Text

Semiannual Radiological Effluent Release Rept,Jul-Dec 1992. W/930301 Ltr
	ML18036B185
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1992
From:	Pierce G; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9303180239
	Download: ML18036B185 (534)
	v • d • e

ACCEI ERAT~O DOCUMENT DISTRIBUTION 'SYSTEM REGULAT~ INFORMATION DISTRIBUTIO~YSTEM (RIDS)

ACCESSION NBR:9303180239 DOC.DATE: 92/12/31 NOTARIZED: NO DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION PIERCEEG.D. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Browns Ferry Nuclear Plant Semiannual Radiological Effluent Release Rept,Jul-Dec 1992." W/930301 ltr.

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2)

COPIES RECEIVED:LTR Semiannual

~ ENCL Effluent Release Reports g SIKE: g ~5 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-4 3 3 HEBDON,F 1 1 ROSS,T. l 1 WILLIAMS,J. 1 1 INTERNAL: C l 1 NRR/DRSS/PRPB11 2 2 G~ 01 1 1 RGN2 DRSS/RPB 2 2 RGN2 FILE 02 1 1 EXTERNAL BNL TICHLER I J03 1 1 EG&G SIMPSON,F 2 2 NRC PDR 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17

0 0

,P

Tennessee Valley Authority, Post Office Box 2000, Decatur. Alabama 35609 VAR Oi 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY THROUGH DECEMBER 1992 In accordance with the BFN Radiological Effluent Manual, Section F.2, and Regulatory Guide 1.21, Revision 1, two copies of the Semiannual Radioactive Effluent Release Report are provided. The report consists of the following:

1. The Radiological Impact Report (Enclosure 1)

2. Effluent and Waste Disposal Semiannual Report (Enclosure 2)

3. The Inoperable Radiological Effluent Instrumentation Report (Enclosure 3)

4. Changes to the Offsite Dose Calculation Manual (Enclosure 4)

BFN Technical Specifications 3.2.D.2, 3.2.K.2, and 6.12.2 require the Inoperable Radioactive Effluent Instrumentation Report and changes to the Offsite Dose Calculation Manual to be included with the Semiannual Radioactive Effluent Release Report.

U.S. Nuclear Regulatory Commission rwa oz >993 Please refer any questions or comments to me at (205) 729-7566.

Sincerely, G. D. ierce Interim Manager of Site Licensing PAB 1G-BFN Enclosure cc (Enclosure):

NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

c 0,

~

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT (BFN)

"THE RADIOLOGICAL IMPACT ASSESSMENT REPORT"

BFN Rad Impact July-December 1992 Page 1 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 Potential doses to maximum individuals and the population around Browns Ferry are calculated for each quarter as required in Section 5.2 of the Offsite Dose Calculation Manual (ODCM). Measured plant releases for the reporting period are used to estimate these doses. Dispersion of radioactive effluents in the environment is estimated using meteorological data and riverflow data measured during the period. In this report, the doses resulting from releases are described and compared to limits established for Browns Ferry.

The ODCM specifies limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of radioactive effluents. These limits are set well below the NRC 10CFR20 limits which govern the concentrations of radioactivity and exposures permissible in unrestricted areas. This ensures that radioactive effluent releases are as low as reasonably achievable (ALARA).

The limits for

~ ~

doses at or beyond the site boundary from airborne noble gases releases are:

Less than or equal to 5 mrad per quarter and 10 mrad per year (per reactor unit) for gamma radiation, and Less than or equal to 10 mrad per quarter and 20 mrad per year (per reactor unit) for beta radiation.

The limit for the dose to a member of the general public at or beyond the site boundary from iodines and particulates released in airborne effluents is:

Less than or equal to 7.5 mrem per quarter and 15 mrem per year (per reactor unit) to any organ.

The limit for doses to a member of the general public from radioactive material in liquid effluents released to unrestricted areas, is:

Less than or equal to 1.5 mrem per quarter and 3 mrem per year (per reactor unit) to the total body, and 0 Less than or equal to 5 mrem per quarter and 10 mrem per year (per reactor unit) to any organ

BFN Rad Impact July-December 1992 Page 2 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 The Environmental Protection Agency (EPA) limits for total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are:

Less than or equal to 25 mrem per year to the total body, Less than or equal to 75 mrem per year to the thyroid,

- and-Less than or equal to 25 mrem per year to any other organ.

Estimated doses to the public are determined using computer models (the Gaseous Effluent Licensing Code, GELC, and the Quarterly Water Dose Assessment Code, QWATA). These models are based on guidance provided by the NRC (in Regulatory Guides 1.109, l.ill and 1.113) for determining the potential dose to individuals and populations living in the vicinity of the plant. The area around the plant is analyzed to determine the pathways through which the public may receive a dose. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum values. Many of these factors are obtained from NUREG/CR-1004. The values chosen will tend to overestimate the dose to this "maximum" person. The expected dose to actual individuals is lower. The calculated doses are presented in Tables lA through 3.

For airborne effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation of airborne radioactivity, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk and beef which contains radioactivity deposited from the atmosphere onto vegetation which is then eaten by milk and beef animals.

There are four routine release points from Browns Ferry Nuclear Plant:

the turbine building, the radwaste building, the reactor building, and the stack.

Releases from the turbine building are considered ground-level releases.

The ground-level joint frequency distribution (JFD) is derived from windspeeds and directions measured 10 meters above ground and from the vertical temperature difference between 10 and 46 meters, and is presented in Table 4A and 4B.

BFN Rad Impact July-December 1992 Page 3 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 Releases from the radwaste and reactor buildings are considered split-level releases. Portions of the release are treated as elevated while other portions are considered ground-level depending on the ratio of the vertical exit velocity to the horizontal wind speed. The split-level dispersion approach is implemented using a model that requires two complete quarterly JFDs for each effluent vent, one for the elevated releases and one for the ground-level releases. The ground-level portion of the split-level JFD, is based on wind speeds and directions measured 10 meters above ground-level and from the vertical temperature difference between 10 and 46 meters. The elevated portion of the split-level JFD is based on wind speeds and direction measurements at the 46-meter level and the vertical temperature difference between 46 and 91 meters. Both of these JFDs are given in Tables 5A, 5B, 5C and 5H.

Releases from the stack are considered to be elevated-level releases.

The JFDs for elevated releases are based on wind directions and wind speeds measured at 91 meters and the vertical temperature difference between 46 and 91 meters, and are given in Tables 6A and 6B.

t t t Neteorological variables at Browns Ferry are measured continuously.

Neasurements collected include wind speed, wind direction, and temperature at heights of 10, 46 and 91 meters above the ground.

Quarterly joint frequency distributions (JFDs) are calculated for each release point using the appropriate levels of meteor'ological data. A joint frequency distribution gives the percentage of the time in a quarter that the wind is blowing out of a particular upwind compass sector in a particular range of wind speeds for a given stability class A through G. The wind speeds are divided into nine wind speed ranges.

Calms are distributed by direction in proportion to the distribution of noncalm wind directions less than 0.7 m/s (1.5 mph). Stability classes are determined from the vertical temperature difference between two measurement levels. The JFDs are given in Tables 4A, 4B, 5A, 5B, 5C, 5H, 6A and 6B.

The generally open terrain around BFN is not believed to cause any significant effects on the transport and dispersion of gaseous effluents from the plant. Within 30 kilometers of BFN, the terrain is mostly gently rolling hills (30-60 meters). Between 30 and 80 kilometers the hills become larger to the north and south, and mountainous to the east and northeast. The Tennessee River/Wheeler Lake may have a minor effect on transport and dispersion in the immediate vicinity of BFN during periods of winds with a southerly component, overcast skies, and relatively high wind speeds. Then, the lower layer (10-46 meters) stability class tends to be more stable than would be expected. However, during this infrequent condition, dose estimates will be conservative.

Dose estimates for maximum external air exposures (gamma-air and beta-air doses) are made for points at and beyond the site boundary as described in the BFN ODCN.

BFN Rad Impact July-December 1992 Page 4 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 External doses to the skin and total body, due to submersion in a cloud of noble gases, are estimated for the nearest residence in each sector.

Doses to organs due to releases of airborne effluents are estimated for the inhalation, ground contamination, and ingestion pathways. The ingestion pathway is further divided into four possible contributing pathways: ingestion of cow/goat milk, ingestion of beef, and ingestion of vegetables. Doses from applicable pathways are calculated for each real receptor location identified in the most recent land use survey. To determine the maximum organ dose, the doses from the pathways are summed for each receptor. For the ingestion dose, however, only those pathways that exist for each receptor are considered in the sum, i.e., milk ingestion doses are included only for locations where milk is consumed without commercial preparation and vegetable ingestion is included only for those locations where a garden is identified. To conservatively account for beef ingestion, a beef ingestion dose equal to that for the highest site boundary location is added to each identified receptor. For ground contamination, the dose added to the organ dose being calculated is the total body dose calculated for that location, i.e., it is assumed that the dose to an individual organ is equal to the total body dose.

Doses from airborne effluents are presented in Table 1A and 1B.

For liquid effluents, the public can be exposed to radiation from three sources: the ingestion of water from the Tennessee River, the ingestion of fish caught in the Tennessee River, and direct exposure from radioactive material deposited on the 'river shoreline sediment (recreation).

The concentrations of radioactivity in the Tennessee River are estimated by a computer model which uses measured hydraulic data downstream of Browns Ferry. Parameters used to determine the doses are based on guidance given by the NRC (in Regulatory Guides 1.109) for maximum ingestion rates, exposure times, etc. Wherever possible, parameters used in the dose calculation are site specific use factors determined by TVA.

The models that are used to estimate doses, as well as the parameters input to the models, are described in detail in the Browns Ferry Nuclear Plant ODCM.

BFN Rad Impact July-December 1992 Page 5 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992

'v t Radioactivity concentrations in the Tennessee River are calculated assuming that releases in liquid effluents are continuous. All routine liquid releases from Browns Ferry, located at Tennessee River Mile 294, are made through diffusers which extend into the Tennessee River. It is assumed that releases to the river through these diffusers will initially be entrained in one-fifth of the water which flows past the plant. The QWATA code makes the assumption that this mixing condition holds true until the water is completely mixed at the first downstream dam, at Tennessee River Mile 283.0.

Doses are calculated for locations between the plant site and the mouth of the Tennessee River. The maximum potential recreation dose is calculated for a location immediately downstream from the plant outfall.

The maximum individual dose from ingestion of fish 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 individual dose from drinking water is assumed to be that calculated at the nearest downstream public water supply (Champion Paper Company). This could be interpreted as indicating that the maximum individual, as assumed for liquid releases from Browns Ferry, is an individual who obtains all of his drinking water at the Champion Paper Company, consumes fish caught from the Tennessee River between BPK and Wheeler Dam, and spends 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year on the shoreline just below the outfall from Browns Ferry. Dose estimates for the maximum individual due to liquid effluents for each quarter in the period are presented in Tables 2A and 2B, along with the average river flows past the plant site for the periods.

Population doses for highest exposed organ due to airborne effluents are calculated for an estimated 627,000 persons living within a 50-mile radius of the plant site. Ingestion population doses are calculated assuming that each individual consumes milk, vegetables, and meat produced with the sector annulus in which he resides. Doses from external pathways and inhalation are based on the 50-mile human population distribution.

Population doses for total body and the maximum exposed organ due to liquid effluents are calculated for the entire downstream Tennessee River Population. Water ingestion population doses are calculated using actual population figures for downstream public water supplies. Fish ingestion population doses are calculated assuming that all sport fish caught in the Tennessee River are consumed by the Tennessee River population.

Recreation population doses are calculated using actual recreational data on the number of shoreline visits at downstream locations.

Population dose estimates for airborne and liquid effluents are presented in Tables 1A, 1B, 2A and 2B.

BFN Rad Impact July-December 1992 Page 6 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 External gamma radiation levels were measured by thermoluminescent dosimeters (TLDs) deployed around BFN. The quarterly gamma radiation levels determined from these TLDs during this reporting period averaged approximately 15.6 mR/quarter at onsite stations and approximately 13.8 mR/quarter at offsite stations, or approximately 1.8 mR/quarter higher onsite than at offsite stations. Thj.s is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than the levels offsite. This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plants, or other undetermined influences. Fluctuations in natural background dose rates and in TLD readings tend to mask any small increments which may be due to plant operations. Thus, there was no identifiable increase in dose rate levels attributable to direct radiation from plant equipment and/or gaseous effluents.

No routine activities within the site boundary by members of the public have been identified which would lead to their radiation exposure.

XQXhh MZ~

To determine compliance with 40 CFR 190, annual total dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources are considered.

The annual dose to any organ other than thyroid for the maximum individual is conservatively estimated by summing the following doses:

the total body air submersion dose for each quarter, the critical organ dose (for any organ other than the thyroid) from airborne effluents for each quarter from ground contamination, inhalation and ingestion, the total body dose from liquid effluents for each quarter, the maximum organ dose (for any organ other than the thyroid) from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for total body or any organ dose (other than thyroid) to determine compliance.

The annual thyroid dose to the maximum individual is conservatively estimated by summing the following doses'. the total body air submersion dose for each quarter, the thyroid dose from airborne effluents for each quarter, the total body dose from liquid effluents for each quarter, the thyroid dose from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for thyroid dose to determine compliance.

Cumulative annual total doses are presented in Table 3.

BFN Rad Impact July-December 1992 Page 7 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE lA Doses from Airborne Effluents Third Quarter 1992 Individual Doses Quarterly Percent ~~t'~

~tw~~ ~gij t External Gamma air 6.9E-03 mrad 5mrad < 1X NW/7400 meters Beta air 3.4E-03 mrad 10 mrad < 1 X NW/7400 meters Submersion Total Body 8.5E-03 mrem 10 mrad 1 X NE/3772 meters Skin 1.3E-02 mrem 10 mrad <11o NE/3772 meters Organ Doses Child/Liver 5.9E-02 mrem 7.5 mrem NNW/1791 meters Child/Thyroid 2.5E-02 mrem 7.5 mrem NNW/1791 meters Child/Total Body 7.6E-03 mrem 7.5 mrem <1X, NNW/1791 meters Population Doses 1.7E-01 man-rem 1.9E-Ol man-rem (bone)

Population doses can be compared to the natural background dose for the entire 50-mile population of about 56,430 man-rem/yr (base'd on 90 mrem/year for natural background).

BFN Rad Impact July-December 1992 Page 8 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 1B Doses from Airborne Effluents Fourth Quarter 1992 Indivudual Doses Quarterly Percent J.agent~

~t~w Q,~t Q~~m' External Gamma air 1.4E-02 mrad 5 mrad < 1 X NW/7600 meters Beta air 6.8E-03 mrad 10 mrad < 1 X NW/7600 meters Submersion Total Body 1.7E-02 mrem 10 mrad < 1 X SSE/6706 meters Skin 2.6E-02 mrem 10 mrad < 1 X SSE/6706 meters Organ Doses Child/Liver 4.9E-02 mrem 7.5 mrem < 1 X NNW/1791 meters Child/Thyroid 4.6E-02 mrem 7.5 mrem < 1 X NNW/1791 meters Child/Total Body 4.4E-02 mrem 7.5 mrem < 1 X NNW/1791 meters Population Doses 4.7E-01 man-rem 4.8E-01 man-rem (liver)

Population doses can be compared to the natural background dose for the entire 50-mile population of about 56,430 man-rem/yr (based on 90 mrem/year for natural background).

BFN Rad Impact July-December 1992 Page 9 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 2A Doses from Liquid Effluents Third Quarter 1992 Individual Dose (mrem) hm G~p Qxgaa Dose Quarterly Percent of

~m nQ ~~t ~gj t Adult Total Body 4.8E-02 1.5 mrem 3.2X Teen Liver 7.2E-02 5 mrem 1.5X Child Thyroid 5.8E-03 5 mrem < 1.0X Average Riverflow past BFH (cubic feet per second): 35,275 Population Doses 4.3E-Ol man-rem 6.4E-01 man-rem (liver)

Population doses can be compared to the natural background dose for the entire 50-mile population of about 56,430 man-rem/yr (based on 90 mrem/year for natural background).

BFN Rad Impact July-December 1992 Page 10 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 2B Doses from Liquid Effluents Fourth Quarter 1992 Individual Dose (mrem)

Dose Quarterly Percent of

~~t ~~@ t Adult Total Body 2.4E-02 1.5 mrem 2 7o Teen Liver 3.5E-02 5 mrem < 1 X Child Thyroid 3.5E-03 5 mrem < 1 X Average Riverflow past BFN (cubic feet per second): 61,988 Population Doses 1.7E-01 man-rem 2.8E-01 man-rem (liver)

Population doses can be compared to the natural background dose for the entire 50-mile population of about 56,430 man-rem/yr (based on 90 mrem/year for natural background).

0 BFN Rad Impact July-December 1992 Page 11 of 67 Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 3 Total Dose from Fuel Cycle First Second Third Fourth gg~t Qlmz t~ Qg~t Qgg~t Total Body or any Organ (except thyroid)

Total body air submersion 1.2E-03 6.4E-03 8.5E-03 1.7E-02 Critical organ dose (air) 6.0E-03 1.6E-02 5.9E-02 4.9E-02 Total body dose (liquid) 1.2E-02 4.7E-02 4.8E-02 2.3E-02 Maximum organ dose (liquid) 1.7E-02 6.8E-02 7.2E-02 3.4E-02 Direct radiation dose O.OE-OO O.OE-OO O.OE-OO O.OE-OO Total 3.6E-02 1.4E-01 1.9E-01 1.2E-01 Cumulative Total Dose (Total Body or other organ) mrem 4.9E-01 Annual Limit mrem 2.5E+01 Percentage of Limit 2 'X Thyroid Dose (mrem)

Total body air submersion 1.2E-03 6.4E-03 8.5E-03 1.7E-02 Thyroid dose (airborne) 6.0E-03 1.6E-02 2.5E-02 4.6E-02 Total body dose (liquid) 1.2E-02 4.7E-02 4.8E-02 2.3E-02 Thyroid dose (liquid) 3.9E-03 4.9E-03 5.8E-03 3.5E-03 Direct radiation dose O.OE-OO O.OE-OO O.OE-OO O.OE-OO Total (Thyroid) 2.3E-02 7.4E-02 8.7E-02 9.0E-02 Cumulative Total Dose (Thyroid) mrem 2.7E-01 Annual Limit mrem 7.5E+01 Percentage of Limit < 1 X

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 4A, Joint Frequency Distribution in Percent for Ground Level Releases Third Quarter 1992

D5: 55 Nlil 5 14lya4 4 July ember 1992 JOINT PERCENTAGE FREQUENCIES OF D SPEED BY Wl'ND DIRECTZON FOR Page 1 67 STABILITY CLASS A ( T<=-1. 9 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 14 92 SEP 304 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-15.4 18.5-24.4 >5*24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.187 0.0 0.0 0.0 0.187 NNE 0.0 0.0 0.0 0.0 0.0 0.890 0.094 0 ' 0.0 0.984 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 a.o 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 0.609 0 ~ 094 0.0 0.0 0.0 Q.a 0.703 SE 0.0 0.0 0.187 0.797 0.0 0.0 0.0 0.0 0.0 0.984 SSE 0.0 0.0 0.984 0.187 0.0 0.0 0.0 0.0 0.0 1.172 S 0 ' 0.047 0.328 0.375 0.0 0.0 0.0 0.0 0.0 0.750 SSW 0.0 0.0 0.047 0.281 0.0 0.0 0.0 0 ' 0.0 0.328 SW a.a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.047 0.0 0.0 Q.Q 0.0 0.0 o.a47 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0 ' 0.0 0.0 0.0 0.0 0.047 0.0 0 ' 0.0 0.047 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0 0 0.047 1.546 2.'296 0.094 1.125 0.094 0.0 0.0 5. 201 TOTAL HOURS OF VALZD STABILITY OBSERVATIONS 2167 TOTAL HOURS OF STABILITY CLASS A 112 TOTAL BOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 111 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2134 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACZLZTY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEH 10.03 AHD 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED a 5 ' MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UHROUNDED NUMBERS

srN mm Impact July ember 1992 JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS B (- DELTA-T<m-1. 7 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DZRECTION CALM 0.6-1.4 1.5-3.4 3.5-5 ' 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.094 0.0 0.0 0.0 0.094 NNE 0.0 0.0 0.0 0.0 0.094 0.234 0.0 0 ~ 0 0.0 0.328 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 0.047 0.0 0.047 0.0 0.0 0.0 0.0 0.094 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 0.047 0.187 0.047 0.0 0.0 0.0 0.0 0.281 SE 0.0 0.0 0.515 0.187 0.0 0.0 0.0 0.0 0.0 0.703 SSE 0.0 0 ' 0.375 0.094 0.0 0.0 0.0 0.0 0.0 0.469 S 0 ' 0.0 0.562 0.047 0.0 0.0 0.0 0.0 0.0 0.609 SSW 0.0 0.0 0.094 0.141 0.0 0.0 0.0 0.0 0.0 0.234 SW 0.0 0.0 0.094 0.187 0.047 0.0 0.0 0.0 0.0 0.328 WSW 0.0 0.0 0.0 0.0 0.094 0.0 0.0 0 ' 0.0 0.094 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.047 0.047 0.047 0.0 0.0 0.0 0.141 NNW 0.0 0.0 0.0 0.0 0.047 0.0 0.0 0 ' 0.0 0.047 SUBTOTAL 0 ' 0.0 1.734 0.890 0.422 0.375 0.0 0.0 0.0 3.421 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2167 TOTAL HOURS OF STABZl ZTY CLASS B 74 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B '73 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2134 TOTAL HOURS CALM 0 METEOROLOGICAl FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED OH LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEl DATE PRINTED: 10/22/92 MEAN WIND SPEED ~ 4.3 MPH NOTE- TOTALS AND SUBTOTALS ABOVE ARE OBTAZHED FROM UNROUNDED NUMBERS

BFN RAD mpact July ember 1992 JOINT PERCENTAGE FREQUENCIES 0 SPEED BY WIND DIRECTION FOR Page 67 STABZLITY CLASS C (-1 DELTA-T<~-1. 5 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7 . 5-12 . 4 12. 5-18 . 4 18 . 5-24 . 4 )R24.5 TOTAL N 0.0 0.0 0.0 0.234 0.047 0.047 0.0 0.0 0.0 0.328 NNE 0.0 0.0 0.0 0.141 0.234 0.187 0.047 0.0 0.0 0.609 NE 0.0 0.0 0.0 0.234 0.047 0.047 0.0 0.0 0.0 0.328 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 0.047 0.141 0.0 0.0 0.0 0.0 0.0 0. 187 SE 0.0 0.0 0.515 0.187 0.047 0 ' 0.0 0.0 0.0 0.750 SSE 0.0 0.0 0.797 0.047 0.0 0.0 0.0 0.0 0.0 0.843 S 0.0 0.0 0.656 0.094 0.0 0.0 0.0 0.0 0.0 0.750 SSW 0.0 0.0 0.187 0.234 0.0 0.0 0.0 0.0 0.0 0.422 SW 0.0 0.0 0.094 0.187 0.0 0.0 0.0 0.0 0.0 0.281 WSW 0.0 0.0 0.047 0.187 0.141 0.094 0.0 0.0 0.0 0.469 W 0.0 0.0 0.0 0.328 0.187 0.234 0.0 0.0 0.0 0.750 WNW 0.0 0.0 0.0 0.0 0.0 0.047 0.0 0.0 0.0 0.047 NW 0.0 0.0 0.0 0.0 0.281 0.422 0.0 0.0 0.0 0.703 NNW 0.0 0.0 0.0 0.0 0.0 0.094 0.047 0.0 0.0 0.141 SUBTOTAL 0.0 0.0 2.343 2.015 0.984 1.172 0.094 0.0 0.0 6.607 TOTAL HOURS OF VALID STABZLITY OBSERVATIONS 2167 TOTAL HOURS OF STABILITY CLASS C 142 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C 141 TOTAL HOURS OF VALID WIND DIRECTION-WZND SPEED-STABILITY OBSERVATIONS 2134 TOTAL HOURS CALM 0 METEOROLOGICAL FACZLITY: MET FACILITY LOCATED 1. 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED ~ 5 ' MPH NOTE: TOTAIS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

51'5 EAU Zmpac E JOINT PERCENTAGE FREQUENCIES OF D SPEED BY WIND DIRECTION FOR July ember 1992 Page 67 STABILITY CLASS D (- ELTA-T<m-0.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 - SEP 30, 92 WIND WIND SPEED(MPH }

DIRECTION CALM 0.6-1 ~ 4 1.5-3.4 3.5-5.4 5.5-7 ' 7.5-12.4 12.5-18.4 18.5-24.4 za.s TOTAL N 0.002 0.047 0.422 0.562 0.469 0.609 0.0 0.0 0.0 2. 111 NHE 0.002 0.0 0.469 0.375 0.328 0.890 0.0 0.0 0.0 2.064 HE 0.003 0.0 0.562 0.234 0.515 0.187 0.0 0.0 0.0 1.502 ENE 0.003 0.047 0.656 0.375 0.047 0.047 0.0 0.0 0.0 1.175 E 0.002 0.047 0.469 1.172 0 '62 0.187 0.047 0.0 0.0 2.486 ESE 0.005 0.141 0.984 0.843 0.937 0.0 0.0 0.0 0.0 2.910 SE 0.010 0.094 2.109 0.984 0.047 0.047 0.0 0.0 0.0 3.290 SSE 0. 013 0.187 2.671 0.187 0.0 0.0 0.0 0.0 0.0 3.059 S 0.019 0.422 3.796 0.890 0.0 0.0 0.0 0.0 0.0 5. 127 SSW 0.013 0.281 2.577 1.125 0.0 0.0 0.0 0.0 0.0 3.996 SW 0.008 0 '75 1.453 0.375 0.0 0.0 0.0 0.0 0.0 2.211 WSW 0.007 0.187 1.359 1.593 0.843 0.234 0.0 0.0 0.0 4.224 W 0.003 0.094 0.469 1.125 1.265 0.187 0.0 0.0 0.0 3.142 WNW 0.001 0.047 0.187 0.281 0.375 0.469 0.0 0.0 0.0 1.360 NW 0.001 0.047 0.187 0.422 0.281 0.703 0.234 0.0 0.0 1.875 NNW 0.002 0.141 0.234 0.515 0.094 0.094 0.094 0.047 0.0 1.220 SUBTOTAL 0.094 2.156 18.604 11.059 5.764 3.655 0.375 0.047 0.0 41.752 TOTAL HOURS OF VAIZD STABILITY OBSERVATIONS 2167 TOTAL HOURS OF STABILITY CLASS D 897 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 891 TOTAL HOURS OF VALID WIND DZRECTIOH-WIND SPEED-STABILITY OBSERVATIONS 2134 TOTAL HOURS CALM 2 METEOROLOGICAL FACILITYs MET FACZLZTY lOCATED 1 - 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZLITY BASED ON LAPSE RATE MEASURED BETWEEH 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED ~ 4.2 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

0 DrN rCnu XmPaC:C July cember 1992 JOINT PERCENTAGE FREQUENCIES OF D SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS E (- ELTA-T<~ 1.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 '~24.5 TOTAL N 0.052 0.094 0.750 0.937 0.234 0.187 0.0 0.0 0.0 2.254 NNE 0.043 0.187 0.515 0.422 0.141 0.0 0.0 0*0 0.0 1.308 NE 0.040 0.141 0.515 0 ~ 141 0.141 0.0 0.0 0 ' 0.0 0.977 ENE 0.106 0.656 1.078 0.281 0.047 0.0 0.0 0.0 0.0 2. 168 E 0.126 0.375 1.687 1.687 0.094 0.094 0.047 0 ' 0.0 4.109 ESE 0.129 0.515 1.593 0.797 0.047 0.047 o.a o.a 0.0 3.128 SE 0.109 0.562 1.218 0.234 0.0 0 ' 0.0 0.0 0.0 2.124 SSE 0.097 0.797 0.797 0.047 0.0 0.0 0.0 0.0 0.0 1.737 S 0.100 0.562 1.0'78 0.141 0.0 0.0 0.0 0.0 0.0 1.881 SSW 0.077 0.750 0.515 0.047 0.0 0.0 0.0 0 ~ 0 0.0 1.389 SW 0.052 0.328 0.515 0.047 0.047 0 ' 0.0 0.0 0.0 0.989 WSW 0.072 0.281 0.890 0.141 0.0 0.047 0.0 0 0 0.0 1.430 W 0.040 0.141 0.515 0.0 0.094 0' 0.0 0.0 0.0 0.790 WNW 0.014 0.047 0.187 0.047 0.0 a.o 0.0 0.0 0.0 0.295 NW 0.023 0.141 0.234 0.047 0.094 0.0 0.0 0.0 0.0 0.538 NNW 0.046 0.047 0.703 0.375 0.0 0.094 0.0 0 ' 0.0 1.264 SUBTOTAL 1.125 5.623 12 '93 5.389 0.937 0.469 0.047 0' 0.0 26.382 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2167 TOTAL HOURS OF STABILITY CLASS E 574 TOTAL HOURS OF VALZD WIND DIRECTION-WIND SPEED-STABZLITY CLASS E 563 TOTAL HOURS OF VALZD WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2134 TOTAL HOURS CALM 24 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10 ~ 42 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED ~ 2.7 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

mpact JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABILITY CLASS F DELTA-T<~ 4.0 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0 '-1 ' 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >>24.5 TOTAL N 0.106 0.234 0.890 0.562 0.0 0.0 0.0 0.0 0.0 1.793 NNE 0.098 0.281 0.750 0.609 0.047 0.047 0 ' 0.0 0.0 1.831 NE 0.035 0.047 0.328 0.047 0.047 0.0 0.0 0.0 0.0 0.504 ENE 0. 071 0.141 0.609 0.562 0.0 0.0 0.0 0.0 0.0 1.383 E 0.124 0.328 0.984 0.375 0.0 0.0 0.0 0.0 0.0 1.811 ESE 0.022 0.094 0.141 0.0 0.0 0.0 0.0 0.0 0.0 0.256 SE 0.022 0.141 0.094 0.0 0.0 0.0 0.0 0.0 0.0 0.256 SSE 0.022 0.187 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.256 S 0.018 0.141 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.205 SSW 0.031 0.187 0.141 0.0 0.0 0.0 0.0 0.0 0.0 0.359 SW 0.004 0.0 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0. 051 WSW 0.013 0.094 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.154 W 0.004 0.0 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.051 WNW 0.004 0.047 0.0 0.0 0;0 0.0 0.0 0.0 0.0 0.051 NW 0.035 0.141 0.234 0.0 0.0 0.0 0.0 0.0 0.0 0.410 NNW 0.044 0.141 0.328 0.094 0.0 0.0 0.0 0.0 0.0 0.607 SUBTOTAL 0.656 2.202 4.733 2.249 0.094 0.047 0.0 0.0 0.0 9.981 TOTAL HOURS OF VAZZD STABILITY OBSERVATIONS 2167 TOTAL HOURS OF STABILITY CLASS F 219 TOTAZ HOURS OF VALZD WIND DZRECTZON-WIND SPEED-STABILITY CLASS F 213 TOTAL HOURS OF VALID WIND DZRECTZON-WIND SPEED-STABZLZTY OBSERVATIONS 2134 TOTAL HOURS CALM 14 METEOROLOGICAL FACILITY: MET FACZLITY LOCATED 1. 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED ~ 2.4 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

or ll nnu ~uipai a.

JOINT PERCENTAGE FREQUENCIES OF 'D SPEED BY WIND DIRECTZOH FOR July Page F'ember 67 1992 STABZLITY CLASS G { > 4.0 C/100 M)

BROWHS FERRY NUCLEAR PLANT JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0 ~ 6-1.4 1.5-3.4 3.5-5.4 5.5-7 ' 7.5-12.4 12.5 18.4 18.5-24.4 >=24.5 TOTAL N 0.342 0.656 1.172 0.281 0.0 0.0 0.0 0.0 0.0 2.450 NNE 0.2&9 0.609 0. 937 0.141 0.141 0.0 0.0 0.0 0.0 2.117 NE 0.088 0.328 0.141 0.0 0.0 0.0 0.0 0.0 0.0 0.556 ENE 0.123 0.141 0.515 0.141 o.a 0.0 0.0 0 ' 0.0 0.919 E 0.035 0.141 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.222 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 0.0 0.0 Q.o 0.0 0.0 0.0 0 ' 0.0 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 0.0 Q.Q a.o 0.0 0 ' 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0~0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 a.a 0.0 0.0 0.0 W 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.009 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.056 NNW 0.053 0.234 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.334 SUBTOTAL 0.937 2.156 2.858 0.562 0.141 0.0 0.0 0.0 Q.o 6.654 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2167 TOTAL HOURS OF STABZLITY CLASS G 149 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G 142 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2134 TOTAL HOURS CALM 20 METEOROLOGZCAL FACILITY: MET FACILZTY LOCATED 1.3 KM ESE OF BROWNS FERRY HUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10 03 AND 45.30 METERS WZND SPEED AND DZRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED a 1.9 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 4B Joint Frequency Distribution in Percent for Ground Level Releases Fourth Quarter 1992

JOINT PERCENTAGE FREQUENCIES OF D SPEED July ocember 1992 BY WZND DIRECTION FOR Page 67 STABZLITY CLASS A (D <=-1.9 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1 '-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24 ' >~24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.046 0.0 0.0 0.0 0.046 NNE 0.0 0.0 0.0 0.0 0.046 0.463 0.0 0.0 0.0 0. 509 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 E 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.046 0.231 0.324 0.0 0.0 0.0 0.0 0. 601 SE 0.0 0.0 0.139 1.156 0.278 0.0 0.0 0.0 0.0 1.573 SSE 0.0 0.0 0.278 0.463 0.046 0.0 0.0 0.0 0.0 0.786 S 0.0 0.0 o.o46 0.463 0.0 0.0 0.0 0.0 0.0 0.509 SSW 0.0 0.0 0.046 0.093 0.0 0.0 0.0 0.0 0.0 0.139 SW 0.0 0.0 0.046 0.046 0.0 0.0 0.0 0.0 0.0 0.093 WSW 0.0 0.0 0.0 0.0 0.046 0.046 0.0 0.0 0.0 0.093 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.046 0.093 0.0 0.0 0.139 NNW 0.0 0.0 0.0 0.0 0.0 0.046 0.046 0.0 0.0 0.093 SUBTOTAL 0.0 0.0 0.601 2.451 0.740 0.648 0.139 0.0 0.0 4.579 TOTAL HOURS OF VALZD STABILITY OBSERVATZONS 2195 TOTAL HOURS OF STABILITY CLASS A 99 TOTAL HOURS OF VALID WIND DZRECTZON-WIND SPEED-STABILITY CLASS A 99 TOTAL HOURS OF VALID WZND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1 ' KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WZND SPEED AND DIRECTZON MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED RR 5 ' MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

r mpac JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABZZITY CLASS B (- DELTA-T<=-1.7 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 - DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >24.5 TOTAL N 0.0 0.0 0.0 o.o46 0.093 0.139 0.046 0.0 0.0 0.324 NNE 0.0 0.0 0.0 0.0 0.093 0.278 0.0 0.0 0.0 0.370 HE 0.0 0.0 0.0 0.0 0.0 0.046 0.0 0.0 0 ' 0.046 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 ESE 0.0 0.0 0.0 0.231 0.0 0.0 0.0 0.0 0.0 0.231 SE 0.0 0.0 0.093 0.185 0. 139 0.046 0.0 0.0 0.0 0.463 SSE 0.0 0.0 0.0 0.093 0.0 0.0 0.0 0.0 0.0 0.093 S 0.0 0.0 0.278 0.046 0.0 0.0 0.0 0.0 0.0 0.324 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.093 0.093 0.0 0.0 0.0 0.0 0.0 0.185 WSW 0.0 0.0 0.0 0.093 0.0 0.093 0.0 0.0 0.0 0.185 W 0.0 0.0 0.0 0.0 0.185 0.0 0.0 0.0 0.0 0.185 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.093 0.0 0.0 0.093 NW 0.0 0.0 0.0 0.0 0.0 0.093 0.046 0.0 0.0 0.139 HNW 0.0 0.0 0.0 0.0 0.0 0.093 0.0 0.0 0.0 0.093 SUBTOTAL 0.0 0.0 0.463 0.786 0.509 0.786 0.185 0.0 0.0 2.729 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS B 59 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B 59 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED ~ 6. 8 MPH NOTE: TOTALS AND SUBTOTAIS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

mp July cember 1992 JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WZND DIRECTION FOR Page 67 STABZLZTY CLASS C (- DEITA-T<~-1.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WZND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12 4 12.5-18.4 18.5-24.4 >=24.5 TOTAL H 0.0 0.0 0.0 0.093 0.139 0.231 0.0 0.0 0.0 0.463 NNE 0.0 0.0 0.0 0.046 0.093 0.324 0.0 0.0 0.0 0.463 NE 0.0 0.0 0.0 0.093 0.046 0.093 0.0 0.0 0.0 0. 231 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 0.139 0.0 0.0 0.0 0.0 0.0 0.139 SE 0.0 0.0 0.278 0.093 0.139 0 '93 0.0 0.0 0.0 0. 601 SSE 0.0 0.0 0.231 0.093 0.046 0.0 0.0 0.0 0.0 0.370 S 0.0 0.046 0.093 0.0 0.046 0.0 0.0 0.0 0.0 0.185 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.139 0.0 0.0 0.0 0.0 0.0 0.139 WSW 0.0 0 ' 0.0 0.185 0.139 0.093 0.0 0.0 0.0 0.416 W 0.0 0.0 0.0 0.093 0.046 0.0 0.0 0.0 0.0 0.139 WNW 0.0 0.0 0.0 0.046 0.139 0.093 0.046 0.0 0.0 0.324 NW 0.0 0.0 0.0 0.046 0.046 0.278 0.046 0.0 0.0 0. 416 NNW 0.0 0.0 0.0 0.093 0.046 0.093 0.0 0.0 0.0 0. 231 SUBTOTAL 0.0 0.046 0.601 1.156 0.925 1.295 0.093 0.0 0.0 4.117 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS C 89 TOTAL HOURS OF VALID WIND DIRECTZOH-WIND SPEED-STABILITY CLASS C 89 TOTAL HOURS OF VALID WIND DIRECTION-WIHD SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DZRECTZOH MEASURED AT THE 10.42 METER IEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED ~ 6.3 MPH NOTE TOTALS AND SUBTOTALS ABOVE ARE OBTAZNED FROM UNROUNDED NUMBERS

