fE-05 1.437E-95 2713, 4.M4E-M 3.911E-M 1834. 1.145E-05 1.197E-95 EsE 2713.

sE 3414, 1.440E M 1.420E M 2T13. 3.702E M 3.579E-06 3414. 1.825E M 9.911E 0T 3414.

SSE 3444. 3444. 2.420E-96 2.534E 96 s 8.593E ST 8.310E-ST 3444. 2.181E 06 2.932E-06 4433. 4433. 5.432E 9T 5.253E ST 4433.

ssu 975. 975. 1.499E-86 1.443E 06 2.853E M 2.759E- M 975. 1.M2E-85 1.000E-95 su 632. 432. 6.990E-86 5.89FE-06 432. 2.227E-05 2.154E-05 usu 555. 555. T.858E-M T.599E- M 555. 3.400E-05 3.200E 05 W 518. 518. T.924E-06 T.M 3E- M WNW 518. 3.300E-05 3.2TdE-85 503. 503. O.499E-06 8.219E- M 543.

au 495. 495. 3.430E-95 3.317E-95 .

9.567E-06 9.251E-M 495. 3.1T4E-95 3.069E-05 muu 510 510. 1.82SE-85 9.909E-86 518. 3.395E-95 3.281E-85 00AIStAMB slTE SETESM001 CAL MTA 1/75 - 12/ST l

l l

l EPSPROJ/odcm/tneaikt 8 F-11 <

BftAIDWOOD Revision 1.9 4 June 1996 Table F-7 (Continued) !

adsmsm Offsite Finite Plume Gamma Dose Factors Based on 1 cne Depth at the Unrestricted Area Bounsfary for Kr- -

i penewiruf Wrirestricted Rimed stede(Vent) Release arensed Level Rolesee i

Direction Aree teamd Radius V VRAR Redlus 8 SBAR (metere) (meters) tared /yr)/(uct/sec) (meters) tared /yr)/(ucl/sec) a 610. 610. 3.3tM-03 3.21FE-03 610. S.000E 03 T.85M-03 NME 914. 914. 1.650E-03 1.642E-03 914. 3.M 9E-03 3.54M 83 NE 792. F92. 1.249E-83 1.21M-83 42. 3.373E-03 3.275E-03 ENE M1. Mt. 1.516E-83 1.472E-93 701. 4.STFE-03 3.95aE 83 E 1936, 1936. 1.150E-03 1.11M-83 1936. 2.954E-03 2.868E-03 ESE 2713. 2713. 3.MEE-M 3.834E-M 2T13. 8.084E-M T.M9E-M !

SE 3414. 3414. 2.559E-M 2.486E-M 3414, 4.691E-M 4.555E-M t

3444. 3444. :

SSE 2.231E-M 2.16M-M 3444. 4.090E-M 3.979E-M s 4&33. 4433, 1.162E-M 1.129E M 4633.

2.055E-M 1.99st-M '

SSW 975. 975. 8.25M-M S.015E-M 975. 2.4TFE-03 2.405E 83 '

SW 432. 432. 1.758E-83 1.MM-83 632. 5.625E-83 5.462E-03 WSu 555. 555. 2.229E-83 2.165E 83 535. l

8. M3E-03 8.450E-83

w 518. 518. 2.2ME-83 2.218E-83 518. 8.931E 03 8.671E-83 .

Wuu 503. 503. 2.431E-83 2.360E-03 503. 9.052E-03 8.78pE-03 '

[

uw 495. 495. 2.F92E-83 2.711E 83 495. 8.646E-03 8.395E-83 muu 510. 510. 2.982E 03 2.Spdf-03 519. 9.023E-83 8.M1E-93

~

l 30AISWDDB stTE SETEOROLOBICAL MTA 1/75 - 12/ST f

i i

r r

i

- t i

g wawcmanne 1;ia*1 te l 9 'Im j

e 4 _ _

e. .,

N BRAIDWOOD .

Revision 1.9 June 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr 48 sounuind unrestricted Nimed Mode (Vent) Release Grenaul Level Release Directlen Area Sewuf Sadlue V VSAR Radius 4 GSAR (meters) (meters) (ered/yr)/(ucl/sec) (meters) (ared/yr)/(ucl/sec) u ele. 618. T.99FE 03 T.TF2E-83 610.

NME 914. 914. 1.960E 02 1.911E-02 4.019E-93 3.90GE-03 914 8.899E-03 8.444E 03 HE 792. 792. 3.059E 03 2.9F4E-03 792.

ENE 701. 701. 8.441E-83 8.199E-03 3.725E-03 3.621E-03 701. 9.S NE-83 9.588E-03 E 10M. 10M. 2.873E 03 2.790E-93 1936 ESE 2F13. 2713. T.3ME-83 T.182E-03 SE 3414, 1.022E 93 9.M IE M 2T13. 2.215E-03 2.152E-95 3414. 6.859E-M 6.678E-M 3414 SSE 3444 3444 1.39dE-83 1.35FE-83 5.929E M 5.764E-M 3444 1.185E-93 1.151E-03 s 4633. 4633.

ssu 975 3.30lf M 3.218E- M 4433. 6.90FE-M 6.792E-M 975. 2.06eE 03 2.009E 03 9F5 su 632. 6.46aE-03 6.281E 83 632. 4.389E-83 4.26FE-83 632 usu 555. 1.422E-82 1.381E 92 555. 5.589E 03 5.433E-83 555.

W 518, 2.182E-82 2.119E-82 514. 5.40FE-83 5.449E-83 514.

uuW 503. 503. 2.20M-92 2.141E-82 5.MFE 03 5.TF9E-03 543 2.232E-82 2.16FE-82 NW 495 495. 6.894E-03 6.622E-83 495 2.09FE-82 2.03eE-02 -

muu 510. 519. T.26M-83 T.888E-83 510. 2.215E-82 2.151E-82

.i BRAleWest SITE NETEOROLOGICAL DATA 1/78 - 12/ST l

l EPSPROJmdtmbaas e t e F-13

BRAIDWOCD.~ Ravision 1.9 l

June 1996 r

TatWe F-7 (Continued)

Maximum OffsNe Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Aree Boundary for Kr-89 i

(

Downulful Unrestricted Nined Nede(Went) Release Grenaud Level Release Directlen Aree Botsul Bedlue V VSAR Redlue G ESAR !

(motore) (aeters) (aradryr)/(di/sec) (meters) (ared/yr)/(Wl/sec) i n 6tc. 610. 4.323E-03 4.199E-03 ele. T.65M-03 7.43M-83 i uuE 914. 914. 1.492E-03 1.H3E-93 914. 2.H 5E-03 2.569E-93 NE 792. F92. 1.385E-03 1.260E-83 792. 2.219E-03 2.155E-03 i

ENE 791. 701. 1.5TFE-03 1.532E 83 701. 3.014E-03 2.929E 03 i E 1936. 1036. 9.092E-M 8.833E-M tem. 1.38FE-93 1.34FE 83 2713. !

ESE 2F13. 1.148E-M 1.100E-M 2713. 9.T20E-05 9.442E 05 SE 3414. 3414. 4.392E-05 4.244E-95 3414. 2.903E-OS 2.09FE-05 i SSE 3444, 3444, 3.822E-05 3.712E-95 3444.

i 3.0F9E 05 2.990E-05 i 5 4633. 4633. 9.02FE-M 8.769E-M -4633.

l 6.190E M 6.821E M !

SSW 975. 975. 6.764E-M 4.5F1E- M 975 . 1.0 Mk-03 1.83M 83 SW 632. 432, 1.750E-03 1.700E-SI 632.

