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Rev 14 to RETS Manual.
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Site:	Browns Ferry
Issue date:	10/01/1993
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TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT RET$ 55lJIlIL RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (SETS)

REVISION 14 PREPARED BY: DALE W. NIX PHONE: 2682 RESPONSIBLE ORGANIZATION: CHEMICAL TECHNICAL SUPPORT APPROVED BY: M. BAJESTANI DATE: 10/01/93 EFFECTIVE DATE: 11/03/93 LEVEL OF USERS REFERENCE USE VALIDATIONDATE: NOT REQUIRED QUALITY-RELATED 032018363901010101110393 BFNP RETS RETS NANUAL b 110393 10 9404110417 940329

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(1496)

REVISION LOG Procedure Number: RETS MANUAL Revision Number: 14 Pages Affected: ALL; GENERAL REVISION Pagination Pages: NONE Description of Change:

This change makes the RETS Manual methodology for dose assessment and setpoint calculations consistent with that to be used in the Canberra Effluent Management System (EMS) software to be implemented on the Genie (ND9900) Computer System on October 1, 1993. General descriptions of the major changes are as follows: doses will be calculated for each release (airborne and liquid) from the plant; all doses will include the dose from all identified radionuclides; a 31-day dose projection will be calculated based on the release being assessed and all previous and ongoing releases; cumulative quarterly and annual dose will be maintained and reported for each release which will include all completed releases made during the applicable period; dose rates (from all ongoing releases) will be calculated for airborne releases to be compared to the instantaneous dose rate limit in the Technical Specifications; and setpoints corresponding to the Tech Spec limits will be calculated for each release and compared to both the default setpoint for the applicable monitor and the expected response of the monitor to the release to insure conservation.

RETS. Manual Revision 14 Page 1 Browns Ferry Nuclear Plant Radiological Effluent Technical Specification (RETS)

Manual 1132(206)

RETS Manual Revision 14 Page 2 INDEX Section I. Introduction II. Radiological Effluent Manual (REM)

III. Offsite Dose Calculation Manual (ODCM)

IV. Process Control Program (PCP) 1132(206)

RETS. Manual

~

Revision 14 Page 3 RETS Manual Section I Introduction 1132(206)

RETS Manual Revision 14 Page 4 RETS Manual Section I INTRODUCTION The Radiological Effluent Technical Specification (RETS) Manual contains three documents; the Radiological Effluent Manual (REM), the Offsite Dose Calculation Manual (ODCM), and the Process Control Program (PCP). All three documents are referenced by the Radiological Effluent Technical Specifications which were issued on February 5, 1987 as Technical Specification Amendments Nos. 132, 128, and 103 to unit 1, 2, and 3, respectively.

The REM and the ODCM were approved by the NRC when they issued the RETS.

The REM is controlled by the NRC, so changes to the REM must be approved by the NRC before they are put in this manual. The ODCM and PCP are controlled by TVA, so changes to the ODCM and the PCP must be approved by PORC. Initial NRC approval of the PCP is required and has been requested.

1132(206)

RETS Manual Revision 14 Page 5 RETS MANUAL Section II RADIOLOGICAL EFFLUENT MANUAL REM)

For the Browns Ferry Nuclear Plant Limestone County, Alabama Tennessee Valley Authority 1132(206)

RETS. Manual Revision 14 Page 6 RADIOLOGICAL EFFLUENT MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV. NO.

A. INTRODUCTION A-1 Bi RESPONSIBILITIES B-1 C. 1. LIQUID EFFLUENTS SAMPLING C-1 AND ANALYSIS PROGRAM

2. LIQUID WASTE TREATMENT C-5 D. 1. GASEOUS EFFLUENTS SAMPLING D-.l AND ANALYSIS PROGRAM

2. GASEOUS WASTE TREATMENT D-5 E. RADIOLOGICAL ENVIRONMENTAL MONITORING 1~ SAMPLING AND ANALYSIS E-1

2. LAND USE CENSUS E-3

3. INTERLABORATORY E-5 COMPARISON PROGRAM F. REPORT CONTENT

1. ANNUAL RADIOLOGICAL F-1 ENVIRONMENTAL OPERATING REPORT

2. SEMIANNUAL RADIOACTIVE F-2

'. EFFLUENT RELEASE REPORT SPECIAL REPORTS (RADIOLOGICAL ENVIRONMENTAL MONITORING)

F-3 1132(206)

RETS Manual Revision 14 Page 7 A. INTRODUCTION The purpose of this manual is to provide the sampling and analysis programs which provide input to the ODCM for calculating liquid and gaseous effluent concentrations and offsite doses. Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept as-low-as-reasonable-achievable (ALARA).

The Radiological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Browns Ferry Plant are not higher than expected.

In addition, this manual outlines the info'rmation required to be submitted to the NRC in both the Annual Radiological Environmental Operating Report and the Semiannual Radioactive Effluent Release Report.

A-1 1132(206)

RETS Manual Revision 14 Page 8 B. RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.

All changes to this manual shall be approved by the NRC prior to implementation.

It shall be the responsibility of the Plant Manager to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the Technical Specifications.

B-1 1132(206)

RETS Manual Revision 14 Page 9 C. LI UID EFFLUENT SAMPLING AND ANALYSIS PROGRAM C.l Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with Table C-l.

The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of the Technical Specifications.

C-l 1132(206)

RETS Hanual Revision 14 Page 10 TABLE C-1 RADIOACTIVE LI ID HASTE SAHPLING AND ANALYSIS PROGRAH SYSTEH DESIGN CAPABILITY LIQUID RELEASE SAMPLING HINIHUH ANALYSIS TYPE OF ACTIVITY LONER LIHIT OF DETECTION TYPE FRE UENCY FRE UENCY ANALYSIS i /ml )

Batch Haste Each Batch Each Batch Prior Principal Gamma SE-7<3)

Releases<1) to Release Emitters<4)

One Batch Honthly Dissolved and 1 E-5<3) per Honth Entrained Gases<5)

Honthly Honthly Tritium 1 E-5 Proportional Composite <2) Gross a 1 E-7 Quarterly Sr-89, Sr-90 5 E-8 Proportional Quarterly Composite <2) Fe-55 1 E-6 C-2 ll32("~6)

RETS Manual Revision 14 Page ll TABLE NOTATION TABLE C-1 (1) A batch release is the discharge of liquid wastes of a discrete volume.

The discharge shall be thoroughly mixed prior to sampling.

(2) A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.

(3) The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95K probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb E

V

2.22 x 10

Y

exp (-Mt)

Where'.

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

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

E is the counting efficiency (as counts per disintegration),

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and ht for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

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

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

e C-3 1132(206)

RETS Manual Revision 14 Page 12 TABLE NOTATION TABLE C-1 Continued)

(4) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:- Zn65, Co60, Cs137, Mn54, Co58, Cs134, Ce141, Ce144, Mo99, and Fe59 for liquid releases. This list does not mean that only these nuclides are to be detected and reported.

Other nuclides detected within a =95K confidence level, together with the above nuclides, shall also be identified and reported as being present.

Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide. I-131 shall have a LLD of (1 E-6.

(5) Gamma Emitters Only.

0 C-4 1132(206)

RETS. Manual Revision 14 Page 13 C.2 LI UID RADIOACTIVE WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.21 mrem to any organ per unit (see Figure 4.8-1b, Technical Specification).

Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days, in accordance with the ODCM.

With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of limits specified above prepare and submit the Special Report pursuant to Section 6.7.2 of the Technical Specifications.

C-5 1132(206)

RETS Manual Revision 14 Page 14 D. GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D.l Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table D-1. Dose rates shall be determined to be within limits of the Technical Specifications using methods contained in the ODCM.

Samples of offgas system effluents shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.

D-1 1132(206)

RETS Manual Revision 14 Page 15 TABLE 0-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM SYSTEM DESIGN CAPABILITY GASEOUS RELEASE SAMPLING HINIHUH ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF DETECTION TYPE FRE UENCY FRE UENCY ANALYSIS i/ml)

A. Containment Prior to Each Prior to Each Purge Principal Gamma 1E-4(1)

Purge Purge Grab Sample Emitters(3)

H-3 1E-6 B. 1. Stack Grab Sample Monthly(4) Principal Gamma 1E-4(1)

Emitters(3)

2. Building Grab Sample Monthly(4) H-3 1E-6 Venti lation

a. Reactor/

Turbine

b. Turbine Exhaust C.. Radwaste C. All Release Continuous Charcoal Sample I-131 lE-12(2)

Points Listed Sampler Weekly(4) in B. Above Continuous Particul~te Sample Principal Gamma 1E-11 Sampler Weekly(4> Emitters(3) and I-131 1E-12(2)

Continuous Composite Particulate Gross Alpha 1E-11 Sampler Sample Monthly Continuous Composite Particulate Sr-89, Sr-9p 1 E-11 Sampler Sample Quarterly 0-2

RETS Manual Revision 14 Page 16 TABLE NOTATION TABLE D-1 (1) The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95K probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb E *V

2.22 x 10

Y

exp (-Xht)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

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

E is the counting efficiency (as counts per disintegration),

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and 4t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

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

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

(2) When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.

D>>3 1132(206)

RETS Manual Revision 14 Page 17 TABLE NOTATION TABLE D-1 Continued)

(3) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

(4) Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.

D-4 1132(206)

RETS. Manual Revision 14 Page 18 D.2 GASEOUS RADIOACTIVE WASTE TREATMENT Doses due to gaseous releases to areas at and beyond the site boundary shall be projected in accordance with the ODCM at least once per 31 days.

1132(206)

RETS. Manual Revision 14 Page 19 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.l SAMPLING AND ANALYSIS The radiological monitoring program required by this section provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The radiological environmental monitoring program shall be conducted as specified in Table E-l.

The radiological environmental monitoring samples shall be collected pursuant to Table E-1 from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirement of Table E-1 and the detection capabilities required by Table E-2.

With the radiological environmental monitoring program not being conducted as specified in Table E>>l, in lieu of a LER, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table E-3 when averaged over any calendar quarter, in lieu of a LER, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a report which identifies the cause(s) for exceeding the limit(s) and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of the Technical Specifications. When more than one of the

,radionuclides in Table E-3 are detected in the sampling medium, this report shall be submitted if:

~Conc 1 + Conc(2) + ... > 1.0 Limit(1) Limit(2)

When radionuclides other than those in Table E-3 are detected and are result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of the Technical Specification.

E-1 1132(206)

RETS Manual Revision 14 Page 20 Such reports are not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1 identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

In lieu of a LER, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s) and table(s) for the ODCM reflecting the new locations.

The provisions of Technical Specification 1.0.C are not applicable.

The detection capabilities required by Table E-2 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as an a posterior (after the fact) limit for particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions, Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

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

E-2 1132(206)

RETS Manual Revision 14 Page 21 E.2 LAND USE CENSUS A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles).

With a land use census identifying a location(s) which yields calculated dose or dose commitment greater than the maximum value a,

currently being calculated in section D.2 of this manual, in lieu of a LER, identify the new locations in the next Annual Radiological Environmental Operating Report.

With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with section E.l, add the new location(s) to the radiological environmental monitoring programs within 30 days owner consents.

if the The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) (via the same exposure pathway) may be deleted from this monitoring after October 31 of the year in which this land use census was program conducted. In lieu of a LER, identify the new location(s) in the next Annual Radiological Environmental Operating Report and provide a revised figure(s) and table for the ODCM reflecting the new location(s).

Broad leaf vegetation sampling may be performed at the site boundary in the direction section with the highest D/g in lieu of the garden census.

E-3 1132(206)

RETS. Manual Revision 14 Page 22 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

a. Within a 2 mile radius from the plant or within the 15 mrem per year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

b. Within a 5 mile radius from the plan, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.

The best'urvey information from the door-to-door, mail, telephone, aerial or consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20K of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

E-4 1132(206)

RETS Manual Revision 14 Page 23 E. 3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by, the Commission.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM (or participants in the EPA cross check program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

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

E-5 1132(206)

RETS Hanual Revision 14 Page 24 TABLE E-1 RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH Number of Samples Exposure Pathway and Sampling and Type and Frequency

~dl S Sam le Locationsa Collection Fre uenc of Anal sis

1. AIRBORNE Radioiodine and Hinimum of 5 locations Continuous operation of Radioiodine canister.

Particulates sampler with sample Analyze at least once collection as required by per 7 days for I-131.

dust loading but at least once per 7 days. Particulate sampler.

Analyze for gross beta radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the average of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.

2. DIRECT RADIATION At least 40 locations At least once per 92 days. Gamma dose. At least with > 2 dosimeters once per 92 days.

at each location.

aSample locations are given in the ODCH.

E-6 1132(206)

RETS Hanual Revision 14 Page 25 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sam le L tk Collection Fre uenc of Anal sis

3. HATERBORNE

a. Surface 2 locations Compositeb sample collected Gamma i sotopi c analysis over a period-of < 31 days. of each composite 'sample.

Tritium analysis of com-posite sample at least .

once per 92 days.

b. Drinking Minimum of downstream 1 Composi teb sample collectedc Gross beta and gamma location, or all water over a period < 31 days. isotopic analysis of supplies within 10 miles each composite sample.

downstream which are Tritium analysis .of taken from the Tennessee composite sample at least River. once per 92 days.

c. Sediment Minimum of 1 location At least once per 184 days. Gamma isotopic analysis of each sample.

d. Groundd aSample locations are shown in the ODCH.

>Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.

cComposite samples shall be collected over a period within 3 miles downstream of the plant.

of < 14 days for 131I if drinking water is obtained dGround water movement in the area has been determined to be from the plant site toward the Tennessee River.

Since no drinking water wells exist between the plant and the river, ground water will not be monitored.

E-7 1132(206)

RETS Manual Revision 14 Page 26 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure. Pathway and Sampling and Type and Frequency and/or Sam le Sam le Locationsa Collection Fre uenc of Anal sis

4. INGESTION

a. Hi lk 3 locations At least once per 15 days I-131 analysis of each when animals are on pasture; sample. Gamma isotopic at least once per 31 days analysis at least once at other times. per 31 days.

b. Fish 2 samples One sample in season, or at Gamma isotopic analysis least once per 184 days if on edible portions.

not seasonal. One sample of commercial and game species.

c. Food Productse 2 locations At least once per year Gamma isotopic analysis at time of harvest. on edible portion.

aSample locations are shown in the ODCH.

eSince water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed; E-8 1132(206)

RETS Hanual Revision 14 Page 27 TABLE E-2 HAXIHUM VALUES FOR THE LONER LIHITS OF DETECTION (LLD)a c Airborne Parti cul ate Hater or Gas Fish Hi lk Food Products Sediment Analysi s (pCi/1) (pCi /m3) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry) gross beta 1 xl0-2 N.A. N.A. N.A. N.A.

2000 N.A. N.A. N.A. N.A. N.A.

Hn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 30 N.A. 260 N.A. N,A. N.A.

Co-58, 60 15 N.A. 130 N.A. N.A. N.A.

Zn-65 30 N.A. 260 N.A. N.A. N.A.

Er-95 30 N.A. N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A. N.A.

I-131 lb 7 x 10-2 N.A. 60 N.A.

Cs-134 5x102 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.

La-140 15 N.A. N.A. 15 N.A. N.A.

E-9 1132(206)

RETS Manual Revision 14 Page 28 TABLE E-2 (Continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95K probability with 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb E

V

2.22

Y + exp (-Xdt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as picocurie per unit mass or volume),

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

E is the counting efficiency (as counts per disintegration),

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

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

'A is the radioactive decay constant for the particular radionuclide, and ht is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).

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

E-10 1132(206)

RETS. Manual Revision 14 Page 29 TABLE E-2 (Continued)

TABLE NOTATION

b. The LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0. pCi/L for I-131.

c. Other peaks which are measurable and identifiable, together with the radionuclides in Table E-3, shall be identified and reported.

E-11 1132(206)

RETS Hanual Revision 14 Page 30 TABLE E-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONHENTAL SAMPLES Reporting Levels Hater Airborne Particulate Fish Hi lk Food Products A~nal s1s ~(C1 I 1) or Gases ( Ci/m3) ( Ci/K wet) ~(C1 /1 > ( Ci/K wet)

H-3 2 x 104<<) N.A. N.A. N.A. N.A.

Hn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-58 1 x 103 N.A. 3 x 104 N.A. N.A.

Co-60 3 x 102 N.A. 1 x 104 N.A. N.A.

Zn-65 3 x 102 N.A. 2 x 102 N.A. N.A.

Zr-Nb-95 4 x 102 N.A. N.A. N.A. N.A.

I-131 0.9 N.A. 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 N.A. N.A. 3 x 102 N.A.

(a)For drinking water samples. This is 40 CFR Part 141 value.

E-12 1132(206)

RETS Manual Revision 14 Page 31 F. REPORT CONTENT F.l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine Annual Radiological Environmental Operating Reports covering operation of the plant during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by section E.2 of this manual. If harmful effects or evidence of irreversible damage are, detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some 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 environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by section E.3 of this manual.

F-1 1132(206)

RETS. Manual Revision 14 Page 32 F. 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the Regional Office of Inspection and Enforcement within 60 days after January 1 and July 1 of each year. The report shall include summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the format of Appendix B thereof. Calculated offsite dose to members of the public resulting from the release of liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1. The Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period (a) container volume, (b) total curie quantity, (specify whether determined by measurement or estimate), (c) principal radionuclides (specify whether determined by measurement or estimate),

(d) sources of waste and processing employed (e.g. dewatered spent resins, compacted dry waste, etc.), (e) type of container (e g., LSA, Type A, Type B, large quantity), and (f) solidification agent or absorbant (e.g. concrete, urea formaldehyde, etc.).

F-2 1132(206)

RETS Manual Revision 14 Page 33 F.3 SPECIAL REPORTS (Radiolo ical Environmental Monitorin If measured levels of radioactivity in an environmental sampling medium are determined to exceed the reporting level values of Table E-3 when averaged over any calendar quarter sampling period, a report shall be submitted to the Commission pursuant to Section E.l of this Manual.

F-3 1132(206)

RETS Manual Revision 14 Page 34 RETS MANUAL Section III OFFSITE DOSE CALCULATION MANUAL (ODCM) 1132(206)

RETS . Manual Revision 14 Page 35 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 1 of 10)

Section page INTRODUCTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 46 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS ~............. ~.......... 48 1/2 ' APPLICABILITY - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 48 1/2.1 INSTRUMENTATION . . .. .... . .. . .... .- . . .... . ........ 50 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 50 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..... 55 1/2.2 RADIOACTIVE EFFLUENTS .............. ....... .... ..... ..... . 60 1/2.2.1 LIQUID EFFLUENTS ..........-................................. 60 1/2.2.1.1 CONCENTRATION ......... . .. .............. ~ ............... 60 1 /2.2.1.2 DOSE ...................................................... 64 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM .......................... 65 1/2.2.2 GASEOUS EFFLUENTS ........................................... 66 1 /2 2.2.1 DOSE RATE ........ ~ ~ ~ ~ ~ . ~ ~ ...... ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ 66 1/2.2.2.2 DOSE NOBLE GASES ......--...........-.-.--.-....--.....-. 69 1/2.2 2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS . 70 1/2.2.2.4 GASEOUS RADWASTE TREATMENT .................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 71 1 /2-2.3 TOTAL DOSE .................................................. 72 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ......................... 73 1/2.3.1 MONITORING PROGRAM .......................................... 73 1/2.3o2 LAND USE CENSUS +oooo.o.oo.ooooooooooooooo.o-..-........o.... 81 1/2.3.3 .INTERLABORATORY COMPARISON PROGRAM ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ -~- ~ ........ 83 1132(206)

RETS Manual Revision 14 Page 36 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 2 of 10)

Section page BASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 84 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 85 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . ~ ~ ~ ~ 85 1/2.2 RADIOACTIVE EFFLUENTS ...... .. ................o. ............ 85 1/2.2.1.1 CONCENTRATION ~ .. . -... ...-........-...-.--.............. 85 1 /2.2.1.2 DOSE ....... . ~ ..-..-.. ........-. .. .........--........ .

~ ~ 86 1/2.2 1.3 LIQUID WASTE TREATMENT .. . . ...o....... ~ ~ .. .... .--....

~ ~ 86 1 /2.2.2.1 DOSE RATE . . .... .. ........ '.. ..... . .............. 87 1/2.2.2.2 DOSE NOBLE GASES .. . .. ... ..

~ ~ ...o o.. . . .... .

~ ~ ~ 88 1/2.2.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM o...woo.oo.o.woo. ~ ..o..oooo.o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 89 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ~ .................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t 90 1 /2.2.3 TOTAL DOSE .. ~ ~ . ................. ......... . .... ...

~ ~ ~ ~ ~ ... ~ 90 1/2. 3 RADIOLOGICAL ENVIRONMENTAL MONITORING ........................ 90 1/2.3 MONITORING 1 PROGRAM .... . ......... ......... .......... ...

~ ~ ~ ~ ~ ~ 90 1/2.3.2 LAND USE CENSUS ...................................-......... 91 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM . ......... .. ..........

~ ~ ~ ~ 91 3.0 DEFINITIONS .--.......... . ................. -.... ... . . ....

~ ~ ~ 92 3.0.A. CHANNEL CALIBRATION .... .. ~ ~ ~ ~ .. ~ ~ ~ -. ~ . ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 3.0.B. CHANNEL FUNCTIONAL TEST .............................. ~....... 93 3.0.C. GASEOUS WASTE TREATMENT SYSTEM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ " " "" .

~ ~ ~ ~ ~ 93 3.0.D. DOSE EQUIVALENT I-131 .............................. ......... ~ 93 3.0.E. MEMBER(S) OF THE PUBLIC ............. ...... ..................

~ 93 3.0.F. OPERABLE OPERABILITY . ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 3.0.G. PURGE PURGING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t 94 1132(206)

RETS Manual Revision 14 Page 37 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 3 of 10)

Section page 3 .O.H. RATED POWER ... ..... .... ........ ...... ... ............... 94 3.0.I. SITE BOUNDARY .........-.... .... -......-..................-. 94 3.0.J. SOURCE CHECK ... .... . . ~ ~ ~ ~ ~ ~ ~ ~ ................ . .. .... 94 3.0.K. UNRESTRICTED AREA ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ----- - ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ......

~ 95 3 ~ 0 q L q VENTING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 95 4 .0 (NOT USED) ............... ........ ~ ~ ~ ~ ~ .. .... ........ 98 5.0 ADMINISTRATIVE CONTROLS .... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . .. ............ 99 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 100 5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ~ ~ ~ ~ .~.~. ~ ........ 100 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES ..... . ................ ~ ~ ~ 101 5.4 SPECIAL REPORTS ....... ....o........ ....o... .o. ....... ..... 101 6.0 LIQUID EFFLUENTS .oo.e......ee..o........... ~ ~ ...'................ 102 R ELEASE POINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 103 6.1 LIQUID RELEASES ............. ......... .... ...

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 104 6.1.1 Pre-release Analysis/MPC Sum of the Ratios ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 104 6.1.2 Release Flow Rate Calculations ................................ 104 6.1.3 Post-release Analysis ............................... ~ ~ ~ . ~ ~ ~ . ~ ~ 105 6.2 INSTRUMENT SETPOINTS ....... ...................................

~ ~ 106 6.2.1 Release Point Monitor Allowable Values ........................ 106 6.2.2 Default Allowable Values ...................................... 107 6.2.2.1 Radwaste Discharge Monitor .................................. 107 6.2.2.2 Raw Cooling Water and Residual Heat Removal Service Water Monxtors ..................................................... 108 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION ..................... 109 6.3.1 Dose Calculation .............................................. 109 1132(206)

RETS. Manual Revision 14 Page 38 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

Section page 6.3.2 Cumulative Doses 110 6.3.3 Comparison To Limxts ........................................ 110 6.4 LIQUID RADWASTE TREATMENT SYSTEM ~ .. ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ . .

~ ~ ~ ~ ........ 111 6.5 DOSE PROJECTIONS ... .... .... .... ... o.. ..........o. .... 112 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES ............. ..... .... 113 6..6.1 Water Ingestion .......-.......-..................---.......... 113 6.6.2 Fish Ingestion ........ ........-..................- ..-....... 114 6..6.3 Shoreline Recreation .. ........... .....-.-. -.............'..

~ ~

114 Total Maximum Individual Dose ..... " .... --....... ..........

t 6.6.4 115 6.6.5 Population Doses ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 116 6.7 LIQUID DOSE FACTOR EQUATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ 118 6.7.1 Water Ingestion Dose Factors .................................. 118 6.7.2 Fish Ingestion Dose Factors .......... " ....... "" .- " " . " --- 118 6.7.3 Shoreline Recreation Dose Factors ............................. 118 7.0 GASEOUS EFFLUENTS ... .. .. .....

~ ~ . ... ... .. . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

RELEASE POINTS DESCRIPTION ~ ................ .- . ... ..... .......

~ ~ ~ .

139'.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ -- ~ 140 7.1.1 Maximum Allowable Value ....................................... 140 7.1.2 Default Allowable Values .................-................... 141 7.2 RELEASE RATE LIMIT METHODOLOGY ................. .............. ~ 142 7.3 GASEOUS EFFLUENTS DOSE RATES . ................................

~ 144 7.3.1 RELEASE SAMPLING .............. ..... .. .. ............ ......

~ ~ ~ ~ ~ 144 7.3.2 144 e

NOBLE GAS DOSE RATES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

7.3.2.1 Total Body Dose Rate .......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 144 7 .3.2.2 Skin

~ ~ ~ S lC Dose Rate ......................-.............-..-...... 145 1132(206)

RETS. Manual Revision 14 Page 39 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 5 of 10)

Section page I

7.3.3 I-131, I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS ORGAN DOSE RATE ~ ~ ~ ~ ~ ~ ~ 146 7.4 CUMULATIVE DOSE NOBLE GASES ................................... 147 7.4.1 Gamma Dose to Air .........-.--.-.............................. 147 7..4.2 Beta Dose to Axr .............-.-....----..................;... 148 7.4.3 Cumulative Dose Noble Gas ..... ~ ~ ~ ........................... 148 7.4.4 Comparison to Limits ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .......... ... ............

~ ~ 148 7.5 CUMULATIVE DOSE ORGAN DOSE DUE TO I-131, I-133, TRITIUM PARTICULATES WITH HALF LIVES GREATER THAN 8 DAYS ~ ~ ~ ~ ~ ~ ~ 149 7.5.1 Organ Dose Calculation ........................................ 149 7 .5.2 Cumulative Doses .............................................. 150 7.5.3 Comparison to Limits .......................................... 150 7.6 GASEOUS RADWASTE TREATMENT ...................................... 151 7.6.1 DOSE PROJECTIONS .............................................. 151 7 '.2 SYSTEM DESCRIPTION ............................................ 151 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES ....................... ~ 152 7 .7.1 Noble Gas Dose ................................................ 152 7 .7.1.1 Gamma Dose to Axr ........................................... 153 7 .7.1.2 Beta Dose to Axr ............................................

A ~

153 1132(206)

RETS Manual Revision 14 Page 40 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 6 of 10)

Section page 7.7.2 Radioiodine, Particulate and Tritium Maximum Organ Dose ..... 154 7 .7.3 Population Doses .................--.. ........................ 156 7 .7.4 Reporting of Doses .............-........-..-.................. 157 7.8 GASEOUS DOSE FACTOR EQUATIONS ...o .... ......................... 158 7.8.1 Pasture Grass-Cow-Goat-Milk Ingestion Dose Factors ............ ]58 7.8.2 Stored Feed-Cow/GoatMilk Ingestion Dose Factors .............. 159 7.8.3 Pasture Grass-Beef Ingestion Dose Factors ..................... 160 7.8.4 Stored Feed-Beef Ingestion Dose Factors ....................... 161 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors .................. 162 7.8.6 Stored Vegetable Ingestion Dose Factors ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 163 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 164 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor ................. 165 7.8.9 Tritium-Pasture Grass-Beef Dose Factor ........................ 166 7.8.10 Tritium-Stored Feed-Beef Dose Factor ......................... 167 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor .................... 168 7.8.12 Tritium-Stored Vegetables Dose Factor ........................ 169 7.8.13 Inhalation Dose Factors ............................... ~ .. ..

~ ~ 170 7.8.14 Ground Plane Dose Factors .................................... 170 7.9 DISPERSION METHODOLOGY ................ o........................

~ 171 7.9.1 Annual Average Air Concentration ................ . ..... ..... ~ ~ ~ 172 7.9.2 Relative Concentration ........................................ 173 7 .9.3 Relative ~Disperse.on ...........................................

~

173 7.9.4 Effective Release Height

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 74 1132(206)

RETS Manual Revision 14 Page 41 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 7 of 10)

Section page 8 .0 TOTAL DOSE .......................-.................. '........-.. 227 9.0 ENVIRONMENTAL MONITORING PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~..... 229 9.1 MONITORING PROGRAM DESCRIPTION ............. .......o............ 230 9.2 DETECTION CAPABILITIES ....... . .. . .- ~ ... . .............. 230 9.3 LAND USE CENSUS .... ........-.. .--.-.--.--.....................

~ 230 9.4 INTERLABORATORY COMPARISON PROGRAM .............................. 230 1132(206)

0 RETS. Manual Revision 14 Page 42 Browns Ferry Nuclear Plant

~ Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 8 of 10)

LIST OF TABLES page Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .. 51 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~~ ~ ~ 53 Table 1 1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . 56 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~~~~ ~ 58 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .. 61 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM ooo ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 67 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 75 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES o.................o.oo...o...oo 78 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTR'ATIONS IN ENVIRONMENTAL SAKS ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~~~~ ~ ~ ~ ~ 80 Table 3.1 FREQUENCY NOTATION ........................................ 96 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS .................... 119 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA .. ~ ~ - ~ ~ 120 Table 6.3 DOSE CALCULATION FACTORS .....................-.....-. . . 123 Table 6.4 INGESTION DOSE FACTORS .................................... 125 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH ............... 133 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND.. 134 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA ...................... 175 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UN IT AT BFN ..oooo...o.o.o........o.o....oo.o.............. 176 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION 177 Table 7.4 NOBLE GAS DOSE FACTORS ........................-.......- 205 1132(206)

RETS Manual Revision 14 Page 43 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 9 of 10)

LIST OF TABLES page Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES .......... 206 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT ........ 207 Table 7.7 INHALATION DOSE FACTORS .................-......--........ 208 Table 9.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ............ 231 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS ...........-.--........... .....................

~ 236 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS -................... 237 1132(206)

RETS Manual Revision 14 Page 44 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 10 of 10)

LIST OF FIGURES page Figure 3.1 LAND SITE BOUNDARY . ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ -- ~ ~ ~ --- ~ ~ ~ ~ ~ ~ ~ ". ~ ~ - ~ ~ . ~ 97 Figure 6.1 LIQUID RELEASE POINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ -~-~- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 136 Figure 6.2 LIQUID RADWASTE SYSTEM ~ --- ~ ~ ~ ~ ~ ~ ---- --------

~ ~ ~ .......... 137 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING ... ........... ~ 216 Figure 7.2 NORMAL BUILDING VENTILATION .............................. 217 Figure 7.3 PLUME DEPLETION EFFECT ...............------.............. 218 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME ~ ~ ..... 222 Figure 7.5 RELATIVE DEPOSITION ...................................... 223 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT .............................. ....... ~ 238 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ................................ ~ . ~ 239 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT .................... ... ~ ~ . ~ ~ ~ 240 1132(206)

RETS Manual Revision 14 Page 45 SECTION 1.0 AND 2.0 CONTROLS AND SURVEILLANCE RE UIREMENTS 1132(206)

RETS Manual Revision 14 Page 46 INTRODUCTION The Browns Ferry Nuclear Plant (BFN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the BFN Technical Specifications. The ODCM is divided into two major parts. The first part of the ODCM contains: 1) Radioactive Effluent Controls specified by the BFN Technical Specifications; 2) Radiological Environmental Monitoring Controls required by the BFN Technical Specifications; 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by BFN Technical Specifications; and, 4) Administrative Controls for the ODCM requirements. The second part of the ODCM contains the methodologies used to: 1) calculate offsite doses resulting from radioactive gaseous and liquid effluents; 2) calculate gaseous and liquid effluent monitor Alarm/Trip setpoints; and, 3) conduct the Environmental Radiological Monitoring Program.

The BFN ODCM is maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Any licensee initiated ODCM changes will be implemented in accordance with BFN Technical Specifications.

1132(206)

RETS Manual Revision 14 Page 47 Radioactive waste release levels to UNRESTRICTED AREAS should be kept "as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20, Appendix B, Table II. At the same time, the requirements specified in this manual permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20. It is expected that by using this operational flexibility and exerting every effort to keep levels of radioactive releases "as low as reasonably achievable" in accordance with criteria established in 10 CFR Part 50, Appendix I, the annual releases will I

result in a small fraction of the annual average concentration limits specified in 10 CFR Part 20, Appendix B, Table II.

The surveillance/testing requirements given in this manual provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and gaseous effluents. These requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive materials released to the environment. Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 5.0 of this manual.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may e from time to time require the licensee to take such actions as the Commission deems appropriate.

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RETS Manual Revision 14 Page 48 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Compliance with the Controls contained in the succeeding sections is required during the conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

1.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.

1132(206)

RETS Manual Revision 14 Page 49 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.0 APPLICABILITY SURVEILLANCE RE UIREMENTS 2.0.1 Surveillance Requirements shall be met during the conditions specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25K of the surveillance interval.

2.0.3 Performance of a Survei'llance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a Control and associated action statements unless otherwise required by these Controls. Surveillance Requirements do not have to be performed on inoperable equipment.

1132(206)

RETS. Manual Revision 14 Page 50 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 The radioactive liquid effluent monitoring instrumentation listed in Table 1.1-1 shall be OPERABLE with the applicability as shown in Tables 1.1-1 and 2.1-1. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 6.2 to ensure that the limits of Control 1.2.1.1 are not exceeded.