BFN RAD Impact JOINT PERCENTAGE FREQUENCIES 0 July ember 1992 SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS D (- DELTA-T<I-0.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED{MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12. 4 12. 5-18. 4 18. 5-24. 4 )5524.5 TOTAL N 0.0 0.0 0.324 0.971 1.434 1. 804 0.324 0.046 0.0 4.903 NNE 0.0 0.0 0.185 0.648 0.601 0. 879 0.139 0.0 0.0 2.451 NE 0.0 0.0 0.185 0.278 0.786 0.786 0.0 0.0 0.0 2.035 ENE 0.0 0.093 0.278 0.370 0.324 0.139 0.0 0.0 0.0 1.203 E 0.0 0.093 0.648 0.463 0.0 0.0 0.0 0.0 0.0 1.203 ESE 0.0 0.093 0.694 1.203 0.416 0.046 0.046 0.0 ' 2.498 SE 0.0 0.0 0.093

0. 231

l. 619 0.971 1.434 0.833 0.0 0 '

0 0.0 4.949 SSE 1.758 0.833 0.185 0.139 0.0 0.0 0.0 3.145 S 0.0 0.370 0.925 0.694 0.231 0.046 0.0 0.0 0.0 2.266 SSW 0.0 0.185 0.648 0.278 0.046 0.093 0.0 0.0 0.0 1.249 SW 0.0 0.0 0.324 0.093 0.046 0.046 0.0 0.0 0.0 0.509 WSW 0.0 0.0 0.509 0.416 0. 231 0.324 0.0 0.0 0.0 1.480 W 0.0 0.046 0.231 0.>40 0.601 0.740 0.0 0.0 0.0 2.359 WNW 0.0 0.0 0.185 0.463 0.231 0.971 0.324 0.093 0.0 2.266 NW 0.0 0.0 0.555 0.555 0.463 0.786 0.463 0.093 0.0 2.914 NNW 0.0 0.0 0.185 1 ~ 064 1.665 2.498 0.185 0.0 0.0 5.597 SUBTOTAL 0.0 1.203 9.251 10.037 8.696 10.130 1.480 0.231 0.0 41.027 TOTAL HOURS OF VALID STABZLZTY OBSERVATZONS 2195 TOTAL HOURS OF STABILITY CLASS D 890 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABZIITY CLASS D 887 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 0 METEOROLOGICAL FACZLZTY: MET FACZLITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10 WIND SPEED AND DIRECTION MEASURED AT THE 10 '2 '3 AND 45.30 METERS METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED ~ 640 MPH NOTE TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

mpact JOINT PERCENTAGE FREQUENCIES 0 July ember 1992 SPEED BY WIND DIRECTION FOR Page 67 STABZLZTY CLASS E (- ELTA-T<= 1 ~ 5 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 - DEC 31, 92 WIND WIND SPEEDtMPH)

DIRECTION CALM 0.6-1 ~ 4 1.5-3.4 3.5-5.4 5 '-7 ' 7.5-12.4 12.5-18.4 18.5-24 ' >>24.5 TOTAL N 0.002 0.046 0.278 0.971 0.324 0. 185 0.0 0.0 0.0 1.806 NNE 0.002 0.046 0.278 0.324 0.231 0.093 0.0 0.0 0.0 0.974 NE 0.004 0.185 0.324 0.694 0.648 0.185 0.0 0.0 0.0 2.039 EHE 0.005 0.139 0.601 0.185 0.139 0.046 0.0 0.0 0.0 1.115 E 0.006 0.231 0.555 0.555 0.093 0.0 0.0 0.0 0.0 1.439 ESE 0.008 0.139 0.925 1.388 0.324 0.093 0.0 0.0 0.0 2.875 SE 0.016 0.509 1.758 0.971 0.648 0.509 0 ' 0.0 0.0 4.410 SSE 0.022 0.278 2.821 0.740 0.463 0.093 0.0 0.0 0.0 4.416 S 0.009 0.139 1.064 0.833 0.324 0.046 0.0 0.0 0.0 2. 414 SSW 0.003 0.139 0.324 0.185 0.093 0.0 0.0 0.0 0.0 0.743 SW 0.004 0.093 0.416 0.0 0.093 0.0 0.0 0.0 0.0 0.605 WSW 0.004 0.231 0.324 0.416 0.185 0.046 0.0 0.0 0.0 1.207 W 0.002 0.046 0.185 0.231 0,0 0.093 0.0 0 0 0.0 0.557 WNW 0.001 0.046 0.093 0.278 0.185 0.0 0.0 0.0 0.0 0.602 NW 0.002 0.046 0.231 0.324 0.370 0.185 0.0 0.0 0.0 1.158 NNW 0.004 0.185 0.370 0.555 0.694 0.370 0.046 0.0 0.0 2.224 SUBTOTAL 0.093 2.498 10.546 8.649 4 F 810 1.943 0.046 0.0 0.0 28.585 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CIASS E 623 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 618 TOTAL HOURS OF VALID WZND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 2 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1 ~ 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45-30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEI DATE PRINTED'1/14/93 MEAN WIND SPEED ~ 4.0 MPH NOTE: TOTALS AND SUBTOTAIS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

July cember 1992 JOZNT PERCENTAGE FREQUENCIES OF SPEED BY WIND DIRECTION FOR Page 67 STABZI ITY CLASS F ELTA-T<= 4 0 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.009 0.0 0.324 0.601 0.046 0.0 0.0 0.0 0.0 0.980 NNE 0.006 0.046 0.185 0.601 0.231 0.0 0.0 0.0 0.0 1. 070 NE 0.008 0.093 0.185 0.093 0.046 0.0 0.0 0.0 0.0 0.424 ENE 0 '13 0.139 0.324 0.324 0.139 0.0 0.0 0.0 0.0 0.938 E 0 '31 0.185 0.925 0.509 0.0 0.0 0.0 0.0 0.0 1.650 ESE 0.026 0.231 0.694 0.463 0.0 0.0 0.0 0.0 0.0 1.413 SE 0.027 0.231 0.740 0.139 0.093 0.0 0.0 0.0 0.0 1.230 SSE 0.039 0.278 1. 110 0.231 0.093 0.046 0.0 0.0 0.0 1.796 S 0.006 0.093 0.139 0.185 0.046 0.046 0.0 0.0 0.0 0.515 SSW 0.005 0.0 0.185 0.0 0.0 0.0 0.0 0.0 0.0 0.190 SW 0.003 0.046 0.046 0.0 0.0 0.0 0.0 0.0 0.0 0.095 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.001 0.0 0.046 0.0 0.0 0.0 0.0 0.0 0.0 0.048 NW 0.004 0.0 0.139 0.324 0.0 0.0 0.0 0.0 0.0 0.466 NNW 0.006 0.046 0.185 0.324 0.0 0.0 0.0 0.0 0.0 0.562 SUBTOTAL 0.185 1.388 5.227 3.793 0.694 0.093 0.0 0.0 0.0 11.378 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS F 252 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 246 TOTAI HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 4 METEOROLOGZCAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZIZTY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS WIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED = 3.1 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

ip July cember 1992 JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS G tD T ) 4. 0 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 24 .5 TOTAL N 0.154 0.324 0.740 0.278 0.0 0.0 0.0 0 ' 0.0 1.496 NNE 0.134 0.370 0.555 0 '24 0.0 0.0 0.0 0.0 0.0 1.383 NE 0.107 0.231 0.509 0.046 0.0 0.0 0.0 0.0 0.0 0.894 ENE 0.114 0.093 0.694 0.046 0.0 0.0 0.0 0.0 0.0 0.947 E 0.107 0.278 0.463 0.278 0.0 0.0 0.0 0.0 0.0 1.125 ESE 0.013 0.046 0.046 0.0 0.0 0.0 0.0 0.0 0.0 0.106 SE 0.034 0.139 0.093 0.0 0.0 0.0 0.0 0.0 0.0 0.265 SSE 0.074 0.324 0.185 0.0 0.0 0 ' 0.0 0.0 0.0 0.583 S 0.034 0.231 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.265 SEW 0.013 0 '93 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.106 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.013 0.093 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.106 NNW 0.034 0.185 0.046 0.046 0.0 0.0 0.0 0.0 0.0 0.311 SUBTOTAL 0.833 2.405 3.330 1.018 0.0 0.0 0.0 0.0 0 ' 7.586 TOTAL HOURS OF VALID STABZLITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS G 183 TOTAL HOURS OF VALID WZND DIRECTION-WIND SPEED-STABZLZTY CLASS G 164 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2162 TOTAL HOURS CALM 18 METEOROLOGICAL FACZLZTY: MET FACZLITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45 WIND SPEED AND DIRECTION MEASURED AT THE 10 '2 METER LEVEL

'0 METERS DATE PRINTED: 01/14/93 MEAN WIND SPEED ~ 1.9 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 5A.

Joint Frequency Distribution in Percent for Split-Level Releases Ground Level Portion Third quarter 1992

kl4 ~4 4 July cember 1992 SPLZT JOINT PERCENTAGE PREQUENCI F WIND SPEED BY WIND DZRECTZON FOR Page 67 STABILITY CLASS A A T<~-1.9 C/100 M)

BROWNS PERRY NUCLEAR PIANT PART 1 OF 2 GROUND LEVEL REIEASE MODE JUL 1, 92 - SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.4-4.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5<<12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.035 0.0 0.0 0.0 0.035 NNE 0.0 0.0 0.0 0.0 0.0 0.157 0.019 0.0 0.0 0:176 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 o.a 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 0.042 0.010 0.0 0.0 0.0 0.0 0.052 SE 0.0 0.0 0.005 0.043 0.0 0.0 0.0 0.0 0.0 0.04&

SSE 0.0 0.0 0.045 0.009 0.0 0.0 0.0 0.0 0.0 0.054 S 0.0 0.0 0.029 0.055 0.0 a.o 0.0 0.0 0.0 0.084 SSW 0.0 0.0 0.007 0.015 0.0 0.0 0.0 0.0 0.0 0.021 SW 0.0 0.0 0.0 0.0 0 ~0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a W 0.0 0.0 0.0 0.007 0.0 0.0 0.0 0.0 0 ' 0.007 WHW 0.0 0.0 0.0 0.0 0.0 O.a 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.008 0.0 0.0 0.0 0.008 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 SUBTOTAL 0.0 0.0 0.085 0.171 0.010 0.200 0.019 0.0 0.0 0.485 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF GROUND LEVEL RELEASE 128.630 TOTAL HOURS OP STABZLZTY CLASS A 10.200 TOTAL HOURS OF GROUND LEVEL STABIIZTY CLASS A 10.200 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BETWEEN 10.03 AHD 45.30 METERS WIND DIRECTION MEASURED AT 10 42 METER LEVEZ WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED: 10/22/92 4

NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

urn mm xmpacr.

SPLIT JOINT PERCENTAGE PREQUENCI WIND SPEED BY WIND DIRECTION POR July "ember 1992 Page 67 STABILZTY CLASS B DELTA T<~-1.7 C/100 M}

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND IEVEL RELEASE MODE JUL li 92 SEP 30 i 92 WIND WIND SPEED(MPH}

DIRECTION CALM 0. 6-1. 4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5 18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0. 012 0.0 0.0 0.0 0.012 NNE 0.0 0 ' 0.0 0.0 0.007 0.037 0.0 0.0 0.0 0.044 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 0.003 0.0 0 ' 0.0 0.0 0.003 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 a.o 0.0 ESE 0.0 0.0 0.0 0.015 0.004 0.0 0.0 0.0 0.0 0.019 SE 0.0 0.0 0.008 0.005 0.0 0.0 0 0 0.0 0.0 0.013 SSE 0.0 0.0 0.012 0.0 0.0 0.0 0.0 0.0 0.0 0.012 S 0.0 0.0 0.015 0.0 0.0 0.0 0.0 0.0 0.0 0.015 SSW 0.0 0.0 0.0 0.007 0.0 0.0 0.0 0.0 0.0 0.007 SW 0.0 0.0 0.002 0.0 0.007 0.0 0.0 0.0 0.0 0.009 WSW 0.0 0.0 0.0 0.0 0.012 0.0 0.0 0.0 o.a O.a12 W 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.001 0.003 0.007 0.0 0.0 0.0 0. 011 NNW 0.0 0 ' 0.0 0.0 0.003 0.0 0.0 0.0 0.0 0.003 SUBTOTAL 0.0 0 ' 0.038 0.028 0.040 0.056 0.0 0.0 0.0 0.161 TOTAL HOURS OP VALID OBSERVATIONS 2105.000 TOTAL HOURS OP GROUND LEVEL RELEASE 128.630 TOTAL HOURS OF STABZLZTY CLASS B 3. 380 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS B 3.380 METEOROLOGICAL=FACILITY: MET FACILITY LOCATED 1.3 KM ESE OP BROWNS FERRY NUCLEAR PLANT 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 LEVEI EPFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED PROM UNROUNDED NUMBERS

Pf g [gal/ l.lllp04 I SPLZT JOINT PERCENTAGE PREQUEHCZE F WIND SPEED BY WIND DZRECTIOH POR July ember 1992 Page 67 STABILITY CLASS C DEZTA T<~-1.5 C/100 M)

BROWNS PERRY NUCLEAR PLANT PART 1 OP 2 GROUND LEVEL RELEASE MODE JUL 1, 92 SEP 30, 92 WIND WIND SPEEDtMPH)

DIRECTION CALM 0 '-1.4 1.5-3.4 3.5-5.4 5.5-7 ' 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0.000 0.005 0.009 0.0 0.0 0.0 0.014 NNE 0 ~0 0.0 0.0 0.004 0.020 0.030 0. 010 0.0 0.0 0.065 NE 0.0 0.0 0.0 0.002 0.003 0.006 0.0 0.0 0.0 0.011 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 ESE 0.0 0.0 0 ' 0. 010 0". 0 0.0 0.0 0.0 0.0 0.010 SE 0 ' 0.0 0.019 0.017 0.007 0.0 0.0 0.0 0.0 0.043 SSE 0.0 0.0 0.029 0.0 0.0 0.0 0.0 0.0 0.0 0.029 S 0.0 0.0 0.004 0.011 0.0 0.0 0.0 0.0 0.0 0.015 SSW 0.0 0.0 0.0 0.005 0.0 0.0 0 ' 0.0 0.0 0.005 SW 0.0 0.0 0.0 0.009 0.0 0.0 0.0 0.0 0.0 0.009 WSW 0.0 0 ' 0.0 0.008 0.018 0. 016 0.0 0.0 0.0 0.041 W 0.0 0.0 0.0 0.003 0.019 0.036 0.0 0.0 0 ' 0 '59 WHW 0.0 0.0 0.0 0.0 0.0 0.005 0.0 0.0 0.0 0.005 HW 0.0 0.0 0.0 0 ' 0.019 0.062 0.0 0.0 0.0 0 ~ Q81 HHW 0.0 0.0 0.0 0.0 0.0 0.014 0.017 0.0 0.0 0.030 SUBTOTAL 0.0 0 ' 0.052 0.070 0.091 0.179 0.027 0.0 0.0 0.419 TOTAL HOURS OP VALID OBSERVATIONS 2105.000 TOTAL HOURS OP GROUND LEVEL RELEASE 128.630 TOTAL HOURS OF STABILITY CLASS C 13.810 TOTAL HOURS OP GROUND LEVEL STABILITY CLASS C 8. 810 METEOROLOGICAL PACZLITY: MET FACILITY LOCATED 1.3 KM ESE OP BROWNS FERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BETWEEN 10.03 AND 45.30 METERS WIND DIRECTION MEASURED AT 10.42 METER LEVEL WZHD SPEED MEASURED AT 10.42 METER LEVEL EFPLUENT VELOCITY II 12.60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAZNED PROM UNROUNDED NUMBERS

DPN 1CMJ Lmpac.c July -ember 1992 SPLIT JOZHT PERCENTAGE FREQUENCZ WIND SPEED BY WIND DIRECTION FOR Page 2 67 STABZLITY CLASS D DELTA T4:~-0. 5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE JUL 16 92 SEP 306 92 WIND WIND SPEEDtMPH)

DIRECTION CALM 5.6-3.4 1.5-3.4 3.5-5.4 5.5-3 ~ 4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL H 0.0 0.0 0.0 0.011 0.050 0.112 0.0 0.0 0.0 0.173 NHE 0.0 0.0 0.000 0.011 0.040 0.165 0 ' 0.0 0.0 0.217 NE 0.0 0.0 0.0 0.004 0.047 0.026 0.0= 0.0 0.0 0.077 EHE 0.0 0.0 0.0 0.015 0.005 0.008 0.0 0.0 0.0 0.028 E 0.0 0.0 0.0 0.066 0.076 0.034 0.012 0.0 0.0 0.188 ESE 0.0 0.0 0.007 0.078 0.155 0.0 0.0 0.0 0.0 0.241 SE 0.0 0.0 0.053 0.136 0.009 0.010 0.0 0.0 0.0 0.208 SSE 0.0 0.0 0.133 0.026 0.0 0.0 0.0 0.0 0.0 0.158 S 0.0 0.0 0.229 0.136 0.0 0.0 0 ' 0.0 0.0 0.366 SSW 0.0 0.001 0.074 0 '44 0.0 0.0 0.0 0.0 0.0 0.219 SW 0.0 0.0 0.027 0.024 0.0 0 ' 0.0 0.0 0.0 0.050 WSW 0.0 0.0 0.02& 0.079 0.124 0.040 0.0 0.0 0.0 0.271 W 0.0 0.0 0.0 0.028 0.129 0 '29 0.0 0.0 0.0 0.187 WHW 0.0 0.0 0.0 0.002 0.027 0.066 0.0 0.0 0.0 0.095 HW 0.0 0.0 0 ' 0.007 0.020 0.105 0.090 0.0 0.0 0.221 HNW 0.0 0.0 0.0 0.010 0.011 0. 014 0.037 0.048 0.0 0.119 SUBTOTAL 0.0 0.001 0.551 0.778 0.695 0.608 0.139 0.048 0.0 2.818 TOTAL HOURS OF VALID OBSERVATZOHS 2105.000 TOTAL HOURS OF GROUND LEVEL RELEASE 128.630 TOTAL HOURS OF STABILITY CLASS D 1241.070

'TOTAL HOURS OF GROUND LEVEI STABILITY CLASS D 59.320 METEOROLOGZCAZ FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10.03 AHD 45.30 METERS WIND DIRECTION MEASURED AT 10.42 METER LEVEL WIND SPEED MEASURED AT 10 EFFLUENT VELOCITY ~

'2 12.60 M/S METER LEVEL DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

DC 55 CQSJJ k444F454 ~

July cember 1992 SPLIT JOINT PERCENTAGE FREQUEHCZ WIND SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS E DELTA T(m 1 5 C/100 M)

BROWNS FERRY HUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE JUL 1 ~ 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 5.5-5.4 5.5-7.4 7 '-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.000 0.0 0.040 0.095 0.027 0.036 0.0 0.0 0.0 0.198 NNE O.OO0 O.o 0.022 o.o46 0.021 0.0 0.0 0.0 0.0 0.089 NE 0.000 0.005 0.009 0 ~ 016 0.020 0.0 0.0 0.0 0.0 0.050 ENE 0.000 0.011 0.025 0 ~ 019 0.007 0.0 0.0 0.0 0.0 0.063 E 0. 001 0.004 0.070 0.153 0 '13 0.025 0.032 0.0 0.0 0.298 ESE 0.001 0.004 0.084 0.090 0.008 0.010 0.0 0.0 0.0 0.197 SE 0.001 0.030 0.085 0.039 0.0 0.0 0.0 0.0 0.0 0. 156 SSE 0.001 0.030 0.077 0.009 0.0 0.0 0.0 0.0 0.0 0.117 S 0.001 0.028 0.072 0.026 0.0 0.0 0.0 0.0 0.0 0.127 SSW 0.000 0.015 0.019 0.008 0.0 0.0 0.0 0.0 0.0 0.043 SW 0.000 0.0 0.005 0.005 0 ' 0.0 0.0 0.0 0.0 0. 010 WSW 0.000 0.0 0.016 0.010 0.0 0.009 0.0 0.0 0.0 0.034 W 0.000 0.002 0.002 0.0 0.011 0.0 0.0 0.0 0.0 0.015 WNW 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 NW 0.0 0.0 0.0 0.0 0.013 0 ' 0.0 0.0 0.0 0.013 HHW 0.000 0.0 0.019 0.027 0.0 0.007 0.0 0.0 0.0 0.053 SUBTOTAL 0.007 0.129 0.545 0.543 0.119 0.086 0.032 0 ~0 0.0 1. 461 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF GROUND LEVEL RELEASE 128.630 TOTAL HOURS OF STABILITY CLASS E 636 F 080 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS E 30.760 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWHS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10.03 AHD 45 '0 METERS WIND DIRECTZOH MEASURED AT 10.42 METER LEVEL WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED HUMBERS

54 ~ ~ 5 July cember 1992 SPLZT JOINT PERCENTAGE FREOUEHCI WIND SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS F 4 DELTA TC~ 4.0 C/100 M)

BROWNS FERRY NUCZ EAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION 0.6-1.4 1.5-3.4 3 ~ 5-5 ' 5 '-7 ' 7.5-12.4 12.5-18.4 18.5-24.4 )~24.5 TOTAL H 0.000 0.0 0.057 0.065 0.0 0.0 0.0 0.0 0.0 0.122 NNE 0.000 0.0 0.048 0.091 0.009 0.010 0.0 0.0 0.0 0.157 NE 0.000 0.0 0.021 0.007 0.009 0.0 0.0 0.0 0.0 0.036 ENE 0.000 0.006 0.015 0.060 0.0 0.0 0.0 0.0 0.0 0.082 E 0 F 000 0.011 0.025 0.029 0.0 0.0 0.0 0.0 0.0 0.065 ESE 0.000 0.0 0.011 0.0 0.0 0.0 0.0 0.0 0.0 0.011 SE 0.000 0.005 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.008 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW Q.QQQ Q.O Q.OOO 0.0 0.0- 0.0 0.0 0.0 0.0 0.000 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 WHW 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 HW 0.000 0.0 0.000 0.0 0.0 0.0 0.0 0.0 0.0 O.OQO NNW 0.000 0.001 0.010 0.013 0.0 0.0 0.0 0.0 0.0 0.024 SUBTOTAL 0.001 0.024 0.190 0.265 0.018 0.010 0.0 0.0 0.0 0.506 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF GROUND LEVEL RELEASE 128.630 TOTAL HOURS OF STABILITY CLASS F 170.900 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS F 10.660 METEOROLOGICAL FACILITY: MET FACZLZTY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BETWEEN 10.03 AHD 45.30 METERS WIND DIRECTION MEASURED AT 10 '2 METER LEVEL WZND SPEED MEASURED AT 10.42 METER ZEVEL EFFLUENT VELOCITY ~ 12. 60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED HUMBERS

BFN RAD Impact SPLIT JOINT PERCENTAGE FREQUENCI WIND SPEED BY WIND DIRECTION FOR July 'ember 1992 Page 67 STABZLZTY CLASS G A T > 4 ' C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUHD IEVEL RELEASE MODE JUL 1, 92 SEP 30, 92 WIND WIND SPEEDtMPH)

DZRECTZOH CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >%24 5 TOTAL N 0.0 0.003 0.079 0.0 42 0.0 0.0 0.0 0.0 0.0 0.124 HNE 0.0 0.0 0.058 0.0 22 0.025 0.0 0.0 0.0 0.0 0.105 NE 0.0 0.0 0.005 0.0 0.0 0.0 0.0 0.0 0.0 0.005 ENE 0.0 0.0 0.011 0.0 08 0.0 0.0 0.0 0.0 0.0 0. 019 E 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.002 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 ' 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 HNW 0.0 0.0 0.006 0.0 0.0 0.0 0.0 0.0 0.0 0.006 SUBTOTAL 0.0 0.003 0.161 0.072 0.025 0.0 0.0 0.0 0.0 0.261 TOTAL HOURS OF VAIID OBSERVATIONS 2105.000 TOTAL HOURS OF GROUND LEVEL RELEASE 128.630 TOTAL HOURS OF STABZLZTY CLASS G 29.560 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS G 5.500 METEOROLOGICAL FACILZTY: MET FACZLZTY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10.03 AHD 45.30 METERS WZHD DIRECTION MEASURED AT 10.42 METER IEVEL WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 5B Joint Frequency Distribution in Percent for Split-Level Releases Elevated Portion Third Quarter 1992

July cember 1992 SPLIT JOINT PERCENTAGE FREQUENCI F WIND SPEED BY WIND DIRECTIOH FOR Page 67 STABILITY CLASS A A TC~ 1.9 C/100 M3 BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE JUL 1, 92 - SEP 30, 92 WIND WIHD SPEED(MPH3 DIRECTION CALM 0. 6-1. 4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL H 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 HNE 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 a.o 0.0 a.o 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 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0 ' 0 ' 0.0 F 0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0 ~0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 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 0.0 0.0 0.0 0 ' 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF ELEVATED RELEASES 1976.370 TOTAL HOURS OF STABILITY CLASS A 10.200 TOTAL HOURS OF ELEVATED STABILITY CLASS A 0.0 METEOROLOGICAL FACIZ ZTY: MET FACZLZTY LOCATED 1. 3 KM ESE OF BROWHS FERRY NUCLEAR PLANT STABILZTY BASED ON DELTA-T BETWEEH 45.30 AHD 89.59 METERS WIHD DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY ~ 12 '0 M/S DATE PRINTED: 10/22/92 HOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

B1'N KAD J.mpacc July ember 1992 SPLZT JOINT PERCENTAGE FREQUEHCI WIND SPEED BY WIND DZRECTZOH FOR Page 67 STABILITY CLASS B 4 DELTA T(~-1.7 C/100 M)

BROWHS FERRY NUCLEAR PLANT PART 2 OF 2 EZEVATED RELEASE MODE JUL 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5 ' 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL H 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HNE 0.0 0 ' 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.0 HE 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 a.o 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 WHW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 o.a 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF ELEVATED RELEASES 1976.370 TOTAL HOURS OF STABZLITY CLASS B 3.380 TOTAL HOURS OF ELEVATED STABILITY CZASS B 0.0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1. 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZLZTY BASED ON DELTA-T BETWEEN 45.30 AND 89.59 METERS WIND DIRECTION MEASURED AT 45 ~ 67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRZNTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Ill IQ1l/

l% jWPo%

SPLIT JOINT PERCENTAGE FREQUEHCI F WIND SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABILITY CLASS C 4 DELTA T<~-1.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE JUL 1, 92 - SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0. 6-1. 4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >I24.5 TOTAL H 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HHE 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 ENE 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S 0.0 0.0 0.0 Q.Q a.o 0.0 0.0 0.0 0.0 0.0 SSW 0.0 0 ~ 0 0 ' 0.048 0.0 0.0 0.0 0.0 0.0 0 '48 SW 0.0 0.0 0.0 0.190 0.0 0.0 a.o 0.0 0.0 0.190 WSW 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ~ 0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WHW 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0 '

HW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' a.o NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.238 0.0 0.0 0.0 0.0 0.0 0 '38 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF ELEVATED RELEASES 1976.370 TOTAL HOURS OF STABZLZTY CLASS C 13.810 TOTAL HOURS OF ELEVATED STABZLZTY CLASS C ~ 5.000 METEOROLOGICAL FACILZT'Y: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEH 45.30 AHD 89.59 METERS WIND DIRECTION MEASURED AT 45 67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUEHT VELOCITY ~ 12.60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED HUMBERS

BFN RAD Impact SPLIT JOINT PERCENTAGE FREQUENCI July cember 1992 WIND SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS D DELTA T4l~-0.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE JUL 1 ~ 92 >> SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 2.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 24.5 TOTAL N 0.002 0.095 0.285 0.523 0.512 0.583 0.462 0.0 0.0 2.461 NNE 0.001 0.0 0.190 0.285 0.459 1.449 1.431 0.038 0.0 3.852 NE 0.001 0.0 0.238 0.143 0.460 0.509 0.039 0.0 0.0 1.390 ENE 0.002 0.0 0.333 0.285 0.274 0.043 0.039 0.0 0.0 0.975 E 0. 001 0 ' 0.190 0.475 0.370 0.172 0.116 0.0 0.0 1.324 ESE 0.002 0.0 0.428 0.713 0.861 1.552 0.0 0.0 0.0 3.555 SE 0.010 0.0 2.090 1.758 1.195 1.993 0.661 0.0 0.0 7.707 SSE 0.005 0.0 1.093 1.188 1.605 1.979 0.468 0.0 0.0 6.337 S 0.008 0 '90 1.378 1.283 1.144 2.452 0.856 0.0 0.0 7.310 SSW 0.005 0.0 1.093 1.615 1.053 1.590 0.118 0.0 0.0 5.474 SW 0.004 0.238 0.665 0.950 0.958 0.957 0.274 0.0 0.0 4.o46 WSW 0.002 0.095 0.333 1.140 0.820 0.879 0.158 0.0 0.0 3.427 W 0.001 0.0 0.238 0.808 0.873 1.218 0.117 0.0 0.0 3.254 WNW 0.001 0.0 0.238 0.143 0.417 0.625 0.039 0.0 0.0 1.462 NW 0.001 0.0 0.190 0.333 0.733 0.713 0.429 0.106 0.0 2.505 NNW 0.002 0.095 0.238 0.190 0.235 O.2O8 0.039 0.054 0.0 1.060 SUBTOTAL 0.048 0.713 9.216 11.829 11. 969 16.920 5.248 0 ~ 198 0.0 56.140 TOTAL HOURS OF VALZD OBSERVATIONS 2105.000 TOTAL HOURS OF ELEVATED RELEASES 1976.370 TOTAL HOURS OF STABILITY CLASS D 1241.070 TOTAL HOURS OF ELEVATED STABILITY CLASS D 1181.750 METEOROLOGZCAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 45.30 AND 89.59 METERS WIND DZRECTZON MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRZNTED: 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

0 July cember 1992 SPLIT JOINT PERCENTAGE PREGUEHCIE WIND SPEED BY WIND DIRECTION POR Page 67 STABILITY CLASS E C DELTA T<~ 1.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE JUL 1, 92 SEP 30, 92 WIND WIND SPEEDtMPH)

DIRECTION CALM 0.6-1.4 1 ~ 5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.005 0.0 0.190 0.475 0.683 0.&04 0.116 0.0 0.0 2.273 NNE 0.006 0.095 0.143 0.475 0.677 1.380 0.273 0.0 0.0 3.048 HE 0.009 0.0 0.333 0.333 0.135 0.544 0.0 0.0 0.0 1.354 ENE 0.005 0.095 0.095 0.570 0.319 0.210 0.0 0.0 0.0 1. 294 E 0.009 0.048 0.285 0.190 0.582 0.681 0.038 0 050 0.0 1.883 ESE 0.012 0.0 0.475 0.475 1.460 0.980 0.038 0.032 0.0 3.472 SE 0.022 0.190 0.665 0.855 0.550 0.086 0.0 0.0 0.0 2.369 SSE 0.020 0.190 0.570 0.570 0.187 0.505 0.194 0.0 0.0 2.236 S 0.017 0.095 0.570 0.475 0.373 0.873 0.157 0.0 0.0 2.561 SSW 0.027 0.143 0.903 0.523 0.187 0.380 0.0 0.0 0.0 2.162 SW 0.019 0.190 0.523 0.665 0.231 0.215 0.0 0.0 0.0 1.842 WSW 0.012 0.048 0.428 0.570 0.229 0.166 0.0 0.0 0.0 1. 453 W 0.010 0 '95 0.285 0.285 0.0 0.0 0.0 0.0 0.0 0.675 WNW 0.004 0.0 0.143 0.380 0.047 0 F 082 0.0 0.0 0.0 0.655 NW 0.006 0.0 0.238 0.143 0.048 0.170 0.0 0.0 0.0 0.604 NNW 0.006 0.095 0.143 0.190 0.314 0.127 0.0 0.0 0.0 0.875 SUBTOTAL 0.190 1.283 5.986 7.173 6.023 7.203 0.816 0.083 0.0 28.756 TOTAL HOVRS OF VALZD OBSERVATZONS 2105.000 TOTAL HOURS OF EIEVATED RELEASES 1976.370 TOTAL HOURS OP STABILITY CLASS E 636.080 TOTAL HOURS OF ELEVATED STABILITY CI ASS E 605.320 METEOROLOGICAL PACILITY: MET FACILITY LOCATED 1 ~ 3 KM ESE OF BROWHS PERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BETWEEN 45.30 AHD 89.59 METERS WIHD DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EPPLUENT VELOCZTY ~ 12.60 M/S DATE PRINTED: 10/22/92 NOTE: TOTALS AND SVBTOTALS ARE OBTAINED PROM UNROUNDED NUMBERS

Pg J$ lggJ Jlllgol L July cember 1992 SPLZT JOZHT PERCENTAGE FREQUEHCI WIND SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS F DELTA T<~ 4.0 C/100 M)

BROWNS FERRY NUCLEAR PLAHT PART 2 OF 2 ELEVATED RELEASE MODE JUL 1 i 92 SEP 30 i '92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7 '-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL H 0.007 0.0 0.095 0 ~ 190 0.092 0.418 0.0 0.0 0.0 Q.802 HNE 0.007 0.0 0.095 0.0 0.188 0.839 0.157 0.0 0.0 1.286 NE 0.010 0 0 0.143 0.190 0.228 0.379 0.117 0.0 0.0 1.066 ENE 0.003 0.048 0.0 0.143 0.093 0.084 0.0 0.0 0.0 0.370 E 0.0 0.0 0.0 0.190 0.0 0.587 0.0 0.0 0.0 0.777 ESE 0.010 0.0 0.143 0.0 0.183 0.129 0.0 0.0 0.0 0.465 SE 0.014 0.0 0.190 0.095 0.0 0.0 0.0 0.0 0.0 0.299 SSE 0.010 0.048 0.095 0.048 0.048 0.0 0.0 0.0 0.0 0.248 S 0.003 0.0 0.048 0.143 0.093 0.165 0.0 0.0 0.0 0. 451 SSW 0.014 0.0 0.190 0.238 0.228 0.0 0.0 Q.Q 0.0 0.669 SW 0.010 0.0 0.143 0.285 0 '92 0.0 0.039 0.0 0.0 0.569 WSW 0.0 0 ' 0.0 0.095 0.090 0.0 0.0 0.0 0.0 0.185 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0 0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 NW 0.003 0.0 0.048 0.095 0.0 0.0 0.0 0.0 0.0 0.146 NNW 0.003 0.048 0.0 0.095 0.091 0.044 0 ' 0.0 0.0 0.280 SUBTOTAL 0.095 0.143 1.188 1.805 1.424 2.645 0.314 0.0 0.0 7.612 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OF ELEVATED RELEASES 1976.370 TOTAL HOURS OF STABILITY CLASS F 170.900 TOTAL HOURS OF ELEVATED STABILZTY CLASS F 160.240 METEOROLOGICAL FACZLITY: MET FACZLZTY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZLITY BASED OH DELTA-T BETWEEN 45.30 AHD 89.59 METERS WIND DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED 10/22/92 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Df LX CQSlJ J.344@514 \

SPI IT JOINT PERCENTAGE FREOUEHCZ WIND SPEED BY WIND DIRECTION FOR July - cember 1992 Page 67 STABILITY CLASS G A T > 4.0 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE JUL 15 92 SEP 305 92 WIND WIND SPEEDtMPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-3.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HNE 0.0 0 ' 0.0 0.143 0.134 0.339 0.0 0.0 0.0 0.615 HE 0.0 0.0 0.048 0.095 0.0 0.168 0.0 0 ~ 0 0.0 0.310 ENE 0.0 0.0 0.0 0 ' 0.0 0.040 0.0 0.0 0 ' 0.040 E a.o 0.0 0.0 0.0 0.0 0.083 0.0 0.0 0.0 0.083 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 Q.a 0.0 0.0 0.0 0.0 0 ~0 0.0 0.0 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S 0.0 0.0 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.0 SSW 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0~0 0.0 0.0 0.047 0.0 0.0 0 ' o.a 0.047 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HHW 0.0 0' 0.0 0.048 0.0 0.0 0.0 0.0 0.0 0.048 SUBTOTAL 0.0 0.0 0.048 0.285 0.181 0 ~ 629 0.0 0.0 0.0 1.143 TOTAL HOURS OF VALID OBSERVATIONS 2105.000 TOTAL HOURS OP ELEVATED RELEASES 1976.370 TOTAL HOURS OF STABII ITY CLASS G 29.560 TOTAL HOURS OF ELEVATED STABILITY CLASS G 24.060 METEOROLOGICAL FACILITY: MET PACZLITY LOCATED 1.3 KM ESE OF BROWHS PERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 45.30 AHD 89.59 METERS WIND DIRECTION MEASURED AT 45 67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VEIOCITY ~ 12.60 M/5 DATE PRINTED: 10/22/92 NOTE'OTALS AHD SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 5C.