3.181E-03 3.009E-93 ;

USW 555. 555. 2.009E 03 1.951E-03 555. 4.400E-03 4.475E-03 '

W 518. 510. 2.170E-03 2.100E-03 518. 4.M 9E-83 4.00FE 03 Wuu 503. 503. 2.410E-93 2.341E 83 583. 5.589E-03 5.420E-03 NW 495. 495. 3.22FE-03 3.134E-83 495. T.220E-03 T.020E-03 i Nuu 510. 510. 3.714E-83 3.400E 03 514. T.T35E-03 T.512E-83 p

GRAISWDm SITE IETEGROLOS8 CAL DATA 1/FO - 12/ST s

\

g *aodcrmannen oa,a ta i 9 out

{

~

CRA3OOD '

O -

Revision 1.9 June 1996 Table F-7 (Conthiued) aEanimum Offshe Finite Plume Gamma Dose Factors Based on 1 cm Depth at the IJnrestricted Area E zzfz y for Kr-90 Seeriwind tairectricted Nimed Nede(Vent) Reteese Greased Levet teteese Directlen Aree Beased Redius V VSAR tedius E . ESAR (asters) (moters) (aradryr)/(ucl/sec) (meters) (aredryr)/(uct/sec) m 619 ele. 8.574E-M 8.31FE-M 619. 9.142E-M 5.063E-M NME 914 914. 1.453E-M 1.409E-M 914.

NE 792. 1.212E- M 1.175E- M 792. 1.302E-M 1.263E-M 792.

ENE 701. 791.

1.132E M 1.090E-M 1.874E-M 1.81FE M 791. 1.634E 041.584E-M E 1834. 1834. 5.440E-05 5.384E-05 1834.

ESE 2713. 3.9NE 05 3.BF5E-85 2713. 2.691E ST 2.61GE-ST 2T13.

SE 3414. 1.795E 8F 1.7416-97 3414. 1.462E-98 1.61M-08 3414. 4.T48E 99 4.544E-09 ssE 3444. 3444.

s 2.M7E 00 2.540E OS 3444. 2.83M 08 1.972E-08 4433. 4433. 5.354E-18 5.193E-te 4633.

ssu 975. 3.7ME te 3.592E-te 9F5. 4.411E-85 4.2FM-05 975. 3.80M-85 3.400E-05 SW 632. 432. 2.254E M 2.188E- M 432.

Wsu 555. 555, 1.90DE M 1.920E M 2.200E M 2.21M M 555. 1.85M M 1.799E-M W 514. 518. 2.822E-M 2.T30E-M 518. 1.473E-M 1.622E-M -

nana 503. 503. 3.444E-M 3.341E M 585. ^

NW 495. 2.41M-M 2.339E- M 495. 5.411E-M 5.442E- M 495. 5.535E- M 5.36M- M Inal 510. Ste. 8.014E-M T.FFIE-M Ste. 9.221E-M 8.940E M BeAISMOct SITE NETEGROLOGICAL BATA 1/75 - 12/ST l

I EPSPROJbdcmtram1/kl 4 F-15 i

CRAIDWOOD t

Revision 1.9 June 1996 Tatde F-7 (Continued)

. v Madshun OffsNe Finite Plume Gamme Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m i

l

[

t seesmind unrestricted mined Itsde(vent) Reteeee troised Level Reteese alrectlen Aree tessul Redlue v Weaa medius a esaa t

(meters) teaters) (aradryr)/(ucl/sec) (motore) (ared/yr)T(uct/sec) 1 m ett. ele. 1.355E-M 1.06SE M 610. 4.922E-04 3.831E-M lust 914. 914. 6.125E-85 4.839E 05 914. 1.900E-M 1.553E-M NE 792. 792. 3,806E-95 3.031E-05 792. 1.M4E M 1.520E-M EME M1. 701. 3.15 M-85 4.BBIE-85 Mt. 2.35E -M 1.83N-M }

E 1934. 1936, 3.885E-95 3.824E-05 1836.

Est 1.4TFE-M 1.310E-M 2T15. 2T13. 1.232E-05 9.M9E-M 2T13.

4.412E-05 3.474E-85 SE 3414. 3414. S.612E- M 6.883E- M 3414. 3.044E 85 2.441E-05 SSE 3444. 3444. 6.862E- M 5.499E* M 3444. 2.3SFE-85 1.883E-05 S 4633 4633. 4.603E- M 3.6T6E- M 4633, Ssu 1.914E-s* 1.510E-95 975. 975. 2.441E-051.M9E 05 975.

su 632. 632.

1.504E-M 1.1TdE M 4.0T3E-05 4.813E 85 632. 3.620E-M 2.819E M usu 555. 555. 3.569E-85 6. N2E 05 555.

w 518 5.FB1E M 4.435E M 518. 9.574E-05 T.52FE 85 518, 5.ST4E-M 4.565E M naeu 503. 503. 1.132E- M S.SFRE 85 583.

uW 495 4.171E-M 4.790E- M I 495. 1.147E-M 9.1 TIE 85 495.

Inni 5.515E-M 4.205E M Ste. 519. 1.244E-M 9.TT7E 05 510. 5.690E- M 4.432E-M BRA 80tEW SITE IETECBOLOBBCAl. MTA 1/78 - 12/ST I

i i

t I

g ,m m e,.e. t u e ,+

i e . ___- - - - - - -

'4 0

' ~ "

BRA D -

i Revision 1.9 !

June 1996 Table F-7 (Continued)

- Maulmum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area 2xxiifor Xe-133m Dessutrue threstricted Mined Nede(vent) Delease

~

Ereissa Level Release Directlen Aree Sensul Radius V VSAR Radius G ESAR (motors) (aeters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uct/sec) u ele. ele. 2.561E-M 2.22M-M 610 8.254E-M T.823E-M NmE 914. 914. 1.216E-M 1.MM M 914 3.481E-M 2.904E-M NE 792. 792. 8.185E-05 T.244E-85 F92 3.399E-M 2.912E-M ENE N1. M1. 1.05M-M 9.2T4E 05 M1 4.81FE-M 3.426E-M E ttM. 10M. 8.032E-05 T.091E 05 tem. 2.MM-M 2,524E-M EM 2T13. 2F13. 2.74M-85 2.446E 85 2713. 8.394E-85 7.303E-85 SE 3414. 3414. 1.900E-05 1.69FE-85 3414 5.806E 85 5.06eE-85 stE 3444. 3444. 1.562E 85 1.3ME-05 3444 s 4.609E-05 4.822E-05 4633. 4433. 1.005E-95 8.929E 06 4633 3.632E-05 3.1T1E-85 ssu 975. 9F5. 5.390E-95 4.700E-95 9F5 su 2.651E-M 2.2T6E-M 632. 432. 1.24 M-M 1.092E M 632. 6.991E-M 5.186E-M usu 555. 555. 1.679E-M 1.466E-M 555 u 518.

9.480E M 8.060E M 518. 1.799E-M 1.540E M 518 9.650E-M 8.185E-M sasu 503. 505. 2.046E-M 1.76M-M 543 1.001E-93 8.459E-M mW 495. 495. 2.185E-M 1.8ME-04 495 9.06FE M T.683E- M mm Ste. 510. 2.33FE-M 2.82FE*M 519 9.48FE M 8.859E-M BRA 30WDS SITE MTEOROLesICAL NTA 1/N - 12/ST EPSPROJedenstrad/6 8 8 F-17

l I

BRAIDWOOD Revision 1.9 ;

June 1996 Table F-7 (Continued) ,

Maximum Offsite Finite Plume Gamme Dose Factors Based on 1 ces Depth at the Unrestricted Area N ir for Xe-133 seeswirug threstricted aimed feede(Vent) Release i Directlen Aree tessui medlue 9 troneuf Level Reteese veAR aedius e essa (meters) (motors) (areWyr)/(uct/sec) (asters) (areWyr)/(ist/sec)

N 610. }

610. 2.824E-M 2.53dE M 619 NME 914, 914. 9.letE-M 8.050E- M 1.355E-M 1.224E-M 914 3.MIE-M 3.44eE-M NE 792. 792. 9.079E-05 8.2F3E 05 792. 3.804E-M 3.389E-M ENE M1. 701. 1.141E-M 1.052E-M M1.