APPLICABILITY: This requirement is applicable as shown in Table 1.1-1.

ACTION:

a. With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable,.

or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

b. The action required when the number of OPERABLE channels is less than the minimum channels OPERABLE requirement is specified in the notes for Table 1.1-1. Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE RE UIREMENTS 2.1.1 Each of the radioactive liquid effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-1.

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RETS Manual Revision 14 Page 51 Table 1.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument* OPERABLE A licabilit Action

1. Liquid Radwaste Effluent Monitor (RM-90-130) A/B

2. RHR Service Water Monitor (RM-90-1331 -134)

3. Raw Cooling Water Monitor (RM-90-132)

4. Liquid Radwaste Effluent Flow Rate (77-60 loop)

Alarm/trip setpoints will be calculated in accordance with the guidance given in Section 6.2.

During Releases via this pathway.

~ During operation of an RHR loop and associated RHR service water system.

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RETS Manual Revision 14 Page $ 2 Table 1.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met:

(1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in Control 1.2.1.1, (2) if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in Table 2.2.1 and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend releases via this pathway.

ACTION B With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirementsg suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

I ACT 0 N C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored. If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and an analysis with at least an LLD of 1E-7 pCi/ml (gross) or '< applicable MPC ratio (y isotopic) shall be used to monitor the effluent.

ACTION D With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for radioactivity with an LLD of 1E-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic).

ACTION E With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued 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 during actual releases. Pump curves may be used to estimate flow.

See Table 2.2-1, Table Notation for the definition of LLD.

1132(206)

RETS, Manual Revision 14 Page 5.3 Table 2.1-1 (Page 1 of LIQUID EFFLUENT MONITORING INSTRUMENTATION 2)'ADIOACTIVE SURVEILLANCE REQUIREMENTS-INSTRUMENT SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

a. Liquid Radwaste Effluent D4 R5 Monitor (RM-90-130)

b. RHR Service Water D4 R5 Q2 Monitor (RM-90-133,-134)

c. Raw Cooling Water D4 R5 Monitor (RM-90-132)

d. Liquid Radwaste Effluent D4 N/A Flow Rate (77-60 loop) 1132(206)

RETS Manual Revision 14 Page 54 Table 2.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION NOTE: Each requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25'X of the interval given.

The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the alarm/trip setpoint.

b. Instrument indicates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

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

a. Instrument indicates measured levels above the alarm/trip setpoint.'.

Instrument indicates an inoperative/downscale failure.

c Instrument controls not set in operate mode.

3 This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.

4 INSTRUMENT CHECK shall consist of verifying indication during periods of release. INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days which continuous, periodic, or batch releases are made.

5 The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))

radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.

1132(206)

0 RETS. Manual Revision 14 Page 55 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 The radioactive gaseous effluent monitoring instruments listed in Table 1.1-2 shall be OPERABLE with the applicability as shown in Table 1.1-2. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 7.2 to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded.

APPLICABILITY: As shown in Table 1.1-2.

ACTION:

a. Pith a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

b. Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

c. The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instrument(s) to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE RE UIREMENTS 2.1.2 Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-2.

1132(206)

RETS Manual Revision 14 Page 56 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE .GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels/

Instrument Action

1. Stack (RM-90-147B & 148B)

a. Noble Gas Monitor A/C

b. Iodine Cartridge B/C

c. Particulate Filter B/C

d. Sampler Flow Abnormal D e.. Stack Flow (FT, FM, FI-90-271) D

2. Reactor/Turbine Building Ventilation (RM-90-250)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

d. Sampler Flowmeter D

3. Turbine Building Exhaust (RM-90-249, 251)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

e. Sampler Flowmeter D

4. Radwaste Building Vent (RM-90-252)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

e. Sampler Flowmeter D

5. Offgas Post Treatment

a. Noble Gas Activity Monitor (RM-90-265, -266)

b. Sample Flow Abnormal (PA-90-262) 1132(206)

RETS Manual Revision 14 Page 57 Table 1.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION

At all times.

~ During releases via this pathway ACTION A With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION B With a number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed in accordance with the sampling and analysis program specified in Table 2.2-2 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional e testing, calibration, or repair without providing or initiating. grab sampling.

ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue 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 F With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Purging during SI performance is not considered a loss of monitoring capability.

1132(206)

RETS Manual Revision 14 Page 5.8 Table 2.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

1. STACK

a. Noble Gas Monitor M Rl Q2

b. Iodine Cartridge N/A N/A N/A

c. Particulate Filter N/A N/A N/A

d. Sampler Flow Abnormal N/A R Q.

e. Stack Flowmeter N/A R Q

2. REACTOR/TURBINE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

3. TURBINE BUILDING EKHAUST

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

4. RADWASTE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

5. OFF GAS POST TREATMENT4

a. Noble Gas Activity D Rl Q3 Monitor

b. Sample Flow Abnormal D N/A 1132(206)

RETS Manual Revision 14 Page 59 Table 2.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTE: Each requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25K of the interval given.

1 The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))

radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.

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

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperative/downscale failure.

3. Instrument controls not set in operate mode (stack only).

The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperative/downscale failure.

3. Instrument controls not set in operate mode (stack only).

The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.

4 The noble gas monitor shall have a LLD of 1E-5 (Xe-133 Equivalent)

The noble gas monitor shall have a LLD of 1E-6 (Xe-133 Equivalent) 1132(206)

0 RETS Manual Revision 14 Page 60 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (see Figure 3.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.

APPLICABILITY: At all times.

ACTION%

If the above limits are exceeded, appropriate action shall be initiated without delay to bring the release within limits. Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.1.1.1 Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and the length of time over which each discharge occurred.

2.2.1.1.2 Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in Table 2.2-1.

2.2.1.1.3 The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.

2.2.1.1.4 The results of the analysis of samples collected from release points shall be used with the calculational methodology in ODCM Section 6.1 to assure that the concentrations at the point of discharge are maintained within the above limits.

1132(206)

RETS Manual Revision 14 Page 61 Table 2.2-1 (Page 1 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

System Design

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

Type Frequency Frequency Analysis (pci/ml)

Batch Waste Each Each Batch Principal 5xlO 7 3 Releasesl Batch Prior to Gamma Release Emitters4 One Batch Monthly Dissolved and lxlO 5 3 per Month Entrained Gases5 Monthly Monthly Tritium lx10 5 Proportional Composite2 Gross Alpha lxlO 7 Quarterly Quarterly Sr-89, Sr-90 5xlO-8 Proportional Composite2 Fe-55 lx10-6 1132(206)

RETS. Manual Revision 14 Page 62 Table 2.2-1 (Page 2 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1 A batch release is the discharge of liquid waste of a discrete volume. The discharge shall be thoroughly mixed prior to sampling.

2 A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged'rom the plant and is representative of the liquid discharged.

3 The LLD is defined for the purpose of these requirements as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95K probability with only a 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66sb E V 2.22E+06 Y exp (-Xdt)

Where:

= the "a priori" lower limit of detection as defined above (microcurie per unit mass or volume) sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X the radioactive decay constant for the particular radionuclide (s 1), and the elapsed time between midpoint of sample collection and time of counting (s).

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

It should be recognized that the LLP is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

4 The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Zn-65, Co-60, Cs-137, Mn-54, Co-58, Cs-134, Ce-141, Ce>>144, Mo-99 and Fe-59 for 1132(206)

RETS, Manual Revision 14 Page 63 Table 2.2-1 (Page 3 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION liquid releases. This list does not mean that only these nuclides are to be detected and reported. Other nuclides detected within a =95K confidence level, together with the above nuclides, shall also be identified and reported as being present. Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD level for that nuclide. I-131 shall have a LLD of < lE-6.

5 Gamma Emitters Only.

1132(206)

RETS . Manual Revision 14 Page 64 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.2 DOSE CONTROLS 1.2.1.2 The doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to

< 5 mrem to any organ, and

b. During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION0 If the limits specified above are exceeded, prepare and submit a Special Report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.1.2 Cumulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in ODCM Section 6.3 at least once every 31 days.

1132(206)

RETS, Manual Revision 14 Page 65 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.3 LI UID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.21 mrem to any other organ per unit.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of limits specified above, prepare and submit the Special Report pursuant to Section 6.9.1.4 of the Technical Specifications.

SURVEILLANCE RE UIREMENTS 2.2.1.3 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 dqys, in accordance with ODCM Section 6.5.

1132(206)

RETS Manual Revision 14 Page 66 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS 1.2.2.1 The dose rate at any time to areas at and beyond the SITE BOUNDARY

{see Figure 3.1) due to radioactivity released in gaseous effluents from the site shall be limited to,the following values:

a. The dose rate limit"for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin, and

b. The dose rate limit for I-131, I-133, H-3 and particulates with greater than eight day half-lives shall be <1500 mrem/yr to any organ.

APPLICABILITY: At all times ACTION: If the limits above are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.

Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.2.1.1 The gross B/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.

.a. For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in Table 1.1-2.

b. For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified above.

.2.2.2.1.2 Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in Table 2.2-2. Dose rates shall be determined to be within the above limits using methods contained in ODCM Section 7.3.

2.2.2.1.3

~ ~ ~ ~ Samples of offgas system effluents shall be analyzed at least weekly to determine the identity and quantity of the principal

~

radionuclides being released. ~

~

1132{206)

RETS Manual Revision 14 Page 67 Table 2.2-2 (Page 1 of 2)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM

System Design

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

Type Frequency Frequency Analysis (pCi/ml)

A.Containment Prior to Prior to Principal lxlo Purge Each PURGE Each PURGE Gamma Grab Emitters3 Sample H-3 lxlo-6 B.l. Stack Grab Sample Monthly Principal lxlo Gamma Emitters3

2. Building Grab Sample Monthly H-3 lx10 Ventilation

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radwaste C.A11 Release Continuous Charcoal I-131 lx10 Points Sampler Sample Listed in Weekly4 B. Above Continuous Particulate Principal lxlo Sampler Sample Gamma Weekly4 Emitters3 I-131 lxl0 Continuous Composite Gross Alpha lx10 Sampler Particulate Sample Monthly Continuous Composite Sr-89, Sr-90 lx10 Sampler Particulate Sample Quarterly 1132(206)

RETS Manual Revision 14 Page 68 Table 2.2-2 (Page 2 of 2)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1 The LLD is defined, for the purpose of this requirement, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95K probability with only a 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66sb E V 2.22E+06 Y exp (-'A ht)

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume) sb ~ the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E ~ the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (s ),

and ht ~ the elapsed time between midpoint of sample collection and time of counting (s).

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

. lt should be recognized that the LLD is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not an a

~osteriori (after the fact) limit for a particular measurement.

When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with

~

the above nuclides, 'shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

4 Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.

1132(206)

RETS Manual Revision 14 Page 69 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2 2.2.2 DOSE NOBLE GASES CONTROLS 1.2.2.2 The air dose to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to noble gases released in gaseous effluents per unit shall be limited to the following:

aO During any calendar quarter, to < 5 mrad for gamma radiation and

<10 mrad for beta radiation;

b. During any calendar year, to < 10 mrad for gamma radiation and

< 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

If the calculated air dose exceeds the limits specified above, prepare and submit a special report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2 2.2.2 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.3 at least once every 31 days.

1132(206)

RETS Manual Revision 14 Page ?0 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2."2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1 2 ' ' The dose to a MEMBER OF THE PUBLIC from radioiodines, radioactive materials in particulate form, and,radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a. To any organ during any calendar quarter to < 7.5 mrem;

b. To any organ during any calendar year to < 15 mrem.

APPL'ICABILITY: At all times.

ACTION:

If the calculated doses exceed the limits specified above, prepare and submit a special report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.2.3 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.4 at least once every 31 days.

1132(206)

RETS Manual Revision 14 Page .71 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 During operation above 25K power, the discharge of the SJAE must be routed through the charcoal adsorbers.

The GASEOUS RADWASTE TREATMENT SYSTEM shall be operable and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluents from each unit, to areas at and beyond the site boundary, would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION With the gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers and in excess of the above limits, prepare and submit a special report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.2.4.1 During operation above 25K power, the position of the charcoal bed bypass valve will be verified daily.

2.2.2.4.2 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected in accordance with Section 7.5 at least once per 31 days.

1132(206)

RETS. Manual Revision 14 Page 72 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a period of one calendar year.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2, 1.2.2.2, or 1.2.'2.3, prepare and submit a Special Report to the Commission pursuant to Technical Specification 6.9.1.4 and limit the subsequent releases such that the above limits are not exceeded.

t SURVEILLANCE RE UIREMENTS 2.2.3 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Sections 6.3, 7.3, and 7.4 and the methods in ODCM Section 8.0.

1132(206)

RETS. Manual Revision 14 Page 73 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1 The radiological environmental monitoring program shall be conducted as specified in Table 2.3-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 2.3-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 2.3-3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected quarter a report which 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 calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3.

When one or more of the radionuclides in Table 2.3-2 is detected in the sampling medium, this report shall be submitted if:

concentration(1) limit level(1) concentration(2) limit level(2)

+... >1.0 When radionuclides other than those in Table 2.3-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

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RETS. Manual Revision 14 Page 74 e l/2 1/2.3 CONTROLS AND SURVEILLANCE RE UIREMENTS RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS ACTION (CONTINUED):

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.3-1, identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 The specific locations from which samples were unavailable may 'ays.

then be deleted from the monitoring program.

Pursuant to Control 1.3.1.b, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

The detection capabilities required by Table 2.3-2 are state-of-the art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an

'a priori (before the fact) limit representint the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report.

SURVEILLANCE RE UIREMENTS 2.3.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures listed below and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-2.

2.3.1.2 If measured levels of radioactivity in a environmental sampling medium are determined to exceed the reporting level values of Table 2.3-3 when averaged over any calendar quarter sampling period, a report shall be submitted to the Commission pursuant to Control 1.3.1.b.

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RETS Manual Revision 14 Page 75 Table 2.3-1 (1 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~8am le Locationsa Collection Fre uenc of Anal sis

l. AIRBORNE Radioiodine/ Minimum of 5 Continuous operation Radioiodine canis ter:

Particulates locations of sampler with Analyze at least once sample collection as per 7 days for I-131.

required. by dust loading but at least Particulate sampler:

once per 7 days. Analyze for gross beta radioactivity

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the average of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92-days.

2. DIRECT At least 40 At least once per Gamma Dose. At least RADIATION locations with 92 days. once per 92 days.

> 2 dosimeters at each location.

Sample locations are given in ODCM Section 9.0.

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RETS Manual Revision 14 Page 76 Table 2.3-1 (2 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locationsa Collection Fre uenc of Anal sis

3. WATERBORNE

a. Surface 2 locations Composite sample Gamma isotopic collected over a analysis of each period of < 31 composite sample.

ays b Tritium analysis of composite sample at least once per 92 days.

b.Drinking Minimum of 1 Composite sample Gross beta and gamma downstream collected over a isotopic analysis of location, or all period of < 31 each composite sample.

water supplies days b Tritium analysis of within 10 miles composite sample at downstream which least once per 92 are taken from days.

the Tennessee River

c. Sediment Minimum of 1 At least once per Gamma isotopic location. 184 days analysis of each sample.

d. Groundd a Sample locations are given in ODCM Section 9.0.

b Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Composite samples shall be collected over a period of < 14 days for I-131 if drinking water is obtained within 3 miles downstream of the plant.

Ground water movement in the area has been determined to be from the plant site toward the Tennessee River. Since no drinking water wells exist between the plant and the river, ground water will not be monitored.

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RETS Manual Revision 14 Page 77 Table 2.3-1 (3 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locationsa Collection Fre uenc of Anal sis

4. INGESTION

a. Milk 3 locations At less t once per 15 I-131 analysis of days when animals each sample. Gamma are on pasture; isotopic analysis at at least once per least once per 31 days 31 days at other times.

b. Fish 2 samples One sample in Gamma isotopic season, or at least analysis on edible once per 184 days portions.

if not seasonal.

One sample of commercial and game species.

c. Food 2 locations At least once per Gamma isotopic Productse year at time of analysis on edible harvest portion.

Sample locations are given in ODCM Section 9.0.

Since water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.

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RETS, Manual Revision 14 Page 78 Table 2.3-2 (1 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES ~

Airborne Food Particulate Fish Products Sediment Water or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg,

~Anal sis ~Ci/L) ~(ci/m3 wet) ~Ci/3) wet ) ~Ar )

gross beta 4 0.01 N/A N/A N/A N/A H-3 2000 N/A N/A N/A N/A N/A Mn-54 15 N/A 130 N/A N/A N/A Fe-59 30 N/A 260 N/A N/A N/A Co-58, 60 15 N/A 130 N/A N/A N/A Zn-65 30 N/A 260 N/A N/A N/A Zr-95 30 N/A N/A N/A N/A N/A Nb-95 N/A N/A N/A e

15 N/A N/A I-131 lb 0.07 N/A 60 N/A Cs-134 15 0.05 130 15 60 150 Cs-137 0.06 150 18 80 180 Ba-140 60 N/A N/A 60 N/A N/A La-140 15 N/A N/A 15 N/A N/A 1132(206)

RETS. Manual Revision 14 Page 79 Table 2.3>>2 (2 of 2)

NAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION LLD)

FOR ENVIRONMENTAL SAMPLES TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66 sb E V 2.22 Y exp(-Mt)

Where:

LLD = the "a priori" lower limit of detection as defined above, (as picocuries per unit mass or volume).

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

E = the counting efficiency, (as counts per disintegration).

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

2.22 = the number of disintegrations per minute per picocurie.

Y = the fractional radiochemical yield, (when applicable).

X = the radioactive decay constant for the particular radionuclide, seconds 1 and dt = for environmental samples is the elapsed time between sample collection, (or end of the sample collection period), and time of counting (for environmental samples, not plant effluent samples),

seconds.

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

It should be recognized that the 11D is defined as an ~ariorl (before the fact) limit representing the capability of a measurement system and not as b LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.

Other peaks which are measurable and identifiable shall be identified and reported.

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RETS Manual Revision 14 Page 80 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or gases Fish Milk Food Products A~nal sis ~(ci/r. ~Ci/m3 Ci/K wet ~Ci/L) Ci/K wet)

H-3 2>>04(.) N.A N.A N.A. N.A.

Mn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co<<58 1 x 103 N.A. 3 x 104 N.A. N.A.

Co-60 3 x 102 N.A. 1 x 104 N.A. N.A.

Zn-65 3 x 102 N.A. 2 x 104 N.A. N.A.

Zr-Nb-95 4 x 102 N.Aa N.A. N.A. N.A.

I-131 0.9 N.A. 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2x 103 70 2 x 103 Ba-La-140 2 x 102 N.A. N.A. 3x 102 N.A.

(a) For drinking water samples. This is 40 CFR Part 141 value.

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RETS. Manual Revision 14 Page 81 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3 2 LAND USE CENSUS CONTROLS 1.3.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing vegetables in each of the 16 meteorological sectors within a distance of 5 miles. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of milk animals and gardens of greater than 500 square feet 'll producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

1 Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in the direction sector with the highest D/g in lieu of the garden census.

APPLICABILITY: At all times.

ACTION:

With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in Section 7.5, identify the new location(s) in the next Annual Radiological Environmental Operating Report.

With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Control 1.3.1, add the new location(s) to the radiological environmental monitoring program within 30 days if the owner consents. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s)

(via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Identify the new location(s) in the next Annual Radiological Environmental Operating Report and provide a revised figure(s) and table(s) reflecting the new location(s).

SURVEILLANCE RE UIREMENTS (see next page) 1132(206)

RETS Manual Revision 14 Page 82 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE RE UIREMENTS 2.3.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

Within a 2-mile radius from the plant or within the 15 mrem pei year isodose line, whichever is larger, enumeration by a door-to-door or .

equivalent counting technique.

20 Within a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

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RETS Manual Revision 14 Page 83 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 Analyses shall be performed on radioactive materials supplied .as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION%

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

SURVEILLANCE RE UIREMENTS 2.3.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program (or participants in the Environmental Protection Agency (EPA) cross check program shall provide the EPA program code desi.gnation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

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RETS, Manual Revision 14 Page 84 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.

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RETS Manual Revision 14 Page 85 BASES 1/2.1 EFFLUENT MONITORING INSTRUMENTATION 1/2.1.1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as 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 in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits or 10 CFR Part 20 Appendix B, Table II, Column 2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments will be calculated in accordance with Section 7.2.1 to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The action required when the number of OPERABLE channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner..

1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A limits of Appendix I to 10 CFR Part 50 to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the 1132(206)

RETS Manual Revision 14 Page 86 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION (continued) controlling radioisotope and its Maximum Permissible Concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission of Radiological Protection (ICRP) Publication 2.

1/2 2 1.2 DOSE This requirement is provided to implement the dose requirements of Section II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The requirement implements the guides set forth in Section II.A of Appendix I.

action provides the required operatin'g flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to 0'his assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable". Also, for fresh water sites with drinking water supplies which can potentially be affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in Section 6.0 implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 6.0 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I," October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I" April 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

1/2.2.1.3 LI UID WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This requirement implements the requirements of 10 CFR Part 50.36a, 1132(206)

RETS Manual Revision 14 Page 87 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.3 LI UID WASTE TREATMENT (continued)

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

1/2.2.2.1 DOSE RATE This requirement is provided to ensure that the dose rate at anytime at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. 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 an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The speci. fied release rate limits restrict, at all times, the corresponding gamma and beta dose rates to an individual at or beyond the SITE BOUNDARY to < 500 mrem/year to the total body or

< 3000 mrem/year to the skin. These release rates also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem/year for the nearest cow to the plant.

The action for this requirement requires that appropriate corrective action(s) be taken to reduce gaseous effluent releases if the limits are exceeded.

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RETS. Manual Revision 14 Page 88 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.2 DOSE NOBLE GASES This requirement is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I.

The action to be taken for exceeding these limits provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.A of" Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides." October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, "Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These ODCM equations also provide for determining the air doses at the exclusion area boundary are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and l.ill.

If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.

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RETS Manual Revision 14 Page 89 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This requirement is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I.

The action to be taken for exceeding these limits provides the required operating flexibility and at the, same time implements the guides set forth in Section IV.A of Appendix I to assure .that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section. III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the UNRESTRICTED AREA. The pathways which were examined in the development of these calculations were: 1) individual inhalation 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 animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.

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RETS. Manual Revision 14 Page 90 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT This requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior their release to the environment. This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable". This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This action requires that a special report be prepared and submitted to explain reasons for any failure to comply with the above requirements.

1/2.2.3 TOTAL DOSE This requirement is provided to meet the dose limitations of This requirement requires the preparation and

'0 CFR 190.

submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to four reactors, is highly unlikely that the resultant dose to a MEMBER OF THE it PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limi.ts. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of five miles must be considered.

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring 1132(206)

RETS Manual Revision 14 Page 91 BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM (continued) program by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

1/2.3.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, mail, telephone, aerial or consulting with local authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via the leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20K of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

1/2.3.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

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RETS. Manual Revision 14 Page 92 SECTION 3.0 DEFINITIONS 1132(206)

RETS. Manual Revision 14 Page 93 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these controls.

3.0.A. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel including alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included in CHANNEL FUNCTIONAL TEST and SOURCE CHECK.

3.0.B. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channel the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip function.

3.0.C. GASEOUS WASTE TREATMENT SYSTEM The GASEOUS WASTE TREATMENT SYSTEM consists of the charcoal adsorber vessels installed in the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.

3.0.D. DOSE E UIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (pCi/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

3.0.E. MEMBER S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant.

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RETS Manual Revision 14 Page 94 DEFINITIONS This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter RESTRICTED AREAS.

3.0.F. OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or .seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

3.0 G. PURGE PURGING PURGE or PURGING is the controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the containment.

3.0 H. RATED POWER RATED POWER refers to operation at a reactor power of 3,293 MWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.,

Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

3.0 I. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA (see Figure 3.1).

3.0.J. SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of 'sources.

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RETS, Manual Revision 14 Page 95 DEFINITIONS 3.0.K. UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposed of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes (see Figure 3.1).

3 O.L. VENTING VENTING is the controlled process of discharging air or gas from primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required. Vent, used in system names, does not imply a VENTING process.

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RETS Manual Revision 14 Page 96 Table 3.1 FRE UENCY NOTATION Notation ~Fee mene At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not Applicable Completed prior to each release 1132(206)

RETS. Manual Revision 14 Page 97 Figure 3.1 LAND SITE BOUNDARY

~y I

I BflOWNS FERAy NUCLEAR PLA~

wsul E.SE.

P~

+~

I r ps~

/

so/

( SS& SSP Land Site Boundary (for

'gaseous effluents)

Unrestricted brea Boundary (for liquid effluents) 1132(206)

RETS, Manual Revision 14 Page 98 SECTION 4.0 (NOT USED) 1132(206)

RETS. Manual Revision 14 Page 99 SECTION 5.0 ADMINISTRATIVE CONTROLS 1132(206)

RETS Manual Revision 14 Page 100 5.0 ADMINISTRATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of land use censuses required by Control 1.3.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an 'analysis of the problems and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Operating. Report shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the, report period. In the event that some 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 report shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program required by Control 1.3.3.

5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Semiannual Radioactive Effluent Release Reports shall. include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly bases following the format of Appendix B thereof. Calculated offsite dose to members of the public resulting from the release of liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision l.

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RETS Manual Revision 14 Page 101 5.0 ADMINISTRATIVE CONTROLS 5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The Semiannual Radioactive Effluent Release Report shall include the information regarding solid waste as specified in the Process Control Program.

5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES As required by BFN TS 6.12, changes to the ODCM:

1. Shall be documented and records of. reviews performed shall be retained as required by BFN TS 6.10.1. This documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the PORC.

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month/year) the change was implemented.

5.4 SPECIAL REPORTS Special Reports shall be submitted to the NRC in accordance with Section 50.73 to 10 CFR 50.

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RETS, Manual Revision 14 Page 102 SECTION 6.0 LI UID EFFLUENTS 1132(206)

RETS, Manual Revision 14 Page 103 6.0 LI UID EFFLUENTS RELEASE POINTS

'he minimum flows available for dilution of radwaste are shown below:

+ open 2 pumps 8 200,000 gpm/pump Radwaste Discharge.

Conduit

+ closed/helper 50,000 gpm 1132(206)

RETS Manual Revision 14 Page 104 6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis/MPC Sum of the Ratios Prior to a batch release, a grab sample will be analyzed to determine the concentration (Ci) of each gamma emitting radionuclide i in the radwaste tank. For those nuclides whose activities are determined from composite samples (i.e., Sr-89, Sr-90, Fe-55, Gross alpha and H-3), the concentrations for the previous period will be assumed as the concentration for the next period to perform all calculations. The following equation is used to calculate MPC fractions (Mi).

Ci (6.1)

Mi =

MPCi where:

Mi = fraction of radionuclide i.

Ci =

MPC concentration of radionuclide i in the radwaste tank, pCi/ml.

MPCi = MPC of radionuclide i as specified in Control 1.2.1.1, pCi/ml.

The sum of the ratios (R) will be calculated by the following relationship:

where:

R = the sum of the ratios.

Mi = MPC fraction from equation 6.1.

6.1.2 Release Flow Rate Calculations The sum of the ratios at the diffuser pipes must be ( 1 due to the releases from the above source. The following relationship will assure this criterion is met:

f (R-1) < F where:

f = the effluent flow rate (gallons/minute) before dilution.

R = the sum of the ratios as determined by Equation 6.2.

F = minimum dilution flow rate for prerelease analysis.

The allowable release rate is calculated before each release and the release rate is continuously monitored during the release so that the MPC limit is not exceeded.

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RETS, Manual Revision 14 Page 105 6.1.3 Post-release Anal sis A post-release analysis will be done using actual release data to ensure that the limits specified in Control 1.2.1.1 were not exceeded.

A composite list of concentrations (Ci) by isotope, will be used with actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equations 6.1, 6.2 and 6.3 to demonstrate compliance with the limits in Control 1.2.1.1. This data and setpoints will be recorded in auditable records by plant personnel.

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RETS Manual Revision 14 Page 106 6.2 INSTRUMENT SETPOINTS Alarm/trip setpoints for each liquid monitor will be established and set such that Equation 6.3 is satisfied. The locations and identification numbers for each liquid effluent radiation detector are shown in Figures 6.1 and 6.2. This section of the ODCM describes the methodology that will be used to determine allowable values. The allowable values are then used to determine the physical settings on the monitors. The physical settings are calculated in the applicable Scaling and Setpoint Document.

6.2.1 Release Point Monitor Allowable Values There is only one point through which routine releases are made from BFN, the Liquid Radwaste System. All releases from the Liquid Radwaste System are in a batch mode, and the monitor is looking at an undiluted waste stream as it comes out of a tank. The purpose of the monitor setpoint for these batch releases is to identify any release that would have the potential to exceed 10 CFR 20 limits after dilution. Allowable values used to determine the setpoints are calculated as described here.

For each release, a setpoint is calculated based on the monitor response to the activity in the release stream if the release were large enough to exceed the 10 CFR 20 limits after dilution. This maximum calculated setpoint, S~, is calculated using Equation6.4 belo~. A comparison is made between this calculated setpoint and the default setpoint (see Section 6.2.2) to determine which is used. The actual monitor setpoint for the release is set equal to the default setpoint, or to the maximum calculated setpoint, whichever is less.

Calculated Maximum Monitor Set oint SF (Fw + (A

Fdil))

(R - B) + B (6.4)

Fw MPC where SF = safety factor for the monitor.

Fw = flow of waste stream, gpm.

Fdil = flow of the dilution stream, gpm.

A = fraction of dilution flow allocated to this release point. For BFN this fraction is equal to one.

B = background, cpm.

MPC = sum of the MPC ratios for the release point as calculated in Section 6.1.2.

R = expected monitor response, cpm,

= B+ E Effi*Ci (6.5) i where B = monitor background, cpm.

Effi = monitor efficiency for nuclide i, cpm per pCi/cc.

Ci = tank concentration of nuclide i, pCi/cc.

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RETS, Manual Revision 14 Page 107 6.2.2 Default Allowable Values 6.2.2.1 Radwaste Dischar e Monitor The default allowable value for the radwaste discharge monitor (RM-90-130), shown in Figures 6.1 and 6.2, will be established using the methodology below. The alarm/trip allowable value will be set such that Equation 6.3 is satisfied. The default trip allowable value for the monitor, which will automatically isolate the release, is set at less than or equal to the limit in Control 1.2.1.1. The alarm allowable value is set at 90K or less of the trip allowable value.

The default maximum activity concentration of liquid radwaste that can be discharged can be calculated as:

F + f f* WFi 1

i MPC.

where:

A default maximum batch activity concentration, pCi/ml.

MPCi Maximum Permissible Concentrati.on, from 10 CFR 20 Appendix B for nuclide i, pCi/ml.

weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

dilution water flow rate, gpm.

maximum discharge flow rate, gpm.

The default maximum activity concentration is based on a selected isotopic mixture so that an allowable value can be calculated. The selected isotopic mixture will be documented in 0-TI-45. If the actual batch MPC is less restrictive than the MPC for the selected isotopic mixture, then the actual activity concentrati.on may be higher than the calculated maximum activity concentrati,on; this is the case for which the maximum allowable value defined in Section 6.2.1 would be indicated.

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RETS. Manual Revision 14 Page 108 The default monitor isolation allowable value, in cps, for releases is calculated using the following equation:

Monitor Isolation Allowable Value = (A + g WFi*Ei) + B where:

A maximum batch activity concentration as calculated above, pCi/ml WFi = weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i Ei efficiency of the monitor for nuclide i, cps/pCi/ml B monitor background, cps The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

6.2.2.2 Raw Coolin Water and Residual Heat Removal Service Water Monitors The allowable value for the Raw Cooling Water (RCW) monitors and the Residual Heat Removal Service Water (RHRSW) monitors (RM-90-132 and RM-90-133,134 respectively), shown in Figure 6.1, will be established using the methodology below. The alarm/trip allowable values will be set such that Equation 6.3 is satisfied. The allowable values for these monitors, which will alarm in the control room, are based on the 10 CFR 20 Appendix B concentration limits. These allowable values are also based on a selected isotopic mixture.

The monitor alarm allowable values, in cpm, for the RCW and RHRSW effluent monitors are calculated using the following equation:

Monitor Allowable Values < '(A

g WFi*Ei) + B where:

A total activity concentration, pCi/ml.

WFi weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

Ei efficiency of the monitor for nuclide i, cpm/pCi/ml.

B monitor background, cpm.

The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

1132(206)

RETS, Manual Revision 14 Page l09 6.3 CUMULATIVE LI UID EFFLUENT DOSE CALCULATION Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). Pathways considered are drinking water ingestion, fish consumption and shoreline recreation. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Wheeler Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways are calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e., shoreline recreation), the total body dose will be added to the internal organ dose for all age groups.

6.3.1 Dose Calculation The general equation for the dose calculations is:

i Ait Dose = Z T Ci D where:

~ A;, the total nuclide i, dose factor to the total body or any organ t for mrem/hr per pCi/ml. The total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shore line recreation, as defined in Section 6.7.

the length of time period over which the concentrations and the flows are averaged for the liquid release, hours.

Ci the average concentration of radionuclide i, in undiluted liquid effluent during the time period T from any liquid release, pCi/ml.

the near field average dilution factor for Ci during any effluent release.

FLOWw 0.30 RF where:

FLOWw = maximum undiluted liquid waste flow during the release, cfs.

0.30 = mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.

RF = default riverflow, cfs. For each release, this value is set to 44,000 cfs (the average monthly riverflow for the t

period is 1986-1992).

From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group.

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0 RETS, Manual Revision 14 Page 3,10 6.3.2 Cumulative Doses Quarterly and annual sums of all doses are determined for each release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums wi11 be the sum of all the doses for each release in the quarter or year respectively.