Joint Frequency Distribution in Percent for Split-Level Releases Ground Level Portion Fourth Quarter 1992

BFN RAD Impact SPLIT JOINT PERCENTAGE FREQUENCY WIND SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABILITY CLASS A A T<~-1.9 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUHD LEVEL RELEASE MODE OCT li 92 DEC 31'2 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 > 24.5 TOTAZ N 0.0 0.0 0.0 0.0 0.0 0.006 0.0 0.0 0.0 0.006 NNE 0 ' 0.0 0.0 0.0 0.005 0.072 0.0 0 ' 0.0 0.077 HE 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 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 0.008 0.047 0.0 0.0 0.0 0.0 0.056 SE 0.0 0.0 0.006 0.026 0 '43 0.0 0.0 0.0 0.0 0.076 SSE 0.0 0.0 0.007 0.033 0 '09 0.0 0.0 0.0 0.0 0 050 S 0.0 0.0 0.0 0.062 0.0 0.0 0.0 0.0 0 ' 0.062 SSW 0.0 0 ' 0.006 0.012 0.0 0.0 0.0 0.0 0.0 0.018 SW 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 WSW 0.0 0.0 0.0 0.0 0.007 0.009 0.0 0.0 0 ' 0.016 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0 ' 0.0 0 F 008 0.018 0.0 0.0 0.026 NNW 0.0 0.0 0.0 0.0 0.0 0.008 0.009 0.0 0.0 0.017 SUBTOTAL 0.0 0.0 0.020 0.143 0 ~ 111 0.104 0.027 0.0 0.0 0.405 TOTAL HOURS OF VALID OBSERVATZONS 2179.000 TOTAL HOURS OF GROUND LEVEL RELEASE 235.440 TOTAL HOURS OF STABILITY CLASS A 8.820 TOTAL HOURS OF GROUND LEVEL STABZLITY CLASS A 8.820 METEOROLOGICAL FACZLITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BETWEEN 10.03 AND 45.30 METERS WIND DIRECTION MEASURED AT 10.42 METER LEVEL WZND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

BPN RAD Impact July cember 1992 SPLZT JOZHT PERCENTAGE FREQUENCI WZHD SPEED BY WIND DIRECTION FOR Page 67 STABZLITY CLASS B DELTA T<~-1.7 C/100 M)

BROWHS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND ZEVEL RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CAIM 0. 6-1. 4 1.5-3.4 3 '-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0 ' 0.0 0.0 0.0 0.007 0.023 0.024 0.0 0.0 0.055 NNE 0.0 0.0 0.0 0.0 0.009 0.038 0.0 0.0 0.0 0;447 NE 0.0 0.0 0.0 0.0 0.0 0.006 0.0 0.0 0.0 0.006 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 0.008 0.0 0.0 0.0 0.0 0.0 0.008 SE 0 ' 0.0 0.0 0.011 0.022 0.028 0.0 0.0 0.0 0.062 SSE 0.0 0.0 0.0 0.012 0.0 0.0 0.0 0.0 0.0 0.012 S 0.0 0.0 0.007 0.008 0.0 0.0 0.0 0.0 0.0 0.015 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.008 0.0 0.0 0.0 0.0 0 ~ 0 0.008 WSW 0.0 0.0 0.0 0.001 0.0 0.029 0.0 0.0 0.0 0.030 W 0.0 0.0 0.0 0.0 0.018 0.0 0.0 0.0 0.0 0.018 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.018 0.0 0.0 0.018 NW 0.0 0.0 0.0 0.0 0.0 0.016 0.011 0.0 0.0 0.027 NNW 0.0 0.0 0.0 0 ' 0.0 0.015 0.0 0.0 0.0 0.015 SUBTOTAI 0.0 0.0 0.007 0.049 0.056 0.156 0.054 0.0 0.0 0.322 TOTAL HOURS OF VALID OBSERVATIONS 2179. 000 TOTAL HOURS OF GROUND LEVEL RELEASE 235.440 TOTAL HOURS OF STABILITY CLASS B 8.830 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS B 7.020 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY HUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10 '3 WIND DIRECTION MEASURED AT 10.42 METER LEVEL AND 45.30 METERS WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY ~ 12. 60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AHD SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact SPZZT JOINT PERCENTAGE FREQUENCI July ember 1992 WIND SPEED BY WIND DIRECTION FOR Page 67 STABIZ ITY CLASS C DELTA T<~-1.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE OCT 1, 92 DEC 31, 92 WZND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0 F 001 0.007 0.032 0.0 0.0 0.0 0.040 NNE 0.0 0.0 0.0 0.0 0.006 0.046 0.0 0.0 0.0 0.052 NE 0.0 0.0 0.0 F 000 0.004 0.011 0.0 0.0 0.0 0.016 ENE 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 0.005 0.0 0.0 0.0 0.0 0.0 0.005 SE 0.0 0.0 0.003 0.0 0.026 0.019 0.0 0.0 0.0 0.048 SSE 0.0 0.0 0.010 0.017 0.008 0.0 0.0 0.0 0.0 0.035 S 0.0 0.0 0.006 0.0 0.028 0.0 0.0 0.0 0.0 0 034 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.006 0.0 0.0 0.0 0.0 0.0 0.006 WSW 0.0 0.0 0.0 0.006 0.017 0.017 0.0 0.0 0.0 0.041 W 0.0 0.0 0.0 0.001 0.003 0.0 0.0 0.0 0.0 0.004 WNW 0.0 0.0 0.0 0 ' 0.005 0.013 0.009 0.0 0.0 0.027 NW 0.0 0.0 0.0 0.001 0.002 0.040 0.020 0.0 0.0 0.063 NNW 0.0 0.0 0.0 0.0 0.001 0.012 0.0 0.0 0.0 0.014 SUBTOTAL 0.0 0.0 0.018 0.037 0.108 0.191 0.029 0.0 0.0 0.384 TOTAL HOURS OF VALID OBSERVATIONS 2179.000 TOTAL HOURS OF GROUND LEVEL RELEASE 235.440 TOTAL HOURS OF STABILITY CLASS C 22.320 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS C 8.360 METEOROLOGICAL FACZLZTY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILZTY BASED ON DELTA-T BETWEEN 10.03 AHD 45.30 METERS WIND DIRECTION MEASURED AT 10.42 METER LEVEL WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY 88 12.60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact SPLIT JOINT PERCENTAGE FREQUENCZ WIND SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABZLITY CLASS D DEITA T(~-0.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL N 0.0 0.0 0.0 0.030 0.148 0.297 0. 111 0.042 0.0 0.628 NNE 0.0 0.0 0.0 0.027 0.056 0.144 0.029 0.0 0.0 0.257 NE 0.0 0.0 0.0 0.006 0.074 0.108 0.0 0.0 0.0 0.189 ENE 0 ' 0 ' 0.0 0.011 0.028 0.022 0.0 0.0 0.0 0.060 E 0.0 0.0 0.004 0.022 0.0 0.0 0 ~0 0.0 0.0 0.026 ESE 0.0 0.0 0.002 0.090 0.061 0.009 0.036 0.0 0.0 0.198 SE 0.0 0.0 0.030 0.116 0.330 0.332 0.0 0.0 0.0 0.809 SSE 0.0 0.0 0.108 0.113 0.026 0.106 0.0 0.0 0.0 0.353 S 0.0 O.C 0.02" 0.104 O.C"8 0 '17 3.0 0.0 0.0 0.229 SSW 0.0 0.001 0.023 0 '34 0.013 0.069 0.0 0.0 0.0 0.141 SW 0.0 0.0 0.0 0.012 0.009 0.033 0.0 0.0 0.0 0.054 WSW 0.0 0.0 0.002 0.022 0.033 0.066 0.0 0.0 0.0 0.122 W 0.0 0.0 0.0 0.039 0.069 0.124 0.0 0.0 0.0 0.233 WNW 0.0 0.0 0.0 0.004 0.019 0.152 0.107 0.069 0.0 0.352 NW 0.0 0.0 0.0 0.001 0.033 0.121 0.189 0.081 0.0 0.424 NNW 0.0 0.0 0.0 0.029 0.165 0.391 0.062 0.0 0.0 0.646 SUBTOTAL 0.0 0.001 0.198 0.662 1.143 1.992 0.534 0.192 0.0 4.721 TOTAL HOURS OF VALZD OBSERVATIONS 2179.000 TOTAL HOURS OF GROUND LEVEL RELEASE 235.440 TOTAL HOURS OF STABILITY CLASS D 1219 '20 TOTAL HOURS OF GROUND LEVEL STABZLITY CLASS D 102.870 METEOROLOGICAL FACILITY- MET FACILITY LOCATED 1.3 EM ESE OF BROWNS FERRY NUCLEAR PLANT 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 DATE PRINTED: 01/14/93 NOTE'OTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

BEN RAD Impact SPLIT JOINT PERCENTAGE FREQUENCZ July ocember 1992 WIND SPEED BY WZND DZRECTZON FOR Page 67 STABILITY CLASS E DELTA T(2I 1.5 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7 '-12.4 12.5-18.4 18.5-24.4 24.5 TOTAL N 0.0 0.0 0.011 0.085 0.041 0.034 0.0 0.0 0.0 0. 171 HNE 0.0 0.0 0.006 0.034 0.034 0.015 0.0 0.0 0.0 0.089 NE 0.0 0.0 0.006 0.071 0.087 0.030 0.0 0.0 0.0 0.194 ENE 0.0 0.0 0.009 0.014 0.017 0.008 0.0 0.0 0.0 0.048 E 0.0 0.002 0.008 0.066 0.013 0.0 0.0 0.0 0.0 O.OS9 ESE 0.0 0.004 0.031 0 '67 0.049 0.017 0.0 0.0 0.0 0.269 SE 0.0 0.017 0.133 0.150 0.120 0.307 0.0 0.0 0.0 0.726 SSE 0.0 0.001 0.319 0.192 0.308 0.092 0.0 0.0 0.0 0.913 S 0.0 0.0 0.095 0.145 0.107 O.J16 0.0 0.0 0.0 0.363 SSW 0.0 0.0 0.023 0.030 0.031 0.0 0.0 0.0 0.0 0.084 SW 0.0 0.0 0. 011 0.0 0.017 0.0 0.0 0.0 0.0 0.028 WSW 0.0 0.0 0.004 0.048 0.029 0.009 0.0 0.0 0.0 0.090 W 0.0 0.0 0.001 0.013 0.0 0.018 0.0 0.0 0.0 0.032 WHW 0.0 0.0 0.0 0.017 0.025 0.0 0.0 0.0 0.0 0.042 NW 0.0 0.0 0.003 0.021 0.047 0.033 0.0 0.0 0 ' 0.104 NNW 0.0 0.0 0.003 0.050 0.098 0.066 0.010 0.0 0.0 0.227 SUBTOTAL 0.0 0.024 0.665 1.103 1.025 0.644 0.010 0.0 0.0 3.470 TOTAL HOURS OF VALID OBSERVATIONS 2179.000 TOTAL HOURS OP GROUND LEVEL RELEASE 235.440 TOTAL HOURS OP STABILITY CLASS E 713.330 TOTAL HOURS OF GROUND LEVEZ STABILITY CLASS E 75.620 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OP BROWNS FERRY NUCLEAR PLANT 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 IEVEL EFFLUENT VELOCITY = 12.60 M/S DATE PRINTED: 01/14/93 NOTE. TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Df fl @AU JlllPclC C July cember 1992 SPLIT JOINT PERCENTAGE FREQUENCY WIND SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS F DELTA T<= 4.0 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL H 0.000 0.0 0.022 0.076 0.006 0.0 0.0 0.0 0.0 0.104 NHE 0.0 0.0 0.0 0.084 0.038 0.0 0.0 0.0 0.0 0.122 NE 0.000 0.0 0.010 0.012 0.007 o.a 0.0 0.0 0.0 0.030 ENE 0.000 0.010 0.008 0.043 0.023 0.0 0.0 0.0 0.0 0.085 E 0.001 0.004 0.048 0.053 0.0 0.0 0.0 0.0 0.0 0.105 ESE 0.001 0.010 0.029 0.055 0.0 0.0 0.0 0.0 0.0 0.095 SE 0.001 0.019 0.048 0.017 0.018 0.0 0.0 0.0 0.0 0.104 SSE 0.002 0.019 0.127 0.067 0.059 0.044 0.0 0.0 0.0 0.318 S 0.000 0.011 0.014 0.031 0.009 0. 011 0.0 0.0 0 ' 0.077 SSW 0.000 0.0 0.028 0.0 0.0 0.0 0.0 0.0 0.0 0.028 SW 0.000 0.0 0.006 0.0 0.0 0.0 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 a.o NW 0.000 0.0 0.011 0.035 0.0 0.0 0.0 0.0 0.0 0.047 NNW 0.000 0.0 0.012 0.041 0.0 0.0 0.0 0.0 0.0 0.053 SUBTOTAL 0.006 0. 074 0.363 0. 514 0.162 0.055 0.0 0.0 0.0 1.173 TOTAL HOURS OF VALID OBSERVATIONS 2179.000 TOTAL HOURS OF GROUND LEVEL RELEASE 235.440 TOTAL HOURS OF STABILITY CLASS F 160.210 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS F 25.570 METEOROLOGICAL FACZLZTY: MET FACILITY LOCATED 1 ~ 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BETWEEN 10.03 AHD 45.30 METERS WIND DIRECTION MEASURED AT 10.42 METER LEVEL WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUEHT VELOCITY = 12.60 M/S DATE PRINTED: 01/14/93 NOTE TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

urn Mau 1mpacE SPLIT JOINT PERCENTAGE FREQUENCY WIND SPEED BY WIND DIRECTION FOR July - cember 1992 Page 67 STABZLITY CLASS G A T > 4.0 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.000 0.0 0.023 0.038 0.0 0.0 0.0 0.0 0.0 0.061 HNE 0.000 0.0 0.028 0.037 0.0 0.0 0 ~0 0.0 0.0 0 '64 NE 0.000 0.0 0.020 0.007 0.0 0.0 0.0 0.0 0.0 0.027 ENE 0.000 0.000 0.026 0.000 0.0 0.0 0.0 0.0 0.0 0.027 E 0.000 0.024 0.020 0.017 0.0 0.0 0.0 0.0 0.0 0.061 ESE 0.000 0.0 0.005 0.0 0.0 0.0 0.0 0.0 0.0 0.005 SE 0.000 0. 010 0.005 0.0 0.0 0.0 0 ~ 0 0.0 0.0 0.014 SSE 0.000 0.027 0.031 0.0 0.0 0.0 0.0 0.0 0.0 0.059 S 0.0 0.0 0.0 O.o 0.0 0.0 0.0 0.0 0.0 0.0 SSW 0.000 0.002 0.0 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 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.000 0.0 0.004 0.006 0.0 0.0 0.0 0.0 0.0 0.009 SUBTOTAL 0 '02 0.063 0.161 0.104 0.0 0.0 0 ~ 0 0.0 0.0 0.330 TOTAL HOURS OF VALZD OBSERVATIONS 2179.000 TOTAL HOURS OF GROUND LEVEL RELEASE 235.440 TOTAL HOURS OF STABILITY CLASS G 45.570 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS G 7.180 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1. 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10.03 AND 45.30 METERS WIND DIRECTION MEASURED AT 10 '2 METER LEVEL WIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRZNTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 5D Joint Frequency Distribution in Percent for Split-Level Releases Elevated Portion Fourth Quarter 1992

BFN RAD Impact SPLIT JOZNT PERCENTAGE FREQUENCY WIND SPEED BY WIND DZRECTION FOR July cember 1992 Page 67 STABILITY CLASS A A T(=-1.9 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 EIEVATED RELEASE MODE OCT 1, 92 - DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >5524.5 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 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4

C.O 0.0 0.0 4 0 O.C 0.0 0.0 0.0 0.0 O.J SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL HOURS OF VALID OBSERVATZONS 2179. 000 TOTAL HOURS OF ELEVATED RELEASES 1943.559 TOTAL HOURS OF STABILITY CLASS A 8.820 TOTAL HOURS OF ELEVATED STABILITY CLASS A 0.0 METEOROLOGICAL FACZLITY- MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZLZTY BASED ON DELTA-T BETWEEN 45.30 AND 89 WIND DZRECTZON MEASURED AT 45.67 METER LEVEL

'9 METERS WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY ~ 12.60 M/S DATE PRZNTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

SiN MA)) impact July cember 1992 SPLIT JOINT .PERCENTAGE FREQUENCY WZHD SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS B DELTA T < =-1. 7 C/10 0 M )

BROWNS FERRY NUCLEAR PLANT PART 2 Of 2 ELEVATED RELEASE MODE OCT 1 i 92 DEC 31, 92 WIND WIND SPEED[MPH)

DZRECTION CALM 0.6-1 ~ 4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~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 0.0 0.0 0.0 0.0 0.0 0.0 HE 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 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 SE 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S C.O 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 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.039 0.0 0.0 0.0 0.039 WSW 0.0 0.0 0.0 0.0 0.044 0.0 0.0 0.0 0.0 0.044 W 0 ~0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 NW 0 ~ 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 HNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.044 0.039 0.0 0.0 0.0 0.083 TOTAL HOURS OF VALID OBSERVATIONS 2179.000 TOTAL HOURS Of ELEVATED RELEASES 1943.559 TOTAL HOURS Of STABILITY CLASS B 8.830 TOTAL HOURS OF ELEVATED STABILITY CLASS B 1.810 METEOROLOGZCAL FACILITY- MET FACILITY LOCATED 1.3 KM ESE OF BROWHS FERRY NUCLEAR PLANT STABILITY BASED OH DELTA-T BE'TWEEN 45.30 AHD 89.59 METERS WIND DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45 EFFLUENT VELOCITY ~

'7 12.60 M/S METER LEVEL DATE PRINTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAZHED FROM UNROUNDED NUMBERS

DFM mm impaCC July cember 1992 SPLIT JOINT PERCENTAGE FREQUENCY WZND SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS C DELTA T<XR-1 ' C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0. 6-1. 4 1. 5-3. 4 3.5-5.4 5.5-7.4 7-5-12.4 12.5-18-4 18.5-24 ' >~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 0.0 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 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 0.087 0.039 0.0 0.0 0.0 0.126 SE 0.0 0.0 0.0 0.046 0.134 0.042 0.0 0.0 0.0 0.222 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.040 0.0 0.0 0.0 0.040 SW 0.0 0.0 0.0 0.0 0.045 0.0 0.037 0.0 0.0 0.081 WSW 0.0 0.0 0.0 0.0 0.088 0.083 0.0 0.0 0.0 0.171 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 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 0.0 0.0 0.0 0.0 SUBTOTAL 0 ' 0.0 0.0 0.046 0.353 0.205 0.037 0.0 0.0 0.641 TOTAL HOURS OF VALID OBSERVATIONS 2179.000 TOTAL HOURS OF ELEVATED RELEASES 1943.559 TOTAL HOURS OF STABILITY CLASS C 22.320 TOTAL HOURS OF ELEVATED STABIIITY CLASS C 13.960 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 45.30 AND 89.59 METERS WIND DIRECTION MEASURED AT 45.67 METER LEVEL WZND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY = 12.60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact SPLIT JOINT PERCENTAGE PREQUENCZ WIND SPEED BY WIND DIRECTION POR July cember 1992 Page 67 STABILITY CLASS D DELTA T4:~-0. 5 C/100 M)

BROWNS PERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE OCT 1, 92 - DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18 '-24.4 >=24.5 TOTAL N 0.0 0.0 0.092 0.597 1.183 2.828- 0.934 0.159 0.004 5.797 NNE 0.0 0.046 0.092 0.321 0.832 1.836 0.751 0.072 0.0 3.949 NE 0.0 0.0 0.138 0.321 0.263 1.061 0.038 0.0 0.0 1 '21 ENE 0.0 0.046 0.184 0.229 0.175 0.163 0.076 0.0 0.0 0.874 E 0.0 0.092 0.092 0 '13 0. 535 0.083 0.0 0.0 0.0 1 '14 ESE 0.0 0.0 0 '29 0.597 0.714 1.007 0.076 0.0 0.010 2.633 SE 0.0 0.092 0.734 1.239 0.943 1.847 1.789 0. 603 0.008 7.256 SSE 0 ' 0.0 0.505 0.321 0.754 1.883 1.162 0.144 0.038 4.807 S .0 0.138 0.275 0.5J7 0 '79 0.888 0.670 0 152 v.0 3.319 SSW 0.0 0.046 0.413 0.275 0.132 0.757 0.298 0.094 0.011 2.027 SW 0.0 0.046 0.275 0.413 0.133 0.403 0.299 0.104 0.0 1.673 WSW 0.0 0.046 0.321 0.321 0.355 0.442 0.297 0.073 0.0 1.855 W 0.0 0.0 0.092 0.551 0.436 0.963 0.414 0.0 0.010 2.466 WNW 0.0 0 ' 0 '46 0.275 0.486 0.679 0.557 0.095 0.010 2.148 NW 0.0 0.0 0.413 0.734 0.358 1.080 0.673 0.223 0.021 3.503 NNW 0.0 0.046 0 '29 0.597 0.830 3.012 1.122 0.085 0.0 5.922 SVBTOTAL 0.0 0.597 4.130 7.802 8.709 18.933 9.157 1.825 0.112 51.264 TOTAL HOURS OF VALID OBSERVATIONS 2179. 000 TOTAL HOURS OF ELEVATED RELEASES 1943.559 TOTAL HOURS OF STABILITY CLASS D 1219.920 TOTAL HOURS OF ELEVATED STABILITY CLASS D 1117. 050 METEOROLOGICAL FACZIITY: MET FACILITY LOCATED 1.3 EM ESE OP BROWNS FERRY NVCLEAR PLANT STABZLZTY BASED ON DELTA-T BETWEEN 45.30 AND 89.59 METERS WIND DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY = 12.60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AND SVBTOTALS ARE OBTAINED PROM UNROUNDED NVMBERS

BFN RAD Impact SPLIT JOINT PERCENTAGE PREQUEHCI July cember 1992 WIND SPEED BY WIND DZRECTZON FOR Page 67 STABILITY CLASS E DELTA T<~ 1.5 C/100 M)

BROWHS FERRY NUCLEAR PLANT PART 2 OP 2 ELEVATED RELEASE MODE OCT 1, 92 - DEC 31, 92 WIND WIND SPEED(MPH)

DZRECTZON CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7 ' 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.001 0.0 0.092 0.046 0.087 0.682 0.076 0.0 0.0 0.984 NNE 0.001 0.0 0.046 0.275 0.264 0.801 0.265 0.0 0.0 1.652 NE 0. 001 0.0 0.046 0.0 0.175 1.436 0.076 0.0 0.0 1.733 EHE 0.001 0.0 0.046 0.138 0.175 0.484 0.076 0.0 0.0 0.920 E 0.006 0.092 0.321 0.184 0.441 0.372 0.0 0.0 0.0 1.416 ESE 0.006 0.046 0.367 0.597 0.535 1.574 0.0 0.0 0.0 3.124 SE 0.009 0.138 0.551 0.780 1.063 2.302 0.486 0.245 0.0 5.574 SSE 0.006 0.0 0.459 0.597 0 '93 1.493 0.597 0.217 0.004 4.165 S 0.004 0.092 0.18I 0.229 0.570 1.062 0.225 0.035 0.0 2.401 SSW 0.001 0.0 0 092 0.367 0.308 0.360 0.226 0.0 0.0 1.355 SW 0.004 0.046 0.275 0.321 0.043 0.279 0.038 0.0 0.0 1.007 WSW 0.001 0.0 0.046 0.413 0.0 0.320 0.076 0 ' 0.0 0.855 W 0.001 0.046 0.046 0.229 0.090 0.121 0.038 0.0 0.0 0.572 WNW 0.001 0.046 0.046 0.184 0.090 0.122 0.0 0.0 0.0 0.489 NW 0.003 0.0 0.229 0.229 0.353 0.608 0.037 0.0 0.0 1. 461 NNW 0. 001 0.0 0.046 0.046 0.264 1.166 0.037 0.0 0.0 1.559 SUBTOTAL 0.046 0.505 2.891 4.635 5.252 13.184 2.253 0.497 0.004 29.266 TOTAL HOURS OP VALID OBSERVATIONS 2179.000 TOTAL HOURS OP ELEVATED RELEASES 1943.559 TOTAL HOVRS OF STABZLITY CLASS E 713.330 TOTAL HOVRS OP ELEVATED STABILITY CLASS E 637.710 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS PERRY NVCLEAR PLANT STABZIITY BASED ON DELTA-T BETWEEH 45.30 AND 89.59 METERS WIND DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EPFI UENT VELOCITY ~ 12. 60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED PROM UNROUNDED NUMBERS

M ll lllilJ JlllPcll I-July cember 1992 SPLIT JOINT PERCENTAGE FREQUENCY WIND SPEED BY WIND DIRECTION POR Page 67 STABILITY CLASS P DELTA T<~ 4.0 C/100 M)

BROWNS FERRY HUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE OCT 1, 92 - DEC 31, 92 WIND WIND SPEED t MPH )

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18 '-24.4 24.5 TOTAL H 0.0 0.0 0.0 0.0 0.0 0.123 0.0 0.0 0.0 0.123 HNE 0.009 0.0 o.o46 0.0 0.045 0.165 0.038 0.0 0.0 0.303 HE 0.009 0.046 0.0 0.0 0.046 0.328 0.0 0.0 0.0 0.429 EHE 0.018 0.092 0 ' 0.092 0.0 0.201 0.152 0.0 0.0 0 ~ 555 E o.a28 a.a 0.138 0.092 0.175 0.244 0.0 0.0 0.0 0.676 ESE 0.046 0.046 0.184 0.184 0.217 0.366 0.0 0.0 0.0 1.042 SE 0.009 0.0 0.046 0.229 0.267 0.124 0.0 0.0 0.0 0.676 SSE 0.028 0.092 0.046 0.046 0.134 0.123 0.0 0.0 0.0 0.469 S 0.0 0.0 0.0 0.092 0.044 0.202 0.038 0.0 0.0 0.375 SSW 0.037 0.046 0.138 0.046 0.0 0.0 0.0 0.0 0.0 0.266 SW 0.028 0.046 0.092 0.229 0.044 0.0 0.0 0.0 0.0 0.439 WSW 0.028 0.0 0.138 0.092 0.0 0.0 o.a 0.0 0.0 0.257 W 0.018 0.046 0.046 0.138 0.0 0.0 0.0 0.0 0.0 0.248 WNW 0~0 0.0 0 0 0.046 0.0 0.0 0.0 0.0 0.0 0.046 HW 0.0 0.0 0.0 0.0 0.0 0.041 0.0 0.0 0.0 0.041 HNW 0.018 0.092 0~0 0.0 0.0 0.125 0.0 0 ' 0.0 0.235 SUBTOTAL 0.275 0.505 0.872 1.285 0.972 2.042 0.228 0.0 0.0 6.179 TOTAL HOURS OF VALID OBSERVATIONS 2179.000 TOTAL HOURS OF ELEVATED RELEASES 1943.559 TOTAL HOURS OF STABZLITY CLASS P 160.210 TOTAL HOURS OF ELEVATED STABZLZTY CLASS P 134.640 METEOROLOGICAL PACZLITY: MET PACZLITY LOCATED 1.3 KM ESE OF BROWNS PERRY NUCLEAR PLANT STABILZTY BASED ON DELTA-T BETWEEN 45.30 AND 89 WIND DIRECTION MEASURED AT 45.67 METER LEVEL

'9 METERS WIND SPEED MEASURED AT 45.67 METER LEVEL EPFLUENT VELOCITY ~ 12.60 M/S DATE PRINTED: ai/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact SPLIT JOINT PERCENTAGE July ember 1992 FREQUENCZ WIND SPEED BY WIND DZRECTION FOR Page 67 STABILITY CLASS G A T ) 4.0 C/100 M)

BROWNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 24.5 TOTAL N 0.0 0.046 0.0 0.0 0.046 0.042 0.0 0.0 0.0 0 '34 NNE 0.0 0.0 0.0 0.046 0.0 0.0 0.0 0.0 0.0 0.046 NE 0.0 0.0 0 ' 0.0 0.089 0.156 0.0 0.0 0.0 0.245 ENE 0.0 0.0 0.0 0.046 0.0 0.080 0.0 0.0 0.0 0.126 E 0.0 0 ' 0.0 0.0 0.046 0.041 0.0 0.0 0.0 0.087 ESE 0.0 0.0 0.092 0.092 0.262 0.084 0.0 0.0 0.0 0.529 SE 0.0 0.0 0.092 0.138 0.044 0.0 0.0 0.0 0.0 0.274 SSE 0.0 0 ' 0.046 0.0 0.0 0.0 0.0 0.0 0.0 0.046 S 0.0 0.0 0.046 0.0 J.O 0.0 0.0 0.0 0.0 0.046 SSW 0.0 0.0 0.0 0.046 0.0 0.0 0.0 0.0 0.0 0.046 SW 0.0 0.046 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.046 WSW 0.0 0.0 0.0 0.092 0.0 0.0 0 ' 0.0 0.0 0.092 W 0.0 0.0 0.0 0.046 0.0 0.0 0.0 0.0 0.0 0.046 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.092 0.275 0.505 0.487 0.403 0.0 0.0 0.0 1.762 TOTAL HOURS OF VALID OBSERVATZONS 2179.000 TOTAL HOURS OF ELEVATED RELEASES 1943.559 TOTAL HOURS OF STABILITY CLASS G 45.570 TOTAL HOURS OF ELEVATED STABILITY CLASS G 38.390 METEOROLOGICAL FACILITY- MET FACILITY LOCATED 1-3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILZTY BASED ON DELTA-T BETWEEN 45.30 AND 89.59 METERS WIND DIRECTION MEASURED AT 45.67 METER LEVEL WIND SPEED MEASURED AT 45.67 METER LEVEL EFFLUENT VELOCITY = 12.60 M/S DATE PRINTED: 01/14/93 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 6A Joint Frequency Distribution in Percent for Stack Releases Third quarter 1992

PC+ KNJ Jill}I4I I July cember 1992 JOINT PERCENTAGE FREGUEHCIES 0 D SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS A ( T<~-1.9 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 - SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6 1 ' 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 25 ~ 5 TOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HHE . 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 EHE 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 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 S'W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW O.o 0.0 0.0 0.0 0.0 0.0 0.0 0:0 0 ' 0.0 HW 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL HOURS OF VAIZD STABILITY OBSERVATIONS 2119 TOTAL HOURS OF STABILITY CLASS A 0 TOTAL HOURS OF VALZD WIND DIRECTION-WIND SPEED-STABZLZTY CLASS A 0 TOTAL HOURS OF VALID WIND DZRECTZOH-WIND SPEED>>STABZLZTY OBSERVATIONS 2110 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1. 3 KM ESE OF BROWNS FERRY NUCLEAR PI ANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DZRECTZON MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED I 0.0 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED HUMBERS

DC 0 LQ$22 l 444@424 4 JOINT PERCENTAGE FREQUENCIES OF D SPEED BY WIND DIRECTION FOR July - cember 1992 Page 67 STABILITY CLASS B (- ELTA-T<~-1. 7 C/100 M)

BROWHS FERRY NUCIEAR PLANT JUL 12 92 SEP 302 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1 ~ 5-3.4 3.5-5.4 5.5-7.4 7.5 12.4 12.5-18.4 18.5 24.4 24.4 TOTAL H 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 '

HE 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 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 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 0.0 0.0 0.0 0.0 0.0 0' 0.0 0 '

S 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a SSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 o.a a.o 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 TOTAL HOURS OF VAIZD STABZLZTY OBSERVATZONS 2119 TOTAL HOURS OF STABILITY CIASS B 0 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B 0 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2110 TOTAI HOURS CALM ~ 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1. 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89 WIND SPEED AHD DZRECTIOH MEASURED AT THE 92.63 METER LEVEL

'9 METERS DATE PRZNTED: 10/22/92 MEAN WIND SPEED ~ 0.0 MPH NOTE: TOTALS AND SUBTOTAIS ABOVE ARE OBTAINED FROM UNROUNDED HUMBERS

urn mm xmpacc JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR July - cember 1992 Page 67 STABZLZTY CLASS C (- DEITA-T<~-1.5 C/100 M)

BROWHS FERRY HUCLEAR PLANT JUI 1, 92 SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5 ' 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~24.5 TOTAL H 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 NE 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 SSE 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.047 0.0 0.0 0.0 0.0 0.0 0.047 SW 0.0 0.0 0.0 0.095 0.0 0.0 0.0 0.0 0.0 0.095 WSW 0.0 0.0 0.0 0.095 0.0 0.0 0.0 0.0 0.0 0.095 W 0.0 0.0 0.0 0.0 0.0 0.0 0 ~0 0 ~0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.237 0.0 0.0 0.0 0~0 0.0 0.237 TOTAL HOURS OF VALID STABZLZTY OBSERVATZONS 2119 TOTAL HOURS OF STABILITY CLASS C 5 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILZTY CLASS C 5 TOTAL HOURS OF VALZD WIND DIRECTION-WZND SPEED-STABILITY OBSERVATIONS 2110 TOTAL HOURS CALM 0 METEOROLOGZCAL FACILITY: MET FACILZTY IOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AHD DIRECTION MEASURED AT THE 92 '3 METER LEVEL DATE PRZNTED: 10/22/92 MEAN WIND SPEED ~ 4.9 MPH NOTE: TOTALS AHD SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

Pl 5% LV1IJ J.543Pa4 L.