E aM. seM. 4.458E-M 3.944E M i s.9:4E-e5 a.iesE-e5 issa. 3.295E-M 2.95M M ESE 2F13. 2F13. 3.0F2E-85 2.812E-05 2713. 9.583E-95 8.440E 05 SE 3414. 3414. 2.135E-95 1.953E 95 3414 SSE 3444. 3444. 4.440E-05 4.011E-95 5

1.748E-05 1.59M-95 3444, 5.275E-05 4.76M 85 4433. 4433. 1.130E*85 1.033E-05 4433 ssu 975. 9 75. 4.215E-05 3.009E-05 su 5.975E-85 5.448E-05 975. 2.9FSE-M 2.45FE*M 632. 432. 1.MPE-M 1.230E-M 432. r vsW 555. 555. 6.72dE-M 5.954E M W

1.830E-M 1.M9E-M $55. 1.M4E-93 9.224E-M !t 518. 518. 1.965E M 1.762E M 518.

upW 503. 503. 1.054E-83 9.311E-M '

2.231E-M 1.990E M 503. 1.000E-83 9.5 FEE M -

uw 495 495. 2.383E M 2.135E-M 495. 9.911E-M S.73eE-M unu 510 510. 2.563E-M 2.299E M Ste. 1. M4E 83 9.221E-M BRAlgueCD SITE NETEGAOLOGICAL DATA 1/F3 - 13f37 I

i i

a..... ... .

e "o

~

l

e. I

BRAIDWOOD ,

Revision 1.9 June 1996 Table F.7 (Continued) i -

Maximum Offste Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Aree Ex i f t or Xe-135m peeswisid tairestricted Mised stede(Went) Release erewuf Levet notenee Strectlen Aree Sewud Redlue V WBAR Redlue G ESAR (metere) (meters) (ero6/yr)/(ut1/sec) (metere) (aredryr)/(uti/sec) e ele. 610. 1.924E-03 1.054E-03 etc. 4.44M -05 4.24aE-03 NME 9 14 . 914. 9.0 TIE M 8.75GE-M 914. 1.91M-03 1.MM-83 NE 792. 792. 6.745E-M 6.509E-M 792. 1.620E-03 1.560E-93 f4E M1. 791. 8.149E M T.862E M 701. 2.191E-43 2.110E-93 E leM. 1936. 5.T18E-M 5.51GE-M 10M. 1.360E-93 1.319E 93 EsE 2T13. 2713. 1.557E-M 1.5eM M 2713. 2.479E-M 2.391E-M st 3414, 3414. 8.MM-95 S.53dE-05 3414. 1.163E-M 1.122E M sst 3444. 3444. 7.741E-05 7.472E-85 3444. 1.06 M-M 1.82M-M s 4433. 4433. 3.2TFE-95 3.163E-85 4633. 4.820E 05 3.879E-85 ssu 975. 975. 4.10 W-M 3.95M M 975. 1.811E-03 9.747E-M FW 632. 632. 8.800E-M 8.58FE- M 632. 2.532E-03 2.439E-43 Wsu 555. 555. 1.092E-83 1.054E-83 555. 3.905E-83 3.M M 43 -

W 518. 518. 1.18 M-03 1.14 M-83 518. 4.362E-03 4.200E 83 tant 543. 543. 1.306E-83 1.258E-83 583. 4.495E-83 4.327E 83 Inf 495. 495. 1.54dE-03 1.490E-05 495.

! 4.49 M-83 4.521E 03 Inne 519. 510. 1.673E-83 1.61M a3 510. 4.400E-83 4.514E 03 seatswoop SITE NETE0BOLOB4 CAL M TA 1/78 - 12/ST l

l l

t l

l I

EPSPHOJedcmbaal,bl S F-19

_ _ _ - - _ _ _ . - . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ ____.___-_________-____.___m . _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ . _ ___ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _

BRAIDWOOD.

I Revision 1.9 June 1996 l

Table F-7 (Continued)

Mexirnum onsite Finite Plume Gamme Dose Factors Based on 1 ces Depth at the Unrestricted Area T: --ir for Xe-1 Deunultad tanrestricted Rised nede(vent) Release Greed Levet toteese Direction Aree Somd Redlue V VSAR Redlue s

G GMR teetere) (meters) (ared/yr)/(ucl/sec) (aetere) (ered/yr)/(ucl/sec) a He. 6te.

l 1.35 M-43 1.30FE-05 ele. 3.6T4E 83 3.548E-03 l NME 914. 914. 4.FBIE M 4.554E-M 914

~

NE 792. F92.

1.65 N-83 1.596E-03 4.952E-M 4.75N-M 792. 1.599E-83 1.54 M-03 l EME 791. 701. 4.084E-M 5.800E M 701. ;

E 1934 1836. 1.83X-05 1.TF9E-85 4.F5M-M 4.595E M 1956 1.395E-95 1.348E-03 Est 2T13. 2713. 1.790E M 1.M4E M 2T13 SE 3414 3414. 4.32dE-M 4.141E M i sst 3444, 1.NGE-M 1.121E M 3414. 2.914E-M 2.814E-M i

3444. 9.782E-85 9.459E-05 3444.

s 4633. 4633. 2.3FFE-M 2.29FE-M ,

5.088E-85 5.674E-45 4433 1.690E-M 1.MIE-M l ssu 9F5 975. 3.32N-M 3.21FE-M su 975. 1.25 X 85 1.211E-85 i 632. 632. T.144E M 6.9tdE-M 632.

usu 555. 555. 2.70N 85 2.615E-85 9.295E M 8.8NE M 555. 4.15eE 85 4.00FE 85 ,

u 518 518. 9.4eN-M 9.991E M t

518 4.151E 05 4. tee -85 inne 5e3. 503. 1.01M 83 9.85M M 585 4.2eM 85 4.esa -85 ;

uu 495. 495. 1.139E-05 1.181E 85 :

495 3.900E-85 3.TF3E-85 3 tant 519. Ste. 1.225E-85 1.185E-85

510. 4.14dE-SS 4.822E-85 i

I seAleuses slTE NETEGROLOGICAL DATA 1/75 - 12/ST 3

i f

I i

i 9

o e O ..

BRAIDWOOD .

Revision 1.9 June 1996 TatWe F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dote Factors Based on 1 cm Depth at the Unrestricted Area E: E i for Xe-137 Seesmind unrestricted Nined Nede(Went) Gelease Orewal Level telease Strectlen Aree temd Godlus V VGAS Godlue 0

00A0 (eetere) (meters) (ered/yr)/(ucl/sec) (meters) (ared/yr)/(uct/sec) 3 410. 410. 4.340E-M 6.154E M 610. 1.202E-03 1.164E-03 uuE 914. 914. 2.570E M 2.494E-M 914. 4.345E- M 4.205E-M mE 792. 792. 1.950E-M 1.00FE-M 792. 3.MSE-M 3.522E-M ENE 701. 701. 2.355E-M 2.279E-M 701. 4.97FE-M 4.014E-M E 1934. 1936. 1.40FE M 1.361E M 1836, 2.400E-M 2.322E-M ESE 2713. 2F13. 2.M2E-051.9FaE 05 2F13. 1.931E-05 1.060E-05 SE 3414. 3414. 0.440E-06 0.195E 06 3414. 4.393E-06 4.10dE-06 SSE 3444. 3444. T.304E 06 T.14dE 06 3444. 4.4744-06 4.265E-06 s 4633. 4433. 1.951E-06 1.00gE 06 4433. 1.45FE-06 1.410E-06 ssu 975. 975. 1.030E M 1.004E-M 975. 1.017E-M 1.753E M sw 632. 432. 2.5FFE-M 2.493E M 632. 5.24dE- M 5.0FdE-M usu 555. 555. 2.97FE- M 2.001E-M 555. T.TME-M T.519E M W 510. Ste. 3.24FE-M 3.143E-M 510. 4.446E- M 0.170E-M Wuu 503. 503. 3.635E-M 3.51FE-M 503. 9.3FIE-M 9.06FE M uw 495. 495. 4.749E M 4.615E M 495. 1.WFE 03 1.129E-03 muu 510. 510. 5.441E- M 5.265E M Ste. 1.222E 03 1.102E 03 00AIRMOS SITE IETE000LestCAL SATA 1/F0 - 12/ST EPSPROJ/odem/bradhi e F-21

BRAIDWOOD Revision 19 June 1996 Table F-7 (Continued)