6.3.3 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 prior to and after each liquid release.

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RETS Manual Revision 14 Page l,ll 6.4 LI UID RADMASTE TREATMENT SYSTEM The liquid radwaste treatment system shall be maintained and operated to keep releases ALARA. A flow diagram for the LRTS is given in Figure 6.2.

1132(206)

RETS. Manual Revision 14 Page 112.

6.5 DOSE PROJECTIONS Dose projections will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.

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RETS Manual Revision 14 Page 113 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

The average dilution factor, D, used for these calculations is:

(for receptors upstream (6.13a)

RF

0.30 of Wheeler Dam) and D = (for receptors downstream (6.13b)

RF of Wheeler Dam) where:

RF = the average actual riverflow for the location at which the dose is being determined, cfs.

0.30 = the fraction of the riverflow available for dilution in the near field, dimensionless.

6.6.1 Water In estion

~ ~

Water ingestion doses are calculated for each Public Water Supply (PWS) xdentifxed wxthxn a 50 mile radius downstream of BFN (Table 6.1). Water ingestion doses are calculated for the t'otal body and each internal organ as described below:

Dorg = 10 9.8E-09 AWit Qi D exp(-8.64E+04 Xi td) (6.14) where 106 ~ conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

AWit = Dose factor for water ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 6.7.1.

Qi = Quantity of nuclide i released during the quarter, Curies.

= dilution factor, as described above, cfs 1.

D Xi = radiological decay constant of nuclide i, seconds (Table 6.3).

td = decay time for water ingestion, equal to the travel time from the plant to the water supply plus one-half day (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) to account for the time of processing at the water supply (per Regulatory Guide 1.109), days.

8.64E+04 = conversion factor, seconds per day.

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RETS Manual Revision 14 Page 114 Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1). Individual fish ingestion doses are calculated for the total body and each internal organ as described below:

Dorg = 10 9.8E-09 0.25 AFit Qi D exP(-8.64E+04 Xi td) where 10 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.

AFit = Dose factor for fish ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in ODCM Section 6.7.2.

= Quantity of nuclide i released during the quarter, Curies.

= dilution factor, as described above, cfs

= radiological decay constant of nuclide i, seconds 1 (Table 6.3).

= decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days.

8.64E+04 = conversion factor, seconds per day.

6.6.3 Shoreline Recreation

~ ~

Recreation doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1). It is assumed that the maximum exposed individual spends 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year on the shoreline at a location immediately downstream from the.diffusers. Individual recreation shoreline doses are calculated for the total body and skin as described below:

Dozg 106 9 ~ 8E&9 rf ARit Qi D exp(-8. 64E+04 Xi td) (6.16) where 106 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:

1st quarter 0.1 2nd quarter 0.3 3rd quarter 0.4 4th quarter 0.2.

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RETS, Manual Revision 14 Page 115 ARiti = Dose factor for shoreline recreation for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in ODCM Section 6.7.3.

Qi = Quantity of nuclide i released during

= dilution factor, as described above, cfs the quarter, Curies.

D Xi = radiological decay constant of nuclide i, seconds (Table 6.3).

td = decay time for recreation, equal to the travel time from the plant to the center of the reach, days.

8.64E+04 = conversion factor, seconds per day.

6.6.4 Total Maximum Individual Dose The total maximum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all'he reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.

1132(206)

RETS Manual Revision 14 Page 116 6.6.5

~ ~ Po ulation Doses For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.

For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is:

3 4 POPWTRt = 10 g POPm g POPa ATMWa TWDOSamt (6.17) m=1 a=1 where:

POP WTRt = water ingestion population dose to organ t, man-rem.

POPa = fraction of population in each age group a (from NUREG CR-1004, Table 3.39).

= 0.665 for adult

= 0.168 for child

= 0.015 for infant

= 0.153 for teen POPm = population at PWS m. The 3 PWSs and their populations are listed in Table 6.1.

ATMWa = ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 6.3. Average water ingestion rates are obtained from R.G.

1.109 Table E-4). The ratios are:

= 0 5069 for adult

= 0.5098 for child

= 0.7879 for infant

= 0.5098 for teen TWDosamt = total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.

10 3 conversion factor for remlmrem.

For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of BFN are consumed by local population. An, additional 7-days decay is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius, downstream is:

3 3 453.6 HVST APRr POPFt = 10 3 10 3 E r=l a=1Zl POPa TFDOSart a a 1132(206)

RETS. Manual Revision 14 Page 117 where:

POPFt total fish ingestion population dose to organ t, man-rem.

HVST = fish harvest for the Tennessee River, 8.32 lbs/acre/year.

APRr size of reach r, acres (Table 6.1).

TFDOSart total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 6.6.2, mrem. Calculated with td in that equation equal to travel time plus 8 days.

POPa fraction of population in each age group a, as given above.

FISHa amount of fish ingested by each age group a, kg/year per person. The average fish ingestion rates (R.G. 1.109 Table E-4) are:

Adult ~ 6.9 Child = 2.2 Teen = 5.2 453.6 = conversion factor, g/lb.

10 3 conversion factor, rem/mrem.

10 3 conversion factor, kg/g.

For shoreline recreation, the general equation used for calculating the population doses, POPR, in man-rem is:

REQFRA POPRt = E (6.19) where:

POPRt = total recreation population dose for all reaches to organ t, man-rem.

REQFRA = fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3, year per quarter.

SHVISr = shoreline visits per year at each reach r, (Table 6.1).

HRSVISr = length of shoreline recreation visit at reach r, 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

103 conversion factor, mrem/rem.

TSHDOSrt = total shoreline dose rate for organ t, in reach r, mrem-quarter/h per quarter.

exp(-Xitr) c FGit 10 24 103 Dr 2.22E11 Xi where:

Qi = total activity released during the quarter, Ci.

Xi = decay constant for nuclide i, day tr = travel time from the plant to reach r,

= transfer coefficient from water to sediment, days.

Kc L/kg-hr, (Table 6.3).

= mass density of sediment, kg/m , (Table 6.3).

dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m .

10 = conversion factor, pCi/Ci.

24 = conversion factor, hr/day.

103 = conversion factor, ml/L.

Dr = dilution factor for reach r, cfs 1. Calculated as described, in Equation 6.13.

2.22E11 = conversion factor, ml/quarter per cfs.

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RETS Manual Revision 14 Page 118 6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors DFLiat Uwa 10 10 AWit =

where:

DFL = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Uw = water consumption rate for age group a, L/year, (Table 6.3).

10~ conversion factor, pCi/pCi.

103 conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.2 Fish In estion Dose Factors DFLiat Ufa Bi 10 10 AFit where:

DFLiat = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Ufa = fish consumption rate for'age group a, kg/year, (Table 6.3).

Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5).

106 conversion factor, pCi/pCi.

103 conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.3 Shoreline Recreation Dose Factors DFGit Kc M W 10 10 U ARit [1-exp(-'hi tbl) ]

where: \

DFGit = dose conversion factor for standing on contaminated ground for I

i nuclide and organ t (total body and skin), mrem/hr per pCi/m2, (Table 6.6).

Kc = transfer coefficient from water to shoreline sediment,, L/kg-hr, (Table 6.3).

M = mass density of sediment, kg/m , (Table 6.3).

W = shoreline width factor, dimensionless, (Table 6.3).

103 conversion factor, ml/L.

106 conversion factor, pCi/pCi.

3600 = conversion factor, seconds/hour.

Xi decay constant for nuclide i, seconds , (Table 6.2).

tbl = time shoreline is exposed to the concentration in the water, seconds, (Table 6.3).

U = usage factor, 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year.

8760 = conversion factor, hours/year.

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RETS Manual Revision 14 Page 119 Table 6.1 RECEPTORS FOR LI UID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Beginning Ending Size Recreation Name TRM+ TRM Wheeler Lake 294.0 275.0 26076 1%408%600 below BFN Wilson Lake 275.0 260.0 15930 3%816%800 Pickwick Lake 260.0 230.0 15048 705,500 Public Water Su lies Within 50 Mile Radius Downstream of BFN Name ~Po ulation Muscle Shoals, AL 259. 6 10%740 Sheffield, AL 254.3 13%065 Cherokee, AL 239.2 3,400

TRM = Tennessee River Mile 1132(206)

RETS, Manual Revision 14 Page 120 Table 6.2 (1 of 3)

RADIONUCLXDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life 'A Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1 20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5 '0E-02 4.00E>>02 4.00E-02 3-OOE-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4 60EW2 Cr-51 3.99E+04 2. 90EW7 2 '0E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2 '0E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6 '0E-04 1.20E-03 1.30E-04 1 20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9 '0E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9 '0E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni>>63 5.27E+07 2.19E-10 1 ~ 90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5 '0E-02 Cu-64 7.62E+02 1.52E-05 1 ~ 20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3 '0E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3+90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7 '0E-01 5 ~ OOE-02 5.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7 '0E-01 5.00E-02 5.00E-02 2.60E-02 Br<<84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2. 60E&2 Br-85 2.87E+00 4.02E-03 7.60E-Ol 5.00E-02 5.00E-02 2. 60E&2 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3. 10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3 ~ OOE<<02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E&2 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E>>02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1 ~ 70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4 '0E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E&3 1 ~ OOE>>05 1.00E-05 4 '0E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E&3 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+Ol 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 1132(206)

RETS, Manual Revision 14 Page 121 Table 6.2 (2 of 3)

RADIONUCL'IDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef)

Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6. 42EW6 1.30E+00 1.00E-03 1.00E-03 7-70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2. 46E&6 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4 30E-01 2.90E-03 I-134 5.26E+Ol 2.20E-04 2.00E-02 1. 20E&2 4.30E-01 2 90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2 90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08EW7 1.00E-02 8.00E-03 3.00E-01 1 50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3 ~ OOE-Ol 1 50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A

'Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A 1132(206)

RETS Manual Revision 14 Page 122 Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef)

Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+Ol 7.50E&4 N/A N/A N/A N/A Ze-135 5.47E+02 2. 11E&5 N/A N/A N/A N/A Ze 137 3.83E+00 3.02E&3 N/A N/A N/A N/A Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A

References:

Half lives for all nuclides: DOE-TIC-11026, "Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.,

Transfer factors for Sb- isotopes are from ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.

Cow-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.

Goat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.

Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.

All other nuclides'ransfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.

1132(206)

RETS Manual Revision 14 Page l23 Table 6.3 (1 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference BRa (infant) 1400 m3/year ICRP 23 BRa (child) 5500 m3/year ICRP 23 BRa (teen) 8000 m3/year ICRP 23 BRa (adult) 8100 m3/year ICRP 23 fg 1 TVA Assumption fL 1 R. G. 1.109 (Table E-15) fpc 1 TVA Assumption fsc 0 TVA Assumption H 9 g/m3 TVA Value Kc 0.072 L/kg-hr R. G. 1.109 (Section 2.C.)

M 40 kg/m2 R. G. 1.109 (Section 2.C.)

P 240 kg/m2 R. G. 1.109 (Table E-15)

Qf (cow) 64 kg/day NUREG/CR-1004 (Sect. 3.4)

(goat) 08 kg/day NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+08 seconds R. G. 1.109 (Table E-15)

(15 years) tbl 4.73K+08 seconds R. G. 1.109 (Table E-15)

(15 years) tcb 7.78E+06 seconds SgN FSAR Section 11.3.9.1 (90 days) tcsf 1.56E+07 seconds SgN FSAR Section 11.3.9.1 (180 days) te 5.18E+06 seconds R. G. 1.109 (Table E-15)

(60 days) 2.59E+06 seconds R. G. 1.109 (Table E-15)

(30 days) tesf 7.78E+06 seconds R. G. 1.109 (Table E-15)

(90 days) tmc 8.64E+04 seconds SgN FSAR Section 11.3.9.1 (1 day) thc 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day) ts 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) tsv 2.38E+07 seconds SgN FSAR Section 11.3.9.1 (275 days)

Um (infant) 0 kg/year R. G. 1.109 (Table E-5)

U (child) 41 kg/year R. G. 1.109 (Table E-5)

Um (teen) 65 kg/year R. G. 1.109 (Table E-5)

'Um (adult) 110 kg/year R. G. 1.109 (Table E-5)

Up (infant) 330 L/year R. G. 1.109 (Table E-5)

Up (child) 330 L/year R. G. 1.109 (Table E-5)

Up (teen) 400 L/year R. G. 1.109 (Table E-5)

Up (adult) 310 L/year R. G.. 1.109 (Table E-5) 1132(206)

RETS Manual Revision 14 Page 124 Table 6.3 (2 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference Uf(infant) 0 kg/year R. G. 1.109 (Table E-5)

Uf(child) 6.9 kg/year R. G. 1.109 (Table E-5)

Uf(teen) 16 kg/year R. G. 1.109 (Table E-5)

Uf(adult) 21 kg/year R. G. 1.109 (Table E-5)

UFL (infant) 0 kg/year R. G. 1.109 (Table E-5)

UFL (child) 26 kg/year R. G. 1.109 (Table E-5)

UFL (teen) 42 kg/year R. G. 1.109 (Table E-5)

UFL (adult) 64 kg/year R. G. 1.109 (Table E-5)

US (infant) 0 kg/year R. G. 1.109 (Table E-5) .

US (child) 520 kg/year R. G. 1.109 (Table E-5)

US (teen) 630 kg/year R. G. 1.109 (Table E-5)

US (adult) 520 kg/year R. G. 1.109 (Table E-5)

Uw(infant) 330 L/year R. G. 1.109 (Table E-5)

Uw(child) 510 L/year R. G. 1.109 (Table E-5)

Uw(teen) 510 L/year R. G. 1.109 (Table E-5)

Uw(adult) 730 L/year R. G 1.109 (Table E-5)

W 0.3 none R. G. 1.109 (Table A-2)

Yv 1.85 kg/m2 NUREG/CR-1004 (Table 3.4)

Yp 1.18 kg/m2 NUREG/CR-1004 (Table 3.3)

Ys 0.64 kg/m2 NUREG/CR-1004 (Table 3.3) 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables)

Qr (iodines) 7.71E-07 sec 1 NUREG/CR-1004 (Table 3.10)

(15.4 d half-life)

+ (particulates) 5.21E-07 (10.4 d sec 1 half-life)

NUREG/CR-1004 (Table 3.10) 1132(206)

RETS Manual Revision 14 Page l25 Table 6.4 (1 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested).

ADULT bone liver t body thyroid kidney lung gi-lli H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 O.OOE+00 0.00E+00 O.OOE+00 2.17E-05 Cr-51 O.OOE+00 O.ODE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 O.OOE+00 4.57E-06 8.72E-07 O.OOE+00 1.36E-06 O.OOE+00 1.40E-05 Mn-56 O.OOE+00 1.15E-07 2.04E-08 O.OOE+00 1.46E-07 O.OOE+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-'5 Co-57 O.OOE+00 1.75E-07 2.91E-07 O.OOE+00 0.00E+00 O.OOE+00 4.44E-06 Co-58 O.OOE+00 7.45E-07 1.67E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.51E-05 Co-60 O.OOE+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 O.OOE+00 0.00E+00 O.OOE+00 1.74E-06 CQ-64 O.OOE+00 8.33E-08 3.91E-08 O.OOE+00 2.10E-07 O.OOE+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0;00E+00 1.03E-05 O.OOE+00 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 O.OOE+00 1.28E-08 O.OOE+00 2.96E>>09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 O.OOE+00 2.47E-07 O.OOE+00 2.49E-05 Br-82 O.OOE+00 O.OOE+00 2.26E-06 0.00E+00 0.00E+00 O.OOE+00 2.59E-06 Br-83 O.OOE+00 O.OOE+00 4.02E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.79E-08 Br-84 O.OOE+00 O.OOE+00 5.21E<<08 0.00E+00 0.00E+00 O.OOE+00 4.09E-13 Br-85 O.OOE+00 O.OOE+00 2.14E-09 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Rb-86 O.OOE+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 O.OOE+00 4.16E-06 Rb-88 O.OOE+00 6.05E-08 3.21E-08 0 ~ OOE+00 O.OOE+00 O.OOE+00 8.36E-19 Rb-89 O.OOE+00 4.01E-08 2.82E-08 O.OOE+00 0.00E+00 O.OOE+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 O.OOE+00 4. 94E&5 Sr-90 7.58E-03 O.OOE+00 1.86E-03 0.00E+00 0.00E+00 O.OOE+00 2.19E-04 Sr-91 5.67E-06 O.OOE+00 2.29E-07 0 ~ OOE+00 O.OOE+00 O.OOE+00 2.70E-05 Sr-92 2.15E-06 O.OOE+00 9.30E-08 O.OOE+00 0.00E+00 O.OOE+00 4.26E-05 Y-90 9.62E-09 O.OOE+00 2.58E-10 0.00E+00 0.00E+00 O.OOE+00 1.02E-04 Y-91m 9.09E-11 O.OOE+00 3.52E-12 0.00E+00 0.00E+00 O.OOE+00 2.67E-10 Y-91 1.41E-07 O.OOE+00 3.77E-09 0.00E+00 O.OOE+00 O.OOE+00 7.76E-05 Y-92 8.45E-10 O.OOE+00 2.47E-ll O.OOE+00 O.OOE+00 O.OOE+00 1.48E-05 Y-93 2.68E-09 O.OOE+00 7.40E-11 O.OOE+00 O.OOE+00 O.OOE+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 O.OOE+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+00 5.12E-10 O.OOE+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 O.OOE+00 3.42E-09 O.OOE+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 O.OOE+00 1.54E-ll O.OOE+00 4.87E-08 Mo-99 O.OOE+00 4.31E-06 8.20E-07 O.OOE+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 O.OOE+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 O.OOE+00 7.97E-08 O.OOE+00 7.06E-07 O.OOE+00 2.16E-05 Ru-105 1.54E-08 O.OOE+00 6.08E-09 O.OOE+00 1.99E-07 O.OOE+00 9.42E-06 RU-106 2.75E-06 O.OOE+00 3.48E-07 O.OOE+00 5.31E-06 O.OOE+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 O.OOE+00 2.91E-.07 O.OOE+00 6.04E-05 1132(206)

RETS Manual Revision 14 Page 1,26 Table 6.4 (2 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested) ~

ADULT bone liver t body thyroid kidney lung gi-lli Sb-124 2.80E-06 5.29E-08 1.11E&6 6.79E-09 0.00E-OO 2. 18EW6 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 O.OOE-OO 1.38E-06 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 O.OOE+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-'06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3. 14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 O.OOE+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 Te-131 1.97E>>08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+00 2.79E-'09 Te-132 2.52E-06 1.63E-06 '1.53E-06 1.80E-06 1.57E-05 O.OOE+00 7.71E-05 I-130 '.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 I-131 4.16E-06 5.95E-"06 3.41E-06 1.95E-03 1.02E-05 O.OOE+00 1.57E-06 I-132 2.03E-07 5.43E-'07 1.90E-07 1.90E-05 8.65E-07 O.OOE+00 1.02E-07 I-133 1. 42E&6 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0 ~ OOE+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22EW5 1.48E-04 1.21E&4 O.OOE+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E&6 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E>>06 2.92E-06 Cs-137 7.97E-05 1.09E&4 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 O.OOE+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-ll 2.84E-09 0.00E+00 6.46E-11 3.92E-ll 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 O.OOE+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-ll 1.59E&9 O.OOE+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-ll 1.34E-09 O.OOE+00 1.85E-11 1.24E-ll 3.00E-26 La-140 2.50E-09 1.26E&9 3.33E-10 O.OOE+00 O.OOE+00 0 ~ OOE+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E&9 7.18E-10 O.OOE+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 O.OOE+00 5.37E-10 O.OOE+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2 '2E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 O.OOE+00 2.13E-09 O.OOE+00 4.03E-05 Pr-144 3.01E-11 1.25E-ll 1.53E-12 0.00E+00 7.05E-12 O.OOE+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0 ~ OOE+00 4.25E-09 O.OOE+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-ll 0.00E+00 3.65E-10 O.OOE+00 2.40E-05

References:

Regulatory Guide 1.109, Table E-ll.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 4.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS, Manual Revision 14 Page 127 Table 6.4'(3 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.32E-05 Cr-51 O.OOE+00 O.OOE+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 O.OOE+00 5.90E-06 1.17E&6 O.OOE+00 1.76E-06 O.OOE+00 1.21E-05 Mn-56 O.OOE+00 1.58E-07 2.81E-08 O.OOE+00 2.00E-07 O.OOE+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+00 O.OOE+00 1.70E-06 1.16E-06 Fe-59 . 5.87E-06 1.37E-05 5.29E-06 O.OOE+00 O.OOE+00 4-32E-06 3.24E-05 Co-57 O.OOE+00 2.38E-07 3. 99E&7 O.OOE+00 O.OOE+00 O.OOE+00 4.44E-06 Co-58 O.OOE+00 9.72E-07 2.24E-06 0.00E+00 O.OOE+00 O.OOE+00 1.34E-05 Co-60 0.00E+00 2.81E-06 6.33E&6 0.00E+00 O.OOE+00 O.OOE+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.19E-06 Cu-64 O.OOE+00 1.15E-07 5.41E-08 O.OOE+00 2.91E-07 O.OOE+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 O.OOE+00 1.28E&5 O.OOE+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 O.OOE+00 1.83E-08 O.OOE+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 O.OOE+00 3.44E-07 O.OOE+00 3.11E-05 Br-82 O.OOE+00 O.OOE+00 3.04E-06 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 5.74E-08 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 7.22E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 3.05E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.98E-05 1.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.41E-06 Rb-88 O.OOE+00 8.52E-08 4.54E-08 O.OOE+00 O.OOE+00 O.OOE+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.43E-17 Sr-89 4.40E-04 O.OOE+00 l. 26E&5 O.OOE+00 0.00E+00 O.OOE+00 5.24E-05 2.33E-04 Sr-90 8.30E-03 0.00E+00 2.05E-03 O.OOE+00 0.00E+00 0.00E+00 Sr-91 8.07E-06 O.OOE+00 3.21E<<07 O.OOE+00 O.OOE+00 O.OOE+00 3.66E-05 Sr-92 3.05E-06 O.OOE+00 1.30E-07 O.OOE+00 O.OOE+00 7.77E-05 O.OOE+00'.OOE+00 Y-90 1.37E-08 O.OOE+00 3.69E-10 O.OOE+00 O.OOE+00 1.13E-04 Y-91m 1.29E-10 O.OOE+00 4.93E-12 0.00E+00 O.OOE+00 O.OOE+00 6.09E-09 Y-91 2.01E-07 O.OOE+00 5.39E-09 O.OOE+00 O.OOE+00 O.OOE+00 8.24E-05 Y-92 1.21E-09 O.OOE+00 3.50E-11 O.OOE+00 O.OOE+00 O.OOE+00 3.32E-05 Y-93 3.83E-09 O.OOE+00 1.05E-10 0.00E+00 O.OOE+00 O.OOE+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 O.OOE+00 1.91E-08 O.OOE+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+00 7.11E-10 O.OOE+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 O.OOE+00 4.42E-09 O.OOE+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 O.OOE+00 2;14E-ll O.OOE+00 4.37E-07 Mo-99 O.OOE+00 6.03E-06 1.15E-06 O.OOE+00 1.38E-05 O.OOE+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 O.OOE+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 O.OOE+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 O.OOE+00 1.09E-07 O.OOE+00 8.99E-07 O.OOE+00 2.13E-05 Ru-105 2.18E-08 O.OOE+00 8.46E-09 O.OOE+00 2.75E-07 O.OOE+00 1.76E-05 Ru-106 3.92E-06 O.OOE+00 4.94E-07 O.OOE+00 7.56E-06 O.OOE+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 O.OOE+00 3.70E-07 O.OOE+00 5.45E-05 1132(206)

RETS. Manual Revision 14 Page 128 Table 6.4 (4 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN bone liver t body thyroid 'kidney lung gi-lli Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 O.OOE-OO 3-38E-06 7.80E-05 Sb-125 2.48E-06 2.71EOS 5.80E-07 2.37E-09 O.OOE+00 2.18E-06 1.93E-05 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E&6 2.30E-06 3.92E-05 0 OOE+00 2.41E-05 Te-127 1.58E-07 5.60E-OS 3.40E-08 1.09E<<07 6.40E-07 0 OOE+00 1.22E-05 Te-129m 1.63E&5 6.05E-06 2.58E-06 5.26E>>06 6.82EW5 O.OOE+00 6.12E-05 Te-129 4.48E-OS l. 67EWS 1.09E&8 3.20E-08 1.76E-06 1.88E-07 1.22E-05 O.OOE+00 0 OOE+00 2.45E-07 9.39E-05 Te-131m 2.44E-06 1.17E-06 9. 76E&7 Te-131 2.79E-OS 1. 15EWS 8.72E-09 2.15E-08 1.22E07 O.OOE+00 2.29E-'9 Te-132 3.49E-06 2421E-06 2.08E-06 2.33E-06 2. 12E-05 O.OOE+00 7.00E-05 I-130 1.03E-06 2. 98E&6 1.19E-06 2. 43EW4 4.59E-06 O.OOE+00 2.29E-06 I-131 5.85E-06 8 '9E-06 4.40E-06 2.39E-03 1 41E-05 O.OOE+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5 98E-06 0.00E+00 2.58E-06 I-134 1.46E&7 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 I-135 6.10E07 1.57E-06 5.82E-07 1.01EW4 2 48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2. 45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+00 1 ~ 84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0 OOE+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0 '0E+00 1.10E-07 1.28E-OS 6.76E-11 Ba-139 1.39E-07 9.78E-ll 4.05E-09 0.00E+00 9 22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 O.OOE+00 1 18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-OS 5.01E-ll 2.24E-09 O.OOE+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-OS 2.99E-ll 1.84E-09 O.OOE+00 2.53E-ll 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+00 0.00E+00 0 OOE+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 O.OOE+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0-OOE+00 5.14E-05 Ce-144 6.96E&7 2.88E-07 3.74E-08 0.00E+00 1.7.2E-07 0 ~ OOE+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 O.OOE+00 4.31E-05 Pr-144 4 30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-OS 6.11E-10 0 ~ OOE+00 5. 99E&9 O.OOE+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-OS 0.00E+00 0.00E+00 O.OOE+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0 ~ OOE+00 5.21E-10 O.OOE+00 2.67E-05

References:

Regulatory Guide 1.109, Table E-12.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 3.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS Manual Revision 14 Page 129 Table 6.4 (5 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-lli H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2. 03E-07 2.03E-07 C-14 1 ~ 21E-05 2.42E-06 2. 42E&6 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.28E-05 Cr-51 O.OOE+00 O.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 O.OOE+00 1.07E-05 2.85E-06 O.OOE+00, 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 O.OOE+00 O.OOE+00 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 7.74E-06 2.78E-'5 Co-57 O.OOE+00 4.93E-07 9.98E-07 O.OOE+00 0.00E+00 O.OOE+00 4.04E-06 Co-58 O.OOE+00 1.80E-06 5.51E-06 ~

O.OOE+00 O.OOE+00 0.00E+00 1.05E-05 Co-60 O.OOE+00 5.29E-06 1.56E-05 O.OOE+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E&5 1.83E-05 0 '0E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 O.OOE+00 2.45E-07 1.48E-07 0.00E+00 5 '2E-07 O.OOE+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn-69 4 '8E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 O.OOE+00 3.94E-05 Br-82 O.OOE+00 0.00E+00 7.55E-06 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 0 ~ OOE+00 O.OOE+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 O.OOE+00 0.00E+00 1 ~ 98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 O.OOE+00 O.OOE+00 9 ~ 12E&9 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 O.OOE+00 6.70E-05 4. 12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 Rb-88 O.OOE+00 1.90E-07 1.32E-07 0 '0E+00 O.OOE+00 0.00E+00 9.32E-09 Rb-89 0 ~ OOE+00 1.17E-07 1.04E-07 O.OOE+00 O.OOE+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 O.OOE+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 0.00E+00 9 06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 O.OOE+00 0.00E+00 1.71E-04 Y-90 4.11E-08 O.OOE+00 1.10E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 O.OOE+00 7.48E-07 Y-91 6 '2E-07 O.OOE+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 O.OOE+00 1.03E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 O.OOE+00 i.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2. 66E&5 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97 2.17E-10 3.92E-ll 1.83E-11 O.OOE+00 4.35E-ll O.OOE+00 1.21E-05 Mo-99 O.OOE+00 1.33E-05 3.29E-06 O.OOE+00 2.84E-05 0.00E+00 1.10E-05 Tc-99m 9 '3E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 O.OOE+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 O.OOE+00 2.81E-07 0 ~ OOE+00 1.84E-06 O.OOE+00 1.89E-05 Ru-105 6.45E-08 O.OOE+00 2.34E-08 O.OOE+00 5.67E-07 O.OOE+00 4.21E-05 Ru-106 1.17E-05 O.OOE+00 1.46E-06 O.OOE+00 1.58E-05 0.00E+00 1.82E&4 Ag-110m 5.39E-07 3.64E-07 2.91E-07 O.OOE+00 6.78E-.07 0.00E+00 4.33E-05 1132(206)

RETSManual Revision 14 Page 130 Table 6.4 (6 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-lli Sb-124 1. 11E-05 1.44E-07 3.89E-06 2.45E-08 O.OOE+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 O.OOE+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 O.OOE+00 1.10E-05 Te-.127m 2. 89E&5 7.78E-06 3.43E-06 6.91E&6 8.24E-05 O.OOE+00 2.34E-05 Te-127 4.71E-07 1 ~ 27K-07 1.01E-07 3.26E-07 1.34E-06 O.OOE+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 O.OOE+00 4.36E-'07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+00 1.73E-06 I-133 5.92E-O6 7.32E>>06 2.77E-06 1.36EW3 1.22E-05 O.OOE+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1. 79E-05 1.19E-06 0.00E+00 5.16E-07 I-135 l. 75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 O.OOE+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0 OOE+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E>>05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 O.OOE+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-O& 0.00E+00 1.93E'10 1.30E-10 2.39E&5 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E>>ll 6.58E-10 1.14E-07 Ba-142 8.74E-OS 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 O.OOE+00 O.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3 '1E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0 00E+00 8.68E&9 0.00E+00 2.47E-05 Ce-143 6. 99E&9 3.79E-06 5.49E-10 O.OOE+00 1.59E-09 O.OOE+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 0 ~ OOE+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 O.OOE+00 6.39E-09 O.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0 ~ OOE+00 2.11E-ll O.OOE+00 8.59E-08 Nd-147 2.79E-OS 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0 '0E+00 0.00E+00 O.OOE+00 3 '7E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 O.OOE+00 2.79E-05

References:

Regulatory Guide 1.109, Table E-13.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 2.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS Manual Revision 14 Page 131 Table 6.4 (7 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT H-3 bone liver t body thyroid kidney lung gi-lli 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E&5 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0-OOE+00 O.OOE+00 O.OOE+00 2.30E-05 Cr-51 0.00E+00 O.OOE+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 O.OOE+00 1.99E&5 4.51E-06 O.OOE+00 4-41E-06 O.OOE+00 7.31E-06 Mn-56 O.OOE+00 8.18E-07 1.41E-07 O.OOE+00 7.03E-07 O.OOE+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 O.OOE+00 O.OOE+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 O.OOE+00 0.00E+00 1.59E-05 2.57E-'5 Co-57 O.OOE+00 1.15E-06 1.87E-06 O.OOE+00 0.00E+00 0.00E+00 3.92E-06 Co-58 O.OOE+00 3.60E-06 8.98E-06 O.OOE+00 0.00E+00 O.OOE+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 O.OOE+00 O.OOE+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 O.OOE+00 0.00E+00 O.OOE+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 O.OOE+00 1.03E-06 O.OOE+00 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn-69 9.33E-08 1. 68E-07 1.25E-08 O.OOE+00 6.98E>>08 O.OOE+00 1.37E-05 Zn-69m 1.50E-06 3.06E-06 2.79E-07 O.OOE+00 1.24E-06 O.OOE+00 4.24E-05 Br-82 O.OOE+00 O.OOE+00 1.27E-05 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Br-83 0.00E+00 O.OOE+00 3.63E-07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 O.OOE+00 3.82E-07 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Br-85 O.OOE+00 0.00E+00 1.94E-08 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 O.OOE+00 0.00E+00 O.OOE+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 O.OOE+00 0.00E+00 O.OOE+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 O.OOE+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 O.OOE+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 O.OOE+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E&5 0.00E+00 1.81E-06 0.00E+00 O.OOE+00 O.OOE+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 O.QOE+00 0.00E+00 2.07E-04 Y-90 8.69E-08 O.OOE+00 2.33E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.20E-04 Y>>91m 8.10E-10 O.OOE+OO 2.76E-11 O.OOE+00 O.OOE+00 O.OOE+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.10E-05 Y-92 7.65E-09 O.OOE+00 2.15E-10 O.OOE+00 O.OOE+00 0.00E+00 1.46E-04 Y-93 2.43E-08 O.OOE+00 6.62E-10 O.OOE+00 0.00E+00 O.OOE+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 O.OOE+00 2.56E-09 O.OOE+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 O.OOE+00 1.24E-08 O.OOE+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 O.OOE+00 7.65E-11 O.OOE+00 3.09E-05 Mo-99 O.OOE+00 3.40E-05 6.63E-06 O.OOE+00 5.08E-05 O.OOE+00 1.12E<<05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 O.OOE+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 O.OOE+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 O.OOE+00 4.95E-07 O.OOE+00 3.08E-06 O.OOE+00 1.80E-05 Ru-105 1.36E-07 O.OOE+00 4.58E-08 0.00E+00 1.00E-06 O.OOE+00 5.41E-05 Ru-106 2.41E-05 O.OOE+00 3.01E-06 O.OOE+00 2.85E-05 O.OOE+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 O.OOE+00 1.04E-06 0.00E+00 3.77E-05 1132(206)

RETS . Manual Revision 14 Page 132 Table 6.4 (8 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested).

INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Te-125m 2.33E-05 7 79E-06 3.15E-06 7.84E-06 O.OOE+00 O.OOE+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127 1.00E&6 3.35E-07 2. 15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E>>05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63EW8 2.38E-07 7.07E-07 O.OOE+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 O.OOE+00 7.11E-'06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 . O.OOE+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 I-135 3.64E-06 7. 24E&6 2. 64E&6 6.49E&4 8.07E-06 0.00E+00 2.62E-06 Cs-134 3 77E-04 7.03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 O.OOE+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6 09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8-81E-11 9.26E-ll 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 O.OOE+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 O.OOE+00 O.OOE+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 O.OOE+00 2.48E-05 Ce-143 1.48E&8 9 82E-06 1.12E-09 0.00E+00 2.86E-09 O.OOE+00 5.73E-05 Ce-144 2.98E-06 l. 22E&6 1.67E-07 0.00E+00 4.93E-07'.13E-08 O.OOE+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 O.OOE+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 O.OOE+00 3.60E-05 W-187 9.03E-07 6 '8E-07 2.17E-07 0.00E+00 O.OOE+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 O.OOE+00 2.87E-05

References:

Regulatory Guide 1.109, Table E-14.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb<<124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 1.

'NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS Manual Revision 14 Page 133 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH H-3 9.0E-01 Tc-99m 1.5E+01 C-14 4.6E+03 Tc-101 1.5E+Ol Na-24 1.0E+02 Ru-103 1.0E+Ol P-32 1.0E+05 Ru-105 1.0E+Ol Cr-51 2.0E+02 RG-106 1.0E+01 Mn-54 4.0E+02 Ag-110m 0.0E+00 Mn-56 4.0E+02 Sb-124 1.0E+00 Fe-55 1.0E+02 Sb-125 1.0E+00 Fe-59 1.0E+02 Te-125m 4.0E+02 Co-57 5.0E+01 Te-127m 4.0E+02 Co-58 5.0E+01 ,Te-127 4.0E+02 Co-60 5.0E+01 Te-129m 4.0E+02 Ni-63 1.0E+02 Te-129 4.0E+02 Ni-65 1.0E+02 Te-131m 4.0E+02 CQ-64 5.0E+01 Te-131 4.0E+02 Zn-65 2.0E+03 Te-132 4.0E+02 Zn-69 2.0E+03 I-130 4.0E+01 Zn-69m 2.0E+03 I-131 4.0E+Ol Br-82 4.2K+02 I-132 4.0E+01 Br-83 4.2E+02 I-133 4.0E+Ol Br-84 4.2E+02 I-134 4.0E+01 Br-85 4.2E+02 I-135 4.0E+01 Rb-86 2.0E+03 Cs-134 1.9E+03 Rb-88 2.0E+03 Cs-136 1.9E+03 Rb-89 2.0E+03 Cs-137 1.9E+03 Sr-89 5.6E+01 Cs-138 1.9E+03 Sr-90 5.6E+01 Ba-139 4.0E+00 Sr-91 5.6E+Ol Ba-140 4.0E+00 Sr-92 5.6E+Ol Ba-141 4.0E+00 Y-90 2.5E+Ol Ba-142 4.0E+00 Y-91m 2.5E+Ol La-140 2.5E+Ol Y-91 2.5E+Ol La-142 2.5E+01 Y-92 2.5E+01 Ce-141 1.0E+00 Y-93 2.5E+01 Ce-143 1.0E+00 Zr-95 3.3E+00 Ce-144 1.0E+00 Zr-97 3.3E+00 Pr-143 2.5E+Ol Nb-95 3.0E+04 Pr-144 2.5E+01 Nb-97 3.0E+04 Nd-147 2.5E+01 Mo-99 1.0E+01 W-187 1.2E+03 Np-239 1.0E+Ol

References:

Bioaccumulation factors for Antimony nuclides are from ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A.

Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.

All other nuclides'ioaccumulation factors are from Regulatory Guide 1.109, Table A-l.

1132(206)

RETS Manual Revision 14 Page 134 Table 6.6 (1 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn>>69m .5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08

'r-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 1132(206)

RETS Manual Revision 14 Page .135 Table 6.6 (2 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin Sb-125 5.48E&9 6.80E-09 Te<<125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1 ~ 10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2. 20E&9 2.60E-06 Te-132 l. 70E&9 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1 ~ 20E-08 ~

1.40E-08 Cs-134 1.20E-08 1 ~ 40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-OS 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2 '0E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

References:

Regulatory Guide 1.109, Table E-6.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Ex osure to Photon and Electron Radiation from Radionuclides Occurrin in Routine Releases from Nuclear Fuel C cle Facilities D. C. Kocher, Health Physics Volume 38, April 1980.

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RETS Manual Revision 14 Page 136 Figure 6.1 LI UID RELEASE POINTS BFH Llquld EIIluent Monitors (Typical Unit end Common Redwdete)

Oendrnoe Oootny Tfolor Intdke Bey flllllborolooTforor RM ty Itt Rrl tO.ISO Tro Sino MMbjy hotel>> tuMny Rolnoolo (oeronont Rrt ty IOO t

Oponhy for II~ Ipor lr 0

(1) Turbine Bulldlng Equipment To Oooyny (2) Reactor BvIldlng Equipment Torreo (3) Condeneer Flea Ooofrry Torroro 1132 (206 )

RETS. Manual Revision 14 Page 137 Figure 6.2 LE UID RADVASTE SYSTEM Floor Floor Floor Drain Dreln Oreln Floor Collector Filter Semple ltM90->So Fl TT~

Dr dine Tenkb Oreln Tenkb Equipment re ne Nde'tb Neetd Yhete Ooncteneetb Sdetb Collector Filter Oemlnerellxer Sdm pie Storege Tank Tenkb Tbhkb 1132 (206 )

RETS. Manual Revision 14 Page 138 SECTION 7.0 GASEOUS EFFLUENTS 1132(206)

RETS Manual Revision 14 Page f39 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION There are eleven monitored discharge points at BFN: a Reactor Building exhaust for each unit, the Radwaste Building Exhaust, two sets of Turbine Deck Roof Fans for each unit, and the Stack. The Reactor and Radwaste Exhausts exit the plant on the roof of the reactor building.

The. Reactor Building Exhausts include exhaust from the refuel floor of the reactor buildings, exhaust from the Primary Containment Purge System, and exhaust from the turbine buildings'hese discharge points are monitored by radiation monitors 1-,2-,3-RM-90-250.

The Radwaste Building Exhaust includes exhaust from the common radwaste building. This discharge point is monitored by radiation monitor RM-90-252.

There are nine roof fans on the roof of each unit's turbine building to provide building ventilation. These are generally used in the warmer months to control building temperature. For each unit, there are two radiation monitors. One of these monitors the exhaust through four of the fans (1-,2-RM-90-249 and 3-RM-90<<251). The other monitors the exhaust through the remaining five fans (1-,2-RM-90-251 and 3-RM-90-249).

The common 600 foot plant stack receives the Condenser Offgas exhaust, the Filter Cubicle exhaust, the Steam Packing and Mechanical Vacuum exhaust, and the Standby Gas Treatment System (SBGTS) exhaust. The stack effluents are monitored by radiation monitors RM-90-147 and 148.

Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.

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RETS, Manual Revision 14 Page 140 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ODCM Control 1.1.2 requires that gaseous effluent monitors have alarm/trip setpoints to ensure that ODCM dose rate limits are not exceeded. This section of the ODCM describes the methodology that will be used to determine the allowable values which are used to calculate the physical settings on the monitors. The monitor setpoints are. calculated in the applicable Scaling and Setpoint Document. Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with the effluent monitor locations.

All gaseous releases from BFN are continuous, so allowable values are calculated for each of the monitors as a part of a release permit package at least once per week. Using the actual radionuclide mix as measured in a sample, a maximum allowable value is calculated (as described below) and compared to a default allowable value assigned to that monitor. The default allowable values are described in Section 7.1.2. The lower of the two values is the recommended setpoint for that release point. If the release point is one of several leading into a common discharge point, all current releases into that discharge point are used in the calculation of the discharge point monitor allowable value (e.g., the stack).

7.1.1 Maximum Allowable Value An expected monitor response is calculated from the sample results:

R = B + Z effi Ci (7.1) where B monitor background, cpm or cps.

eff ~

efficiency factor for the monitor for nuclide i, cpm per pCi/cc or cps per pCi/cc.

Ci measured concentration of nuclide i, pCi/cc.

The expected response is then used to determine the calculated maximum allowable value, S~ in cpm or cps. This value corresponds to the dose rate limit for the measured radionuclide mix and is determined using the following equation.'Rlim S =(ASF ( (R B))) + B DR where dose rate allocation factor for the release/discharge point, dimensionless. The dose rate allocation factor for the stack is 0.1, the building vent allocation factors are equal to 0.9 times the fraction of the total building flow assigned to that particular vent.

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RETS Manual Revision 14 Page 141 SF safety factor for the monitor, dimensionless.

DRlim the dose rate limit, mrem/year.

500 mrem/year to the total body for noble gases, 3000 mrem/year to the skin for noble gases, and DR the calculated dose rate for the release, mrem/year.

DRTB for total body (as described in Section 7.2.3.1),

DRs for skin (as described in Section 7.2.3.2), and

'I = expected monitor response (as calculated above) cpm or cps.

B = the monitor background, cpm or cps.

7.1.2 Default Allowable Values The methodology for determining the default alarm/trip allowable values is divided into two major parts. The first. consists of backcalculating from a dose rate to a release rate limit, in pCi/s, for each release point. The methodology for determining these release rate limits is given in Section 7.2. The second part consists of using the release rate limits to determine default allowable values for the monitors.

The default allowable values are calculated using the following equation.

r f A Allowable Value ( F E + B (7.3) where release rate limit for stack or ground level, pCi/sec. The release rate limits used for the allowable value calculation are 1.44E+07 pCi/sec for the stack and 1.50E pCi/sec for the building vents.

fraction of the limits r which is allowed for the release mode (elevated or ground level).

NOTE: The sum of the f values for elevated and ground levels must be less than or equal to 1. This lowers the limits to ensure that the site dose rate limit will not be exceeded both the stack and the ground level release rate limits were if reached simultaneously.

allocation factor. This is the portion of the release rate limit r which is assigned to the release point under consideration. This ensures that the ground level release rate limit will not be exceeded if all building vents were to reach their limit simultaneously. This is equal to 1 for the stack.

The building vent release rate limit is divided among the ten vents based on the flow rates.

flow rate for the vent, cc/sec. Maximum flow rates are used to ensure conservative setpoints.

'E efficiency of the monitor, (pCi/cc)/cpm or (pCi/cc)/cps.

B background of the monitor, cpm or cps.

The calculation of these setpoints are documented further in Technical Instruction (TI) 15 and the applicable Scaling and Setpoint Document, e including the numerical values for each of the parameters described above.

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RETSManual Revision 14 Page 142 7.2 RELEASE RATE LIMIT METHODOLOGY A dose rate (DTB, DS, or DTH) is calculated based on the design objective source term mix used in the licensing of the plant. Dose rates are determined for (1) noble gases and (2) iodines and particulates as described in Section 7.3.2.

The dose rate limits of interest are:

~ Total Body = 500 mrem/yr Skin = 3000 mrem/yr Maximum Organ = 1500 mrem/yr These limits are divided by the corresponding calculated dose rates described above:

Total Body Dose Rate Limit RTB(vent or stack) ven or s ac Skin Dose Rate Limit RS(vent or stack) ven or s ac )

These ratios represent how far above or below the guidelines the dose rate calculations were.

A total release rate, Q, for each release level (building vent or stack) is calculated, using the source term data in Table 7.2. Thus, two total release rates are calculated:

Qngv = Total noble gas release rate from building exhaust vents, Ci/s.

Qngs Total noble gas release rate from main stack, Ci/s ~

To obtain a release rate limit, r, for each release level, the total release rate, Q, for that release level is multiplied by the corresponding ratio, R:

For noble gases released from building vents:

rngv = RTBv Qngv~

= RSv Qngv whichever is more restrictive, i.e., smaller.

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RETS. Manual Revision 14 Page 143 where rngv = Calculated release rate limit for noble gases released from building vents.

RTBv = Ratio of total body dose rate limit to total body dose rate for building vent releases, as calculated above.

Qngv = Total Table 7.2 noble gas release rate from building vents.

RSV Ratio of skin dose rate limit to skin dose rate for building vent releases, as calculated above.

For noble gases released from the stack:

rngs = RTBs Qngsi or

= RSs Qngs whichever is more restrictive, i.e., smaller.

where rngs = Calculated release rate limit for noble gases released from the stack.

RTBs = Ratio of total body dose rate limit to total body dose rate for stack releases, as calculated above.

Qngs = Total Table 7.2 noble gas release rate from stack.

Rss Ratio of skin dose rate limit to skin dose rate for stack releases, as calculated above.

Noble Gas Stack rngs = 1.44E+01 Ci/s Building Vents rngv 1.50E01 Ci/s 1132(206)

RETS, Manual Revision 14 Page f44 7.3 GASFOUS EFFLUENTS DOSE RATES 7.3.1 RELEASE SAMPLING At least once per week, a grab sample is taken and analyzed to determine the concentration, pCi/cc, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (e.g.,

Sr-89, Sr-90, and alpha emitters).

For those nuclides whose activities are determined from composite samples the concentrations for the previous composite period will be assumed as the concentration for the next period to perform calculations in all subsequent ODCM Sections.

7.3.2 NOBLE GAS DOSE RATES Dose rates are calculated in order to determine compliance with the requirements of ODOM Control 1.2.2.1. Dose rates are calculated for total body and skin due to noble gases using semi-infinite and finite cloud models as described in NUREG 0133. The release mode will determine the model used: turbine building releases are treated as ground level t and use the semi-infinite model; reactor and radwaste building vents are treated as split-level (or mixed mode) and use the semi-infinite model; and stack releases are eleva ted and use the finite cloud model.

7.3.2.1 Total The dose Bod Dose Rate rate to the total body, the following equation:

DRTB in mrem/year, is calculated using

~ [Vi Qis + DFBi ((X/Q)g Qig) + DFBi ((X/Q)m Qim)l (7.4) i where Vi the constant for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume, in mrem/yr per pCi/sec, as given in Table 7.4 Qis the release rate of radionuclide i, in gaseous effluents from the stack, pCi/sec.

DFBi total body submersion dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m (Table 7.4).

x/Qg for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m (Table 7.1).

Qig the release rate of radionuclide i, in the gaseous effluents from all ground level releases, pCi/sec.

X/Qm for split-level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m (Table 7.1).

the release rate of radionuclide i, in gaseous effluents from all split level releases, pCi/sec.

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RETS Manual Revision 14 Page 145 7.3.2.2 Skin Dose Rate The dose rate to the skin, DRs in mrem/year, is calculated using the following equation:

(DFSj. X/Qs + F 1 Bj.) Qis + ({DFSi + 1 1 DFyi) X/Qv Qiv) (7.5)

+ ({DFSi + 1.1 Dpi) X/Qm Qim) where DFSi the skin dose factor due to beta emissions for each identified noble gas radionuclide, mrem/yr per pCi/m3.

X/Q. for stack releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m (Table 7.1).

Bi the constant for long term releases (greater than 500 hrs/yr) for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume, mrad/yr per pCi/sec (Table 7.4).

Qis the release rate of radionuclide i, in gaseous effluents from the stack, pCi/sec.

DF~i the air dose factor due to gamma emj.ssjons for each identj.fied noble gas radionuclide, mrad/yr per pCi/m3 (unit conversion factor of 1.1 mrem/mrad converts aj.r dose to skin dose)

(Table 7.4).

x/Qg for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m (Table 7.1).

Qig the release rate of radionuclide i, jn gaseous effluents from all ground level releases, pCi/sec.

X/Qm for split level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m3 (Table 7.1).

Qim the release rate of radionuclide i, in gaseous effluents from all split level releases, pCi/sec.

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t RETS. Manual Revision 14 Page 146 7.3.3 I-131 I-133 TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS ORGAN DOSE RATE Organ dose rates due to I-131, I-133, Tritium and all radionuclides in particulate form with half-lives of greater than 8 days> DRor in mrem/year, are calculated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation:

DRorg = E FD [ CTD(X/Q)D[RIT+RCTP~ + E Cip[X/Q)DRIi+(D/Q)D[RCPi+RGi]j l (7 ~ 6)

D where:

FD flowrate of effluent stream from discharge point D, cc/s.

CTD concentration of tritium in effluent stream at discharge point D, F1/cc ~

X/QD the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release mode associated with the discharge point D, sec/m , (Table 7.1).

RZT inhalation dose factor for tritium, mrem/year per pCi/m . Dose factor is calculated as described in Section 7.7.13.

RCTp grass-cow-milk dose factor for tritium, mrem/year per pCi/m3. Dose factor. is calculated as described in Section 7.7.7.

CiD concentration of nuclide i in effluent stream at discharge point D, pCi/cc ~ C inhalation dose factor for each identified nuclide i, mrem/year per pCi/m3. Dose factors are calculated ad described in Section 7.7.13.

D/QD the highest calculated annual average relative deposition for any area at or beyond the unrestricted area boundary for the release mode associated with discharge point D, sec/m , (Table 7.1).

RCpi grass>>cow-milk dose factor for each identified nuclide i, m2-mrem/year per pCi/s. Dose factors are calculated as described in Section 7.7.1.

RGi ground plane dose factor for each identified nuclide i, m -mrem/year per pCi/s. Dose factors are calculated as described in Section 7.7.14.

The organ dose rates for all pathways are summed to find the total site dose rate. The maximum organ dose rate is selected from among the dose rates calculated for all locations, organs, and age groups.

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RETS Manual Revision 14 Page 147 7.4 CUMULATIVE DOSE NOBLE GASES Doses to be calculated are gamma and beta air doses due to exposure to noble gases. For elevated releases (stack), a finite cloud model will be used for the gamma dose. All other releases will be calculated using a semi-infinite cloud model. The doses will be calculated at three locations: the land-site boundary locations with the highest annual-average split-level X/Q based on 1977-1988 meteorological data; the land-site boundary location with the highest ground level annual-average X/Q based on 1977-1988 data; and the offsite location with the highest offsite concentration based on 1977-1988 elevated level data. The joint fxequency distributions for the three levels of met data are given in Table 7.3. The locations, and their respective dispersion factors are listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.8.2 No credit is taken for radioactive decay.

7.4.1 Gamma Dose to Air The gamma air dose, DY in mrad, is calculated for each release permit using one of the following equations:

For ground or split-level release/discharge points:

3 ~ 17E&8 T Z [ DFyi Qi X/Q ] (7.7) i For elevated release/discharge points:

DY ~ 3 '7E-08 T E [ Bi Qi ] (7.8) i where:

3.17E-08 conversion factor, years per second.

T duration of release, seconds.

DFYi dose conversion factor for external gamma for nuclide i (Table 7.4), mrad/year per pCi/m3.

Qi the release rate of radionuclide i, pCi/sec.

x/Q the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundar~ for the release type under consideration (Table 7.1), sec/m .

Bi the constant for long term releases (greater than 500 hrs/yr) for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume (Table 7.4), mrad/yr per pCi/sec.

The location with the highest dose is selected as the critical receptor for each release. This receptor is used in the determination of the cumulative doses in Section 7.4.3.

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RETS Manual Revision 14 Page 148 7.4.2 Beta Dose to Air The beta air dose, Dp in mrad, is calculated for each release permit using the following equation:

Dp = 3.17E-08 T E [ DFpi (Qi X/Q ) ]

where:

3.17E-08 = covnersion factor, years per second.

T = duration of release, seconds.

DFpi ~ dose conversion factor for external beta for nuclide i (Table 7.4), mrad/year per pCi/m .

Qi ~ the release rate of radionclide i from the release/discharge point under consideration, pCi/sec.

x/Q = the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release/discharge point under consideration (Table 7.1),

sec/m3.

The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.4.3.

t 7.4.3 Cumulative Dose Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in QDCM Control 1.2.2.2.

For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.

7.4.4 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.

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R ETS Manual Revision 14 Page 149 7.5 CUMULATIVE DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS 7.5.1 Or an Dose Calculation Organ dose due to I-131, I-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release permit for the critical receptor. The critical receptor is defined as the receptor with the highest calculated dose of all the receptors defined in Table 7.1. Annual avenge X/Q and D/Q are calculated using the methodology in Sections 7.8.2 and 7.8.3 using the historical 1977-1988 meteorological data (Table 7.2). Pathways considered to exist at these locations are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.7. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calculation of organ dose is:

Dorg = 3 '7E&8 E Z T Rpi Wp Qi (7.10) i P

~

where:

3.17E-08 ~ conversion factor, year/second.

T = duration of release from release/discharge point under consideration, seconds.

Rpi = dose factor for pathway P for each identified nuclide i, m2-mrem/year per pCi/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mrem/year per pCi/m3 for inhalation and tritium ingestion pathways.

Equations for calculating these dose factors are given in Section 7.7.

Wp = dispersion factor for the release/discharge point under consideration and pathway P (Table 7.1).

~ X/Q for the inhalation and tritium ingestion pathways,

= D/Q for the food and ground plane pathways, Qi = release rate for radionuclide i from release/discharge point under consideration, pCi/s.

The receptor with the highest dose of all locations, age groups and organs is selected as the critical receptor. The age group with the highest dose for that receptor is selected as the critical age group.

The organ dose for the critical age group will be used in the cumulative doses discussed in Section 7.5.2.

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RETS, Manual Revision 14 Page 150 7.5.2 Cumulative

~ ~ Doses quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3.

For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 7.5.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3.

7.5.3 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.

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RETS. Manual Revision 14 Page 151 7.6 GASEOUS RADWASTE TREATMENT 7.6.1 DOSE PROJECTIONS Dose projections will be performed by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.

If the results of the dose projection indicate potential doses in excess of .the monthly fraction of the annual dose limit, efforts will be made to minimize future releases.

7.6.2 SYSTEM DESCRIPTION A flow diagram for the GRTS is given in Figure 7.1. The system includes the subsystems that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pumps, and the gland seal condensers. One gaseous radwaste treatment system is provided for each unit. The processed gases from each unit are routed to the plant stack for dilution and elevated release to the atmosphere. The air-ejector off-gas line of each unit and the stack are continuously monitored by radiation moni.tors.

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RETS Manual Revision 14 Page 1.52 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described below, using the quarterly release values reported by the plant personnel. For iodine releases, it will be assumed that half the iodines released are organic iodines, which contribute only to the inhalation dose. All real pathways and receptor locations (as identified in the most recent land use survey) are considered. In addition, actual meteorological data representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in Section 7.9. Stack releases will be considered elevated releases.

Radwaste and reactor building releases will .be considered split-level releases. Turbine building releases will be treated as ground level.

7.7.1 Noble Gas Dose All measured radionuclides are used to calculate gamma and beta air doses. The dose is evaluated at the nearest SITE BOUNDARY point in each sector and at other locations expected to be maximum exposure points using a semi-infinite cloud model. The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BFN.

Radioactive decay is considered in this calculation. The quarterly release is averaged over one year to obtain an average release rate.

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RETS Manual Revision 14 Page 153 7.7.1.1 Gamma Dose to Air D~ = 7 Xni Dpi where:

Dyn gamma dose to air for sector n, mrad.

Xni air concentration of radionuclide i in sector n, pCi-year/m3. Air concentrations are calculated as described by Equation 7.16.

Dpi gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

7.7.1.2 Beta Dose to Air Dan = 7 Xni DFBi where:

Dan = beta dose to air for sector n, mrad.

Xni air concentration of radionuclide i in sector n, pCi-year/m . Air concentrations are calculated as described by Equation 7.16.

Dpi = beta to air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

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RETS Manual Revision 14 Page 154 7.7.2 Radioiodine Particulate and Tritium Maximum Or an Dose Organ doses due to radioiodine, particulate and tritium releases are calculated using the following equation:

Dorg= 3 '7E-08 [E(D/Q ERP1 + D/Q RGi + X/Q RZi)Qi + E(X/Q RPT)QT] (7.14) i P P where:

Dora Organ dose, mrem.

3. 17E-08 = conversion factor, year/second.

x/Q Relative concentration for location under consideration, sec/m . Relative concentrations are calculated as described by Equation 7.17.

RPi ingestion dose factor for pathway P for each identified nuclide i (except tritium), m2-mrem/year per pCi/second.

Ingestion pathways available for consideration include:

pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.8.1 through 7.8.6.

D/Q = Relative deposition for location under consideration, m Relative deposition is calculated as described in Equation 7.18.

RGi Dose factor for standing on contaminated ground, m2-mrem/year per pCi/second. The equation for calculating the ground plane dose factor is given in Section 7.8.14.

RZi Inhalation dose factor, mrem/year per pCi/m3. The equation for calculating the inhalation dose factor is given in Section 7.8 13.

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RETS Manual Revision 14 Page 155 Qi = adjusted release for nuclide i for location under consideration, pCi. The initial release is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release is equal to the actual release decayed for an average travel time during the period.

9

= Qi0 E fj exp(-Xi x/uj) j ]

where Qi0 = initial average release for nuclide i over the period,

}LCie fj = joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.

Xi = radiological decay constant for nuclide i, sec 1.

X ~ downwind distance, meters.

RPT ~

uj = midpoint value of wind speed class interval j, ingestion dose factor for pathway P for tritium, mrem/year per m/s.

pCi/m3. Ingestion pathways available for consideration are the same as those listed above for Rpi. Equations for calculating ingestion dose factors for tritium are given in Sections 7.8.7 through 7.8.12.

~ Qx = adjusted. release for tritium for location under consideration, pCi. Calculated in the same manner as Qi above.

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RETS,Manual Revision 14 Page 156 7.7.3 Po ulation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 7.5. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.5). For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equation used for calculating the population dose in a given sector element is:

Dosepop = l RATIOP

p POPN

AGE

001

DOSEP where RATIOp = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)

= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor.

= 1.0 for the inhalation pathway.

= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)

= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.

= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh vegetables, only stored vegetables.)

POPN = the population of the sector element, persons (Table 7.6).

AGE = fraction of the population belonging to each age group.

= 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).

0.001 = conversion from mrem to rem.

DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as:

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RETS, Manual Revision 14 Page 157 ADC = exp(-Kit), for milk and vegetables, where decay constant for nuclide i, seconds.

= distribution time for food product under consideration (from Regulatory Guide 1.109, Table D-l).

= 1.21E+06 seconds (14 days) for vegetables.

= 3.46E+05 seconds (4 days) for milk.

exP(-Kit) hitch for meat, 1 exp(-X itcb) where Xi = decay constant for nuclide i, seconds.

t = additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.8.3, 7 days (from Regulatory Guide 1.109, Table D-2).

tcb = time to consume a whole beef, as described in Section 7.8.3.

For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose. This assumes that the maximum individual freezes and eats a whole beef, but the average individual buys smaller portions at a time; Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.

7.7.4 Re ortin of Doses The calculated quarterly doses and calculated population doses described in this section are reported in the Semiannual Radioactive Effluent Release Report as described in ODCM Administrative Control 5.2 1132(206)

RETS Manual Revision 14 Page 158 7.8 GASEOUS DOSE FACTOR E UATIONS 7.8.1 Pasture Grass-Cow-Goat-Milk In estion Dose Factors (m2-mrem/year per pCi/sec) r(1-exp(-AEtem)) Biv(l-exp(-Xitb))

RCPi = 10 DFLiao apFmigfexP( Xi fm) pc +

p E i where:

A 106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

= milk ingestion rate for age group a, L/year.

Uap Fmi = i transfer factor for nuclide from animal's feed to milk, days/L (Table 6.2).

= animal's consumption rate, kg/day.

Xi decay constant for nuclide i, seconds (Table 6.2).

tfm = transport time from milking to receptor, seconds.

fpc = fraction of time animal spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + X .

X weathering decay constant for leaf and plant surfaces, seconds 1.

tern = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m2.

>iv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

~ effective surface density of soil, kg/m2.

NOTE% Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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0 RETS Manual Revision 14 Page 159 7.8.2 Stored Feed-Cow/Goat-Milk In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(-Xitcsf))

Csi = FLiao ap mi ~f sc exP( ~i mc) csf i r(l~xP(-XEtesf)) B (1-exp(-X tb))

Ys XE P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, ~

organ o, mrem/pCi (Table 6.4).

= milk ingestion rate for age group a, L/year.

Uap Fmi = i transfer factor for nuclide from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

fsc = fraction of time animal spends on stored feed, dimensionless.

Xi decay constant for nuclide i, seconds (Table 6.2).

tmc = transport time from milking to receptor, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds 1, equal to Xi + +.

weathering decay constant for leaf and plant surfaces, seconds 1.

tesf = time stored feed is exposed to deposition, seconds.

Ys = agricultural productivity by unit area of stored feed, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS Manual Revision 14 Page 160 7.8.3 Pasture Grass-Beef In estion Dose Factors (m mrem/year per pCi/second)

(1-exp(-'hit b) )

j ~ 10 DFLj ao Uam Ff j Qf exp ( Kits )

RMP i cb r(l~xp(>>XEtem)) Bgv(1-exp( Xitb))

fp +

Yp 'AE P Xi where:

106 conversion factor, pCi/pCi.

DFLj ao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

= meat ingestion rate for kg/year.

Uam Ffi = transfer factor for nuclide i froma,cow's age group feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Xi decay constant for nuclide i, seconds (Table 6.2).

= time for receptor to consume a whole beef, seconds.

tcb ts = transport time from slaughter to consumer, seconds.

fp = fraction of time cow spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + X .

X weathering decay constant for leaf and plant surfaces, seconds tern = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m .

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time over which accumulation on the ground is evaluated, seconds.

P = effective surface density of soil, kg/m2.

NOTE: Factors defined above whjch do not reference a'table for their numerical values, are listed in Table 6.3.

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RETS Manual Revision 14 Page 161 7.8.4 Stored Feed-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(-Kite'b))

RMSi = 10 Ffi ~f Kits)

DFLiao Uam i cb exp(

(1-exP(-Xitcsf)) r(l~xP(-XEtesf)) Biv(l-exP(-Xitb))

fs +

~i, tcsf Ysf 'AE P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, ~

organ o, mrem/pCi (Table 6.4).

Uam = meat ingestion rate .for age group a, kg/year.

Ffi = transfer factor for nuclide i from cow's feed to meat, days/kg (Table 6.2).

= cow's consumption rate, kg/day.

decay constant for nuclide i, seconds (Table 6.2).

= time for receptor to consume a whole beef, seconds.

tcb ts = transport time from slaughter to consumer, seconds.

fs = fraction of time cow spends on stored feed, dimensionless.

tcsf = time between harvest of stored feed and consumption by cow, seconds.

r = fraction of activity retained on pasture grass, dimensionless.

tesf = time stored feed is exposed to deposition, seconds.

Ysf = agricultural productivity by unit area of stored feed, kg/m .

'AE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + Q.

weathering decay constant for leaf and plant surfaces, seconds Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time over which accumulation on the ground is evaluated, seconds.

P = effective surface density of soil, kg/m .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS. Manual Revision 14 Page 162 7.8.5 Fresh Leaf Ve etable In estion Dose Factors (m -mrem/year per pCi/second) r(1~(-ate)) Siv(1-e(-Xitb))

f E i where:

106 conversion factor, pCi/pCi.

i DFL ao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Xi decay constant for nuclide i, seconds 1 (Table 6.2).

= average time between harvest of vegetables and their consumption thc and/or storage, seconds.

= consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

r ~ fraction of deposited activity retained on vegetables, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds

=Xi+A decay constant for removal of activity on leaf and plant surfaces by weathering, seconds 1.

te ~ exposure time in garden for fresh leafy and/or stored vegetables, seconds.

= vegetation areal density for fresh leafy vegetables, kg/m2.

>iv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

~ effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS, Manual Revision 14 Page 163 7.8.6 Stored Ve etable In estion Dose Factors m2-mrem/year per pCi/second)

(1-e(-'>itsv))

FLiao exP( Xithc) USa g i sv r(1~(-ate)) e B'v(1-e(-Xitb))

iv Ysv XE P Xi whe're:

10 = conversion factor, pCi/pCi.

DFLiao ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Xi = decay constant for nuclide i, seconds 1 (Table 6.2).

thc = average time between harvest of vegetables and their consumption and/or storage, seconds.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

tsv = time between storage of vegetables and their consumption, seconds.

r = fraction of deposited activity retained on vegetables, dimensionless.

= the effective decay constant, due to radioactive decay and weathering, seconds 1.

= Xi + +

= decay constant for removal of activity on leaf and plant surfaces by weathering, seconds 1.

te = exposure time in garden for fresh leafy and/or stored vegetables, seconds.

4v == vegetation areal density for stored vegetables, kg/m .

Biv i transfer factor for nuclide from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

= time period over which accumulation on the ground is evaluated, seconds.

P = effective surface density of soil, kg/m .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS Manual Revision 14 Page 164 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor (mrem/year per pCi/m )

RCTP = 10 10 DFLTao FmT Qf Uap ~0.75(0.5/H)] fp exP(-XTtfm) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FmT = transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

= milk ingestion rate for age group a, L/year.

O'.35 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fp = fraction of time animal spends on ~esture, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

tfm = transport time from milking to receptor, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS Manual Revision 14 Page 165 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor (mrem/year per pCi/m )

(1-exP(-XTtcs RCTS = 10 10 DFLTao FmT ~f Uap ~0'75(0'5/H)~ fs exp(-XTtfm)

T csf where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).'

FmT transfer factor for tritium from animal's feed to milk, days/L (Table 6. 2) .

Qf = animal's consumption rate, kg/day.

