Text

Rev 1.3 to Odcm
	ML20100Q176
Person / Time
Site:	Byron
Issue date:	03/31/1996
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-960331, NUDOCS 9603110525
	Download: ML20100Q176 (134)
	v • d • e

X244 ALL Document Control Desk Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission February 29,1996 Mail Station PI-137 Washington,DC 20555

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Please perform the following update to the Offsite Dose Calculation Manual.

Byron Annex Remove Chapter 11, Revision 1.2 Insert Chapter 11, Revision 1.3 Remove Chapter 12, Revision 1.2 Insert Chapter 12, Revision 1.3 Remove Appendix F, Revision 1.2 I Insert Appendix F, Revision 1.3 )

I l

I Please sign below indicating your control copy number is correct and the update has been performed.

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Name- Date i

Please return this signed page to:

Central Files ETWIII 4th Floor !

-or-Comed ,

Central Files 1400 Opus Place Downers Grove,IL 60515 Q OSCf39

i 9603110525 960331 PDR ADOCK 0500 4 0(

p .

BYRON Revision 1.3 March 1996 BYRON ANNEX INDEX F. AGE REVISION ,

CHAPTER 11 11-1 1.3 11-il 1.3 11-iii 1.3 11-iv 1.3 11-1 1.3 11-2 1.3 11-3 1.3 11-4 1.3 11-5 1.3 11-6 1.3 11-7 1.3 11 8 1.3 11-9 1.3 11-10 1.3 ~~

11-11 1.3 11-12 1.3 11-13 1.3 O 1 l

O 11-1

BYRON Rowson 1.3 March 1996 CHAPTER 11 , l 1

RAoioLOGICAL ENVIRONMENTAL MONITORING PROGRAM J

TABLE OF CONTENTS i i

11.0 RADIOLOGICAL ENVIRONMENTAL MONITOFJNG PROGRAM 11-1 O

O 11-il

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

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BYRON Revmon 1.3 March 1996 4 l 1 \

CHAPTER 11 UST OF TABLES ,

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NUMBER HRE PAGE ,

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i 11-1 Radiological Envirmmental Monitoring Program 11-2 f

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BYRON Revmon 1.3 March 1996 -

CHAPTER 11 ,

NUMBER M PAGE 4

11-1 Onsite Air m Locates 11-10

. 11-2 Offsite Air Sampling 8 W 11-11 l 11-3 inner Ring and Outer Ring TLD i % 11-12 11 4 Inoastion and Waterborne Exposure Pathway M Locahons 11-13 1

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O 11-iv

BYRON Revmon 1.3 March 1996 CHAPTER 11 l

l RADIOLOGEAL ENVIRONMENTAL MONITORING PROGRAM .

The radiologkal environmental monitoring program for the environs around Byron Station is given in Table 11 1.

l Figures 11-1 through 114 show semping and monitoring locations l

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l 11-1

BYRON Reveion~1.3 March 1996 Tatdo 11-1 Re Nological Environmental Monitedng Program Exposure Pathway Sampling or Type of Frequency and/or SarW Samohna or Monihotbalmalmos Cogachon Frequency of Analvan

1. Airbome Radoiodne and a. Indicators-Near Field Continuous sampler operslion Radiosodna Canister-Partculaims with sample collechon winddy, 1-131 analyels weekly on or more frequen9y if requi ed near fleid and entrol by dustioeding samples.'

BY-21, Byron Nearsite N, Particulmin Samplar.

0.26 mi N (0.42 km A)

BY-22, Byron Nearsite ESE, Groes bots analysis 0.30 mi ESE (0.48 km F) fo5m. weeldy Star BY-23, Byron Neerslie S. and gemme 0.60 mi S (0.97 km J) isotopic analysis * '

I BY-24, Byron Nearsee SW, queriorly on conpr_

0.65 mi SW(1.05 km L) futors by location on near fleid and control samples. ;

b. Indicators-Far Field BY-1, Byron,3.5 mi N (5.6 km A)

BY-4, Paynes Pt.,4.5 mi SE (7.2 km G) l BY-6, Oregon,4.6 mi SSW (7.4 km K)

I 11-2 O O O .

March Tatde 11-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pattway Sampling or Type of Frequency and/or Samole Sampling or Monitonng Locahons Collechon Frequency of Analysis

1. Arbome (Cont'd) c. Controls BY-8, Leaf River,7.0 mi NW (11.3 km Q)

2. Dract Radiabon a. Indicators-Inner Ring Quartetiy Gamma dose quarterly BY-101-1,0.26 mi N (0.42 km A)

BY-101-2,0.26 mi N (0.42 km A)

BY-102-1,1.0 mi NNE (1.6 km B)

BY-102-2,1.0 mi NNE (1.6 km B)

BY-103-1,1.7 mi NE (2.7 km C)

BY-103-2,1.7 mi NE (2.7 km C)

BY-104-1,1.4 mi ENE (2.2 km D)

BY-104-2,1.4 mi ENE (2.2 km D)

BY-105-1,1.3 mi E (2.1 km E)

BY-105-2,1.3 mi E (2.1 km E)

BY-106-1,1.4 mi ESE (2.2 km F)

BY-106-2,1.4 mi ESE (2.2 km F)

BY-107-1,1.4 mi SE (2.2 km G)

BY-107-2,1.4 mi SE (2.2 km G)

BY-108-1,0.6 mi SSE (1.0 km H)

BY-108-2,0.6 mi SSE (1.0 km H)

BY-109-1, 0.6 mi S (1.0 km J) -

BY-109-2,0.6 mi S (1.0 km J)

BY-110-1,0.6 mi SSW (1.0 km K)

BY-110-2,0.6 mi SSW (1.0 km K)

BY-111-3,0.8 mi SW (1.2 km L)

BY-111-4,0.8 mi SW (1.2 km L)

BY-112-3, 0.8 mi WSW (1.3 km M)

BY-112-4, 0.8 mi WSW (1.3 km M) ,

11-3

BYRON Revision 1.3 March 1996 Table 11-1 (Cont.)

Radiological N Monitedng Program Exposure Pathway Samping or Type of Frequency ansor Samole Samping or MonPomp Localmns Co5edian Frequency of Anahrais l 2. Dract Rasslion BY-113-1,0.7 mi W (1.1 km N)

(Cont'd) BY-113-2,0.7 mi W (1.1 km N)

BY-114-1, 0.8 mi WNW (1.3 km P)

BY-114-2, 0.8 mi WNW (1.3 km P) -

BY-115-1,1.0 mi NW (1.6 km Q)

BY-115-2,1.0 mi NW (1.6 km Q)

BY-116-1,1.4 mi NNW(2.2 km R) 3 BY-116-2,1.4 mi NNW (2.2 km R) j b. Indicators-Outer Ring BY-201-3,.4.5 mi N (7.2 km A)

BY-201-4,4.5 mi N (7.2 km A)

BY-202-1,4.5 mi NNE (7.2 km B)

BY-202-2, 4.5 mi NNE (7.2 km B)

BY-203-1,5.1 mi NE (8.2 km C)

BY-203-2, 5.1 mi NE (8.2 km C)

BY-204-1,4.2 mi ENE (6.8 km D)

BY-204-2,4.2 mi ENE (6.8 km D)

BY-205-1,3.9 mi E (6.3 km E)

BY-205-2,3.9 mi E (6.3 km E)

BY-206-1,4.2 mi ESE (6.8 km F)

BY-206-2,4.2 mi ESE (6.8 km F)

BY-207-1,4.2 mi SE (6.8 km G)

BY-207-2,4.2.ml SE (6.8 km G) t y 9 11-4 O O O

BY i

TeMe 11-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samole Samp6ng or Momionng Locanons Cogechon Frequency of Anahres l

i l BY-208-1,4.1 mi SSE (6.6 km H) l 2. Dract Radinhon BY-208-2,4.1 mi SSE (6.6 km H)

(Cont'd)

BY-209-1,3.8 mi S (6.1 km J)

- BY-209-4,3.6 mi S (5.8 km J)

BY-210-3,4.75 mi SSW (7.6 km K)

BY-210-4,4.75 mi SSW (7.6 km K)

BY-211-1, 5.2 mi WSW (8.4 km L) ,

BY-211-4,4.9 mi WSW (7.9 km L)

BY-212-1,4.9 mi SW (7.9 km M)

BY-212-4, 4.9 mi WSW (7.8 km M)

BY-213-1, 5.0 mi W (8.0 km N) .

BY-213-4, 5.0 mi W (8.0 km N)

BY-214-1,4.8 mi WNW (7.7 km P)

BY-214-4,4.8 mi WNW (7.7 km P)

BY-215-1,5.2 mi NW (8.4 km Q)

BY-215-4. 5.2 mi NW (8.4 km Q) i BY-216-1,4.8 mi NNW (7.7 km R)

BY-216-2, 4.8 mi NNW (7.7 km R) c.Otbat l Indicators One at each airbome location given in part 1.a -

and 1.b.

d. Control One at ecch airbome contml .

location given in part 1.c.

11-5

BYRON Revision 1.3 Man:h 1996 TaNe 11-1 ICont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samnie Samping or Monitoring Locahons CcGechon Frequency of Analyses

3. Wesarbome l a. GmundAMnB aJndicators Quarterly Gamme isolopec' and inhum analysis BY-14, Comed Offsite Won quarterty. ,

0.3 mi ESE (0.5 km F) l BY-18, McCoy Farmstead 1.0 mi SW(1.6 km L) ,

b. Drinidng There is no driniong water pathway within 6.2 mi downstroom of the station.

c. Surface BY-12. Oregon Pool of Rock River, Weeldy grab samples. Gross bote and Downstream of Discharge, isotopicanalysis on 4.5 mi SSW (7.2 km K) . monthly compoone; trihum analysis on quarterty s.-i-:21.

d. Contml BY-2g, Byron, Upstroom of Intake Weeldy grab semples.

Gross bete and y 3.5 mi N (5.6 km A) isotopicanalysis on montNy wi--: 1, intium analysis on quartedy compoelle.

BY-12, Oregon Pool of Rock River. Semiennuouy Gamme isotopic' I e. Sediment Downstroom of Discharge, analysis semiennually.

4.5 mi SSW (7.2 km K) -

11-6 O O O

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Table 11-1 (Cont.)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type of Frequency and/or Samole Sampling or Monitonng Locahons Couachon Frecuency of Anahrmas

4. Ingeston Biweeldy May through Gamme isotopic

and

a. Mik a. Indicators October; monthly- I-131 analysis

on each BY-20, K. Reeverts Dairy Farm. November through AprH. sample 2.1 mi NE (3.4 km C)

BY-27, Kenneth Drusen Dairy Farm, 5.8 mi WSW (9.3 km M)

BY-30, Don Roos Dairy, 5.13 mi SE (8.2 km G)

b. Controls BY-26, Glen Gazzard's Dairy, 13.5 mi N (21.6 km A)

b. _Elati a. Indicator BY-31, Rock River in vicindy of Descharge, .Two times annually Gamma isotopk?

2.6 mi WNW (4.2 km P) analysis on edible porbons.

b. Control BY-29, Byron Upstream of Intake -

3.5 mi N (5.6 km A)

c. Food Products a. Indicakra Annually Gamma litiAyid analysis on each Two samples from each of the four . sample.

major quandrants within 6.2 miles of the station. ,

11-7

BYRON Revision 1.3 March 1996 -

Tatde 11-1 (Cont.)

Radkdogical Environmental Monitedng Program Exposure Pathway Sampung or Type of Frequency andor Samole Samping or Monitoring Locahons Councton Frequency of Analvma Sample locanons for food products may .

very based on availability and therefore are not required to be idenb6ed here but shaN be taken.

b. Control Two samples vnthin 9.3 to 18.6 miles of the station.

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i BYRON Revision 1.3 March 1996 O

CHAPTER 12.0 l

l BPECIAL NOTE The transfer of the Byron Radiologico! Effluent Technical Specifications to the ODCM was approved by the Nuclear Regulatory Commission in Technical Specification Amendment 1 46, dated April 13,1992.

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l BYRON Revision 1.3 March 1996 BYRON ANNEX INDEX CHAPTER 12 ;

1 PAGE REVISION PAGE REVISION 12 -1 1.3 12 - 44 1.3 12 - il 1.3 12 - 45 1.3 1 12 - lii 1.3 12 - 46 1.3 12 - iv 1.3 12 - 47 1.3 i 12 - 1 1.3 12 - 48 1.3 12 - 2 1.3 12 - 49 1.3 12 - 3 1.3 12 - 50 1.3 12 - 4 1.3 12 - 51 1.3 12 - 5 1.3 12 - 52 1.3 12 - 6 1.3 12 - 53 1.3 12 - 7 1.3 12 - 54 1.3 12 - 8 1.3 12 - 55 1.3 12 - 9 1.3 12 - 56 1.3 12 - 10 1.3 12 - 57 1.3 12 - 11 1.3 12 - 58 1.3 12 - 12 1.3 12 - 59 1.3 12 - 13 1.3 12 - 14 1.5 12 - 15 1.3 12 - 16 1.3 12 - 17 1.3 12 - 18 1.3 12 - 19 1.3 12 - 20 1.3 12 - 21 1.3 12 - 22 1.3 12 - 23 1.3 12 - 24 1.3 12 - 25 1.3 12 - 26 . I .3 12 - 27 1.3 12 - 28 1.3 12 - 29 1.3 12 - 30 1.3 12 - 31 1.3 12 - 32 1.3 12 - 33 1.3 12 - 34 1.3 12 - 35 1.3 12 - 36 1.3 t

12 - 37 1.3

( 12 - 38 1.3 i 12 - 39 1.3 l 12 - 40 1.3 2 - 41 1.3 12- 42 1.3 12 - 43 1.3 i

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. i BYRON Revision 1.3 March 1996

~

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS 1 PAGE I 12.1 DEFINITIONS 12-2 1

12.2 INSTRUMENTATION 12-6

1. Radioactive Uquid Effluent Monitoring instrumentation 12-6

2. Radioactive Goseous Effluent Monitoring instrumentation 12-11 12.3 LlQUID EFFLUENTS 12-18

1. Concentration 12-18

2. Dose 12-23

3. Uquid Rodwoste Treatment System 12-25 12.4 GASEOUS EFFLUENTS 12-27 1, Dose Rate 12-27

2. Dose - Noble Goses '

12-32

3. Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form 12-34

4. Gaseous Rodwoste Treatment System 12-36

5. Total Dose 12-38 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-40 l

1. Monitoring Program 12-40 l

2. Land Use Census 12-53 l

3. Interloboratory Comparison Program 12-54 12.6 REPORTING REQUIREMENTS 12-55 l

1. Annual Radiological Environmental Operating Report 12-55

2. Annual Radioactive Effluent Release Report 12-57

3. Offsite Dose Calculation Manual (ODCM) 12-58 ;

4. Major Changes to Uquid and Goseous Rodwoste Treatment Systems 12-59 A

b g:*sWicmWmex%mnby12r13.wpf 12-lii

i BYRON Revision 1.3 March 1996 CHAPTER 12 9,

RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES TABLE I]ILE PAGE 12.0-1 Compliance Matrix 12-1 12.1-1 Frequency Notations 12-5 12.2-1 Radioactive Liquid Effluent Monitoring instrumentation 12-7 12.2-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 12-9 12.2-3 Radioactive Goseous Effluent Monitoring instrumentation _- 12-12 12.2-4 Radioactive Goseous Effluent Monitoring instrumentation Surveillance Requirements 12-15 12.3-1 Radioactive Liquid Waste Sampling and Analysis Program 12-19 12.4-1 Radioactive Goseous Waste Sampling and Analysis Program 12-29 12.5-1 Radiological Environmental Monitoring Program 12-43 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-49 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-50 l

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BYRON Revision 1.3 March 1996 V BYRON STATION Table 12.0-1 COMPLIANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specifica-tion 10 CFR 50 1. Gomma oir dose and beta oir dose due to A-1 12.4.2 6.8.4.e.8 Appendix l oirborne radioactivity in effluent plume. A-2

c. Whole body and skin dose due to A-6 N/A N/A airbome radioactivity in effluent plume A-7 are reported only if certain gommo and beta oir dose criteria are A--13 12.4.3 6.8.4.e.9 exceeded.

2. CDE for all organs and all four age groups A-29 12.3.2 6.8.4.e.4 due to iodines and particulates in effluent plume. All pathways are considered.

3. CDE for all organs and all four age groups due to radioactivity in liquid effluents.

10 CFR 20 1. TEDE, totaling all deep dose equivalent A-38 6.8.4.e.3 components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airbome 1 and liquid-bome). CDE evoluotion 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 I reference, sources at a station. l also part of A-13 10 CFR 20) 2. Organ doses (CDE) to on adult due to 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 on A-9 oduit due to radioactivity in airbome A-28 effluents. For the organ dose, only inholation is considered. A-32 12.3.1 6.8.4.e.2

2. " Instantaneous" concentration limits for liquid effluents.

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osawdemw wwxtymney12r13.wpr 12-1 I

BYRON Revision 1.3 March 1996 12.1 DfFINiilONS 12.1.1 ACTION shall be that which prescribes remedial measures required under designated conditions.

12.1.2 ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor os practicable to verify OPERABILITY of clarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm interlock ond/or Trip Setpoints such that the Setpoints are within the required range and occurocy.

12.1.3 CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and occuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such inot 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, comparison of the channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the some parameter.

12.1.5 DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of clarm and/or trip functions.

12.1.6 DOSE EQUIVALENT F131 shall be that connection of l-131 (microcurie / gram) which alone would produce the some thyroid dose os the quantity and isotopic mixture of I-131, h132,1-133,1-134, and F135 octually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table 111 of TID-14844," Calculation of Distance Factors for Power and Test Reactor Sites".

12.1.7 FREQUENCY - Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc., are performed unless defined otherwise.

The 25% vorlonce shall not be applied to Operability Action statements. The bases to Technical Specification 4.0.2 provide clarifications to this requirement.

12.1.8 MEMBERf S) OF THE PUBLIC means any individual except when that individual is receiving on occupational dose.

12.1.9 OCCUPATION AL DOSE means the dose received by on individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person.

Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntory participation in medical research programs, or as a member of the public.

g:*awocrnwnnexwronw12rt.s.wpf 12-2

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BYRON Revison 1.3

- March 1996 i !

i 12.1.10 OPERABLE / OPERABILITY a system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its wN function (s), and when ou necessary attendant instrumentation,

controls, electrical power, cooing or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or l

. device to perform its function (s) are also copoble of performing their related l l support function (s),

i 12.1.11 OPERATIONAL MODE (i.e. Mode) shoN correspond to any one inclusive

! combination of core reactivity condition, power level, and overage reactor coolant temperoivre specified in Table 1.2 of the Technical Specifications.

l 12.1.12 PROCESS CONTROL PROGRAM (PCP) shou contain the current formelos,

l. sompting, analyses, tests, and determinations to be mode to ensure that processing and packaging of soRd 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 Ports 20,61, 71 and State regulations, buriol ground requirements, and other requirements goveming the <*mami of radioactive wastes.

12.1.13 PURGE / PURGING shou be any controlled process of discharging air or gas from o confinement to rrontain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

( 12.1.14 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolont of 3411 MW,,.

12.1.15 SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.

12.1.16 SOLIDIFICATION shall be the conversion of wet wastes into o form that meets shipping and 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 coolont.

12.1.19 UNRESTRICTED AREA means on area, access to which is neither limited nor controlled by the licensee. 1 l

12.1.20 VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate l form in effluents by possing ventilation or vent exhaust gases through charcoal odsorbers ond/or HEPA filters for 'he purpose of removing iodines or particulates from the gaseous exhoust 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 Air 60spt,6;ic Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components, sw - - - , 12ri 3W 12-3

BYRON Revision 1.3 March 1996

. 12.1.21 VENTING shall be any controlled process of discharging air or gas from o confinement to maintain temperature, pressure, humidity, concentration or other operating 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 HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor'Coolont System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

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 dato 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 penod or estimated release data to forecast a future dose to members of the public. This dato is not incorporated into the database.