Maxielum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe.138 poismind unrestricted Mined Nede(vent) Reteese around Levet Release strectlen Aree Beimd Radius v VBAR Radius a GSAR (meters) (meters) (ered/yr)/(ucl/sec) (eeters) (ered/yr)/(uct/sec) u 610. 610. 4.291E-83 4.879E 93 ele. 9.169E-03 5.890E-03 WNE 914. 914. 1.982E-03 1.925E-03 914 3.906E-03 3.869E 03 NE 792. 792. 1.506E-03 1.460E-83 792. 3.379E-03 3.290E-93 ENE 701. 701. 1.005E-03 1.75 M-03 701. 4.549E-03 4.415E-03 E 1036. 1036. 1.262E-83 1.225E-83 1836. 2.830E-03 2.747E 03 EsE 2713. 2713. 3.395E- M 3.297E-04 2713. 5.079E-M 4.931E M sE 3414. 3414. 1.926E-M 1.871E M 3414 2.381E- M 2.312E M ssE 3444. 3444. 1.685E-M 1.636E M 3444, 2.185E- M 2.121E-04 5 4433. 4433. 7.045E-05 6.M 2E-05 4633. 8.174E-05 T.937E 95 ssu 975. 975. 9.144E-04 8.000E-04 975. 2.091E-03 2.030E 93 SW 632. 632. 1.991E-03 1.934E-03 632. 5.226E-03 5.9T2E-03 Wsw 555. 555. 2.429E-03 2.359E 03 555 8.199E-03 T.957E-83 -

W 510. 518. 2.609E-03 2.534E-03 518. S.973E-03 S.700E-03 l unu 503. 503. 2.834E-83 2.751E-03 503. 9.247E-83 8.973E-03 [

uW 495. 495. 3.387E 83 3.200E-03 495. 9.733E 03 9.445E-03 muu 510. 510. 3.657E-e3 3.551E-e3 518 9.712E-03 9.425E 83 I I

sRAleuoco SITE NETEOROLOGICAL SATA 1/78 - 12/87 I i

{.

-~

i EPF"'OJ' dcmtnans 6 i e

BRAID D- ,

Revision 1.9 June 1996 Table F-7 (Continued)

~

Maximune Offsite Finite Plume Gamma Dose Factors Based on 1 cas Depth at the Unrestricted Area Ex:My for Ar-41 Densneindtetrostricted Nimed Itode(vent) Release Growd Levet Release tirectlen Aree Seimd Radius V VBAR Redless G seat testers) (set'ere) (ered/yr)/(id:l/sec) (metere) tared /yr)/(uct/sec) u ele. 419. 5.141E-93 4.9T7E-83 414. 1.283E-92 1.242E-02 IEIE 914. 914. 2.54GE-03 2.485E-83 914. 5.780E-03 5.595E-03 NE 792. 792. 1.935E 83 1.ST3E-05 792. 5.421E-83 5.248E-03 ENE 701. 701. 2.357E-83 2.282E-83 751. 6.445E-03 4.239E-03 E 18M. ISM. 1.883E-93 1.744E-83 10M. 4.745E 93 4.593E-03 Est 2713. 2T13. 6.281E M 4.000E-M 2F13. 1.352E-53 1.309E-83 st 3414. 3414. 4.120E-M 3.9NE-M 3414. 8.148E M F.800E- M ssE 3444. 3444. 3.500E-M 3.44dE-M 3444. 7.00FE-M 6.783E- M s 4633. 4633. 1.924E M 1.863E-M 4433. 3.770E-M 3.450E-M ssu 975. 975. 1.20DE-83 1.M7E-83 975. 4.467E-05 3.937E-83 su 632. 632. 2.748E-93 2.44GE 03 632. 9.104E-03 8.813E-83 -

usu 555. 555. 3.506E 03 3.392E-83 555. 1.406E-82 1.359E 82 W 518. 518. 3.542E-83 3.448E-83 518, 1.430E-02 1.304E-02 .

tani 503. 543. 3.Se6E 03 3.485E-83 583. 1.449E-82 1.483E-02 NW 495. 495. 4.358E 93 4.211E-05 495. 1.3FIE-82 1.327E-82 same Ste. Ste. 4.647E-33 4.49EE-03 510. 1.439E-02 1.393E-42 BRAISMBGB stTE NETEGROLOGICAL DATA 1/75 - 12/ST EPSPROJ/odctnbrandeti e F-23

CRAIDWOOD Revision 1.9 June 1996 Table F-7s jindmum OffsNe Finne Phame Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-83m pounuirud Restricted Mined Mode (Went) Release alrectlen Area Sound Redlue V Grossul Level Reteese WOAR Redlue S ERAR (asters) (meters) (ered/yr)/(ist/sec) (aetere) (ared/yr)/(uct/sec) a 305 305.

INIE 3.996E-M 3.012E-M 305. 1.521E-95 1.147E-03 265 265. 3.883E-M 2.920E-M 265. 1.406E-03 1.060E-03 NE 299 299.

ElIE 1.555E M 1.173E-M 299. 9.211E-M 6.M5E-M 361. 361. 1.3FIE-M 1.034E-M E 355 361. 7.062E-M 5.325E-M 355. 1.7EM-M 1.346E- M 355.

ESE 425. 425. 9.139E-M 6.891E M 1 1.505E-M 1.135E-M 425. T.634E-M 5.756E M i SE 448 444. 1.19dE M 9.017E-85 444. 4.583E-M 4.964E M SSE 544 544.

1 6.996E-85 5.275E-85 548. 4.053E-M 3.95dE-M 530 530. 4.499E-95 4.900E-05 ssu 530. 4.639E M 3.490E-M i 540. 540. 5.532E-95 4.1TM-05 su 544. 3.829E M 2.887E-M 632. 432. 5.95eE-95 4.472E-05 usu 555 432. 3.6ME-M 2.78dE-M 555. 8.469E 95 4.3adE-85 555.

u 500 500. 5.942E M 4.48AE-M unu 1.M5E-M T.8T6E-85 500. 6.646E-M 5.811E-M 434. 434. 1.497E-M 1.129E-M .

uu 434. 8.320E-M 6.273E-M 428. 428. 1.537E-M 1.159E-M Nuu 428. T.562E-M 5.732E-M 442. 442. 1.433E-M 1.231E M 442. T.667E-M 5.781E-M -

BRAIDWOOD SITE NETEGROLOSICAL M TA 1/75 - 12/37 Note:

Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and 8.6 of Appendix B.

Routine dose calculations are portormed using mixed mode release data.

EP9'mOSodcmtematti e .

s'

BftA OOD -

Revision 1.9 June 1996 TatWe F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area 2;; ir for Kr-85m l

Doeruelrud Restricted Mined Nede(Vent) Release ereund Levet noteese alrectlen Aree eeund Redlue V weak andlus a sean (metere) (metere) (ared/yr)/(di/sec) (motors) taredlyr)/(Wl/sec) u 305. 305. 2.N M 03 2.149E-83 305. 6.552E 93 6.259E-93 umE M5. 265 2.14M -c3 2.054E 83 M5.

NE 299. 299 5.920E-03 5.662E-93 1.094E 83 1.05GE-93 299. 4.111E 83 3.928E-83 ENE 361. 361. 9.4F5E M 9.997E M 361.

E 355. 355. 3.145E 03 3.025E 03 1.197E-93 1. M9E-93 355 4.ST2E 83 3.891E-03 Est 425. 425. 1.97M -93 1.031E-93 425. 3.544E 05 3.427E 83 sE 448. 448. 9.9T4E-M 8.T18E-M 448.

SSE 540 548 3.167E-83 3.829E 93 s

6.060! M 5.83dE-M 548. 2.006E-03 1.99FE-03 550. 530 5.227E-M 5.02M- M 530 seu 540 544. 2.351E-03 2.249E 93 su 4.797E-M 4.61M-M 540, 1.999E 03 1.91M -83 432. 432. 5.199E-M 4.999E-M 432.

usu 555. 1.909E-03 1.905E-83 555. 6.79FE-M 6.444E- M 555.