= milk ingestion rate for age group a, L/year.

o.h , = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fs = fraction of time animal spends on stored feed, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tfm = transport time from milking to receptor, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS. Manual Revision 14 Page 166 7.8.9 Tritium-Pasture Grass-Beef Dose Factor (mrem/year per pCi/m )

RMT = 10 10 DFLTao FfT Qf Uam [0.75(0.5/H)] fp exP(-its)

(l~xP(-step)) (1-exP(-XTtcb))

>T tep XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a,.

organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Uam = meat ingestion rate for age group a, kg/year.

0. 75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fp = fraction of time cow spends on pasture, dimensionless.

'AT decay constant for tritium, seconds (Table 6.2).

= transport time from slaughter to consumer, seconds.

= time pasture is exposed to deposition, seconds.

= time for receptor to consume a whole beef, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS .Manual Revision 14 Page 1.67 7.8.10 Tritium-Stored Feed-Beef Dose Factor (mrem/year per pCi/m )

RMTS = 10 10 DFLTao FfT Qf Uam [0.75(0.5/H)] fs exP(-its)

(lmxP(-XTtcsf ) ) (1~P(-XTtcb) )

~T tcsf XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a,.

organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Uam = meat ingestion rate for age group a, kg/year.

0. 75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fs = fraction of time cow spends on stored feed, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tcb = time for receptor to consume a whole beef, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS, Manual Revision 14 Page 168 7.8.11 Tritium-Fresh Leaf

~ ~

Ve etable Dose Factor (mrem/year per pCi/m )

RgTF = 10 10 DFLTao [0.75(0.5/H)] UFLa fL exP(-XTthc) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0.75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

UFLa = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

thc = time between harvest of vegetables and their consumption and/or storage, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS Manual Revision 14 Page 169 7.8.12 Tritium-Stored Ve etables Dose Factor (mrem/year per pCi/m )

'1-exP(-XTtsv))

RATS = 10 10 DFLTao [0 '5(0 '/H)] USafg T sv exP(-XTthc) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0. 75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

'AT decay constant for tritium, seconds 1 (Table 6.2).

tsv ~ time between harvest of stored vegetables and their consumption and/or storage, seconds.

thc = time between harvest of vegetables and their storage, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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RETS, Manual Revision 14 Pago $ 70 7.8.13 Inhalation Dose Factors (mrem/year per pCi/m )

RI j DFAj ao BRa 10 where:

DFAj ao inhalat j.on dose convers j.on factor for nuclide i, age grouP a and organ o, mrem/pCi (Table 7.7).

BR . = breathing rate for age group a, m /year (Table 6.3).

10 = conversion factor, pCi/pCi.

7.8.14 Ground Plane Dose Factors (m2-mrem/year per pCi/second)

RGi = DFGio (1/Xi) 10 8760 [1 exp(-Xitb)]

where:

DFGio = dose conversion factor for standing on contaminated ground for nuclide j. and organ o (total body and skin), mrem/hr per pCj./m2 (Table 6.6).

Xi decay constant of nuclide i, seconds 1 (Table 6.2).

106 conversion factor, pCi/pCi.

8760 = conversion factor, hours/year.

tb = time period over which the ground accumulation is evaluated, seconds (Table 6.3).

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RETS Manual Revision 14 Page 171 7.9 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected onsite.

Meteorological data for ground level releases consist of windspeed and direction measurements at 10m and temperature measurements of 10m and 45 m.

Hourly average meteorological data for the ground level portion of a split level release consist of wind speeds and directions measured at the 10m level and temperature measurements at 10m and 45m. The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.

Raw meteorological data for the elevated releases consist of windspeed and measured at 93m. Stability class D is assumed to persist during 'irections the entire period for elevated releases, except for the dose calculations described in Section 7.7 when all stability classes will be used to evaluate the elevated results.

Meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability for each release level (ground, split and elevated). The joint-frequency distributions which represent the historical meteorological data for the period January 1977 to December 1988 are given in Table 7.3.

The wind speed classes that are used are as follows:

Number Ran e m/s Mid oint (m/s)

<0.3 0.13 0.3-0.6 0.45 0.7-1.5 1.10 1.6-2.4 1.99 2.5-3.3 2.88 3.4-5.5 4.45 5.6-8.2 6.91 8.3-10.9 9.59 9 >10.9 10.95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, ..., G=7.

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RETS Manual Revision 14 Page 172 A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.3), and building wake effects. Terrain effects on dispersion are not considered except for reducing the effective height of an elevated release by the terrain height.

7.9.1 Annual Avera e Air Concentration X (pCi-year/m )

Air concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 g(2/<)1/2 fjkQip i= 106 g exp'( Xix/u ) exp( he2/2~zk2) 3 17EOS (7 16)

Ezkuj(2m/n) where:

~ joint relative frequency of occurrence of winds in windspeed class j, stability class k, expressed as a fraction.

blowing toward this exposure point,

.Qi ~ amount released of radionuclide i, Ci.

P = fraction of radionuclide remaining in plume (Figure 7.3).

Ezk vertical dispersion coefficient for stability class k a building wake adjustment, which'ncludes (ozk2 + cA/e)1/2, or = 43 ezk, whichever is smaller (for ground level releases).

where azk is the vertical dispersion coefficient for stability class k (m) (Figure 7.4);

c is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (2400 m2).

uj = midpoint value of wind speed class interval m/s ~

x = downwind distance, m.

n = number of sectors, 16.

Xi = radioactive decay coefficient of radionuclide i, s-1 2m/n = sector width at point of interest, m.

he = effective release height, m. The effective release height is calculated as described in Section 7.9.4.

106 = conversion factor, pCi per Ci.

3.17E-OS = conversion factor, years per second.

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RETS Manual Revision 14 Page 173 7.9.2 Relative Concentration X/Q (s/m )

Relative concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 (2/~)1/2 f.k J

X/Q = 7, 7, exp( he2/2ezk2) (7.17) j=l k=1 Zzt uj (2'/n) where:

= joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

vertical dispersion coefficient for stability class k which includes a building wake adjustment, azk2 + cA/e)1/2, or ~ l3 azk, whichever is smaller (for ground level releases).

where ozk is the vertical dispersion coefficient for stability class k (m) (Figure 7.4),

c is a building shape factor (c&.5),

A is the minimum building cross sectional area (2400 m2).

uj midpoint value of wind speed class interval j, m/s.

X = downwind distance, m.

n = number of sectors, 16.

2m/n sector width at point of interest, m.

he effective release height, m. The effective release height is calculated as described in Section 7.9.4.

7.9.3 Relative Dis ersion D/Q (m )

Relative deposition of nuclides at downwind locations is calculated using the following equation:

9 7 (7.18) j=l k=1 (2'/n) where:

fk = joint relative frequency of occurrence of winds in windspeed class j and stability class k> blowing toward this exposure point, expressed as a fraction.

DR = relative deposition rate, m 1 (from Figure 7.5). The choice of figures is governed by the effective release height calculation described in Section 7.9.4. A linear interpolation is used for effluent release heights that fall in between the given curves.

x = downwind distance, m.

n = number of sectors, 16.

2m/n = sector width at point of interest, m.

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RETS Manual Revision 14 Page 174 7.9.4 Effective Release Hei ht For effluents exhausted from release points that are higher than twice the height of adjacent structures (elevated releases) the effective release height is determined by the following equation, consistent with Regulatory Guide 1.111 he = hs + hpr ht <<c where:

c = downwash correction factor for low relative exit velocity,

= 3(1.5-Wo/u)d, where Wo = the vertical plume exit velocity, m/s.

u = mean wind speed at the height of the release, m/s.

d = inside diameter of the release point, m.

NOTE: If c is less than zero, it is set equal to zero.

= plume rise above the release point, m.

hpr hs ~ physical height of release point, m.

ht = maximum terrain height between release point and receptor location, m.

For effluents released from points less than the height of adjacent structures, a ground level release is assumed (he = 0) ~

For effluents released from points at the level of or above adjacent structures, but lower than elevated release points, releases are treated as follows:

Case 1 elevated if Wo/u > 5.

Case 2 ground level (he = 0) if Wo/u l.

Case 3 split level if 1 < wo/u < 5.

Under Case 3 a split level dispersion approach is implemented using a model that requires for each release point two JFDs, one for elevated releases and one for ground level releases. The summation of the elevated and ground level JFDs account for the total period of record.

Releases are considered to be elevated 100(1-Et) percent of the time and ground level 100 Et percent of the time where the entrainment coefficient, Et, is defined by Et = 2.58 1.58(Wo/u) for 1 < Wo/u < 1.5 Et = 0.3 0.06(Wo/u) for 1.5 < Wo/u < 5 1132(206)

RETS Manual Revision 14 Page 175 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA Elev.

above Dir./ plant Ground Vent Mixed Vent Elevated Vent Dist. grade x/Q D/Q x/Q D/Q x/Q D/g N.

(m) 1525 (m) 7 (s/m3) 1.91E-06

(/ )

5.77E-09 (s/m3) 3.88E-07 (1/m~)

2.19E-09 (s/m3) 4.46E-10 (1/m~)

4.99E-10 NNE 1300 4 1.06E-06 2.69E-09 1.65E-07 1.12E-09 3.99E-10 3.17E-10 NE 1250 7 7.13E-07 1.89E-09 1.35E-07 8.90E-10 1.64E-09 3.65E-10 ENE 1450 0 9.08E-07 3.15E-09 1.20E-07 9.36E-10 1.22E-09 3.37E-10 E 1375 0 9.21E-07 3.81E-09 1.50E-07 1.37E-09 8.36E-10 4.25E-10 ESE 1575 0 5.19E-07 3.09E&9 1.25E-07 1.43E-09 4.24E-10 4.78E-10 SE 5600 -6 9.61E-08 3.50E-10 4.30E-08 2.69E-10 5.15E-09 2.14E-10 SSE 2875 -6 5 ~ 20E&7 1.57E&9 9.78E-08 7.40E-10 1.13E-09 3.96E-10 S 2550 -6 1 ~ 02E-06 2. 37E&9 1.41E-07 .9 '9E-10 8.52E-10 4.97E-10 SSW 2425 -6 l. 28E-06 2.88E-09 1.74E-07 1.10E-09 6.10E-10 4.29E-10 SW 2300 -6 8.33E-07 1.71E-09 1.02E07 5.22E-10 2 '5E-10 2.21E-10 WSW 2500 -6 8.17E-07 1.21E-09 7.00E-08 2.15E-10 2 '1E-10 1.14E-10 W 2550 -6 8.51E-07 1.43E-09 6.95E-08 2.40E-10 2.63E-10 1.18E-10 WNW 3325 -6 4.14E-07 7.87E-10 1.04E-07 3.33E-10 l. 75E-09 2.50E-10 NW 2275 -6 1.90E-06 4.65E-09 3.22E-07 1.53E-09 1.83E-09 6 '7E-10 NNW 1650 -6 2.26E-06 5.42E-09 3.63E-07 2.12E-09 8.93E-10 5.54E-10 NW 8500 -6 3.04E-07 4.60E-10 9.90E-08 2.05E-10 8.93E-09 1.37E-10 NOTE: For quarterly dose calculations, doses vill also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

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RETS Manual "Revision 14 Page 176 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN Buildin Vents Ci/ r/Unit) Stack Ci/ r/Unit)

Reactor Radwaste Turbine Gland Complex Building Building Seal and

~Isoeo e Vent Vent Vent ~Off as MVP Kr-85m 6E+0 < 1 2E+0 1.66E+4 O.OE+0 Kr-85 6.3E+2 Kr-87 6E+0 < 1 9.5E+1 7.47E+2 O.OE+0 Kr-88 9E+0 1 1.02E+2 1.35E+4 O.OE+0 Kr-89 1E+0 3.4E+1 5.03E+2 4.10E+3 0.0E+0 Xe-131m 3.09E+2 O.OE+0 Xe-133m OE+0 6.0E+1 , OE+0 8.51E+2 O.OE+0 Xe-133 1.03E+2 2.94E+2 5.81E+2 9.47E+4 3.0E+2 Xe-135m 1.11E+2 6.67E+2 4.64E+2 9.17E+2 O.OE+0 Xe-135 1 73E+2 3.28E+2 6 '2E+2 5.99E+2 2.0E+2 Xe-137 7.8E+1 1.13E+2 3.86E+2 5.04E+3 O.OE+0 Xe-138 1.2E+1 2E+0 1.18E+3 3.15E+3 O.OE+0 I-131 I 5 94E-2 5.0E-3 1.56E-2 4.1E-3 8.5E-3 I-132 I 5.94E-1 5.0E-2 1.79E-1 4 '9E-2 9.73E-2 I-133 I 2.97E-1 2.5E-2 1.23E-1 3.23E-2 6.71E-2 I-134 I 1.49E+0 1.25E-1 2.67E-2 7.0E-3 1.45E-2 I-135 I 5.94E-1 5.0E-2 1.23E-l 3.23E-2 6.71E-2 I-131 0 3 16E-2 2.9E-2 6.5E-3 3.32E-2 2.74E-l I-132 0 3.16E-1 2.9E-1 7.44E-2 3.80E-1 3.14E+0 I-133 0 1.58E-1 1.45E-1 5.13E-2 2.62E-1 2.16E+0 I-134 0 7.90E-1 7.25E-1 1.11E-2 5.68E-2 4.69E-1 I-135 0 3.16E-1 2.90E-1 5.13E-2 2.61E-1 2.16E+0 Cr-51 3E-3 9E-4 1E-3 1E-4 O.OE+0 Mn-54 3E-3 5E-3 2E-3 4E-5 0.0E+0 Co-SS 2E-3 4E-4 9E-5 2E-5 O.OE+0 Fe-59 lE-4 8E-4 4E-4 2E-4 O.OE+0 Co-60 3E-2 6E-3 3E-3 1E-5 0.0E+0 Zn-65 3E-3 2E-4 4E-4 9E-5 O.OE+0 Sr-89 1E-2 3E-1 0.0E+0 Sr-90 2E-3 4E-3 O.OE+0 Nb-95 3E-4 2E-4 9E-6 8E-5 O.OE+0 Zr-95 1E-4 1E-4 SE-6 8E-5 O.OE+0 Ru-103 3E-5 1E-4 2E-4 1E-4 0.0E+0 Ag-110m 7E-6 0.0E+0 Sb-124 3E-5 3E-4 6E-5 SE-5 0.0E+0 Cs-134 5E-3 3E-4 5E>>4 2E-5 0.0E+0 Cs-136 2E-3 5E-5 1E-4 9E-8 O.OE+0 Cs-137 7E-3 4E-4 2E-3 7E-4 O.OE+0 Ba-140 4E-3 5E-4 2E-2 SE-3 0.0E+0 Ce-141 4E-4 2E-4 2E-3 2E-5 O.OE+0 Ce-144 5E-6 4E-6 O.OE+0 Ar-41 2.5K+1 OE+0 OE+0 OE+0 O.OE+0 C-14 OE+0 OE+0 OE+0 9.5E+0 O.OE+0 H-3 OE+0 9.5E+0 OE+0 OE+0 O.OE+0

Not available.

I denotes nonorganic iodine (elemental, particulate, HIO), 0 denotes organic iodine.

1132(206)

RETS Manual Revision 14 Page 177 Table 7'.3 (1 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18. 5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.0 0.0 0.010 0.026 0.281 0.122 0.005 0.0 0.444 NNE 0.0 0.0 0.001 0.009 0.038 .0.284 0.109 0.001 0.0 0.443 NE 0.0 0.0 0.001 0.007 0.024 0.075 0.015 0.0 0.0 0;122 ENE 0.0 0.0 0.001 0.003 0.006 0.004 0.0 0.0 0.0 0.014 E 0.0 0.0 0.001 0.004 0.007 0.006 0.0 0.0 0.0 0.018 ESE 0.0 0.0 0.006 0.061 0.093 0.014 0.0 0.0 0.0 0.173 SE 0.0 0.001 0.106 1.205 0.366 0.044 0.0 0.0 0.0 1.721 SSE 0.0 0.0 0.132 0.672 0.115 0.015 0.0 0.0 0.0 0.934 S 0.0 0.0 0.069 0.557 0.112 0.033 0.0 0.0 0.0 0.772 SSW 0.0 0.0 0.018 0.142 0 057 0.011 0.0 0.0 0.0 0.227 SW 0.0 0.0 0.008 0.097 0.042 0 005 0.0 0.0 0.0 0. 152 WSW 0.0 0.0 0.0 0.055 0.084 0.050 0.004 0.0 0.0 0.193 W 0.0 0.0 0.001 0.014 0.046 0.065 0.007 0.001 0.0 0.133 WNW 0.0 0.0 0.0 0.020 0.037 0.115 0.067 0.007 0.0 0.246 NW 0.0 0.0 0-0 0.005 0.032 0.191 0.144 0.004 0.0 0.375 NNW 0.0 0.0 0.0 0.007 0.012 0.107 0.102 0.019 0.0 0.245 Sub total 0.0 0.001 0.343 2.865 1 098 1.298 0.570 0.036 0.0 6.211 Total hours of valid 'stability observations 103468 Total hours of stability class A - 6379 Total hours of valid wind direction-wind speed-stability class A 6354 Total hours of valid wind direction-wind speed-stability observations - 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 6.81 mph 1132(206)

RETS Manual Revision 14 Page 178 Table 7.3 (2 of 28)

JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class B (-1.9 ( Delta-T 5 -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.0 0.002 0.021 0.072 0. 212 0.044 0.002 0.0 0.353 NNE 0.0 0.0 0.001 0.030 0.093 0. 237 0.047 0.0 0.0 0.408 NE 0.0 0.0 0.002 0.024 0.034 0.080 0.007 0.0 0.0 0;148 ENE 0.0 0.0 0.002 0.010 0.008 0.008 0.0 0.0 0.0 0.027 E 0.0 0.0 0.002 0.011 0.007 0.001 0.001 0.0 0.0 0.022 ESE 0.0 0.0 0.013 0.052 0.021 0.011 0.0 0.0 0.0 0.096 SE 0.0 0.0 0.153 . 0.445 0.053 0.015 0.0 0.0 0.0 0.666 SSE 0.0 0.0 0.130 0.216 0.023 0.012 0.0 0.0 0.0 0.381 S 0.0 0.0 0.072 0.264 0.039 0.012 0.0 0.0 0.0 0.387 SSW 0.0 0.0 0.027 0.104 0.016 0.002 0.002 0.0 0.0 0.151 SW 0.0 0.0 0.013 0.125 0.025 0.007 0.0 0.0 0.0 0.170 WSW 0.0 0.0 0.005 0.088 0.087 0.044 0.008 0.0 0.0 0.232 W 0.0 0.0 0.005 0.024 0.090 0.082 0.016 0.001 0.0 0.218 WNW 0.0 0 0 0.002 0 '44 0.075 0.164 0.071 0.018 0.0 0.374 NW 0.0 0.0 0.001 0.014 0.055 0.236 0.087 0.006 0.0 0.398 NNM 0.0 0.0 0.0 0.007 0.036 0.171 0.058 0.003 0.0 0.275 Sub total 0.0 0.0 0.430 1.478 0.734 1.292 0.340 0.329 0.0 4.304 Total hours of valid stability observations 103468 Total hours of stability class B 4424 Total hours of valid wind direction-wind speed-stability class B 4403 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 tun ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 7.04 mph 1132(206)

RETS Manual Revision 14 Page 179 Table 7.3 (3 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class C (-1.7 < Delta-T 5 -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18. 5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.0 0.011 0.055 0.122 0.231 0.030 0.002 0.0 0.451 NNE 0.0 0.0 0.008 0.062 0.115 0.202 0.027 0.0 0.0 0.414 NE 0.0 0.0 0.002 0.042 0.080 0.086 0.007 0.0 0.0 0;217 ENE , 0.0 0.0 0.004 0.021 0.011 0.011 0.0 0.0 0.0 0.046 E 0.0 0.0 0.004 0.020 0.016 0.003 0.001 0.0 0.0 0.043 ESE 0.0 0.0 0.008 0.048 0.018 0.004 0.0 0.0 0.0 0.077 SE 0.0 0.001 0.213 0.313 0.057 0.013 0.002 0.0 0.0 0.598 SSE 0+0 0.0 0.188 0.166 0.022 0.009 0.0 0.0 0.0 0.385 S 0.0 0.0 0.146 0.232 0.044 0.013 0.0 0.0 0.0 0.434 SSW 0.0 0.0 0.042 0.109 0.014 0.002 0.0 0.0 0.0 0.167 SW 0.0 0.001 0.053 0.143 0.025 0.005 0.001 0.0 0.0 0 '28 WSW 0.0 0.0 0.013 0.140 0.079 0.072 0 006 0.001 0.0 0.311 W 0.0 0.0 0.003 0.048 0.103 0.088 0.022 0.004 0.0 0.267 WNW 0.0 0 0 0.009 0.096 0.109 0.197 0.079 0 '27 0.0 0.518 NW 0.0 0.0 0.002 0.054 0.108 0.211 0.067 0.004 0.001 0.447 NNW 0.0 0.0 0.003 0.016 0.058 0.182 0.055 0 '02 0.0 0.315 Sub total 0.0 0.002 0 707 1.562 0.980 1.328 0.297 0.040 0.001 4.918 Total hours of valid stability observations 103468 Total hours of stability class C 5065 Total hours of valid wind direction-wind speed-stability class C 5031 Total hours of valid wind direction>>wind speed-stability observations 102303 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 6.67 mph 1132(206)

RETS Manual Revision 14 Page .180 Table 7.3 (4 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class D (-1.5 < Delta-T.~ -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12. 5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.016 0. 212 0.471 0.584 1.151 0.368 0.029 0.001 2.832 NNE 0.0 0.013 0.227 0.519 0.647 , 1.156 0.190 0.009 0.0 2.761 NE 0.0 0.014 0.195 0.429 0.446 0.461 0.022 0.0 0.0 1'. 566 ENE 0.001 0.015 0.247 0.346 0.185 0.106 0.004 0.0 0.0 0.903 E 0.001 0.010 0.264 0.435 0.250 0.125 0.008 0.0 0.0 1.092 ESE 0.001 0.013 0.258 0.437 0.241 0.078 0.001 0.0 0.0 1.029 SE 0.003 0.051 1.498 1.203 0.648 0.294 0.005 0.0 0.0 3.702 SSE 0.003 0.031 1.300 0.823 0.228 0.105 0.004 0.0 0.0 2.493 S 0.002 0.029 1.132 1.031 0.290 0.152 0 016 0.001 0.0 2.653 SSW 0.001 0.030 0.624 0.421 0.097 0.053 0.002 0.0 0.0 1.228 SW 0.001 0.018 0.370 0.339 0.065 0.027 0.003 0.001 0.0 0.825 WSW 0.001 0.015 0.456 0.767 0.380 0.331 0.056 0.001 0.0 2.007 W 0.0 0.006 0.220 0.644 0.697 0.651 0.138 0.016 0 0 2.372 WNW 0.0 0.007 0.140 0,444 0.518 1.008 0.637 0.152 0.009 2.914 NW 0.0 0.008 0.090 0.316 0.436 0.815 0.617 0.093 0.011 2.385 NNW 0.0 0.005 0.134 0.363 0.480 1.196 0 568 0.033 0.001 2.780 Sub total 0.015 0.279 7.365 8.989 6.192 7.710 2.636 0.334 0.022 33.543 Total hours of valid stability observations 103468 Total hours of stability class D 34636 Total hours of valid wind direction-wind speed-stability class D 34315 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 6.51 mph 1132(206)

0 RETS. Manual Revision 14 Page 181 Table 7.3 (5 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class E (-0.5 ( Delta-T ~ -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5>>

Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 24.5 Total N 0.005 0.075 0.430 0.529 0 '04 0.371 0.062 0.003 0.0 1.879 NNE 0.006 0.084 0.506 0.580 0.497 .0.413 0.031 0.002 0.0 2.119 NE 0.006 0.113 0.494 0.491 0.369 0.193 0.009 0.0 0.0 1;674 ENE 0.007 0.109 0.642 0.417 0.160 0.037 0.005 0.001 0.0 1.380 E 0.008 0.071 0.744 0.677 0.174 0.065 0.004 0.0 0.0 1.744 ESE 0.009 0.099 0.821 0.772 0.350 0.121 0.002 0.0 0.0 2. 174.

SE 0.022 0.268 1.942 1 ~ 323 0.679 0.328 0.017 0.0 0.0 4.579 SSE 0.013 0.197 1.120 0.695 0.367 0.251 0.030 0.001 0.0 2. 675 S 0.012 0.161 1.016 0.688 0 '94 0.559 0.084 0.003 0.0 3.016 SSW 0.007 0.114 0.547 0.221 0.098 0.101 0.005 0.0 0.0 1.093 SW 0.004 0.084 0.292 0.082 0.023 0.013 0.0 0.0 0.0 0.498 WSW 0.007 0.060 0.641 0.514 0.109 0.098 0.019 0.0 0.0 1.448 W 0.005 0.044 0.463 0.676 0.299 0.152 0.016 0.0 0.0 1.656 WNW 0.002 0.025 0.168 0.153 0.133 0.158 0.053 0.004 0 0 0.697 NW 0.002 0.037 0.183 0.259 0.176 0.271 0.080 0 006 0.0 1.014 NNW 0.004 0.060 0.392 0.508 0.459 0.530 0.085 0.004 0.001 2.044 Sub total 0.119 1.603 10.402 8 586 4.791 3.663 0.500 0.023 0.001 29.689 Total hours of valid stability observations 103468 Total hours of stability class E 30806 Total hours of valid wind direction-wind speed-stability class E 30373 Total hours of valid wind direction-wind speed-stability observations - 102303 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 4.61 mph 1132(206)

RETS. Manual Revision 14 Page 182 Table 7.3 (6 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class F (1.5 ( Delta-T 5 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.012 0.113 0.450 0 '49 0.240 0.056 0.0 0.0 0.0 1.319 NNE 0.013 0.144 0.499 0.572 0.324 .0.094 0.0 0.0 0.0 1.646 NE 0.009 0.114 0.334 0.238 0.122 0.016 0.0 0.0 0.0 0;833 ENE 0.014 0.121 0.564 0.301 0.038 0.004 0.0 0.0 0.0 1.042 E 0.018 0.052 0.831 0.499 0.014 0.0 0.0 0.0 0.0 1.413 ESE 0.012 0.071 0.536 0.119 0.006 0.004 0.0 0.0 0.0 0.749 SE 0.025 0.209 1.021 0.359 0.146 0.066 0.003 0.001 0.0 1.831 SSE 0.014 0.123 0.573 0.309 0.173 0.184 0.018 0.002 0.0 1.395 S 0.008 0.077 0.315 0.218 0.224 0.223 0.013 0.001 0.0 1.078 SSW 0.003 0.052 0.108 0.027 0.008 0.007 0.0 0.0 0.0 0.205 SW 0.003 0.030 0.110 0.014 0.003 0.001 0.0 0.0 0.0 0.161 WSW 0.003 0.027 0.109 0.038 0.001 0.002 0.0 0.0 0.0 0.181 W 0.003 0.026 0.098 0.062 '.006 0.003 0.0 0.0 0.0 0.197 WNW 0.002 0.028 0.080 0.023 0.007 0.005 0.0 0.0 0.0 0.146 NW 0.003 0.033 0.109 0.042 0.022 0.009 0.0 0.0 0.0 0.218 NNW 0.008 0.072 0.302 0.276 0.164 0.044 0.0 '.0 0.0 0.866 Sub total 0.151 1.295 6.040 3.544 1.497 0.716 0.033 0 004 0.0 '3.280 Total hours of valid stability observations 103468 Total hours of stability class F 13774 Total hours of valid wind direction-wind speed-stability class F 13586 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 3.60 mph 1132(206)

RETS Manual Revision 14 Page 183 Table 7.3 (7 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class G (Delta-T ) 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 WIND Dir Calm 0.6-1.4 1.5-3.4 3.5-5.4

'.5-Wind Speed 7.4 (mph) 7.5-12.4 12.5-18.4 18.5-24.4 Total N 0.023 0.178 0.699 0.277 0.043 0.002 0.0 0.0 0.0 1.221 NNE 0.025 0.190 0. 752 0.550 0.166 .0.012 0.0 0.0 0.0 1.694 NE 0.013 0.118 0.369 0.073 0.021 0.001 0.0 0.0 0.0 0;594 ENE 0.015 0.084 0.492 0.168 0.013 0.001 0.0 0.0 0.0 0.773 E 0.013 0.029 0.471 0.280 0.001 0.0 0.0 0.0 0.0 0.794 ESE 0.004 0.020 0.121 0.005 0.0 0.0 0.0 0.0 0.0 0.149 SE 0.013 0.106 0.373 0.069 0.047 0.010 0.0 0.0 0.0 0.618 SSE 0.015 0.095 0.467 0.326 0.120 0.052 0.0 0.0 0.0 1 ~ 075 S 0.005 0.068 0.111 0.128 0.065 0.029 0.0 0.0 0.0 0.407 SSW 0.002 0.036 0.034 0.002 0.0 0 0 0.0 0.0 0.0 0.074 SW 0.004 0.025 0.015 0.003 0.0 0.0 0.0 0.0 0.0 0 '44 WSW 0.001 0.012 0.016 0.002 0.0 0.0 0.0 0.0 0.0 0.030 W 0.001 0.012 0.019 0.003 0.0 0.0 0.0 0.0 0.0 0.034 WNW 0.001 0.020 0.028 0.001 0.0 0.0 0.0 0.0 0.0 0.050 NW 0.003 0.039 0.061 0.003 0.0 0.0 0.0 0.0 0.0 0.105 NNW 0.007 0.086 0.200 0.075 0.022 0 001 0.0 0.0 0.0 0 '92 Sub total 0.140 1.117 4.228 1.966 0.?498 0.108 0.0 0.0 0.0 8.055 Total hours of valid stability observations 103468 Total hours of stability class G 8384 Total hours of valid wind direction-wind speed-stability class G 8241 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 2.95 mph 1132(206)

RETS, Manual Revision 14 Page 184 Table 7.3 (8 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0. 6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.0 ,0. 0 0.0 0.0 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0;0 ENE 0.0 0 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0~0 0 0 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.001 SSE 0.0 0.0 0.002 0.002 0.0 0.0 0.001 0.0 0.0 0.005 S 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSW 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 SW 0.0 0.0 0.0 0.002 0.003 0.002 0.002 0.0 0.0 0.009 WSW 0.0 0.0 0.002 0.001 0.0 0.0 0.002 0.0 0.001 0.006 W 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.001 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 Sub total 0.0 0.0 0.005 0.006 0.004 0.004 0.006 0.0 0.001 0.026 Total hours of valid stability observations 103166 Total hours of stability class A - 27 Total hours of valid wind direction-wind speed-stability class A 26 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 95.63 meter level Mean wind speed = 8.66 mph e

1132(206)

RETS Manual Revision 14 Page 185 Table 7.3 (9 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class B (-1.9 < Delta-T 5 -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 ~24. 5 . To tal N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.001 0.0 0.001 0.0 0.0 0.0 0.002 NE 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.001 0.0 0.0 0.002 0.0 0.0 0.0 0.003 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.001 0.003 0.001 0.005 0.004 0.001 0.0 0.015 SE 0.0 0.0 0.008 0.007 0.002 0.002 0.001 0.0 0.0 0.020 SSE 0.0 ~ 0.0 0.008 0.005 0.002 0.0 0.0 0.0 0.0 0.015 S 0.0 0.0 0.001 0.002 0.002 0.0 0.0 0.0 0.0 0.005 SSW 0.0 0.0 0 ~ 001 0.005 0.001 0.004 0.0 0.0 0.0 0.011 SW 0.0 0.0 0.003 0.016 0.010 0.013 0.007 0.002 0.0 0.050 WSW 0.0 0.0 0.002 0.009 0.004 0.008 0.003 0.0 0.002 0.028 W 0.0 0.0 0.0 0.0 0.004 0.008 0.013 0.004 0.001 0.029 WNW 0.0 0.0 0.0 0.0 0.002 0 '02 0.001 0.001 0.0 0.006 NW 0.0 0.0 0.0 0.0 0.000 0.001 0.0 0.0 0.0 0.001 NNW 0.0 0.0 0.0 0.0 0.000 0.0 0.0 0.0 0.0 0.0 Sub total 0.0 0.0 0.025 0.048 0.028 0.045 0.028 0.008 0.003 0.185 Total hours of valid stability observations 103166 Total hours of stability class B 190 Total hours of valid wind direction-wind speed-stability class B 188 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 8.57 mph 1132(206)

RETS Manual Revision 14 Page 186 Table 7.3 (10 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class C (-1.7 ( Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6>> 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24. 5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.002 NNE 0.0 0.0 0.0 0.0 0.002 0.0 0.002 0.001 0.0 0.005 NE 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.0 0;003 ENE 0.0 0.0 0.001 0.001 0.0 0.003 0.004 0.0 0.0 0.009 E 0.0 0.0 0.0 0.002 0.002 0.003 0.0 0.0 0 ~ 001 0.008 ESE 0.0 0.0 0.003 0.009 0.008 0.020 0.013 0.003 0.001 0.056 SE 0.0 0.0 0.018 0.056 0.022 0.015 0.004 0.0 0.0 0.114 SSE 0.0 0.001 0.018 0.027 0.010 0.005 0.0 0.0 0.0 0.060 S 0.0 0.0 0.011 0.013 0.007 0.002 0.0 0.0 0.0 0.032 SSW 0.0 0.0 0.010 0.008 0.004 0 F 011 0.002 0.0 0.0 0.034 SW 0.0 0.0 0.019 0.045 0.028 0.038 0.019 0.003 0.0 0.152 WSW 0.0 0.0 0.010 0.037 0.033 0.038 0.021 0.005 0.001 0.145 W 0.0 0.0 0.002 0.014 0.022 0.058 0.034 0.011 0.014 0.154 WNW 0.0 0.0 0.002 0.0 0.011 0.035 0.031 0.010 0.005 0.094 NW 0.0 0.0 0.0 0.001 0.001 0.001 0.017 0.001 0.001 0.022 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.002 Sub total 0.0 0.001 0.092 0.212 0.150 0.232 0 '48 0.034 0.023 0.893 Total hours of valid stability observations - 103166 Total hours of stability class C 916 Total hours of valid wind direction-wind speed-stability class C 909 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 8.90 mph 1132(206)