JOINT PERCENTAGE FREQUENCIES OF ND SPEED BY WIHD DZRECTION FOR July cember 1992 Page 67 STABZLITY CLASS D DELTA-T4:55-0.5 C/100 M)

BROWNS FERRY NUCLEAR PLAHT JUL 1 ~ 92 SEP 3Q ~ 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1 ~ 5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >5524 ~ 5 TOTAL H 0.0 0.0 0.284 0.474 0.474 0.948 0.995 0.190 0.0 3.365 NNE 0.0 0.0 0.142 0.142 0.474 0.948 1.374 0.474 0.0 3.554 NE 0.0 0.047 0.190 0.142 0.284 0.664 0.190 0.0 0.0 1. 517 ENE 0.0 0.047 0.142 0.379 0.190 0.095 0.047 0.0 0.0 0.900 E 0.0 0.0 0.142 0.332 0.190 0.190 0.047 0.047 0.0 0.948 ESE 0.0 0.0 0.474 0.521 0.427 1.801 1.043 0.190 0.0 4.4ss SE 0.0 0.0 1.280 1.564 0.995 1.991 2.180 0.569 0.0 8.578 SSE 0.0 0.0 0.900 0.900 0.995 1.659 1.043 0.047 0.0 5.545 S 0.0 0.047 0.853 0.948 0.853 2.607 1.659 Q.Q47 0.0 7.014 SSW 0.0 0.0 0.474 0.758 1.043 1.896 1.232 0.047 0.0 5.450 SW 0.0 0.095 0.995 0.711 0.474 1.659 0.948 0.095 0.0 4.976 WSW 0.0 0.0 0 '27 0.664 0.616 1.327 0.711 0.095 0 ' 3.839 W 0.0 0.0 0.190 0.711 0.758 1.659 0.569 0.047 0.0 3.934 WNW 0.0 0.095 0.142 0.190 0.521 0.948 0.142 0.0 0.0 .2.038 HW 0.0 0.047 0.237 0.190 0.664 0.900 0.474 0.237 0.047 2.796 HHW 0.0 0.047 0.332 0.284 0.190 0.142 0.095 0.047 0.095 1.232 SUBTOTAL 0.0 0.427 7.204 8.910 9.147 19 '31 12.749 2.133 0.142 60.142 TOTAL HOURS OF VALID STABILITY OBSERVATZONS 2119 TOTAL HOURS OF STABILITY CLASS D 1276 TOTAL HOURS OF VALID WZHD DIRECTZON-WIND SPEED-STABZLITY CLASS D 1269 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2110 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1 ~ 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AHD DZRECTZON MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED = 9.2 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAZNED FROM UNROUNDED NUMBERS

Dl i'0 DlW t.ulpa4 1 JOINT PERCENTAGE FREQUENCIES OF HD SPEED BY WIND DIRECTION FOR July ~cember 1992 Page 67 STABZLITY CLASS E ( DELTA-TC~ 1. 5 C/100 M)

BROWNS FERRY NUCLEAR PLANT JUL 1, 92 - SEP 30, 92 WIND 'WIND SPEED(MPH)

DIRECTION 0. 6-1. 4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL H 0.001 0.047 0'. 0 0.190 0.284 a.99s 0.758 0.190 0.0 2. 466 HNE 0.005 0.0 0.190 0.284 0.237 1.043 1.043 0.284 0.0 3.086 HE 0.003 a.a47 0.047 0.190 0.190 0.379 0.427 0.047 0 ' 1.330 EHE 0.003 0.0 0.095 0.095 0.142 0.521 0.047 0.0 0.0 0.903 E 0.008 0.095 0.190 0.0 0.047 0.474 0.190 0.095 0.047 1.145 ESE 0.007 0.047 0.190 0.190 0.095 0.995 1.280 0.0 0.095 2.&98 SE 0.012 0.0 0.427 0.569 0.474 2.085 0.379 0.047 0.0 3 '93 SSE 0.011 0.095 0.284 0.664 0.332 0.711 0.237 0.0 o.a 2.333 S 0.013 0.095 0.379 0.332 0.190 0.758 0.711 0.0 0.0 2.478 SSW 0.007 o.a9s 0. 142 0.332 0.332 0.711 0.616 0.095 0.0 2.329 SW 0.003 0.0 0.095 0.569 0.664 0.948 0.427 0.0 0.0 2.704 WSW 0.005 0 ~0 0.190 0.284 0.142 0 521 0.142 0.0 0.0 1.285 W 0.005 0.0 0.190 0.142 0.284 0.569 0.0 0.0 0.0 1.190 WNW 0.001 0.0 0.047 0.095 0.190 0 142 0.0 0.0 0.0 0.475 NW 0.008 0.047 0.237 0.190 0.190 0.047 0.095 a.a 0.0 0.814 HNW 0.004 0.0 0.142 0.142 0.190 0.332 0.095 0.0 0.0 0.904 SUBTOTAL 0.095 0.569 2.844 4.265 3.981 11.232 6.445 0.758 0.142 30.332 TOTAL HOURS OF VALID STABZLITY OBSERVATIONS 2119 TOTAL HOURS OF STABILITY CLASS E 642 TOTAZ HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 640 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATZOHS 2110 TOTAL HOURS CALM 2 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DIRECTION MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 10/22/92 MEAH WZHD SPEED = 9.2 MPH NOTE: TOTALS AHD SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RM impact July ember 1992 JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DZRECTION FOR Page 67 STABILITY CLASS F ( DELTA-T<~ 4.0 C/100 M)

BROWHS FERRY NUCLEAR PLANT JUL lg 92 SEP 30'2 WIND WIND SPEED(MPH)

DIRECTION 0.6-1.4 1.5-3.4 3.5-5 ' 5 '-7-4 7.5-12.4 12.5-18.4 18.5-24 ~ 4 >~24.5 TOTAL H 0.007 0.047 0.0 0.047 0.047 0.237 0.237 0.095 0 ' 0.718 HHE 0.007 0.0 0.047 0.047 0.0 0.142 0.474 0.047 0 ' 0.766 HE 0.007 0.0 0.047 0.0 0.0 0.474 0.379 0.474 0.0 1.382 EHE 0.0 0.0 0.0 0.0 0.142 0.332 0.0 0.0 0.0 0.474 E 0.0 0.0 0.0 0.190 0.095 0.237 0.0 0.0 0.0 0.521 ESE 0.015 0.0 0.095 0.095 0.0 0.284 0.427 0.0 0.0 0.915 SE 0.022 0.047 0.095 0.0 0.095 0.237 0.047 0.0 0.0 0.543 SSE 0.007 0.0 0.047 0.0 0.047 0.095 0.0 0.0 0 ' 0.197 S 0.0 0.0 0.0 0.0 0.0 0.095 0.190 0.047 0.0 0.332 SSW 0.0 0.0 0.0 0.095 0.095 0.190 0.0 0.0 0.0 0.379 SW 0.0 0.0 0.0 0.190 0.095 0.379 0.379 0.047 0.0 1.090 WSW 0.0 0.0 0.0 0.095 0.0 0.142 0.047 0~0 0.0 0.284 W 0.007 0.0 0.047 0.0 0.0 0.0 0.0 0.0 0.0 0.055 WNW 0.015 0.0 0.095 0.047 0.0 0.0 0.0 0.0 0.0 0.157 NW 0.0 0.0 0.0 0.0 0.0 0.047 0.0 0.0 0.0 0.047 NHW 0.007 0.0 0.047 0.0 0.0 0.047 0.095 0.0 0.0 0.197 SUBTOTAL 0.095 0.095 0.521 0.806 0 '16 2.938 2.275 0.711 0.0 8.057 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2119 TOTAL HOURS OF STABILITY CLASS F 170 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 170 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2110 TOTAL HOURS CALM 2 METEOROLOGICAL FACZLZTY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AHD .DZRECTZON MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED ~ 11.0 MPH NOTE: TOTALS AHD SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

s1'M ica1) Impact July cember 1992 JOINT PERCENTAGE FREQUENCIES 0 ND SPEED BY WIND DIRECTION POR Page 67 STABILITY CLASS G t T > 4.0 C/100 M)

BROWNS PERRY NUCLEAR PLANT JUL 1, 92 - SEP 30, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5 3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.047 0.0 0 ~0 0.0 0.047 HHE 0.0 0.0 0.0 0.0 0.0 0.284 0.047 0.0 0.0 0.332 HE 0.0 0.0 0.0 0.0 0.0 0.237 0.237 0.0 0.0 0.474 EHE 0.0 0.0 0.0 0.0 0.0 0.142 0.047 0.0 0 ' 0.190 E 0.0 0.0 0.0 0.0 0.0 0.047 0.0 0.0 0.0 0.047 ESE 0.0 0.0 0.0 0 ' 0.0 0.0 0.095 0.0 0.0 0.095 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 SW 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.047 0.0 0.0 0.047 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 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 0.0 0.0 0.0 O.Q 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.758 0.474 O.Q 0.0 1.232 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2119 TOTAL HOURS OF STABILITY CLASS G 26 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G 26 TOTAL HOURS OP VALID WZND DZRECTIOH-WIHD SPEED-STABILITY OBSERVATIONS 2110 TOTAL HOURS CALM 0 METEOROLOGZCAL FACILITY: MET PACZLITY LOCATED 1.3 KM ESE OP BROWHS FERRY NUCLEAR PLAHT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WZND SPEED AND DIRECTION MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 10/22/92 MEAN WIND SPEED = 12.0 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED PROM UNROUNDED NUMBERS

Radiological Impact Assessment Browns Ferry Nuclear Plant July December 1992 TABLE 6B Joint Frequency Distribution in Percent for Stack Releases Fourth Quarter 1992

BFN RAD Impact JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABILITY CLASS A (D <~-1.9 C/100 M)

BROWNS FERRY HUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5 ' 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >a24.5 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 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL HOURS OF VALID STABZLITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS A 0 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 0 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABZLZTY OBSERVATIONS 2188 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY MET FACILITY LOCATED 1 3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEH 45.30 AND 89.59 METERS WIND SPEED AND DZRECTZON MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED = 0.0 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAZNED FROM UNROUNDED NUMBERS

BEN RAD Impact JOINT PERCENTAGE FREQUENCIES 0 July cember 1992 D SPEED BY WZHD DIRECTION FOR Page 67 STABILITY CLASS B {- ELTA-T<=-1.7 C/100 M)

BROWNS FERRY HUCLEAR PIANT OCT 1, 92 - DEC 31, 92 WZHD WIND SPEEDtMPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HE 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 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.046 0.0 0.0 0.046 WSW 0.0 0.0 0.0 0.0 0.0 0.046 0.0 0.0 0.0 0.046 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 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 HNW 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 0.0 0.0 5

SUBTOTAL 0.0 0.0 0.0 0.0 0.0 0.046 0.046 0 ' 0.0 0.091 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS B 2 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B 2 TOTAL HOURS OF VALZD WIND DIRECTION-WZHD SPEED-STABILITY OBSERVATZONS 2188 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DIRECTION MEASURED AT THE 92 '3 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED I 11. 8 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact JOINT PERCENTAGE FREQUENCIES OF SPEED BY WIND DZRECTZON FOR July -"ember l992 Page 67 STABZZ ZTY CLASS C (- ELTA-T(~-1. 5 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >~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 0.0 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 0.183 0.046 0.0 0.0 0.$ 29 SE 0.0 0.0 0.0 0.0 0.046 0.091 0.0 0.0 0.0 0.137 SSE 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 0.0 0.0 S 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 0.0 0.0 0.046 0.0 0.0 0.0 0.046 SW 0.0 0.0 0.0 0.0 0.0 0.046 0.0 0.046 0.0 0.091 WSW 0.0 0.0 0.0 0.0 0.0 0.137 0.0 0.0 0.0 0.137 W 0.0 0 ~ 0 0.0 0.0 0.046 0.0 0.0 0.0 0.0 0.046 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.091 0.503 0.046 0.046 0.0 0.686 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS C 15 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C 15 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2188 TOTAL HOURS CALM 0 METEOROLOGICAL FACZLZTY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZLZTY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DIRECTION MEASURED AT THE 92.63 METER LEVEL DATE PRZNTED: 01/14/93 MEAN WZND SPEED ~ 10.8 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact JOINT PERCENTAGE FREQUENCIES OF D SPEED July cember 1992 BY WIND DIRECTZON FOR Page 67 STABILITY CLASS D (- ELTA-T<=-0.5 C/100 M)

BROWNS FERRY NUCLEAR PLAHT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12. 4 12. 5-18. 4 18. 5-24. 4 >~24.5 TOTAL N 0.0 0.0 0.091 0.411 0.686 2.971 1.782 0.548 0.091 6.581 NHE 0.0 0.0 0.091 0.183 0.274 1.645 1. 188 0.091 0.0 3.473 NE 0.0 0.0 0.091 0.137 0.274 1.188 0.274 0.0 0.0 1.965 ENE 0.0 0.0 0.091 0.183 0.183 0.320 0.046 0.046 0.0 0.868 E 0.0 0.0 0.091 0.366 0.320 0.457 0.0 0.0 0.0 1.234 ESE 0.0 0.0 0.091 0.503 0.686 0.960 1.005 0.137 0.046 3.428 SE 0.0 0.0 0.183 0.548 0.777 0.914 2.057 1.645 1.828 7.952 SSE 0.0 0.0 0.137 0.320 0.503 1. 554 1.463 0.457 0.366 4.799 S 0.0 0.0 0.274 0.320 0.731 1.371 0.868 0.457 0.046 4 '68 SSW 0.0 0.0 0.183 0.366 0.274 0.457 0.640 0.274 0.137 2.331 SW 0.0 0.046 0.366 0.320 0.229 0.274 0.503 0.229 0.229 2.194 WSW 0.0 0.0 0.229 0.274 0.274 0.503 0.457 0.366 0.0 2.102 W 0.0 0.0 0.046 0.457 0.411 0.960 0.777 0.274 0.046 2.971 WNW 0.0 0.0 0.366 0.274 0.320 0.731 0.640 0.548 0.183 3.062 HW 0.0 0.046 0.229 0.594 0.457 1.051 1.097 0.503 0.229 4.205 NNW 0.0 0.046 0.137 0.274 0.594 3.291 2.148 0.548 0.0 7.038 SUBTOTAL 0.0 0.137 2.697 5.530 6.993 18.647 14.945 6.124 3.199 58.272 TOTAL HOURS OF VALZD STABILITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS D 1281 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 1275 TOTAL HOURS OF VALID WZND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2188 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45 '0 WIND SPEED AND DIRECTION MEASURED AT THE 92.63 METER LEVEL AND 89.59 METERS DATE PRINTED: 01/14/93 MEAN WIND SPEED = 12.2 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact JOZNT PERCENTAGE FREQUENCIES 0 July cember 1992 D SPEED BY WIND DIRECTION FOR Page 67 STABILITY CLASS E (- DELTA-T<~ 1. 5 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >a24.5 TOTAL H 0.0 0.0 0.046 0.091 0.0 0.411 0.777 0.091 0.0 1.417 HNE 0.0 0.0 0.137 0.137 0.137 0.366 0.731 0.320 0.0 1.828 HE 0.0 0.046 0.091 0.137 0.0 0.457 1.051 0.183 0.0 1.965 ENE 0.0 0.0 0.091 0.046 0.046 0.274 0.686 0.137 0.0 1.280 E 0.0 0.0 0.183 0.091 0.137 0.320 0.091 0.0 0.0 0.823 ESE 0.0 0.0 0.137 0.137 0.229 0.594 0.640 0.274 0.0 2.011 SE 0.0 0.0 0.274 0.320 0.503 1.143 1.737 1.325 0.868 6.170 SSE 0.0 0.091 0.137 0.274 0.548 l. 417 1.280 0.594 0.183 4.525 S 0.0 0.046 0.091 0.229 0.503 1.782 1.005 0.091 0.0 3.748 SSW 0.0 0.0 0.091 0.091 0.229 0.640 0.777 0.274 0.0 2.102 SW 0.0 0.0 0.137 0.046 0.137 0.320 0.457 0.0 0.0 1.097 WSW 0.0 0.046 0.137 0.091 0.183 0.229 0.366 0.091 0.0 1.143 W 0.0 0.0 0.137 0.274 0.183 0.137 0.091 0 '46 0.0 0.868 WNW 0.0 0.0 0.046 0.183 0.091 0.046 0.091 0.0 0.0 0.457 NW 0.0 0.0 0.046 0.137 0.183 0.594 0.274 0 '46 0.0 1.280 NNW 0.0 0.046 0.0 0.046 0.0 0.594 0.960 0.046 0.0 1.691 SUBTOTAL 0.0 0.274 1.782 2.331 3.108 9.324 11.015 3.519 1.051 32.404 TOTAL HOURS OF VALID STABZIZTY OBSERVATIONS 2195 TOTAL HOURS OF STABILZTY CLASS E 709 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 709 TOTAL HOURS OF VALID WIND DZRECTION-WIND SPEED-STABILITY OBSERVATIONS 2188 TOTAL HOURS CALM 0 METEOROLOGZCAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABZLITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DIRECTION MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED = 12.4 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

BFN RAD Impact JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR July cember 1992 Page 67 STABILITY CLASS F ( ELTA-T<= 4. 0 C/100 M)

BROWNS FERRY NVCLEAR PLANT OCT 1, 92 - DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 )MR24. 5 TOTAL N 0.0 0.0 0.0 0.0 0.0 0.091 0.091 0.0 0.0 0.183 NNE 0.0 0.0 0.0 0.0 0.0 0.091 0.046 0.046 0.0 0.183 NE 0.003 0.0 0.046 0.0 0.0 0.183 0. 137 0.0 0.0 0.368 ENE 0.006 0.0 0.091 0.0 0.046 0.366 0.274 0.0 0.0 0.783 E 0.003 0.0 0.046 0.0 0.046 0.229 0.091 0.0 0.0 0.414 ESE 0.009 0.0 0.137 0.091 0.183 0.229 0.366 0.091 0.0 1.105 SE 0.003 0.0 0.046 0.091 0.046 0.137 0.320 0.046 0.0 0.688 SSE 0.003 0.0 0.046 0.0 0.046 0.411 0.046 0 ' 0.0 0. 551 S 0.003 0.046 0.0 0.091 0.091 0.091 0.274 0.091 0.0 0.688 SSW 0.003 0.0 0.046 0.0 0.046 0.091 0.137 0.0 0.0 0.323 SW 0.0 0.0 0.0 0.0 0.137 0.091 0.0 0.0 0.0 0.229 WSW 0.003 0.046 0.0 0.0 0.091 0.183 0.0 0.0 0.0 0.323 W 0.0 0~0 0.0 0.0 0.0 0.137 0.0 0.0 0.0 0.137 WNW 0.003 0.0 0.046 0.046 0.0 0.0 0.0 0.0 0.0 0.094 NW 0.006 0.046 0.046 0.229 0.046 0 ' 0.0 0.0 0.0 0.371 NNW 0.003 0.0 0.046 0.046 0.0 0.046 0.0 0.0 0.0 0.140 SUBTOTAL 0.046 0.137 0.594 0.594 0.777 2.377 1.782 0.274 0.0 6.581 TOTAL HOURS OF VALID STABZLZTY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS F 144 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 144 TOTAL HOURS OF VALID WIND DIRECTZON-WIND SPEED-STABILITY OBSERVATIONS 2188 TOTAL HOURS CALM 1 METEOROLOGICAL FACILITY: MET FACILITY LOCATED 1.3 KM ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DIRECTION MEASURED AT THE 92 '3 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED RR 10.0 MPH NOTE'OTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM VNROUNDED NUMBERS

srM mm impact July cember 1992 JOINT PERCENTAGE FREQUENCIES 0 D SPEED BY WIND DIRECTION FOR Page 67 STABZLZTY CLASS-G ( T > 4. 0 C/100 M)

BROWNS FERRY NUCLEAR PLANT OCT 1, 92 DEC 31, 92 WIND WIND SPEED(MPH)

DIRECTION CAI M 0.6-1.4 1.5-3.4 3 '-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 >=24.5 TOTAL N 0.0 0.0 0.046 0.0 0.0 0.0 o.o46 0.0 0.0 0.091 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.046 0 ' 0.0 0 ~ 046 NE 0.0 0.0 0.046 0.0 0.0 0.0 0.091 0.091 0.0 0.229 ENE 0.0 0.0 0.0 0.0 0.0 0.091 0.091 0.0 0.0 0.183 E 0.0 0.0 0.0 0.046 0.0 0.091 0.0 0.0 0.0 0.137 ESE 0.0 0.0 0.0 0~0 0.0 0.0 0.046 0.0 0.0 0.046 SE 0.0 0.0 0.091 0.046 0.091 0.274 0.274 0.0 0.0 0.777 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.046 0 0 0.0 0.046 S 0.0 0.0 0.0 0.0 0.0 0.0 0.137 0.0 0.0 0.137

- SSW 0.0 0.0 0.0 0.0 o.o46 0.0 0.0 0.0 0.0 0.046 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.046 0.0 0.0 0.0 0.0 0.046 W 0.0 0.0 0.0 0.0 0.0 0. 137 0.0 0.0 0.0 0.137 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0 ' 0.0 0.0 0.0 NW 0.0 0.0 0.046 0.0 0.0 0.0 0.0 0.0 0.0 0.046 NNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.229 0.091 0.183 0.594 0.777 0.091 0.0 1.965 TOTAL HOURS OF VALZD STABZLITY OBSERVATIONS 2195 TOTAL HOURS OF STABILITY CLASS G 44 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABZLZTY CLASS G 43 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2188 TOTAL HOURS CALM 0 METEOROLOGICAL FACZLZTY: MET FACZLZTY LOCATED 1.3 EM ESE OF BROWNS FERRY NUCLEAR PLANT STABIIZTY BASED ON LAPSE RATE MEASURED BETWEEN 45.30 AND 89.59 METERS WIND SPEED AND DIRECTION MEASURED AT THE 92.63 METER LEVEL DATE PRINTED: 01/14/93 MEAN WIND SPEED = 11.3 MPH NOTE: TOTALS AND SUBTOTALS ABOVE ARE OBTAINED FROM UNROUNDED NUMBERS

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT (BFN)

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT

EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT SUMNARY SECOND HALF 1992 The radioactive effluents for the second half of 1992 were normal for a three unit boiling water reactor plant with one unit operating and the other two in extended outage.

The release of radioactive material to the environment from Browns Ferry has been a small fraction of the 10 CFR 20 Appendix B and 10 CFR 50 Appendix I limits.

Page 1 of 16

EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT SUPPLEMENTAL INFORNATION SECOND HALF 1992 A. Fission and Activation Gases in Gaseous Effluent:

The release of fission and activation gases is regulated by the dose limits of 10 CFR 50 Appendix I. The air dose, to areas at and beyond the site boundary due to noble gases released in gaseous effluents per unit, shall be limited during any calendar quarter to g 5 millirad (mrad) for gamma radiation and g 10 mrad for beta radiation; and during any calendar year to g 10 mrad for gamma radiation and g 20 mrad for beta. radiation.

B. and C. Iodines and Particulates with Half-Lives Greater than Eight Days in Gaseous Effluents.

The release of iodines and particulates in gaseous effluent is regulated by the dose limits of 10 CFR 50 Appendix I. 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 eight days in gaseous effluent released per unit to areas at and beyond the site boundary shall be limited to any organ during any calendar quarter to g 7.5 millirem (mrem), and during any calendar year to Z 15 mrem.

D. Liquid Effluents The release of radioactive liquid effluents is regulated by the dose limits of 10 CFR 50 Appendix I. 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 during any calendar quarter to g 1.5 mrem to the total body and < 5 mrem to any organ and during any calendar year to < 3 mrem to the total body and < 10 mrem to any organ.

Page 2 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1992 A. Fission and Activation Gases in Gaseous Effluent:

1. The instantaneous release rate of fission and activation gases is regulated by the dose rate limit of 10 CFR 20 Appendix B. The dose rate at any time to areas at and beyond the site boundary due to noble gases released in gaseous effluents from the site shall be limited to < 500 mrem per year to the total body and

< 3000 mrem per year to the skin.

2. The BFN Offsite Dose Calculation Manual (ODCM) determines the maximum noble gas release rate based upon the dose rate limits in Section III. The instantaneous noble gas release rates are limited by the following equation:

g3, + gal<1 0.15 14.4 Ql = The release rate from the building exhaust vents in Ci per second.

Q2 = The release rate from the main stack in Ci per second.

B.~ and C.~ Iodines and Particulates

~

with Half-Lives Greater than Eight Days in Gaseous Effluents

1. The instantaneous release rate of particulates and iodines is regulated by the dose rate limit of 10 CFR 20 Appendix B. The dose rate at any time to areas at and beyond the site boundary, due to I-131, H-3 and particulates with greater than eight days half-lives released in gaseous effluents from the site, shall be limited to < 1500 mrem per year to any organ.

2. The BFN ODCM determines the maximum particulate and iodine release rate based upon the dose rate limit in Section III. The instantaneous iodine and particulate release rates are limited by the following equation:

Q3 + g4<1 2.19 35.7 Q3 = The release rate from the building exhaust vents in pCi per second.

Q4 = The release rate from the main stack in pCi per second.

Page 3 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1992 t t (Continued)

D. Liquid Effluents

1. The concentration of radionuclides in liquid effluents released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B,

Table II, Column 2 for radionuclides other than dissolved or entrained noble'ases.

2. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi per milliliter (ml) total activity.

IV. tvt A. Fission and Activation Gases.'.

Noble gases in the building vent and stack gaseous effluent are continuously monitored. The flow rate of the stack is continuously monitored and the building vent effluent flow rates are calculated once a shift based on the configuration of operating exhaust fans. The flow rate data is consolidated weekly to determine the volume of airborne effluent released from the plant. The noble gas monitor data is consolidated monthly to determine the total curies of noble gases released during the month.

2. Gas grab samples are taken and analyzed monthly to determine the relative noble gas activity concentrations. This information is used to apportion the total curies of noble gases released among different noble gas radionuclides.

3. The tritium concentration is determined by the analysis of a monthly grab sample for each release point.

B. and C. Iodines and Particulates

1. Iodines and particulates are continuously sampled on impregnated charcoal filters and particulate filters, respectively. The charcoal and particulate samples are replaced at least weekly and analyzed to determine specific activity concentrations. The specific activity concentrations and vent flow rate data are used weekly to verify that release rate limits were not exceeded. The specific activity concentrations and total volume of gaseous effluent are used on a monthly basis to determine the total curies of each particulate and iodine released during the month.

Page 4 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1992

~

t ~

t t'v't nt'n

2. The gross alpha concentration is determined by analysis of a monthly particulate filter composite sample and strontium -89 and -90 are determined by analysis of a quarterly particulate filter composite sample for each release point.

D. Liquid Effluents

1. The gamma ray emitting radionuclide concentrations are determined for each batch by gamma ray spectroscopy analysis of a grab sample.

The allowable release rate is calculated for each batch based upon the known dilution flow. The flow rate of the liquid effluent is continuously monitored and the total volume released in each batch is determined. The total gamma activity released in each batch is determined by multiplying the radionuclide concentrations by the total volume discharged. The total gamma activity released during the month is then determined by summing the gamma activity content of each batch discharged during the month.

2. The gross alpha and tritium concentrations are measured on a monthly composite sample. The strontium -89 and -90 and iron -55 are measured on a quarterly composite sample.

V. 33~t Third Fourth ggazt~ gg~t Units A. Liquid

1. Number of batches released 75 117 Each

2. Total time period for batch releases 19400 32088 Minutes

3. Maximum time period for a batch release 355 365 Minutes

4. Average time period for batch releases 258 274 Minutes

5. Minimum time period for a batch release 140 165 Minutes

6. Average stream flow during period of release of effluent into a flowing stream 36172 62842 cfs B. Gaseous None VI. ABNORMAL/UNPLANNED RELEASES (1)

NUMBER OF TOTAL RELEASES ACTIVITY A. Liquid None None B. Gaseous None None (1) All abnormal/unplanned releases shall be discussed in the summary.

Page 5 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Third Fourth A. Fission and Activation Products F2 t QQQX t~ QQGX t f.r ~~r

1. Total Releases Curies 4.91E-Ol 1.04E+00

2. Average Diluted Concentration Released During Period pCi/ml 1.12E-08 1.43E-08

3. Percent of Applicable Limit (1.00E-07 pCi/ml) 1.12E+01 1.43E+01 B. Tritium

1. Total Releases Curies 7.75E+00 9.54E+00

2. Average Diluted Concentration Released During Period pCi/ml 1.76E-07 1.31E-07

3. Percent of Applicable Limit (3E-03 pCi/ml) 5.87E-03 4.36E-03 C. Dissolved and Entrained Noble Gases

1. Total Releases Curies 1.17E-02 1.63E-01

2. Average .Diluted Concentration Released During Period pCi/ml 2.66E-10 2.23E-09

3. Percent of Applicable Limit (2E-04 pCi/ml) 1.33E-04 1.11E-03 D. Gross Alpha Radioactivity

1. Total Releases Curies ND 3.51E-03 48

2. Average Diluted Concentration Released During Period pCi/ml ND 4.81E-11 E. Volume of Liquid Waste to Discharge Canal (Before dilution) Liters 8.55E+06 1.40E+07 3 F. Volume of Dilution Water for Period Liters 4.40E+10 7.29E+10 10 G. Total CCW flow for Six Months Gigagallons 153.6 1 Includes Ze-133, Xe-135, and others Page 6 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR SECOND HALF 1992 BATCH MODE Third Quarter Fourth Quarter (Required by Regulation (REG) Guide 1.21)

1. Cr-51 2.32E-02 5.72E-02

2. Mn-54 4.07E-03 1.23E-02

3. Co-58 1.50E-03 4.59E-03

4. Fe-59 ND ND

5. Co-60 1.95E-02 1.71E-02

6. Zn-65 2.84E-03 2.15E-02

7. Nb-95 ND ND

8. Zr-95 ND ND

9. Mo-Tc-99m 3.55E-02 1.79E-01

10. I-131 1.35E-02 1.50E-02 ll. Ze-133 4.37E-03 2.45E-02

12. Cs-134 1.11E-02 1.23E-02

13. Xe-135 7.35E-03 3.91E-02

14. Cs-137 1.28E-01 1.05E-01

15. Ba-140 2.74E-04 7.47E-05

16. La-140 1.29E-04 ND

17. Ce-141 ND ND

18. Sr-89 2.96E-02 8.03E-03

19. Sr-90 2.14E-03 1.07E-03 Page 7 of 16

EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT LIQUID RELEASES FOR SECOND HALF 1992 BATCH NODE 0

~~t~Required Third Quarter Fourth Quarter (Not by Regulation (REG) Guide 1.21)

1. Fe-55 1.86E-03 1.25E-02

2. Na-24 2.05E-01 5.40E-01

3. Sr-91 ND 1.05E-03

4. I-132 1.08E-04 8.42E-04

5. I-133 1.07E-02 3.69E-02

6. I-135 ND 1.56E-02

7. Ze-133m 1.79E-04

8. Xe-135m 8.41E-11 2.38E-07

9. Y-91m 1.25E-05 5.43E-04

10. Sr-92 7.49E-05 2.54E-04

11. Ag-110m 8.62E-04 3.97E-04

12. Ru-103 4.13E-04 1.74E-04

13. Sb-124 5.97E-05 ND

14. Cs-136 2.75E-04 7.61E-04

15. Tc-104 ND 4.57E-10

16. I-134 ND 5.68E-06 Page 8 of 16

0 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Third Fourth Summation of All Releases gg~t @gal>~t A. Fission and Activation Gases

1. Total Releases Curies 3.59E+03 1.01E+04 45

2. Average Release Rate for Period pCi/sec 4.56E+02 1.29E+03

3. Percent of Technical Specification (TS) limit 5.52E-03 8.93E-03 B. Iodines.

1. Total Iodine-131 6 I-133 Ci 4.52E-02 2.99E-02 36

2. Average Release Rate for Period pCi/sec 5.76E-03 3.80E-03

3. Percent of TS limit 2.43E-01 1.60E-01 C. Particulates

1. Particulates with half-lives

> eight days Ci 9.20E-03 2.06E-02 35

2. Average release rate for period pCi/sec 1.17E-03 2.62E-03

3. Percent of TS limit 5.23E-02 1.18E-01

4. Gross alpha radioactivity Ci ND ~ 7.01E-07 D. Tritium

1. Total release Ci 7.53E+00 3.96E+00 21

2. Average release rate for period pCi/sec 9.58E-01 5.04E-01

3. Ground level release Ci 7.23E+00 3.89E+00

4. Elevated release Ci 2.99E-01 7.25E-02 Reporting period 182 days.

The dose rate limit for Noble gases shall be < 500 mrem per year to the total body and < 3000 mrem per year to the skin and the dose rate limit for I-131, I-133, H-3, and particulates with ~ eight day half-lives shall be 1500 mrem per year to any organ.

Page 9 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 GASEOUS EFFLUENTS ELEVATED RELEASE Third Fourth

1. Fission Gases gg~t~ ~t~

Kr-85m Ci 6.18E+02 1.56E+03 Kr-85 Ci ND ND Kr-87 Ci 2.24E+02 8.52E+02 Kr-88 Ci 9.64E+02 2.82E+03 Ze-133 1.65E+03 4.40E+03 Ze-135m Ci ND ND Ze-135 3.51E+Ol 2.73E+02 Ze-138 Ci ND ND Others (specify)

Ar-41 Ci 1.15E+01 1.15E+01 Ze-133m Ci 5.35E+Ol 1.95E+02 Ci 3.56E+03 1.01E+04

2. Iodines I-131 Ci 8.35E-04 5.56E-04 I-132 Ci 2.09E-03 2.10E-03 I-133 Ci 2.89E-03 1.99E-03 I-134 Ci ND ND I-135 Ci 5.47E-03 3.00E-03 Ci 1.13E-02 7.65E-03 Page 10 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 GASEOUS EFFLUENTS ELEVATED RELEASE Third Fourth QLU~t gib ~~r

3. Particulates Sr-89 1 Ci 3.27E-05 5.69E-05 Sr-90 1 6.60E-08 1.80E-07 Cs-134 ,Ci ND ND Cs-137 Ci ND ND Ba-140 Ci 1.12E-04 8.34E-05 La-140 Ci 5.71E-05 8.00E-05 Others (specify)

Ag-110m Ci ND ND Ba-139 Ci 1.10E-01 5.56E-02 Co-58 Ci ND ND Co-60 Ci ND ND Cr-51 Ci ND ND Na-24 Ci ND ND Mn-54 Ci ND 7.99E-05 Mn-56 Ci ND ND MoTc-99m Ci ND ND Zn-65 Ci ND ND Sr-91 Ci 3.94E-03 5.59E-03 Y-92 Ci ND ND Rb-88 Ci ND 1.82E+00 X-91m Ci ND 1.95E-03 Ru-103 Ci ND ND Cs-136 Ci ND ND Ci 1.14E-01 1.88E+00

4. Tritium Ci 2.99E-01 7.25E-02 Predicted estimation of releases.

Include all particulate nuclides (even those with half-lives ( 8 days)

Page ll of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Third Fourth Qg~~t Qg~>~

1. Fission Gases.

Kr-85m ND ND Kr-85 ND ND Kr-87 .Ci ND ND Kr-88 Ci ND ND Xe-133 Ci ND ND Xe-135m Ci ND ND Xe-135 2.80E+01 ND Xe-138 Ci ND ND Others (specify)

Ar-41 Ci ND ND Xe-133m Ci ND ND 2.80E+01 ND

2. Iodines I-131 Ci 3.69E-03 2.79E-03 I-132 Ci 1.81E-02 2.34E-02 I-133 Ci 3.78E-02 2.46E-02 I-134 Ci 2.06E-02 ND I-135 Ci 4.68E-02 ND Ci 1.27E-01 5.07E-02 Predicted estimation of releases.

Page 12 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 19921 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Third Fourth gg~t~ gggg ttt

3. Particulates Sr-89 1 Ci 1.69E-03 2.25E-05 Sr-90 1 Ci 4.09E-07 ND Cs-134 3.14E-05 1.72E-04 Cs-137 Ci 6.53E-04 4.80E-04 Ba-140 Ci 4.98E-04 5.59E-04 La-140 Ci 3.62E-04 3.97E-04 Others (specify)

Ag-110m Ci 3.67E-04 8.54E-04 Ba-139 Ci 9.38E-01 5.02E-01 Co-58 Ci 1.82E-04 3.07E-04 Cr-51 Ci 3.95E-03 9.93E-03 Co-60 Ci 3.49E-04 5.22E-03 Mn-54 Ci 2.34E-04 3.25E-04 Mn-56 Ci 1.41E-02 ND MoTc-99m Ci 4.49E-03 1.77E-03 Na-24 Ci 1.36E-01 9.48E-02 Zn-65 Ci 6.78E-04 1.83E-03 Sr-91 Ci 5.91E-03 9.98E-03 Y-92 Ci 3.80E-02 ND Rb-88 Ci ND ND Y-91m Ci ND 4.63E-02 Ru-103 Ci ND 9.63E-05 Cs-136 Ci ND 1.47E-04 1.15E+00 6.75E-01

4. Tritium Ci 7.23E+00 3.89E+00 Predicted estimation of releases.

Include all particulate nuclides (even those with half-lives < 8 days)

Page 13 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite For Burial Or Disposal (Not Irradiated Fuel)

1. Type of Waste Qrgggg t

a. Spent resins, filter m3 8.75E+01 sludges, evaporator Ci 5.91E+01 1.50E+01 bottoms, etc.

b, Dry compressible waste m3 5.71E+01 contaminated equip., etc. Ci 3.45E+00 1.50E+Ol C ~ Irradiated components, m3 O.OOE+00 control rods, etc. Ci O.OOE+00 1.50E+01 d~ Other m3 O.OOE+00 Ci O.OOE+00 N/A Dry compressible waste shipped from processor to the burial ground.

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

a. Spent resins, filter sludge, evaporator bottoms, etc.

~t~

1. Iron 55 (2) 4.35E+00 2.53E+00

2. Cobalt-60 (1) 1.98E+01 1.15E+01

3. Cesium-134 (1) 1.72E+00 1.02E+00

4. Cesium-137 (1) 2.65E+01 1.54E+01

5. Nickel-63 (1) 3.20E+01 1.86E+Ol

6. Manganese-54 (1) 1.00E+00 5.85E-01

7. Iodine-131 (1) 4.00E+00 2.35E+00

8. Barium/Lanthanum-140 (1) 3. 95E+00 2.30E+00

9. Zinc-65 (1) 2.70E+00 1.57E+00

10. Chromium-51(1) 4.00E+00 2.32E+00 (1) Measured (2) Calculated Page 14 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

A.

~ Solid Waste Shipped Offsite For Burial Or Disposal

~

(Not Irradiated Fuel) (Continued)

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

b. Dry compressible waste, contaminated equipment, etc.

1. Iron-55 (2) 2.50E+01 8.63E-01

2. Cobalt-60 (2) 6.52E+01 2.25E+00

3. Nickel-63 (2) 2.59E+00 8.94E-02

4. Cesium-137 (2) 6.99E+00 2.42E-01 (1) Measured (2) Calculated

c. Irradiated components, control rods, etc.

None

d. Other None Number of Mode of Shtua~t 15 Sole Use Truck Barnwell, SC 29 Sole Use Truck Quadrex, Oak Ridge, TN Sole Truck SEGj Oak Ridge, TN Page 15 of 16

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1992 SOLlD WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

B. Irradiated Fuel Disposition Number of Mode of

~g~t t t D t t None N/A N/A C. Description of Shipments Number of Type Number of Container Type gg~t ~t~~Type 0 1l* H~t 37 Strong A-LSA See Note See Note DAW Tight Container (STC) 14 High A-LSA 14 5.83m3 Dewatered Integrity Resin Container (HIC)

HIC B-LSA 5.83m3 Dewatered Resin Solidification agents used: None Absorbents used: None NOTE: 37 shipments to waste processor contained the following:

Type of Number of Volume Each ggggcQ~ Q~c~~

40'ealand (STC) 72.50 20'ealand (STC) 36.25 "FR" Box (STC) 12 06.40 "B" Box (STC) 28 02. 66 "7A/55 Gallon" 1211 00. 21 Drums STC)

Leaded Box (STC) 12.90 "Waltz Mill" 36.25 Fuel Rack Box (STC)

Page 16 of 16

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT (BFN)

INOPERABLE RADIOLOGICAL EFFLUENT INSTRUMENTATION REPORT

This report is to comply with Browns Ferry Nuclear Plant Technical Specifications (TSs), Sections 3.2.D.2, 3.2.K.2 and Offsite Dose Calculation Manual (ODCM),

Sections 1/2.1.1 and 1/2.1.2. The BFN TS and ODCM require the exertion of best efforts to return inoperable radiological effluent monitoring instrumentation to an operable status within 30 days. Failure to return the inoperable instruments to an operable status requires a description in the next Semiannual Radioactive Effluent Release Report.

During the reporting period, July 1 through December 31, 1992, there was no airborne or liquid radiological effluent instrumentation inoperable for periods greater then 30 days.

The Effluent Monitors, which have been placed in "out-of-service" status with their effluent streams isolated, are not applicable for this report.

During this period, Units 1 and 3 were defueled and Unit 2 operating.

Page 1 of 1

ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT (BFN)

CHANGES TO THE BFN OFFSITE DOSE CALCULATION MANUAL JULY THROUGH DECEMBER 1992

CHANGES TO THE ODCM BFN Technical Specification 6.12.2 requires that changes to the Offsite Dose Calculation Manual (ODCM) be submitted to the commission with the semiannual Radioactive Effluent Release Report for the period in which the changes were made. This report covers the period between July through December 1992.

During this period, two revisions have been made to the ODCM. Revision 12 was a general revision and is submitted in its entirety. Revision 13, only the pages affected by the changes are submitted. Reference the attached notebook which contains the above changes.

Page 1 of 1

Steodhrd Sheet Form ONP STD'.4.44 Rev 1

~ SITE ADMINISTRATION OF SSP-2 3 STANDARD SITE PROCEDURES NOV 04 1991 PRACTICE FORM SSP-1 Page 1 of 2 PROCEDURE CONTROL FORM NO-: TRACKING NO. REV. NO.

/4 ex. ~

PROCEDURE 7e,~4~ic~/

&('efa~cc~r'4$

5 e 8 ~ 7 ec~pi d ~ g (A 4 i~J (For no.

( Z call (Site Procedures

/7~ ~~ tt 7820 or 2489) corn letes)

ROUTED FOR: g~Q [ ] EDITORIAL OR TYPO

[~ REVISION "il"/ ] ROUTINE NONZNTENT CHANGE [ ] CHANGE REQUEST

[ ] NEW INSTRUCTION [ URGENT INTENT CHANGE [ ] ADMINISTRATIVE HOLD

[ ] CANCELLATION REQUESTO R or PREPARER.