W 500 500, 3.061E 03 2.929E-93 7.204E-M 6.915E- M See. 3.224E 03 3.0SEE-93 wuw 434 434, 8.M7E-M E.57aE-M 434 au 420. 420. 3.744E-83 3.597E-93 9.954E-M 9.552E-M 428. 3.505E 83 3.351E 03 muu 442, 442. 1.96AE-03 1.025E-03 442 3.712E 83 3.551E-83 BRAISWDOS slTE IETEeneteelCAl. MTA 1/75 - 12/ST EPSPROJJbdcm>brekMi 8 F-25

_ -_______s

BRAIDWOOD..

Itevision 1.9 Jee 1996 !

Table F-7a (Contiswed) !

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area 5:zf_, for Kr-8 1

Deesmind Restricted Mined 80ede(Vent) Release trosed Level Release Directlen Aree Beimd Redius V VBAR Redfue +

e 884R (meters) (meters) (aradryr)/(uti/sec) (setore) (aradryr)/(ucl/sec) i u 305 305.

NME 265 2.52M-85 2.43M 85 305. 7.053E-05 6.820E 05 265. 2.309E-85 2.310E-05 265.

NE 299 299. 6.35M-05 4.141E-85 341, 1.248E-85 1.207E-05 299. 4.44 M-95 4.296E 05 ENE 361.

E 1.083E-85 1.M FE-05 341. 3.404E-05 3.29M-95 355. 355. 1.366E-85 1.320E-05 ESE 425 355. 4.396E 05 4.251E 95 425. 1.22SE 05 1.180E 05 425.

SE 448 448. 3.809E-95 3.NGE 05 1.M2E-85 1.GeBE 05 444. 3.470E 95 3.355E-05 SSE 540 540.

s 7.829E- M 6.7FFE M 548. 2.290E 05 2.215E-05

$30 538. 4.111E- M 5.909E-e6 530. 2.632E 85 2.545E-85 ssu 548 548.

su 5.594E 06 5.409E-06 544. 2.217E 95 2.144E-05 632. 632. 6.990E M 5.89M M usu 432. 2.22?E-85 2.154E-05 555. 555. 7.85EE M 7.599E- M W 500 555. 3.400E-05 3.2EEE 85 500. 8.255E-M 7.983E-M 500 wuu 434. 434. 3.541E 05 3.424E 85 NW 1.009E-85 9.757E 06 434. 4.111E-85 3.9FaE-05 42E. 428. 1.131E-05 1.993E-95 428. 3.002E 05 3.6FFE 85 :

nuW 442. 442. 1.209E-05 1.149E-85 442. 4.05dE 05 3.922E-85 BRAIDWOOD SITE NETE000 LOGICAL MTA 1/75 - 12/87 f

I l

l i

t EP" ' c m besas a1 e

BR 000 Revision 1.9 June 1996 Table F-7a (Continued) 40idmum Offsite Finite Plume Gamma Dose Factors Based on 1 cm D0pth at the Restricted Area Ex "Ly for Kr-87 Seenwind Rastricted Mined Mode (vent) Delease Scened Levet Selease Strection Aree Gened Sedlue V VSAS Sedlue G OSAR (metere) (metere) (aredryr)/(ucl/sec) (metere) (ared/yr)/(utf/sec)

N 305. 305 T.400E-03 T.M4E-03 305. 1.9T2E-02 1.91M-02 NME 265, 265 T.100E-05 4.095E-03 265. 1.002E 02 1.F49E-02 NE 299 299. 3.700E-03 3.6 TIE-03 299. 1.225E-02 1.199E 02 ENE 341. 361. 3.246E-05 3.152E-03 361.

E 355 355. 9.572E-03 9.294E-03 EsE 4.060E-03 3.M3E 03 355. 1.220E-02 1.105E-02 425. 425. 3.644E-05 3.539E 03 425.

SE 440. 440. 1.060E-02 1.037E-02 3 001E-03 2.992E-03 440.

sst 540. 540. 2.111E 03 2.050E-03 9.262E-03 0.992E-03 s 540. 4.'t9E-03 5.9F1E-03 530 530 1.742E-03 1.711E-03 ssW 530 4.549E-03 6.359E-03 540. 540. 1.664E 03 1.616E-03 540.

su 432. 432. 5.72FE*05 5.561E-03 Wsu 1.750E 031.707E-03 432. 5.625E-03 5.442E 03 555. 555. 2.229E 03 2.145E-03 555.

W $00. 500. 0.703E 03 0.450E 03 2.375E 03 2.30$E-03 500. 9.363E 03 9.09W-03 cans 434. 434. 2.903E-03 2.010E-03 uw 434. 1.090E-02 1.066E 02 420. 420. 3.315E 03 3.219E-03 420.

mwW 442. 442. 1.044E-02 1.014E-02 3.533E 05 3.431E-03 442. 1.090E 02 1.050E-02 00A7*4D00 stTE NETE000 LOGICAL DATA 1/70 - 12/07 EPSPROJodemtuud 61 e F-2 7

BRAIDWOOD Revision 1.9 June 1996 Table F-7a (Continued)

Mswimum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted i Area ": zt for Kr-se poemuirud Restricted Mined Mode (vent) Retenee Direction Aree Sensed Radius eresul Levet totenee V Vtat Redlue 8 Stat (meters) (meters) (ared/yr)/(Wl/sec) (meters) (ared/yr)/(d l/sec)

N 305. 305. 1.790E-02 1.739E 02 305. 4.712E-02 4.5FW 82 NNE 265. 265. 1.690E-82 1.658E-02 265.

NE 299. 299, 4.272E-82 4.146E-92 9.121E-SS 8. M M 93 299. 2.94FE-82 2.M M-02 ENE 361. 361. 7.060E 83 7.64 M 93 341.

E 355. 355. 2.2SIE 02 2.214E-82 9.8TM-03 9.595E 83 355. 2.920E 82 2.M M-82 EsE 425 425. 8.010E 03 8.5TM 03 425. 2.570E 92 2.50M-82 sE 448. 448. 7.516E-03 7.30E 93 444. 2.2TM-02 2.295E 42 ssE 548 548. 5.155E 83 5.912E 03 544. 1.505E 82 1.462E-82 S 530 530. 4.382E-93 4.268E 03 ssu 550. 1.666E 02 1.618E 82 540. 540. 4.992E 83 3.970E 03 540.

su 432. 632. 1.429E-02 1.300E-82 4.309E-05 4.24FE 03 632. 1.42N-92 1.381E-82 usu 555. 555, 5.58pE-93 5.43M -83 W

555. 2.182E-82 2.119E 92 -

500 500. 5.M4E 93 5.680E 03 See.

wuu 434, 434, 2.300E-02 2.24 M 82 7.074E 03 6.0T3E-83 434. 2.690E-02 2.61 M-02 MW 420 420. 8.864E-83 7.03FE-03 428. 2.520E-02 2.44M-82 .

muu 442. 442. 8.580E-83 S.33N 83 442. 2.660E-82 2.503E-42 GRAISWDOB SITE SETEGROLeSICAL DATA 1/75 - 12/87 C

..,g.. . . . m, , ..

BRA Revision 1.9 June 1996 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Aree S;;.-_ip for Kr-89 l L

i Domulvut Restricted nined Mode (Vent) Release Grownf Lovet Release Directlen Aree Se e d Redlue V WBAR Redfue E ESAR teaters) (seters) (eradryr)/(ucl/sec) (meters) (ared/yr)/(ucl/sec) i a 305 305. 1.24 M-82 1.200E-82 305. 2.61M 02 2.53GE-02 NME M5 N5. 1.21X-92 1.1 FEE-92 M5.

NE 299. 299. 2.655E-82 2.579E-02 ,

6.0 FEE-93 5.89eE 03 299. 1.43OE-82 1.39FE-82 ENE 361. 361. 4.63M -93 4.588E-03 361.

E 355. 355. 1.132E-SE 1.099E-02 5.715E-03 5.55 M-03 355. 1.340E 02 1.321E-02 ;

EsE 425. 425.

sE 5.133E-05 4.90M-83 425. 1.804E 921.85M-92 l 448 444. 4.043E-93 3.92FE-93 ssE 448. 8.014E 03 F.784E-93 !