O I

1

)

I i

l l

S asawemwnexeymney12rt-3.wpf 12-4 l

l l

l l BYRON Revmon 1.3

! March 1996 l '

lO

, V l

TABLE 12.1-1

! FREQUENCY NOTATIONS

l Notaten Frecuency l

$ - Shiftly At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D - Dolly At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l W - Weekly At least once per 7 days ;

M - Monthly At least once per 31 days Q - Quarterty At least once per 92 days _1

\

SA - Semionnually At least once per 184 days A - Annually At least once per 366 days l

R - Refuel Cycle At least once per 18 months S/U - Startup Prior to each reactor startup N.A. ,

Not applicable )

P - Prior Prior to each rochooctive release

l l *Each frequency requirement shall be performed within the specified time intervol with l the maximum allowable extension not to exceed 25% of the frequency intervol. The 25%

l variance shall not be opplied to Operability Action statements. The bases to Technical ,

l Specification 4.0.2 provide clarifications to this requirement. These frequency notations do not apply to the Radiological Environment Monitoring Program os described in l

Section 12.5.

l t

g: w .._ _ ,_. 2,12rt-3.wpf 12-5 i

BYRON Revision 1.3 March 1996 O

12.2 INSTRUMENTATION 12.2.1 Radioactive Uquid Effluent Monitoring instrumentation Ooerability Reauirements l

12.2.1.A The radiooctive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their AlarmSrip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and odiusted in accordance with the i methodology and parameters in the ODCM. l Acolicability: At all times l

Action j 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 i 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 4 Radioactive Effluent Release Report pursuant to Section 12.6 why this ,

inoperability was not corrected within the time specified. l Surveillance Reauirements 12.2.1.B Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l CHECK CHANNEL CAllBRATION and DIGITAL and ANALOG CHANNEL l 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, os applicable, the releases of radioactive materials in liquid effluents during actual 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 clarm/ trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criterio 60, 63, and 64 of Appendix A to 10 CFR Port 50.

O c:*awdemwnnexeyroney12r13.wpf 12-6

Revision March ihs TABLE 12.2-1 .

RADIOACTIVE UQUD EFFLUENT MONITORNG NSTRUMENTATION MNIMUM CHANNELS NSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alorm and Automatic Termination of Release

o. Uquid Rodwoste Effluent une (OREPR001) 1 31

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

c. Condensate Polisher Sump Discharge (OREPR041) 1 34

2. Radioactivity Monitors Providing Alcrm But Net Providing Automatic Termination of Release

o. Essential Service Water

1) Unit I a) RCFC 1 A and 1C Outlet (IRE-PR002) 1 32 b) RCFC IB ond ID Outlet (IREPR003) 1 32

2) Unit 2 a) RCFC 2A and 2C Outlet (2REPR002) 1 32 b) RCFC 2B and 2D Outlet (2REPR003) 1 32

b. Station Blowdown Une (OREPR010) 1 32

3. Row Rote Measurement Devices

o. Liquid Rodwoste Effluent une (Loop-WX001) 1 33

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

c. Station Blowdown Une (Loop-CWO32) 1 33 g:hhbuty12rt-3.wpf 12-7

l BYRON R& vision 1.3 March 1996 TABLE 12.2-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ,

l 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 I

b. At least two technically qualified members of the facility stoff I independently verify the release rate calculations and discharge line !

volving. l l

Otherwise, suspend release of radioactive effluents via this pathway. l l

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 , grob ,

samples are collected and analyzed for radioactivity 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 requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per i 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during 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 Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at o lower limit of detection as specified in Table 12.3-1:

o. At least onco per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131, or

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 coolont is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.

O g:*abdanknnextyronty12r1-3.wpf 12-8

Revison March lnd TABLE 12.2-2 RADIOACTIVE LIQUD EFFLUENT MONITORNG NSTRUMENTATION SURVEILLANCE REQUREMENTS DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATONAL NSTRUMEt{I CHECK CHECK CAUBRATON IESI IESI

1. Radioactivity Monitors Providing Alarm and Automatic Termnation of Release

o. Liquid Rodwoste Effluent Line (OREPR001) D P R(3) Q(1) N.A.

b. Fire and Oil Sump Discharge (ORE-PR005) D M R(3) Q(1) N.A.

c. Condensole Polisher Sump Discharge (OREPR041), D M R(3) Q(1) N.A.

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

a. Essential Service Water

1) Unit 1 o) RCFC 1 A and IC Outlet (IREPR002) D M R(3) Q(2) N.A.

b) RCFC IB and ID Outlet (1REPR003) D M R(3) Q(2) N.A.

2) Unit 2 o) RCFC 2A and 2C Outlet (2REPR002) D M R(3) Q(2) N.A.

b) RCFC 2B and 2D Outlet (2REPR003) D M R(3) Q{2) N.A.

b. Station Blowdown Une (OREPR010) D M R(3) Q(2) N.A.

3. How Rote Measurement Devices

o. Liquid Rodwoste Effluent Line (Loop-WX001) D(4) N.A. R N.A. O

b. Liquid Rodwoste Effluent low Flow Line D(4) N.A. R N.A. Q (Loop-WX630)

c. Station Blowdown une (Loop-CWO32) D(4) N.A. R N.A. Q stewsemwu=xwmnw12rt-smpf 12-9

BYRON R; vision 1.3 March 1996 TABLE 12.2-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEllLANCE REQUIREMENTS TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room clarm 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.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room clarm 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 - clarm 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.

(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 meosviement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and i measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of l 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 en days on .

which continuous, periodic, or batch releases are made. !

l l

1 ghbdermannextyrontw12ri-3.wpf 12 10

BYRON Ravision 1.3 March 1996 O

U 12.2.2 Radioactive Goseous Effluent Monitorina instrumentation Ooerability 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 ore not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Aoolicability: As shown in Table 12.2-3 Action *

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

2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown p in Table 12.2-3. Restore the inoperable instrumentation to OPERABLE V 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.

Surveillance Reauirements 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and CHANNEL OPERATIONAL TEST of 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 opplicable, the releases of radioactive materials in gaseous effluents during actual or potentici releases of gaseous 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 exceeding the limits of RETS. The instrumentation also includes i provisions for monitoring (and controlling) the concentrations of potentially I explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERABILITY and !

use of this instrumentation is consistent with the requirements of General Design l Criterio 60,63, and 64 of Appendix A to RETS. The sensitivity of any noble gas ,

activity monitor used to show compliance with the gaseous effluent release !

requirements of Section 12.4 shall be such that concentrations os low as 1x10

uCi/cc ore measurable, g*awkrnWinexWatW12r13.wpf 12-11 l

O O BYRON O

Rcvision 1.3 March 1996 TABLE 12.2-3

^ RADIOACTIVE GASEOUS EFFLUENT MONITORNG NSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Plant Vent Monitonng System - Unit I

c. Noble Gas Activity Monitor-Providing Alarm

1) High Range (IREPR028D) 1 39

2) Low Range (IREPR0288) 1 39

b. lodine Sompier (IREPF:028C) 1 40

c. Particulate Sompier (IREPR028A) 1 40

d. Effluent System Flow Rote Measunng Device (LOOP-VA019) 1 36

e. Sompier Flow Rote Measuring Device (IFT-PRl65) 1 36

2. Plant Vent Monitoring System - Unit 2

c. Noble Gas Activity Monitor-Providing Alarm i

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

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

b. lodine Sampler (2REPR028C) 1 40

c. Particulate Sampler (2RE-PR028A) I '

40

d. Effluent System Pow Rote Measuring Device (LOOP-VA020) 1 36

e. Sampler Flow Role Measuring Device (2FT-PR165) 1 36 g:'kamwmexeyroney12rt-3mpt 12-12

Revision March 1976 TABLE 12.2-3 (Continuedl RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (CONTDI MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

3. Not Used.

4. Gas Decay Tonk System

o. Noble Gas Activity Monitor-Providing Alarm and Automatic -

Termination of Release (OREPR002A and 2B) 2 35

5. Containment Purge System

o. Noble Gas Activity Monitor-Providing Alarm (REPR001B) 1 37

b. lodine Sampler (REPR001C) 1 40

c. Particulate Sompier (REPR001A) 1 40

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tonk Vent-Component Cooling Water une (OREfR009 and REPR009) 2 41 9:wamwnnexeyroney12rt.3.wpf 12-13

BYRON RLvision 1.3 j March 1996 TABLE 12.2-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION fCONT'D1 TABLE NOTATIONS

At all times.

ACTION 35 - With the number of chonnels 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 volve lineup.

Otherwise, suspend release of radioactivo 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 vio this pathway may continue for up to 30 days prov,ded grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these somptes are analyzed for principle gamma emitters at on LLD as specified in 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 offected pathway may continue for up to 30 days provided somptes are continuously collected with auxiliary 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 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 , gaseous grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.4-1.

O giswdcymannexeyroney12rt-3.wpr 12 14

o o -

B eN Revision is March 1996 TABLE 12.2-4

! RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

- DIGITAL i CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CAllBRATiON TEST IS REQUIRED l 1. Plant Vent Monitonng System - Unit 1

c. Noble Gas Activity Monitor-Prov' ding AkNm

1) High Range (IREPR028D) D M R(3) Q(2)

2) Low Range (1REPR0288) D M R(3) Q(2)

b. lodine Sompier (IREPR028C) D M R(3) Q(2)

c. Particulate Sampler (IREPR028A) D M R(3) Q(2)

d. Effluent System Flow Rote Measuring D N.A. R Q Device (LOOP-VA019)

e. Sampler Flow Rote Measuring Device D N.A. R Q (IFT-PRl65)

2. Plant Vent Monitoring System - Unit 2

c. Noble Gas Activity Monitor-Providing Alarm

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

2) Low Range (2REPR0288) D M R(3) O(2)

b. lodine Sampler (2REPR028C) D M R(3) Q(2) gwawkmwmexeyrontytzri-3mpf 12-15

O O BYRON O

Rsvision 1.3

' March 1996 '

i TABLE 12.2-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVRi f ANCE REQUIREMENTS

! DIGITAL

CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CALBRATION TEST IS REQUIRED l

2. Plant Vent Monitonng System - Unit Two (Continued)

c. Particulate Sampler (2REPR028C) D M R(3) Q(2) *

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

, Device (LOOP-VA020) *

e. Sampler Flow Role Measunng Device D N.A. R Q

~

(2FT-PR165)

3. Not Used

! 4. Gas Decoy Tonk System i

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

Providing Alarm and Automatic j Termination of Release (OREPR002A and 2B) i 5. Containment Purge System

) o. Noble Gas Activity Monitor-

! Providing Alarm (REPR0018) D P R(3) O(2)

b. lodine Sompier (REPR001C) P P _ R(3) N'.A.

c. Particulate Sompier (RE-PR001 A) P P R(3) N.A.

6. Rodsocctivity Monitors Providing Aloim and Automatic Closure of Surge Tork j

Vent-Component Cooling Water Line (OREPR009 and REPR009) D M R(3) , Q(1)

1

^

]

shmWmentponty12r1-1wpf 12-16

BYRON Rsvision 1.3 March 1996 '

i TABLE 12.2-4 IConhnued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVOLLANCE REQUIREMENTS r

TABLE NOTATONS :

'At all times. 'l (1) The DIGITAL CHANNEL OPERATONAL TEST shdi also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the

. following conditions exists: _

o. Instrument indicates measured levels above the Alarm / Trip Setpoint, or ~ !

, 1 bi Circuit failure (monitor loss of communications - olarm only, detector loss of l counts, or monitor loss of power), or j

c. Deiector check source test failure, or

-l

d. Detector channel out-of-service, or l

e. Monitor loss of sample flow.

The DIGITAL CHANNEL OPERATONAL TET shall also demonstrate that control room O (2) alarm annunciation occurs if any of the following conditions exists: *

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

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

c. Detector check source test failure, or

d. Detector chonnel out-of-service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL CAllBRATON shall be performed using one or more of the reference standards certified by the National institute of Standards and Technology (NIST) or using stondords 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 CAllBRATION, sources that have been related to the initial calibration shall be used.

s:*swoomwwmmyroney12rt-3.wpf 12-17

~

BYRON Rcvision 1.3 March 1996 12.3 LlOUID EFFLUENTS 12.3.1 Concentration Ooerobility Reovirements 12.3.1.A The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Byron Station ODCM Annex, Appendix F, Figure F-1) conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. For dissolved or entroined noble gases, the concentration shall be limited to 2x10d microcurie /mi total activity.

Acolicabilifv: 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.

1 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 with the limits of 12.3.1.A.

Bases 12.3.1.C This specification 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 ,

10CFRPort 20.1001-20.2402. This limitation provides additional ossurance that the j levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will !

result in exposures within: (1) the Section ll.A design objectives of Appendix 1, l 10 CFR Port 50, to o MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Port i 20.1301 to the population.

This specification applies to the release of radioactive materials in liquid effluents from all units of 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 con be found in HASL Procedures Manual, H ASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anot. Chem. 40. 586-93 (1968), and Hartwell, J.K., ' Detection Umits for Radioonalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

ghWdembrmertyronty12rt.3W 12 18

BYRON Rsvision 1.3 March 1996 TABLE 12.3-1

( RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM TYPE OF ACTIVITY OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS ANALYSIS (LLD)D)

TYPE FREQUENCY FREQUENCY (pCi/ml)

1. Batch P P Fincipal Gamma 5x107 Release Each Botch Each Batch Emitters (3)

Tanks (2) 1-131 1x104 P M Dissolved and lx104 One Batch /M Entrained Goses (Gamma Emitters)

P M H-3 1x104 Each Batch Compositeld)

Gross Alpha Ix10-7 P Q Sr-89, Sr-90 5x104 Each Batch Compositeldi Fe-55 1x104

2. Continuous Continuous ('l W Principal Gammo 5x10 7 Releases (8 Composite ('l Emitterst38 l-131 1x104

c. Circulating M M Dissolved and 1x104 Water Grab Sample Entrained Goses Blowdown (Gammo Emitters)

Continuoust'8 M H-3 1x104

b. Waste Water Composite '1 l

Treatment Discharge to Circulating Gross Alpha Ix10-7 Water Discharge

c. Condensate Continuous t 'l Q Sr-89, Sr-90 5x104 Polisher Sump Composite (')

Discharge p

C g:*sucmmnexeyroney12ri-3.wpf 12-19

BYRON Rcvision 1.3 March 1996 TABLE 12.3-1 iContinued1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE TYPE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)DI FREQUENCY FREQUENCY ANALYSIS (pCi/ml)

3. Continuous W(7) Wl7) Principal Gamma 5x107 Release!8) Ernmille#! l Grab Sample ,

Essential 1-131 1x104 l

Service Water, Reactor Containment Dissolved and Entrained Goses Fan Cooler '

(Gamma Emitters) 1x108 (RCFC)

Outlet Line H-3 1x105 0

e e

Ol l

ou-m. wwm.sw i2-20 l l

i BYRON Rsvision 1.3 l March 1996 i

I (.)h TABLE 12.31 fContinued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS

[ -(1) The LLD is defined, for purposes of these specifications, os the smallest concentration of rodlooctive materialin a sompie that will yield a net count, above system background, i

that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a ' Year

signol.

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

! LLD = _ _446A ~

j E

V

2.22 x 10'

Y

exp (-Aat) i Where:

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

4 s= the standard deviation of the background counting rate or of the i~

counting rate of a blank sample os oppropriate (counts per minute),

E= the counting efficiency (counts per disintegration),

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

2.22 x 10' = the number of disintegrations per minute per microcurie, 1

Y= the froclional radiochemical yield, when opplicable, i

l A= the radioactive decoy constant for the particular radionuclide j (sec '), and i

at = the elapsed time between the midpoint of somple collection 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 on offer the fact limit for o i particular measurement.

j (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to l sompling for analyses; each batch shall be isolated, and then thoroughly mixed by a '

i method described in the ODCM to assure representative sompling.

[ (3) The principal gamma emitters for which the LLD specification applies include the i following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, i Ce-141, and Ce-144. This list does not mean that only these nuclides are to be i considered. Other gomma peaks that are identifiable, together with those of the F above nuclides, shall also be analyzed and reported in the Rodioactive Effluent Release Report pursuant to Section 12.6.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

s:*swoomwineuwoney12rt-3W 12-21 l

1

BYRON Rsvision 1.3 March 1996 TABLE 12.3-1 lContinued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,

from o volume of a system that has on input flow during the continuous release.

(6) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate cf flow of the effluent stream. Prior to analyses, all samples taken for the composite shoa be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(7) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and RE-PR003 indicates measured levels greater than Ix104 pCi/ml above background at any time during the week.

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g:WaWWmex%eonW12ri-3W 12-22

BYRON Revision 1.3 March 1996 12.3.2 D9Et OoeroNitv 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 Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

1. During any calendor quarter to less than or equal to 1.5 mrems to the whole b( >dy and to less than or equal to 5 mrems to any organ, and .

2. During any calendor year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any orgon.

Aoollcobility: 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, o 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 calendor quarter and the current calendor year shall be determined in accordonce with the methodology and parameters in the ODCM of least once per 31 days.

Bases 12.3.2.C This section is provided to implement the requirements of Sections ll.A. Ill.A and IV.A of Appendix 1,10 CFR Port 50. The Operability Requirements implement the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and of the some time implement the guides set forth in Section IV.A of Appendix 1 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 Section lil.A of Appendix i that conformance with the guides of Appendix I be shown by calculational procedures based on models and dato, such that the octual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the octual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,"Colculation of Annual Doses to Mon From Routine Releases of Reactor Effluents For the Purpose of f) Evoluoting Compliance with 10 CFR Port 50, Appendix r Revision 1, October v 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

s:*swedenamerrorey12rt-3.upt 12-23

BYRON R vision 1.3 March 1996 12.3.2 Rost (Continued)

Bases

)

This section applies to the release of radioactive materials in liquid effluents from each reactor at the site. When shared Rodwaste Treatment Systems are used by more than one unit on a site, the wastes from oil units are mixed for shared treatment; by such mixing, the effluent releases cannot occurately 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 Rodwoste Treatment System. For determining conformance to Operability Requirements, these l allocations from shared Rodwoste Treatment Systems are to be added to the I releases specificolly attributed to each unit to obtain the total releases per unit. l l

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l g:wawansonnextyonw12ri-3.wpf I 12 24 J

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

BYRON Rsvision 1.3 March 1996 12.3.3 Llauid Radwaste Treatment Svstem Ooernhility Raouirements 12.3.3.A The Liquid Rodwoste 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 Byron Station ODCM Annex, Appendix F Figure F-1) would exceed L 0.06 mrem to the whole body or 0.2 mrom to any orgon in a 31-day period.

i Aoolicabihty: At all times.

Action:

1. With radioactive liquid waste being discharged without treatment and in i

excess of the above limits and any portion of the Uquid Rodwoste :

Treatment System not in operation, propor5 and submit to the I Commission within 30 days, pursuant to Technical Specification 6.9.2, o !

Special Report that includes the following information:

l l o. Explanation of why liquid rodwoste was being discharged without treatment, identification of any inoperable equipment or i 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.B Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be -

projected of least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Rodwoste Treatment System is not ;

being fully utilized. ;

12.3.3.2.B The installed Liquid Rodwoste Treatment System shall be considered OPERABLE by meeting Sections 12.3.1.A and 12.3.2.A. ,

Bases 12.3.3.B The OPERABluTY of the Liquid Rodwoste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low os is reasonably ochievable". This section implements the requirements of 10 CFR 50.360, General Design Criterion 60 of Appendix A to 10 CFR Port 50 and the design i objective given in Section ll.D of Appendix i to 10 CFR Port 50.