[ ]

a. /e, URGENT NONINTENT CHANGE Print Ar Name ri

[

d <2

] ADMIN HOLD RELEASE Date Phone TEMPORARY APPROVAL OF URGENT NONZNTENT CHANGE: (NA for other type changes)

KNOWLEDGEABLE KNOWLEDGEABLE MANAGER (SRO): MANAGER (2ND):

Print Name Initial & Date 'rint Name Initial & Date SPONSOR CHECK ORGANIZATION REVIEWS NEEDED. CHECKED ORGANIZATIONS CONCUR AND SIGN ORGANIZATION Si ture & Date ORGANIZATION Si ture & Date OPERATIONS / lg la ee MAINTENANCE RADCON e TRAINING WORK CONTROL CHEMISTRY TECH'UPPORT RESTART PROJ MODIFICATIONS LICENS ING SPONSOR IS PROCEDURE QUALITY-RELATED? [ ] YES [ ] NO OR REQUIRED BY TECH SPECS? [ ] YES [ ] NO IF EITHER IS YES, SPONSOR AND/OR IQR IDENTIFY IQR DISCIPLINE(S) BELOW IS PROCEDURE A COMPLEX INFREQUENTLY PERFORMED TEST OR EVOLUTION? [ ] YES [ ] NO IF YES~ TECH SUPPORT OR OPS AS APPLICABLE MUST PERFORM IQR OR CROSS-DISCIPLINE REVIEW AND ENSURE THAT DISCI L: E REQUIREMENTS OF SSP-8.1 OR SSP-12.1 ARE MET.

4 8 CROSS ISC LINE(S) ' 4c.~ (u or-7

/e IR Si ture t R Si ture(s) & Date SPONSOR: IS WALKDOWN BEFORE APPROVAL REQUIRED?

Zf yes, walkdown performed by :

[] YES [ NO Signature & Date HAS THE CURRENT REVISION OF THIS PROCEDURE BEEN VALIDATED'?[ ] YES [ ] NO [~NA DOES THIS REVISION'EED TO BE VALIDATED? YES 0 FOR PMIs, SDSPs, AND SSPs ONLY: IF PORC (NA OTHERWISE) REQUIRED: i- 3-R>.

(NA IF NOT) ORC CHAIRMAN 'gna e & Date SPONSOR Si ture & Date PLANT MANAGER Si ture & Date FOR SSPs AND SDSPs ONLY (NA OTHERWISE OR (NA IF APPROVAL AUTHORITY HAS ALREADY IF PRINCIPAL MANAGER HAS AIZ1M)Y SIGNED SIGNED ABOVE.)

ABOVE~)

PRINCIPAL MANAGER Signature & Date APPROVAL AUTHORITY Signature & Date TVA 40004 (ONP-I24S) $(pl- gQ Awffcvn /Lg er I-c(

Standard Shaet Form ONP.ST&4AA.3 Rev I SITE ADMINISTRATION OF SSP-2m 3 STANDARD SITE PROCEDURES PRACTICE . NOV 04 199l FORM SSP-2 Page 1 of 2 SAHPTY ASSESSMENT FORM Procedure No. E.< Tracking No.

YES NO Does a previous safety assessment adequately address this change?

If yes, go to page 2, and state in the summary section which previous assessment is applicable.

List the specific Tech Spec requirements (by number) associated with this procedure:

/. lL 4.5.3 ~ t YES NO NA A. Does this procedure (or source notes) specify the Tech Spec requirements it implements? (If a procedure does not it fully satisfy a Tech Spec requirement, must state what part of the requirements it does fulfill.)

B. Does this procedure satisfy all associated Tech Spec requirements?

C. Is this procedure consistent uith the basis for the applicable Tech Spec requirements?

If any of the preceding questions A through C are answered 'NO"p then

1) Change the procedure to achieve a "YES" answer, or

2) Obtain a License Amendment from NRC before proceeding.

List the SAR sections and documents related to this procedure:

D. Does the procedure require system operation consistent with the SAR?

E. Are setpoints and acceptance criteria consistent with the SAR?

F. Is the 'procedure consistent with personnel duties and responsibilities specified in the SAR'?

G. Are prerequisites for plant systems status and equipment condition adequate and consistent with safe operation?

TVA 4XOl (ONP-1248)

. Srandard Shoes'orm ONP.~.4A.3 Rev 1 SITE ADMINISTRATION OF SSP-2.3 STANDARD SITE PROCEDURES PRACTICE HOY 04 I991 FORM SSP-2 Page 2 of 2 NO NA H. Does the procedure fulfillthe requirements of all applicable SAR sections?

I. If the procedure is a test that could impact nuclear safety, has the test been authorized by NRC?

If any of the preceding questions D through I are answered "NO", then

1) Change the procedure to achieve a "YES" answer, or

2) Complete a Safety Evaluation .per SSP-12.13.

J. Does the procedure make a temporary alteration to a Radwaste System? If YES, complete a Safety Evaluation per SSP-12.13.

K. Is this procedure change safe from a Nuclear Safety standpoint? If NO, revise or cancel the procedure.

Provide a summary of why this procedure is safe:

cbwi c.d S c) i

~4~5'e +4m< Mate c. '

Z +M

'.ls eo 5 M ic. e 4>~

s is

~ ~

Q Prepared by:

.59 e 1 Revi

~ye~ jt Oat Safety Assessment Reviewer Date Sponsoring Manager (Must be a 50.59 Level I Reviewer and also be IgR qualified or be a 50.59 Level II Reviewer)

TVh 40004 (ONP-1248)

e t

SCauhrd SbeeC Form ONP-~.<.C-3 1

SITE ADlfINISTRATIONOF SSP-2e3 STANDARD SITE PROCEDURES Page 26 of 46 PRACTICE REV 0005 APPENDIX C (Continued)

TXPXCAL COVERSHEET AND REVISION LOG The detailed description of change vill only be issued to controlled copies for the latest revisioc. DCRH or Site procedcre maicCaios a complete history oi all revisioas

. REVISION LOG Procedure Number. E cC ~~ ~f Revision Number:

(Site Procedures completes)

Pages Affected: s-y Description of Change.

ca <<s ~ s Pe ~&

77< i C-A sc e. t- e yahoo u eA rm,'r es e~l Z G, 2- z 4.a y 1'~ tZ Ajg uy t

h 78r V~/ Pa~ rC e Ca si eC~2 ice- Wutr ver'i'I rw ei lX

~ei le, ye~.

yLe s.zW hL.+a~u~/ X ea oue 8 H~o Ho:m bo7es

/le~a 8 . ~. - t 8,;~. r>zc r-,

ti Iz < 2- .

A 55 u.

Parallel Procedure ts W

$ 5/

~ 3'-sz-l Chan es g,2- 7 includin tractin number:

M

./>> f 2-5c

< WiLK

-/ i/wy 8]g 5 TVA 40004 (ONP-ITS)

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT RETS mNUQ, RADIOLOGICAL EKHENT TECHNICAL SPECIFICATION (RETS)

REVISION 12 PREPARED BY: DALE W. NIX PHONE: 2682 RESPONSIBLE ORGANIZATION: CHEMICAL TECHNICAL SUPPORT h

APPROVED BY: A. W. SORRELL DATE: 11/17/92 EFFECTIVE DATE: 11/18/92 VALIDATION DATE: NOT REQUIRED QUALITY-RELATED j&QJI

(1496)

REVISION LOG Procedure Number: RETS MANUAL Revision Number: 12 Pages Affected: 49, 54, 59 Pagination Pages: 1-48, 50-53, 55-58,60-266 Description of Change:

The change makes the ODCM consistent with TS change 311. This change removes the provision in control/surveillance requirement 2.0.2 that limits the combined time interval for three consecutive surveillance tests to less than 3.25 time the interval specified in the ODCM for the surveillance test. The 3.25 time interval is removed from two notes (pp.

54, 59).

RETS Manual Revision 12.

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 251 of the surveillance interval.

2.0.3 Performance of a Surveillance 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.

59(206)

RETS Manual RevLsion 54 12'age 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.

1 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.

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

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

b. Instrument indi.cates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

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 consi.st of verifying indication during peri.ods 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 ade 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 thag participate in measurement assurance activities with the NIST.

59(206)

RETS Manual Revision 12" 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 oE the interval given.

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

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

2. Instrument indicates an inoperative/downscale Eailure.

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 nob)e gas monitor shall have a LLD of lE-5 {Ze-133 Equivalent) 5 The noble gas monitor shall have a LLD of 1E-6 (Xe-133 Equivalent)

'9(206)

'Stlndaid Sheet Form ONP.STDA.4.4 3 Rev 1 SITE ADMINISTRAT/ON OF ,", . SSP-2.3, STANDARD SITE PROCEDURES PRACTICE

,,'....NOV 04 1991 FORM SSP-2 Page 1 of 2 SAFETY ASSESSMENT FORM Procedure No. Jf w~./ Tracking No.

YES NO Does a previous safety assessment adequately address this change2 If yee, go to page 2, and state in the summary section whi.ch previous assessment ia applicable.

Li.st the speci.fic Tech Spec requirements (by number) associated with this procedure'.

w cd/

YES NO NA A. Does this procedure (or source notes) speci.fy the Tech Spec requirements it implements2 (If a procedure does not it must state what fully satisfy a Tech Spec requirement, part of the requirements it does fulfill.)

B. Does this procedure satisfy all associated Tech Spec requirements2 C. Is this procedure coosisteot with the basis for the applicable Tech Spec requiremente2 If any of the preceding questions A through C are answered "NO", then

1) Change the procedure to achi.eve a "YES" answer, or

2) Obtain a License Amendment from NRC before proceeding.

List the SAR secti.one and documents related to this procedure:

D. Does the procedure require system operation consistent with the SAR2 E. Are setpointe and acceptance criteria consistent with the SAR2 F. Is the procedure consistent wi.th p'ereonnel duties and responsibili.ties specified in the SAR2 G. Are prerequi.sites for plant systems status and equi.pment condition adequate and consistent with safe operation'2 TVA 40004 (ONP-1248)

Standard Shoat Form ONP.STDH.4.43 Rav I SITE ADMINISTRATION OF ,'.I',SSP-2.3 STANDARD SITE PROCEDURES ~A \<

PRACTICE NOV 04 1991 FORM SSP-2 Page 2 of 2

YES NO NA H. Does the procedure fulfillthe requirements of all applicable SAR sections'2 I. If the procedure is a test that could impact nuclear safety, has the test been authorised by NRC2 If any of the preceding questions D through I are answered 'NO", then

1) Change the procedure to achieve a "YES" answer, or-

2) Complete a Safety Evaluation per SSP-12.13.

J. Does the procedure make a temporary alteration to a Radwaste System2 If YES, complete a Safety Evaluation per SSP-12.13.

K. Is this procedure change safe from a Nuclear Safety standpoint2 If NO, revise or cancel the procedure.

Provide a summary of why this procedure is safe:

Prepared by: tl g.f g2-50.59 Level I Reviewer Date Safet Assessment Reviewer Date , Sponsoring Manager Date (Must be a 50.59 Level I Reviewer and also be IQR qualified or be a 50.59 Level II. Reviewer)

TVh 40004 (ONP-1248)

i RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS MANUAL Revision 33'- Tracking No. 13 Technical, Specification (TS)

References:

Sections 1.0 BB, 1".0 EE, 3/4.8, 6.5.1.6 g, 6.5.1;6.h; 6.5.2.8 n, 6.5.2.8 o, 6.5.2.8 p, 6.8.1.1 g, 6.8.1.1 h, 6.8.1..1 i, 6.11, 6.12, and 6.13.

Final Safety Analysis Report (FSAR)

References:

Sections 1.6.1.6, 2.6.2, 7.12, 9.0, 10.12.5.2, 10.12.5.4, and 10.17.

Provide a summar of wh this rocedure is safe.'everal typographical errors were corrected., This includes corrections to the stack monitor designation, units.,in equations, number of pumps available for minimum dilution flow;; and values in the tables.

F "a 'w"~"'~

A station was added to collect drinking Water'-";(public water) from the Florence, Alabama municipal water supply.",,; The city of Florence, Alabama has recently built a second water treatment plant. This plant draws water from the Tennessee'River at river mile 259.8. Since this is a new water supply taken from the river downstream from BFN, the station will be added to the BFN radiological environmental monitoring program.

The only ,systems,.potentially affected by a change'to the ODCM will be the liquid and gaseous effluent and process.'onitoring systems described in the BFN FSAR. The typographical, changes and the addition of a monitoring station do not affect':=. any system.

This change is .safe from a nuclear safety standpoints

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT RETS MANUAL RADIOLOOICAL EFFLOEHT TECHNICAL SPECIFICATION (NETS)

REVISION 13 PREPARED BY: DALE lF. NIX . PHONE: 2682 RESPONSIBLE ORGANIZATION: CHEMICAL TECHNICAL SUPPORT APPROVED BY: J. SCALICE DATE: 12/22/92 EFFECTIVE DATE: 12/29/92 VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

(1496)

REVISION LOG Procedure Number: RETS MANUAL Revision Number: 13 Pages Affected: 56, 103, ill, 115 118-120, 202> 204, 215, 217, 234, 237, 241 Pagination Pages: 1-55,57-102, 104-110, 112-114, 116, 117, 121-201, 203, 205-214, 216, 218-233, 235, 236, 238-240, 242-266 Description of Change:

Several typographical .errors were corrected. This includes corrections to the stack monitor designation, units in equations, number of pumps available for minimum dilution flow, and values in tables. Add the collection of drinking water (public water) from the Florence, Alabama municipal water supply.

RETS Manual Revision'3 Page 1 Brogans Ferry Nuclear Plant Radiological Effluent Technical Specification (RETS)

Manual 600(207)

RETS Manual Revision 13 Page 2 INDEK Section I. Introduction II. Radiological Effluent Manual (REM)

III. Offsite Dose Calculation Manual (ODCM)

IV. Process Control Program (PCP) 600(207)

RETS Manual Revision 13 Page 3 RETS Manual Section I Introduction 600(207)

RETS Manual Revision 13 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.

600(207)

RETS Manual Revision 13 Page 5 RETS MANUAL Section II RADIOLOGICAL EFFLUENT MANUAL (REM)

For the Browns Ferry Nuclear Plant Limestone County, Alabama Tennessee Valley Authority 600(207)

RETS Manual Revision,13 Page 6 RADIOLOGICAL EFFLUENT MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV. NO.

A. INTRODUCTION A-l,,

B. RESPONSIBILITIES B<<l C. 1. LIQUID EFFLUENTS SAMPLING C-l AND ANALYSIS PROGRAM

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

2. GASEOUS WASTE TREATMENT E. RADIOLOGICAL ENVIRONMENTAL MONITORING

1. SAMPLING AND ANALYSIS E-l

2. LAND USE CENSUS E-3

3. INTERLABORATORY'OMPARISON E-5 PROGRAM F. REPORT CONTENT 1.. ANNUAL RADIOLOGICAL F-1 ENVIRONMENTAL OPERATING REPORT

2. SEMIANNUAL RADIOACTIVE F-2 EFFIUENT RELEASE REPORT

3. SPECIAL REPORTS (RADIOLOGICAL F-3 ENVIRONMENTAL MONITORING) 600(207)

RETS Manual Revision 13 Page 7 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).

R 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 information required to be submitted to the NRC in both the Annual Radiological Environmental Operating Report and the Semiannual Radioactive Effluent Release Report.

A-1 600(207)

0

'I RETS Manual Revisi'on 13 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-1 600(207)

RETS Manual Revision 13 Page 9 C. LI UID EFFLUENT SAMPLING AND ANALYSES PROGRAM C.l Radioactive liquid ~aste 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 600(207)

RETS Hanual Revision 13 Page l0 TABLE C-I RADIOACTIVE LI UID HASTE SAHPLING AND ANALYSIS PROGRAH Y H S GM CAPABILITY LIQUID RELEASE SAHPLING HINIHUH ANALYSI S TYPE Of ACTIVlTY HNER LIHIT Of DETECTION TYPE FRE ENCY FRE ENCY ANALYSIS (LLO)

Batch Haste Each Batch Each Batch Prior Principal Gamma 5E-7'I3>

Releases<1> to Release Emi tters<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-2 600(207)

RETS Manual Revision 13 Page 11 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. k (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 (-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 disint'egration),

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

2.22 x 10 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 1Lp 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.

C-3 600(207)

RETS Manual Revision 13 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, Csl34, Cel41, Cel44, 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 cl E-6.

(5) Gamma Emitters Only.

600(207)

RETS Manual Revision, 13 Page 13 C.2 I.I 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 tht 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 o! 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 0he liquid radwaste treatment systea 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 radwaate, system shall be used to reduce the radioactive materials in liquid ~astes 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-lb, 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 yubmit the Special Report pursuant to Section 6.7.2 of the Technical Specifications.

C-5 600(207)

RETS Manual Revision. 13 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.

600(207)

e RETS Manual Revision 13 Page 15 TABLE D-l RADIOACTIVE GASEOUS WASTE SAHPLING AND ANALYSIS PROGRAM SYSTEM DESIGN CAPABILITY GASEOUS RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF DETECTION TYPE FRE ENCY FRE UENCY ANALYSIS i /ml)

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

Purge Purge Grab Sample Emitters(3)

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

Emitters(3)

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

a. Reactor/

Turbine

b. Turbine Exhaust c~ Radwaste C. Al 1 Release Continuous Charcoal Sample I-131 1E-12(2)

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

Continuous Composite Particulate Gross Alpha 1E-11 Sampler Sample Monthly Continuous Compos te Particulate Sr-89, Sr-90 lE-11 Sampler Sample Quarterly D-2

RETS Manual Revision 13 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 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 Lit should be used in the calculation.

it should be recognized that the IIh is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a ~osterior (after the fact) limit for a particuiar measurement.

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

600(207)

RETS Manual Revision .13 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.

600(207)

RETS Manual Revision 13 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.

600(207)

RETS Manual Revision 13 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-l 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'hat 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) + ~Canc(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-1 600(207)

RETS Manual Revision 13 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-l 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 1.0eC 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 11D 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-2 600(207)

RETS Manual Revision 13 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 wi.thin a distance of five miles. {For elevated releases as defined in Regulatory Guide l.ill, 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 a calculated dose or dose commitment greater than the maximum value 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 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. 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 si,te boundary in the direction section with the highest D/g in lieu of the garden census.

E-3 600(207)

RETS Manual Revision 13 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 survey information from the door-todoor, 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 l..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.

600(207)

RETS Manual Revision, 13 Page 23 E-3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison is provided to ensure that independent checks on the precision

'rogram 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-5 600(207)

RETS Hanual Revision 13 Page 24 TABLE E-1 RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH Number of Samples Exposure Pathway and Sampling and Type and Frequency

~dl 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-6 600(207)

RETS Manual Revision 13 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 Sam le Locationsa Collection Fre uenc of Anal sis

3. HATERBORNE

a. Surface 2 locations Compositeb sample collected Gamma isotopic 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 Hinimum of downstream 1 Composite> sample col 1 ectedc 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 Hinimum of 1 location At least once per 184 days. Gamma isotopic analysis of each sample.

d. Ground" aSample locations are shown in the ODCH.

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

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

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-7 600(207)

e RETS Hanual Revision 13 Page 26 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sam le ti Col)ection Fre uenc of Anal sis

4. INGESTION

a. Hi lk 3 locations At least once per )5 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 analysts least once per )84 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 (primari)y broad )eaf vegetation) is not required un)ess milk sampling is not performed.

600(207)

RETS Manual Revision 13 Page 27 TABLE E-2 MAXIMUM VALUES FOR THE LOWER LIHITS OF DETECTION (LLD)a c

~

A rborne Particulate Water or Gas Fish Mi lk Food Products Sediment Analysis (pCi/1) (pCi/m3) (pCi/kg, wet) (pCi/1) (pCi/kg, set) (pCi/kg, dry) gross beta lxl0-2 N.A. N.A. N.A. N.A.

H-3 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.

Zr-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 15 5x102 130 15 60 150 6 x 10-2 150 18 80 180 Cs-137 18 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-9 600(207)

RETS Nanual Revision 13 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 (<<Mt)

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),

U 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'or 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).

itshould be recognized that the 1bp 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-10 600(207)

RETS Manual Revision l3 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-ll 600(207)

RETS Hanual Revision 13 Page 30 TABLE E-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONHENTAL SAHPLES Reporting Levels Hater Airborne Particulate Fish Hi lk Food Products A~nal sls ~(C1/ l > II ( Ci/K wet) ~(Ci /l l ( 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.As 1 x 104 N.A. N.A.

Co-58 1 x103 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 x102 N.A. 2 x 102 N.A. N.A.

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

I-131 0.9 N.A. 1 x 102 Cs-134 30 10 1 x103 60 1 x 103 Cs-137 50 20 2 x103 70 2 x 103 Ba-La-140 2 x102 N.A. N.A. 3 x 102 N.A.

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

E-12 600(207)

RETS Manual Revision 13 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 0vidence 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 radio'logical 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.

600(207)

0 RETS Manual Revision 13 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.

'L 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-2 600(207)

RETS Manual Revision 13 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-3 600(207)

RETS Manual Revision 13 Page 34 RETS MANUAL Section III OFFSITE DOSE CALCULATION MANUAL ODCM 600(207)

RETS Manual Revision 13 Page 35 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 1 of 10)

Section page INTRODUCTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ o ~ o ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ 4c 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ..o.oooo~ o ~ ~ ~ 48 1/2oO APPLICABILITY ..o..o. ~ oooo o os .o oo. oooo'o. .. 48 1/2.1 INSTRUMENTATION ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ . ~ ~ ~ o .. 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 . ~ . .. . .. . .. . . .. ... . ..o... .. ~ 60 1/2.2.1 LIQUID EFFLUENTS . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ . ~ ~ 60 1/2.2.1.1 CONCENTRATION ...............o......... .......... ....... ~ ~ ~ 60 1/2.2.1.2 DOSE ............. .. .... ...... ..... .. . .

~ ~ ~ c4 r.

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-I IVES 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 ~... ~........... ~ ~ o o ~ o ~ ~ ~ 73 1/2.3.1 MONITORING PROGRAM .. . ~ ~ ~ ~ . . ~ . ~ .. ~ . ~ .. ~ . ~ .. ~ . ~ ~ ... ~ ~ ~ ~ ~ ~ ~ 73 1/2.3.2 LAND USE CENSUS ..oo...oo......oo . ". . .o o......o. . " .o . 81 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ...... .. ~ ~ ~ . ~ ~ . ~ ~ .~ .... .. ~ 83 600(207)

RETS Manual Revision '13 Page 36 Brogans Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 2 of 10)

Section page BASKS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 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 ~ ... ~ . .. . . o..... .................... 85 1 /2.2.1.2 DOSE .... ...... .ooo .... ...o................. .......... ~ 86 1/2.2.1.3 LIQUID WASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ .. ~ ~... 86 1

/2.2.2.1 DOSE RATE ......... --....... ---.....-....-. ..... ....... ~ 87 1/2.2.2.2 DOSE NOBLE GASES - .... .- . . .. ... ... .. ~ ~ . .... 88 1/2.2.2.3 DOSF I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM ~ ~ .~ ~ .. ... ... ...

~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ... ... ... ~ 89 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 90 1 /2.2.3 TOTAL DOSE .o............. ...o .........o........o.. ...... ~ ~ 90 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING... ~ ~................. 90 os 1/2.3.1 MONITORING PROGRAM . ~ ....o ..o. ~ ~ . .. . ~ . . ~ o... o. .. ~ o. 90 1/2o3 2 ~ LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 91 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ........ ~................. 91 3.0 DEFINITIONS ... . . ~ . . ~ . ..o. . ~ 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 . .. . .... .... . ~ ~ . ... ... .... ..

~ ~ ~ ~ ~ ~ 94 3.0.G. PURGE PURGING . o.. ~ ~ ~ . .. . .. .

~ ~ ~ ~ ~ ~ ~ ... .... . ~ ~ .. .~ 94 600(207)

RETS Manual Revision 13 Page 37 Browns Ferry Nuclear Plant Of f site Dose Calculation Manual TABLE OF CONTENTS (Page 3 of 10)

Section page 3.0.H. RATED POWER ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 3.0.I. SITE BOUNDARY . . ... . . .. . . . .... .... . .. . . 94 3 ~0 oJ ~ SOURCE CHECK ~ o ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o o o o ~ o ~ ~ ~ 94 3oO.K. UNRESTRICTED AREA o ~ ~ ooo o ~ oooo o oooo ooo ~ ~ oo o 95 3.0.L. VENTING ~ -~~~~~~~~~~~~o~~~~~~~ - ~ ~ ~ ~ - ~ ~ -~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ 95 4 ~ 0 (NOT USED) ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ 98 5 0 ADMINISTRATIVE CONTROLS . .. . . ... ........... ..o. ..... 99 5.1 ANNUAL RADIOLOGICAL ENVlRONMENTAL OPERATING REPORT . ~ ............ 100 5.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT . ................

~ 100 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES . .... .........o.......

~ ~ ~ 101

'0 5 o4 SPECIAL REPORTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o 101 01 6.0 LIQUID EFFLUENTS .~. ~ ~ . ~ ~ - .. ~ - . .-. ~ .... .. ... ..... ..

~ ~ ~ 102 RELEASE POINTS ...... o. . .. ~ . ......... .-......... .. ............ ~ 103 6 1 LIQUID RELEASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1A4 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 ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 106 6.2.1 Radwaste Discharge Monitor .................................... 106 6.2.2 Raw Cooling Water and Residual Heat Removal Service Water Monitors ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . .... 107 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION ....... .... ........

~ ~ 108 6.3.1 Monthly Analysis ................................... ~ ~ ~ o ~ ~ ~ o ~ ~ ~ 108 6.3.1.1 Water Ingestion .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 109 600(207)

~

Section 6.3.1.2 6.3.1.3 6.3.1.4 6.5 6.6 Fash Ingestion DOSE PROJECTIONS DOSE CALCULATIOS 6.6. 1 Water Ingestion 6..6.2 Fash Ingestion

~ ~

os Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS TREATMENT SYSTEM

~

(Page 4 FOR REPORTING PURPOSES

.~

of 10)

Recreation .. .. ".-....... . .. .-.. ........ .... -......-

Monthly Sugary ....-..-."-----.-- .- ..-.. - ....".......

6.4 LIQUID RADWASTE .. ~ .~~ ~ ~

.... .... ........ ........o..

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

~ ~ ~ ~

RETS o ~ ~ ~ ~ o

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

Manual Revision.13 Page 38 page 110 111 112 113 114 115 115 116 6.6.3 Shoreline Recreation . ... ..

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

~ ~ .............. 116 6.6.4 Total Maximum Individual Dose ................................. 117 6..6.5 Population Doses ..........o.. ....................... ........

I o

~ 118 6.7 LIQUID DOSE FACTOR EQUATIONS' . ..... . . . .. ...o ..........

~ ~ ~ ~ ~ 120 6.7.1 Water Ingestion Dose Factors ~ ~ ~ ~ o ~ ~ ~ ~ ~ 1 20 6.7.2 Fish Ingestion Dose Factors ~ ~ ~ oo ~ ~ ~ ~ o 120 6.7.3 Shoreline Recreation Dose Factors ............................. 120 7.0 GASEOUS EFFLUENTS oo.......oooo'....o.ooo ooooo.oo..oooo'...oooo

~ 140 RELEASE POINTS DESCRIPTION . ....... ...~.. .. .-. .... . ....- . ... 141 7.1 RELEASE RATE LIMIT METHODOLOGY ~ ... ....... ~ .~ ..... ....

~ ~ ~ .". ~ ... 142 7.2 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ~ .................. 147 7.2.1 Alarm/Trip Setpoints .......................................... 147 7.2.2 Allowable Values ............. ................................ 147 7.3 GASEOUS EFFLUENTS - DOSE RATES . ..... ...-...

~ ~ ~ ~ ................. 149 7.3.1 Noble Gas Dose Rates .........................................'. 149 600(207)

RETS Manual Revision .13 Page 39 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 5 of 10)

Section page 7.3.2 I-131, I-133, Tritium and all Radionuclides in Particulate Form with Half-lives of Greater than 8 days-Organ Dose Rate ....... .-.. .-.--- " . . ..---.... ........... 150 7.4 DOSE NOBLE GASES .. .. .. . . . .... e.. .... .... . . .. ~ 151 7.4.1 Monthly Noble Gas Dose .-.-.. ....---.--. .-..-.... ..... ..... 151 7.4.1.1 Monthly Conservative Model Gamma Air Dose ................. 151 7.4.1.2 Monthly Conservative Model Beta Air Dose .................. 152 7.4.1.3 Cumulative Dose Noble Gas ................................. 152 7.4.1.4 Comparison to Laments .... .. ....... ........................

~ ~ ~ 152 7.5 CUMULATIVE DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS ........ ~ .. 153 7.5.1 Monthly Conservative Model Infant Thyroid Dose from Milk Ingestion .................................................... 154 7.5-2 Monthly Conservative Model Child Bone Dose from Vegetable Ingestxon .....................................o.............. 155 7.5.3 Monthly Conservative Model Teen Gastrointestinal Tract (GIT)

Dose from Vegetable Ingestion ................................ 156 7.5.4 Cumulative Doses .......... ...................................

~ 157 7.5.5 Total Monthly Dose - Comparison to Limits ..................... 157 7o6 GASEOUS RADWASTE TREATMENT ..oo...oo.-oe.....o..oe ~ ...e.eo...o.... 158 7.6.1 Dose Progectxons .............................................. 158 7.6.2 System Descrxptxon .... .... ............. ................... 158 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES .. ..... ..

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

~ 159 7.7.1 Noble Gas Dose ....-........................................... 159 7.7.1.1 Gamma Dose to Air ....."...................................... 160 7.7.1.2 Beta Dose to Axr ............................................ 160 600(207)

RETS Manual Revision 13 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 ..... 161 7.7.3 Population Doses ........ .. ......... ........................ 163 7.7.4 Reporting of Doses .............. . .. ........................ 164 7-8 GASEOUS DOSE FACTOR E(UATIONS .................... ...... .... .. 165 7.8.1 Pasture Grass-CowGoatMilk Ingestion Dose Factors ............ 165 7.8.2 Stored Feed-Cow/Goat-Milk Ingestion Dose Factors .............. 166 7.8.3 Pasture Grass-Beef Ingestion Dose Factors ..................... 167 7.8.4 Stored Feed-Beef Ingestion Dose Factors ....................... 168 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors .................. 169 7.8.6 Stored Vegetable Ingestion Dose Factors ....................... 170 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor ....... .......~ 17l 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor ................. 172 7.8.9 Tritium-Pasture Grass-Beef Dose Factor ............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 173 7.8.10 Tritium-Stored Feed-Beef Dose Factor .............. ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ 174 7.8.11 Tritium-Fresh I.eafy Vegetable Dose Factor .................... 175 7.8.12 Tritium-Stored Vegetables Dose Factor .................;...... 176 7.8.13 Inhalation Dose Factors ...- ...; ...................... 177 7.8.14 Ground Plane Dose Factors .................................... 177 7.9 DISPERSION METHODOLOGY ... ..- ............ ... ..... ..... .

~ ~ ~ ~ 178 7.9.1 Annual Average Air Concentration .............................. 179 7.9.2 Relative Concentration ......................................... 180 7.9.3 Relative Dxspersion ... . " ... " -.. .. " ...................... 180 7.9.4 Effective Release Height ...................................... 181 600(207)

RETS Manual Revision 13 Page 41 BroNns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 7 of 10)

Section page 8..0 TOTAL DOSE . .. ~ . ~ ~ o. ~ ~ ~ . . ~ . . .. . .. . ... ... . .. .. 228 9.0 ENVIRONMENTAL NNITORING PROGRAM ....................... ~....... 230 9.1 MONITORING PROGRAM DESCRIPTION . . .. ... ... . . ....... .... .. 231 9.2 DETECTION CAPABILITIES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ .. ~..... 231 Lieu 9.~ 3 Ltmu USE CaaSUS ~ ~ ~ ~ ~ . ~ ~ ~ . ~ o ~ ~ ~ o ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ .. ~ ~ . ~ ~ ~ ~ ~ ~ 231 9.4 INTERLABORATORT CNPARISON PROGRAM ~ ~ . ~ ~ .. ~ ...................... 231 600(207)

RETS Manual Revision 13 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 REQUIRHSTS .. .... ..

~ ......... ........ 53 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . 56 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONiTORING INSTRUMENTATION SURVEILLANCE REQUIREMFWXS . ~ ~ ~ ~ ~ . ~ .....- ~ ~ . ~ ~ .. .....

~ ~ 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 ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 67 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ oe ~ eoe ~ ~ oo ~ ~ ~ ~ ~ oo ~ ~ e ~ ~~ oe ~ o ~ oo ~ ~ ~ ~ o ~ ~ 75 Table 2 3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 78 Table 2 3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ . ~ ~ ~ 80 Table 3.1 FREQUENCY NOTATION ..... .... ~ ~ ~ ~ ~ ~ ~ . ~ ~ .. ..

~ ~ ............... 96 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS .... ....... ... ~ ~ ~ .. 121 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA ....... 122 Table 6.3 DOSE CALCULATION FACTORS ...... .... ......................

~ 125 Table 6.4 INGESTION DOSE FACTORS .. . . .:.. ..... .. ... .. .. '.

~ ~ ~ 127 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH ............... 135 Table 6 6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND. ~ 136 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA ~ .. ~ ~ . ~ ~ ... . ~ ~ ... 182 Table 7.2 UNIT AT BFN ......"............".... "..........

EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE 183 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ e ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ oo' ~ ~ ~ 184 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES ................ 206 600(207)

e RETS Manual Revision 13 Page 43 Bzowns 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 .......... 207 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT . . . .. 208 Table 7.7 INHALATION DOSE FACTORS ~ ~ . ~ .. . .. . . . . .... 209 Table 9.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ............ 232 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING- PROGRAM SAMPLING LOCATIONS . . .... . ....... ........ .. .... .... ....

~ 237 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS ~ ~ ~ ~ . . ~ . 23S 600(207)

RETS Manual Revision 13 Page 44 Ferry Nuclear Plant 'rowns 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 . . --.. . . .-.... ..............

~ 138 Figure 6.2 LIQUID RADWASTE SYSTEM ...... ............................

~ 139 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING ............... 217 Figure 7.2 NORMAL BUILDING VENTILATION . ............

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ , 218 Figure 7.3 PLUME DEPLETION EFFECT ~ ~ .. ~ ~ ~ ~ --. ~ ~ .................. 219 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME ....... 223 Figure 7.5 RELATIVE DEPOSITION ... . .... --- . . -. .... ......... 224 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ -- ~ ~ -- ~ ~ ~ ~ - ~ ----. ~ ~ 239 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 240 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT ~ ~ ~ ~ ~ - ~ ~ . ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ 241 600(207)

RETS Manual Revision 13 Page 45 SECTION 1.0 AND 2.0 CONTROLS AND SURVEILLANCE RE UIREMENTS 600(207)

RETS Manual Revision 13 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.

600(207)

RETS Manual Revision.13 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 result in a small fraction of the annual average concentration limits specified in 10 CFR Part 20, Appendix B, Table II.

I I

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 materials released to the environment. Reports on the to'adioactive 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 an'd any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

600(207)

RETS Manual Revis i'on,13 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.

600(207)

RETS Manual Revision 13 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 Surveillance 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.

600(207)

RETS Manual Revision .13 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'he 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.

600(207)

RETS Manual Revision 13 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-90-1330 -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.

600(207)

RETS Manual Revision 13 Page 52 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 ~t:

(1) liquid waste activity and flowrate shall be continuously monitored and recorded durini release and shall be set to alarm and automatically close the waite dilcharge 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 requirements, 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.

ACTION 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 LLD1 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 radioactivt.ty with an LLD1 of lE-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.

600(207)

RETS Manual Revision 13 Page 53 Table 2.1-1 (Page 1 of 2)

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

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

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

c. Raw Cooling Water D4 R5 Q2 Monitor (RM-90-132)

d. Liquid Radwaste Effluent D4 N/A Flow Rate (77-60 loop) 600(207)

RETS Manual Revision 13 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 25K of the interval given.

1 The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the follo~ing 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.

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.

b. Instrument indicates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

madel'functional test shall 3 This 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 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.

600(207)

RETS Manual Revision 13 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. Alara/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: Aa ahcwn 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.

600(207)

RETS Manual ~

Revision 13 Page 56 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels/

Instrument

1. Stack (RM-90-147B 5 148B)

a. Noble Gas Monitor A/C

b. Iodine Cartridge s/c

c. Particulate Filter s/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 s/c

d. Sampler Flowmeter D

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

a. Noble Gas Monitor A/C

b. Iodine Sampler s/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) 600(207)

RETS Manual Revision 13 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 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.

600(207)

RETS Manual Revision,13 Page 58 Table 2.1-2 (Page 1 oE 2)

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

1. STACK

a. Noble Gas Monitor4 D M Rl Q2

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

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

d. Sampler Flow Abnormal D N/A R Q

e. Stack Flowmeter D N/A R Q

2. REACTOR/TURBINE BUILDING VENT

a. Noble Gas Monitor D M Rl Q2

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

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

b. Sampler Flowmeter D N/A R Q

3. TURBINE BUILDING EXHAUST

a. Noble Gas Monitor D M Rl Q2

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

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

b. Sampler Flowmeter D N/A R Q

4. RADWASTE BUILDING VENT

a. Noble Gas Monitor5 D M Rl Q2

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

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

b. Sampler Flowmeter D N/A R

5. OFF GAS POST TREATMENT

a. Noble Gas Activity Monitor

b. Sample Flow Abnormal D

D N/A'l M

(}2 600(207)

RETS Manual Revision 13 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 25X 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.

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).

3 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) 600(207)

RETS Nanual Revision 13 Page 60 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 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 UIRENENTS 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. A 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.

600(207)

RETS Manual Revision 13 Page 61 2.2-1 (Page 1 of 3)

'able 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 5xl0 " 3 Releasesl Batch Prior to Gamma Release Emitters4 One Batch Monthly Dissolved and lx10"5 3 per Month Entrained Gases>

Monthly Monthly Tritium lx10 5 Proportional Composite2 Gross Alpha lx10 7 Quarterly Quarterly Sr-89, Sr-90 5x10-8 Proportional Composite2 Fe-55 lx10-6 600(207)

RETS Manual Revision 13 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 from 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 95'X 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 LLD =

E V 2 22E+06 Y exp (-X6t)

Where:

LLD = 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 sire (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, U, Y, and ht should be used in the calculation.

it should be recognized that the ILP is defined as an riori (before the

~a fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

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 600(207)

RETS Manual Revision .13 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 =95%

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 ( 1E-6.