540 548, 2.63M-03 2.541E 03 '

5 540. 5.13FE 93 4.994E-83 530 530. 1.95eE 93 1.000E-03 sw 540 530. 4.955E 83 3.93EE-03 540. 1.9 FEE 93 1.914E-03 548. [

su 632. -632. 4.039E 83 3.922E-93 1.75GE 03 1.700E SE 632. 3.181E 03 3.009E 83 ;

usu 555. 555 u

2.009E 03 1.95 M-03 555. 4.400E 03 4.4F5E-93 500 500. 2.313E-83 2.24FE 03 500, unu 434. 434. 5.385E-83 5.230E-83 3.129E-83 3.848E 03 434. T.74M-83 F.53dE-03 :

NW 428. 428. '

4.110E 83 3.993E-03 428. 9.FSEE-83 9.424E-83 unu 442. 442. 4.6FM-93 4.53FE-03 442. 1.01FE-02 9.8FM-93 I

BRAltuCS SITE NETEEBOLeulCAL DATA 1/F8 - 12/ST t-i l

1 l i

l i

E rse n v 4 4. t,...: ei e a

F ts t

BRAIDWOOD Revision 1.9 June 1996 Table F-7a (Continued)

Merimum Offsite Finite Plume Gamma Dose Factors Based on 1 cas Deptle et the Restricted Area inni:p for Kr-90 pensufrul Restricted Nined Itode(Vent) Release Greerud Level Rolesee Direction Aree Beimd Redius V VBAE Radius & GBAR (meters) (aeters) (ared/yr)/(est/sec) (aeters) tered/yr)/(ucl/sec) a 305. 305. 5.60EE 03 5.515E 93 305. 4.210E-03 7.9 ME 03 NME 265. 265. 4.05 M 93 5.NGE-93 265. 9.3F5E-03 9.007E-83 NE 299. 299. 2.447E-93 2.3F4E 93 299. 3.836E-03 3.719E-93 ENE 361. 361. 1.410E-03 1.367E-03 361. 1.M1E 031.002E-83 E 355, 355. 1.896E-83 1.BME-83 355. 2.575E-83 2.496E 03 ESE 425. 425. 1.516E-93 1.479E-83 425. 1.810E-83 1.762E-93 sE 448. 444, 1.032E 831.001E-05 448. 1.147E-83 1.112E-03 ssE 540. 540 5.10SE M 5.930E- M 548. 6.813E- M 5.830E-M s 530. 530. 3.5ME-M 3.457E-M $30.

ssu 4.307E-M 4.176E-M 540. 540 3.74M-M 3.630E-M 548. 4.345E- M 4.213E-M su 632. 632. 2.254E-M 2.186E M 632.

vsw 1.900E-M 1.920E M t

555. 555. 2.200E-M 2.212E M 555. 1.855E-M 1.799E-M

! W 500 500.

3.175E-M 3.000E-M 588. 1.971E-M 1.911E-M WNw 434. 434. 5.443E-M 5.319E-M 434. 4.559E-M 4.420E M NW 420. 428. 8.796E-M 8.532E-M 428. 9.766E-M 9.44GE M NNW 442. 442. 1.222E 03 1.185E-83 442. 1.523E 83 1.477E 83 BRAIDWOOD SITE IETEOROLestCAl. M1A 1/78 - 12/87 m

E,_.....i. g , ..

0 . t CRAAD

Revision 1.9 June 1996 Table F-7a (Contkwed)

Maulmum OffsMe FinMe Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m i

Seanuiruf Goetricted aimed Mode (Went) Gelease Grensid Levet telease Olrectlen Aree Sound Redlue V WGAS Godlus G . OSAR .

(meters) (meters) teredryr)/( W l/sec) (metere) (ered/yr)/(W I/sec) l i

N 305. 305 3.505E-M 2.001E M 305 WWE M5. M5 1.342E-03 1.MOE-03 3.471E M 2.710E-M 265 1.225E-03 9.409E-M NE 299. 299. 1.442E M 1.135E-M 299.

ENE 361. 361.

9.221E-M 6.3TFE-M 1.274E-M 1.002E M 361. 6.22FE-M 4.032E-M i

E 355. 355. 1.M4E-M 1.30FE- M 355.

ESE 425. 8.136E- M 6.311E-M 425. 1.406E M 1.100E*M 425 SE 440. 440. 6.00FE-M 5.349E- M 1.152E M 9.000E 05 440 6.093E-M 4.733E-M ssE 540 540. 6.790E-05 5.395E 05 540 3.TT2E-M 2.936E-M s 530. 530. 6.550E 05 5.1F2E 05 530. 4.533E-M 3.523E-M SSW 540. 540. 5.419E 05 4.299E-05 540.

SW 632. 632.

3.656E-M 2.046E M 6.073E-05 4.013E-05 632. 3.620E-M 2.Ol9E-M usu 555. 555. 0.5HE 05 6.762E 05 555, W 500. 500.

5.701E M 4.435E-M 1.00K M 7.904E 05 500. 6.1ME-M 4.005E-M WNW 434. 434. 1.391E M 1.000E- M 434, NW 420. 420. 7.616E-M 5.90FE-M 1.429E-M 1.121E-M 420 6.00FE- M 5.205E-M Meu 442. 442. 1.521E-M 1.1ME-M 442.

7.02FE-M 5.461E-M MAleWDB SITE MTEOROLOGICAL MTA 1/70 - 12/07 4 EPSPROJtocmbad/H 8 F-31 m

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

BRAIDWOOD Revision 1.9 June 1996 TatHe F-7a (Continued)

. Mawimum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area E:: i i for Xe-133m Doesmind aestricted Mixed Mode (vent) Release Greemd Level Release Direction Aree Bened Rodius V VBAR Redlue G GBat (meters) (aeters) (arodryr)/(ucl/sec) (meters) (ared/yr)/(ucl/sec) u 305. 305. 6.300E-M 5.411E-M 305. 2.135E-03 1.790E 03 uNE 265. 265. 6.95M-M 5.184E-M 265 NE 299. 299. 1.McE-831.632E 03 2.759E M 2.399E-M 299. 1.321E-03 1.115E-83 ENE 361. 341. 2.41FE-M 2.999E M 341, E 355. 355. 1.005E-03 S.44 M- M 3.110E M 2.69M M 355. 1.30FE-03 1.10 M 03 ESE 425. 425. 2.791E M 2.354E M 425.

SE 448. 444. 1.125E-93 9.516E-M 2.251E-M 1.964E-M 444. 9.971E- M 8.442E-M SSE 540. 540. 1.41M-M 1.M5E M 540, s 534. 530. 4.325E-M 5.379E-M 1.29M-M 1.131E M 530. 7.461E-M 6.326E M SSW 540. 540. 1.12M-M 9.809E 05 540.

su &32. 632.

4.124E-M 5.209E M 1.24M-M 1.092E M 632. 6.091E-M 5.186E M Wsv 555. 555. 1.679E M 1.446E-M 555.

W 500. 500. 9.480E-M 8.060E M 1.083E M 1.632E-M 500 1.014E-03 8.589E M

~

l WNW 434, 434. 2.4M-M 2.129E M 434 1.222E-03 1.831E 93 wu 428. 420. 2.634E M 2.2TFE M 428.

muu 442. 442. 1.10FE-03 9.360E-M 2.81M-M 2.434E-M 442. 1.157E-83 9.90M-M BRA 19WD00 SITE E TEOROLOGICAL DATA 1/78 - 12/87 L

I EPSPRohodembens/tt e F-R

l BRA _. 000 I Revision 1.9 June 1996 Tetde F-7e (Contlewed) i Bloximum Offshe Finite Plume Gemme Dose Factors Based on 1 cm Depth at the Restricted Area Sc=- _ti for Xe-133 b

i Denewiruf Restricted Nimed feede(vent) Release Greemd Levet Roteeee Direction Aree Bewid Redius V WBAR Radius 6 80AR teeters) (metere) tared /yr)/(uti/sec) (metere) tered/yr)/( w l/sec) u 305. 305 4.818E M 4.5eE-M 305. 2.299E-03 2.813E-83 uut 245. 265. 4.509E M 5.TT4E M 265. 2.004E-93 1.823E-83 NE 299 299. 2.904E-M 2.479E M 299.