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om .. _ -- ---- _, . _.w12rt-3.wpf 12-25 i

BYRON Rsvision 1.3 March 1996 12.3.3 Llauid Radwaste Treatment System (Continued)

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

This section opplies to the release of radioactive materials in liquid effluents from each unit at the site. When shared Rodwoste 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 connot accurately be ascribed to a specific unit. An estimate should be mode 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 Rodwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Rodwoste Treatment Systems are to be odded to the releases specifically attributed to each unit to obtain the total releases per unit.

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O l gmbdomennexeyronty12ri-3.*W 12-26

BYRON Rsvision 1.3 March 1996

\

12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rote Ooerobilifv Recurements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas of and beyond the SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

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

2. For lodine-131, lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to-o dose rate of 1500 mrem /yr to any orgon.

Acohcobihtv At all times.

Action:

1. With the dose rote (s) exceeding the above limits, immediately restore the

/* release rate to within the above limit (s).

Surveillance Reauirements 12.4.1.1.B 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.

12.4.1.2.B The dose rate due to' lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be 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 onelysis program specified in Table 12.4-1.

Bases 12.4.1.C This section is provided to ensure that the dose at any time of and beyond the SITE BOUNDARY from gaseous effluents from oll Units on the site will be within the annual dose limits of RETS. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in on UNRESTRICTED AREA, either within or outside the SITE BOUNDARY specified in 10 CFR 20.1301.

s:wswkmwmenyoney12r13mpf 12-27

BYRON R3 vision 1.3 March 1996 l

12.4 GASEOUS EFFLUENTS Bases For MEMBERS OF THE PUBUC who may of times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBUC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculatio.ns for such MEMBERS OF THE PUBUC, with the oppropriate 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 bockground to o MEMBER OF THE PUBUC of or beyond the SITE BOUNDARY to less than or equal to a dose rate of 500 mrem / year to the whole body or to less than or ecual to a dose rate of 3000 mrem / year to the skin. These release rate limits also restrict, at all times the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrems/ year.

This section applies to the release of radioactive rnaterials 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 con be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantit.ative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Defection Limits for Radioonalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975),

interoretations l

12.4.1.D This Technical Standard requires sampling and analysis following a power change exceeding 15% of Roted Themial Power within a 1 - hour period. The interpretation of this requirement for power changes is os follows:

c) Samples are required to be pulled within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the power 'ronsient.

l b) If there are several power transients that exceed 15% RATED THERMAL POWER per hour, sampling need only be performed offer the 1911 transient but within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the first transient that exceed 15% of RATED THERMAL POWER.

In all cases, sample analysis sho!! be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of the :

stort of the initial transient.

O g:*abdomWnnextyronty12ri-3.wpf 12-28

N Rsvision i

(

March 19 l

TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l

l MINIMUM TYPE OF LOWER LIMIT OF SAMPLING ANALYSIS ACTIVITY ANALYSIS DETECTION (LLD)"I GASEOUS RELEASE TYPE FREQUENCY FREQUENCY (pCi/cc)

P P ,

Principal Gamma Emitters A

1. Waste Gas Decay 'Eoch Tank Each Tonk 1x10' Tonk Grob Sompie

2. Containment Purge P P .

Each Purge m Each Purgem Principoi Gamma Emitters A 1xl&*

Grab Sample ,

3. Auxiliary Bldg. Mt'IA M Principal Gamma Emittersm Ixl&d Vent Stock Grab Sompte H-3 1x10' (Unit I and 2)

Continuous'4 W l-131 lx10'2 Charcoal Sample ,,

Continuous (8 W'78 Principal Gamma EmmittersA Particulate Sample Ixl&"

Continuous'4 Q Gross Alpha Composite Ix1&"

Particulate Sample Continuoust" Q Sr-89, Sr-90 Composite Ix1&"

Particulate Sample Continuous N.A. Noble Goses: Gross Beto or Noble Gas Monlior Gamma 1x10' ghbdtm\ennexeyronty12rt-3.wpf 12-29

BYRON R: vision 1.3 March 1996 TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATlONS (1) The 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 " rear signol.

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

LLD = 4.66 s_

E

V 2.22 x 10'

Y

exp (-Aat)

Where:

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

s=

o the standard deviation of the background counting rate or of the counting rate of a blank sample as oppropriate (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 e the eiosped time between the midpoint of sample collection cnd the time of counting (sec). I 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 on offer the fact limit for a particular measurement.

(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 lodine and particulate releases. This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, I 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 1, June 1974. l g:*awkrnwwwreymney12ri 3.wpf 12-30

I BYRON Rsvision 1.3 March 1996 TABLE 12.4-1 (Continggdl d RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIQMS (3) Sompling and analysis shall also be performed following shutdown, startup, or o 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 hnooded.

(5) Tritium grab somotes shall be taken of least once per 7 days from the spent fuel pool j 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 12.4.1.A.12.4.2.A and 12.4.3.A. I l I (7) Samples shall be changed at least once per 7 days and analyses shall be completed 1 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months offer changing, or offer removal from sompier. 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 POWER within a 1-hour period and analyses sho: 1 be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When 1 samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased

( by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased

, more than a factor of 3.

d I

4 1

4 4

o g*awcmwmemponty12r13.wpf 12-31

BYRON Rcvision 1.3 March 1996 12.4.2 Dose - Noble Gases Ooerability Reauirements 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to creas at and beyond the SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

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

2. Durina any calendor year: Less than or equal to 10 mrods for gamma radiation and less than or equal to 20 mrads for beta radiation.

Acolicability: At all times.

Action'

1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, o Speclot 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 12.4.2.B Cumulative dose contributions for the current calendar quarter and the current calendor 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 ll.B, Ill.A and IV.A of Appendix 1,10 CFR Port 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 some time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous effluents at or beyond the Site Boundary will be kept "as low as is reasonable achievable." The Surveillonce Requirements implement the requirements in Section Ill.A of Appendix ! that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through appropriate pathways is unlikely to be substantially underestimated.

O g%swdovnannextymney12ri-3.wpf 12-32

BYRON Rsvision 1.3 March 1996 f

, 12.4.2 Dose - Noble Goses (Continued)

Bases ,

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the octual release rates of radioactive materials in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,"Colculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evoluoting Comphonce with 10 CFR Port 50, Appendix r Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estimating Atmospheric Transport and Dupersion of Goseous Effluents in Routine Releases from 1.ight-Water Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY ore based upon the historical overage atmospheric conditions.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site.- When shared Rodwoste 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 connot occurately be ascribed to a specific unit. An estimate should be mode of the contributions from each l

unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not procticable, the treated effluent releases may be allocated equally to each of the radiooctive waste producing units sharing the Rodwoste Treatment System. For determining conformance to Operability Requirements, these allocotions from shared Rodwoste Treatment Systems are to be odded to the

p

,V releases specifically attributed to each unit to obtain the total releases per unit.

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BYRON Rsvision 1.3 March 1996 12.4.3 Dose - lodine 1-131, lodine-133. Tritium, and Radioactive Material in Particulate EQIID

Ooerobility Reauirements 12.4.3.A The dose to o MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium, and all 4

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 i

(see Byron Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the foHowing:

1. During any calendor cuarter. Less than or eauol to 7.5 mrems to any organ, and 4

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

Acolicability- 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 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 compilance with the above limits.

Surveillance Reauirements 12.4.3.B Cumulative dose contributions for the current calendor quarter and the current calendor year for lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 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 H.C. Ill.A and !

IV.A of Appendix 1,10 CFR Port 50. The Operability Requirements are the guides I set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the some time implement the guides set forth in Section IV.A of Appendix l fo assure that the releases of radioactive material in gaseous effluents at or beyond the Site Boundary will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix I be shown by calculational procedures based on models and dato, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

g*abdcmhnexMron%12r13.wpf 12-34 a.

BYRON Rsvision 1.3 March 1996 12.4.3 Qgan (Continued)

. Rmas The ODCM calculational methodology and parameters for calculating the doses due to the octual release rates of the subject materials me consistent with the methodology provided in Regulatory Guide 1.109,"Colculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evoluoting Compliance with 10 CFR Port 50., Appendix t' Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estimating Atmosphenc Transport and Dispersion of Goseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the octual doses based upon the historical overage atmospheric conditions.

The release rate specifications for lodine-131, lodine-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) individualinholation of airborne 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 animors graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man.

This section opplies to the release of rodioactive materials in gaseous effluents from each unit of the site. When shored Rodwoste Treatment Systems are used by more than one unit on a site, the wastes from oil units are mixed for shared treatment; by such mixing, the effluent releases connot occurately be ascribed to o 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 shoring the Rodwoste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Rodwoste Treatment Systems are to be odded to the releases specifically attributed to each unit to obtain the total releases per unit.

s:mawcmwmen v roney12rt-3.wpf 12-35

BYRON Revision 1.3 March 1996 12.4.4 Gaseous Radwaste Treatment System Ooerability Reauirements 12.4.4.A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases O om each unit, to creas at and beyond the SITE BOUNDARY (see Byron Station ODCM Annex, Appendix F, Figure F-1) would exceed:

1. 0.2 mrod to air from gamma radiation, or

2. 0.4 mrod to air from beto radiation, or

3. 0.3 mrem to any organ of a MEMBER OF THE PUBUC.

Acolicability: At all times.

Action:

1. With radioactive gaseous waste being discharged without treatment and in excess of the above 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) token to prevent a recurrence.

Surveillance Reauirements l 12.4.4.1.B Doses due to gaseous releases from each unit to creas 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 Goseous Rodwoste !

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 12.4.4.1.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment.

O gmedemwnnexwmnwt2ri-3.wpf 12 36

BYRON Rsvision 1.3 March 1996 12.4.4 Gaseous Rodwoste Treatment System (Continued)

Bases l 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 "os low as is reasonably achievable".

This section implements the requirements of 10 CFR 50.360, General Design Criterion 60 of Appendix A to 10 CFR Port 50 and the design objective given in Section ll.D of Appendix 1 to 10 CFR Port 50. The specified limits goveming the use of appropriate portions of the Goseous Rodwoste Treatment System were specifie<:1 as a suitable fraction of the dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10 CFR Port 50, for gaseous effluents.

This section opplies to the release of radioactive materials in gaseous effluents from each unit of the site. When shared Rodwoste 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 occurately 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 shoring the Rodwoste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Rodwoste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

l g:e .._ _t,=ty12r13.wyt 12 37 l

BYRON Revision 1.3 March 1996 12.4.5 Total Dose Ooerability Reauirements 12.4.5.A The annual (colendor year) dose or dose commitment to any MEMBER OF THE PUBUC 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.

Acolicability: At all times.

Action:

1. With the calculated doses from the release of radioactive n aterials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2, 12.4.2, or 12.4.3, calculations should be mode including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 12.4.5 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technico! Specification 6.9.2, o Special Report that defines the corrective action to be token to reduce subsequent relseses to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include on analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBUC from uranium fuel cycle sources, including all effluent pathways and direct radiction, for the calendor year that includes the release (s) covered by this report it shall also describe levels of radiation and concentratiori'of radioactive materialinvolved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Port 190 has not already been corrected, the Special Report shall include o request for a variance in occordance with the provisions of 40 CFR Port 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

Surveillance Reauirements 12.4.5.1.B Cumulative dose contributions from liquid and gaseous effluents shall be determined in 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.B Cumulative dose contributions from direct radiation from the units and from rodwoste storage tanks shall be determined in accordance with the j methodology and patometers in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Section 12.4.5.

O g*awdcrnwnnexeymney12ri-3.wpf 12 38 l l

U

l BYRON Rsvision 1.3 I March 1996 1

\

1 i

l 12.4.5 Total Dose (Continued) ,

i l l Rmas j

! 12.4.5.C This section is provided to meet the dose limitations of 40 CFR Port 190 that have

been incorporated into 10 CFR Port 20 by 46 FR 18525. The Section requires the

prepuui;0n 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 orgon, except the thyroid, which

. shall be limited to less than or equal to 75 mroms. For sites containing up to four

reactors, it is highly unlikely that the resultant dose to o MEMBER OF THE PUBUC will exceed the dose limits of 40 CFR Port 190 if the individual reactors remain

! within twice the dose design objectives of Appendix 1, and if direct radiation i doses from the reactor units and outside storoge tanks are kept small. The

! Special Report will describe a course of action that should result in the limitation j of the annual dose to o MEMBER OF THE PUBLIC to within the 40 CFR Port 190 limits. For the purposes of the Special Report, it may be assumed that the dose i commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the some site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed

! the requirements of 40 CFR Port 190 the Special Report with a request for o i variance (provided the release conditions resulting in violation of 40 CFR Port i 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 o timely request and fulfills the requirements of 40 CFR Port 190 until NRC staff action is completed. The j' variance only relates to the limits of 40 CFR Port 190, and does not apply in any 2

way to the other requirements for dose limitation of 10 CFR Port 20, as i oddressed in Sections 12.3.1 and 12.4.1. An individual is not considered a

j. MEMBER OF THE PUBLIC during any period in which he/she is engaged in i carrying out any operation that is part of the nuclear fuel cycle.

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g:weesonennemeyventy12ri-smpf 12 39

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BYRON Rsvision 1.3 March 1996 l

12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorino Prooram Ooerobility Reovirements ;

I 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, o description of the reasons for not ;

conducting the program os required and the plans for preventing a j recurrence.

2. With the level of radioactivity as the result of plant effluents in on environmental sampling medium at a specified location exceeding the j reporting levels of Table 12.5-2 when overaged over any calendor ;

quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification .6.9.2, o Specio! 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 potential annual dose

to a MEMBER OF THE PUBLIC is less than the calendor 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 the sampling medium, this report shall be submitted if:

concentration (11 . concentration (21 + ...>1.0 l reporting level (1) reporting level (2)'

When radionuclides other than those in Table 12.5-2 are detected and l ore the 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 calendor year limits of l Section 12.3.2,12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents: however, in such on event, the condition shall be reported and dese.ibed in the l Annual Radiological Environmental Operating Report required 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.

O g*stocrnwnatyroney12rt swpf 12-40

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BYRON Ravision 1.3 ;

March 1996 12.5 ltADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) l 3. With the milk somples unovoilable from one or more of the sompie i locations required by Table 12.5-1,- identify specific locations for obtaining replacement samples and odd them within 30 days no the Radiological Environmenid Monitonng Program given in the ODCM. The specific l locations from which somples were unavailable may then be deleted from the monitoring program. Submit controlled version of the ODCM ,

within 180 days including a revised figure (s) and tobie reflecting the new l locahon(s) with supporting information identifying the cause of the unovailability of samples and justifying the selection of new location (s) for obtaining samples.

L Survamance Reauirements #

12.5.1.B The radiological environmental monitoring program somples shall be collected

- pursuant to Table 12.5-1 from the specific locations given in the table and figure (s) in the ODCM, and shdi be ondyzed pursuant to the requirements of Table 12.5-1 and the detection capabluties requFed by Table 12.5-3. 3 I

Bases 12.5.1.C The ROdiciogicd Environmentd Monitoring Program required by this section provides representative measurements of radiation and of radioactive moierials- 1 in those exposure pathways and for those radionuclides that lood to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Port 50 and thereby supplements the radiciogical 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 mereciing program is provided by the Radiologicd Assessment Bronch Technicd Position on Environmentd Monitoring.

The initially specified monitoring program will be effective for of least the first 3 years of commercid operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample ondyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 ore 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 on offer the fact limit for o particular measurement, j Detailed discussion of the LLD, and other detection limits, con be found in HASL :

Procedures Monuol, HASL-300 (revised annually), Currie, LA., " Limits for Quaitative Detection and Quontitative Determination - Application to Radiociwirsity," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K.. " Detection 4 Limits for Radioonalyticd Counting Techniques," Atlantic Richfield Honford Company Report ARH-SA-215 (June 1975).

e:*snododennedreney12rt-smpt 12-41

BYRON Rsvision 1.3 March 1996 12.5 EADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

Interoretations 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 i: defined l os water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking.

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ghbdanunnextyronby12r13.wpf 12 42

Revision March 19 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS"' COLLECTION FREQUENCY FREQUENCY OF ANALYSIS

1. Airborne Samples from o total of eight locations: Continuous sampler Radioiodine Canister-Radioiodine and operation with sample I-131 onalysts weekly Porticulates o. Indicolor- Near Field collection weekly (or more on near field samples ;

frequently if required due to and control. 82 Four samples from locations within 4 km (2.5 dust loading).

mi) in different sectors. Parhculate Sumcier-Gross beto analysis

b. Indicator- For Field following weekly filter changem ond gamma Three additional locations within 4 to 10 km isotopic analysis"8 (2.5 to 6.2 mi) in different sectors. quartesty on composite filters by

c. Control location on near field somples and control.t3 One sample from o control location within 10 to 30 km (6.2 to 18.6 mi).

gwedennennextyronty12rt-3.wpf 12-43

BYRON R vision 1.3 March 1996 TABLE 12.5-1 (Continued) j RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS"3 COLLECTION FREQUENCY FREQUENCY OF ANALYSIS

2. Direct Forty routine monitoring stations either with Quarterly Gamma dose on Radiation'8 , a thermoluminescent dosimeter (TLD) or each TLD quarterfy.

with one instrument for measuring dose role continuously, placed as follows:

a. Indicolor- Inner Ring *

(100 Series TLD)

One in each meteorological sector, in the general area of the SITE BOUNDARY:

b. Indicolor- Outer Ring (200 Series TLD)

One in each meteorological sector, within 6 to 8 km (3.7 to 5.0 mi): and

c. Other One of each Airborne location given in part 1.0. and 1.b.

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

[300 Series TLD) g xtyron%12rt-3.wpf

O N Rsvision 1.3 March 1{

TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND l ANDI OR SAMPLE AND SAMPLE LOCATIONS"8 COLLECTION FREQUENCY FREQUENCY OF ;

ANALYSIS ;

2. Direct d. Control Quarterly Gamma dose on Rodiation'5' (Cont'd) each TLD quarterty. -

One at each Airbome controllocation i given in part 1.c

3. Waterbome o. Indicator Quarterly Gomma isotopic'9 ;

o. Ground / Well ond kitium analysis !

Samples from two sources only if likely to quartetty. !

be offected.89

b. Drinkingt71 c. Indicolor Weeldy grab somples. Gross beto and -

gomma isotopic One Sample from each community analyses'9 on monthly !

drinbng water supply that could be composite; kitium j offected by the stolion discharge within analysis on quarterly -

10 km (6.2 mi) downstream of discharge. composite. ,

c. Surfoce if no community water supply (Dnnhng Weekly grab samples. Gross beto and l Water 4 71 Water) exists within 10 km downstream of gunisisc isotopic l discharge then surface woler sampling shall analyses'9 on nx>nthly be performed. composite: kitium i analysis on quarterly ,

c. Indcotor composite.

One sample downstreomm t

d. Control o. Control Weekly grab samples. Gross beto and i' Sample'73 gomma isotopic One surface sompie upstream of analyses'9 on monthly i discharge. composite: kifium ;

onolysis on quarterly composite.

g:Wawdemwmentyronty12rl-3.wpf 12-45

BYRON Rsvision 13 March 1996 TABLE 12.5-1 (Continued)

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

e. Sediment a. Indicolor Semsonnually. Gamma isotopic analysis 19 At least one sample from downstream m semiannually.

area within 10 km (6.2 mi).

4. Ingestion o. Indicator Brweekly m when animals are Gammo isotopic t9 on posture (May through and

o. Milk

Samples from milking animals from o October), monthly of other I-131"5 onotysis on maximum of three locations within 10 km times (November through each sample. ,

I (6.2 mij distance. April).

b. Control One sample from milking animals of a controllocation within 15 to 30 km (9.3 to 18.6 mi).

b. Fish o. Indicator Two times.onnually. Gammo isotopic analysis'9 on edible Representative samples of commercially portions and recreationally important species in discharge area.