RETS, Manual Revision 14 Page $ 87 Table 7.3 (11 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class D (-1.5 ( Delta-T 5 0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24. 5 To tal N 0.001 0.010 0.100 0. 270 0.468 1.721 1.698 0.468 0.062 4.797 NNE 0.001 0.020 0.098 0. 258 0.455 . 1.685 1.334 0.211 0.020 4.081 NE 0.0 0.010 0.070 0. 203 0.364 0.952 0.438 0.035 0.006 2;079 ENE 0.001 0.009 0.088 0.194 0.221 0.396 0.134 0.023 0.009 1.074 E 0.001 0.009 0.122 0. 202 0.206 0.339 0.190 0.042 0.013 1.123 ESE 0.001 0.009 0.173 0.336 0.374 0.844 0.691 0.239 0.058 2.724 SE 0.001 0.015 0.265 0.729 0.712 1.364 1.288 0.804 0.337 5.516 SSE 0.002 0.018 0.319 0.581 0.568 1.442 1.293 0.551 0.249 5.021 S 0.001 0.009 0.277 0.491 0.463 1.321 1.336 0-738 0.300 4.936 SSW 0.001 0.015 0.222 0.348 0.344 0.935 0.914 0.423 0.166 3.368 SW 0.001 0.013 0.254 0.453 0.340 0.760 0.712 0.219 0.091 2.844 WSW 0.001 0.009 0.194 0.556 0.397 0 641 0.541 0.246 0.093 2.679 W 0.001 0.008 0.129 0.525 0.630 1.103 0.759 0-316 0.173 3.643 WNW 0.001 0.004 0.108 0.262 0.497 1.481 1.124 0.608 0.260 4.345 NW 0.001 0.012 0.121 0.298 0.458 1.244 1.380 0.842 0.219 4.573 NNW 0.001 0.010 0.098 0.201 0.312 1.184 1.467 0.534 0.117 3.924 SLib total 0.015 0.177 2.639 5.907 6 808 17.412 15.297 6.299 2.172 56.727 Total hours of valid stability observations 103166 Total hours of stability class D - 58662 Total hours of valid wind direction-wind speed-stability class D 57750 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.90 mph 1132(206)

RETS Manual Revision 14 Page 188 Table 7.3 (12 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class E (0.5 < Delta-T < 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

W.IND 0.6- 1.5- 3.5- 5.5- 7.5- 12. 5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 Total N 0.001 0.013 0.066 0.099 0.149 0.537 0.735 0.139 0.005 1. 744 NNE 0.001 0.007 0.061 0.080 0.134 ,

0.614 0.836 0.202 0.002 1.936 NE 0.002 0.011 0.075 0.107 0.161 0.640 0.686 0.176 0.001 1;858 ENE 0.001 0.006 0.063 0.103 0.122 0 '43 0.328 0.071 0.005 1.142 E 0.002 0.010 0.097 0.162 0.199 0.461 0.173 0.026 0.003 1.133 ESE 0.003 0.014 0.129 0.179 0.252 0.671 0.696 0.173 0.027 2.143 SE 0.003 0.009 0.152 0.381 0.429 1.259 1.286 0.609 0.282 4.411 SSE 0.003 0.019 0.150 0.369 0.465 1.114 1.080 0.550 0.256 4.006 S 0.003 0.015 0.143 0.293 0.365 0.927 0.975 0.369 0.108 3.199 SSW 0.002 0.014 0.116 0.155 0.188 0.595 0.712 0.215 0.024 2.021 SW 0.002 0.008 0.083 0.139 0.193 0.606 0.631 0.117 0.022 1.799 WSW 0.002 0.006 0.086 0.135 0.169 0.493 0.359 0.047 0.014 1.310 W 0.001 0.007 0.071 0.132 0.190 0.469 0.271 0.041 0.003 1.184 WNW 0.002 0.013 0.079 0.143 0.184 0.474 0.206 0.033 0.002 1 ~ 136 NW 0.002 0.012 0.084 0.159 0.162 0.378 0.282 0.089 0.004 1.173 NNW 0.002 0.009 0.079 0.099 0.165 0 '72 0.443 0.092 0.001 1.202 Sub total 0 032 0.170 1.533 2.736 3.466 10.055 9.698 2.950 0.757 31.398 Total hours of valid stability observations 103166 Total hours of stability class E 32314 Total hours of valid wind direction-wind speed-stability class E 31964 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.74 mph 1132(206)

RETS. Manual Revision 14 Page 189 Table 7.3 (13 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class F (1.5 < Delta-T ~ 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.001 0.004 0.010 0.026 0.032 0.099 0.181 0.063 0.0 0.415 NNE 0.001 0.003 0.014 0.024 0.019 .0.129 0.342 0.181 0.0 0.711 NE 0.001 0.001 0.024 0.029 0.033 0.173 0.346 0.215 0.001 0;823 ENE 0.001 0.002 0.015 0.031 0.045 0.188 0.277 0.097 0.0 0.656 E 0.002 0.003 0.034 0.051 0.086 0.220 0.116 0.003 0.001 0.516 ESE 0.002 0.003 0.038 0.073 0.121 0.341 0.274 0.030 0.001 0.883 SE 0.001 0.006 0.027 0.059 0.121 0.353 0.357 0.031 0.004 0.958 SSE 0.001 0.0 0.028 0.045 0.078 0.287 0.225 0.022 0.001 0.687 S 0 001 0.003 0.030 0.051 0.075 0.194 0.225 0.028 0.0 0.607 SSW 0.001 0.001 0.021 0.042 0.052 0.168 0.212 0.062 0.0 0.559 SW 0.001 0.004 0.026 0.029 0.046 0.168 0.191 0.033 0.0 0.498 WSW 0.001 0.002 0.016 0.031 0.050 0.139 0.144 0.002 0.0 0.386 W 0.001 0.009 0.012 0.047 0.036 0.096 0.042 0.002 0.0 0.245 WNW 0.001 0.002 0.013 0.033 0.038 0.070 0.033 0.0 0.0 0;190 NW 0.001 0.005 0.024 0.039 0.030 0.052 0.016 0.003 '.0 0.170 NNW 0.001 0.004 0.029 0.021 0.025 0.057 0.053 0.018 0.0 0.208 Sub total 0.017 0.051 0.360 0.633 0.888 2.733 3.033 0.791 0.008 8.513 Total hours of valid stability observations 10.166 Total hours of stability class F - 8738 Total hours of valid wind direction-wind speed-stability class F - 8666 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11. 66 mph 1132(206)

RETS, Manual Revision 14 Page 190 Table 7.3 (14 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0. 005 0.004 0.003 0.004 0.021 0.038 0.006 0.0 0.081 NNE 0.0 0.0 0.002 0.002 0.005 0.041 0.087 0.029 0.002 0.169 NE'NE 0.0 0.001 0.010 0.009 0.007 0.062 0.119 0.061 0.003 0;271 0.0 0.003 0.006 0.009 0.009 0.060 0.088 0.020 0.001 0.196 E 0.0 0.002 0.011 0.007 0.018 0.089 0.035 0.004 0.0 0.166 ESE 0.0 0.0 0 '09 0.024 0.028 0.062 0.055 0.005 0.0 0.183 SE 0.0 0.002 0.013 0.026 0.043 0.118 0.045 0.006 0.0 0.253 SSE 0.0 0.001 0.010 0.020 0.027 0.114 0.082 0.001 0.0 0.254 S 0.0 0.0 0.010 0.019 0.037 0.077 0.038 0.001 0.0 0.182 SSW 0.0 0.0 0.006 0.015 0.021 0.049 0.040 0.005 0.0 0.136 SW 0.0 0.001 0.011 0.013 0.028 0.028 0.052 0.014 0.0 0.148 WSW 0.0 0.001 0.009 0.013 0.008 0.020 0.024 0.002 0.0 0.076 W 0.0 0.0 0.006 0.011 0.008 0.005 0.004 0.0 0.0 0.034 WNW 0.0 0.001 0.013 0.009 0.008 0.005 0.001 0.0 0.0 0.037 NW 0.0 0.001 0.010 0.012 0.009 0.002 0.0 0.0 0.0 0.034 NNW 0.0 0.003 0.008 0.009 0.006 0.006 0.009 0.001 0.0 0.042 Sub total 0.0 0.021 0.136 0.197 0.265 0.758 0.718 0.154 0.006 2.259 Total hours of valid stability observations 103166 Total hours of stability class G 2319 Total hours of valid wind direction-wind speed-stability class G 2300 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta<<T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 10.93 mph 1132(206)

RETS Manual Revision 14 Page 191 Table 7.3 (15 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12. 5- 18.5-Dir Calm 1.4 3.4 54 74 124 18. 4 24.4 -24.5 Total N 0.0 0.0 0.0 0.0 0.002 0.045 0.028 0.004 0.0 0.078 NNE 0.0 0.0 0.0 0.0 0.003 .0.044 0.025 0.001 0.0 0.073 NE 0.0 0.0 0.0 0.0 0.002 0.011 0.003 0.0 0.0 0;016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.001 E 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 ESE 0.0 0.0 0.0 0.003 0.011 0.002 0.0 0.0 0.0 0.017 SE 0.0 0.0 0.001 0.053 0.044 0.009 0.0 0.0 0.0 0.107 SSE 0.0 0.0 0.004 0.046 0.021 0.008 0.0 0.0 0.0 0.078 S 0.0 0.0 0.002 0.033 0.021 0.012 0.0 0.0 0.0 0.068 SSW 0.0 0.0 0.0 0.010 0.009 0.004 0.0 0.0 0.0 0.023 SW 0.0 0.0 0.0 0.003 0.003 0 ~ 001 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.0 0.003 0.010 0.010 0.002 0.0 0 0 0 '25 W 0.0 0.0 0.0 0.0 0.004 0.010 0.002 0.001 0.0 0.016 WNW 0.0 0.0 0.0 0.0 0.003 0.017 0.016 0.005 0.0 0.040 NW 0.0 0.0 0.0 0.0 0.002 0.028 0.035 0.002 0.0 0.067 NNW 0 0 0.0 0.0. 0.0 0.001 0.017 0.027 0.016 0.0 0.060 Sub total 0.0 0.0 0.008 0.151 0.137 0.218 0.138 0.028 0.0 0.680

, Total hours of valid observations 101961 Total hours of ground level release - 10832.031 Total hours of stability class A 718.45 Total hours of ground level stability class A 693.58 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 192 Table 7.3 (16 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class B (-1.9 ( Delta-T < -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6<< 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 ~24.5 Total N 0.0 0.0 0.0 0.0 0.006 0.030 0.010 0.002 0.0 0.048 NNE 0.0 0.0 0.0 0.0 0.007 . 0.035 0.011 0.0 0.0 0.053 NE 0.0 0.0 0.0 0.0 0.003 0.011 0.002 . 0.0 0.0 0.016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 E 0.0 0.0 0.0 0.0 0.001 0.0 0.001 0.0 0.0 0.002 ESE 0.0 0.0 0.0 0.002 0.002 0.002 0.0 0.0 0.0 0.006 SE 0.0 0.0 0.001 0.014 0.007 0.003 0.0 0.0 0.0 0.025 SSE 0.0 0.0 0.001 0.012 0.006 0.008 0.0 0.0 0.0 0.026 S 0.0 0.0 0.001 0.012 0.008 0.004 0.0 0.0 ~ 0.0 0.025 SSW 0.0 0.0 0.0 0.006 0.003 0.001 0.002 0.0 0.0 0.012 SW 0.0 0.0 0.0 '.002 0.002 0.002 0.0 0.0 0.0 0.005 WSW 0.0 0.0 0.0 0.004 0.009 0.009 0.003 0.0 0.0 0.024 W 0.0 0.0 0.0 0.0 0.007 0.011 0.006 0.001 0.0 0.025 WNW 0.0 0.0 0.0 0.0 0.005 0.023 0.018 0.013 0.0 0.058 NW 0.0 0.0 0.0 0.0 0.004 0.033 0.021 0.004 0.0 0.062 NNW 0.0 0.0 0.0 0.0 0.002 0.026 0.015 0.002 0.0 0.045 Sub total 0.0 0.0 0.003 0.052 0.072 0.198 0.088 0 022 0.0 0.435 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class B 618.82 Total hours of ground level stability class B 443.89 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 193 Table 7.3 (17 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class C (-1.7 < Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12. 5- 18. 5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 Total N 0.0 0.0 0.0 0.0 0.009 0.033 0.007 0.001 0.0 0.050 NNE 0.0 0.0 0.0 0.001 0.008 , 0.028 0.006 0.0 0.0 0.043 NE 0.0 0.0 0.0 0.0 0.006 0.011 0.001 0.0 0.0 0;019 ENE 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.0 0.003 E 0.0 0.0 0.0 0.0 0.001 0.001 0.001 0.0 0.0 0.003 ESE 0.0 0.0 0.0 0.002 0.002 0.001 0.0 0.0 0.0 0.005 SE 0.0 0.0 0.002 0.012 0.009 0.004 0.001 0.0 0.0 0.028 SSE 0.0 0.0 0.003 0.007 0.005 0.006 0.0 0.0 0.0 0.021 S 0.0 0.0 0.001 0.012 0.009 0.004 0.0 0.0 0.0 0.026 SSW 0.0 0.0 0.0 0.007 0.002 0.001 0.0 0.0 0.0 0.011 SW 0.0 0.0 0.0 0.002 0.002 0.001 0 001 0.0 0.0 0.006 WSW 0.0 0.0 0.0 0.004 0.009 0.013 0.003 0.001 0.0 0.030 W 0.0 0.0 0.0 0.0 0.008 0.013 0.008 0.004 0.0 0.032 WNW 0.0 0.0 0.0 0.0 0.006 0.028 0.018 0.020 0.0 0.072 NW 0.0 0.0 0.0 0.0 0.007 0.029 0.017 0.002 0.001 0.056 NNW 0.0 0.0 0.0 0.0 0.004 0 026 0.014 0.002 0.0 0.046 Sub total 0.0 0.0 0.006 0.049 0.089 0.201 0.076 0.030 0.001 0 452 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class C 1307.02 Total hours of ground level stability class C 460.54

,Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 194 Table 7.3 (18 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Release Ground Level Portion Stability Class D (-1.5 ( Delta-T 5 -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24 5 Total N 0.0 0.0 0.0 0.009 0.050 0.182 0.098 0.023 0.001 0.362 NNE 0.0 0.0 0.0 0.010 0.057 .0.178. 0.046 0.007 0.0 0. 297 NE 0.0 0.0 0.0 0.008 0.038 0.068 0.005 0.0 0.0 0;119 ENE 0.0 0.0 0.0 0.011 0.018 0.016 0.001 0.0 0.0 0.047 E 0.0 0.0 0.001 0.022 0.031 0.022 0.003 0.0 0.0 0.078 ESE 0.0 0~0 0.002 0.028 0.032 0.014 0.0 0.0 0.0 0.075 SE 0.0 0 ~0 0.027 0 '17 0.114 0.082 0.004 0.0 0.0 0.344 SSE 0.0 0.0 0.035 0.091 0.052 0.061 0.004 0.0 0.0 0.244 S 0.0 0.0 0.034 0.097 0.059 0.064 0.014 0.001 0.0 0.269 SSW 0.0 0.0 0.014 0.042 0.018 0.026 0.002 0.0 0.0 0.102 SW 0.0 0.0 0.003 0.010 0.005 0.007 0.002 0.001 0.0 0.028 WSW 0.0 0.0 0.004 0.036 0.049 0.065 0.028 0.001 0.0 0.183 W 0.0 0.0 0.001 0.023 0.070 0.103 0.053 0.014 0.0 0.263 WNW 0.0 0.0 0.0 0.003 0.036 0.154 0.164 0.107 0.009 0.472 0.0 0.0 0.003 0.033 0.126 0.173 0.073 0.011 0.418 NNW 0.0 0.0 0.0 0.007 0.041 0.196 0.157 0 '27 0.001 0.428 Sub total 0.0 0.0 0.122 0.517 0.701 1.363 0.753 0.253 0.022 3.732 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class D 54573.199 Total hours of ground level stability class D 3804.72 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Effluent velocity 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 195 Table 7.3 (19 of 28)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class E (0.5 < Delta-T 5 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0.0 0.005 0.040 0.054 0.064 0.021 0.002 0.0 0.185 NNE 0.0 0.0 0.008 0.048 0.068 0.071 0.010 0.001 0.0 0.206 NE 0.0 0.001 0.008 0.044 0.051 0.033 0.003 0.0 0.0 0.140 ENE 0.0 0.001 0.014 0.037 0.023 0.007 0.003 0.001 0.0 0.087 E 0.0 0.0 0.015 0.060 0.024 0.012 0.001 0.0 0.0 0.113 ESE 0.0 0.001 0.021 0.068 0.049 0.022 0.001 0.0 0.0 0.162 SE 0.0 0.004 0.094 0.167 0.122 0.107 0.014 0.0 0.0 0.507 SSE 0.0 0.002 0.070 O.ill 0.106 0.164 0.030 0.001 0.0 0.485 S 0.0 0.003 0.068 0.100 0.112 0.281 0.077 0.003 0.0 0 '43 SSW 0.0 0.001 0.027 0.033 0.020 0.050 0.005 0.0 0.0 0.135 SW 0.0 0.0 0.007 0.008 0.004 0.006 0.0 0.0 0.0 0.025 WSW 0.0 0.0 0.016 0.043 0.016 0.023 0.013 0.0 0.0 0.111 W 0.0 0.0 0.009 0.049 0.038 0.027 0.006 0.0 0.0 0.129 WNW 0' 0.0 0.001 0.008 0.015 0.026 0.015 0.003 0.0 0.069 NW 0.0 0.0 0.001 0.015 0.021 0.046 0.025 0.005 0.0 0.112 NNW 0.0 0.0 0.004 0.035 0.059 0.092 0.024 0.004 0.001 0.219 Sub total 0.0 0.014 0.368 0.865 0.784 1.029 0.248 0.020 0.001 3.328 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class E 32478.371 Total hours of ground level stability class E 3393.06 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 196 Table 7.3 (20 of 28)

SPLINT JOINT PERCENTAGE 1'RE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class F (1.5 ( Delta-T < 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18. 5-Dir Calm 1 4 3 4 5.4 7.4 12.4 18.4 24.4 Total N 0.0 0.0 0.014 0.051 0.038 0.010 0.0 0.0 0.0 0.112 NNE 0.0 0.001 0.016 0.068 0.051 0.017 0.0 0.0 0.0 0.152 NE 0.0 0.002 0.012 0.030 0.020 0.003 0.0 0.0 0.0 0.066 ENE 0.0 0.004 0.018 0.031 0.006 0.001 0.0 0.0 0.0 0.061 E 0.0 0.001 0.017 0.034 0.002 0.0 0.0 0.0 0.0 0.054 ESE 0.0 0.002 0.019 0.010 0.001 0.001 0.0 0.0 0.0 0.032 SE 0.0 0.005 0.064 0.052 0.030 0.036 0.002 0.001 0.0 0.191 SSE 0.0 0.005 0.050 0.056 0.060 0.138 0.017 0.002 0.0 0.328 S 0.0 0.003 0.028 0.035 0.054 0.121 0.013 0.001 0.0 0.255 SSW 0.0 0.002 0.007 0.005 0.002 0.003 0.0 0.0 0.0 0.019 SW 0.0 0.001 0.004 0.001 0.001 0.0 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.004 0.003 0.0 0.0 0.0 0.0 0.0 0.008 W 0.0 0.0 0.003 0.006 0.001 0.001 0.0 0.0 0.0 0.010 WNW 0.0 0.0 0.002 0.002 0.001 0.001 0.0 0.0 0.0 0.006

~ oo Sub o.o 0.0 0.0 0.002 0.007 0.004 0.031 0.003 0.025 0 '02 0.008 0.0 0.0 0.0 0.0 0.0 0.0 0.010 0.071 total 0.0 0.027 0.265 0.418 0.296 0.340 0.032 0.004 0.0 1.383 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class F 9482 Total hours of ground level stability class F 1410.51 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 197 Table 7.3 (21 of 28)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0.0 0.020 0.034 0.007 0.0 0.0 0.0 0.0 0.062 NNE 0.0 0.001 0.022 0.071 0.028 0.002 0.0 0.0 0.0 0. 123 NE 0.0 0.001 0.009 0. 010 0.004 0.0 0.0 0.0 0.0 0.023 ENE 0.0 0.002 0.008 0.011 0.002 0.0 0.0 0.0 0.0 0.024 E 0.0 0.0 0.009 0.007 0.0 0.0 0.0 0.0 0.0 0.016 ESE 0.0 0.0 0.006 0.0 0.0 0.0 0.0 0.0 0.0 0.006 SE 0.0 0.004 0.027 0.012 0.013 0.007 0.0 0.0 0.0 0.062 SSE 0.0 0.003 0.053 0.065 0.044 0.041 0.0 0.0 0.0 0.206 S 0.0 0.002 0.011 0.022 0.016 0.016 0.0 0.0 0.0 0.067 SSW 0.0 0.001 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.002 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.001 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.001 W 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.001 WNW 0 ' 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.001 NW 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.002 NNW 0.0 0.0 0.005 0.009 0.003 0.0 0.0 0.0 0.0 0.017 Sub total 0.0 0.014 0.174 0.242 0.116 0.066 0.0 0.0 0.0 0.614 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class G - 2783.14 i Total hours of ground level stability class G 625.73 Meteorological facility: located 1.3 hn ESE of BFN Stability'ased on Delta-T between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Effluent velocity = 12.60 m/s t

1132(206)

RETS Manual Revision 14 Page 198 Table 7.3 (22 of 28)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24. 5 To tal N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ~ 0.0 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSE 0.0 0.0 0.003 0.002 0.0 0.0 0.001 0.0 0.0 0.006 S 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.002 SSW 0.0 0.0 0.002 0.001 0.002 0.0 0.0 0.0 0.0 0.005 SW 0.0 0.0 0.0 0.003 0.002 0.002 0.001 0.0 0.0 0.007 0.0 0.0 0.0 0.0 0.0 0.0 WSW W

WNW

'.0 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.001 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.004 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 Sub total 0.0 0.0 0.007 0.007 0.005 0.004 0.002 0.0 0.0 0.024 Total hours of valid observations 101961 Total hours of elevated releases 91128.969 Total hours of stability class A - 718.45 Total hours of elevated stability class A 24.87 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed measured at 45.67 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 199 Table 7.3 (23 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class B (-1.9 c Delta-T 5 -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.001 0.0 0.2 0.0 0.0 0.0 0.001 NE 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.001 0.002 0.004 0.001 0.0 0.0 0.008 SE 0.0 0.0 0.010 0.008 0.0 0.004 0.0 0.0 0.0 0.021 SSE 0.0 0.0 0.007 0.009 0.001 0.0 0.0 0.0 0.0 0.017 S 0.0 0.0 0.005 0.008 0.004 0.0 0.0 0.0 0.0 0.017 SSW 0.0 0.0 0.004 0.010 0.005 0.009 0.001 0.0 0.0 0.028 SW 0.0 0.0 0.0 0.022 0.007 0.007 0.001 0.0 0.0 0.036 WSW 0.0 0.0 0.0 0.002 0.006 0.009 0 F 001 0.0 0.0 0.018 W 0.0 0.0 0.0 0.0 0.006 0.007 0.006 0.002 0.0 0.020 WNW 0.0 0.0 0 0 0.001 0.0 0.002 0.002 0.0 0.0 0.004 NW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Sub total 0.0 0.0 0.025 0.062 0.029 0.042 0.010 0.002 0.0 0.172 Total hours of valid observations 101961 Total hours of elevated releases 91128.969 Total hours of stability class B 618.82 Total hours of elevated stability class B 174.930 Meteorological facility: located 1;3 km ESE of BFN Stability'based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed measured at 45.67 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 200 Table 7.3 (24 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class C (-1.7 ( Delta>>T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6<< 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 To tal N 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 NNE 0.0 0.0 0.0 0.0 0.003 0.003 0.001 0.001 0.0 0.007 NE 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.0 0.0 0.0 0.003 0.002 0.0 0.0 0.005 E 0.0 0.0 0.0 0 '02 0.004 0.003 0.0 0.0 0.0 0.008 ESE 0.0 0.0 0.0 0.007 0.008 0.012 0.002 0.0 0.0 0.029 SE 0.0 '.0 0.030 0.063 0.010 0.011 0.001 0.0 0.0 0.116 SSE 0.0 0.0 0.020 0.054 0.007 0.004 0.0 0.0 0.0 0.084 S 0.0 0.0 0.027 0.025 0.010 0.001 0.0 0.0 0.0 0.063 SSW 0.0 0.0 0.010 0.030 0.021 0.009 0.001 0.0 0.0 0.071 SW 0.0 0.0 0.011 0.063 0.040 0.022 0.003 0.0 0.0 0.139 WSW 0.0 0.0 0.002 0.025 0.028 0.046 0.006 0.0 0.0 0.108 W 0.0 0.0 0.001 0.004 0.031 0.057 0.015 0.008 0.0 0.117 WNW 0.0 0.0 0.0 0.003 0.003 0.030 0.025 0.003 0.0 0.064 NW 0.0 0.0 0.0 0.002 0.002 0.002 0.010 0.0 0.0 0.015 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.002 Sub total 0.0 0.0 0.101 0.278 0.166 0.206 0.066 0.013 0.001 0.830 Total hours of valid observations 101961 Total hours of elevated releases 91128.969 Total hours of stability class C 1307.02 Total hours of elevated stability class C 846.48 Meteorological facility: located 1;3 km ESE of BFN Stability'based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed and direction measured at 45.67 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 201 Table 7.3 (25 of 28)

JOINT PERCENTAGE FRE VENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class D (-1.5 < Delta-T < -0.5 degrees C per 100 m)

BROWNS fERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18. 5-Dir Calm 1.4 3,4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.005 0.120 0.359 0.577 1.660 1.059 0.135 0.003 3.919 NNE 0.0 0.017 0.129 0.416 0.719 1.926 0.915 0.070 0.001 4.193 NE 0.0 0.016 0.124 0.358 0.469 0.904 0.153 0.008 0.0 2.032 ENE 0.0 0.012 0.122 0.245 0.244 0.260 0.034 0.003 0.0 0.920 E 0.0 0.018 0.124 0.219 0.245 0.298 0.088 0.008 0.0 0 '99 ESE 0.001 0.010 0.224 0.499 0.561 0.822 0.138 0.005 0.0 2. 260 SE 0.002 0.025 0.753 1.509 0.945 1.586 0.834 0.143 0.006 5.803 SSE 0.002 0.036 0.520 0.867 0.705 1.411 0.981 0.277 0.013 4.811 S 0.001 0.012 0.417 0.769 0.603 1.197 1.036 0.320 0.022 4.376 SSW 0.001 0.017 0.240 0.524 0.409 0.792 0.479 0.119 0.006 2.586 SW 0.001 0.016 0.322 0.749 0.425 0.&20 0.297 0.053 0.002 2.484 WSW 0.001 0.010 0.178 0.604 0.505 0.575 0.279 0.053 0.001 2.204 W 0.0 0.008 0.111 0 '82 0. 701 1.163 0.432 0.086 0.004 2.985 WNW 0.0 0.008 0.107 0.330 0.481 1.140 0.823 0.246 0.009 3.145 NW 0.0 0.007 0.110 0.382 0.535 1.281 1.115 0.289 0.007 3.726 NNW 0.0 0.013 0.117 0.277 0.400 1.264 1.092 0.181 0.005 3.348 Sub total 0.012 0.227 3.715 8.588 8.524 16.899 9.754 1.994 0.080 49.792 Total hours of valid observations 101961 Total hours of elevated release 91128.969 Total hours of stability class D 54573.199 Total hours of elevated stability class D - 50768.48 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at. the 45.67 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 202 Table 7.3 (26 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class E (-0.5 < Delta-T 5 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0. 6- 1. 5- 3.5- 5.5- 7.5- 12. 5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.001 0.019 0.146 0.239 0.369 0.794 0.160 0.001 0.0 1. 729 NNE 0.001 0.019 0.159 0.273 0.374 0.935 0.228 0.003 0.0 1.992 NE 0.001 0.021 0.138 0.271 0.320 0.713 0.133 0.002 0.0 1.598 ENE 0.002 0.018 0.179 0.260 0.298 0.407 0.057 0.0 0.0 1.221 E 0.001 0.007 0.111 0.283 0.338 0.558 0.046 0.003 0.0 1.347

. ESE 0.003 0.019 0.299 0.587 0.719 0.866 0.069 0.004 0.0 2.566 SE 0.005 0.034 0.558 1.105 1.027 1.327 0.446 0.064 0.004 4.570 SSE 0.003 0.021 0.293 0.612 0.522 0.938 0.659 0.156 0.010 3.214 S 0.002 0.018 0.207 0.453 0.335 0.779 0.437 0.075 0.003 2.309 SSW 0.001 0.014 0.167 0.304 0.277 0.519 0.212 0.020 0.001 1.514 SW 0.002 0.013 0.213 0.331 0.321 0.342 0.102 0.014 0.001 1.337 WSW 0.001 0.015 0.162 0.290 0.256 0.291 0.040 0.005 0.0 1.061 W 0.001 0.007 0.113 0.280 0.316 0.347 0.051 0.001 0.0 1.114 WNW 0.001 0.015 0.082 '0.183 0.205 0.243 0.038 0.003 0.0 0.771 NW 0.001 0.012 0.107 0.179 0.183 0.294 0.111 0.003 0.0 0.890 NNW 0.001 0.014 0.109 0 '92 0.256 0.563 0.154 0.004 0.0 1.293 Sub total 0.026 0.262 3.043 5.843 6.115 9.916 2.942 0.359 0.018 28.526 Total hours of valid observations - 101961 Total hours of elevated release 91128.969 Total hours of stability class E 32478.371 Total hours of elevated stability class E - 29085.311 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at" the 45.67 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 203 Table 7.3 (27 of 28)

JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class F (1.5 ( Delta-T ~ 4.0 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 Total N 0.001 0.002 0.035 0.082 0.066 0.306 0.038 0.0 0.0 0.530 NNE 0.001 0.002 0.038 0.088 0.097 0.438 0.144 0.0 0.0 0.808 NE 0.001 0.005 0.041 0.115 0.135 0.349 0.102 0.0 0.0 0.748 ENE 0.001 0.009 0.037 0.103 0.149 0.255 0.057 0.0 0.0 0.612 E 0.001 0.003 0.031 0.084 0.133 0.269 0.023 0.001 0.0 0.545 ESE 0.003 0.008 0.115 0.243 0.294 0.183 0.002 0.0 0.0 0.848 SE 0.004 0.009 0.162 0.410 0.274 0.177 0.005 0.001 0.0 1.041 SSE 0.002 0.011 0.088 0.147 0.127 0.161 0.022 0.001 0.0 0.559 S 0.002 0.008 0.079 0.120 0.122 0.171 0.023 0.0 0.0 0.525 SSW 0.001 0.013 0.057 0.119 0.121 0.140 0.010 0.0 0.0 0.461 SM 0.001 0.008 0.061 0.101 0.093 0.063 0.0 0.0 0.0 0.327 WSW 0.001 0.004 0.043 0.072 0.080 0.047 0.001 0.0 0.0 0.248 W 0.001 0.007 0.037 0.063 0.063 0.047 0.001 0.0 0.0 0.219 WNW 0.001 0.005 0.026 0.047 0.029 0.024 0.0 0.0 0.0 0.133 NM 0.001 0.005 0.033 0.047 0.029 0.016 0.002 0.0 0.0 0.132 NNW 0.001 0.006 0.025 0.032 0.043 0.068 0.005 0.0 0.0 0.179 Sub total 0.022 0.103 0.910 1.873 1 ~ 855 2.717 0.434 0.003 0.0 7.916 Total hours of valid observations 101961 Total hours of elevated release 91128.969 Total hours of stability class F 9482 Total hours of elevated stability class F 8071.49 Meteorological facility: located 1.3 km ESE of BFN Stahility based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at'he 45.67 meter level Effluent velocity. = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 204 Table 7.3 (28 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24. 4 -24.5 To tal N 0.0 0.0 0.007 0.023 0.022 0.064 0.002 0.0 0.0 0.118 NNE 0.0 0.001 0.013 0. 025 0.045 0.130 0.051 0.0 0.0 0.264 NE 0.0 0.002 0.018 0.021 0.051 0.122 0.021 0.0 0.0 0.234 ENE 0.0 0.003 0.005 0.017 0.027 0.071 0.010 0.0 0.0 0.133 E 0.0 0.001 0.003 0.019 0.013 0.043 0.002 0 0 0.0 0.082 ESE 0.001 0.006 0.048 0 '03 0.054 0.016 0.0 0.0 0.0 0.229 SE 0.003 0.005 0.107 0.219 0.107 0.035 0.0 0.0 0.0 0.475 SSE 0.001 0.005 0.045 0.064 0.038 0.025 0.0 0.0 0.0 0.177 S 0.001 0.002 0.026 0.040 0-035 0.011 0.0 0.0 0.0 0 '16 SSW 0.0 0.003 0.012 0.014 0.030 0.023 0.001 0.0 0.0 0.083 SW 0.0 0.006 0.009 0.008 0.028 0.012 0.0 0.0 0.0 0;063 WSW 0.0 0.001 0.013 0.008 0.0 0.001 0.0 0.0 0.0 0.023 W 0.0 0.0 0.014 0.011 0.005 0.004 0.0 0.0 0.0 0.033 WNW 0.0 0.002 0.009 0.004 0.005 0.002 0.0 0.0 0.0 0.022 NW 0.0 0.006 0.005 0.010 0.008 0.003 0.0 0.0 0.0 0.031 NNW 0.0 0.0. 0.012 0.010 0.005 0.007 0.0 0.0 0.0 0.034 Sub total 0.006 0.042 0.344 0.592 0.471 0.568 0.087 0.0 0.0 2.116 Total hours of valid observations 101961 Total hours of elevated release 91128.969 Total hours of stability class G - 2783.14 Total hours of elevated stability class G 2157.41 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at'he 45.67 meter level Effluent velocity = 12.60 m/s 1132(206)

RETS Manual Revision 14 Page 205 Table 7.4 NOBLE GAS DOSE FACTORS Submersion dose Air dose mrem/yr per pCi/m3 mrad/yr per pCi/m3 DFBi DFSi DFyi DFBi Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Kr-83m 7.56E-02 .1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+Ol 1.95E+03 Kr-87 5,92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03

Reference:

Regulatory Guide 1.109, Table B-l.