Eut M1. Mt. 1.431E-03 1.254E 85 2.412E-M 2.343E-M Mt. 1.090E-83 9.5 TIE-M E 355 355. 3.343E-M 3.011E-M 355. 1.414E-93 1.M1E-03 Est 425. 425. 2.954E-M 2.45dE M 425. 1.22eE-03 1.079E-83 SE 444 448 2.44GE M 2.214E-M 448.

SSE See. 540 1.00AE-03 9.581E-M 1.555E-M 1.411E M 544. 4. NEE-M 4.15eE-M s 538 530. 1.400E-M 1.27EE M seu 530. 3.1T4E-M T.209E M 548. 544. 1.231E M 1.197E M 540.

su 632. 432. 4.754E-M 5.9T4E M

. 1.M7E M 1.23eE-M 432. 4.TadE-M 5.954E-M Wou 555 555. 1.steE-M 1.M9E-M 555. 1.M4E-03 9.224E M W 500 500. 2.855E-M 1.M2E-M See. 1.teEE-83 9.759E-M talu 434. 434. 2.409E-M 2.394E M let 434. 1.323E-83 1.140E-93 420. 428. 2.800E-M 2.557E M 425.

sent 442. 442. 1.204E 83 1.059E 93 3.0T1E-M 2.749E-M 442, 1.384E-83 1.114E 03

' BRAltuent SITE BETEGROLSSICAL SATA 1/75 - 12/ST l I i

l l

EPSPROJedcm.brast1rti e F-33

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

CRAIDWOHD Revision 1.9 June 1996 Table F-7a (Continued)

A14W[ mum Offslie Finite Plume Gamma Dose Factors Based on 1 cm Deptis at the Restricted Aree z--fzy for Doeswirut teetricted Mined Icede(Verit) Reteese scound Level Retenee Strectlers Aree Beimd Redlue V VSAR Redlue 4 ESAR (meters) (aetere) (aredryr)/(uCI/sec) (meters) (ared/yr)/(tCl/sec)

N 305. 305. 4.5NE-93 4.429E-03 305.

NNE 265 1.180E-82 1.13M-92 265. 4.30FE-03 4.22FE-83 265.

NE 299. 299. 1.125E-82 1.00M 02 2.254E-83 2.174E-83 299. T.820E-83 6.F64E*83 ENE 361. 361. 1.883E-93 1.816E-83 341.

E 355. 5.730E-83 5.52M-03 355. 2.326E-83 2.24M-93 355.

ESE 425. 7.076E-93 6.811E-03 425. 2.121E 83 2.046E-83 425. 6.001E-03 5.7FM-83 sE 444. 448. 1.72M-93 1.662E-03 448.

ssE 548 4.819E-93 4.640E-03 540 1.1 FEE-03 1.13FE-03 540.

s 538 3.220E-83 3.101E-03 530. 9.052E-M 8.F34E-M 530.

ssu 548 2.85 M-03 2.74FE-93 540 9.830E-M 8.720E-M 544.

SW 632. 2.739E-93 2.630E-93 632. 8.89EE-M 8.58FE- M 632. 2.532E-83 2.439E-83 usW 555. 555. 1.092E 831.854E-83 555. 3.989E-03 3.M 2E-93 W 500, 500. 1.246E 03 1.203E-83 500.

WWW 434 4.61FE-83 4.444E-83 434 1.59M-83 1.5365-03 434.

NW 428 5.652E 83 5.441E-83 428. 1.869E-83 1.002E-03 428. 5.820E-83 5.60M 83 NNW 442. 442. 2.013E 831.MSE 83 442. 5.812E-83 5.59dE 83 BRAIDWoop stTE 8EIEOROLO51 CAL DATA 1/73 - 12/87 l

6 O II

BRA OD. .

Revision 1.9 June 1996 Table F-7a (Continued)

Madmum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area E:z_ty for Xe-135 Dessultui Restricted Nimed Nede(Verit) Beteese Greimd Levet Release Directlen Aree Beisul Redius V VBAR Redlus G 8BAR (meters) (metere) tared /yr)/(ucl/sec) (motore) (ared/yr)/(ist/sec)

N 305. 305. 3.039E-03 2.936E-83 305. 8.709E-93 S.486E-03 NME 265. 265. 2.800E-93 2.781E-83 2M. 7.854E 83 7.583E-03 NE 299. 299. 1.481E-03 1.431E-93 299. 5.482E 93 5.292E-83 ENE 361. 361. 1.204E-93 1.M IE-83 M1. 4.211E-03 4.M5E-93 E 355. 355. 1.621E-03 1.56FE-93 355. 5.425E-03 5.23FE-03 Est 425. 425. 1.45M 831.486E-03 425. 4.794E-03 4.629E-83 SE 444. 444. 1.255E-03 1.194E-e3 448. 4.257E 05 4.110E-03 ssE 540. 540. 8.285E-M S.000E-M 544, 2.811E-03 2.714E-03 s $30. 530. 7.163E-M 6.923E-M 530. 3.19FE-93 3.087E-93 ssu 548. 540. 6.561E M 6.342E-M 548. 2.799E-03 2.615E-03 sW 632. 632. 7.144E M 6.90$E-M 632. 2.79AE 83 2.615E-03 wsW 555, 555. 9.295E-M S.896E M 555. 4.15GE 83 4.00FE-83 u 500. 500, 9.004E- M 9.473E- M 500. 4.340E-03 4.190E-03 -

land 434. 434. 1.21GE-e3 1.168E-83 434. 5.M4E-83 4.869E-83 NW 428. 428. 1.348E 83 1.302E-83 425. 4.686E-03 4.524E-03 NNW 442. 442. 1.444E-83 1.39FE-83 442, 4.98FE-05 4.815E-83 seAIGNOW stTE IETEcBOLOSICAL DATA 1/75 - 12/87 g EPSPROJtdembred/tt e F-35

BRAIDWOOD Revision 1.9 June 1996 Table F-7s (Continued)

Alaximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area EzQ for Xe-137 poiswirus mostricted Rised nede(vent) Beteese areisd Level Retenee Directlen Aree Sound Redius V WGAR Redius 8 GBAR (asters) (meters) (aredtyr)/(ucl/sec) (meters) (ared/yr)/(uCI/sec) a 305. 305. 1.TME-03 1.79M 83 305. 3.915E-83 3.7ESE-83 NME M5. M5. 1.71M -93 1.65 M-03 MS. 3.M9E-03 3.821E 03 NE 299. 299. 8.519E-M 8.244E-M 299. 2.1FRE 93 2.180E 83 ENE 361. 361. 6.624E-M 6.410E-M 361. 1.74SE-83 1.692E-83 E 355. 355. 8.157E-M T.89M-M 355. 2.180E-03 2.032E 83 i Est 425. 425. T.34M M T.14M-M 425. 1.690E-93 1.434E-03 SE 448. 444. 5.002E-M 5.415E-M 448. 1.259E-93 1.219E-03 ssE 544. 540. 3.822E-M 3.899E M 540. 8.154E-M T.990E-M s 538. 536. 2.seM-M 2.71M-M 530. 4.471E-M 6.26M-M ssu 548. 548. 2.364E-M 2.TTEE-M 548. 6.459E-M 6.25eE-M su 632. 632. 2.5TM M 2.493E-M 432. 5.246E-M 5.0 Tat M Wsu 555. 555. 2.9FM- M 2.881E- M 555. T.TT1E M T.519E-M W 500. 500. 3.45M M 3.NIE M 500. 9.141E- M 8.044E M l

Wuw 434. 434. 4.671E-M 4.520E M 434. 1.275E 03 1.234E 83 428. 428. 6.01FE-M 5.82M-M NW 428. 1.54M -83 1.493E-83 t=* 442. 442. 6.7ME M 6.56SE M 442. 1.58EE-03 1.53FE-83 l paAISWDOO SITE iETEGROLOSICAL MTA 1/75 - 12/ST I

f I

I I e

-~

EPe" denit>reas tI e

,3g -

~

BRA _ OOD ',

Revision 1.9 June 1996 Table F-7e (Continued)

MaWimum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Denewirut teatricted Mined nede(Vent) Reteeee tround Leve( Re(eese alrectlen Aree Seimd Redlue V VSAR Redlue G ESAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(ucl/sec)

N 305. 305. 1.001E 82 9.T14E 83 305.

guE 265. 2.45FE-82 2.304E-92 265. 9.55 M 03 9.2T3E 83 265. 2.34FE-02 2.2?9E-02 NE 299. 299. 5.016E-93 4.870E-83 299 361. 1.459E-02 1.416E-82 ENE 361. 4.169E-93 4.948E-83 361. 1.195E-92 1.160E-82 E 355. 355. 5.13FE-03 4.900E-03 355.