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

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B Rsvision March 1996 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIV5 SAMPLES SAMPLING AND TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONSm COLLECTION FREQUENCY FREQUENCY OF -

ANALYSIS

c. Food Products . c. Indicator Annvolly Gamma isotopict'3 onalysis on each 1 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 vegeloble sample t"3 .

At least one broad leot vegetable (or '

vegetation)("3 i

b. Control Two representative samples similar to 4 indicator samples grown within 15 to 30 km (9.3 to 18.6 mi).

i g:*abdemwnex%ror2y12rt-3.wpf 12 47

BYRON Rsvision 1.3 March 1996 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centeriine of the midpoint of the two units and additionc! description where pertinent, shall be provided for each and every sample location in Table 1.1-1 of the ODCM Station Annexes. Refer to NUREG-0133," Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

(2) For 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 airborne effluents from the station, or at the discretion of the Heoith Physics Support Director.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivitv 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more offer sampling to allow for radon and thoron daughter decay.

If gross beto 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 identification and quantification of gommo l (4) 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 radiction. The 40 locations is not an absolute number. The number of direct radiation monitoring 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 chorocteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(6) Groundwater samples shall be token when this source is topped 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 on estuary must be taken for 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, oil milk sampling shall be discontinued.

(9) B'rweekly refers to every two weeks.

(10) 6-131 onalysis means the analytical separation and counting procedure are specific for this radionuclide.

(11) One sample shall consist of a volume / weight of sample large enough to fill contractor specified container.

ghWdcmunnextyronty12ri-3mpf 12 48

O O aed, BYRON TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/t) OR GASES (pCi/m ) 8 (pCi/kg, wet) (pCi/t) (pCi/kg, wet)

H-3 20.00008 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 2A 0.9 3 100 Cs-134 30 10 1.000 60 1,000 Cs-137 50 20 2.000 70 i 2.000 Bo-La-140 200 300 (1) For drinking water samples. This is 40 CFR Port 141 value. If no drinking water oathway exists, o value of 30.000 pCi/t may be used.

(2) If no drinking water pathway exists, o value of 20 pCi/t may be used.

g:tabdcmWmex%rorey12rt-3.wpf 12-49 >

Revision 1.3 March 1996 BYRON TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISM LOWER LIMIT OF DETECTION (LLD)N#

WATER : AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/t) OR GASES (pCi/m') (pCi/kg, wef) (pCi/f) (pCl/kg, wef) (pCi/kg, dry) l Gross Belo 4 0.01 1000 ,

l H-3 200 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 i

1-131 1/15M 0,07 100 0.5/5t8 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Bo-La-140 15 15 gwwdanwnnextyroney12ri-3.wpf 12-50 1

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1 Revision 1.3 ,

March 1996 BYRON TABLE 12.5-8 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS l 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 RWol Environmental Operating Report.

(2) Required detection capabilities for thermoluminescent dostnoters used for environmental ,

measurements shall be in accordonce with the recommendations of Regulatory Guide 4.13. *

(3) The Lnwer Limit of Detection (LLD) is defined, for purposes of these specifications, as the ' smallest ,

concentration of radiooctive material in a sample that will yield a not count, above system background, that will be detected with 95% probabikty'with only 5% probability of falsely concluding that a blank observation represents a 'Yeof" signol.

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

4.M S. + 3/t.

LLD =

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

4.s S.

LLD -

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

Where: 4.M S. >> 3/t.

LLD = the "o pnori" Minimum Detectable Concentration (picoCuries per unit mass or volume),

s. = the standard deviation of the background counting rate or of the counting rate of a blank sample, os appropriate (counts per minute),

, VTotal Counts Cb 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 rodiochemical yield, when applicable, A = the radioactive decoy constant for the particular radionuclide (seed ),

s:wtart-smpf 12-51

i Ravision 1.3 l March 1996 BYRON

. TABLE 12.5-3 (Continued)

' DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS l

t, = counting time of the background or blank (minutes), and l

1 at= the elapsed time between sompie collection, or end of the sample collection period, and the time of counting (sec).

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

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

l Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine 1 l conditions. Occasionally, background fluctuations, unavoldoble small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

l in such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

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

(5) A value of 0.5 pCi/t shall be used when the animals are on posture (May through !

October) and a value of 5 pCi/t shall be used at all other times (November through ,

April).

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O okawdemwnnexwyronwy12rt 3.wpf 12-52

BYRON Revision 1.3 March 1996 1 .2 Land Use Census

.rability Recuirements 12.5.2.A. A Land Use Census shall be conducted and shallidentify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors

of the nearest milk animal, the nearest residence", and an enumeration of livestock. For dose calculation, o garden will be assumed at the nearest residence.

Acolicability: At all times.

Action:

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment, via the some exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new 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 I calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from l this monitoring program offer October 31 of the year in which this Land Use Census was l conducted. Submit in the next Annual Radiological Environmental Operating Report I documentation for a change in the ODCM including a revised figure (s) and table (s) for the l ODCM reflecting the new locofion(s) with information supporting the change in sampling locations.

This requirement may be reduced according to geographical limitations; e.g. of a lake site where some sector's will be over water.

"The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Recuirements 12.5.2.B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, cerio: survey, or by consulting local agriculture authorities. The results of the l Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE l BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring 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. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

ghWdcrmarmextyror2y12rt-3.wpf 12-53

BYRON Rsvision 1.3 March 1996 12.5.3 Interioboratory Comoorison Procram Ooerobility Reauirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interloboratory l Comparison Program that correspond to samples required by Table 12.5-1.

Acolicability- At all times.

Action-i

1. With analyses not being performed as required above, report the corrective !

octions taken to prevent a recurrence to the Commission in the Annua!

l Radiological Environmental Operating Report.

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

Boses l 12.5.3.C The requirement for participation in on interioboratory Comparison Program is provided to ensure that independent checks on the precision and occuracy of the measurements of l radioactive materialin environmental samples matrices are performed cs part of the 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 1 to 10 CFR Port 50.

O g:*aWicrnunnexeyronty12ri-3 wpf 12-54

BYRON Ravision 1.3 March 1996

? REPORTING REQUIREMENTS <

\ l 12.6.1 Annud Radiologicd Environmental Ooeroting Reoort' Routine Annud R~*olagical Environmental Operating Report covering the operation of I the Unit (s) dunng the previous calendor year shall be submitted prior to May I of each l year.

The Annual R~*alagical Environmental Operating Report shall include summones, interpretailons, and on analysis of trends of the results of the rodological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls os appropriate, and with previous environmental surveillance reports, and on ossessment of the observed impacts of the plant operation l on the environment.

The Annual Radiologicd Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements l_ token 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. !

The reports shall also include the following: a summary description of the Radiological 3

l Environmental Monitoring Program: legible maps covering all sampling locations keyed to o table giving distances and directions from the midpoint between the two units: reasons for not conducting the Radiological Environmental Monitoring Program os required by Section 12.5.1, o Table of Messed Samples and a Table of Sample Anomalies for all deviations from the sompling schedule of Table 11.1-1; discussion of environmental sompie measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents discussion of all analyses in which the LLD required by Table 12.5-3 was not ochievable: result of the Land Use Census required by Section 12.5.2: and the results of the licensee participation in on interloboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

l l *A single submittal may be made for a multiple unit station.

I os. .. _ _,. .c.ey12ri-3.wpr 12-55

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BYRON RLvision 1.3 i March 1996 l

12.6 REPORTING REQUIREMENTS (Cont'd) ,

12.6.1 Annual Radiolooico! Environmental Ooerotino Reoort (Cont'd) i The Annual Radiological Environmental Operating Report shall also include on annual I summary of hourty meteorological dato collected over the applicable year. This annual summary may be either in the form of on 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 distributions 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 dato on site in a file that shall be provided to the NRC upon request.

The Annual Radiological Environmental Operating Report shall also include on l assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendor year. This report shall also l include on assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBUC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation, for the previous colander year. The ossessment of radiation doses shall be performed in occordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Port 190," Environmental Radiation Protection Standards for Nuclear Power l Operation." 3 J

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4 BYRON Rsvision 1.3 March 1996 REPORTING REQUIREMENTS (Cont'd)

. 2 Annual Rivervw-tive Effluent Release Reoort"

' Routine Annual Radioactive Effluent Release Reports covering the operation of the unit g

during the previous calendor year of operation shall be submitted prior to May 1 of the l

following year.

f The Annual Rodcoctive Effluent Release Reports shallinclude a summary of the quantities of radiooctive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,"Measunng Evoluoting, and Reporting RcdiccC;"y in Solid Wastes and Releases of Radioactive Materials in Liquid and Goseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summorned on a quarterly basis following the format of Appendix B thereof. &

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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 Port 61), type of container (e.g., LSA, Type A, Type B, large Quantity), and SOUDIFICATION ogent or absorbent (e.g, cement, ureo formaldehyde).

' The Annual Rodcoctive Effluent Release Reports shoH include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive matenols in gaseous and liquid effluents made during the reporitng period.

The Annual Radiooctive Effluent Release Reports shoN include any changes made during the reporting period to the PCP as well as any major changes to Liquid, Goseous or Solid Rodweste Treatment Systems, pursuant to Section 12.6.3.

The Annual Rad 6oactive Effluent Release Reports shall also include the following: on 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, l respectively; and description of the events leading to liquid holdup tonks or gas storage :

l tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively, i

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" A single submittal may be mode for o multiple unit station. The submittal should I combine those sections that are common to all units at the station; however, for l units with separate rodwoste systems, the submittal shall specify the releases of )

radioactive material from each unit. i l

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BYRON Rsvision 1.3 March 1996 12.6.3 Offsite Dose Calculation Manual f0DCM) 12.6.3.1 The ODCM shall be approved by the Commission prior to 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 oppropriate analyses or evoluotions justifying the changes (s) and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CF.R 20,106,40 CFR Port 190,10 CFR 50.360, and Appendix 1 to 10 CFR~ Port 50 and not adversely impact the occuracy or reliability of effluent, dose, or setpoint calculations.

~

b. Shall become effective offer review and occeptance by the Onsite Review and investigative 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 the 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 a part of or concurrent with the Annuol' 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 offected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

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BYRON Rsvision 1.3 March 1996 12.6.4 Maior Chonoes to Liould and Goseous Rodwoste Treatment Systems ***

Ucensee-initiated major changes to the Rodwoste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Comivii ion in the Annual Radioactive Effluent {

Release Report for the penod in which the evoluotion was reviewed by the Onsite Review and investigative Function. The discussion of each change shall contain:

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

2) Sufficient detailed information to totally support the reason for the ,

change without benefit of odditional and supplementalinformation:

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

4) An evoluotion of the change ohich shows the predicted releases of rodioactive materials in liquid and gaseous effluents that differ from those previously predicted in the Ucense opplication and amendments thereto:

5) An evoluotion of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBUC in the UNRESTRICTED AREA

{ and to the general population that differ from those previously estimated in the Ucense application and amendments thereto:

6) A componson of the predicted releases of radioactive materials, in .

liquid and gaseous effluents, to the octual releases for the period prior to when the changes are to be rnode:

7) An estimate of the exposure to plant operating personnel os a result of the change; and

8) Documentction of the fact that the change was reviewed and found acceptable by the Onsite Review and investigative Function,

b. Shall become effective upon review and acceptance by the Onsite Review and investigative Function.

- - Ucensees may choose to submit the information coiled for in this standard as port of the annual FSAR update.

O g:N12ri-3.wpf 12-59

BYRUN Revision 1.3 March 1996 BYRON ANNEX INDEX PAgi REVISION PAGE REVISION APPENDIX F F-1 1.3 F-43 1.3 F-il 1.3 F-44 1.3 F.51 1.3 F-45 1.3 '

F-iv 1.3 F-46 1.3 F-1 1.3 F-47 1.3 ,

F2 1.3 F-3 1.3 :

F-4 1.3 F-5 1.3 F-6 1.3

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F-7 1.3 1 F-8 1.3 )

F-9 1.3 F-10 1.3 F-11 1.3 F-12 1.3 F-13 1.3 F-14 1.3 O F-15 F-16 F-17 1.3 1.3 1.3 F-18 1.3 F-19 1.3 F-20 1.3 F-21 1.3 F-22 1.3 F-23 1.3 i F-24 1.3 F-25 1.3 ~ l F-26 1.3 i F-27 1.3 F-28 1.3 F-29 1.3 F-30 1.3 F-31 1.3 F-32 1.3 F-33 1.3 F-34 1.3 F-35 1.3 F-36 1.3 F-37 1.3 t-38 1.3 F-39 1.3 F-40 1.3 O-F-41 F-42 1.3 1.3 FJ

l BYRON Revnion 1.3 l March 1996 i APPENDIX F O

STATION 4PECIFIC DATA FOR BYRON UNITS 1 AND 2 I TABLE OF CONTENTS l

P. AGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 l l

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i BYRON Revision 1.3 March 1996 APPENDIX F LIST OF TABLES NUMBER IIILE Eefri F-1 Aquatic Environmental Dose Parameters F-2 F-2 Station Characteristics F4 F-3 Crt6 cal Ranges F F-4 Average Wind Sp% F6 F-5 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-7 F-Se X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary F-8 F8 D/Q at the Nearest Mik Cow and Meat Animal Locations Within 5 Miles F-9 F-7 Maximum Offalte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Os Boundary for Selected Nucides F-10 ,

1 F-7s Maximum Offsite Finito Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuc5 des F-25 ,

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l Supplemental Tables A Mixed Mode Joint Frequency Distribution Table Summaries - 250 and 30 Foot Elevation Data F-40

-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-44

-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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BYRON Revision 1.3 March 1996 APPENDIX F UST OF FIGURES NUMBER IlIl2 Edfdi F-1 Unrestricted Aree Boundary F-46 F-2 Restricted Area Boundary F-47 l

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BYRON Revision 1.3 I March 1996 O

APPENDlX F STATION 8PECIFIC DATA FOR BYRON UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the Byron site. Included is a figure showing the unrestdcted area boundary and values of parameters used in offsite dose assessment.

Dose factors are changed from previous revisions only if a higher value is justified based on new census data. Nearest resident, mik cow, and meet animal ranges are changed from previous revisions only if a more conservative value is justified based on new census data.

Original tables were based upon the 1993 Annual Land Use Census performed by Tolodyne isotopes Midwest Laboratories.

F.2 REFERENCES Sargent & Lundy, Analysis and Technology Division Byron Calculation No. ATD-0150, l1. Revisions 0,1, and 2.

2. " Irrigation from the Rock River" letter imm G.P. Lahti (Sargent & Lundy) to J.C. Golden (NSEP), June 4,1990.

3. "Vedlication of Environmental Parameters used for Commonwealth Edison Company's Ofinite Dose Calculations," NUS Corporation,1988.

4. "Vedfication of Environmental Parameters used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group,1992. j l

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BYRON Revision 1.3 March 1996 0 .

Tatdo F-1 Aquatic Environmental Dose Parameters General information*

There are no putic potable water intakes on the Rock River clownstroom of the station.

Thors is no irrigallon occoning on the Rock River downstreer.4 of the station.

t.creet;or. :r.c:udes or.r, or more of the .ot.'ow'rs: . bc.at:rs, wat rm s, swim,*s, und sport fishing.

Acconting to Section 2.4.1.2 and F10ure 2.4 6 of the Byron Environmental Report, there are four downstroom dams on the Rock River within --- ;,, -T; 50 miles of the station one at Oregon, Dixon, and two at Storing.

Water and Fish inosalion Pammators Parameter" Maham IN", IM 1.0 F", ofs. 6.55E4 F', cis 6.25E3 f,hi* 24.0 f", hrd 115 Limits on Radonctivity in Unorotected Ouldoor Tanks

l Outelde Temporary Tank 5 10 Cf (per Technical Specincetion 3.11) , 1 l

This is bened on information in the Byron Environmental Report, Figure 3.3-1 and Section 2.1.3.2.1.

The parameters are deRned in Section A.2.1 of Appendtx A.

t' (hr) = 24 hr (en stations) for the ilsh ingestion pathway O

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BYRON Revision 1.3 i . March 1996 k

l Table F-1 (Cont'd) i Aquatic Environmental Dose Parameters

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i t"(hr) = 115 hr (Rock River flows into Mississippi River about 115 miles downstroom of the j station at the rate of 1 mph based on the data in Table 2.2-5 of the Byron Station i Environmental Report).

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See Section A.7.4 of Appendix A.

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

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j BYRON Revisson 1.3

. March 1996 O

Table F4 i Station Characteristics i STATION: Byron 1

LOCATION: 3.7 miles SSW of Byron, IRnois j l

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CHARACTERISTICS OF ELEVATED RELEASE POINT: Not appicable (NA) l

1) Release Height = m 2) Diameter = m l l

3) Exit Speed = msd 4) Heat Content = KCal S4* ;

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CHARACTERISTICS OF VENT STACK RELEASE POINTS

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1) Release Height = 60.66 m' 2) Effective Diameter = 2.80 m

3) Exit Speed = 13.00 mad '

'The station has two adjacent rectangular vent stack release points of the same height and cross sechon. Their centers are 15.01 m apart.

CHARACTERISTICS OF GROUND LEVEL REi. EASE 4

1) Release Height = 0 ft

2) Building Factor (D) = 60.6 m' METEOROLOGICAL DATA A_250.Jt Tower is locatpd 1036 m,,,fdBLof vent stack release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA)

Vent 250A 250 - 30 A Gmund 30 A 250 - 30 A

'Used in calculating the .T-::;-ic'c-ycal and dose factors in Tabios F-5, F-6, and F-7. See Sections B.3 L through B.6 of Appendix B.

F.4

BYRON Reymon 1.3 March 1996 O Table F 3 Critical Ranges Unrestricted 4

Area Restricted Nearest Nearest Dairy Farm l Boundary

Area Boundary Resident

Within 5 Miles

Direction (m) (m) (m)

N 1875 777 4300 None NNE 1829 538 1600 None NE 1GGG 023 1000 3000 ENE- 1234 474 2100 None E 1227 468 2100 None ESE 991 480 2300 None SE 1006 427 1200 None SSE 800 410 1000 None l8 945 295 800 7700 SSW 975 299 1000 None SW 1067 451 1200 None WSW 1212 3 34) 2700 None lW 1189 379 2700 1200 4000 5300 WNW 1227 385 NW 1128 445 1600 4800 i NNW 1044 658 2100 None 1

See Updated Final Safety Analysis Report Table 2.1-1a and Environmental Report. Used in calculating l the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.

The distances are rounded to the nearest conservative 100 meters.

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BYRON Revmon 1.3 March 1996 Table F-4 O

Average Wind Speeds Avermae Wind Speed (m/secP Downwind Direction Elevated

Mixed Mode Ground Level

N 7.9 6.3 4.2 NNE 7.6 6.3 4.5 NE 6.8 5.8 4.1 ENE 6.6 5.6 4.0 E 6.9 5.9 4.5 ESE 6.9 5.9 4.5 SE 6.5 5.7 4.0 SSE 6.2 5.4 3.7 S 6.3 5.4 4.0 SSW - 6.0 5.3 3.9 SW 6.1 5.4 4.2 WSW 6.4 5.6 4.1 W 6.8 5.5 3.4 WNW 7.1 5.7 3.7 NW 7.1 5.7 3.8 NNW

7.7 6.0 4.1

" Based on Byron site meteorological data, January 1978 throu9h December 1987. Calculated in Reference 2 of Soc 6on F.2 using formules in Section B.1.3 of Appendix B.

7he elevated and ground level values are provided for reference purposes only. Routine dose calcuistions are performed using the mixed mode values.