5 Gamma Emitters Only-600(207)

RETS Manual Revision 13 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.

ACTION:

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.

600(207)

RETS Manual Revision 13 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 days, in accordance with ODCM Section 6.5.

600(207)

RETS Manual Revision 13 Page 66 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2 2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLLYhTS 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 mremlyr 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 icaediately 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 8/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.

0

b. For effluent streams without continuous monitoring capabi.lity, the active.ty 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.

600(207)

RETS Manual Revisi:on 13 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 lxl0 Gamma Emitters3

2. Building Grab Sample Monthly H-3 lxlO Ventilation

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radwaste C.All Release Continuous Charcoal I-131 lxlo Points Sampler Sample Listed in Weekly4 B. Above Continuous Particulate Principal 1xlO Sampler Sample Gamma Weekly4 Emitters3 I-131 lxlO Continuous Composite Gross Alpha lx10 Sampler Particulate Sample Monthly Continuous Composite Sr-89, Sr-90 lxlO Sampler Particulate Sample

'Quarterly 600(207)

RETS. Manual Revision 13 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 5'X 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 2.22K+06 Y exp (-X 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,

= the radioactive decay constant for the particular radionuclide (s 1) ~

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 It should be recognized that the Zip 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.

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.

600(207)

RETS Manual Revision 13 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 CASES 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.'.

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: ht all times.

ACTION:

If the calculated air dose exceeds the limits specified above, prepare and submit a specia1 report pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIRENEhTS 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.

600(207)

RETS Manual Revision 13 Page 70 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 1.2.2.3 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.

APPLICABILITY: 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.

600(207)

RETS Manual Revision 13 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 25'X 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 opera'tion above 25'X 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.

600(207)

RETS Manual Revision.13 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.

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.

600(207)

RETS Manual Revision 13 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(l) +

concentration(2)

+ . . . > 1.0 limit level(1) limi,t level(2)

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.

600(207)

RETS 'Manual Revision 13.

Page 74 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2. 3 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 3O days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Control 1.3.l.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 (begore the fact) limit representing the capability og a meascrement system and not as a posteriori (after the fact) limit Eor 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 l.b.

600(207)

RETS- Manual Revision 13 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

~Sam le Locationsa Collection Fre uenc of Anal sis

l. AIRBORNE Radioiodine/ Minimum of 5 Continuous operation Radioiodine canister:

Particulates locat:ions 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 locat.ion) 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.

600(207)

RETS Manual Revision 13 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 Locations 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.

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

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

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

River 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.

600(207)

0 RETS Manual Revision 13 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 S~am le Locationsa Collection Fre uenc of Anal sis

4. INGESTION

a. Milk 3 locations At least 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 t imes ~

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.

600(207)

RETS'anual Revision 13 Page 78 Table 2.3-2 (1 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)a>c FOR ENVIRONMENTAL SAMPLES Airborne Food Particulate Fish Products Sediment Water or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg, A~nal sis ~Ci/L) ~Ci/m3) wst) ~Ci/L ~sat ~dr )

gross beta 4 0.01 N/A N/A N/A N/A 8-3 2000 N/A N/A N/A N/A N/A Mn-54 N/A 130 N/A N/A N/A Fe-59 30 N/A 260 '/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 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 18 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 600(207)

RETS Manual Revision .13 Page 79 Table 2.3-2 (2 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES TABLE NOTATION a 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:

4e66 Sb E V 2.22 Y exp(-Xht)

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).

= the radioactive decay constant for the particular radionuclide, seconds 1 and ht = 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 ht should be used in the calculation.

It should be recognised that the Llh is defined as an riori (before the

~a 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.

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

600(207)

RETS Manual Revision 13 Page 80 Table 2.3-3 RFPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or gases Fish Milk Food Products

~Ana> sis ~Ci/L ~Ci/L) Ci/K wet H-3 2 104(a) N.A N.A N.A. N A.

Mn-54 1 x 103 N.A. 3x 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 10> N.A. N.A. N.A. N.A.

I-131 0.9 N.A. 3 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% 102 N.A.

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

600(207)

RETS Manual Revision 13 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 gardenl 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 all milk animals and gardens of greater than 500 square feet 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/Q 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 calcul'ated dose or dose commi'tment(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) 600(207)

RETS Manual Revision 13 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:

l. 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.

2. 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.

6OO(2OZ)

RETS Manual Revision 13 Page 83 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL EhVIRONMENTAL 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 Coamisaion.

APPLICABILITY: At ~ ' 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 UIRENENTS 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 checlr. program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

600(207)

RETS Manual Revision .13 Page 84 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS SURVEILLANCE REgUIREKBVS 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.

600(207)

RETS Manual Revision 13 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 durSng actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with guidance provided Sn 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 requS.red 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 600(207)

RETS Manual Revision 13 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'ection II.A of Appendix I.

This action 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 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 S0.36a, 600(207)

RETS Manual Revision 13 Page 87 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.3 LI UID PASTE 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 vill be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated vith 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 vithin 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 specified 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. P The action for this requirement requires that appropriate corrective action(s) be taken to reduce gaseous effluent releases if the limits are exceeded.

600(207)

RETS Manual Revision 13 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 calculati,onal 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 1.111.

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.

600(207)

RETS Manual Revision 13 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 flexibilityand 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 She requirements in Section 'III.A of Appendix I that conformance with the guides of Appendix I be shown by calcu)ational 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 radionucl9des, 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.

600{207)

RETS 'Manual Revision 13 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 vere 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 vith the above requirements.'/2.2.3 TOTAL DOSE This requirement is provided to meet the dose limitations of 40 CFR 190. This requirement requires the preparation and 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, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC vill 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 vithin 40 CFR 190 limits. 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 radiim 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'his 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 600(207)

RETS Manual Revision 13 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 environmental exposure pathways. 'he 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.

600(207)

S RETS Manual ~

Revision 13 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 FUNCTIONAI, 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 I-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.

600(207)

RETS Manual ~

Revision 13 Page 94 DEFINITIONS This category shall include non-employees of the licensee who are permitted to uae 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, aa part of their formal job function, occasionally enter RESTRICTED AREAS.

3.0.F OPERABLE - OFKRABILITY 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 PURGIMG PURGE or PURGINC ia 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 MVt.

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.

600(207)

RETS Manual Revision 13 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).

3.0.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 ov gas is not provided or required. Vent, used in system names, does not imply a VENTING process.

600(207)

RETS Manual Revision 13 Page 96 Table 3.1 FRE UENCY NOTATION Notation ~Pre uenc At least once per 12 hours.

At least once per 24 hours.

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 600(207)

RETS Manual Revision 13 Page 97 Figure 3.1 LAND SITE BOUNDARY Pg

+~

Cp r' r 0

~y BAOWNS PEPNy NUCLEhR PLhNT o

P~

+~

p>~

$ $ vJ Land Site Boundary (for

'gaseous effluents)

\

~ 0 ~ 0 ~ ~ ~ 11 ~ 0 ~ 0 Unrestricted brea Boundary (for liquid effluents) 600(207)

RETS Manual Revision 13 Page 99 SECTION 5.0 ADMINISTRATIVE CONTROLS 600(207)

RETS'anual Revision 13 Page 100

'.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,'-'evision 1, June 1974, with data summarized on a quarterly basis followix1g the format of Appends 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 1.

600(207)

RETS Manual Revision 13 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 BFM TS 6.12, changes to the ODCM:

l. 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 indi. cate 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.

600(207)

RETS Manual Revisi'on .13 Page 103 6.0 LI UID EFFLUENTS RELEASE POINTS The minimum flows available for dilution of radwaste are shown below:

~ - open 2 pumps 8 200,000 gpm/pump 4

Radwaste Discharge

~ closed/helper 4

- 50,000 gpm Conduit 600(207)

RETS Manual Revision 13 Page 104 6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis/MPC Sum of the Ratios Prior to release, a grab sample will be analyzed to determine the concentration (Ci) of each gamma emitting radionuclide i in the radwaste tank. The following equation is used to calculate MPC fractions (Mi).

Ci Mi MPCi

~here:

Mi = MPC fraction of radionuclide i.

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

as specified in Control 1.2.1.1, pCi/ml.

MPCi =

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

R~ 7 Mi 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.

600(207)

RETS Manual Revision.13 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 vere not exceeded.

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

600(207)

RETS Manual Revision 13 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 Radwaste Dischar e Monitor The allovable value for the radvaste discharge monitor {RM-90-130) shown in Figures 6.1 and 6 2, will be established using the methodology belov.

The alarm/trip allowable value vill be set such that Equation 6.3 is satisfied. The trip allovable 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 50K of the trip allowable value.

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

f* WFi i

i MPC.

where:

A maximum batch activity concentration, pCi/ml.

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

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

F dilution water flov rate, gpm.

f maximum discharge flov rate, gpm.

1 The maximum activity concentration is based on a selected isotopic mixture so that an allovable value can be calculated. The selected isotopic mixture vill 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 concentration may be higher than the calculated maximum activity concentration.

600(207)

RETS Manual Revision 13 Page 107 monitor isolation allowable value, in cps, for releases is calculated

'he using the following equation:

Monitor Isolation Allowable Value = (A

Z WFi*E.) + B where:

A maximum batch activity concentration as calculated above, yCi/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 c 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 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.

600(207)

RETS Manual Revision 13 Page 108

'.3 CUMULATIVE LI UID EFFLUENT DOSE CALCULATION 6.3.1 Monthl Anal sis Principal radionuclides vill be used to conservatively estimate the monthly contribution to the cumulative dose. If the projected dose calculated by this monthly method exceeds the monthly fraction of the annual limits in Control 1.2.1.2, then the methodology in Section 6.6 will be implemented.

The 20 nuclides listed below, based on operational source terms, contribute more than 95 percent of the total estimated dose to the total body and the most critical organ for both the water and fish ingestion pathways. The organs considered for both water ingestion and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver.

H-3 Fe-59 Sr-90 I-131 Na-24 Co-58 Zr/Nb-95 I-133 Cr-51 Co-60 Mo/Tc-99m Cs-134 Mn-54 En&5 Ag-110m C5-136 Fe-55 Sr-89 Sb-124 C6-137 A conservative calculation of the monthly dose will be done according to the following procedure. First, the monthly operating report containing the release data vill be obtained and the activities reported (if any) for each of the above 20 radionuclides will be noted. This information will then be used in the following calculations.

600(207)

RETS Manual Revision 13 Page 109 6.3.1.1 Water In estion The dose to an individual from ingestion of water is described by the following equation.

20 Djk ~ ~~10 p

i=1 (DFL) ijk Iik (6.4) where:

Djk = dose for the jth organ and the kth age group from the 20 radionuclides, mrem.

= the organ of interest (bone, GIT, thyroid, liver or total body) ~

k = the age group being considered, child or adult.

1012 conversion factor, pCi/Ci.

0. 95 = conservative correction factor, considering only 20 radionuclides.

DFLijk = ingestion dose commitment factor for the ith radionuclide for the jth organ for the kth age group, mrem/pCi (Table 6.4)

Iik = monthly activity ingested of the ith radionuclide by the kth age group, Ci.

The activity ingested due to drinking water, Iik, is described by:

103 Ai Uwa (1/12)

I k (6.5) where:

10 = conversion factor, ml/L.

Ai = activity released of ith radionuclide during the month, Ci.

Uwa = maximum individual water consumption rate corresponding to the kth age group (Table 6.3), L/yr.

1/12 = conversion factor, yr/month.

F = average river flow rate for the month (cubic feet per second) d = fraction of river flow available for dilution (0.30) 7.34E+10 = conversion from cubic feet per second to millili,ters per month Inserting this for Iik in equation 6.4, the dose equation for water ingestion then becomes:

20 3.98E+03 Uwa DFLijk Ai i=1 600(207)

RETS Manual Revision 13 Page 110 The dose to an individual from the consumption of fish is described by Fquation 6.4. In this case, the activity ingested of the ith radionuclide due to eating fish (Iik) is described 103 Ai Bi Ufa (1/12)

~ + by'here:

103 = conversion factor, g/kg.

Ai = activity released of the ith radionuclide during the month, Ci B i = bioaccumulation factor of ith radionuclide, pCi/g per pCi/ml.

(Table 6.5)

Uffa = amount of fish eaten yearly by the kth age group (Table 6.3),

kg/yr.

1/12 = conversion factor, yr/month.

F = average river flow rate for the month, cubic feet per second.

d = fraction of river flow available for dilution, 0.30.

7.34E+10 = conversion from cubic feet per second to milliliters per month.

Inserting this for Iik in equation 6.4, the dose equation for fish ingestion then becomes:

3.98E+03 Djk Ai Bi Ufa DFLijk i=l 600(207)

RETS Manual Revision Page ill 13 Recreation '.3.1.3 For the recreation dose calculation, the total dose is estimated based on a calculation of the shoreline dose for Co-58, Co-60, Cs-134, and Cs-137. The shoreline dose due to these four nuclides is expected to contribute over 95 percent of the total recreation dose. The total body and maximum organ dose to an individual via the shoreline recreation pathway are assumed to be equal. The recreation dose is described by the following equation:

4 1012 Dz = g 42 Dpi Ki (6.9) i=1 where:

Dr = recreation dose from plant releases, mrem.

1012 conversion factor, pCi/Ci.

0.95 ~ conservative correction factor for considering only 4 radionuclides.

42 ~ assumed monthly exposure time for maximum individual, hours DFGi = dose commitment factor for standing on contaminated ground for the ith radionuclide, mrem/hr per pCi/m2 (Table 6.6).

concentration of ith radionuclide in shoreline sediment, Ci/m2, as described by the following equation (based on equation A-5 in Regulatory Guide 1.109).

= 10 6.94E-04 100 RHLi Wfl~xp(-Xitb] Ci (6.10)

~here:

103 ~ conversion factor, ml/L.

6.94E-04 = conversion factor, d/min.

RHLi ~ radiological half-life of the ith radioisotope, minutes (Table 1.11).

100 = conversion factor, L/(N2d) (defined in Regulatory Guide 1.109).

W = shoreline width factor (Table 6.3).

XX = decay constant of .the ith radionuclide, sec (Table 1.11).

tb = buildup time in sediment, seconds (Table 6.3)

C' = concentration of ith radionuclide in the Tennessee River, Ci/ml.

= Ai/(F d 7 '4E+10) where:

Ai = activity released of ith radionuclide during the month, Ci/month.

F = average river flow for the month, cfs.

d = fraction of river flow available for dilution, 0.30.

7.34E+10 = conversion from cfs to ml/month.

600(207)

RETS Manual Revision 13 Page 112 The recreation dose equation then becomes:

Dr = ~ 1 (29.8 Al + 1690 A2 + 539 A3 + 812 A4) (6.11) where:

Al, A2, A3, A4, = the activities of Co-58, Co-60, Cs-134, and Cs-137, respectively, pCi.

6.3. 1. 4 Mon thl Summa To obtain the total monthly dose to the total body, sum the total body dose from water ingestion, the total body dose from fish ingestion, and the recreation dose. This value will be compared to the limit for total body dose. To obtain the total monthly dose to the maximum organ, sum the maximum organ dose from water ingestion, the maximum organ dose from fish ingestion, and the recreation dose. This value will be compared to the limit for maximum organ dose. Calendar quarter and calendar year doses are first estimated by summing the doses calculated for each month in that year. However, if the annual doses determined in this manner exceed or approach the specification limits, doses calculated for previous quarters with the methodology of ODCM Section 6.6 will be used instead of those quarterly doses estimated by summing monthly results. An annual check will be made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in ODCM Section 6.6. If less than 95 percent of the dose has been estimated, either a new list of principal isotopes will be prepared or a new correction factor will be used. The latter option will not be used if less than 90 percent of the total dose is predicted..

600(207)

RETS Manual Revision 13 Page 113'.4 LI UID RADWASTE 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.

600(207)

RETS Manual Revision 13 Page 114'.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.

600(207)

e RETS Manual Revision,13 Page 115 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 (for receptors downstream (6.13b) 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) identified within a 50 mile radius downstream of BFN (Table 6.1). Water ingestion doses are calculated for the total body and each internal organ as described below:

Dorg = 10 9.8E&9 AMit 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.

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

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

= dilution factor, as described above, cfs l.

"- radiological decay constant of nuclide i, seconds (Table 6.3).

= 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.

600(207)

RETS Manual Revision 13 Page 116

'ish 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&9 0.25 AFit Qi D exp(-8.64E+04 Xi td) (6.15) where 106 = 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 1.

= 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.

8.64K+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:

Dorg = 10 9.8E-09 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 O.l 2nd quarter 0.3 3rd quarter - 0.4 4th quarter 0.2; 600(207)

RETS Manual Revision 13 Page 117 AR t Rat = 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 the quarter, Curies.

D = dilution factor, as described above, cfs 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 the 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-600(207)

RETS Manual Revision 13 Page 118 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 thea 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 E 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.

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 co nversion factor for rem/mrem.

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 APR>>

POPFt ~ 10 3 10 3 Z r=l Z a=1 POPa TFDOSart a a 600(207)

RETS Manual Revision 13 Page 119 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

a. as described in Section 6.6.2, mrem. Calculated with age'roup td in that equation equal to travel time plus 8 days.

POP 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. Tbe average fish ingestion rates (R.G. 1.109 Table E-4) are!

Adult = 6.9 Child ~ 2.2 Teen c 5.2 453. 6 ~ conversion factor, g/lb.

10 3 conversion tactor, 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 1 (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.

Qi exp(-Xitr) c M DFGit 012 24 103 Dr 2.22Ell 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, days.

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

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

DFGit ~ dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m2.

1012 = 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.

2.22Ell ~ conversion factor, ml/quarter per cfs.

600(207)

RETS Manual Revision 13 Page 120 6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors DFLiat Uwa 10 10 AWit =

where:

DFLiat = 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.

10 = 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.'FLiat

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

Vfa = 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 103 106 U ARit = [1-exp(-Xi tb)]

where:

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

nuclide and organ t (total body and skin), mrem/hr per pCi/m ,

(Table 6.6).

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

M = mass density of sediment, kg/m2, (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 1, (Table 6.2).

tb ~ 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.

600(207)

RETS Manual Revision 13 Page 121 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+ TRN 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 TRM ~Po ulation Muscle Shoals, AL 259.6 10,740 Sheffield, AL 254.3 13%065 Cherokee, AL 239.2 35400

TRM = Tennessee River Mile 600{207)

RETS 'anual Revision 13 Page 122 Table 6.2 {1 of 3)

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

H-3 6 46E+06 1. 79K&9 4.80EWO 1.00E-02 1.70E-01 20E&2 C-14 3.01E+09 3.84K-12 5.50E+00 1.20E-02 1.00E-Ol 3 10E-02 Na-24 9.00E+02 1. 28K&5 5.20E02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 S.61K&7 1.10E+00 2.50E02 2.50E-01 4. 60E&2 Cr-51 3.99E+04 2. 9OK-07 2.SOE&4 2.20E-03 2 20E-03 2.40E-03 Mn-54 4.50E+05 2. 57K&8 2.90EW2 2.50E-04 2.50E&4 8.00E04 Mn-56 1.55E+02 7.45K-05 2. 90EW2 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8. 13KW9 6.60EW4 1.20E-03 1.30E-04 1 20EW2 Fe-59 6.43E+04 1. SOKW7 6.60E04 1.20E-03 1 30E-04 l. 20EW2 Co-57 3.90E+05 X. 96K&8 9.40E-03 1.00E-03 1-OOE-03 1 30E&2 Co-58 1.02E+05 l. 13K&7 9.40E-03 1.00E-03 1.00E-03 l. 30E-02

'Co-60 2.77K+06 4.17K&9 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19K-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65K-05 1-90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52K&5 1.20E-01 1.40E02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28K-08 4.00E-Ol 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.9OE-02 3.00E-02 Zn-69 5.56E+Ol 2.08E&4 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60EWl 5.00E-02 5-OOE-02 2.60E-02 Br-83 1.43E+02 8.08EW5 7.60E-Ol 5 ~ OOE-02 5.00E-02 2. 60E&2 Br-84 3.18E+Ol 3.63E-04 7-60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E>>01 5.00E-02 5.00E-02 2.60E-02 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 6.49K&4 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E&4 1.30E&1 3.00E-02 3.00E-02 3.10E-02 Sr<<89 7.28E+04 l. 59E-07 1.70E02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03K&5 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr<<92 1.63E+02 7.09E&5 1.70E-02 1.40E-03 1.40E-02 6 OOE-04 Y-90 3.85E+03 3.00E&6 2.60E&3 1.00E-05 1.00E>>05 4.60E-03 Y-91m 4.97E+Ol 2. 32EW4 2.60K-03 1.00E-05 1.00E-05 4.60E-03

'-91 8.43E+04 1. 37E&7 2.60E-03 1.00E>>05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-O3 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 l. 91EW5 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 I. 25E-07 1.70E-04 5.00E-06 5.00E-O6 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40K-02 Nb-95 5.05E+04 2. 29EW7 9.40E&3 2.50E-03 2.50E-03 2. SOE&l Nb-97 7.21E+01 1.60K&4 9.40E-03 2.50E-03 2.50E-03 2. 80E&l Mo-99 3.96Ej03 2. 92E&6 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61K+02 3. 20E-05 2.50E-01 2.50E-02 2.50E-02 4.0OE-Ol Tc-101 1.42E+01 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-Ol Ru-105 2.66E+02 4.34E-05 5.00E02 1.00E-06 1.00E-06 4.00E-Ol Ru-106 5.30E+05 2. 18E&8 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E&1 5 '0E-02 5.00E-02 1.70E-02 600(207)

RETS Manual Revision 13 Page 123 Table 6.2 (2 of 3)

RADIONUCLIDE DECAX 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&9 N/A 1.50E&3 1.50E-03 N/A Te-125m 8.35K+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&5 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2. 39EW7 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66EW4 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80K+03 6.42EW6 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50K+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 1.00E-03 Te-132 4.69E+03 46E&6 1.30E+00 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&7 2.00E&2 1.20E&2 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E&5 2.00E-02 1. 20E-02 4.30E-Ol 2.90E-03 I-133 1.25E+03 9. 24E&6. 2.00E-02 l. 20E&2 4.30E-OI 2.90E-03 I-134 5.26E+01 2. 20E&4 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E&2 1 20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E&8 1.00EW2 8.00E&3 3.00E-01 1.50E&2 Cs-136 1.90K+04 6.08E-07 1.00EW2 8.00E-03 3.00E-Ol 1.50E-02 Cs-137 1.59K+07 7.26E-10 1.00E&2 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E&4 1.00E-02 8.00E-03 3.00E-Ol 1.50E&2 Ba-139 8.31E+01 l. 39E&4 5.00E>>O3 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6.28EO7 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E&3 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07K+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 2.00E4 La-142 9.54K+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&3 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&4 1.00E-04 1.20E&3 Pr-143 1.95K+04 5 ~ 92E&7 2.50E&3 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73K+01 6. 68E-04 2.50E&3 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E&3 5.00E-06 5.00E-06 3.30E-03 M-187 1.43E+03 8.08E&6 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np<<239 3.39E+03 3.41E-06 2.50E-03 S.OOE-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E&4 N/A N/A N/A N/A Kr-83m 1.10K+02 1 ~ 05E&4 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&9 N/A N/A N/A N!A Kr-87 7.63K+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 3.16K+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39K&1 2.14E-02 N/A N/A N/A N/A Xe-131m l. 70K+04 6.79E&7 N/A N/A N/A N/A Xe-133m 3.15K+03 3. 67E-06 N/A N/A N/A N/A 600(207)

0 RETS Manual Revision 13 Page 124 Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life Biv Fmi Fmi'goat)

Ffi (minutes) (1/s) (cow) {beef)

Xe-133 7.55K+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-135 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83K+00 3.02E-03 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.

600(207)

RETS Manual Revision.13 Page 125 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) fP 1 TVA Assumption 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)

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

(15 years )

tcb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) tcsf 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days )

te 5.18E+06 seconds R. G. 1.109 (Table E-15)

(60 days) tep 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) tfm 8.64E+04 secollds SQN FSAR Section 11.3.9.1 (1 day) thc 8.64E+04 secollds NUREG/CR-1004, Table 3.40 (1 day) 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) tsv 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days )

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

Um (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) 600(207)

RETS Manual Revision 13 Page 126 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)

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

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

U~(teen) 510 L/year R. G. 1.109 (Tabl.e E-5)

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

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

Yf 1.85 kg/m2 NUREG/CR-1004 (Table 3.4) 1.18 kg/m2 NUREG/CR-1004 (Table 3.3)

Yp Ysf 0.64 kg/m2 NUREG/CR-1004 (Table 3.3)

Ysv 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables) 7.71E-07 1 NUREG/CR-1004 (Table 3.10)

Q (iodines) sec half-life)

(15.4 d Q (particulates) 5.21E-07 sec 1 NUREG/CR-1004 (Table 3.10)

(10.4 d half-life) 600(207)

RETS Manual Revision .13 Page 127 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&7 1.05EW7 1 ~ 05EW7 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E&7 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 l. 70E&6 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-O4 1.20E-05 7.46E-06 0.DOE+00 0 DOE+00 O.DOE+00 2.17E-05 Cr-51 O.DOE+00 0.DOE+00 2. 66EW9 1.59E&9 5.86E-10 3.53EW9 6.69E-07 Mn-54 O.DOE+00 4.57E&6 8. 72E-07 O.DOE+00 1.36E-06 O.DOE+00 1.40E-05 Mn-56 O.DOE+00 1.15EW7 2.04E-08 0 DOE+00 1.46E-07 O.DOE+00 3.67E-06 Fe-55 2.75E-06 1.90E&6 4.43E-07 O.DOE+00 O.DOE+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.DOE+00 0 DOE+00 2.85E-06 3.40E-05 Co-57 O.DOE+00 l. 75E&7 2.91E-07 O.DOE+00 O.DOE+00 O.DOE+00 4.44E-06 Co-58 O.DOE+00 7.45E-07 1.67E-06 O.DOE+00 0.DOE+00 O.DOE+00 1.51E-OS Co-60 O.DOE+00 2.14E-06 4.72E-06 O.DOE+00 O.DOE+00 O.DOE+00 4.02E-05 Ni-63 1.30E-04 9.DIE&6 4.36E-06 D I ODE+00 O.DOE+DO D.ODE+OD 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 O.DOE+00 O.DOE+00 O.DOE+00 1.74E-06 CL1-64 O.OOE+00 8.33E-08 3.91E&8 O.DOE+00 2.10E&7 O.DOE+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 O.DOE+00 1.03E-05 O.DOE+00 9.70E-06 Zn-69 1.03E-08 1.97E&8 1. 37EW9 O.DOE+00 1.28E-08 0.DOE+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 O.DOE+00 2.47E-07 O.DOE+00 2.49E-05 Br-82 O.DOE+00 O.OOE+00 2.26E-06 O.ODE+00 O.DOE+00 O.DOE+00 2.59E-06 Br-83 O.DOE+00 D.DOE+00 4.02E-08 O.DOE+00 O.DOE+00 O.DOE+00 5.79E-08 Br-84 O.DOE+00 O.DOE+00 5.21E-08 O.DOE+00 O.DOE+00 0.DOE+00 4.09E-13 Br-85 D.DOE+00 0.DOE+00 2.14E-09 O.DOE+00 O.DOE+00 0-DOE+00 O.DOE+00 Rb-86 O.DOE+00 2 11EW5 9 '3E-06 D.DOE+00 0.DOE+00 O.DOE+00 4.16E-06 Rb-88 0.DOE+00 6.05E-08 3 ~ 21E&8 O.DOE+00 0.DOE+00 O.DOE+00 8.36E-19 Rb-89 O.DOE+00 4.01E-08 2. 82E-08 O.DOE+00 O.DOE+00 O.DOE+00 2.33E-21 Sr-89 3.08E-04 O.DOE+00 8.84E-06 0.DOE+00 O.DOE+00 O.DOE+00 4.94E-05 Sr-90 7.58E-03 O.DOE+00 1.86E-03 O.DOE+00 O.DOE+00 O.DOE+00 2.19E-04 Sr-91 5.67E-06 O.DOE+00 2.29E-07 O.DOE+00 0.00K+00 O.DOE+00 2.70E-05 Sr-92 2.15E-06 0.DOE+00 9.30E-08 O.OOE+DD O.DOE+DO 0 DOE+00 4.26E-05 Y-90 9.62E-09 0.DOE+00 2.58E-10 O.DOE+00 O.DOE+00 O.DOE+00 1.02E-04 Y-91m 9.09E-11 O.DOE+00 3.52E-12 O.DOE+00 O.DOE+00 O.DOE+00 2.67E-10 Y-91 1.41E-07 O.DOE+00 3.77E-09 0 DOE+00 O.DOE+00 O.DOE+00 7.76E-05 Y-92 8.45E-10 0.DOE+00 2.47E-11 O.DOE+00 O.OOE+00 O.DOE+00 1.48E-05 Y-93 2.68E-09 0 DOE+00 7.40E-11 Q.DOE+00 O.DOE+00 O.DOE+00 8.50E-05 Zr-95 3.04E-08 9. 75E&9 6.60E&9 O.DOE+00 1.53E-08 O.

DOE+00'.DOE+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+00 5.12E-10 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.DOE+00 3.42E-09 O.DOE+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 O.DOE+00 1.54E-11 O.DOE+00 4.87E-08 Mo-99 O.DOE+00 4.31E-06 8.20E-07 0 DOE+00 9.76E-06 O.DOE+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 O.DOE+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 O.DOE+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 O.DOE+00 7.97E-08 O.DOE+00 7.06E-07 0.DOE+00 2.16E-05 Ru-105 1.54E-08 O.DOE+00 6.08E-09 0.DOE+00 1.99E-07 O.DOE+00 9.42E-06 RU-106 2-75E-06 0 DOE+00 3.48E-07 0.DOE+00 5.31E-06 O.DOE+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 O.DOE+00 2.91E-07 O.DOE+00 6.04E-05 600(207)

RETS Manual Revision 13 Page 128 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 5.29EWS 1.11E-06 6.79E-09 O.OOE-OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-OB 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-OB 2.38E-OB 8.15E-OS 4.48E-07 O.OOE+00 8.68E-06 Te-129m 1.15E-05 4.29E&6 1.82E-06 3.9SE-06 4.80E-05 O.OOE+00 5 79E-05 Te-129 3.14E-OS 1.18E-OS 7.65E-09 2.41E-OS 1.32E&7 O.OOE+00 2-37E-OS Te-131m 1.73E-06 8.46E&7 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 Te-131 1.97E-OS 8.23E&9 6.22E-09 1.62E-OS 8.63E-OS 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 7.56E-07 2.23E-06 S.BOE-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.9SE-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-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 I-134 1.06E-07 2.8SE-07 1.03E-07 4.99E-06 4.58E-07 O.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 6.22E-05 1.48E-04 1.21E-04 O.OOE+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2 92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-OS 1.09E-07 5.40E-OB O.OOE+00 8.01E-OB 7.91E-09 4.65E-13 Ba-139 9.70E-OS 6.91E-ll 2.84E-09 0 ~ OOE+00 6.46E-11 3 92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-OB 1.33E-06 O.OOE+00 8.67E-09 1.46E-OB 4 18E-05 Ba-141 4.71E-OB 3.56E-11 1.59E-09 O.OOE+OO 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-OS 2.19E-11 1.34E-09 O.OOE+00 1.85E-ll 1 24E-11 3-OOE<<26 La-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+00 0.00E+00 0.00E+00 9 25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.1SE-10 O.OOE+00 2.94E-09 O.OOE+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 2.62E-OB O.OOE+00 1.21E-07 0 ~ OOE+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-11 1.53E-12 O.OOE+00 7.05E-12 O.OOE+00 4 33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-IO O.OOE+00 4.25E-09 O.OOE+00 3.49E-05 8-187 1.03E-07 8. 61E-08 3.01E-OS O.OOE+00 O.OOE+00 O.OOE+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0 OOE+00 3.65E-10 0 ~ 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.

600(207)

RETS Manual Revision 13 Page 129 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&7 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. 76EW4 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&9 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 O.OOE+00 5.90E-06 1.17E-06 O.OOE+00 1.76E-06 O.OOE+00 1.21E-05 Mn-56 O.OOE+00 1.58E-07 2.81E&8 O.OOE+00 2.00E-07 O.OOE+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6. 25EW7 O.OOE+00 O.OOE+00 1.70E-06 1.16E-06 Fe-59 5. 87E&6 1.37E-05 5.29E&6 O.OOE+00 O.OOE+00 4.32E-06 3.24E-05 Co-57 O.OOE+00 2.38E-07 3.99E-07 O.OOE+00 0.00E+00 O.OOE+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.34E-05 Co-60 O.OOE+00 2.81E&6 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 0.00E+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 1.15EW7 5.41E-08 O.OOE+00 2. 91E&7 O.OOE+00 8~92E-06 Zn-65 5.76E-06 2.00E-05 9.33EW6 O.OOE+00 l. 28E-05 O.OOE+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 I. 96E&9 O.OOE+00 1.83E-08 O.OOE+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5 19E&8 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 0.00E+00 Br-83 O.OOE+00 0.00E+00 5.74E-OS 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 O.OOE+00 7.22E-08 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 0.00E+00 3.05EW9 0 ~ OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 O.OOE+00 4.41E-06 Rb-88 O.OOE+00 8 ~ 52E&8 4;54E-08 0.00E+00 0.00E+00 O.OOE+00 7.30E-15 Rb-89 O.OOE+00 5.50E&8 3.89E-08 0 OOE+00 0.00E+00 O.OOE+00 8.43E-17 Sr-89 4.40E-04 O.OOE+00 1.26E-05 0 ~ OOE+00 0.00E+00 O.OOE+00 5.24E-05 Sr-90 8.30E-03 0 OOE+00 2.05E-03 0 ~ OOE+00 O.OOE+00 O.OOE+00 2.33E-04 Sr-91 8.07E-06 O.OOE+00 3 ~ 21E&7 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 0.00E+00 O.OOE+00 7.77E-05 Y-90 1.37E-08 O.OOE+00 3.69E-10 0.00E+00 0.00E+00 0.00K+00 1.13E-04 Y-91m 1.29E-10 O.OOE+00 4.93E-12 0.00E+00 0.00E+00 O.OOE+00 6.09E-09 Y-91 2.01E-07 O.OOE+00 5.39E&9 O.OOE+00 O.OOE+00 O.OOE+00 8.24E>>05 Y-92 1.21E-09 0 OOE+00 3.50E-11 O.OOE+00 O.OOE+00 O.OOE+00 3.32E-05 Y-93 3 83E&9 0 ~ OOE+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E<<04 Zr-95 4.12E&8 1.30E-08 8.94E-09 0.00E+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&9 O.OOE+00 4.42E-09 O.OOE+00 1.95E-05 Nb-97 7.37E-11 1.83E-ll 6.68E-12 O.OOE+00 2.14E-11 O.OOE+00 4.37E-07 Mo-99 0 OOE+00 6.03E-06 1.15E-06 0 ~ OOE+00 1.38E-05 O.OOE+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-OS 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 0.00E+00 8.99E-07 O.OOE+00 2.13E-05 RQ-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 0.00E+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 0.00E+00 5.45E-05 600(207)

RETS Manual Revision 13 Page 130 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-OB 1.51E-06 8.78E-09 O.OOE-OO 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-OB 5.80E-07 2 37E-09 0.00E+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-06 2.30E-06 3.92E-05 O.OOE+00 2.41EW5 Te-127 1.58E-07 5.60E-OB 3.40E-OS 1.09E-07 6.40E-07 O.OOE+00 1.22E-05 Te-129m 1.63E-05 6.05E06 2.58E-06 5 26E-06 6.82E-05 O.OQE+00 6.12E-05 Te-129 4.48E-OS 1.67E-OS 1.09E-OS 3.20E-OB 1.88E-07 0 OOE+00 2.45E-07 Te-131m 2.44E-06 1.17E-06 9. 76E&7 1.76E-06 1.22E-05 0.00E+00 9.39E&5 Te-131 2.79E-OB 1.15E-OB 8.72E-09 2. 15E-08 1.22E-07 O.OOE+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 O.OQE+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04, 4.59E-06 0 OOE+00 2.29E&6 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E&3 1.41E-05 O.OOE+00 1 62E-06 I-132 2.79E-07 7.3QE-Q7 2.62E-07 2.46E-05 1.15EW6 O.OOE+00 3.18E07 I-133 2.01E-06 3.41E-06 1.04EW6 4.76E-04 5.98E-06 O.OOE+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E&7 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 I-135 6 10E-07 1.57E-06 5. 82E-07 1 01E&4 2.48E-06 O.OOE+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0 OOE+00 6.26E&5 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OQE+00 1.84E-05 2.90E&6 2.72E06 Cs-137 1.12E-04 1.49E-04 5.].9E-05 0.00E+00 5.07E-05 1.97E-05 2. 12E&6 Cs-138 7.76E-QB 1.49E&7 7.45E-OB O.OOE+00 1.10E-07 1 28E-08 6.76E-ll Ba-139 1.39E-07 9.78E-11 4.05E-09 0 OOE+00 9.22E-ll 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-QB 1.83E-06 O.OOE+00 1.18E-OB 2.34E-OS 4.38E-05 Ba-141 6.71E-OS 5.01E-11 2.24E-09 O.OOE+00 4.65E-11 3.43E-ll 1.43E-13 Ba-142 2.99E-OS 2.99E-ll 1.84E-09 0.00E+00 2.53E-ll 1.99E-ll 9 '8E-20 La-140 3.48E-09 1.71E-09 4.55E-10 O.OQE+00 O.OOE+00 0.00E+00 9 '2E-05 La-142 1.79E-10 7 '5E-11 1.98E-ll O.OOE+00 O.OOE+OQ 0'.OOE+QQ 2.42E-06 Ce-141 1.33E-OB 8.88E-09 1 ~ 02E-09 0 OOE+00 4.18E-09 O.OOE+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E&7 2.88E-07 3.74E-O& 0 OOE+OQ 1.72E-07 O.OOE+00 1.75E-04 Pr-143 1.31E-OS 5.23E-09 6 '2E-10 O.OOE+00 3.04E-09 0 00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 O.OOE+00 1.01E-11 O.OOE+00 4.74E-14 Nd-14/ 9.38E-09 1.02E-OB 6.11E-10 O.OOE+00 5.99E-09 O.OOE+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-OB O.OOE+00 O.OOE+00 0 OOE+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-ll O.OOE+QO 5.21E-10 0 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.