EsE 425. 1.4 TIE-92 1.42FE-02 425. 4.479E-03 4.54 M-93 425. 1.24FE 82 1.210E-82 sE 448, 448. 3.82FE-83 3.T16E-93 444. 9.982E-03 9.68FE-03 sst 544. 540. 2.630E 03 2.554E 03 548 s 4.694E-03 6.49FE-03 530. 530. 2.82M 031.964E-83 530.

ssu 540. 5.85FE-83 5.684E-93 540. 2.02 M 93 1.962E-03 540. 5.661E-03 5.495E-03 su 632. 432. 1.991E 03 1.934E 03 632.

vsw 5.226E-03 5.972E-85 555. 555. 2.429E 03 2.359E-03 555 8.199E-E3 T.95FE-93 w 500. 500. 2.T39E 03 2.659E-03 500 kuu 9.542E 03 9.221E 03 434. 434. 3.459E 03 3.358E-03 434.

su 1.164E 82 1.130E 82 428. 428. 4.09M 83 3.9F4E-83 428. i 1.20FE-02 1.1T2E-et muu 442. 442. 4.399E-03 4.2TM 03 442. !

1.204E 021.168E 02 ,

BRAltvem SITE IETEmeLeticAL DATA 1/FB - 12/Sy EPSPROJtdemtraa.tek 1 - e F-3 7

I I

BRAlOWOOD-Revision 1.9 June 1996 Tot >le F-7a (Continued)

Maximum Offsite Finita Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Seemuirud Restricted Mlaed Mode (Vent) Beteese Greemd Levet Release Directlen Aree Geestd Radius V VSAR Redius G ORAR (meters) (aeters) (ared/yr)/(ist/sec) (motors) (ared/yr)/(uct/sec)

N 305. 305 1.160E 021.122E-02 303.

NME 265. 265. 3.106E 02 3.006E 02 1.101E 02 1.065E-02 265. 2.026E-02 2.T36E 02 NE 299. 299. 5.03M 03 5.646E-03 299.

ENE 361. 361. 1.936E-02 1.074E-02 5.023E-03 4.063E-03 361. 1.505E 021.456E-02 E 355. 355. 4.295E-03 6.094E-03 355.

ESE 425. 425. 1.925E 02 1.064E-02 5.640E-03 5.459E-03 425. 1.609E-02 1.635E-82 M 440. 440. 4.703E-03 4.630E-03 440.

SSE 540. 1.4 TTE-02 1.430E-02 540. 3.262E 03 3.157E-03 540.

0 530, 9.701E-03 9.460E-03 530. 2.756E-03 2.647E-03 530.

' Ssu 540. 540. 1.066E-02 1.032E-02 2.500E-03 2.497E-03 540 9.211E-03 0.917E-03 su 632. 632. 2.740E-03 2.640E-03 632. 9.104E-03 0.StM-03 WSW 555. 555. 3.504E 03 3.392E-03 555.

W 500. 500. 1.404E-02 1.359E-02 3.715E-03 3.596E-03 500. 1.490E-021.450E 02 ww 434. 434. 4.539E-03 4.39M-03 434.

w 420. 420. 1.75 M-02 1.697E*02 5.159E 03 4.994E-03 420. 1.652E-02 1.599E-02 mm 442. 442. 5.499E-03 5.32M 03 442. 1.734E-02 1.679E-02 ORAIDWDoD SITE METEOROLetlCAL DATA 1/70 - 12/07 m

,_..... , g .. -

BRA D ,

Revision 1.9 June 1996 .

Sg;M ealTatWe A Mixed Mode Joint Frequency Distritation TatWe Summaries 203 Fool Elevation Date Summary f ebte of Percent by Direction ents Class class N NNE NE ENE E E5E SE SSE 5 55W SW W5W W WNW NW NNW fotal a .290 .323 .449 .395 .303 .256 .292 .2SS .474 .369 .2o2 .197 .999 8 997 .249 .284 .208 .205 .tS7

.274 .443 .42t S.076

.329

.194 .220 .3S2 .268 .190 .192 .206 .225 .327 C .302 .429 .293 .201 .203 .277 .312 .437 .404 .322

.335 3.833 D t.523 8.590 2.449 1.974 1.372 5.004 8.324

.342 .373 .399 457 .409 5.474 9.529 2.038 4.900 9.999 f.844 2.109 2.248 2.198 2.084 E .479 .St2 .784 .978 .984 .870 0.134 9.439 2.079 29.783 f.500 9.045 .929 .993 1.933 .922 F .344 .278 .290 .298 .387 .496 .530 .4 38 .559 .324 .396

.790 14.864 G .564 .095 .000 .079 .194

.397 .589 .SSS .554 .437 7.tes

.474 .270 .283 .184 .199 .250 .210 .253 .268 .t84 .359 2.944 total 3.520 3.439 4.418 4.943 3.649 3.900 4.025 4.488 4.918 5.187 4.322 4.904 4.794 S.231 5.100 4.545 70.074 Summery TabIe of Percont by De#octIon and Speed Speed N NNE NE ENE ESE E 5E 55E 5 55W SW W5W W WNW NW NNW Total

.45 .000 .014 .027 .025 .006 .000 .087 .087 .oot .ool .002 .004 .037 .026 .006 .024 .222 1.05 .044 .032 .042 .04S .024 .o25 .034 .039 .033 2.05 .224 .264

. 032 .023 .025 .037 .035 .040 .024 .532

.201 .2SO .239 .213 .243 .22S .237 .220 .2o8 .208 .242 .244 .244 .243 3.819 3.05 .4CS .426 .540 .890 .459 .334 .467 .438 .594 .303 .393 .384 .447 .437 .507 4.05 487 7.313

.449 .622 .758 .973 .870 .453 .884 .643 .895 .598 S.OS .524

.543 .663 .478 .702 .749 .762 10.629

.599 .875 .928 .SSI .482 . Set .439 .789 .477 .781 . Set .730 .782 .889 .008 09.470 4.06 .47o .407 .788 .575 .574 .587 .457 .729 .944 .325 .833 .768 .788 .975 .909 .876 12.279 4 S.05 .722 .789 .994 .534 .726 .999 4.073 f.227 2.070 9.SSS 1.268 9.138 9.378 9.598 9.381 1.041 50.05 .137 18.480

.454 .374 .094 . 327 .tSS .235 .423 .727 .821 .245 .218 .339 404 .399 .245 4.SS7 13.06 .007 .coe .006 .002 .000 .000 .084 .026 .047 .037 .002 .012 .007 .028 .020 .092 .245 18.00 .00o . coo . coo . coo . coo . coo .00o . coo . coo . coo .000 .000 . coo .00o . coo .00o .000 99.00 .Ooo . coo .coe . coo .aco . coo .oOo . coo . coo . coo .000 .coe .000 .000 . coo .000 .000 Total 3.620 3.439 4.480 4.143 3.889 3.990 4.02S 4.438 8.988 5.987 4.322 4.104 4.784 S.23t S.too 4.546 70.076 NOTE: Wind directions in tables are presented in Nind from and not Nind io" direction.

In ordet to deterrrune the knas mased ma.1e esfues 70 076% of the elevated value (presented in the 250 FT Mixed Mode table) and 29 924 % 04 ene y ounis is. e . ease iv e S** te=l = tt'e to I I Mined Mode table) are used to calculate the final values.

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