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. O CYRON sevlolon 1.3 i Merch 1996 [

Table F-5 i i

XtQ and DN3 Maxima et or Beyond the Unrestricted Area Eoundary 1 r

Deurwirul Rimed Nede(vent) Retenee eroemd Level Release f streetten Redlue x/4 Redlue e/e Redlue x/4 e/G !

testers) (see/uP*3) (meters) (1/uP*2) (sesters) (sec/w**3) (1/uP*2) i

., N 1875. 1.98BE-ST 1875. 1.985E-99 1875. 8.6ME-ST 4.4T1E-99 . [

NEE 1829. 1.4TFE-ST 1829. 1.92FE 99 1829. T.531E-ST 4.271E-99 - i NE 1585. 1.53OE-97 1595. 1.821E-99 1505. T.8NE-ST 4.3EEE-99 I ENE 1234. 1.353E-9T 1234. 1.764E-99 1234. 5.000E-ST 5.03dE-99

E 122T. 1.4EEE-ST 1227. 2.335E-99 1227. 1.14M N 6.220E-99 ESE 991. 2.519E-9T 991. 3.540E-99 991. 1.992E-N 9.99EE-99 5 l SE 1996. 3.920E-97 1996. 3.578E-99 1906. 2.480E N 1.118E-08 i SSE 800. 4.49FE-97 800. 3.M1E-99 808. 4.152E- N 1.429E-0G ;

S MS. 2.249E-9T 945. 2.79EE-99 MS. 1.94dE- N 9.344E-99 ssif 975. 1.4NE-9T 975. 1.9 FOE-99 975. 1.385E-96 4.4 FEE-99 -

su 196T. 1.148E-9T 1967. 1.78dE-99 196T. 9.2FTE-9T 5.314E-99 [

U5W 1212. 1.199E-9T 1212. 1.903E-99 1212. T.44dE-97 5.98EE-99 P W 1199. 1.753E-9T 1199. 1.9 FEE-99 1189. 9.348E-ST 5.330E-99 I isnt 1227. 1.295E-ST 1227. 1.292E-99 1227. 6.543E-97 3.T45E-99 I Inf 1129. 1.40dE-97 1129. 1.T19E-99 1125. 8.80FE-ST 4.994E-99 i Isai 1944. 3.94FE-0T 1944.- 3.II3E-99 1944. 1.43EE-06 8.8T1E-99 l i

syren alte Noteereietteet esta 1/78 - 12/37 i

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Note: Based on Reference 2 of Section F.2 and the formules in Sections B.3 and B.4 of AppendE B.

. xna is used for bote sidn, and inheisson dose pathways. See Secuens C A A.1.3, and 161.4.2 of Apprendix.A. !

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DNa is used for produce and leefy vegetable pathways. Secuan A.1.4 of Appendix A. !

The greemd level reisese dWe are provided for referettoo purposes orily, h dose ce6h are performed using trdxed mode date.

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Redus is the approximate tRetence from the midpoint between geoeous efiluent reloose pcints to the locanon of highest X/Q or DNa et or beyond the unrestricted area boundary (UAB).

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klYHUN Revfolon 1.3 March 1996 d ~~ Telde F-8e XN3 and DNn Maximo et or Beyond the Restricted Area Boundary i

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Rised mode (Vent) meteese tromd Levet Retense Domulnd Redlus N/e B/s pirectlen Redius X/t Redlus 9/t (asters) (see/uP*S) (metere) (1/eP*2) (astere) (see/uP*3) (1/W**2)

TTT. 6.35M-97 TTT. 7.004E 09 TTT. 3.2ME- M 2.934E-98 N

330. 8.TNE-ST 538. 1.044E OS 538. 5. OSSE-M 3.195E-95 NEE 528. 6.855E-ST 528. T. NEE W SIS. 4.3T1E- M 2.44eE-08 NE ;

474. 5.341E-DT 474. 5.MM 99 474. 4.914E- M 2.344E-08 Est 440. 5.35M-M 2.95eE-98 E 460. 6.69E-9T 448. T.958E-Of 400. T.37M-97 480. S.965E 99 400. 5.434E- M !.144E-98 i ESE 427. 1.12dE-M 42T. 1.965E-98 42T. 1.024E-95 8.352E-08 st 419. 1.349E-M 410. 8.744E 99 419. 1.355E-55 4.944E-98 ssE :

295. 1.441E-06 295. 1.171E-85 295. 1.391E-95 !. 797E-95 s

299. 9.352E-97 299. 5.295E 99' 299. 9.374E 96 4. 19M -98 SSW 451. 3.949E-97 451. 5.065E 99 451. 3.448E- M 2.995E-OS su 386. 6.998E-07 386. T.425E-99 386. 4.699E-96 3.SSR-98 Usu l 3M. 1.M1E 06 379. 3.114E-99 379. 6.009E M 3.275E-98 W 4.3BIE M ;t.379E OS lenf 305. T.454E-97 305. 6.001E-99 305.

445. T.394E 97 445. 6.117E-09 445. 4.06SE 06 :!.190E 98 NW 2.90gE-96 1.SNE-98 usu 488. 6.125E-ST GSS. 6.1TM-99 488.

Byron site seteoreteeleet Dete 1/75 - 12/ST i

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Note: Bened on Reference 2 of Secton F.2 and the formules in Sectons B.3 and B.4 of Agipener B.

The ground level release date are provided for reference purposes only. Roudne done calculeuano are penome!

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RecRus is the -;---,J . ^J tRetence from the rnidpoint between geneous efiluent rotsese points to the loceNon of highest XKt or DM3 at or beyond the realdcted area boundary (RAB). i i

F-8

N Revi .3 March 1996 Tsble F-6 D/O at the Nearest Milk Cow and Meat Animal Locations within 5 miles Downwind Nearest Milk Cow D/Q(1/m"2) Nearest Meat Animal DiO(1/m"2)

Radius Mixed Ground Radius Mixed Ground Direction Release Release (meters) Release Release (meters) 8000 1.895E-10 3.643E-10 4800 4.499E-10 9.079E-10 N

1.835E-10 3.192E-10 2400 1.282E-09 2.677E-09 NNE 8000 3000 7.187E-10 1.462E-09 5500 2.799E-10 5.027E-10 NE 8000 1.096E-10 1.928E-10 3700 3.792E-10 7.603E-10 ENE 8000 1.417E-10 2.361E-10 3600 5.164E-10 9.770E-10 E

S000 1.614E-10 2.635E-10 2400 1.082E-09 2.209E-09 ESE 8000 1.698E-10 3.050E-10 2700 3.439E-10 2.085E-09 SE 8000 1.387E-10 2.664E-10 5100 2.923E-10 5.968E-10 SSE 7700 1.381E-10 2.477E-10 900 2.967E-09 1.014E-08 S

8000 9.795E-11 1.729E-10 3500 3.645E-10 7.563E-10 SSW 8000 9.554E-11 1.596E-10 5100 2.006E-10 3.574E-10 SW 1.202E-10 1.858E-10 2700 6.571E-10 1.270E-09 WSW 8000 3.281E-10 6.590E-10 2700 5.945E-10 1.310E-09 l W 4000 5300 1.464E-10 2.968E-10 5300 1.464E-10 2.968E-10 WNW 4800 1.978E-10 4.088E-10 6100 1.339E-10 2.674E-10 NW 8000 1.349E-10 2.571E-10 2200 1.092E-09 2.596E-09 NNW Byron Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 2 in Section F.2 and the formulas in Section B.4 of Appendix B.

Approximate distance from the station as determined by annual census.

The ground level release data are provided for reference purposes only.

Routine dose calculations are performed using mixed mode release data.

F-9

CYRON Revmon 1.3

.,- March 1996.

Table F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83rn Doesuelnd Unrestricted Mixed Nede(Vent) Release Gromd Level Reteese 81rection Area 8e e d Redlus V V8AR Radius G G8AR ;

(meters) (meters) (ared/yr)/(tCl/sec) (meters) (ared/yr)/(uCl/sec) t M 1875. 18 5 . 2.330E-05 1.757E-05 1875. 9.565E-05 T.212E-05 <

NME 1829. 1829. 1.957E-05 1.460E-05 1829. 8.084E-05 6.095E-05 NE 1585. 1585. 1.773E-05 1.336E-05 1585. 8.469E-05 6.386E-05 ,

l ENE 1234. 1234. 1.672E-05 1.260E-05 1234. 1.002E-04 T.555E-05 E 1227. 1227. 2.049E-05 1.545E-05 1227. 1.252E-04 9.441E-05 l ESE 991. 991. 3.142E-05 2.369E-05 991. 1.925E-04 1.451E-04 i sE 1006. 1006. 3.694E-05 2.785E-05 1006. 2.683E-04 2.023E-04 E

+

SSE 800. 800. 5.135E-05 3.872E-05 800. 4.267E-04 3.217E-04 I

s 945. 945. 2.723E-05 2.053E-05 945. 2.121E-04 1.600E-04 ssu 975. 975. 1.795E-05 1.353E-05 975. 1.407E-04 1.061E-04 ,

f SW 106T. 1967. 1.379E-05 1.040E-05 1067.

USW 1212. 1212. 1.483E-05 1.118E 05 1212. 8.590E-05

~ 9.817E-05 T.402E-05 6.477E-05 I

W 1189. 1189. 2.193E-05 1.654E 05 1189. 1.100E-04 8.293E-05 ,

WNW 1227. 1227. 1.514E-05 1.141E-05 1227. T.802E-05 5.883E-05 +

W 1128. 1128. 2.112E-05 1.593E-05 1128. 1.033E-04 T.789E-05 ,

NNW 1044. 1944. 3.852E 05 2.904E-03 1044. 1.691E-04 1.275E-04 :

Byron site Noteoreto81cel Date 1/78 - 12/87

i i

l 1

Note: Based on Reference 2 of Sechon F.2 and the formulas in Sechons B.5 and B.6 of Appendet B.

Approximate distance from midpoint between gasous effluent re8asse points.

(' : f)GYRON

%./

O bevision 1.3 L

March 1996 4 Telde F-7 (Cont!nued)

RAeximum ONsite Finite Plume Genwne Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr40m l

l pounuind unrestricted Nimed Mode (Vent) Roteese tround Level Reteese ,

Directlen Aree Sound Redlue .V VBAR Redlue G 90AR (metera) (asters) (aradryr)/( w l/sec) (estere) (aradryr)/(uct/sec) i N 1875. 1875. 2.1FFE- M 2.894E- M 1875. 6.403E- M 6.14M -M l NNE 1829. 1829. 2.97EE-04 1.999E-04 1829. 5.544E-94 5.319E-04 ;

NE 1585. 1585. 2.922E-M 1.M7E-M : 1585. 5.TT3E-M 5.539E-04 !

ENE 1234. 1234. 1.904E- M 1.911E-M 1254. 6.395E-M 6.133E-M !

E 122T. 1227. 2.331E-M 2.MM-M 122T. T.968E-M T.640E-M I ESE 991. 991. 3.260E-M 3.13OE-M - 991. 1.136E-85 1.8OEE 03 I SE 1006. 1996. 3.T18E-M 3.5FIE-M 1906. 1.584E-05 1.517E-03 SSE 800. 800. 4.395E-M 4.223E-M 800. 2.2T3E-85 2.175E-03 ;

S MS. MS. 2.813E-M 2.79EE-M M5. 1.248E-03 1.188E-03 t esu 975. 975. 2.079E-M 2.802E-M 975. 8.631E-M 8.2TM-M f EU 1967. 1967. 1.6SOE-M 1.42FE-M 196T. 6.2SM-M 6.92FE-M i usu 1212. 1212. 1.751E-M 1.6SFE-M 1212. 5.594E-M 5.366E- M ;

W 1189. 1189. 2.992E-M 2.91M-M 1189. 6.72M-M 6.446E-M temi 1227. 1227. 1.464E-M 1.409E-M 1227. 4.690E- M 4.496E-M [

NW 1128. 11N. 1.926E-M 1.85N-04 1128. 6.01FE-M 5.766E-M ,

NNW 1944. 1944. 3.120E-M 3.005E-M 1944. 9.676E-M 9.272E-M l

Byron Site Meteerstesical Date 1/75 - 12/87 i

, .e .

F-11 u___ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ - . _ _ _ __ - __ _ _ _ . _ -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- _________m_._ _ . _ _____.;

GYRON Revision 1.3

'" March 1996 Table F-7 (Condnued)

Maximum ONelle Finho Phune Genene Does Factors Bened on 1 ene Depth at the Unsestricted Area Bonadery for Kr.45 Deemeind unrestefeted Rfmed Nede(Vent) Roteeee Grenend Levet Reteese Direetten Aree Bound Redfus V VGAR Redfue e GBAR teeters) testers) tarodryr)/tutt/see) (noters) teredryr)/(utt/see) t

, N 18F5. 18F5. 2.535E-96 2.45M-86 1875. T.318E 4 T.9TFE-n6 i NME 1829. 1829. 2.46 N-06 2.3EEE 4 1829. 4.302E-M 6.1 TIE-06 i NE 1585. 1585. 2.415E 4 2.355E-96 1585. 4.622E-M 6.485E-f4 '

EWE 1234. 1254. 2. MFE-96 2.20pt e 1254. T.225E4 6.900E-te E 1227. 1227. 2.787E-96 2.6P5E-86 122T. 9.191E 4 S.001E f4 EsE 991. 991. 3.82EE-06 3.792E-96 M1. 1.2FUE-05 1.22EE-tS EE 1906. 1906. 4.364E-96 4.220E-96 1906. 1.EESE-95 1.743e!-tS set 800. ROS. 5.153E-06 4.955E-96 800. 2.5TFE-95 2.492E-CS ,

s 945. 965. 3.321E-06 3.211E 4 945. 1.494E-95 1.358E-t$ i seu 9F5. 975. 2.49M 4 2.411E 4 9F5. 9.880E-96 9.543E-(4 ~ '

su 196T. 196T. 2.918E-96 1.951E 4 196T. .T.232E 4 6.995E-te usu 1212. 1212. 2.97EE-06 2.982E 4 1212. 6.305E4 6.100E-te !

W 1189. 118F. 2.43dE-96 2.35dE-96 1187. T.4F2E 4 T.225E-(6 '

WNU 122T. 1227. 1.79 N 4 1.652E 4 1227. 5.191E-96 5.919E-te i i mt 1128. 1128. 2.23EE-96 2.164E-06 1120. 4.678E-96 6.450E-C6 Mai 1944. 1944. 3.579E-06 3.441E-96 1944.- 1.9T1E-95 1.55dE t3 !

i Byron site Noteoreteelset Date 1/78 - 12/ST t

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O _ __ _ _ _ . _ _ _ _ _

9 _ _ . _

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

.. evision 1.3 March 1996 l t

w Tatdo F-7 (Continued)

Isaximuun Offsite Finite Plume Genune Dose Factors Based on 1 cm Depth at the UErnstricted Area Boundary for Kr-87 l i

I l

Doomulnd unrestrleted Mined Nede(Vent) Release tround Levet Re(sese !

Ofrectlen Aree sound Redlue V VBAE Redlue S GRAE l

(asters) (meters) (aradryr)/ tut 1/ses) (meters) (mradryr)/(stf/see) ,

u 1875. 1875. T.12EE- M 6.91dE- M 1875. 1.811E-85 1.758E-55 i ENE 1829. 1829. 4.991E-M 4.692E-M 1829. 1.555E-05 1.510E-85 !

HE 1505. 1585. 4.817E-M 6,420E-M 1505. 1.422E-05 1.574E-95 l ENE 1254. 1254. 6.85M-M 6.MIE-M 1254. 1.822E-55 1.76fE-95 :

E 1227. 122T. T.958E-M T.791E-M 1227. 2.214E-05 2.149E-85 I Est 991. 991. 1.12dE-55 1.9ME-55 991. 3.25dE-85 3.142E-E5 i' SE 1986. 1906. 1.2ME-85 1.227E-85 1906. 4.35dE-05 4.225E-05 Set 800. 800. 1.455E-55 1.413E-85 500. 6.185E-05 f.005E-05 t S 945. 945. 9.600E-M 9.401E-M 945. 3.451E-95 3.350E-85 !

seu 975. 975. 7.214E-M T.00EE-M 975. 2.574E-85 3.305E-95 .

su 1967. 196T. 5.927E-M 5.75dE-M 196T. 1.725E-85 1.675E-85 I usu 1212. 1212. 6.132E-M 5.955E- M 1212. 1.413E-03 1.566E-05 !

W 1989. 1189. T.981E-M 4.877E-M 1189. 1.971E-95 1.914E-03 i lent 1227. 1227. 4.978E-M 4.854E-M 1227. 1.381E-93 1.341E-05 !

Inf 1128. 1128. 6.517E-M 6.329E-M 1128. 1.753E-95 1.792E-05 !

lunt 1944. 1944. 1.040E-85 1.010E-05 1944. 2.828E-85 2.744E-85 i I

syren site Noteereleglemt Date 1/78 - 12/ST I i

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F-13 !

t i

i

Revision 1.3 March 1996 !

Table F-7 (Continued) -

L Maxinnun Offelte Finito Plume Genune Dose Factors Besod on 1 can Depth at the Unrestricted Amo Bonnelery for Mr.88 poeswivui Unrestricted Rimed Mode (Vent) Reteese Greed Level Reteese !

. Directlen Aree tend Redlue V VRAE Redlue G GRAE (astere) testere) taradryr)/(utt/see) (astere) (areWyr)/(utt/se:) .

R 18F5. 1875. 1.M1E-85 1.752E-85 18F5. 4.651E-85 4.495E-85 ENE 1829. 1829. * .744E-85 1.65dE-85 1829. 4.015-55 5.85W -55 i NE 1555. 1585. 1.725E-55 1.6TFE-95 1585. 4.174E-55 4.95dE-55 r EEE 1234. 1234. 1.721E-55 1.6T4E-95 1254. 4.61FE-95 4.4 NE-85 !

E 1227. 122T. 2.GOSE-85 1.953E-55 1227. 5. M1E-05 5.550E-85 t Est 991. 991. 2.794E-85 2.71N-85 991. 8.145E-85 T.951E-55 SE 1996. 1906. 3.153E-85 3.OddE-85 1986. 1.124E-92 1.992E-02 '

SSE 800. SOS. 3.45dE-05 3.554E-85 500. 1.601E-82 1.555E 02 i s M5. 945. 2.414E-95 2.348E-85 M5. 8.851E-55 8.57FE-05 t asu 9F5. 975. 1.821E-85 1.TT1E-95 975. 4.14dE-05 5.9 FEE 85 !

su 196T. 196T. 1.48dE-85 1.445E-85 196T. 4.48BE-95 4.560E-SI usu 1212. 1212. 1.525E-55 1.485E-85 1212. 4.000E-05 3.M4E 85 W 1989. 118P. 1.75dE-95 1.MFE 05 1989. 4.885-05 4.M5E 85 i Wuu 1227. 1227. 1.255E-05 1.281E-05 192T. 3.400E-E5 3.395E 85 !

Inf - 1128. 1125. 1.611E-85 1.56FE-55 1125. 4.344E-85 4.219E 55 i lumi 1M4. 1944. 2.540E-85 2.4TFE-M 1944. 6.9F4E-SS 6.TF5E 05 syren site Reteorotegical pote 1/78 - 12/8T ,

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F-14

_ _ _ _ _ _ , _ . _ _..__.________....._.________.m_.._ _._._...__..__...._......__.._._m. _ . . _ . . - _ _

evision 1.3 March 1996

'.. Table F-7 (Continued) 88anknum Offsite Finite Plume Genune Dose Factors Based on 1 cm Depth at the Umrestricted Area Boundary for Kr-89 f

poesmind unrestricted Wlmed Nede(Vent) Reteese grewul Level Release [~

9trectlen Aree Bewed Redius Y VBAR Redlue S EBMt

(meters) (meters) (arodryr)/(tCl/see) (meters) (ared/yr)/(uct/sec) !