600(207)

0 RETS Manual Revision 13 Page 131 Table 6-4 (5 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD liver t body thyroid kidney lung gi-lli H-3 .03E-07 2 03E-07 2-03EW7 2.03E-07 2.03E-07 2.03E-07 C-14 l. 21E-05 2. 42K&6 2. 42E-06 2.42EM6 2.42E-06 2. 42E&6 2.42E-O 6 Na-24 5.80E-06 5.80E-06 5.80E&6 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 O.DOE+00 O.ODE+00 0.DOE+00 2.2SE-05 Cr-51 O.OOE+00 O.DOE+00 8.90E-09 4.94E&9 1.35E-09 9.02E-09 4.72E-07 Mn-54 O.DOE+00 1.07E-05 2.85E-06 O.ODE+00 3.00E-06 0.DOE+00 8.98E-06 Mn-56 O. DOE+00 3. 34E&7 7. 54E-DS O. DOE+00 4.04E&7 O.OOE+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 O.DOE+00 O.ODE+00 3.45E&6 1.13E-06 Fe-59 '.65E-05 2.57E-05 1.33E-05 O.DOE+00 O.DOE+00 7.74E-06 2.78E-05 Co-57 O.DOE+00 4.93E-07 9.98E-47 0.00E+00 O.DOE+00 O.DOE+00 4.04E<<06 Co-58 1.80E-06 5.51E-06 O.DOE+00 0.00E+00 O.ODE+00 1.05E-OS Co-60 O.DOE+00 5.29E-06 1.56EM5 O.DOE+00 O.DOE+00 0.00E+00 2.93E--0 5 Ni-63 5.38E-04 2.88E-05 1.83EM5 O.OOE+00 O.ODE+00 O.OOE+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.DOE+00 0.00E+00 O.DOE+00 2.56E-05 CG-64 O.OOE+00 2.45E-07 1.48E-07 2.45E O.DOE+00 5.92E-07 0.00E+00 l.15E-05 Zn-65 1.37E<<05 3 65E-05 2.27E-05 O.DOE+00 2.30E-05 O.DOE+00 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E&9 O.DOE+00 3.84E-DS O.DOE+0 0 3.99E-06 Zn-69m 7.10E&7 1.21E-06 1.21E 1.43E-07 O.ODE+00 7.03E-07 O.OOE+00 3.94E-05 Br-82 O.DOE+00

~ 0.

OoOOE+00 7 '5E-06 OeODE+00 0 'OE+00 OeODE+00 DeODE+00 Br-83 O.DOE+00 O.DOE+00 1.71E&7 O.DOE+00 O.ODE+00 O.ODE+00 0.DOE+00 Br-S4 O.DOE+00 O.DOE+00 1.98E&7 O.DOE+00 O.DOE+00 O.ODE+00 0.00E+00 Br-85 O.DOE+00 9.12E-09 O.ODE+00 O.DOE+00 0.DOE+00 0.00E+00 Rb-86 O.DOE+00 6.70E-05 4.12E-05 O.ODE+00 O.DOE+00 O.OOE+00 4.3lE--06 Rb-88 0.DOE+00 1.90E-07 1.32E-07 O.DOE+00 O.OOE+00 0.DOE+00 9.32E-09 Rb-89 O.OOE+00 1.17E-07 1.04E-07 O.DOE+00 O.DOE+00 O.DOE+00 1.02E-09 Sr-89 1.32E-03 O.DOE+00 3.77E&5 O.DOE+00 O.OOE+00 O.OOE+00 5.11E-05 Sr-90 1.70E-02 O.DOE+00 4.31E&3 O.OOE+00 0.00K+00 O.ODE+00 2.29E-04 Sr-91 2.40E-05 O.DOE+00 9.06E-07 0.DOE+00 0.00E+00 O.ODE+00 5.30E-05 Sr-92 9.03E-06 O.DOE+00 3.62E-07 0.DOE+00 O.ODE+00 O.ODE+00 1.71E-04 Y-90 4.11E-08 0.DOE+00 1.10E-09 O.DOE+00 0.00E+00 O.ODE+00 1.17E-04 Y-91m 3.82E-10 O.DOE+00 1.39E-11 O..ODE+00 O.ODE+00 O.OOE+00 7.4SE-07 Y-91 6.02E-07 0 DOE+00 1.61E-08 0.00E+00 O.ODE+00 O.DOE+00. 8.02E-05 Y-92 3.60E-09 O.OOE+00 1.03E-10 O.ODE+00 O.OOE+00 0.00 E +0 0 1.04E-04 Y-93 1.14E-OS 0.DOE+00 3.13E-10 O.DOE+00 O.ODE+00 O.OOE+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E&8 O.ODE+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 01E-09 5.96E-10 O.DOE+00 1.45E-09 O.ODE+00 1.53E-04 Nb-95 2. 25E-DS 8. 76E-09 6. 26K&9 0. OOE+00 8. 23E&9 O.ODE+0 0 1.62E-05 Nb-97 3.92E-ll 1.83E-ll O.DOE+00 4.35E-ll O.ODE+00 1.21E-05 Mo-99 O.DOE+00 1.33E-05 3.29E-06 O.ODE+00 2.84E-05 O.ODE+0+ 0 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00K&8 O.ODE+00 2.63E-DS 9 19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-DS O.ODE+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 .DOE+00 O.DOE+0 2.81E-07 O.DOE+00 1.84E-06 0.DOE+00 1.89E-05 Ru-105 ODE+00 2 34E-08 O.ODE+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 O.OOE+00 1.46E-06 O.DOE+00 1.58E-05 O.OOE+00 1.82E-O 4 Ag-110 m 5 39E-07 3.64E-07 2.91E-07 O.DOE+00 6.78E-07 O.ODE+00 4.33E-05 cnnf~n73

RETS Manual Revision 13 Page 132 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&7 3.89E-06 2.45EWS O.OOE+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-OS 1.50E-06 6.63E-09 O.OOE+Qo 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.2QE-06 O.OOE+00 O.OQE+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.9lE&6 8.24E>>05 O.OQE+00 2.34E-05 Te-127 4.71E-07 1.27E-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 5.94EW5 Te-129 1.34E-07 3.74E-OB 3.1SEWS 9.56E-QB 3. 92EW7 O.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2. 65E-06 5.12E-06 2.41E-05 O.OOE+00 1.01E-04 Te-131 8.30E-OB 2.53E-OB 2.47E-QS 6.35E-QS 2.51E-07 O.OOE+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E&6 4.15E-05 O.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E&6 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 I-131 l. 72E&5 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-06 I-132 S.QOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+00 1.73E-06 I-133 5.92E-06 7.32E-06 2. 77E&6 1.36E-03 1.22E-05 O.OOE+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E&7 1.79E-05 1.19E-06 0.00E+QO 5.16E-07 I<<135 1.75E-06 3.15E-06 1.49E-O6 2.79E-04 4.83E-06 O.OOE+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 O.OQE+00 1.19E-04 4.22E-05 2.02E&6 Cs-136 2.35E-05 6.46E-05 4.18E-05 O.OOE+00 3.44E-05 5.13E&6 2.27E-06 Cs-137 3.27E-Q4 3.13E-04 4.62E-05 O.OQE+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 O.OQE+00 2.23E-07 2.40E-OB 1.46E-07 Ba-139 4.14E-02 2.21E-10 1.20E-OB 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-QB 4.85E-06 O.OOE+00 2.37E-OS 4.34E-OB 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 O.OOE+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-QS 6.29E-11 4.88E-09 O.OOE+00 5.09E-11 3.70E-11 1.14E>>09 La-140 1.01E-QS 3.53E-09 1.19E-09 O.OOE+00 0.00E+00 0;OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 O.OOE+00 O.OOE+00 O.OOE+00 3.31E-Q5 Ce-141 3.97E-QS 1.98E-OB 2.94E-09 O.OQE+00 8.68E-Q9 O.OOE+00 2.42E-45 Ce-143 6.99E-09 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 O.OQE+00 3.61E-07 O.OQE+00 1.70E>>04 Pr-143 3.93E-OB 1.1&E-QB 1.95E-09 0.00K+00 6.39E-09 O.OQE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 O.OOE+00 2.11E-11 O.OQE+00 8.59E-OS Nd-147 2.79E-QB 2.26E-QB 1.75E-09 O.OQE+00 1.24E-QB O.OQE+00 3.58E-05 W-182 4.29E-07 2.54E-07 1.14E-07 O.OQE+00 O.OOE+00 O.OOE+00 9.52E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+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, Nh-97, Sh-124 and Sb<<125 are from NUREG-0172 A e S ecific Radiation Dose Coamitment Factors'or 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.

600(207)

RETS Manual Revxsxon 13 Page 133 Table 6.4 (7 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT H-3 bone 3.08E&7 liver 3.08E-07 t body 3.08E-07 thyroid 3.08E07 kidney 3.08E-07 lung gi-lli 3.08E-07 3.08E-07 C-14 2.37E-05 5.06K-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E&5 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 l. 70E-03 1.00K-04 6.59E&5 O.OOE+00 0.00E+00 O.OOE+00 2.30E-05 Cr-51 0.00E+00 O.OOE+00 1.41E-08 9.20E-09 2.01E-09 l. 79EWS 4. 11EW7 Mn-54 O.OOE+00 1.99K&5 4.51E-06 O.OOE+00 4.41E-06 O.OOE+00 7.31E-06 Mn-56 O.OOE+00 d. 18K-07 1.41E-07 0.00E+00 7.03E-07 O.OOE+00 7.43E-05 Fe-55 1.39E&5 8.98K&6 2.40E-06 O.OOE+00 O.OOE+00 4.39E-06 1.14E-06 Fe-59 3.08E-OS 5 ~ 38K-05 2. 12EW5 O.OOE+00 0.00E+00 1.59E-05 2.57E-05 Co-57 O.OOE+00 1. 15E-06 1.87E-06 0.00K+00 O.OOE+00 0.00E+00 3. 92K&6 Co-58 0.00E+00 3.60E-06 8-98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 O.OOE+00 1.08E-05 2.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.57E-05 Ni-63 Ni-65 6.34E&4 3.92E-05 2.20E-05 4.70E-06 5.32E-07 2.42E-07 0.00E+00 O.OOE+00 O.OOE+00 l. 95EW6 O.OOE+00 O.OOE+00 O.OOE+00 4. 05E-05 CU-64 0.00E+00 6 '9K-07 2. 82EW7 O.OOE+00 1.03E-06 O.OOE+00 1.25E-05 Zn-65 1.84E-05 6 ~ 31E&5 2.91E-05 O.OOE+00 3 06E-05 O.OOE+00 5.33E-05 Zn-69 9.33EOS 1.68E-07 1.25E-08 O.OOE+00 6.98E>>OS 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 0 ~ OOE+00 1.27E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 3.63E-07 0.00K+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 0 ~ OOE+00 3 '2E-07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Rb-86 O.OOE+00 1 70E-04 8.40E-05 O.OOE+00 O.OOE+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4 98E-07 2.73E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.85E-07 Rb-89 O.OOE+00 2.86E-07 1.97E-07 0.00E+00 0.00K+00 0 OOE+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 O.OOE+00 0.00K+00 O.OOE+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00K+00 O.OOE+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E&6 O.OOE+00 O.OOE+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0 OOE+00 O.OOE+00 O.OOE+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2. 33E&9 O.OOE+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 O.OOE+00 2.76E-11 O.OOE+00 0.00E+00 O.OOE+00 2.70E-06 Y-91 1.13E-06 O.OOE+00 3.01E-OS 0.00E+00 0.00E+00 O.OOE+00 8.10E-05 Y-92 7 65E-09 O.OOE+00 2.15E-10 0.00E+00 0.00E+00 O.OOE+00 1.46E-04

'-93 2.43E-OS 0.00E+00 6.62E-10 0.00E+00 O.OOE+00 O.OOE+00 1.92E-04 Zr-95 2.06E&7 5.02E-08 3.56E-OS 0.00E+00 5.41E-OS O.OOE+00 2.50E-05 Zr<<97 1.48E-08 2.54E-09 1.16E&9 O.OOE+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-OS 1.73E-08 1 ~ OOE-08 0.00E+00 1.24E-08 O.OOE+00 1.46E-05 Nb-97 4.59E-10 9.79E-ll 3.53E-11 0.00E+00 7.65E-11 O.OOE+00 3.09E-05 Mo-99 O.OOE+00 3.40E-05 6 '3E-06 0.00E+00 5.08E-05 O.OOE+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-OS 0.00E+00 4.26E-OS 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2 83E-08 0.00E+00 3.40E-OS 1.56E-09 4.86E-07 Ru-103 1 ~ 48E-06 O.OOE+00 4.95E-07 0.00K+00 3.08E-06 O.OOE+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4. 58E-'08 0.00E+00 1.00E-06 0.00E+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&6 0.00E+00 3.77E-05 600(207)

0 RETS Hanual Revision 13 Page 134 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&5 3.15E-07 6.63E-06 5.68E-08 O.OOE+00 1.34E-05 6.60E-05 Sb-125 1~ 23E-05 1.19E-07 2.53E-06 1.54E-OS 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-06 3.35E-07 2. 15EW7 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 Te-129m 1.00EW4 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 6.63E-OS 2.38E-07 7.07E-07 O.OOE+00 2.27E-05 Te-131m 1.52E&5 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+00 1.03E-04 Te-131 1. 76E-07 6.50EOS 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&6 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 I-130 6.00EW6 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 l. 20E&6 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&7 1.7SE-06 6.33E-07 4.15E-05 1.99E&6 O.OOE+00 1.84E-06 I-135 3. 64E&6 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+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 O.OOE+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&7 O.OOE+00 3.90E-07 6.09E-OS 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.5SE-OS O.OOE+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 O.OOE+00 4.06E-OS 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-OS O.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 O.OOE+00 8.81E-11 9.26E-11 7.59E-07 1a-140 2.11E-08 8.32E-09 2.14E-09 0.00K+00 0.00E+00 O.OOE+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 O.OOE+00 O.OOE+00 O.OOE+00 6.86E-05 Ce-141 7.87E-OS 4.80E-08 5.65E-09 O.OOE+00 1.48E-OS O.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 O.OOE+00 2.86E-09 O.OOE+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+00 4.93E-07 O.OOE+00 1.71E-04 Pr-143 8.13E-OS 3.04E-OS 4.03E-09 O.OOE+00 1.13E-OS O.OOE+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 O.OOE+00 3.84E-ll O.OOE+00 4.93E-06 Nd-147 5.53E-08 5.68E-OS 3.48E<<09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-05 M-187 9.03E-07 6.28E-07 2.17E-07 O.QOE+00 0.00E+00 O.OOE+00 3.69E-05 Np-239 1.11E-OS 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.

600(207)

RETS Manual Revision 13 Page 135 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH H-3 9.0E-Ol Tc-99m 1 5E+01 C-14 4.6E+03 Tc-101 1.5E+Ol Na-24 1.0E+02 Ru-103 1.0E+01 P-32 1.0E+05 Ru-105 1.0E+Ql Cr-51 2.0E+02 Ru-106 1.0E+01 Mn-54 4.0E+02 Ag-110m O.OE+00 Mn-56 4.0E+02 Sb-124 1.0E+00 Fe-55 1.0E+02 Sb-125 1 OE+00 Fe-59 1.0E+02 Te-125m 4.0E+02 Co-57 5.0E+Ol Te-127m 4.0E+02 Co-58 5.0E+Ol Te-127 4.0E+02 Co-60 5.0E+Ol 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 Cu-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+01 Br-82 4.2E+02 I-132 4.0E+01 Br-83 4.2E+02 I-133 4.0E+Ol Br-84 4.2K+02 I-134 4.0E+Ol Br-85 4.2K+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 5.6K+01 Cs-138 1.9E+03 Sr-90 5.6K+01 Ba-139 4.0K+00 Sr-91 5.6E+01 Ba-140 4.0E+00 Sr-92 5.6E+01 Ba-141 4.0E+00 Y-90 2.5E+Ol Ba-142 4.0E+00 Y-91m 2.5E+01 La-140 2.5E+01 Y-91 2.5E+Ol La-142 2.5E+Ol Y-92 2.5K+01 Ce-141 1.0E+00 Y-93 2.5K+01 Ce-143 1.0E+00 Zr-95 3.3E+00 Ce-144 1.0E+00 Zr-97 3.3K+00 - Pr-143 2.5E+01 Nb-95 3.0E+04 Pr-144 2.5E+01 Nb-97 3.0K+04 Nd-147 2.5E+01 Mo-99 1.0E+01 W-187 1.2E+03 Np-239 1.0K+01

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 NUREGlCR-1004, Table 3.2.4.

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

600(207)

RETS Manual Revision 13 Page 136 Table 6.6 {1 of 2)

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

Nuclide Total Body Skin 8-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-OB 2.90E-OB P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 kin-54 5.80E-09 6.80E-09 Mn-56 1.10E-OS 1.30E-OB Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-$ 7 l. 77E&9 2. 21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-OS 2.00EWB Ni-63 0.0 0.0 Ni&5 3.70E-09 4.30E-09 C0-64 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&9 Br-82 3.18E-OB 3.90E-OB Br-83 6.40E-11 9.30E-11 Br-84 1.20E-OS 1.40E-OB 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-OB 1.80E-OS Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-OS 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 '0E-09 Nb<<95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-OS Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-10l 2. 70E&9 3.00E-09 RU-103 3. 60E&9 4.20E-09 Ru-105 4. 50EW9 5.10E-09 RQ-106 1.50E-09 1.80E-09 Ag-110m 1.80E-OS 2.10E-OB Sb-124 2.17E-OB 2.57E-OB 600(207)

RETS Manual Revision 13 Page 137 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-09 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 1.70E-09 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 '0E-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-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2 '0E-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 2.20E-09 2.50E-09 Ce-144 3.20E<<10 3.70E-10 Pr-l43 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.

600(207)

RETS Nanua1 Revision '13 Page 138 Figure 6. 1 LI UXD RELEASE POINTS BFH Ltqutd Ellluent Monitors PypIcet Unit end Common Redwaste)

Oondtnoot Oooanp Helot thteke Bey IllIll eottft e Helot Leeft I nllll fllftt 1st fut to Its

'Its bbto S&tftte no stfot SMtdlnt nstbtsNo tottottonl N tt ftt t

Oft onbte 1st No/of bled 0

flftttot (1) Turbine Bulldlng Equlprnent (2) Reactor Bulfdlng Equipment Te Oeolne (3) Condenser Tettoto Slettd own Ftelll Octane Tettete 600(207)

RETS Manual Revision .l3 Page 139 Figure 6.2 LI UID RADWASTE SYSTEM.

Floor Floor Drain 'Drain Drain Tl~

1 Floor BMQO-130 Fl Collector Filter Sample Drelna Tanka Tank Laundry Drain Tanka Equipment ra na Waate Condenaate Weatb Weate Weate Demlherellzer Sample Storage Collector Filter Tanka Tenka Tank 600(207)

RETS Manual Revision 13 Page 141 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. These 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.

600(207)

RETS Manual Revision.13 Page 142 7.1 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 below.

Total Bod Dose Rate The dose rate to the total body from nuclide i, DTBi in mrem/year, is calculated using the following equation:

DTBi ( /Q) Qi. DFBi

~here X/Q relative concentration, s/m . Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

Qi release rate of noble gas nuclide i, pCi/sec.

DFBi total body dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4) ~

Skin Dose Rate The dose rate to the skin for nuclide i, Dsi in mrem/year, is calculated using the following equation.'si

= ("/Q) Qi(DFSi + 1 11 DFYi) where X/Q = relative concentration, s/m 3.. Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

Qi = release rate of noble gas nuclide i, pCi/sec.

DFSi = skin dose factor due to beta radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4).

= the average ratio of tissue to air energy absorption coefficients, mrem/mrad.

DFYi = dose conversion factor for external gamma for noble gas nuclide i, mrad/year per pCi/m3 (Table 7.4).

600(207)

RETS Manual Revision.13 Page 143 Oz an Dose Rate due to I-131 I-133 Tritium and All Radionuclides in Particulate Form with Half-lives of Greater Than 8 Da s Organ dose rates 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:

For tritium, Dozg = QT( /Q) [RIT + RCTP~

For all other particulates, Dozg Qj [( /Q)RIj + ( /Q) [RCPi+RGi] 1 where release rate of tritium in, pCi/sec.

relative concentration, s/m3. Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.9.2 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

RIT inhalation dose factor for tritium, mrem/year per pCi/m3. Dose factor is calculated as described in Section 7.8.13.

RCTp Grass-cow-milk dose factor for tritium, mrem/year per pCi/m .

Dose factor is calculated as described in Section 7.8.7.

Qi release rate of nuclide i, pCi/sec.

RIi inhalation dose factor for each identified nuclide i, mrem/year per pCi/m3. Dose factors are calculated as described in Section 7.8.13.

D/Q relative deposition, 1/m2. Relative deposition is calculated for the land-site boundary in each of the sixteen'sectors as described in Section 7.9.3 using the historical meteorological data for the period 1977-1979 given in Table 7.3.

RCpi Grass-cow-milk dosq factor for each identified nuclide i, m -mrem/year per pCi/s. Dose factors are calculated as described in Section 7.8;l.

RGi ground plane dose factor for each identified nuclide i",

m2-mrem/year per pCi/s. Dose factors are calculated as described in Section 7.8.14.

600(207)

RETS Manual Revision 13 Page 144 rate limits of interest are:

'he dose 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 )

Maximum Organ Dose Rate Limit RTH(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 nuclide type (noble gas or iodine/particulate) and release point (building vent or stack) is calculated, using the source term data in Table 7.2. Thus, four total release rates are calculated:

Qgv = Total noble gas release rate from building exhaust vents,.Ci/s.

Qngs = Total noble gas release rate from main stack, Ci/s.

Qzpv ~ Total iod ine and particulate release rate from building exhaust vents, Ci/s.

Qips Total iodine and particulate release rate from main stack, Ci/s.

To obtain a release rate limit, r, for each nuclide type and release point, the total release rate, Q, for that nuclide type and release point is multiplied by the corresponding ratio, R:

For noble gases released from building vents:

ngv = TBv Qngvi

~ Rsv Qngv whichever is more restrictive, i.e., smaller.

600(207)

RETS Manual Revision 13 Page 145

'here rngv = Calculated release rate limit for noble gases released from building vents.

RTav = 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 = Res Qngs~ or

= RSs Qngs whichever is more restrictive, i.e., smaller.

where rngs = Calculated release rate limit for noble gases released from the stack.

RTas = 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.

For iodines and particulates with half-lives greater than 8 days released from building vents:

ripv = RTHv Qipv where ripv = Calculated release rate limit for iodines and particulates released from building vents.

RTHv = Ratio of maximum organ dose rate limit to maximum organ dose rate for building vent releases, as calculated above.

Qipv = Total Table 7.2 iodine and particulate release rate from building vents.

For iodines and particulates with half-lives greater than 8 days released from the stack:

rips RTHs Qips where rips Calculated release rate limit for iodines and particulates released from the stack.

RTHs = Ratio of maximum organ dose rate limit to maximum organ dose rate for stack releases, as calculated above.

Qips Total Table 7.2 iodine and particulate release rate from stack.

600(207)

RETS Manual Revision 13 Page 146" The release rate limits, r, calculated for BFN using this methodology are:

Noble Gas Iodine and Particulate Stack rngs = 1.44E+Ol Ci/s rips = 3.57E-05 Ci/s Building Vents rngv = 1.50EWl Ci/s ripv = 2.19E-06 Ci/s The values listed are used as administrative guidelines for operation.

The instantaneous release rates, r in Ci/sec, for each nuclide type and release point are limited by the following equations:

For noble gases, rngv + rags 0.15 14.4 For iodines and particulates, ripv + rips ( 1 2.19E-06 3.57E-05 600(207)

RETS Manual Revision 13 Page 147 7.2 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS 7.2.1 Alarm/Tri Set pints Control 1.1.2 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODCM describes the methodology that will be used to determine these allowable values which are used to calculate setpoints. Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.

The methodology for determining 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 nuclide and release point. The methodology for the calculation of these release rate limits is given in Section 7.1. The second consists of using the release rate limits to determine the allowable values which are used to calculate the physical settings on the monitors. The methodology for the calculation of the allowable values iI given below. The monitor setpoints are calculated in the applicable Scaling and Setpoint Document.

7.2.2 Allowable Values To determine allowable values for gaseous effluent monitors, shown in Figures 7.1 and 7.2 ~ the noble gas release rate limits are used.

The allowable values are calculated using the following equation r f A Allowable Value c + B F E where r 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+05 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 if both the stacks and the ground level release rate limits were 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.

600{207)

RETS'anual Revision 13 Page 148.

= flow rate for the vent, cc/sec. Maximum flow ries are used to-ensure conservative setpoints.

= efficiency of the monitor, (pCi/cc)/cpm (or (pCi/cc)/cps for the stack monitor)

= background of the monitor, cpm (cps for the stack monitor)

The calculation of these setpoints are documented further in Technical Instruction (TI) 15 and the applicable Scaling and Setpoint Document, including the numerical values for each of the parameters described above.

600(207)

RETS Manual Revision 13 Page 149 7.3 GASEOUS EFFLUENTS DOSE RATES 7.3.1 Noble Gas Dose Rates Dose rates are calculated for total body and skin, due to submersion within a cloud of noble gases, 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 Browns Ferry Nuclear Plant (BFN). The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e.,

the nearest SITE BOUNDARY points in each sector (from Table 7.1) and at other locations expected to be the maximum exposure points.

The noble gas radionuclide mix used in this calculation is based on the design objective source term given in Table 7.2. Dispersion of the released radioactivity is handled as described in Section 7.9 using historical annual average meteorological data given in Table 7.3. No credit is taken for shielding by residence.

To calculate the noble gas dose rate from radiological effluents discharged from a given release point for any one of the potential maximum-exposure points, the equations given in Section 7.7.1 are used.

The total body and skin dose rate calculations are repeated for each release point. Dose rates for releases from all building vents are summed. The maximum stack and building vent total body and skin dose rates will be used to determine release rate limits.

600(207)

RETS Manual Revision 13

~

Page 150 7.3.2 I-131 I-133 Tritium and all Radionuclides in Particulate Form with Half-lives of Greater than 8 da s Or an Dose Rate Dose rates are calculated for the critical organ, thyroid, of the critical age group, infant. Pathways considered are inhalation, ground contamination an4 milk ingestion. The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest SITE BOUNDARY points in each of the 16 sectors (from Table 7.1) and at other locations expected to be the maximum exposure points. This calculation assumes that a (hypothetical) cow is at each of these locations. These cows are assumed, conservatively, to obtain 100 percent of their food from pasture grass.

The inhalation, ground contamination, and milk ingestion dose rates (in mrem/year) for the selected organ (thyroid) and age group (infant) are calculated using Kqwtion 7.9 as described in Section 7.6.2. For determining the total thyroid dose rate from iodines and particulates:

DTH = DTHI + DTBG + DTHM (7.1) where:

= total thyroid dose rate, mrem/yr.

DTHI ~ thyroid dose rate due to inhalation, mrem/yr.

DTBG = total body dose rate due to ground contamination, mrem/yr. The thyroid dose rate is assumed to be equal to the total body dose rate for thi! pathway.

DTHM = thyroid dose rate due to pasture grass-cow-milk ingestion, mrem/yr.

The iodine and particulate dose rates are calculated for the design objective source term given in Table 7.2. The above dose rate calculation is repeated for each release point. Dose rates for releases from all building vents are summed. The maximum stack and building vent thyroid dose rates will be used to determine release rate limits.

600(207)

RETS Manual Revision 13 Page 151

'.4 DOSE NOBLE GASES 7.4.1 Monthl Noble Gas Dose Doses to be calculated are gamma and beta air doses due to exposure to cloud of noble gases'he use of a finite cloud model a'emi-infinite would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BFN. Releases of Ar-41, Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 are considered. Because only these nuclides are considered, the dose is divided by 0.9, to account for a possible 10 percent contribution of dose from other nuclides.

The dispersion factor used will be the highest annual-average X/Q based on 1977-1979 meteorological data (Table 7.3). Dispersion factors are calculated using the methodology described by Equation 7.11. Stack releases are considered elevated releases. All other vent releases will be treated as ground level, No credit is taken for radioactive decay.

7.4.1.1 Monthl Conservative Model Gamma Air Dose (x/Q) 106 DY ~ Qi DFY (7.2) 0.9 3.15E+07 i where:

DY = gamma dose to air, mrad.

x/Q = highest annual-average relative concentration at or beyond the SITE BOUNDARY, s/m3 (from Table 7.1).

= 1.84E-06 for ground level releases,

= 2.08E-08 for elevated releases (stack).

0.9 = fraction of total gamma dose expected to be contributed by the assumed nuclides.

106 pCi/Ci conversion factor.

3.15E+07 = s/yr conversion factor.

Qi = monthly release of radionuclide i, Ci.

DPY gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m (Table 7.4).

600(207)

RETS Manual Revision 13 Page 152 .

7.4.1.2 Monthl Conservative Model Beta Air Dose (x/0) 106 DB = Qi DFSi (7.3) 0.9 3.15E+07 i where:

Dg = beta dose to air, mrad.

x/0 = highest annual-average relative concentration at or beyond the SITE BOUNDARY, s/m3 (from Table 7.1).

= 1.84E-06 for ground level releases,

= 2.08E-08 for elevated releases (stack).

0.9 = fraction of total beta dose expected to be contributed by the assumed nuclides.

106 pCi/Ci conversion factor.

3.15E+07 = s/yr conversion factor.

= monthly release of radionuclide i, Ci.

DFBi = beta-to<<air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

7.4.1.3 Cumulative Dose - Noble Gas Cumulative calendar quarter doses are estimated by summing the doses calculated for each month in that quarter. Cumulative calendar year doses are estimated by summing the doses calculated for each month in that year.

7.4.1.4 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits to determine compliance.

600(207)

0 RETS Manual Revision 13 Page 153 7.5 CUMULATIVE DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone and teen gastrointestinal tract (GIT) from vegetable ingestion. Releases of H-3, I-131, and I-133 are considered for the milk pathway. H-3, Sr-89, Sr-90, Cs-134, and Cs-137 releases are considered for the vegetable pathway .to the child bone. H-3, Co-58, and Co-60 releases are considered for the vegetable pathway to the teen GIT. The most critical real cow location is considered for the milk pathway and the most critical location with a home-use garden is considered for the vegetable pathways (see Table 7.1). The cow is assumed to graze on pasture grass for the whole year.

The highest annual-average X/Q and D/Q based on 1977-1979 meteorological data (Table 7.3) will be used for ingestion pathway locations.

Dispersion values are calculated as described by Equations 7.12 and 7.13. Stack releases are considered elevated releases. All other vent releases will be treated as ground level.

No credit is, taken for radioactive decay.

Doses are divided by 0.9 to account for a possible 10 percent contribution from other nuclides.

The maximum monthly organ dose is the highest of the three doses calculated.

600(207)

RETS Manual Revision 13 Page 154 .

7.5.1 Monthl Conservative Model Infant Th roid Dose-from Milk

~In ection The monthly thyroid dose from milk ingestion is calculated using the following equation:

PQi D/Q + (QT RCpT) X/Q 106 i RCpi) (7.4) where 0.9 (3.15E+07)

= monthly release of iodine nuclide i, Ci.

= monthly release of H-3, Ci.

RCpi = I-131 or I-133 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/m2-s. Dose factors are calculated as described in Section 7.8.1.

RCpT ~ H-3 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/m . The dose factor is calculated as described in Section 7.8.7.

D/Q = highest relative deposition rate for a location with an identified milk cow, m 2 (from Table 7.1).

= 3.16E-10 for ground level releases,

= 2.30E-10 for elevated releases {stack).

X/Q = highest relative air concentration for a location with an identified milk cow, s/m3 {from Table 7.1).

= 1.47E-07 for ground level releases,

= 1.69E-OS for elevated releases (stack).

0.9 ~ fraction of dose expected to be contributed by I-131, I-133 and H-3.

3.15E+07 = s/yr.

106 ~ pCi/Ci.

600(207)

RETS Manual Revision 13 Page 155 7.5.2 Monthl Conservative Model Child Bone Dose from Ve etable

~Zn estion The monthly bone dose from vegetable ingestion is calculated using the following equation:

106 DBC = i (Qi DFi) D/Q +

E QT DFT

~ +

X/Q (7.5) where

= monthly release of Sr or Cs nuclide i, Ci.

= monthly release of H-3, Ci.

DF 1 = Total vegetable ingestion dose factor to child bone for Sr-89, Sr-90, Cs-134 or Cs-137, mrem/yr per pCi/m 2 -s.

RVFi + RVSi, where RVFi is the dose factor for fresh leafy vegetables (as calculated in Section 7.8.5) and RVSi is the dose factor for stored vegetables (as'alculated in Section 7.8.6).

DFT = Total vegetable ingestion dose factor for child bone for H-3, mrem/yr per pCi/m3.

= RVFT + RVST, where RVFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 7.8.11) and RVSi is the tritium dose factor for stored vegetables (as calculated in Section 7.8.12).

D/Q = highest relative deposition rate for a location with an identified home use garden, m 2 (from Table 7.1).

= 4.46E-09 for ground level releases,

= 1.13E-09 for elevated releases (stack).

X/Q = highest relative air concentration for a location with an identified home use garden, s/m (from Table 7.1).

= 1.57E-06 for ground level releases,

= 9.50E-09 for elevated releases (stack).

3.15E+07 = s/yr.

106 ~ pCi/Ci.

0.9 = fraction of total child bone dose expected to be contributed by H-3, Sr-89, Sr-90, Cs-134, and Cs-137.

600(207)

RETS Manual Revision 13 Page 156 '

' ' Monthl Conservative Model Teen Gastrointestinal Tract GIT)

Dose from Ve etable In estion The monthly teen GIT dose from vegetable ingestion is calculated using the following equation:

106 DCT =$ (Qi DFi) D/Q + QT DFT X/Q (7-6) where

= monthly release of cobalt nuclide i, Ci.

QT = monthly release of H-3, Ci.

DFi = Total vegetable ingestion dose factor to the teen GIT for Co-58 or Co-60, mrem/yr per pCi/m 2 -s.

RVFi + RVSi~ where RVFi is the dose factor for fresh leafy vegetables (as calculated in Section 7.8.5) and RVSi is the dose factor for stored vegetables (as calculated in Section 7.8.6).

DFT = Total vegetable ingestion dose factor to the teen GIT for H-3, mrem/yr per pCi/m .

= RVFT + RVST, where RVFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 7.8.11) and RVST is the tritium dose factor for stored vegetables (as calculated in Section 7.8.12).

D/Q = highest relative deposition rate for a location with an identified home use garden, m 2 (from Table 7.1).

= 4.46E-09 for ground level releases,

= 1.13E-09 for elevated releases (stack).

y/Q = highest relative air concentration for a location with an identified home use garden, s/m (from Table 7.1).

= 1.57E-06 for ground leveL releases,

= 9.50E-09 for elevated releases (stack).

3.15E+07 = s/yr.

106 = pCi/Ci.

0.9 = fraction of total teen GIT dose expected to be contributed by H-3, Co-SS, and Co-60.

600(207)

RETS Manual Revision 13 Page 157 7.5.4 Cumulative Doses Cumulative calendar quarter doses are estimated by summing the doses calculated for each month in that quarter. Cumulative calendar year doses are estimated by summing the doses calculated for each month'in that year.

7.5.5 Total Monthl Dose Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits to determine compliance.

600(207)

RETS Manual Revisi'on 13 Page 158 7.6 GASEOUS RADWASTE TREATMENT 7.6.1 Dose Pro ections 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 S stem Descri tion 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 line of each unit and the stack are continuously monitored by 'ff-gas radiation monitors.

600(207)

RETS'anual Revision 13 Page 159 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated gaseous releases foz 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 teal pathways and receptor locations (as identified

~

in the most recent land use survey) are considered. In addition, actual meteorological date representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in Section 7.9. Stacks releases will be considered elevated releases.

Radwaste and reactor building releases will be considezed split-level releases. Turbine building releases will be treated as ground level.

7.7.1 Noble Gas Dose All measured radionuclkdes are used to calculate gamma and beta air doses. The dose ia 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.

600{207)

RETS Manual Revision 13 Page 160 Gamma Dose to Air '.7.1.1 DYn = 7 Xni DFyi (7.7) 1 where:

gamma 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 7.11.

DFYi gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m (Table 7.4).

7.7.1.2 Beta Dose to Air Bn = E Xni FBi (7.8) 1 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 7.11.

DFBi = beta to air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

600(207)

RETS Manual Revision 13 Page 161 F 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:

org = 3.17E-O8 [E( /Q Dor ERP 1~ + /Q RGi + X/Q RIi)Qi + E(X/Q RPT)QTJ (7.9)

P where:

Dora Organ dose, mrem.

3.17E-08 = conversion factor, year/second.

x/Q Relative concentration for location under consideration, sec/m3. Relative concentrations are calculated as described by Equation 7.12.

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 2.

Relative deposition is calculated as described in Equation 7.13.

ROi 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.

RIi Inhalation dose factor, mrem/year per pCi/m3. The equation for calculating the inhalation dose factor is given in Section 7.8 13.