Finite Cloud Dose Factors mrad/yr per pCi/s Highest Site Boundary Highest Site Boundary Highest Offsite Location Ground Vent Releases Mixed Vent Releases Elevated Vent Releases N Sector at 1525 m NNN Sector at 1650 m NM Sector at 8500 m Bi Vi Bi Vi Bi Vi Ar-41 1.30E03 1.50E-03 1.63E-03 1.87E-03 2. 71E-04 3. 12E-04 Kr-83m 1.08E-05 1.23E-05 1.31E-05 1.48E-05 2. 25E-06 2. 55E-06 Kr-85m 7.29E-05 8.57E&5 9.38E-05 1.10E-04 1.52E-05 1.78E-05 Kr-85 2.68E-04 3.11E&4 3.34E-04 3.88E-04 5.56E-05 6.46E-05 Kr-87 8.46E-04 9.72E-04 1.11E-03 1.28E-03 1.76E-04 2.02E-04 Kr-88 1.84E-03 2.09E-03 2.42E-03 2.75E-03 3.82E-04 4.34E-04 Kr-89 1.89E-03 2.17E-03 2.49E-03 2.86E-03 3.94E-04 4.51E-04 Kr-90 1. 17E-03 1. 36E-03 1.54E-03 1.78E-03 2.44E-04 2.83E-04 Xe-131m 5.87E-05 6.67E&5 7.10E-05 8.08E-05 1.22E-05 1.39E-05 Xe-133m 9.91E-05 1.14E-04 1.22E-04 1.41E-04 2.06E-05 2.37E-05 Xe-133 1.34E-04 1.52E&4 1.61E-04 1.83E-04 2.78E-05 3.15E-05 Xe-135m 7.20E-04 8.43E-04 9.31E-04 1.09E&3 1.50E-04 1.75E-04 Xe-135 4.73E-04 5.54E-04 6.01E-04 7.05E-04 9.83E-05 1.15E-04 Xe-137 6.74E-04 7.68E-04 8.87E-04 1.01E-03 1.40E-04 1.60E-04 Xe-138 1.24E-03 1.43E-03 1.63E-03 1.87E-03 2.59E-04 2.97E-04

Reference:

TVA generated values.

1132(206)

RETS Manual Revision 14 Page 206 Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sector Element Sector Element Site boundary - 1 mile 0.8 mile 1 2 miles 1.5 miles 2 3 miles 2.5 miles 3 4 miles 3.5 miles 4 5 miles 4.5 miles 5 10 miles 7.5 miles 10 20 miles 15 miles 20 30 miles 25 miles 30 40 miles 35 miles 40 50 miles 45 miles 1132(206)

RETS Manual Revision 14 Page 207 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT Distance to Midpoint of Sector Element 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 0 10 55 35 85 670 1515 2615 10660 3690 5 15 65 55 915 2990 2230 3125 3420 5 25 45 88 4180 14180 6625 5385 12625 0 15 50 40 70 1310 4990 9615 13860 5425 0 30 10 40 945 1910 73405 75125 4610 ESE 0 5 0 0 165 1880 2535 7465 9575 SE 0 0 0 20 10390 30945 4660 6230 13850 SSE 0 0 0 50 1630 6250 11630 15175 18945 0 20 35 90 1250 3805 1800 4475 3730 0 60 75 175 845 5895 1270 1490 2535 SW 0 20 35 90 685 2970 2280 2725 10675 WSW 0 35 15 135 295 3060 3005 11545 3755 0 25 5 30 625 2960 6830 35070 4785 0 0 25 55 50 885 9300 39875 5545 0 0 0 5 345 4345 5215 5485 3260 5 35 25 20 625 2090 2440 12350 7360 1132(206)

RETS Manual Revision 14 Page 208 Table 7.7 (1 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver

l. 58E-07 t body thyroid kidney lung gi-lli H-3 C-14 1.58E-07 2.27E-06 1.58E-07 1.58E-07 1.58E-07 l. 58E-07 1.58E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4. 26E-07 4. 26E&7 Na-24 P-32 1.28E-06 1.28E-06 1.28E-06 1.28E-06 l. 28E&6 1.28E-06 1.28E-06 1.65E-04 9.64E-06 6.26E-06 O.OOE+00 0.00E+00 O.OOE+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 l. 25E&8 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-11 O.OOE+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2. 12E&6 4.93E-07 O.OOE+00 0.00E+00 9.01E<<06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E&6 O.OOE+00 0.00E+00 1.27E-04 2.35E>>05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 O.OOE+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 O.OOE+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 O.OOE+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 O.OOE+00 O.OOE+00 2.23E-05 1.67E06 Ni-65 1.92E-10 2.62E-11 1.14E-ll 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 O.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 O.OOE+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m Br-82 1.02E-09 2.45E-09 2.24E-10 O.OOE+00 1.48E-09 2.38E-06 l. 71E&5 O.OOE+00 0.00E+00 1.69E-06 0 '0E+00 0 '0E+00 0.00E+00 1.30E-06 Br-83 O.OOE+00 0.00E+00 3.01E-08 0 ~ OOE+00 0.00E+00 O.OOE+00 2.90E>>08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Rb<<86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0 ~ OOE+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 0 '0E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2. 39E&5 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 O.OOE+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93. 1.18E-08 0.00E+00 3.26E-10 0.00E+00 O.OOE+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2. 21E&4 1.88E-05 Zr-97 '1.21E-08 2.45E-09 1.13E-09 O.OOE+00 3.71E-09 9.84E-06 6.54E>>05 Nb-95 1.76E-06 9. 77E&7 5.26E-07 O.OOE+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0 ~ OOE+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 O.OOE+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5 '2E-15 7.52E-15 7.38E-14 O.OOE+00 4.99E-08 1.36E-21 1.35E-13'.29E-07 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 O.OOE+00 1.27E-10 1.37E-06 6.02E-06 RU-106 8.64E-06 0.00E+00 1.09E-06 O.OOE+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E+00 2.46E&6 5.79E-04 3-78E05 1132(206)

RETS Manual Revision 14 Page 209 Table 7.7 (2 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver t body thyroid kidney lung gi-lli Sb-124 3.90E&6 7.36E-08 1.55E-06 9.44E-09 O.OOE+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E>>07 3.60E-05 6-37E&5 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E&6 1.49E>>03 7.66E&6 0.00E+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E<<07 0 '0E+00 5.08E-08 I-133 1.08E-06 1.85E-06 5 65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 O.OOE+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 O.OOE+00 6.56E-07 Cs-134 . 4.66E-05 1.06E-04 9.10E-05 O.OOE+00 3.59E-05 1.22E-05 1 30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1 07E-05 1.50E06 1.46E&6 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9 40E&6 1.05E-06 Cs-138 4.14E-08 7.76E-08 4 05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8 '5E-15 2.42E>>07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 O.OOE+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5. 73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 O.OOE+00 1.06E-04 9.72E-04 ~ 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E>>08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E>>07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2. 76E&5 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 O.OOE+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 .0.00E+00 8.75E-09 4.70E-06 1.49E-05

Reference:

Regulatory Guide 1.109, Table E-7.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 8.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS Manual Revision 14 Page 210 Table 7.7 (3 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN bone liver t body thyroid kidney lung gi-1 1 i H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6i09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 O.OOE+00 0.00E+00 O.OOE+00 1.16E-05 Cr-51 0.00E+00 O.OOE+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 O.OOE+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 O.OOE+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3'.93E-06 Co-58 O.OOE+00 2.59E-07 3.47E-07 O.OOE+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E&6 1.67E-'5 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Zn-69m 1.44E-09 3.39E-09 3.11E-10 O.OOE+00 2.06E-09 3.92E-06 2.14E-05 Br-82 O.OOE+00 0.00E+00 2.28E-06 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 4.30E-08 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 O.OOE+00 2.29E-09 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.40E-08 O.OOE+00 0.00E+00 0.00E+00 3 '5E-15 Rb-89 0.00E+00 4.40E-08 2 91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 O.OOE+00 1.56E&6 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00K+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 O.OOE+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 O.OOE+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 O.OOE+00 5.36E-ll O.OOE+00 0.00E+00 3.35E-06 2.06E-05 Y-93, 1.69E-08 O.OOE+00 4.65E-10 O.OOE+00 O.OOE+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 O.OOE+00 8.42E-06 3.36E-04 1.86E-05 Zr-97. '1.72E-08 3.40E-09 1.57E-09 O.OOE+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 O.OOE+00 1.14E-11 4.91E>>07 2.71E-07 Mo-99 O.OOE+00 2.11E-08 4.03E-09 O.OOE+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 O.OOE+00 7.20E-12 1.44E-07 7.66E>>07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 O.OOE+00 1.12E-07 O.OOE+00 9.29E-07 9.79E-05 1.36E&5 Ru-105 1.40E-10 O.OOE+00 5.42E-11 O.OOE+00 1.76E-10 2.27E-06 l. 13E-05 Ru-106 1.23E-05 O.OOE+00 1.55E-06 O.OOE+00 2.38E-05 2.01E-03 1. 20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 O.OOE+00 3.13E-06 8.44E-04 3.41E-05 1132(206)

RETS Manual Revision 14 Page 211 Table 7.7 (4 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN Sb-124 bone liver t body thyroid kidney lung gi-lli 5.38E>>06 9.92E-08 2.10E-06 1.22E<<08 O.OOE+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Te-125m 6.10E-07 2.80E-07 8.34E-OS 1.75E-07 O.OOE+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E<<05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E>>12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E&9 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E>>08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E&7 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E<<06 4.58E-07 0 OOE+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1 ~ 23E-14 4.11E-07 9.33E-14 Ba-142 4 '2E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2 '9E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-ll 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2. 28E&5 N-187 1.50E-09 1.22E-09 4.29E-10 O.OOE+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1. 25E&8 8.11E-06 1.65E-05 Reference Regulatory Guide 1.109, Table E-8.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 7.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS Manual Revision 14 Page 212 Table 7.7 (5 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD bone liver t body thyroid kidney lung gi-lli H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P>>32 7.04E-04 3.09E-05 2.67E-05 O.OOE+00 0.00E+00 O.OOE+00 1.14E-05 Cr-51 O.OOE+00 O.OOE+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 O.OOE+00 1. 16EW5 2.57E-06 O.OOE+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E+00 4.48E-10 8.43E-11 O.OOE+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 l. 28E&5 6.80E-06 2. 10E-06 O.OOE+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 O.OOE+00 O.OOE+00 3.43E-04'.37E-04 1.91E-05 Co-57 O.OOE+00 2.44E-07 2.88E-07 0.00E+00 O.OOE+00 3.58E-06 Co-58 O.OOE+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2+99E-04 9.29E-06 Co-60 O.OOE+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1 ~ 91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 O.OOE+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-ll 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 O.OOE+00 5.39E-10 2.90E-10 O.OOE+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 0 '0E+00 1.58E-11 3.84E-07 2 75E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 O.OOE+00 O.OOE+00 1.28E-07 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Br-85 0.00E+00 O.OOE+00 6.84E-09 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 O.OOE+00 5.36E-05 3.09E-05 O.OOE+00 O.OOE+00 0.00E+00 2.16E-06 Rb<<88 O.OOE+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 O.OOE+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3 ~ 99E&3 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7 '4E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+00 6.59E&6 O.OOE+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 O.OOE+00 O.OOE+00 6 '6E-06 6.46E-05 Y-93. 5.04E-08 0.00E+00 1.38E-09 O.OOE+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 O.OOE+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-ll 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 O.OOE+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 O.OOE+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 O.OOE+00 4.57E-06 O.OOE+00 4.97E-05 3.87E-03 1 ~ 16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 O.OOE+00 5.74E-06 1.48E-03 2.71E-05 1132(206)

RETS Manual Revision 14 Page 213 Table 7.7 (6 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD Sb-124 bone 1.55E-05 liver t body thyroid kidney lung gi-lli

2. OOE-07 5.41E&6 3.41E-08 O.OOE+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 O.OOE+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E&7 1. 64E&6 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1. 65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5 19E-06 1.85E-06 8. 22E07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-11 6.94E-ll 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E>>07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 O.OOE+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 I-133 4 '8E>>06 . 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5 '4E-07 2. 69E-07 ~

1.37E-05 8.92E-07 O.OOE+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0 ~ OOE+00 1.20E-06 Cs-134 1 ~ 76E-04 2. 74E-04 6.07E-05 O.OOE+00 8 '3E-05 3 ~ 27E&5 1.04E-06 Cs-136 1.76E-05 4. 62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.4SE-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0 OOE+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 O.OOE+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9 73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6 '8E-08 2.04E08 0.00E+00 0.00E+00 4.94E-05 6 '0E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 .

1.06E&5 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E&8 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E>>03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-ll 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2. 92E&6 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 O.OOE+00 1 ~ 11E&5 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 Reference Regulatory Guide 1.109, Table E-9.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 6.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206) '

RETS Manual Revision 14 Page 214 Table 7.7 (7 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT H-3 bone liver t body thyroid kidney lung gi-lli 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4. 62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 .

3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7-54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 O.OOE+00 0.00E+00 O.OOE+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 O.OOE+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 O.OOE+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E>>05 6.77E-06 O.OOE+00 0 OOE+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 O.OOE+00 O.OOE+00 2.71E-04 3.47E&6 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7. 95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2. 28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-ll O.OOE+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2. 22E&5 O.OOE+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 O.OOE+00 2.87E-11 1.05E&6 9.44E&6 Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Br-84 0.00EMO O.OOE+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0 OOE+00 O.OOE+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 O.OOE+00 0.00EMO O.OOE+00 2.42E-07 Rb-89 0.00E+00 2;29E-07 1.47E-07 0.00E+00 0.00E+00 O.OOE+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 O.OOE+00 O.OOE+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E>>03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00')0 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 l. 92E&4 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1. 75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 O.OOE+00 0.00E+00 1 ~ 75E-05 9.04E-05 Y-93. 1.07E-07 0.00E+00 2. 91E&9 O.OOE+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8. 24E-05'.07E-07 1.99E-05 1.45E-05 O.OOE+00 2. 22E&5 1.25E<<03 1.55E-05 Zr-97 1.83E-08 8.36E-09 O.OOE+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-ll 0.00E+00 2.22E-ll 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 O.OOE+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 O.OOE+00 6.42E-10 1.12E-05 3.46E-05 RQ-106 6.20E-05 O.OOE+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E<<06 3.57E-06 O.OOE+00 7.80E-06 2.62E-03 2.36E>>05 e 1132(206)

RETS Manual Revision 14 Page 215 Table 7.7 (8 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT bone liver t body thyroid kidney lung gi-lli Sb>>124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 O.OOE+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93K&6 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-ll 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1 ~ 26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 O.OOE+00 9.21E-07 I-135 2. 76E&6 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E06 0.00E+00 9.59E-09 1 ~ 14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 '.84E-11 2.36E<<14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1 ~ 20E-04 6.06E-05 La-142 7.36E>>10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3. 75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3 '5E-05 Ce-144 2.28E-03 8.65E-04 ,

1.26E&4 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-ll 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 O.OOE+00 0.00E+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4. 73E&8 4.25E-05 1.78E-05 Reference Regulatory Guide 1.109, Table E-10.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1132(206)

RETS Manual Revision 14 Page 216 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING Elevated Release (600 feet) from common stack Fl 90-271 RM 90-147, 148 Fram SGTS (common) Dllutlon Alr Steam Packing Exhauster (1 of 3) Mechanical Vacuum Pump S JAE Condenser ; Recomblners 8000 cubic foot Charcoal Adsorber Vessels Holdup Volume f

1132(206)

4 RETS Manual Revision 14 Page 217 Figure 7.2 NORMAL BUILDING VENTILATION ROOF FANS

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Refuel, Turbfne Oeek Ftoar RM 90-249 RQ 90.26f RQ 90-262 Q 4ILolfltlll Pure ~ dydee Turbine Buiiding Control Reactor Building (Typical for eachuntt) Bpy (typfcal for each unit) lo dere y~

(omoedeney

" Used seasonally to control temperature 1132{206)

RETS Manual Revision 14 Page 218 Figure 1.3 PLUME DEPLETION EFFECT (Page 1 of 4) 1.0 0.9 0.9 O.T g 0.8 0.5 a

O 0'I 0.1 0.1 1.0 10.0 100AI TIN PLUME TIIAVELOISTANCE IIIILOMETEnS)

I'Io~ Ooplotlon EIIoet lot Otound Loool Itoleotot IAIlAtmotpbotlo Stoblcty Ctottotl 1132(206)

RETS Manual Revxaxon 14 Page 219 Figure 7.3 PLUME DEPLETEON EFFECT (Page 2 of 4) 1.0

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RETS Manual Revision 14 Page 221 Figure 7.3 PLUME DEPLETION EFFECT (Page 4 of 4) 1.0 NEUTHAL'to) os O.d UHSTASLE IA,O,CI .

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0.1 0.1 1.0 10.0 100.0 S00.0 I'LUME ThhVEL DISTANCE IKILOMETEIIS}

Flome Ostrletlorr Ellsct lor 100srr hslseses ILettess rlsrrote Pesqolll Steblllty CbssI 1132(206)

RETS Manua1 Revision 14 Page 222 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 1000 100

10 0.1 1.0 10 100 PLUME TRAVEL DISTANCE {l(iLOMETEBS)

Vertical Standard Deviation of Material in a Plurne (Letters denote Pasqulll Stability Class)

'I 1132(206)

RETS Manual Revision 14 Page 223 Figure 7.5 RELATIVE DEPOSITION (Page 1 of 4) 1.0. 10.0 100.0 200.0 PLUME TRAV EL DiSTANCE (KILOMETEi1S) itelelivc Ocposition for Qrou>>tl-Level nclecscs (All Atmospltcric StclsilitY Cicssesl

RETS Manual Revision 14 Page 224 Figure 7.5 RELATIVE DEPOSITION (Page 2 of 4) 10 3 UNSTABLE (A ,c) 10<

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Aefetive Deposition for 30 ns Aeleeses (Letters denote Pesquill Stability Cfess) 1132(206)

RETS Manual Revision 14 Page 225 Figure 7.5 RELATIVE DEPOSITION (Page 3 of 4) 10 l UNSTABLE (A,B C 10 B NEUTRAL (D)

C N BL LU NEUTRAL i-ls:

z0 1O-6 I-O

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STAB (E,F,G) 10 0 0.1 1.0 10.0> 100.0 200.0 PLUME TBAVEL DISTANCE (K1LOMETERS)

Relative Deposition lor 60 nt Releases (Lettnrs denote Pnsquill Stability Classj 1132(206)

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RETS Manual Revision 14 Page 227 SECTION 8.0 TOTAL DOSE 1132(206)

RETS Manual Revision 14 Page 228 8.0 TOTAL DOSE To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by: first, summing the total body air submersion dose, and the critical organ dose (except thyroid) from gaseous effluents; the total body dose, and critical organ dose (except thyroid) from liquid effluents for each quarter calculated in accordance with Sections 6.6 and 7.7. Then to this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable'o the plant as determined by the environmental monitoring program outlined in Section 9.0. These quarterly sums are then conservatively summed for the four calendar quarters to estimate the maximum individual dose for the year. This dose i's compared to the limit in Control 3.2.3, i.e., 25 mrem per year to the total body or any organ (except thyroid), to determine compliance.

The total annual thyroid dose to the maximum individual will be conservatively estimated in the following manner. For each calendar quarter, a total dose will be obtained by summing the total body gaseous submersion dose,'he gaseous thyroid dose, the liquid total body dose, and the liquid thyroid dose. To this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in Section 9.0. These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year. This dose is compared to the limit in Control 3.2.3, i.e., 75 mrem per year to determine compliance.

1132(206)

RETS Manual Revision 14 Page 229 SECTION 9.0 ENVIRONMENTAL MONITORING PROGRAM 1132(206)

RETS Manual Revision 14 Page 230 9.1 MONITORING PROGRAM DESCRIPTION An environmental radiological monitoring program as described in Tables 9.1, 9.2 and 9.3 and in Figures 9.1, 9.2, and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.

The atmospheric environmental radiological monitoring program shall consist of 10 monitoring stations from which samples of air particulates and radioiodine shall be collected.

The terrestrial monitoring program shall consist of the collection of milk, soil, drinking water, and food crops. In addition,'irect gamma radiation levels will be measured at 40 or more locations in the vicinity of the plant.

The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish.

9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-2 are achieved.

t A 9.3 LAND USE CENSUS land use survey shall be conducted in accordance with the requirements in Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.

9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).

If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

1132(206)

RETS Manual Revision 14 Page 231 Table 9.1 (1 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number 'of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis AIRBORNE Particulates 6 samples from Continuous sampler Particulate sampler.

locations (in operation with sam- Analyze for gross different sectors) ple collection as beta radioactivity at or near the required by dust >24 hrs following site boundary loading but at least filter change.

(LM-l, LM-2, once per 7 days. Perform gamma isotopic LM-3, LMW, analysis on each LM-6, and LM-7) sample when gross beta activity is >10 2 samples from times the average of control locations control samples.

greater than 10 Perform gamma miles from isotopic analysis the plant on composite (by (RM-1 and RM-6) location) sample at least once per 3 samples from 31 days.

locations in communities approx-imately 10 miles from the plant (PM-1, PM-2 and PM-3)

Radioiodine Same locations as Continuous sampler I-131 every 7 days air particulates operation with charcoal canister collection at least once per 7 days

'SOIL Samples from same Once every year Gamma scan, Sr&9, locations as air Sr-90 once per year particulates DIRECT 2 or more dosi. At least once per Gamma dose once per meters placed at 92 days 92 days locations (in dif-ferent sectors) at or near the site boundary in each of the 16 sectors 1132(206)

RETS Manual Revision 14 Page 232 Table 9.1 (2 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations . Collection Fre uenc of Anal sis DIRECT (con- 2 or more dosi- At least once per Gamma dose once per tinued) meters placed at 92 days. 92 days.

stations located approximately 5 miles from the plant in each of the 16 sectors 2 or more dosi-meters in at least 8 additional locations of special interest WATERBORNE Surface 1 sample upstream Collected by auto- Gamma scan at (TRM 305.0) matic sequential- least once per 31 1 sample im- type sampler with days. Composite for mediately down- composite sample tritium at least once stream of dis- taken at least once per 92 days charge (TRM 293.5) per 31 daysa.

1 sample down-stream from plant (TRM 285.2)

Drinking 1 sample at the Collected by auto- Gross beta and gamma first potable matic sequential- scan at least once surface water type sampler with per 31 days. Compo-supply downstream composite sample site for Sr-89, Sr-90 from the plant taken at least once and tritium at least (TRM 282.6) per 31 daysa~ once per 92 days.

a Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

This assumes that the nearest drinking water intake is >3.0 mile downstream of the plant discharge. If a drinking water intake is constructed within 3.0 miles downstream of the plant discharge, sampling and analysis shall be every 2 weeks.

1132(206)

RETS Manual Revision 14 Page 233 Table 9.1 (3 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Drinking 3 additional sam- Grab sample taken Gross beta and gamma (continued) ples of potable at least once per scan at least once surface water 31 days. per 31 days.

downstream from Composite for Sr-89 the plant and Sr-90 and tritium (TRM 274.9, at least once per TRM 259.8, 92 days and TRM 259.5) 1 sample at a control location (TRM 306) 1 additional Collected by auto-sample at a con- matic sequential-trol location type sampler with (TRM 305) composite sample taken at least once per 31 daysa GROUND 1 sample adjacent Collected by auto- Composite for gamma to the plant matic sequential- scan, Sr-89, Sr-90, (well 06) type sampler with and tritium at least composite sample once per 92 days.

taken at least once per 31 days.

1 sample at a Grab sample taken Composite for gamma control location at least once per scan, Sr-89, Sr-90, upgradient from 31 days. and tritium at least the plant once per 92 days.

(Farm Bn)

AQUATIC Sediment 2 samples At least once per Gamma scan, Sr-89, upstream from 184 days and Sr-90 analyses discharge point (TRM 297.0 and TRM 307.52)

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The surface water control sample shall be considered a control for the drinking water sample.

1132(206)

RETS Manual Revision 14 Page 234 Table 9.1 (4 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Sediment 1 sample in At least once per Gamma scan, Sr-89 and (continued) immediate down- 184 days Sr-90 analyses stream area of discharge point (TRM 293.7) 2 additional samples down-stream from the plant(TRM 288.78 and 277.98)

INGESTION Milk At least 2 At least once per Gamma scan and I-131 samples from 15 days when animals on each sample..

dairy farms in are on pasture; at Sr-89 and Sr-90 at the immediate least once per 31 least once per 31 days vicinity of the days at other times.

plant (Farms B and Bn)

At least 1 sample from control lo-cations (Farm Gl or Be)

Fish 3 samples repre<< At least once per Gamma scan at least senting commercial 184 days once per 184 days on and game species edible portions.

in Guntersville Reservoir above the plant 3 samples repres-enting commercial and game species in Wheeler Reservoir near the plant 1132(206)

RETS Manual Revision 14 Page 235 Table 9.1 (5 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locations Collection Fre uenc of Anal sis Clams 1 sample down- At least once per Gamma scan on flesh stream from the 184 days. only discharge 1 sample upstream from the plant.

(No permanent stations established; depends on avail-ability of clams).

Fruits 6 Samples of food At least once per Gamma scan on edible Vegetables crops such as year at time of portion corn, green beans, harvest tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from Once per 31 days I-131, gamma scan (pasturage) farms producing once per 31 days.

milk but not Sr-89 and Sr-90 providing a milk analysis on the last sample (Farm T). monthly sample of each quarter.

Control sample from 1 control dairy farm (Farm Gl) 1132(206)

RETS Manual Revision 14 Page 236 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Approximate Indicator (I)

Location Distance or Samples Number a Station Sector (Miles) 1 PM-1 NW 13.8 I AP, CF, S 2 PM-2 NE 10.9 I AP, CF, S 3 PM-3 SSE 7.5 I AP, CF, S 4 LM-7 W 2.1 I AP, CF, S 5 RM-1 W 31.3 C AP, CF, S 6 RM-6 E 24.2 C AP, CF, S 7 LM-1 N 1.0 I AP, CF, S 8 LM-2 NNE 0.9 I AP, CF, S 9 LM-3 ENE 0.9 I AP, CF, S 10 LMW NNW 1.7 I AP, CF, S 11 M-6 SSW 3.0 I AP, CF, S 12 Farm B NNW 6.8 I, M 13 Farm Bn N 5.0 I M$ W 18 Farm Gl WSW 35 C M$ V 22 Well 86 NW 0.02 I W 23 TRMc 282 6 I PW 24 TRM 303.0 12.0 C PW 25 TRM 259.6 3404 I PW 26 TRM 274.9 19.1d I PW 27 TRM 285.2 8.8d I SW 28 TRM 293.5 0.5d I SW 29 TRM 305.0 ll.od Ce SW 30 TRM 307.52 13.52 C 'SD 31 TRM 293.7 0.3 I SD 32 TRM 288.78 5.22d I SD 33 TRM 277.98 16.02d I SD 34 Farm Be NW 28.8 C M 36 Farm T WNW 3.2 I V 37 TRM 297.0 3.0d C SD Wheeler Reservoir I/O F$ CL (TRM 275-349)

Guntersville Reservoir (TRM 349-424) 70 TRM 259.8 34 2d PW See Fi'gures 9.1, 9.2, and 9.3 Sample codes:

AP ~ Air particulate filter S = Soil SD ~ Sediment CF ~ Charcoal Filter SW = Surface Water CL = Clams F ~ Fish V = Vegetation PW = Public Water W = Well Water M ~ Milk TRM = Tennessee River Mile Miles from plant discharge (TRM 294)

Also used as a control for public water 1132(206)

RETS Manual Revision 14 Page 237 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or Number Station Sector Miles Offsite (Off) 1 NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W-3 W 31.3 Off 6 E-3 E 24.2 Off 7 N-1 N 1.0 On 8 NNE-1 NNE 0.9 On 9 ENE-1 ENE 0.9 On 10 NNW-2 NNW 1.7 On 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 On 40 NNE-3 NNE 5.2 Off 41 NE-1 NE 0 8 On 42 NE-2 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-1 E 0.8 On 45 E-2 E 5.2 Off 46 ESE-1 ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-1 SE 0.5 On 49 SE-2 SE 5.4 Off 50 SSE-1 SSE 5.1 .

Off 51 S-1 S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-2 SSW 3.0 Off 54 SSW-2 SSW 4,4 Off 55 SW-1 SW 1.9 On 56 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-1 W 1.9 On 62 W-2 W 4.7 Off 63 W-4 W 32.1 Off 64 WNW-1 WNW 3.3 Off 65 WNW-2 WNW 4,4 Off 66 NW-1 NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-1 NNW 1.0 On 69 NNW-3 NNW 5.2 Off aTLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two. miles from the plant.

1132(206)

RETS manual Revision 14 Page 238 Figure 9.1SAHPLING LOCATIONS RADIOLOGICAL P E5VIRO58ENTAL B8 SILE OP THE WITHIN 1 HAS Sa8.V 6 SS.V6 HH4 '7 gp ee ~

68.R6 SOS.V 6 28'UGLg

~ <6 pg Phb $9 gee.a6 g88.f 6 ~ 1 g>S.V6 S68 Scale QQVjf 6 gQe Daa(woe)

RETS Manual Revision 14 Page 239 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO S MILES FROM THE PLANT OI4.IS I I.24 HNW NNK I13 224.2$ SAIS HW 42 202.1 4 dd.dd WHW ((

C, 8

.KHt 85 ~ 10 24 I.2 36,64 Id.l ~

el

~ 82 4 ~ ~ BIIOWHS FK HUCLKAIIPL HF 24AIS ss

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224.24 63 I2AIS 68,

~ 64 2 I2.74 44.24 62 Sdt SCALK

~ O O.d I 0.4 2 I 4 I.24 14AI4 LOLK8 1132(206)

RETS Manual Revision 14 Page 240 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT 34L75 1145 325.25 W II%IICKSVAO 303.75 I'AY tTTaVILLI dd.25 34 251A5 75.75 uae 6

~ 2 43 4d 255.75 10 AS IIII5 YILL!

old 326.2 123.75 HALIYYILLd 5!

213.'75 5CALR 0 IO I 0 55 55I NLtS 10145 155.75 1132(206) .

RETS Manual Revision 14 Page 241 RETS MANUAL Section IV PROCESS CONTROL PROGRAM (vcr) 1132(206)

RET.'evi Page 1.0 U.S. Wuciaar Regulatory Conenlssicin OCT 16 "'-'f you have any questions concerning this request, piease telephone J. L. Turner at {205) 729-2853.

Enciosed is a cheek for the $ 150 review fee required by 10 CFR 170.12 Very tmly'ours, IEI(BESS EE V L KY AUillOHZ It- idley, 0 ector 20 l Fi Huclear &cen4ing and Reguiatory Affairs

~

Subscribed an4 sMarn to @fore me ee on thL>> /~i'Qda of ~ C 1987.

Rotary Public ly Coos!Lssian Expires Con fp ~ ~

,e ~ ~ i~ ~ ~ ~ ~

Endiasures cc {Enclosures)!

llr. O. C. Zech, Assistant Directo.

Regional Inspections Division of IVA Projects Office af SpeciaL Projects U.S. llucLear R'egulatory'oaaaissian Region. II 101 Harietta St., HM, Suite 2900 2 ~ Atlanta, Ccargia 50523 Nr. J. h. XMaLLnski, Assistant Director for Projects Division'of 9VA Projects Of fLce of Speciai Pro j ects U.S. Nuclear Regulatory Commission

>350 East>>'Mast IILghvay E("4 222 Bethesda, llaryland 20814 Brains Ferry Resident Inspector Bro~s Ferry Nuclear Plant Route 2, PO. Bbx 511 Athens, Alabcuaa 55ill IV-15 1132(206 1132(206) .

RETS Manual Revision 14 Page 243 2.9 Mixed waste - Low level radioactive wastes containing chemical constituents which are hazardous under Environmental Protection Agency regulations in 40 CFR Part 261.

2.10 Solidification agent Material, which when mixed in prescribed proportions with liquid or wet solid wastes, can form a free standing product with no free liquid.

2.11 Solidify To immobilize by use of a solidification agent or method which converts the liquid or wet solid waste to a free standing monolithic solid.

2.12 Stability A property of the waste form such that it is able to maintain its structural integrity under the expected disposal conditions; stabilized waste should maintain its gross physical properties and identity over a 300 year period.

2.13 Wet solid wastes Spent powdered ion exchange resins, filter aid sludge, bead ion exchange resins, and other sludges or slurries consisting of liquids with a high insoluble solid content.