N 18 5 . 1875. 3.874E-M 3.764E-M 18 5 . 5.119E M 4.9 TIE-M NME 1829. 1829.- 3.91M M 3.805E-M 1829. 4.514E- M 4.384E M i NE 1585. 1585. 4.092E-M 3.9F5E-M 1585. 4.994E-M 4.851E-M ;

ENE 1234. 1234. 4.909E-M 4.759E-M 1234. T.966E- M 6.863E-M

E 1227. 1227. 5.876E- M 5.799E-M 1227. 8.900E-M 8.723E-M :

ESE 991. 991. 1.001E-05 9.729E-M 991. 1.662E-85 1.414E-85 ;

SE 1986. 1006. 1.052E-95 1.022E-03 1906. 1.854E-85 1.782E-05 !

SSE 800. 800. 1.274E-05 1.23 M-05 800. 2.736E-95 2.65M-05 5 M5. MS. 8.388E-M 8.149E-M M5. 1.633E-05 1.586E-85 l tsu 975. 975. 6.163E-M 5.929E-M 975. 1.138E-85 1.195E-95 !

su 1967. 1067. 4.8TFE-M 4.730E M 1967. 8.395E-M 8.154E-M i Umf 1212. 1212. 4.748E-M 4.612E-M 1212. T.570E-M T.353E- M i N 1189. 1989. 5.142E-M 4.995E-M 1189. 8.490E-M 8.246E- M !

leal 1227. 1227. 3.590E-M 3.488E-M 1227. 5.905E- M 5.735E-M !

NW 1128. 1129. 5.205E-M 5.957E-M 1128. 8.806E- M 8.553E-M i uuW 1944. 1M4. 9.40EE- M 9.139E- M 1944. 1.738E-85 1.688E-85 i

Byron site Meteerstegicet Date 1/78 - 12/8T [

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F-15 l l

^

GYRON Revision 1.3 l

.,. Mendi1996 Table F-7 (Continued)

Maxineene ONelle Finite Plume Gamma Deee Factors Based on 1 cui Depth at else Umestricted Ases Soundary for Kr-te i

~

pounufnd Unrestricted Mixed flode(Vent) Rolesse ernsul Levet Reteese '

Streetten Aree Sound Ro61ue V VGAR Redfue a GBAR (metere) (meters) (erodryr)/( d t/sec) (setore) (erodryr)/(utt/see)

N 1875. 1875. 5.729E-06 5.550E-06 1875. 2.499E-06 2.423E-06 NME 10N. 1829. 6.704E-06 6.504E-06 1829. 3.SSOE- M 3.443E 96 NE 1505. 1505. 5.89FE-06 S.651E- M 1585. 5.993E-06 4.959E 86 EEE 1234. 1254. 2.985E-05 2.ODGE-95 1234. 1.415E-95 1.372E 95 t E 122T. 1227. 3.111E-95 3.910E-05 1227. 2.640E-OS 2.560E 05 EsE 991. 991. 8.428E-05 8.175E-05 991. T.903E-85 T.663E 05 st 1906. 1906. T.485E-05 T.259E-95 1006. 4.509E-05 6.309E 95 i sst 800. 800. 1.NIE-M 1.MM-M SOS. 1.36FE-M 1.325E- M !

s MS. 965. 6.35EE-05 C.191E-95 M5. 6.374E-85 6.181E 95 ;

seu 975. 9F5. 4.960E-95 3.953E-05 975. 3.621E-95 3.511E 85 su 196T. 1MT. 2.851E-95 2.FG5E-05 196T. 2.690E-05 2.616E 95 Usu 1212. 1212. 2.98FE-95 2.OESE-95 1212. 1.563E-95 1.516E 95 ;

W 1189. 1189. 2.195E-05 2.MM-95 11W. 8.TF5E-M 8.509E 96 uni 122T. 1227. 1.541E-95 1.495E-95 122T. S.279E-06 0.02EE M i W 11N. 11N. 2.69EE-05 2.61eE-95 11N. 1.614E-05 1.56SE 95 )

INRI 1944. 1944. 6.975E-95 5.EBEE 95 1M4. 4.455E-95 4.32EE-05 j i

tyren site Noteerstestest Date 1/78 - 12/87 i i

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F-16 O O O i 1

., ,evision 1.3 March 1996

., Table F-7 (Continued)

RAaximum Offsite Finite Plume Gesune Dose Factors Bened on 1 cm Depth at the Unnstricted Area Boundary for Xe-131m Deunufnd tweetrfeted Nined Mode (Vent) Reteese greed Levet Reteese Directlen Aree Bound Redfue V VeMt Redfue e eMR

.. (motors) (meters) (aredryr)/(uct/see) (meters) (aradryr)/(utt/sec)

N 1875. 1875. 2.385E 05 1.89FE 95 1875. 9.75FE-05 T.690E-05 NNE 1829. 1829. 2.962E-05 1.65GE-95 1829. 8.424E-05 6.6fl8E-95'

. NE 1585. 1505. 1.951E-05 1.548E-05 1585. 8.80M-95 4.90dE-05 i ENE 1234. 1254. 1.814E-85 1.450E-05 1234. 1.003E-M T.SSOE-95 E 1227. 1227. 2.20$E-05 1.TFUE-85 122T. 1.290E-M 1.9H9E-M ESE 991. 991. 3.255E-85 2.600E-05 991. 1.885E-M 1.4M-M SE 1906. 1986. 3.83M-05 3. M1E-95 1906. 2.T41E-M 2.1:39E- M set 800. SOS. 5.2SFE-05 4.185E-95 000. 4.3OSE- M 3.351E- M S 945. M5. 2.M 1E-05 2.294E-95 M5. 2.140E M 1.6TUE-M ssu 9F5. 9F5. 1.939E-05 1.55FE-05 975. 1.451E-M 1.1?;4E-M su 196T. 1MT. 1.511E-05 1.216E-95 1967. 1.030E-M 8.Or m -05 Usw 1212. 1212. 1.568E-05 1.261E-05 1212. 8.542E-05 6.6ME-05 W 1189. 1189. 2.220E-05 1.760E-05 1189. 1.95dE-M 8.212E-05 :

unt 1227. 1227. 1.534E-05 1.222E-85 1227. T.4E3E-05 5.st e -05 ml 1128. 1128. 2.119E-05 1.604E-95 1128. 9.9ME 05 T.F:4E-05 WNi 1944. 1944. 3.T49E-95 2.966E-95 1944. 1.610E-M 1.2!FE-M i

l syren site noteerstoeleet esta 1/73 - 12/ST l

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F-17

.__-_ __-___-___ - _____ - _ - _ _ _ - - _ _ _ _ - _ _ _ - - - - - - - _ _ ___-___ _ __ ______I

- BYRON

~

Revision 1.3

,, - Mardi 1996

'a Table F-7 (Continued)

Ilexinnun ONella Finite Plume Genune Dome Factors Based on 1 cm Depth at the Unrestricted Ame Boumbery for Xo-133m l

i Dounalrul Unrestricted steed nede(vent) Roteese tround Levet Reteese !

Bfrectlen Aree Sound Redlue V VBAR Redlue S EBfA i

(meters) (meters) taradryr)/(uct/see) (meters) (aradryr)/ tid:1/oes) !

N 1875. 1875. 5.052E-05 4.463E-95 1875. 1.T79E-M 1.53(4-M NME 1829. 1829. 4.421E-05 4.113E-85 1829. 1.541E M 1.33'.E- M !

NE 1985. 1985. 4.42OE-05 3.MdE-95 1985. 1.40fE- M 1.3 Sit- M EWE 1254. 1234. 4.244E-85 3.799E-05 1234. 1.799E M 1.541E-M E 1227. 1227. 5.972E-95 4.53OE 05 1227. 2.29M M 1.9T'E M ESE 991. 991. T.221E-05 6.419E-05 991. 3.291E-M 2.82tt-M !

SE 1906. 1986. 8.369E-95 T.422E 05 1806. 4.735E-M 4.Mit-M i stE 300. 800. 1.988E-M 9.370E-05 800. T.16dE-M 6.98!E-M !

3 MS. M5. 4.295E-85 5.509E-05 945. 3. NEE-M 3.15't-M !

SSW 975. 975. 4.48EE-85 4.911E-85 975. 2.539E-M 2.1 Tit-M i SW 1967. 196T. 3.574E-95 3.203E-05 1967. 1.825E-M 1.56t-M l Muu 1212. 1212. 3.697E-05 3.31M -95 1212. 1.549E-M 1.33ed M i V 1189. 1189. 4.M7E-85 4.21M-85 1189. 1.055E-M 1.61'E-M i WNW 1227. 1227. 3.314E-55 2.937E-95 1227. 1.318E- M 1.132E-M y let 1129. 11N. 4.462E-85 3.95EE-95 11N. 1.731E-M 1.4& A- M :

Nuu 1944. 1944 T.543E-85 6.413E-05 1944. 2.800E-M 2.397E-M !

I t

Byron site Noteoreteeleet Date 1/75 - 12/ST l i

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F-18 ;

O G G !

CYRON % i

. e sevision 1.3 Man:h 1996

, Table F-7 (Continued) !

Maximum ONsite Finite Plume Gamme Deze Factors Besod on 1 cm Depth at the Uniestricted Area Boundary for Xo-133 ;

I t

Dewalnd Unrestricted Rimed nodotwent) Roteese ereund Levet Rotonse f; Direetten Aree sound Redfue V VWut Redlue 8 edAR (meters) (asters) teredtyr)/(utf/see) (meters) (aradryr)/(w:l/see) ;

~

N 1875. 1875. 5.651E 05 5.145E-95 1875. 2.914E-M 1.80dE-M NNE 1829. 1829. 5.158E-05 4.714E-05 1829. 1.74dE-M 1.5ME-M '

NE 1585. 1585. 4.921E-05 4.513E-05 1585. 1.820E- M 1.631E-M ENE 1254. 1254. 4.792E-95 4.320E-95 1234. 2.83OE- M 1.81dE-M .

122T. '

E 1227. 5.410E-85 5.145E-95 1227. 2.582E-M 2.380E-M

EsE 991. 991. T.99dE-05 T.395E-05 991. 3.684E- M 3 281E-M r SE 1906. 1906. 9.261E-95 8.450E-95 1906. 5.28FE-M 4-.79EE-M I set 800. 800. 1.173E- M 1.061E-M 800. T.899E-M 6 981E-M

s M5. MS. 6.95eE-05 4.347E-85 MS. 4.122E- M 3 44SE-M seu 975. 975. 4.M2E-05 4.534E-95 975. 2.940E- M 2.530E-M su 196T. 1967. 3.944E-05 3.62FE-95 1967. 2.054E- M 1 854E- M UsW 1212. 1212. 4.094E-05 3.764E-05 1212. 1.751E-M 1.569E-M i W 1189. 1189. 5.295E-05 4.825E 05 1189. 2.119E-M 1,895E-M last 1227. 122T. 3.679E-05 3.354E-05 122T. 1.481E- M 1.322E- M !

Int 1128. 1128. 4.M5E-05: 4.494E-85 1128. 1.958E- M 1.726E- M lumi 1944. 1944. 8.37dE-95 T.500E-95 1944. 3.130E- M 2.788E-M i Syren 31te Iteteoretesteet Sete 1/78 - 12/87 e

F-19 i

r6YRON Revlolon 1.3 !

March 1996 Table F-7 (Comuneaed) l pgazinnun Offette Finite Plume Genune Does Factoes IBened on 1 cas Depth at 11ee Unrestetsted Asse Boundary for Xe-135sn

- l Dounutnd Unrestrleted Niend lande(vent) esteese tround Levet Release L Directlen Aree geneid Redfue V VBAE tedlue e sear .

(motore) (meters) turedfyr)/(ett/ sos) (meters) teredfyr)/(tC1/sec) !

u 18F5. 18F5. 3.35 M-M 3.25EE-t4 1875. T.5F45- M T.381E-M unt 1829. 1829. 3.191E-M 3.geOE-M 1829. 6.35M-M 6.124E-M i NE 1585. 1505. 3.171E-M 3.961E-M 1585. 4.MM-M 6.40dE-M !

Eut 1254. 1234. 3.275E-M 3.1M-M - 1234. T.919E-M T.653E-M E 122T. M T. 3.FME-M 3.M5E-M 1227. 9.332E-M 9.M3E-M !

EsE 991. 991. 5.722E-M 5.524E-M 991. 1.582E-05 1.44EE-85 i SE 1986. 1806. 4.teuE-M 4.062E-M 1906. 1.SNE-05 1.759E-85 set see. 800. T.139E-M 6.009E-M See. 2.54dE-85 2.45M-85 s MS. MS. 4.850E-M 4.dSEE- M MS. 1.505E-95 1.458E-85 ,

ssW 9F5. 975. 3.539E-M 3.414E-M 975. 1.919E-85 9.81FE- M !

su 1967. It6T. 2.924E-M 2.825E-M 196T. T.3 FEE- M T.111E- M !

WEU 1212. 1212. 3.958E-M 2.952E-M 1212. T.3 N E-M T.129E- M t U 1189. 1189. 3.53eE-M 3.40FE-M 1189. 9.31dE-M 8.9 FEE- M tant 1227. 1227. 2.475E-M 2.389E-M 1227. 4.54M-M 6.30FE-M Ini 1138. 1128. 3.325E-M 3.20gE-M 1128. 8.4 m - M 8.1 M -M mai 1944. 1944. 5.5W-M 5.344E-M 1944. 1.425E-85 1.373E-85 syren site festeerstesteet Date 1/F5 - 12/ST

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i F-20 !

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9-- _- __

CYRON \

~

jewision 1.3 i March 1996 i

- Table F-7 (Continued)

Ileximum Offsite Finite Plume Gemme Dose Factors Based on 1 cm Depth et the Unigstricted Asse Boundary for Xe-135 ,

Deunuttal Unrestricted Nined Mode (Vent) Reteese Src>ud Levet Ret <sese V 'JdAR Redlus 8 ERAR 1 Directlen Aree sound Redlus (meters) (asters) (erodryr)/(dt/sec) (meters) (aradryr)/(Jct /sec)

N 1875. 1875. 2.998E-M 2.8981-M 1875. 8.831E-M 5.532E-M ,

NME 1829. 1829. 2.878E- M 2.785E M 1829. F.673E-M T.41N-M !

RE 1585. 1585. 2.005E-M 2.71M-M 1585. F.977E-M T.787E-M i

ENE 1234. 1234. 2.749E-M 2.658E-M 1234. 8.TFIE-M S.475E-M E 1227. 122T. 3.233E-M 3.126E-M 1227. 1.999E-83 1.961E-83 I Est 991. 991. 4.48tA- M 4.337E- M 991. 1.549E-85 1.496E-83 !

SE 1906. 1906. 5.112E-M 4.M2E-M 1906. 2.178E-83 2.104E-83 '

t SSE 800. 800. 6.MSE-M 5.M3E-M 800. 3.113E-83 3.006E-03 3 M5. MS. 3.878E-M 3.749E-M M5. 1.781E-03 1.643E-03 f Ssu 975. 975. 2.880E-M 2.785E-04 975. 1.190E-83 1.150E-83 l

su is5T. 1MT. 2.337E-04 2.260E-96 1967. 8.696E-94 8.400E-04 1212. F.667E- M T.407E- M Usu 1212. 1212. 2.415E-M 2.335E-M ,

W 1989. 1189. 2.873E- M 2.FF8E- M 1189. 9.144E-M 8.835E-M '

inni 1227. 122T. 2.01N-M 1.M5E-M 122T. 6.344E-M 6.150E-94 inf 11N. 1128. 2.MIE-M 2.553E-M 1128. 8.1752-M F.89dE-04 lumf 1944. 1944. 4.267E M 4.124E-34 1944. 1.313E-GS 1.268E-83 t

Byron site noteerelegical Date 1/78 - 12/ST ,

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F-21

Revisiort 1.3 March 1996 4

Table F-7 (Continued)

RIaximune Offsite Finite Plume Gemme Dose Factors Based on 1 est Depth at the Usuestdcted Area Boundary for Xe-137 D

Dourusind unrestricted Rimed Mode (Vent) Rolesse transed Levet Reteese .

Directlen Aree Sensed Redlue V VBAR Redlue S EBrW (metere) (meters) tared /yr)/(utt/see) (metere) (ared/yr)/ test /see)

N 1875. 1875. 4.485E-05 6.197E-95 1875. 9.597E-05 9.23:'t-95 i NME 1829. 1829. 4.350E-05 4.153E-95 1829. 8.275E-95 3.00ME-95 !

NE 1585. 1585. 6.540E-05 4.348E-95 1505. 9.063E-95 5.T7DE-05 I i ENE 1234. 1254. T. M7E-95 T.362E-05 1234. 1.N 3E M 1.203E-M i E 1227. 122T. f.065E-95 5.TT3E-05 1227. 1.555E-M 1.5tk.E-N ' -

EsE 991. 991. ' 1.509E-M 1.461E-M 991. 2.885E-M 2.T14E-M st 1906. 1906. 1.59dE-M 1.544E- M TOOS. 3.144E-M 3.M:1-M '

ssE SOS. 800. 1.905E-M 1.M3E-M 308. 4.627E-M 4.4Tel-M i s MS. M5. 1.267E-M 1.226E-M M5. 2.775E-M 2.60'E-M ssW 975. 975. 9,229E-05 S.932E-05 975. 1.953E-M 1.87tlE-M !

su 1967. 1967. T.424E-05 T.185E-95 1MT. 1.418E-M 1.3T.1-M usu 1212. 1212. T.355E-05 T.118E-05 1212. 1.309E-M 1.26ti-M i W 1989. 1189. S.987E-05 T.827E-05 -1189. 1.510E- M 1.4#.T-M leaf 1227. 1227. 5.651E-05 5.469E-85 122T. 1.054E-M 1.82' E-M i Inf 1128. 1128. 8.18EE-05 T.M1E 05 11N. 1.535E-M 1.48 (-M i NInf 1944. 1944. 1.454E-M 1.40FE-M 1944. 2.944E-M 2.Mif-M !i Byron site Noteorotegicet Date 1/78 - 12/ST L

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evision 1.3 l March 1996

'<, Tatste F-7 (Continued) !

Maximum Offelte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Un:estricted Area IBoundary for Xe-138 !

Deesmind Unrestricted Nimed Nede(vent) Reteese tround Level Retesse Directlen Area sound Redlus V VBAR Redlus e asMt l l

(astere) (meters) taradryr)/tucl/ sos) (metere) (aradryr)/tus:l/see) [

i I u 1875. 18T5. T.31FE-M T.196E-M 1875. 1.559E-55 1.515E-85 i NNE 18N. 1829. T.MSE-M 6.85dE-M 18N. 1.310E-05 1.2 TIE-85 !

NE 1585. 1585. T.054E-M 6.85eE-M 1585. 1.3T1E-85 1.350E-85 l ENE 1234. 1234. T.35FE-M T.145E-M 1254. 1.654E-85 1.58dE-55 l

E 122T. 122T. 8.489E-M 8.244E M 122T. 1.95dE-85 1.879E 85 i EsE . 991. 991. 1.282E-85 1.24M-03 991. 3.185E-55 3.91N-65 !

sE 1906. 1906. 1.402E-85 1.36EE-85 1906. 3.755E-05 3.644E-85 r set 800. 800. 1.509E-85 1.543E-85 800. 5.212E-55 5.058E-05 l 3 M5. 945. 1.089E-05 1.05EE-55 M5. 3.195E-85 3.01N-85 ;

ssW 975. 975. T.991E-M T.761E-M 975. 2.10FE-55 2.944E-85 t su 106T. 1967. 6.618E-M 6.42FE-M IMT. 1.531E-95 1.48FE-95 usu 1212. 1212. 6.871E-M 6.674E-M 1212. 1.535E-05 1.490E-05 i U 1189. 1189. T.811E-M T.50dE-M 1999. 1.925E-05 1.869E-05 L last 1227. 1227. 5.482E-M 5.324E-M 1227. 1.351E-95 1.311E-03 !

NW 1128. 1128. T.355E- M T.142E- M 1120. 1.756E-05 1.704E-95 !

Inni 1M4. 1944. 1.215E-95 1.10EE-55 1M4. 2.955E-55 2.880E-85 l

[

Byron site Noteorelegiest Date 1/78 - 12/ST 4

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BYRON Revision 1.3 a- March 1996 -

w Talile F-7 (Continued)

Maxineunt ONotte Finito Munse Genume Does Facters Beeed on 1 can Depele at the Unrestricted Aree Boundary for Ar.41 Doomuind Unrestrleted Rimed IInde(Vent) Beteese t'reasul Levet teleeur Direction Aree Beesid Redlus v VRAE Radius e etAE

, testere) (notere) (eradryr)/tesf/see) (meters) (eradryr)/(uC1/sec)

N 1875. 1875. 1.120E-05 1.OME-95 1875. 2.955E-85 2.M2E 55 InE 1829. 1829. 1.855E-95 1.05EE-85 1829. 2.531E-85 2.450E-85

NE 1585. 1585. 1.9T1E-95 1.95N-65 1585. 2.45N-65 2.553E 85 ENE 1254. 1254. 1.089E-85 1.055E-05 1254. 2.945E-85 2.MM-05 *

. E 1227. 122T. 1.244E-05 1.295E-05 122T. 3.409E-85 5.495E 85 Est 991. 991. 1.753E-95 1.697E-85 991. 5.240E-85 5.072E- 5 SE 1986. 1906. 1.975E-05 1.912E-05 1906. T.125E-95 4.t95E-85 ssE 800. 800. 2.290E-E5 2.21eE-85 800. 1.015E-92 9.r2SE-05 s MS. M5. '1.510E-85 1.442E-95 MS. 5.41dE-85 5.43aE-85 i' seu 975. 975. 1.12EE-95 1.ONE-95 975. 3.BB4E-95 3.739E-85 SW 1967. 106T. 9.220E-M 8.953E-M 1967. 2.RIGE-85 2.755E-85 Wsu 1212. 1212. 9.52FE-M 9.IIIE-M 1212. 2.5ME-05 2.511E-85 W 1989. 1189. 1.10SE-05 1.07EE-95 1189. 3.148E E5 3.(47E 05 tenf 1227. 1227. T.765E-M T.517E- M 122T. 2.291E-85 2.151E-95 -

l Inf 1120. 1129. 1.916E-05 9.857E- M 1128. 2.503E-05 2.715E-85 luni 1944. 1M4. 1.4218-E5 1.579E-85 1944. 4.51GE-95 4.!44E-85 syren site Iseteoretesteet Date 1/78 - 12/ST i

I, F-24 O 9 O

1.3 March 1996

Telde F-7a Maximum Offette Finite Phune Gamme Dose Factors Bened on 1 cm Depth at the Restrk:ted Acan Boundary for Kr-43m i

pounwind Restricted Nised Nede(vent) Reteese tressed Levet Retestee ;

Directlen Area Bensid Endlue V VBAR Redlus e GBAR (meters) (meters) tered/yr)/tucl/sec) (meters) (aredtyr)/(ed:l/sec) l n 117. TTT. T.987E-95 6.822E-05 TTT. 3.STN M 2.924E-M ;

NME $38. 538. 1.059E- M T.904E-95 538. 5.645E-M 4.272E-M )

NE 528. 525. 8.2T1E-85 6.23dE-05 528. 4.960E-M 3.740E-M ENE 474. 474. 6.500E-05 4.901E 95 474. 4.405E-M 3.473E-M ,

E 448, 448. 8.031E-85 6.95dE-95 448. 5.067E- M 4.424E-M ,

Est 488. 400. S.955E-05 6.737E-85 400. 6.859E-M 4.553E-M l sE 4?T. 427. 1.280E-M 9.453E-95 427. 1.044E-03 7.879E-M t ssE 419. 419. 1.377E-W4 1.550E- M 410. 1.218E-85 9.125E- M '

l s 295. 295. 1.444E-M 1.19dE-M 295. 1.295E-85 9,76M-M ssu 299. 299. 9.895E-85 T.441E-05 299. 9.12EE-M 4 AS5E-M su 451. 451. 4.721E-85 3.540E-85 451. 4.eOIE-M 3.017E- M !'

. Usu 306. 305. T.311E-85 5.513E-85 386. 5.291E- M 3.905E- M W 379. 379. 1.136E-M S.546E-85 379. 4.47dE-M 4.SSIE-M i uuW 305. 385. T.990E-95 4.831E-85 3E5. 4.444E-M 3.501E-M j NW 445. 445. 8.000E-95 6.090E-85 445. 4.352E-M 3.281E-M !

uuW 458. 658. T.540E-05 5.491E-95 458. 3.4SdE-M 2.429E-M i '

syren site Noteeretesical pote 1/78 - 12/87 i P

1 i

Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. ,

5

%,. ;..r distance from midpoint totween geneous emuent reisese points.

i F-25 !

r

BYRON

~

Revlolon 1.3 March 1996 Table F-7a (Continued)

Maxineuse ONelle Finite Phune Genune Dose Factors Based on 1 cui Depth at the Reedricted Area Boundary for Kr-88xa ;

De m wind Restricted Mixed leade(vent) Reteese treed Levet meteese etractlen Aree Be n d Redlue V VBAR Redlue 8 sear

r teeters) (metere) (are# yr)/(uct/see) (meters) tere #yr)/tect/see) j 2.915!-85 1.929E-85 u FFT. TTT. 5.990E-M 5.755E-M TTT.

NME 538. 538. 8.304E-M T.9eOE-M 538. 2.732!-s5 2.614E-85 NE 528. 528. 6.981E- M 6.712E-M 528. 2.441!-85 2.355E-85 . ,

ENE 474. 474. 5.790E-M 5.56pE- M 474. 2.225!-85 2.129E-05 !

E 468. 448. 4.M 1E-M 6.57N -M 448. 2.791!-95 2.469E-05 !

ESE 480. 480. T.3TFE-M T.992E-M 480. 2.899! 85 2.767E-55 i SE 427. 427. 9.007E-M 9.425E-M 427. 4.7851-85 4.569E-85 ssE 419. 410. 9.459E-M 9.000E-M 410. 5.325!-05 5.004E-05 ;

3 295. 295. 1.04M -05 1.005E-85 295. 5.472!-85 5.22GE-05 ;

seu 299. 299. T.854E-M T.549E- M 299. 3.979E-05 3.001E-85 ,

su 451. 451. 4.441E-M 4.273E-M 451. 1.962!-05 1.878E-03 usu 306. 386. 4.265E-M 6.025E-M 386. 2.485!-05 2.378E !

W 379. 379. T.731E-M T.421E-M 379. 2.912!-85 2.784E-05 i leaf 305. 385. 5.485E-M 5.384E-M 305. 2.058!-85 1.96 N-05 l Inf 445. 445. 5.54dE-M 5.344E-M 445. 1.975!-05 1.008E-85 mal 458. 658. 5.350E-M 5.118E-M d58. 1.750!-85 1.675E-05 i

l syren site stateerstesteel Date 1/75 - 12/87 1 . ;

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ __ _ __ ___ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _____i

YRON t (Q 1.3 1996 i

Table F-7a (Continued)

Maximum Offsite Finite Phane Gamma Dose Facters Based on 1 cm Depth at the Restricted Area Boundary for Kr-85 z

Doesmind Restricted Nimed Nede(Vent) Reteese tround Levet Retenee [

strectlen Area Seemd Redlue V VBAE tedlue e se#A 1 (meters) (metere) (ered/yr)/(uct/sec) , (metere) (aredfyr)/(uct/r.ec)

N 7TT. 7TT. 6.81M-06 6.593E-M TTT. 2.20M-05 2.138.E-05 ,

NME 538. 538. 9.56M- M 9.252E-06 538. 2.9T1E-05 2.STIE-05 NE 528. 528. 8.10 M-06 7.M OE-06 528. 2.65eE-05 2.57tE-05 EF 474. 474. 6.7T1E-06 6.54M-M 474. 2.41K-05 2.331E-05 i L 468. 448. 7.994E-06 7.730E-06 440. 3.044E-05 2.90.E-05 .

EsE 480. 480. S.548E-06 S.264E- M 488. 3.14M-05 3.MIE-05 I sE 427. 427. 1.133E-05 1.095E-OS 42T. 5.222E-05 5.05tE-05 ,

SSE 410. 410. 1.090E-05 1.054E-05 410. 5.859E-05 5.64;1-05 s 295. 295. 1.28M-05 1.140E 05 295. 5.918E-05 5.7EE-05 seu 299. 299. 9.1TFE-06 8.874E-06 299. 4.315E-05 4.171E-05 su 451. 451. 5.220E-06 5.040E-06 451. 2.153E-05 2.00;'E-05

UsW 386. 306. 7.292E-06 7.051E-06 386. 2.687E-05 2.59tlE-05 i U 379. 3M. S.828E-06 S.53 M-06 379. 3.134E-05 3.031E-05 UNW 385. 335. 4.27dE-06 6.069E-06 305. 2.212E-05 2.13'8E-05 NW 445. 445. 6.362E-06 4.15 M-06 445. 2.130E-05 2.06tE 05 NNW 458. 458. 4.044E-06 5.84M-06 458. 1.90FE-OS 1.048,E-05 !

Byron site Noteorelegice( Date 1/78 - 12/87 i

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

l

- BYRON Revlakm 1.3 f March 1996

Table F-7a (Continued) :

IAanimune ONsite Finite Pluene Gemme Dose Factors Beeed on 1 con Depth at the Re.stricted Asse Boundary for Kr-47 seeswleul teatricted aimed Mode (Vent) Reteese treesid Lewit Reteese 9irestIen Area Seasid Redlue V VBAE Redlue 11 SAR (asters) (aeters) (aradryr)itutt/see) (seters) tared'yr)/(egf/see) l N TTT. TTT. 2.90EE-93 1.944E-85 TTT. 5.M:1-E5 5.MSE-05 NEE 538. 558. 2.M9E-85 2.MM-05 $50. 8.12 TIE-85 T.eME-85 :

NE 528. 528. 2.424E-05 2.354E-85 528. 7.23 M-85 T.82 M-85 ,

EEE 474. 474. 2.M5E-05 1.984E-85 474. 6.61:1E-85 6.421E-OS i 468. 2.396E-85 2.32M-95 460. 8.19E-85 T.959E-85 ;

E 448.

ESE 400. 400. 2.5 ME-95 2.501E-85 480. 5.56'E-05 8.314E-85 4 SE 427. 427. 3.395E-85 3.295E-85 427. 1.3FM-02 1.353E-82 .

SSE 410. 410. 3.199E-85 3.09M-05 410. 1.53'E-82 1.48dE-02 s 295. 295. 3.453E-85 3.547E-85 295. 1.62M-82 1.575E-82 SSW 299. 299. 2.759E-05 2.799E-85 299. 1.174E-82 1.140E-02 l 451. 5.79 E-85 5.543E-05 i su 451. 451. 1.5SM-85 1.541E-85 usu 386. 386. 2.253E-85 2.14 E-85 306. T.441E-85 T.227E-85 u 379. 379. 2.457E-05 2.500E-95 379. 0.791E-05 S.534E-05 W 305. 385. 1.894E-85 1.859E-85 305. 4.22M-85 6.04M 85 It2 445. 445. 1.907E-85 1.852E-05 445. 5.91M 85 5.M7E-95 l NEW GSS. 658. 1.753E-05 1.731E-85 450. 5.19 5-85 5.961E-95 erren site IIsteorotesteet Date 1/75 - 12/ST l

F-28 9 . _ - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ . - . _ _ .

9 - - - _ - _ - _ _

9

1.3 March 1996

Table F-7a (Continued) blazinann Offsite Finite Plume Genune Does Factors Beeed on 1 can Depth at the Restricted Area Boundary for Kr-88 Dounutrul Restricted Mixed Nede(Vent) Reteese Groumi Levet Reteese Direction Aree Sound Radius V VSAE Redlue 8 esAE (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(scl/seel N 7TT. 777. 4.8T3E-03 4.737E-85 TTT. 1.449E-02 1.407E-SE NEE 530. 538. 4.M9E-83 6.756E 83 538. 1.964E-02 1.907E-82

, NE 528. 525. 5.936E-85 5.7T1E-85 528. 1.755E-82 1.704E-82 .

ENE 474. 474. 5.009E-05 4.879E-83 4T4. 1.599E-92 1.553E-92 E 468. 468. 5.OO9E-85 5.724E-85 468. 1.99EE-02 1.MOE-GE EsE 408. 480. 6.284E-03 6.199E-95 488. 2.87EE-02 2.916E-92 SE 427. 427.

8.2SEE-05 S.050E-05 427. 3.413E-02 2;.313E-92 ssE 419. 410. 7.85E-85 T.618E-83 410. 3.785E-02 5.674E-St 295. m. s.esa-as s.634E-o3 295. 3.917E-02 3.e02E-et ssu 299. 299. 6.829E 85 6.639E-93 299. 2.846E-02 2.763E-92 SW 451. 451. 3.896E-85 3.78BE-t3 451. 1.4032-02 1.363E-02 usu 386. 386. 5.427E-85 5.276E-85 306. 1.787E-02 1.735E-92 '

W 379. 379. 6.431E-85 6.251E-23 379. 2.997E 02 2.036E-02 WNW 385. 385. 4.504E-85 4.455E-03 '385. 1.4S M-02 1.440E-02 NW 445. 445. 4.622E-55 4.492E-03 445. 1.419E-01 1.37EE-02 muW 658. 658. 4.324E-85 4.2ESE-83 658. 1.25 E-02 1.222E-02 syren site noteoreteeleet esta 1/78 - 12/87 t

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. Reviolon 1.3 March 1996

'a Table F-7a (Continued)

Maxineum ONelle Finite Plunie Gemene Does Factors Based on 1 con Depth at the Restricted Area Boundary for Kr-89 Seemuleuf Beettleted steed Itode(Vent) Reteese Grossed Level Release Directless Aree teamd Redlue V VBAR Redlue G GBAR (metere) (meters) (aradryr)/(utf/see) (metwo) (erodryr)/(esf/ses)

N FTT. FFT. 2.255E-ES 2.1F N-95 7/T. 4.485E-85 4.535E-85 NEE $38. 538. 3.MM-85 3.641E4 538. 7. NEE-85 7.720E-85 NE 528. 538. 3.005E-85 3.et1E-85 528. 4.42dE-05 6.43dE-85 EEE 4M. 4M. 2.445E-85 2.560E-85 4M. 6.153E-05 5.9 FEE-ES E 440. 448. 3.10EE-85 3.814E 85 460. T.42M-95 T.213E-85 Est 480. 488. 3.404E-05 3.300E-95 480. 7.840E-05 T.414E 4 SE ,427. 427. 4.4edE-85 4.355-95 427. 1.1NE-82 1.142E-52 set 410. 410. 3.8pgE-95 3.7 ME-85 Alt. 1.141E-82 1.100E-SE

's 295. 295. 5.51N -85 5.340E-05 295. 1.M3E-82 1.405E-82 Stil 299. 299. 4.13M -05 4.91M -85 299. 1.248E-02 1.21M-82 su 451. 451. 2.134E-85 2.875E-ES 451. 5.19FE-85 5.MM-85 usu 306. 386. 3.353E-95 3.235 -85 386. S.487E-85 8.243E-85 y 34. 3M. 3.853E 05 3.722E-45 3M. 1.85M-82 1.00M-St unt 305. 3E5. 2.751E-85 2.67M-85 305. 7.433E-83 T.21W-85 gif 445. 445. 2.d51E-85 2.57M-85 445. 4.50dE-83 4.319E-85 Igni 458. 458. 2.15 N-5 2.09FE 4 e58.. 4.73E -43 4.4EEE-85 syren site festeereteeleet Date 1/75 - 12/ST l -

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1.3 Mach 1996 Table F-7a (ConHnued)

Manknum Offsite FhWe P'izuse Genune Dose Factors Based on 1 cm Depen at the Reshicted Aree Boundary for Mr-te Deunwind Restricted Mixed Itode(Vent) Reteese treemd Levet Reteese Directlen Aree Bound Redlue V VBAR Radim 8 -sett (meters) Datore) tared /yr)/(tCl/sec) (meters) taradryr)/(utt/see) ,

N TTT. TTT. 2.929E-M 2.553E-M TTT. 2.MFE-M 2.695E-M mut 538. 530. 9.214E-M 8.M8E-M 530. 1.979t.-95 1.035E-85 N 528. 528. 6.927E-M 6.T20E-M 520. 8.M9E-M T.805E-M ENE 474. 474. 6.455E-M 6.262E-M 474. 5.222E-M T.971E-M -

E 468. 468. 8.495E-M 4.239E-M 468. 1.189E-85 1.155E-05 ESE 480. 480. 9.079E M S.887E-M 488. 1.225E 05 1.18 M-85 "I

- 427. 427. 1.26AE-93 1.230E-85 427. 1.5555-83 1.79BE-85 sst 410. 419. 1.055E-85 1.OM E-95 419. 1.699E-S5 1.M IE-85 s 295. 295. 2.202E 85 2.13dE-85 295. 4.311E-85 4.179E-05 ssu 299. 299. 1.624E-05 1.575E-55 299. 3.114E-55 3.919E-05 su 451. 451. 5.560E-M 5.395E-M 451. 8.797E-M S.441E- M usu 306. 306. 1.053E-85 1.M 1E-85 386. 1.791E-85 1.M 9E-85 u 379. 379. 1.999E-85 1.06dE-05 3M. 1.410E-55 1.561E-85 unu 305. 385. 8.130E-M T.894E-M 385. 1.195E-05 1.158E-85 AW -

445. 445. 6.799E-M 6.585E-M 445. 9.880E-M S.082E-M uuW - 650. 458. 3.357E-M 3.23dE- M 458. 3.795E- M 3.590E- M tyren site noteorelegicet Date 1/78 - 12/ST

. . O $

7 F-31

BYRON Revision 1.3 March 1998

'a Table F-Ta (Condneed)

Maulmann OWelle Finite Phune Gemene Deee Facters Based on 1 ens Depdi at the Roetricted Area Boundary for Xe-131m seemine teettleted utsed nede(vent) meteese tree d Levet meteese Directlen Aree Dee d Redius V VBAR Redfue S ERAR

. (asters) (aeters) (aradryr)/tuCIIsoe) (asters) taredryrH (utt/see) u 777. 7T7. 7.405E-05 5.9WE-85 77T. 3.SSFE-M 2.795E-M NME 538. 530. 1.01M-M 8.00M-85 538. 5.144E-04 4.000E-M ut 528. 528. 8.079E-05 6.401E-05 528. 4.534E-04 3.530E- M EuE 474. 4M. 6.397E-85 5.981E-85 474. 4.18eE-M 3.249E-M E 448. 448. 7.M0E-95 6.21M-85 448. 5.37EE-M 4.177E- M Est 480. 400. S.M 1E-85 6.M 2E-85 480. 5.499E-04 4.2FIE- M SE 427. 427. 1.224E-M 9.443E-85 427. 9.505E-04 7.43dE- M SSE 419. 410. 1.314E-M 1.834E-M 410. 1.120E-83 S.677E-M S 295. 295. 1.379E-M 1.000E- M 295. 1.157E-83 8.957E-M SW 299. 299. 9.485E-05 7.499E-05 299. 8.215E-M 6.344E- M W 451. 451. 4.71M-85 3.751E-95 451. 3.720E-94 2.097E- M Wau 306. 306. 7.M IE-95 5.500E-85 3% 4.M1E M 3.4SEE-M V 379. 379. 1.953E-94 S.27EE-85 3M. 5.723E-M 4.441E-M uuW 385. 385. 7.411E 95 5.829E-95 3E- 4.OBEE-bl 3.left M ml 445. 445. 7.532E-05 5.923E-05 4(.5. 3.87EE M 3.OO9E-M Muu 458. 658. 7.gsft-85 5.500E-85 450. * .187E- M 2.400E- M Byron Site noteerstesteet Dete 1/78 - 12/57 e

i

.h8 F-32

1.3 Mitch 1996 Table F-7a (Continued)

Mentnuun Offelte Finite Plume Gamme Dose Fasters Based on 1 cm Depth at the Restricted Ame Boundary for Xo-133m Deemuirud Restricted nimed nede(Vent) Reteese troerui Levet Reteese Directlen Aree Beamd Redless V VSAR Redius 8 13AR (metere) (meters) (eradryr)/(uct/sec) (metere) tured/yr)/(uct/see)

N TTT. 7TT. 1.485E-M 1.2ME- M 777. 4.051E- M 5.152E-M NME 538. 5M. 2.01 M-M 1.764E- M 538. 8.473E-M 7.182E-M NE 528. 528. 1.65 M -M 1.45 M-M 528. 7.500E- M 6.:ITIE-M ENE 474. 474. 1.340E-M 1.182E-M 474. 6.OO9E-M 5.%8E-M E 448. 448. 1.612E-M 1.418E- M 448. 8.750E-M 7.438E-M ESE 488. 480. 1.75M-M 1.541E-M 4C3. 9.024E-M 7.444E- M SE 427. 427. 2.410E-M 2.195E- M 427. 1.544E-U 1.50M-05 stE 410, 410. 2.444E-M 2.134E-M 410. 1.774E-53 1.l93E-05 3 295. 295. 2.641E-M 2.290E-M 295. 1.822E-03 1.331E-03 seu 299. 299. 1.897E-M 1.662E- M 299. 1.306E-03 1.100E-85 W 451. 451. 1.0014 M s.916E-95 451. 6.134E-M 5.19pE- M usu 306. 306. 1.459E-M 1.204E-M 306. 7.755E M 6.545E- M W 3M. 379. 1.985E M 1.722E-M 379. 9.244E M 7. ION-M uni 385. 385. 1.402E M 1.21M-M 305. 6.573E-M 5.544E-M .