3.0 REFERENCES

3.1 Code of Federal Regulations (CFR) Title 10, Parts 20, 61, and 71

[10 CFR 20, 10 CFR 61, and 10 CFR 71] Energy 3.2 Code of Federal Regulations (CFR) Title 49 [49 CFR] Transportation 3.3 Browns Ferry Nuclear Plant Final Safety Analysis Report, Volume 4, Chapter 9.3, Solid Radwaste system 3.4 Browns Ferry Nuclear Plant Technical Specifications (BFN Tech Spec) 4.8.F.l, 3.8.F.l & 3.8.F.2, 6.10.l.f, and 6.11.1, 2 & 3 3.5 TVA Office of Nuclear Power Radioactive Material Shipment Manual (RMSM) 3.6 Nuclear Regulatory Commission (NRC) Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983, Rev. 0 3.7 Nuclear Regulatory Commission (NRC) Technical Position on Waste Form, May 1983, Rev. 0 3.8 Topical Report No. TP-02-NP-A Rev. 0 IV-3 1132(206)

RETS Manual Revision 14 Page 244 4.0

~ WASTE CHARACTERISTICS 4.1

~ Waste Streams Three general waste streams applicable to this PCP have been identified for Browns Ferry. These are the Condensate Waste Phase Separator (CWPS), Reactor Water Cleanup Phase Separator (RWCU), and Dry Active waste (DAW). Other waste streams may be established based upon plant operational needs.

CWPS is fed by several waste sub-streams, including the Equipment Drain, Chemical Waste, Floor Drain, Fuel Pool Cooling, and Condensate systems.

RWCU is fed by Reactor Water Cleanup only.

DAW is used for wastes generated within the regulated areas of the reactor buildings and turbine buildings which cannot be appropriately attributed to either RWCU or CWPS. DAW normally includes paper, plastic, wood, metal and other such material generated as a result of the operation and maintenance of the plant.

4.2 Waste Form Wet solid radioactive wastes consist of bead resins, filter aids (such as activated charcoals or carbons), powdered resins, and slurries or sludges.

Wastes which may require solidification may include, but are not limited to, liquids which cannot be processed using installed plant systems, oils, chemicals, aqueous filter media, and decontamination wastes.

Wastes are processed as appropriate to ensure that the minimum physical characteristics required by 10 CFR and disposal site criteria are met. All Class B and Class C waste is st'abilized. On occasion, Class A waste (such as aqueous filter media with a concentration > 1 uCi/cc of isotopes with half-lives > 5 years) may be solidified or stabilized by BFN. Class A liquid wastes may be either solidified or packaged in sufficient absorbent material to absorb twice the volume of the liquid, as appropriate to the specific disposal site criteria or license requirements.

Tests are performed on those wastes which are solidified to ensure the adequacy of the solidification agent and procedural technique; These tests are made on a minimum of three samples from each waste batch to be solidified.

IV-4 1132(206)

RETS Manual Revision 14 Page 245 4.3 Waste Classification Scaling factors which relate hard-to-measure isotopes to key isotopes commonly measured at BFN have been developed for each waste stream. These scaling factors are used in the classification of the waste for disposal. Scaling factors may be developed on an as needed basis depending on changing plant operational conditions. Updates are performed at least every two years for waste normally considered to be Class A, on an annual basis for other wastes, or when the scaling factors are considered to be high or low by a factor of ten.

Batch samples, separator samples, or sludge samples are taken for radiochemical analysis prior to processing the waste for shipment.

DAW samples or area smears are taken to establish the relative percent abundance of isotopes for the DAW waste stream.

Materials which do not fit within the scope of existing scaling factors and waste streams are sampled. The samples are sent offsite for analysis and development of scaling factors prior to disposal of the materials.

5.0 SHIPMENT MANIFESTS 5.1 Manifest Pre aration Manifests are prepared for each shipment of radioactive waste for disposal. Programmatic guidance for manifest preparation is provided through the TVA Office of Nuclear Power, Radwaste Branch to ensure that all 10 CFR and 49 CFR criteria are met. Procedures for manifest preparation implement the specific requirements of 10 CFR 20.311, Transfer for Disposal and Manifests.

5.2 Manifest Trackin Acknowledgment of receipt for each shipment to a disposal site is sent to BFN Radwaste Group by the disposal site. Shipments for which acknowledgment is not received within the time limits allowed in 10 CFR 20.311 are traced by the TVA Office of Nuclear Power, Radwaste Branch.

IV-5 1132(206)

RETS Manual Revision 14 Page 246 6.0 ADMINISTRATIVE CONTROLS 6.1 Procedures and Surveillance Detailed procedures are written and maintained by BFN which cover plant process systems, waste packaging, and shipment requirements.

Surveillance Instructions are used to verify that plant Technical Specifications for waste processing are met.

Programmatic guidance is provided through the TVA Office of Nuclear Power, Radwaste Branch. The Radwaste Branch maintains the Radioactive Material Shipment Manual and the Package Quality Assurance Program (for packages licensed under 10 CFR 71).

6.2 ualit Assurance/ ualit Control Quality assurance audits are conducted by the BFN site Quality Assurance organization, and by the TVA Division of Nuclear Quality Assurance (DNQA). Audit findings are reviewed by BFN management, ensuring prompt corrective actions when needed.

Quality control measures include quarterly tests of the resin dewatering system performed by BFN personnel upon actual dewatered High Integrity Containers (HICs) or liners, site review of all radwaste vendor procedures before use, and second party verification by BFN personnel of end points or acceptance criteria in vendor procedures. Quality control of solidification methods is performed through controlled testing of a minimum of three samples from each batch to be solidified. Proportions of solidification agents are established which meet the standards for waste form and free liquid criteria.

6.3 T~rninin Personnel involved in processing radioactive waste for shipment are trained in site procedures, regulatory requirements, and disposal site criteria. Training and retraining sessions are held when needed to support operations. Retraining is required on an annual basis to maintain qualification. Personnel found not complying with procedures may have their qualifications revoked by the Radwaste Group Supervisor, if deemed necessary. Qualifications may retraining, and approval of be reestablished through completion of the Radwaste Group Supervisor.

IV-6 0 1132(206)

RETS Manual Revision 14 Page 247 6.4 Retention of Records Records are maintained to furnish documentation of items or activities affecting quality. Quality assurance records are stored in accordance with plant instructions and the TVA Nuclear Quality Assurance Manual. Retention times for radwaste records are established in the Radioactive Material Shipment Manual.

7.0 APPENDICES 7.1 Solidification Descri tion Topical Report

Reference:

None System or method in use: None Plant/Equipment Interfaces: None 7.2 Dewaterin Descri tion Topical Report

Reference:

DW-11118-01-P-A, Chem Nuclear Systems, Inc., CNSI Dewatering Control Process Containers, and RDS-25506>>01-P, Chem Nuclear Systems, Inc., RDS-1000 Radioactive Waste Dewatering System, Rev. 0 NOTE: See appended letter of interim approval from NRC to TVA of May 6, 1988.

Topical Report

Reference:

TP-02-NP-A, Nuclear Packing, Inc.

Covering Nuclear Packaging, Inc. Dewatering System, Rev. 0.

System or method in use: Vacuum dewatering using portable air driven diaphragm pumps and 10 HP electric high vacuum pump; and/or, Vacuum dewatering/high speed drying using the CNSI RDS-1000 Radioactive Waste Dewatering System; and/or pressure vessel dewatering using portable air driven pumps, and/or Nuclear Packaging, Inc. Dewatering System.

Plant/Equipment Interfaces: See appended letters of February ll, 1987 and October 16, 1987 from TVA to NRC and 2.

(RIMS 8L44 870211 808 and NL44 871016 807), and Attachment 1 IV-7 1132(206)

RETS Manual Revision 14 Page 248 8y 081 j. 8o 8,:.

SN 1578 Lookout Plsco FHB 111<87 V ~ S. Hucleor ROgulotory Comnission Attn! Document Control Desk Of flee of Nuclear Reactor Regulation Mashing,ton ~ 0 ~ Co ZOSSS Attent,loni llc'. D. tl. Hullcc'n the )letter of the Docket Hos. 50>>259 Tennessee Valley Authority 50-'260 50>>296 BROMNS FERllX tNCLEAR PLANT (BFN) - PROCESS CONTROL PROCRAH FOR DEltINERALIZER tlES IN DEMATKtlIHQ Demineralixer r'csin defeat'erin's performed ot BFH usinE equipmcnt fabricated by TVA 5o meet Chem-Hucliar Systems; Inc., (CNSI) equipment specifications.

SFH hos adopted tho operatlnE mithodology outlined by CNSI ln,a topical ropoc't (CNSI-DM-1111S-01-P) titled, "CNSI Dewatoring, Control Process Co'ntainors:.

Topical lleport." HllC accepted this topical c'sport, for reference by license applicants in a letter . ftom C ~ 0 ~ Thomas (NtlC) to t.. K. Poppe (CNSI) .dated Juno ll, 1985.

The enclosure providei information required by HRC to ravioli applicability ot the report to speeifio licensees as outlbled in the associated.safaty, Mo request that HRd review tho enclosed information ond provide -'voluatlon.

approval foc'so of 'this report os o process control program as defined in the.

Radiological Effluent Teclinleal Specification (NETS) amendment (TVA BFH T8-221, dated September 30, 1986). It is further requested that NRd approval of the process contcol program coincide Mlth the NETS im'plementation date or that the submittal be accepted on.'an interim basis until approval'f the Program ls flilbllzed.

lf you hove any questions concerning this request, please call L; V; Tonty at (205) 729-2677.

Very truly yours, TEHNESSEE Vhg X AUTtlORITX pd~ b.oc6 8/ggltl if oy tl. Orldley, Diroetoc" Nuclear Safety. and Licensing 0

\

Enclosure cct See pogo 2 IV-8 1132(206)

RETS Manual Revision 14 Page 249 4~

V.S. Nuclear Regulatory Commission FEB l11187 .

ee (Rnclosure) I V.S. Nublear llegulatory Concnlss ion Region II Attn! Dt. J. Nelson Crace,'egional hdminlstrator 101. Harie'tta Streetf IIMf Suite 2900 Atlanta, Ceorgia 30323 Hr. C. R. Cears Scold Ferry Pro)ect Honager V.S. Nuclear Regulatory Conmlssion 1920 Norfolk hvenue 'e thesda, )Iaryi and 20814 Hr. C. C~ Zech, Dicectoc TVh Pro)eats V.S; Nuolear Hegulatocy Commission 101 Hacletta St. ~ IIMf Suite 2900 Atlanta, Ceorgla 30323 Brome Ferry Resident InsPector Droms Ferry Nuclear Plant P.D. Box 311 Athens, Alabama 35611 IUHI JOM I l VII8 JL ee (Fnclosure)!

HIHSy HR 4N 72h-C R. M. Cantc'ell, M12 A12 C-K R. S. Cbristenbucy, Rll 833 C-K M. 11. 11annum, BR IN 768-C H . L IIOHis y Brouns Fec'ry Il. J.'lay, BFN - Licensiiig D. H. IliellPls LP 5N 302B-C .

H. V Parker, LP 4N 45h-C

11. P. Pomrelucl Brome Ferry L. J. Hiales, BR 58 144X-'C C. C. Robertson, LP 5S 83R-C H. K. Seiberllng, 116C-C D. 1. Milliamsi M10 885 C-K 0519e IV-9 1132(206)

RETS Manual Revision 14 Page 250 ENCLOSURE Dewatering is conducted at BFN using plant equipment and plant personnel.

Chem-Nuclear Systems, Inc., (CNSI) high-integrity containers and the CNSI dewatering procedures are used.

l. EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT DATED DECEMBER 1983.

BFN dewaters powdered resin, filter media, and mixtures of powdered resin with small quantities of bead resin (normally less than 10 percent bead resin) using Chem-Nuclear Procedure FO-OP-022, "Ecodex Precoat/Powdex/Solka-Floe/Diatomaceous Earth Dewatering Procedure for CNSI 14-195 or Small Liners." The dewatering system was fabricated by TVA to meet the equipment specifications in FO-OP-022. The TVA dewatering system differs from the Chem-Nuclear system in that:

(a) TVA's system has no off-gas collector. The high integrity containers are open to the waste packaging room air during filling and dewatering. Air from this room is normally discharged through the Radwaste Building ventilation system. This air then flows through a HEPA filter and is released through a monitored release point on the Reactor Building roof.

(b) The valves on the pump suction manifold are manually operated. The system is not operated remotely. However, the high integrity containers are enclosed behind a shielded wall or inside a shielded cask during filling and dewatering to keep radiation levels in the vicinity of the system near background.

(c) There are no vacuum gauges at each inlet connection. A single vacuum gauge is provided at the flush inlet connection to the manifold. This vacuum gauge will indicate a break in vacuum in any active (not isolated) filter set. Loss of vacuum normally occurs in sequence from the top to the bottom set of filters. When vacuum breaks at a given filter level, that level is isolated. Therefore, vacuum is monitored 'continually for all active filter sets.

(d) There is no automatic level control or level indicating instrument in the TVA dewatering system. Level is determined by visual observations.

TVA has conducted tests which conclude that mixtures of bead and powdered resin, in proportions of up to 50-percent bead, can be adequately dewatered using a modified procedure for dewatering powdered resin.

These tests were conducted using TVA-fabricated steel liners with dewatering internals similar to those found in the Chem-Nuclear high-integrity containers and a dewatering pump which is inferior to that 1132(206)

RETS Manual Revision 14 Page 251 specified in FO-OP-022, in that it is limited to a vacuum of 13" Hg and has a flow rate of six SCFM. In addition, the dewatering procedure used for the tests called for only four hours of bulk dewatering, as opposed to three eight-hour pumping cycles specified in FO-OP-022. The conditions of the test were clearly less conducive to proper dewatering than those specified in FO-OP-022 (this equipment and procedure is not used for normal operation). However, results show that adequate dewatering is guaranteed either by extending the dewatering time in the procedure or by applying an additional dewatering cycle at the end of the bulk dewatering process using a high flow rate (approximately 200 SCFM at 28" Hg) vacuum pump. TVA has modified FO-OP-022 to include two hours of additional dewatering with the 200 SCFM vacuum pump for all resin.

2. INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT (a) The high-integrity container is filled with spent resin slurry through a one-inch flexible hose. Flow through the hose is controlled by way of a diaphragm-operated valve. The hose is connected to the high-integrity container with an Evertight quick disconnect fitting that has been modified for remote operation.

(b) The dewatering pump discharges through a one-inch flexible hose to the plant waste packaging drain header which leads to the waste package drain tank. The connection to the header is made by an OPW 633 D Kamlock quick disconnect fitting.

(c) Radwaste compressed air is supplied through a flexible hose with Chicago connections to the air operated positive displacement pump.

(d) Demineralized water is provided by a flexible hose with Chicago connections to the flush-inlet valve on the dewatering pump suction manifold.

(e) The dewatering system is located inside the radwaste packaging room (see figure 1'). Any leaks or spills will be contained inside this room by exterior doors which are closed during filling, and collected in radwaste floor drains. Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or potable water supply.

3. LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT See Figure 1.

IV-11 1132(206)

RETS Manual Revision 14 Page 252

4. WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement.

Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.

5e DESCRIPTION OF WASTE CONTAINER High-integrity containers manufactured by CNSI are used for packaging resin. The following containers are used: 8-120,14-195, 14-170 and are discussed in a topical report dated December 1983 entitled, "Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity Containers CNSI-HIC-14571-01-NP."

6. CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment (note l.a above).

IV-12 1132(206)

RETS Manual Revision 14 Page 253 FIGURE 1 ReEaren.ca. Browna Parry FsAR 9.2 t b I ~

I ~

I 1 0 f ft. 3 [re,:

~ e I

~ ~ee eeee e eg 29ft.

Css>>o Operate>>r fja Ilea ns 3tn.

Cham-Hsccloar

~ I ~

glttcu 6 ll.

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~

) O'I>>

~ ~ ~

I

{

~ 'i

~ ~

~ ~+ ~

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Waste Packaging Room Layout for Chem Nuclear system Plan Elevation IV-13 565'132(206)

Manual i 01 6'0~

RETS Revision 14 L44 8 ~

Page 254 5tf 15 8 Lookout Place

~

OUT Lg!307 U.'~. 'ffuclear Regulatory Comm/.ssion AT S! Document Control Desk .

Mashing ton, D.C. 20555 Ctfltlemeni In the 'lla t ter o f Docket tfas. 50-259 Tennessee Valley Authority 50-260

'50-296 BRO'NfS FERRY HUCI.EAR PUQfT (BFU) PROCESS COffTROL PROCRAll FOR DKLIlfKRALIZER RESIff DEMAT<~C By letter t am me Ko D. p.. lfullec.dated February 1', 1987, TVA described its process central program tor demineralizer resin dewatering and requested ffRC to review and approve Lt as described in that letter. This resin..devatering process Mas tLae-consuming. Chem-ffuclear Systems Inc. (CNI) has since improved this process by develaping the RDS-1000, Rapid De~tering System, for accelerating the de~atering process. The time savings in this .de~atering praOess vill al'lax BFH.to accommodate,its spent reship ftenetatedgux~ng pouar paiduction. TVA"ihtends ta implement'the RDS>>1010:..praca'ss,before 4nit 2

~ restart. Tharafoie, khiff submittal supersedes t.'u February..ill 19df latter..

~ Cansequenb)y, T'lA, l>as elected nat to answer ffRd's ret(uest for additional information from J. A. Xvolinski ta S. A. ffhite dated July 21, 1987 concerning i

BFIf's current de~staring process in separate submittal. ffo~ever, these items are addressed ln the enclasures to this letter for the RbS-1000 systeia.

Demineral&er resin divatering ~ill be performed at BFtf using CfSZ equipmant.

The operating methodoiogy outlined by CHSZ in topical reports DM-11118-01-P-A, "ClfSI Devatering Central Process Cantainers Topical Report" and RDS-25506-01-P, "RDS-1000 Radioactive ffaste De~staring System" vill be used.

HRC accepted CHSI. Tbpioal Report DM-11118-01-P-h far reference by license applicants ln a letter fram C. O. Thomas (HRC) to L f: Poppe (CSSI) dated June 11. 1985. CHSI Topical Report RDS-25506-01-P ~s submitted to HRC by CSSZ for appraval by letter fram Q. B. 1(ouse (CHSZ) ta R. L. Ehch (HRC) dated Larch 26,.1987 and a nanproprietary copy is enclased ta this latter (enclosure 2), These CJSI topical reports ~ill form the basis af thi BN deminerali=or resin devatering proces>> and system.

Enclosure 1 provides information required by HRC to review applicability of the report to specific licensees es outlined in the safety evaluation far CHSZ Topical Report DWt1118-01-P-A. Procedures far this ne~ process and system ara scheduled to be intirnally approved by Oatober 1987 ~ TVA requests that ffffu reriev the enclosed intarmatloa and provide approval, within this same tor usa 'ot tlfis report as a process . control program as defined in',

-'- <~4"'lmetrame>

the ffrff teelmlcal, speeitleatian 6.9. - - ~~ ~

IV-14 1132(206)

RETS Manual Revision 14 Page 255 1Qq7 U.S. Duclear Regulatory Conenissicin

~ ~

OCT y6 If you turner have any questions concerning this request, Pl.ease telephone (205) 729-2853.

J. t..

Enclosed is a

~ I~

at, cheek for the 5150 revieM fee required by 10 CFR 110.12.

Very t~ly'ours, IHRlKSSKE V Lr EY AU llORI R. idley, D eetor lluelear l.icenking and Regulatory Affairs Subse lbed an/ sworn to f ore ttle

~ t.e on this gi~rda of 1981 l.

Hotary Public Qy Ceceeisslon Expires

~ ~ i ~ ~ ~

y ~ ~

~ ~

knd losures'e (Enclosures) l llr. C. C. Zech, Assistant Directe.

Regional Inspections Division of IVA Projects Office of Special Pro)ects U.S. lluelear R'eguiatory CoamLssion Region II Suite 2900 101 llarietta St., HM, Atlanta, Cnorgia 50323 Hr. J. h. Xuolinski, Assistant Dirictor for Pro) eets Division'of. VVA Pro)sets Office of Special Pro)eets U.S. Huclear Regulatory Commi.ssion 4350 East-Meet lliglway Kl"4 521 Bethesda, Hery land 20814 Brovns Ferry Resident Inspector Brogans Ferry Nuclear Plant Route 2, P..O. Box 511 Athens, Alabasas 55411 IV-15 1132(206) .

RETS ~n~i Revision 14 Page 256 U.S. Uuelaar Regulatory Ceaamksi ion ee (Enclesures)!

Br. C. C. Tech Ass staht~ Director llegiehal Knspec iohs Division oE T'IA Projects Office of Speci.al Pro) ro eats. t U,S.

,o e llucleat Regulatory Celllcliss o ss'on Region ZZ

~ . 101 Harietta St., HM, Suite 2900 Atlanta, Ceorgi.a 30323 g ga(e(Y ltr. J..

Eor A. ZMel.inski, Assistant Projects

>~s Fclri ('u~-"

Division oE XVA Prejeets OEE! eo of Special Proj ee t s gg Z0'87 V.S. lluclear Regulatory Comakssi.en 4350 East-Meat lHghua ulfO E4M 322 Betbesda, Haryland 20814

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~ g ~ ig Br'dms Feery Resident;:Inspector ~g gn

!Brains Far~ .Nuclear Plant ~

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Rou ta 2, P. 0 .. Box. 3Q Athens, Alabama 35611 JDM! JLT! XBL!CEL ee (Enalosl!res)!

RIES, llR 48 yXA-C C, E E . Ayers, LP 6l! 25D-C E. S.. Christenbury.

Ch Ell. B33 C-K M. Il. i(annus!, .BR IH 778-C T. A. Ippoli.to to, Bethesda License OEEien

. C. Kaxanas, LP AU a5A-C A Q.r)cobe MLE AIR C-K Bay, Bro~s Ferry C R. hullee, BR 9S 168A-'C D R. Hichols, BR 5S 100A-C ll. P. Pomr mrehn; Broms Ferry'.

J. Sc6th LP 68 38A-C D. l.. Ml.lllams, M10 885 C-K IV-16 1132(206)

RETS Manual Revision 14 Page 257 ENCLOSURE 1 Dewatering will be conducted at BFN using the Chem-Nuclear Systems, Inc.

(CNSI) Rapid Dewatering System (RDS-1000). CNSI high-integrity containers and/or steel liners and plant specific versions of CNSI Procedure FO-OP-032, "Setup and Operating Procedure for the RDS-1000 Unit" and CNSI Procedure FO-OP&35, "Setup and Operating Procedure for Dewatering Pre-Coat Media in a 21-300 Liner Using the RDS-1000" will be used.

1. EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORTS DW-11118-01-P-A AND RDS-25506-01-P TVA's system has no off-gas system connection available for interface with the RDS-1000. The rapid dewatering skid of the RDS-1000 system has a HEPA filter installed downstream of the safety relief valve and manual bypass valve. Liners will be vented through this HEPA filter to the waste packaging room. Air from this room is normally discharged through the radwaste building ventilation system. This air then flows through an installed HEPA filter before release through a monitored release point on the reactor building roof. Exterior doors from the waste packaging room are closed during liner filling and dewatering operations.

2. INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT A. A plant connection stand (PCS) is provided as part of the RDS-1000 system. Its components are:

1. A remotely operated valve to control influent to the liner;

2. A diaphragm pump with connections to the liner fillhead for initial gross dewatering;

3. Manifolds for air and service water supplies to control elements and flushing systems.

B. Radwaste building compressed service air will be provided to the PCS at approximately 40 SCFM at 80 psig (+20, -10 psig) through a flexible hose. The connection to plant air and water is made via quick-disconnect fittings. The PCS connection to CNSI equipment is also a quick-disconnect fitting.

IV-17 1132(206)

RETS Manual Revision 14 Page 258 C. Radwaste building service water (demineralized) will be, provided to the PCS at approximately 25 gpm at 80 psig (+20 psig) through a flexible hose. Both connection points (plant and PCS) are equipped with quick-disconnect fittings.

D. The dewatering pump discharge is provided by a 1.5 inch flexible hose to the plant waste packaging drain header which leads to the waste package drain tank. The connection to the drain header is made by a 1-inch Kamlock quick-disconnect fitting. The dewatering pump connection is a 1.5 inch Kamlock quick-disconnect fitting. A 1 to 1.5-inch Kamlock adaptor will be used at the drain header.

E. The connection to the plant waste media line will be made either by a 1.5-inch 150 ANSI flat faced flange connection or by a flange connection to Kamlock quick-disconnect adaptor utilizing existing flexible hose. A waste isolation valve will be installed downstream of this connection, providing local control by the CNSI operator over the flow of waste to the liners being filled. The waste isolation is controlled remotely, and is interlocked to close on high waste level, high-high level, decreasing air pressure, or loss of electrical power.

3. LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT See Figure 1 The RDS-1000 system will be located inside the radwaste packaging room, elevation 565'. Any leaks or spills will be contained inside this room by exterior doors, which are closed during liner filling and dewatering operations. Any spillage will be collected in the radwaste floor drains.

Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or potable water supply IV-18 1132(206)

RETS Manual Revision 14 Page 259 WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similarly behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. Computerized calculation of individual container isotopic contents is performed. Maintenance, testing, and independent verification of this program ascertain correct data manipulation. TVA QA audits of the vendor laboratory conducting the periodic sample analysis confirm quality practices at that location.

Procedural controls, corporate assessments of the radwaste program, periodic QA audits 'of the program, and management evaluation of audit findings ensure quality in the plant program.

5. DESCRIPTION OF WASTE CONTAINER High-integrity containers manufactured by CNSI are used for packaging resin. The following containers are used: 8-120,14-195, and 14-170.

They are discussed in a topical report dated December 1983 entitled, "Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity Containers CNSI-HIC-14571-01-NP." CNSI 21-300 steel liners are compatible with the dewatering system and may also be used.

6. CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment.

IV-19 1132(206)

RETS Manual Revision 14 Page 260 FIGURE 2 narcrenca Brawna Flurry O( or l.ocul lan Cua. rc~nlo cw<<trial pllllltl L=SAf< .0.2 1b I

(lg I'Idiot cauuaet lc>u utouiI anil luis-Iuuu Illlo IllCQL IIII' (9 IIIC local lnn (altcraata) uIL I<I local lofti

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Haste Packaging Room Layout for Chem Nuclear System Plant Elevation

-20 565'132(206)

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RETS Manual Revision 14 V g~ ~tti~~

Page 261 UtnTED ST~TKS NUCLEAR REGULATpFtY CQQQ1SS)pN

'~(l Q . I 7TA5HIHQ fo+ o, e tophet Qfttffgtglg, paid 5>>tel 1

a A '0

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sr~la~n >~

'ocket Ilas. 50-259/260/296'ay 6, 1988 'Y I

1 i'~~n Hr, S, A. Mhite yyl f. l LiC+

Hanacer oi 1lucleai'o~er Tennessee Yalley Autnori:r

.611 38'ookout Place IICf II01 Ha rk e t Stree ~

Chat tanoooa, Tennesse 37402-2801 o~ I

Dear Hr. Mhfte:

~

) 0~ I SUBJKCT: IATB(H APPROYAf. OF BAOHAS FORAY PROC=-ZS CarfTAOt..

(T'C 64700, 64701, 64 02) PAaaAe'e have eomoleted our revffe~ of ~ ~

the aro~ns Ferry revised procesi cont~I program (PCP) submf tted ~i tn your letter dated Octooer 18, 1987.

the Brogans Ferr'r PC P for.

e Technical Specfffcatfons, implementingthe licensee the requirements of Sectfon 6.9 c'n

. vendor' I cans ino top f ea I reports: has refqrenced the follo~fno 1

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l. 01 -11118t01-P-A; Chem-Aucl ear. Syst'ems

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Inc., 01SI

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Devaterfpq'ant".51,

,Process Conta fners Topical Report.

~ ~ ~ los Z. a AOS-2Sa06-0I-P; Chem-1luelear System, Oe~aterfno Svstem, Aev. 0. Ine., ROS-1000 Radfoae:fve l1as e Tootcal Reoor: 11o, I above has referencfno fn future lfeensino been approved by the staff i~d accepted apoffca:fons. The remain)no topical reoor .

<<i (11o, 2) fs unoer'review by the 11AC staf,. Thb tfRC staff's review of this eood ~ has oenerated ouestfons Chem-11uel ear SvStemS reoufrfno the vendor of: the process lnC.) tO prOVide reSpOnSeS. The Vendar reSpanSeS ~ere submitted to thh 11RO by letter dated revfeM of these responses has Haich 31, 1988. The staff's prelfmfnary <<

fol meetfno indicated that this topfcal report fs acceptable tlie requfrements fn See-fon 11.4 of Standard Aevfept Plan (SAP) and 10 CFA 61.

~ ~

Based on oour r revfev,'e ffnd the revised PCP for Brains Feit"rg, Unfts 1 3 acceptable as an fnterfm approval effectfve untf 1 'the 11AC 2 and ts'eview of the topfckl report (Reference staff compfetes proceed with solfdfffcatfon of 2) described above:.: You may resin fn accordance fifth the revised radfoac"fve wastes and desaterfn9 of spent acceptance are conformance to the Brogans Ferry pCp. The basis for ffcensae's Il-3> SAP Sac fon 11.4, and to tha raqufrenants pcp to Braach Tejbstfcal position

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aehnfeal Speefi'fcatfons. 4 Sactfan 6.9 of the 1

IV-21 1132(206)

RETS Manual Revision 14 Page 262 Mr. S. A. Mhlte, May 6, 14M lf vou have any ouest)ons concernlno this issue, please contac= jour Manaoer, G. Gears at 30l-49Z-0767; Pro'ec:

S l nce re 1 y,

r Robert A. Hermann, Actintt Assistant Olrec."r TVA Pro)ects Olvision Office of Special Pro)ec.s cc: See nex. pace IV-22 1132(206)

RETS Manual Revision 14 Page 263 ATTACHMENT 1 Dewatering is conducted at BFN using Chem-Nuclear System, Inc (CNSI) supplied portable air driven pumps. Dewatering will be performed on CNSI 24 inch diameter pressure vessels.

1. EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT None. Plant specific versions of CNSI Procedure FO-OP-025 and vendor supplied equipment will be used to dewater vessels.

2. INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT (a) The dewatering pump discharges through a flexible to a plant floor drain. This water will be processed through Radwaste.

(b) Compressed air is supplied from the plant air system through a flexible hose with Chicago connections to the air driven pump.

(c) The dewatering system will be located in a permanent plant building.

Any leaks or spills will be contained inside this building and collected in floor drains. Failure of any of the components will not provide a pathway for radioactive releases to the environment or to a portable water supply.

3. LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT The dewatering will be performed in a permanent plant building. The dewatering pump will be located in the immediate vicinity of the pressure vessels and as close as possible to a floor drain.'.

WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent off,site for analysis. An inferential measurement program is then established whereby concentrations of.radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.

5. DESCRIPTION OF WASTE CONTAINER The waste containers are the CNSI 24 inch diameter carbon steel and fiberglass re-inforced plastic pressure vessels.

6. CAPABILITY TO MEET 10CFR50 Appendix I This dewatering process does not cause any direct releases to the environment (see note 2C above),.

IV-23 1132(206)

RETS Manual Revision 14 Page 264 ATTACHMENT 2 Dewatering will be conducted at BFN using the Pacific Nuclear Systems, Inc./Nu Pac Services Division, Inc. Resin Drying (Dewatering) System. Pacific Nuclear Systems, Inc./Nu Pac Services Division, Inc. high-integrity containers and plant specific versions of Pacific Nuclear Systems, Inc./Nu Pac Services Division, Inc. procedures OM-43-NS, "Operating Procedure for the Resin Drying (Dewatering) System," and OM-16-NS, "Users Guide for the Nu Pac Crosslinked Polyethylene High Integrity Containers" will be used.

1. EXCEPTIONS OR DEVIATIONS TAKEN TO PACIFIC NUCLEAR TOPICAL REPORT TP-02-NP-A TVA's system has no off-gas connection available for connection to the Resin Drying System. The Resin Drying System blower skid contains a HEPA filter which removes airborne particulate matter from the container vent pathway during the container filling cycle and vents this air to the general area around the skid. This air is then discharged through the plant ventilation system. This air flows through an installed HEPA filter through a monitored release point prior to its release to the environment.

2. INTERFACES BETWEEN PLANT AND PACIFIC NUCLEAR SYSTEMS, INC EQUIPMENT A. Plant compressed service air will be supplied to the Resin Drying System at approximately 40 SCFM at 100 psi through a flexible hose.

B. Plant service water (demineralized) will be supplied to the Resin Drying System at approximately 25 gpm at 80 psi through a flexible hose.

C. The Resin Drying System will discharge the water removed from the high-integrity container to the plant radwaste system through a flexible hose.

D. The connection to the waste transfer line is made via a high Pressure flexible hose to the fillhead which is connected to the high-integrity container. A waste isolation valve provides the Pacific Nuclear System operator local control over the flow of waste to the liners. The waste transfer isolation is controlled remotely and the fillhead is interlock to close automatically on high waste level, or high fillhead pressure alarms.

3. LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT The Resin Drying System will be located inside a permanent plant building. Any leaks or spills would be contained inside this building.

Any spillage would be collected in the plant floor drains. Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or a portable water supply.

IV-24 1132(206)

RETS Manual Revision 14 Page 265

4. WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similarly behaving isotopes which can be readily measured. Scaling factors are developed on a waste stream specific basis. Scaling factors are periodically reconfirmed through sampling and analysis. Computerized calculation of individual container isotopic contents is performed. Maintenance, testing, and independent verification of this program ascertain correct data manipulation. TVA QA audits of the vendor laboratory conducting the periodic sample analysis confirm quality practices at that location.

Procedural controls, corporate assessments of the Radwaste program, periodic QC audits of the program, and management evaluation of audit finding ensure qualify in the plant program.

5. DESCRIPTION OF WASTE CONTAINERS High-integrity containers manufactured by Pacific Nuclear Systems, inc.

are used for packaging resin.

6~ CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment.

LAST PAGE 1132(206)

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