W 445. 445. 1.425E M 1.23M-M 445. 6.279E-M 5.296E-M

! NNW 450. 450. 1.353E-M 1.17EE-M 458. 5.321E-M 4.522E-M i

pyren site noteorelegicet Date 1/78 - 12/87 i

i 9

F-33 :

. DYRON Revision 1.3 March 1996 Table F-7a (Condnued)

Maxinnun Offsite Finite Phnne Gennna Dose Factors Based on 1 con Depth at the Restricted Area Boundary for Xo-133 Bounwirul Bestricted Nixed Hede(Vent) Beteese Oromd Level Reteese Birectlen Aree Bond Radius V VMR Redlue 8 88AR (meters) (meters) (aradryr)/tutt/sec) (meters) (greWyr)/(Wl/sec) 8 TTT. TTT. 1.648E-M 1.47BE-M TTT. 4.f91E-M 5.9NE-M NNE 538. 538. 2.288E-M 1.991E-M 538. 9.2T3E M 8.1FIE-M NE 528. 528. 1.88FE-M 1.43dE-M 528. 3.238E-M 7.2T1E-M

~ ENE 474. 474. 1.459E- M 1.324E-M 474. T.544E-M 6.453E- M E 448. 448. 1.752E-M 1.58dE-M 468. 9.5940-M 8.448E-M EsE 488. 488. 1.915E-M 1.T32E M 488 9.866E-M 8.493E M SE 427. 427. 2.415E- M 2.357E M 427. 1.674E.-83 1.478E-83 stE 418. .418. 2.657E-M 2.379E-M 418. 1.989E 83 1.671E-83 s 295. 295. 2.831E-M 2.541E-M 295. 1.954E -83 1.788E-83 ssU 299. 299. 2.834E-M 1.834E- M 299. 1.48?t-83 1.233E-83 su 451. 451. 1.897E-M 9.97M -85 451. 4.715E M 5.928E-M usu 386. 386. 1.584E-M 1.435E-M 386. 3.466E-M 7.455E-M U 3M. 3F9. 2.144E-M 1.922E-M 379. 1.883E 33 8.812E-M Wuu 305. 385. 1.512E-M 1.35M-M 385. 7.114E M 6.24eE-M

' NW 445. 445. 1.541E-M 1.382E-M 445. 6.885E-M 5.TFTE M uuW d58. 658. 1.48dE-M 1.335E-M 458 5.868E-M 5.18EE-M i

Syren sito Noteerste8 feet Beta 1/78 - 12/8T i

I 4*

e F-34 9 - -- -- -

9- - -

1.3 March 1996 l

Taide F-7a (Continued) !

Maxinnun Offetto Finite Plume Gamme Does Factors Based on 1 cm Depth at the Restricted Ama Boundary for Xe-135m l

h Dounwind Reestictet Mixed Nede(Vent) Reteese Grourul Level Release Directlen Aree Bound Redlue V VSAR Redfue S eBAR

(meters) (meters) (aradryr)/(w:l/sec) (meters) (aradryr)/(uct/sec)

W TTT. TTT. 1.114E-03 1.9T4E 93 777. 3.179E-93 3.0 4E-83 NME 533. 538. 1.404E-53 1.540E-83 538. 4.528E-E 4.354-03 ;

NE 5?S. 528. 1.341E-83 1.294E-83 528. 3.M 3E-M 3.817E-85 .

l 3.455E-E 3.51M 43 !

[

ENE 474. 4M. 1.127E-83 1.OSM-53 474.

E 448. 448. 1.31M-83 1. N7E-05 448. 4.309E-M 4.220F-83 I

Est 400. 480. 1.44 M-83 1.394E-05 400 4.4SEE-M 4.50BE-93 ,

I SE 427. 42T. 1.901E-83 1.533E-93 427. 7.254E-g! 6.fe4E-83

! ,419. 419. 1.722E-03 1.M1E-85 410. 7.557E-8! 7.273E-53 ssE 5 295. 295. 2.194E-93 2.829E-03 295. 9.119E-E! 8.775E-83 i

ssp 299. 299. 1.56pE-03 1.514E-83 299. 6.478E-S! 6.235E-83 '

f 8.7dSE-M S.455E-M 451. 2.948E-91 2.839E-03 su 451. 451.

usu 306. 386. 1.2ept-83 1.244E-93 306. 4.397E-E! 4.147E-03 !

U 379. 379. 1.553E-93 1.490E-93 379. 5.N7E-E!. 5.85eE-83 '

i tenf 305. 305. 1.197E-83 1.M7E-83 305. 3.752E-8".3.611E-83 '

WW 445. 445. 1.103E-83 1.064E-53 445. 3.444E-OS 3.317E-93 uuW 658. 455. 1.013E-OS 9.779E-M 450. 2.066E-W!! 2.750E-83 i

j syren site diteerelegicet Date 1/78 - 12/87 ;

1 e

1 i

t i

l F-35 l

,: \

GYRON l Revision 1.3 l Menh 1906 !

=

Table F-7a (Continued)

Maximum Offelte Finite Plume Genune Does Factors Bened on 1 cm Depth et the Restricted Asse Boundary for Xo-135 j i

l pouresind seatricted Rised node (Vent) Reteese creasul Levet te(esee Strectlen Aree teamd Redlue V VGAR Redlus 1 GBAR !

(astere) (asters) (aredfyr)/(utt/see) (meters) taradryr)/(est/see) , j u TTT. TTT. 8.14dE M 7.SF3E-M TTT. 2.T15E-03 2.625-W ENE 538. 538. 1.131E 83 1.W 3E-03 530. 3. M M-83 3.535E-03 i NE 528. 528. 9.534E-M 9.215E-M 520. 3.2TM-93 3.162E-53 ,

EWE 4M. 4M. T.91M-M 7.d54E-M 4M. 2.98 M- M 2.879E-83 ,

E 068. 460. 9.35GE-M 9.858E-M 460. 3.M5E-83 3.61dE-83 >

ESE 480. 400. 1.000E-83 9.T23E-M 480. 3.SF7E-83 3.743E-83 I

SE 427. - 42T. 1.335E-93 1.290E-05 42T. 6.41 X-6 6.18EE-83 35E 4ta. 419. 1.200E-C1 1.243E-05 410. 7.14tE-83 6.Sp2E- M :

5 295. 295. 1.8298 S$ 1.373E-03 295. 7.2SlE-93 7. NEE-93 SSW 299. 299. 1JJ79E-83 1.935E-83 299. 5.3S M-E3 5.125E-83 su 451. 451. 6.981E- M 5.87EE-M 451. 2.MIE-83 2.55EE-83 !

' Weg 386. 306. S.542E-M 8.25M-M 306. 3.319E-83 3.235E-e3 -

,- U -379. 379. 1.M M-95 1.811E-83 379. 3.877E-83 3.M2E-B l Val 355. 305. T.42EE-M 7.17EE-M 305. 2.737E-93 2.M2E-fti I

WW 445. 445. 7.543E-M T 7-M 445. 2.631E-83 2.54EE-93 .

unu d58. 658. 7.23OE-M 6.ErJ-M WS. 2.351E 85 2.27EE-85

! Byron site noteore(egfeet Date 1/78 - 12/ST ;

i i . . . . ,

i -

i

}

1

- i F-38 !

O O O ,

t

?-

BYRON

- Reviolon 1.3 March 1996

. Table F-7a (Contimsed)

Maximum Offsite Finite Plume Gamme Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xo-137 t

I i

Dounwind aestricted Rised stedo(vent) Retenee crewul Levet Referee V VSAR Redlus e GBAR

strection Aree Bound Redlue tuotere) tenters) tared /yr)/(uct/see) (meters) tared /yr)/(w f/see) ,

a m m. 3.3=E M 3.nu-M m. 7.6 n-M 7.37m-M

,,, 5. . Sm. 5.n u-M 5.22M-M sm. i.n=-e3i ==-a t NE Sas. SN. 4.433E M 4.50E-M SN. 1.850E-93 1.016E-85 l ENE 474. 474. 3.764E M 3.643E-M 474. 9.72W-M 9.413E M E 468. 440. 4.41 M-M 4.275E- M 468. 1.168E-93 1.130E-95 .

400. 1.n M-83 1.1 M -03 '

EsE 488. 400. 4.060E M 4.NIE-M st 427. 427. 4.397E- M 6.190E- M 427. 1.056E-83 1.79dE-83 ;

sst 419. 410. 5.573E-M 5.393E-M 410. 1.81M -83 1.75M-03 ;

5 295. N5. 7.6ME-M 7.45EE-M 295. 2.671E-03 2.584E-03 .

ssu 299. 299. 5.740E-M 5.55 M 84 299. 1.901E-83 1.e40E-a3 ;

su 451. 451. 3.91M M 2.918E-M 451. 8.062E M 7.801E-M i usu 306. 386. 4.678E-04 4.52FE- M 306. 1.303E-83 1.26 M-03 y 3M. 379. 5.469E-M 5. NEE-94 379. 1.602E-83 1.55GE-03 yuu 385. 305. 3.92eE.M 3.793E-M 305. 1.148E-03 1.11 M-83 l pu 445. 445. 3.007E- M 3.604E-M 445. 1.012E-93 9.792E-M ;

ung 658. St. 3.1M E-M 3.gpgE- M 658. 7.56SE-M 7.322E-M Byron site P h oeleet Date 1/78 - 12/87 i

y e $

~

GYRON Revision 1.3 March 1996

~*

Table F-7s (Continued) !

Maatnuun Offsits Finite Plume Genune Dose Factors Bened on 1 sen Depth at the Reistricted Area Boundary for Xo-138 l

1 poumsind Restricted Rised Nede(Vent) Reteese Greed Levet toteese Streetlen Aree Bessid Redites V VSAR Redlue 8 MAR (meters) (asters) (are#yr)/(uct/see) (asters) (are W yr)/(igl/see) .

[

E TTT. 777. 2.444E-85 2.375E-85 TTF. 4.5FM-55 6.355E-85 ;

NNE 538. 530. 3.545E-05 3.442E-85 538. 9.48 M-35 9.129E- M i NE 528. 523. 3.004E 85 2.91 M- H 528. 8.251E-85 T.900E-85 ;

4M. 474. T.585E 85 T.361E-85 ENE 474. 2.542E-05 2.449E-05 E 448. 448. 2.95GE 85 2.864E-05 448. 9.espt 85 S.83OE-95 .

ESE 400. 480. 3.242E 85 3.14M-85 480. 9.7EEE-85 9.421E-85 i su 427. 427. 4.245E-e5 4.122E-85 427. 1.49M-BE 1.453E-SE !

410. 1.552E-SE 1.500E-92 ;

SSE 418. 410. 3.820E-05 3.799E-85 3 295. 295. 4.720E-55 4.585E-05 295. 1. OBOE-82 1.853E-SE seu 299. 299. 3.54EE-85 3.445E-85 299. 1.341E 02 1.381E-SE l SU 451. 451. 1.9f9E-85 1.953E-85 451. 6.100E-85 5.93OE-85 i ved 386. 306. 2.911E-85 2.StM-03 306. 8.964E 85 8.499E-85 W 3M. 3M. 3.444E 85 3.344E-05 379. 1.09EE-92 1.98SE-82

. tenf 305. 305. 2.441E-95 2.30fE-85 305. 7.014E-ES T.5EIE-GS nu 445. 445. 2.444E-85 2.375E-55 445. 7.144E 85 4.954E-85 !

lunt 488. 458. 2.234E-88 2.199E-85 658. 5.954E 85 5.78BE-E5 1 Syren site noteersteeleet Date 1/75 - 12/SF >

I f i

i i t

l i

e i

.- nc '

l 1

O 9" O i

i

! ~

O l BYRON i Revision 1.3 L Mefth 1996 1 Table F-7s (Continued) l Maninnnn OWsite Finite Phnne Gamme Dese Factort Based on 1 cm Depth at the Restricted Asse Boundary for Ar.41 !

-i i pewnsind Restricted Nimed Nede(Vent) Reteese Gretsid Levet Release !

Directlen Aree Bound Redlue V VBAE Redlue a WA

(seters) (est3rs) taredryr)/(utf/sec) (meters) teradryr)((utf/sec) ,

777. 9.43EE-01 9.13dE-85 :

N 7tT. 77T. 3.11 M-85 3.013E-85 '

NME 538. 538. 4.41dE-95 4.275E-05 538. 1.2SEE-ti 1.244E-et WE 528. 528. 3.75M -05 3.435E-55 528. 1.14M 03: 1.110E-02 i

). ENE 474. 474. 3.140E-85 3.959E-05 474. 1.04M-ti: 1.01M-st !

E 448. 448. 3.711E-55 3.592E-95 448. 1.304E-E!1.382E-SE i Est 400. 480. 3.982E-05 3.5 M-95 480. 1.350E-E! 1.314E-02 ,

f

> SE 427. 427. 5.25M-85 5.000E-05 427. 2.224E-E! 2.152E-SE asE 418. 410. 4.9F3E-85 4.814E-85 419. 2.45M-E! 2.379E-SE i s 295. 295. 5.64 M-85 5.444E-85 295. 2.571E E! 2.4ept-st ;

I seu 299. 299. 4.300E-85 4.14 N -OS 299. 1.80$E-0?. 1.805E-et su 451. 451. 2.45GE-85 2.371E-85 451. 9.118E-El S.020E-05 usu 306. 386. 3.43 M 85 3.337E-85 386. 1.174E-El 1.13M-St W 379. 379. 4.100E-85 3.9 FEE 85 379. 1.382E-S! 1.335E-SE i 4 tant 305. 385. 2.926E-05 2.EI3E-85 305. 9.7EEE-El 9.475E-85 Inf 445. 445. 2.952E-85 3.5 M -55 445. 9.334E-El 9.55dE-05

Inni 458. 450. 2.70pE-85 2.481E-55 650. 8.224E-El T.961E-05 syren Site Meteerstegicat Date 1/75 - 17/ST t

t

. i 1

^*

__n-..--

'i l

OYRON !

Revision 1.3 i March 1996 i

Supplesnental Tame A i

Mined Mode JeInt Frequency Distribution Table 8ennnuwtes j i

200 Foot Elevallon Dets Summary 7etste of Percent by Direetten eruf Ctese I Clase N 9edE NE ENE E ESE SE SSE 5 SSW SW WSW W tSAf NW peaf 70tet r

t A .353 .294 .339 .346 .331 .179 .178 .483 .391 .333 .390 .3W .389 .249 .338 .304 3.799 i 5 .158 .133 .933 .134 .088 .074 .089 .307 .158 .303 .174 .34J .939 .138 .870 .181 3.179 c .217 .nsa . eS3 .99o .tss .oes .138 .972 .s3s .378 . set .973 .223 .3s3 .313 .333 3.as7 !

D 3.392 1.789 1.858 3.2o. f. Set 1.o83 1.130 1.945 3.343 3.433 3.285 1.833 3.399 3.849 3.398 3.438 33.578 ;

E 1.o83 .909 .837 1.o19 f.303 .99t t.12. 1.408 3.357 3.475 3.038 f.599 1.001 f.728 1.908 9.383 23.437 l F .380 .320 .308 .297 .443 .499 .581 .557 1.015 1.088 .583 .450 .436 .518 .835 .481 S. SOS r S .2IS .141 .134 .I13 .feo .199 .399 .323 .3IS .342 .333 .241 .139 .ISS .1st .188 3.489 fotal 4.539 3.853 3.494 4.958 4.040 3.983 3.474 4.493 S.595 7. 908 S.045 4.873 5.148 5.710 S.3Go 4.9e8 77.395 l

Su===ary 7 state of Percent by Direotten and Speed Speed N DedE IIE ENE E Est St SSE S SSW SW UStr W teef Def ISIN 7etet

.45 .t:00 .031 .000 . coo .cos .0o0 . Coo .000 .000 .089 .014 .005 .00. .co. .018 .097 .14 1.08 .049 .040 .037 .020 .034 .OSS .Ott .015 .089 .040 .ON .OSS .041 .000 .057 .037 .59.4 3.oS .333 .179 .308 .336 .174 .148 .157 .148 .177 .300 .394 .198 .345 .310 .347 .198 3.330 3.oS .448 .380 .438 .487 .404 .300 .335 .377 .396 .464 .498 .438 .431 .488 .907 .487 S.813 4.oS .612 .381 .478

493

. .435 .338 .379 .408 .488 .584 .SGS .578 .570 .593 .543 .593 S.430 5.oS .772 .838 .837 .591 .475 .373 .400 .497 .Sto .749 .893 .730 .795 .879 .978 .781 10.998 S.oS .793 .SSS .374 .848 .543 .391 .473 .533 .799 .978 1.000 .928 .SSS .997 9.384 .994 13.350 8l.05 1.174 .993 .775 1.037 1.208 .794 .989 1.357 9.988 3.399 f.783 f.399 9.479 1.908 f.700 1.403 31.7o0 10.00 .431 .293 .377 .999 .538 .485 .SSS .933 1.573 1.493 .774 .479 .S48 .894 .720 .448 91.350 93.oS .070 .048 . CSS .07s . cts .30< .oe8 .338 .379 .39: .148 .ots .133 .143 .137 .oSS 3.138 .

IS.co .co .o00 .coe .000 .00o .000 .coe . coo .coe . coo n .c. .co.n .O.o

..o . coo.

. . . . .c.on .co.o

. .. . ..o. . .co. .c.o.o..c.oo .ooo

. . . . .c.o.o 7 1.i 4 . =0 3. =3 3.4m 4. t= 4.04.' 3. =3 . 4 u 4.498 S. 9. 7.10 S.04. 4. m 5.949 5.79. S.38. 4 . 9. n . 3.1.

EE MhbhM bl W b" WId not W W h .

i

, in onier to determine the Snel mired modo values. 77.315% of the elevated value (presosted in the 250 FT Mhred Mode table) s and 22.e85% of the ground level value (presented in the 30 FT Mixed Mode table) are uned to calculSte em Snel values. ,

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