600(207)

RETS Manual Revision 13 Page 162 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 j=l fj exp(-Xi x/uj) where Qi0 = initial average release for nuclide i over the period,

@Cia f ~ = joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.

Xl = radiological decay constant for'nuclide i, sec 1.

x = downwind distance, meters.

uj = midpoint value of wind speed class interval j, m/s.

RPT ingestion dose factor for pathway P for tritium, mrem/year per 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..

adjusted release for tritium for location under consideration, pCi. Calculated in the same manner as Qi above.

600(207)

0 RETS Manual Revision 13 Page 163 .

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 is calculated, and then multiplied by the population in that sector average'ose 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:

Dose pop = g RATIOp

POPN

AGE

0.001

DOSEp (7.10)

P where RATIOp a 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:

600(207)

RETS Manual Revision 13 Page 164

'DC

= 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) Kitch ADC for meat, 1 exp(-'A i cb) ~

where decay constant for nuclide i, seconds.

= 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 5.2 600(207)

RETS Manual Revision 13 Page 165 7.8 GASEOUS DOSE FACTOR E UATIONS 7.8.1 Pasture Grass-Cow-GoatMilk In estion Dose Factors (m2-mrem/year per pCi/sec)

( P( E ep) ) Biv(1-exP(-Xi tb ) )

CPi = lO6DF iaoUapFmiQfexp(-'Aitfm)fp +

p E i 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 = transfer factor for nuclide i from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

'hi decay constant for nuclide i, seconds 1 (Table 6.2).

tfm = transport time from milking to receptor, seconds.

fp = fraction of time animal spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

the effective decay constant, due to radioactive decay and XE weathering, seconds 1, equal to'i + Aw.

weathering decay constant for leaf and plant surfaces, seconds tep = time pasture is exposed to deposition, seconds.

= agricultural productivity by unit area of pasture grass, kg/m2.

Yp 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/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6-3.

600(207)

RETS Manual Revision 13 Page 166'

' 2 Stored Feed-Cow/Goat-MiIk In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exp(-Kites RCSi = 10 DFLiao Uap Fmi ~f fs exp(-Xitfm) csf i r(lmxP(-XEtesf ) ) Biv(l~xP( Xitb) )

Ysf )'E 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.

fs ~ fraction of time animal spends on stored feed, dimensionless.

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

tf = transport time from milking to receptor, seconds.

= time between harvest of stored feed and consumption by animal, tcsf seconds.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + +.

weathering decay constant for leaf and plant surfaces, seconds tesf = time stored feed is exposed to deposition, seconds.

Ysf = agricultural productivity by unit area of stored feed, 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'actors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

600(207)

RETS Manual Revision 13 Page 167'.8.3 Pasture Grass-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(-Xitcb))

RMPi = 1, DFLiao Uam Ffi Qf i cb exP(-Kits) r(l~xP(<<'XEtep))

+

Biv(l~P( Xi b))

fp Yp XE P Xi where:

106 conversion factor, pCi/pCi.

D~iao 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).

Qf = cow's consumption rate, kg/day.

'Ai decay constant for nuclide i, seconds 1 (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 'hi + Q.

weathering decay constant for leaf and plant surfaces, seconds 1.

tep ~ time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, 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 over which accumulation on the ground is evaluated, seconds.

P = 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.

600(207)

RETS 'Manual Revision 13 Page 168 7.8.4 Stored Feed-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(-Xitcb))

RMS1 = 106 DFliao Uam Ffi Qf i cb exp( Kits)

(l~p(-X.it cssf ) ) r(l~xp(-XEtesf ) ) Biv(l~xp(-Xitb))

fs +

Xi tcsf Ysf 'AE P Xi where:

106 conversion factor, pCi/pCi.

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

= meat ingestion rate for age group a, kg/year.

Uam Ffi = transfer factor for nuclide i from cow's 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.

fs = fraction of time cow spends on stored feed, dimensionless.

tcsf ~ time between harvest of stored feed and consumption by cow, seconds.

r ='raction 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 .

XE the effective decay constant, due to radioactive decay and weathering, seconds 1, 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/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

600(207)

RETS. Manual Revision 13 Page 169 .

y.8.g Fzesh Leaf Ve etable In estion Dose Factors (m2-mrem/year per pCi/second) r(1-e(-%Etc)) Biv(1~( Xitb))

R~Fi 106 DFiiao e(-~ithc) UF~fl, f E r

where:

106 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 (Table 6.2).

thc = average time between harvest of vegetables and their consumption and/or storage, seconds.

= consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year

= fraction of fresh leafy vegetables grown locally, dimensionless.

= fraction of deposited activity retained on vegetables, dimensionless.

the effective decay constant, due to radioactive decay and weathering, seconds

+ Q decay constant for removal of activity on leaf and plant surfaces by weathering, seconds l.

te ~ exposure time in garden for fresh leafy and/or stored vegetables, seconds.

Yf = 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/m .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

600(207)

RETS Manual Revision 13 Page 170'.8.6 Stored Ve etable In estion Dose Factors m2-mrem/year per pCi/second)

(I-e(->itsv))

RVSi = 10 DFLiao exP(- ithc) USafg sv r(lm(-XEte) ) Biv(1~( Xitb))

Ysv ~E P Xi where:

106 conversion factor, pCi/pCi.

DFL1 ao = ingestion dose conversion factor for nuclide i, age group a, organ o, area/pCi (Table 6.4).

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

= average time between harvest of vegetables and their consumption thc and/or storage, seconds.

USa = consumption rate of stored vegetables by the receptor in age group a, tg/yasr.

fg = fraction of stored vegetables grown locally, dimensionless, tsv = time between storage of vegetables and their consumption, seconds.

~ fraction of deposited activity retained on vegetables, dimensionless.

the effective decay constant, due to radioactive decay and weathering, seconds

~Xi++

decay constant for removal of activity on leaf and plant surfaces by weathering, seconds te = exposure time in garden for fresh leafy,and/or stored vegetables'econds.

Ysv = 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).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m 2 .

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

600(207)

RETS Manual Revision 13 Page 171 Tritium-pasture Grass-Cow/GoatMilk Dose Factor '.8.7 (mrem/year per pCi/m )

RCTP = 10 DFLTao FmT Qf Uap ~0 75(0.5/H)] fp ep( ~Ttfm) 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/m>.

fp = fraction of time animal spends on pasture, 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.

600(207)

RETS Manual Revision 13 Page 172'.8.8 Tritium-Stored Feed-Cow/GoatMilk Dose Factor (mrem/year per pCi/m )

(1-exP(-XTtcsf))

RCTS 103 106 DFLTao FmT Qf 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.)5 ~ 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.

decay constant for tritium, seconds (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.

600(207)

RETS Manual Revision 13 Page 173'.8.9 Tritium-Pasture Grass-Beef Dose Factor (mrem/year per pCi/m )

RMT = 103 10 DFLTao FfT Qf Uam [0.75(0.5/H)l fp exp(

its)'l~xp(

XTtep) ) (l~xP(-XTtcb) )

XT tep XT tcb where:

103 conversion factor, g/kg.

106 conversion tactor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, area/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.

XT decay constant for tritium, seconds (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tep = time pasture is exposed to deposition, 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.

600(207)

RETS Manual Revision 13 Page 174 .

7.S.10 Tritium-Stored Feed-Beef Dose Factor (mrem/year per pCi/m )

its) 1 RMTS = 10 10 DFLTao FfT Qf Uam [0.75(0.5/8)] fs exp{

{l~xp(-'XTtcsf)) {1-exp{-XTtcb))

~T tcsf XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTa o = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6 4).

= transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

~ 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.

'AT decay constant for tritium, seconds -1 (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.

600(207)

RETS Manual Revision 13 Page 175 7.8.)). Tritium-Fresh Leaf Ve etable Dose Factor

{mrem/year per pCi/m )

RVTF = 10 106 DFLTao ~0.75(0.5/H)J 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.

600(207)

RETS 'Manual Revision 13 Page 176 7.8.12 Tritium-Stored Ve etables Dose Factor (mrem/year per pCi/m )

l~xP(->Ttsv))

RVTS = 10 10 DFLTao [0.75(0.5/H)] USafg exP (-XTthc) ~

T sv 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.

3 ~ absolute humidity of the atmosphere, g/m 3 .

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

XT 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.

600(207)

RETS Nanual Revision 13 Page 177 Inhalation Dose Factors '.8.13 (mrem/year per pCi/m )

RZi DFAiao BRa 106 where:

DFAi iao = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem/pCi (Table 7.7).

BR = breathing rate for age group a, m3/year (Table 6.3).

10~ = conversion factor, pCilpCi.

7 8.14 Ground Plane Dose Factors (m2-mrem/year pe'r pCi/second)

RGi = DFGio (I/Xi) 106 8760 fl exp(-Xitb)]

where.

DFGio = dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem/hr per pCi/m 2 (Table 6.6).

decay constant of nuclide i, seconds (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).

600(207)

RETS Manual Revxsxon 13 Page 178

'.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 directions measured at 93m. Stability class D is assumed to persist during the entire period for elevated releases, except for the dose calculations described in Section 7.7 when all stability clas'ses 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 1979 are given in Table 7.3.

The wind speed classes that are used are as follows:

Number Mid oint (m/s 1 <0.3 0 13 2 0.3-0.6 0.45 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3. 3 2.88 6 3.4-5. 5 4 '5 7 5.6-8.2 6 91 8 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. .. ~ 1 G=7.

600(207)

RETS Manual Revision 13 Page 179 '

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 flak )

Air concentrations of nuclides at downwind locations are calculated using the following equation:

go p g(2/e)l/2 3 exp(-'Aix/u ) exp( h 2/2ozk2) 106 3.17E-08 (7.11) j=l =1 Zzkuj(2'/n) where:

->>joint relative frequency of occurrence of winds in windspeed class j, stability class expressed as a fraction.

k, blowing toward this exposure point, Qi = amount released of radionuclide i, Ci.

= fraction of radionuclide remaining in plume (Figure 7.3).

E zk = vertical dispersion coefficient for stability class k which includes a building wake adjustment,

= (ozk2 + cA/a')1 2, or = J3 azk, whichever is smaller (for ground level releases).

where a zkk 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).

x

= midpoint value of wind speed class interval

= downwind distance, m.'

j, m/s.

n = number of sectors, 16.

i = 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-08 = conversion factor, years per second.

600{207)

RETS'anual Revision 13 Page 180 7.9.2 Relative Concentration X/Q (sec/m )

Relative concentrations of nuclides at downwind locations are ca].culated using the following equation:

9 7 X/O = (2/~)'/2 fjk exp( h 2/2o k2) (7.12)

7. E j=l k=1 Ezk uj (2'/n) where:

f -k = joint relative frequency of occurrence of winds in windspeed class j, stability class k, expressed as a fraction.

blowing toward this exposure point, Ezk ~ vertical disPersion coefficient for stability class k which includes a building wake adjustment,

= (o k2 + cA/e)112 or ~ v'3 azk, 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&.5),

A is the minimum building cross-sectional area (2400 m2).

uj x

= midpoint value of wind speed class interval

= downwind distance, m.

j, m/s.

n = number of sectors, 16.

2'/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 D/~ = E 7. (7.13) j=l k=1 (2m/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 (from Figure 7.5). The choice of figures is governed by the effective release height calculation described in Section 7.9.4. A is used for effluent release heights that fall linear'nterpolation in between the given curves.

x = downwind distance, m.

n = number of sectors, 16.

2'/n = sector width at point of interest, m.

600(207)

1+

~ ~ e ~~~(cp

RETS Manual Revision 13 Page 181 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 W0 = 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.

h pr hs = physical height of release point, m.

h t ~ 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 < 1.

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 coef ficient, Et, is def ined by Et ~ 2.58 1.58(Wo/u) for 1 < Mo/u < 1.5 Et 0 3 0 06(Mo/u) for 1.5 < Wo/u < 5 600(207)

RETS Manual Revision 13 Page 182 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA GROUND LEVEL ELEVATED DISTANCE Elev above X/Q D/Q x/Q D/Q POINT from plant plant grade (s/m3) (1/m ) (s/m ) (1/m )

(m) (m)

Site Boundary 1525 N 7 1.60E-06 5.64E-09 NIA N/A Site Boundary 1300 NNE 4 7.88E-07 1.97E-09 N/A N/A Site Boundary 1250 NE 7 4.52E-07 1.56E-09 N/A N/A Site Boundary 1450 'NE 0 7.30E-07 2.92E-09 N/A N/A Site Boundary 1375 E 0 8.24E-07 4.04E-09 N/A NIA Site Boundary 1575 ESE 0 4.56EW7 3.28E-09 N/A N/A Site Boundary 5600 SE -6 7. 61EM8 3.63E-10 N/A N/A Site Boundary 2875 SSE 4.86E-07 1.77E-09 N/A N/A Site Boundary 2550 S -6 8.27E-07 2.24E-09 N/A N/A Site Boundary 2425 SSW -6 1.08E-06 2.92E-09 N/A N/A Site Boundary 2300 SW -6 6.87E-07 1.75E-09 N/A N/A Site Boundary 2500 WSW -6 6.38E-07 1.14E-09 N/A N/A Site Boundary 2550 W -6 6. 70EM7 1.25E-09 N/A N/A Site Boundary 3325 WNW -6 3.69E-07 9.07E-10 N/A N/A Site Boundary 2275 NW -6 1.69E-06 4.92E&9 N/A N/A Site Boundary 1650 NNW -6 1.84E-06 5.29E-09 N/A N/A Air Dose Point 6100 NW <<6 N/A N/A 2.08E-08 4 '5E-10 Garden 1830 NNW 34 1.57E>>06 4.46E-09 N/A 1 ~ 13E-09 Garden 4437 E 19 N/A N/A 9.50E-09 N/A Milk Cow 8045 N 34 1.47E-07 3.16E-10 N/A 2.30E-10 Milk Cow 10975 HNW 34 NIA N!A 1.69E-OS N/A NOTE: For quarterly dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

600(207)

0 RETS Manual Revision 13 Page 183 7.2 'able EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN Buildin Vents {Ci/ r/Unit) Stack {Ci/ r/Unit Reactor Radvaste Turbine Gland Complex Building Building Seal and

~jsoeo e Vent Vent Vent ~Off as MVP Kr-85m 6E+0 c 1 2E+0 1.66E+4 O.OE+0 Kr-85 6.3E+2 Kr-87 6E+0 c 1 9.5E+1 7.47E+2 O.OK+0 Kr-88 9E+0 < 1 1.02E+2 1.35E+4 O.OE+0 Kr-89 lE+0 3.4E+1 5.03E+2 4.10E+3 O.OK+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 2.94K+2 5.81E+2 9.47E+4 3.0E+2 Xe-135m 1.11E+2 6.67E+2 4.64E+2 9 '7E+2 0.0E+0 Xe-135 1.73E+2 3.28E+2 6.72E+2 5.99E+2 2.0E+2 Xe-137 7.8K+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-l 5.0E-2 1.79E-l 4.69E-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 'E-3 1.45E-2 I-135 I 5.94E-1 5.0E-2 1.23E-1 3.23E-2 6.71E-2 I-131 0 3.16E-2 2.9E-2 6.5E-3 3.32E-2 2.74E-1 I-132 0 3.16E-1 2.9E-l 7.44E-2 3.80E-1 3.14K+0 I-133 0 1.58E-1 1.45E-l 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-l 5.13E-2 2.61E-1 2.16K+0 Cr-51 3E-3 9E-4 lE-3 lE-4 0.0E+0 Mn-54 3E-3 5E-3 2E-3 4E-5 O.OE+0 Co-58 2E-3 4EW 9E-5 2E-5 0.0E+0 Fe-59 1E-4 8E-4 4E-4 2E-4 0.0E+0 Co-60 3E-2 6E-3 3E-3 IE-5 O.OE+0 Zn>>65 3E-3 2E-4 4E-4 9E-5 O.OE+0 Sr-89 lE-2 3E-.l O.OK+0 Sr-90 2E-3 4E-3 O.OK+0 Nb-95 3E-4 2E-4 9E-6 8E-5 O.OE+0 Zr-95 1E-4 1E-4 8E-6 8E-5 0.0E+0 Ru-103 3E-5 1E-4 2E-4 1E-4 0.0E+0 Ag-110m 7E-6 0 OE+0 Sb-124 3E-5 3E-4 6E-5 8E-5 0.0K+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 0.0E+0 Ba-140 4E-3 5E-4 2E-2 8E-3 O.0K+0 Ce-141 4E-4 2E-4 2E-3 2E-5 O.OK+0 Ce-144 5E-6 4E-6 O.OE+0 Ar-41 2.5E+1 -OE+0 OE+0 OE+0 O.OE+0 C-14 OK+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.

600(207)

RETS'anual Revision 13 Page 184 Table 7.3 (1 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T< -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5 7.5>> 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.0 0.04 0.12 0.05 0.0 0.0 0. 21 NNE 0.0 0.0 0 0 0.05 0.19 0.10 0.0 0 0 0.34 NE 0.0 0.0 0.0 0.04 0.06 0.0 0.0 0.0 0.10 ENE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 E 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0 01 ESE 0.0 0.01 0.11 0 17 0.02 0.0 0.0 0.0 0.31 SE 0.0 0.03 ~

1.11 0 40 0.02 -0.0 0.0 0.0 1.56 SSE 0.0 0.04 0 52 0 10 0 02 0 0 0.0 0 0 0.68 S 0.0 0.01 0.38 0.11 0.04 0.0 0.0 0 0 0.54 SSW 0.0 0.0 0.04 0.05 0.01 0.0 0.0 0 0 0.10 SW 0.0 0.0 0.05 0.04 0.0 0.0 0.0 0.0 0.09 WSW 0.0 0.0 0.04 0 07 0.04 0.0 0.0 0.0 0.15 W 0.0 0.0 0.01 0.05 0.05 0.01 0.0 0 0 0.12 WNW 0.0 0.0 0.02 0.03 0.09 0.06 0.0 0.0 0 20*

NW 0.0 0.0 0.0 0.02 0.17 0.11 0.0 0 0 0.30 NNW 0.0 0.0 0.01 0.01 0.06 0.09 0.02 0.0 0.19 Sub-total 0.0 0.09 2.29 1 19 0.90 0.42 0.02 0~0 4.91 Total hours of valid stability observations - 25935 Total hours of Stability Class A - 1262 Total hours of valid wind direction-wind speed-Stability Class A- 1259 Total hours calm 0 All columns and calm total 100 percent of joint valid observations 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 = 6.8 mph 600(207)

RETS Manual Revision 13 Page 185 Table 7.3 (2 of 22)

JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Stability Class B (-1.9 < Delta-T< -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Mind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-1.4 3.4 5 ' 7.4 12.4 18.4 24.4 >24.5 Total NN 0.0 0.0 0.05 0.09 0.30 0.04 0.01 0.0 0.49 NNE 0.0 0.0 0.05 0 07 0.27 0.05 0.0 0.0 0.44 NE 0.0 0.0 0.04 0 02 0.09 0.01 0.0 0.0 0.16 ENE 0.0 0.01 0.01 0.01 0.01 0.0 0.0 0.0 0.04 E 0.0 0.0 0.02 0 01 0.0 0.0 0.0 0.0 0-03 ESE 0.0 0.02 0.10 0 04 0.0 0.0 0.0 0.0 '.16 SE 0.0 0.13 0.64 0.09 0.02 0.0 0.0 0.0 0.88 SSE 0.0 0.09 0.31 0 '2 0.01 0.0 0.0 0.0 0.43 S 0.0 0.05 0.42 0.07 0.02 0.0 0.0 0.0 0.56 SSM 0.0 0.02 0 07 0.01 0.0 0.0 0.0 0.0 0.10 SW 0.0 0.0 0 17 0.02 0.0 0.0 0.0 0.0 0.19 MSM 0.0 0.0 0 11 0 13 0.05 0.01 0.0 0.0 0.30 W 0.0 0.02 0.04 0.17 0.17 0.03 0 0 0.0 0.43 MNM 0.0 0.0 0.07 0.11 0.23 0.08 '0.04 0.0 0.53 NW 0.0 0.0 0.01 0.07 0.27 0.13 0.01 0.0 0.49 NNM 0.0 0.0 0 0 0.07 0.19 0.12 0.0 0.0 0.38 Sub-total 0.0 0.34 2.11 1 00 1.63 0.47 0.06 0.0 5.61 Total hours of valid stability observations 25935 Total hours of Stability Class B 1445 Total hours of valid wind direction-wind speed-Stability Class B - 1440 Total hours calm - 0 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta<<T measured between 10.03 and 45.30 meters Mind speed and direction measured at the 10.42 meter level Mean wind speed = 7.2 mph 600(207)

RETS Manual Revision 13 Page 186 Table 7 3 (3 of 22)

JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Stability Class C (-1.7 < Delta-T< -1.5 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Mind Speed {mph) 0.6- . 1.5- 3.5- 5.5- 7 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.01 0.08 0.11 0.21 0 02 0.0 0.0 0.43 NNE 0.0 0.01 0.07 0.09 0.17 0."20 0.0 0.0 0.36 NE 0.0 0.0 0.03 0.08 0.05 0-0 0.0 0.0 0.16 ENE 0.0 0.0 0.02 0.02 0.0 0.0 0.0 0.0 0.04 E 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.05 ESE 0.0 0.01 0.05 0.02 0.0 0.0 0.0 0.0 0.08 SE 0.0 0,17 0.29 0.09 0.01 0.0 0.0 0.0 0.56 SSE 0.0 0.12 0.17 0.04 0.01 0.0 0.0 0.0 0.34 S 0.0 0.11 0.25 0.04 0.02 0.0 0.0 0.0 0.42 SSM 0.0 0.03 0.06 0.01 0.0 0.0 0.0 0.0 0.10 SM 0.0 0.03 0.12 0.03 0.01 0.0 0.0 0.0 0.19 WSW 0.0 0.0 0.11 0.07 0-07 0.0 0.0 0.0 0.25 W 0.0 0.0 0.05 0.12 0.10 0.02 0.01 0.0 0.30 WNM 0.0 0.01 0.12 0.13 0.17 0.07 0.04 0.0 0.54 NM 0.0 0.0 0.05 0.09 0.22 0.10 0.01 0.0 0.47 NNM 0.0 0.0 0.02 0.08 0.18 0.10 0.0 0.0 0.38 Sub-total 0.0 0.50 1.52 1.04 1.22 0.33 0.06 0.0 4.67 Total hours of valid stability observations 25935 Total hours of Stability Class C 1202 Total hours of valid wind direction-wind speed-Stability Class C- 1197 Total hours calm 0 All columns and calm total 100 percent of joint valid observations 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 = 7.0 mph 600(207)

RETS 'Manual Revision 13 Page 187 .

Table 7.3 {4 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stability Class D (-1.5 < Delta-T< -0.5 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Mind Speed {mph) 0.6- 1.5- 3 5- 5.5- 7.5- 12.5- 18.5-1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.19 0.41 0.53 1.00 0.37 0.01 0.0 2.51 NNE 0.01 0.20 0 56 0.58 1.18 0.18 0.01 0.0 2.72 NE 0.01 0.12 0 38 0.43 0.52 0.01 0.0 0.0 1.47 ENE 0.0 0.26 0.23 0.15 0.05 0.01 0.0 0.0 0.70 E 0.0 0.20 0.31 0.17 0.05 0.0 0.0 0 0 0.73 ESE 0.0 0.24 0.51 0.30 0.08 0.0 0.0 0.0 1.13 SE 0.02 1.14 1.31 0.83 0.26 0.0 0.0 0.0 3.58 SSE 0.01 0.99 0 '9 0-26 0.11 0.02 0.0 0.0 2.38 S 0.0 0.92 1.17 0.34 0.17 0.0 0.0 0.0 2.60 SSM 0.0 0.45 0 29 0.08 0.04 0.0 0.0 0.0 0.86 SW 0.0 0.24 0.29 0.09 0.02 0.01 0.0 0.0 0.65 WSM 0.0 0.32 0.70 0.29 0.33 0.11 0.0 0.0 1.75 W 0.0 0.18 0.55 0.62 0.63 0.22 0.03 0.0 2.23 WNW 0.0 0.0 0.13 0.39 0.42 0.38 1.10 0.82 0 '2 0.01 3.09 NM 0.04 0.28 1.01 0.87 0.14 0.02 2.74 NNM 0.0 0.13 0.40 0.55 1.54 0.74 0.05 0.0 3 41 Sub-total 0.05 5.77 8.77 6.02 8.09 3.36 0.46 0.03 32.55 Total hours of valid stability observations - 25935 Total hours of Stability Class D 8438 Total hours of valid wind direction-wind speed-Stability Class D 8341 Total hours calm 1 All columns and calm total 100 percent of joint valid observations 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 " -7.1 mph 600(207)

RETS Manual Revision 13 Page 188 Table 7.3 (5 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class E (-0.5 < Delta-T< 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.04 0.47 0.54 0.43 0.41 0.05 0.01 0.0 1.95 NNE 0.05 0.61 O. 74 0.55 0.47 0.04 0.0 0.0 2.46 NE 0.05 0.57 0.63 0.42 0.27 0.02 0.0 0.0 1.96 ENE 0.05 0.71 0.45 0 17 0.08 0.02 0.0 0.0 1.48 E 0.04 0.61 0.74 0.16 0.07 0.0 0.0 0 0 1.62 ESE 0.03 0.76 1.01 0 '3 0.16 0.01 0.0 0 0 2.50 SE O.ll 2.04 1.75 0.92 0.55 0.02 0.0 0.0 5.39 SSE 0.07 1.16 0.78 0.48 0.33 0.04 0.0 0.0 2.86 S 0.05 1.03 0.74 0.44 0.63 0.14 0.01 0.0 3.04 SSW 0.02 0.52 0.14 0.08 0.06 0.01 0.0 0.0 0.83 SW 0.04 0.30 0.07 0.02 0.03 0.0 0.0 0.0 0.46 WSW 0.01 0.53 0.60 0.14 0.11 0.04 0.0 0.0 1.43 W 0.02 0.37 0.77 0.42 0.27 0.04 0 0 0.0 1.89 WNW 0.03 0.15 0.13 0.11 0.22 0.09 0.02 0.0 0.75 NW 0.02 0.17 0.20 0.14 0.25 0.09 0.02 0.0 0.89 NNW 0.05 0.41 0.48 0.54 0.59 0.09 0.01 0.0 2.17 Sub-total 0.68 10.41 9 77 5 55 4.50 0.70 0.07 0 0 31-68 Total hours of valid stability observations - 25935 Total hours of Stability Class E 8264 Total hours of valid wind direction-wind speed-Stability Class E- 8098 Total hours calm 3 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 lan 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 = 5.0 mph 600(207)

I 0

RETS Manual Revision 13 Page 189 Table 7.3 (6 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class F (1.5 < Delta-T< 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3 5- 5.5- 7.5- 12.5- 18.5-1.4 3.4 5,4 7.4 12.4 18.4 24.4 >24.5 Total N 0.05 0.36 0.52 0 '8 0.06 0.0 0.0 0.0 1.27 NNE 0.05 0.51 0.66 0.34 0.11 0.0 O.D 0.0 1.67 NE 0.07 0.34 0.27 0 18 0.01 0.0 0.0 0.0 0.87 ENE 0.03 0.53 0.33 0.05 0.0 0.0 0 0 0.0 0.94 E 0.01 0.59 0.52 0.03 0 0 0.0 0.0 0.0 1 15 ESE 0-0 0.52 0 22 0.0 0.0 0.0 0.0 0.0 0. 74 SE 0.09 0.97 0.48 0.17 0 13 0.01 0.0 0.0 1.85 SSE 0.05 0.54 0.34 0.17 0. 25 0.02 0 Ol 0.0 1.38 S 0.03 0,29 0.18 0.20 0 27 0.01 0.0 0.0 D.98 SSM 0.03 0.13 0.03 D.D 0 Dl 0.0 0-0 0.0 0.20 SW 0.0 0.09 0.03 0.0 0 0 0.0 0.0 0.0 0.12 WSM 0.0 0.09 0.07 0 0 0.0 0.0 0.0 0.0 0.16 W 0.02 0.09 0.06 0.0 0 Ol 0.0 0.0 0.0 0.18 WNM 0.01 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.10 NW 0.01 0.08 0.04 0 01 0.0 0.0 0.0 0.0 0.14 NNM 0.05 0.27 0.27 0 16 0.05 0.0 0.0 0.0 0.80 Sub-total 0.50 5.48 , 4 03 1 59 0.90 0.04 0.01 0 0 12.55 Total hours of valid stability observations - 25935 Total hours of Stability Class F 3268 Total hours of valid wind direction-wind speed-Stability Class F 3223 Total hours calm 2 All columns and calm total 100 percent of )oint valid observations Meteorological facility: located 1.3 hn ESE of BFN Stabili.ty based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 3.0.42 meter level Mean wind speed = 4.0 mph 600(207)

RETS Manual Revision 13 Page 190 7.3 (7 of 22) 'able JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Mind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-1.4 3.4 5 ' 7.4 12.4 18.4 24.4 >24.5 Total N 0.07 0.76 0.32 0.02 0.0 0.0- 0.0 0.0 1.17 NNE 0.05 0.83 0.51 0-18 0.02 0.0 0.0 0.0 1.59 NE 0.04 0.34 0.12 0.02 0.0 0.0 0.0 0.0 0.52 ENE 0.04 0.48 0.18 0.02 0.0 0.0 0.0 0.0 0.72 E 0.02 0.52 0.34 0.0 0.0 0.0 0.0 0.0 0.88 ESE 0.01 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.08 0.43 ~

0.09 0.04 0.03 0.0 0.0 0.0 0.67 SSE 0.03 0.44 0.31 0.16 0.08 0.0 0.0 0.0 1.02 S 0.05 0.09 0.12 0.10 0.04 0.0 0.0 0.0 0.40 SSW 0.05 0.05 0.01 0.0 0.0 0.0 0.0 0.0 0.11 SM 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 WSM 0.02 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.04 W 0.01 0.01 0 0 0.0 0.0 0.0 0.0 0.0 0.02 WNW 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.03 NM 0.04 0.04 0.0 0.0 0.0 0.0 0.0 0.0 0.08 NNM 0.05 0.23 0.12 0.03 0.0 0.0 0.0 0.0 0.43 Sub-total 0.57 4.45 2.13 0.57 0.17 0.0 0 0 0.0 7.89 Total hours of valid stability observations 25935 Total hours of Stability Class G 2056 Total hours of valid wind direction-wind speed-Stability Class G- 2019 Total hours calm 4 All columns and calm total 100 percent of joint valid observations 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 = 3.2 mph 600(207)

RETS Manual Revision 13 Page 191 7.3 (8 of 22) 'able JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Disregarding Stabili ty Class BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-1.4 3.4 5 ~4 7.4 12.4 18.4 24.4 >24.5 Total N 0.02 O.l.9 0.38 0.64 2.07 2.47 0.61 0 06 6.44 NNE 0.0 0.13 0.33 0.60 2.46 2.69 0.50 0.04 6. 75 NE 0.0 0.12 0.35 0.64 2.16 1.85 0.58 0.02 5.72 ENE 0.02 0.14 0.32 0.36 1.15 0.95 0.34 0.04 3.32 E 0.0 0.22 0.47 0.45 0.99 0.43 0.08 0.01 2.65 ESE 0.01 0 23 0.53 0.66 1.79 1.63 0.42 0.09 5.36 SE 0.02 0.36 1.26 1.36 3.25 '3.20 1 54 0.69 11.68 SSE 0.01 0.38 1.20 1.22 2.97 2.59 1.16 0.59 10.12 S 0.02 0.40 0 90 1.05 2.53 2.40 1.03 0.43 8.76 SSW 0.0 0.31 0.65 0.69 1.73 1.77 0.73 0.19 6.07 SW 0.02 0-38 0.66 0.69 1.55 1.62 0.50 0.14 5.56 WSW 0.01 0.26 0.69 0.68 1.15 1.05 0 36 0.17 4.37 W 0.02 0.20 0.66 0.81 1.76 1.04 0.42 0 '5 5.26 WNW 0.01 0.17 0.46 0.69 2.03 1.54 0 '6 0.30 5 '6 NW 0.02 0 19 0.49 0.70 1.80 2.01 0.96 0.28 6.45 NNW 0.01 0.22 0.28 0.41 1.66 2.13 0.70 0.13 5.54 Sub-total 0.19 3.90 9.63 11.65 31.05 29.37 10.69 3.53 100.01 Total hours of valid wind observations 25784 Total hours of observations 26280 Recoverability percentage - 98.1 Total hours calm 2 All columns and calm total 100 percent of joint valid observations Meteorological facility: located 1.3 lan ESE of BFN

~

Wind speed and direction measured at the 92.63 meter level Mean wind speed ~ 12.0 mph 600(207)

RETS Manual Revision 13 Page 192 7.3 (9 of 22) 'able JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T< -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7 12.5- 18.5-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 0.02 0.01 0.0 0.0 0.03 NNE 0.0 0.0 0.0 0.0 0.0 0.03 0.02 0.0 0.0 0.05 NE 0.0 0.0 0.0 0.0 0.0 0.01 0 0 0.0 0.0 0.01 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 0.02 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.0 0.05 0.04 0.01 0.0 0.0 0.0 0.10 SSE 0.0 0.0 0.0 0.03 0.02 0.01 0.0 0.0 0.0 0.06 S 0.0 0.0 0.0 0.02 0.02 0.01 0.0 0.0 0.0 0.05 SSV 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 WSW W

0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

'.0 0.0 0.01 0.01 0.0 0.01 0.0 0.0 0.0 0.0 0.02 0.01 WNW 0.02 NW 0.0 0.0 0.0 0.0 0.0 0.02 0.02 0.0 0.0 0.04 NNW 0.0 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.0 0.05 Sub-total 0.0 0.0 0.0 0.10 0.12 0.15 0.08 0.02 0.0 0.47 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class A 133.1 Total hours of ground level Stability Class A 127 5 Meteorological facility: located 1 3 hn ESE of BFÃ 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 600(207)

RETS 'Manual Revision 13 Page 193 7.3 (10 of 22) 'able SPI,ZT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class B (-1.9 < Delta T c -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4'4.4 >24.5 Total N 0.0 0.0 0.0 0.0 0.01 0.05 0.01 0.01 0 0 0.08 NNE 0.0 0.0 0.0 0.0 0.01 0.05 0.01 0.0 0.0 0.07 NE 0.0 0.0 0.0 0.0 0.0 0.01 0 0 0.0 0.0 O.O1 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 0.01 0.0 0 0 0.0 0.0 0.01 SE 0.0 0.0 0.0 0.02 0.02 0.01 0.0 0.0 0.0 0.05 SSE 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.02 S 0.0 0.0 0.0 0.02 0.01 0.01 0.0 0.0 0.0 0.04 SSW 0.0 0.0 0.0 0.0 0.0 0.0 0 0 0.0 O.D 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0~0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.02 0.01 0 0 0.0 0 0 0.03 W 0 0 0.0 0.0 0.0 O.D1 0.02 0.02 0 01 o.o o.o6 WNW 0.0 0.0 0.0 0.0 D.ol 0.03 0.02 0.03 0.0 0.09 NW 0.0 0.0 0.0 0.0 0.01 0.04 0 03 0.0 0.0 0.08 NNW 0.0 0.0 0.0 0.0 0.0 0.03 0 04 0.0 0.0 0.07 Sub>>

total 0.0 0.0 0.0 0.05 0.12 0.26 0.13 0.05 0.0 0.61 Total hours of valid observations - 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class B 185.1 Total hours of ground level Stability Class B 163.4 Meteorological facility: located 1.3 hn ESE of BBl 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 600(207)

RETS Manual Revision 13 Page 194 Table 7.3 (11 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class C (-1.7 < Delta-Tc -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5 7.5- 12.5- 18.5-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 0.01 0.03 0.0 0.0 0.0 0.04 NNE 0.0 0.0 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.03 NE 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 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 00 00 '00 00 0.0 0.0 SE 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 S 0.0 0.0 0.0 0.01 0.01 0 01 0.0 0.0 0.0 0.03 SSW 0.0 0.0 0.0 0.0 0 0 0.0 0.0 0.0 0.0 0.0 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.01 0 01 0.01 0.01 0.0 0.04 WNW 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.03 0.0 0.08 NW 0.0 0.0 0.0 0.0 0.01 0 03 0.02 0.01 0.0 0.07 NNW 0.0 0.0 0.0 0.0 0.01 0.02 0.03 0.0 0.0 0.06 Sub-total 0.0 0.0 0.0 0.03 0.11 0.17 0.08 0.05 0.0 0.44 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class C - 259.0 Total hours of ground level Stability Class C- 106.3 Meteorological facility: located 1.3 tun ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Effluent velocity = 12.60 m/s 600(207)

RETS Manual Revision 13 Page 195'able 7.3 (12 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class D (-1.5 < Delta-T< -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph)

0. 6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5<<

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 0.01 0.04 0.15 0.10 0.01 0 0 0.31 NNE 0.0 0.0 0.0 0.01 0.05 0.18 0.05 0.01 0.0 0.30 NE 0.0 0.0 0.0 0.01 0.04 0.08 0.0 0.0 0.0 0.13 ENE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 0.0 0.01 0.02 0.01 0.0 0.0 0.0 E

ESE 0.0 0.0 0.0 0 0 0.0 0.03 0.04 0.13 0.01 0.06

'.0 0.0 0.0 0.0 0.04 0.08 SE 0.0 0.0 0.01 0 11 0.0 0.0 0.31 SSE 0.0 0.0 0 02 0 09 0.06 0.05 0.02 0.0 0.0 0.24 S 0.0 0.0 0.02 0.09 0.06 0.06 0.0 0.0 0.0 0.23 SSW 0.0 0.0 0.01 0.02 0.01 0.01 0.0 0.0 0.0 0.05 SW 0.0 0.0 0.0 0 01 0.01 0.0 0.01 0.0 0.0 0.03 WSW 0.0 0.0 0.0 0.03 0.03 0.06 0.04 0.0 0.0 0.16 W 0.0 0.0 0.0 0 02 0.06 0.10 0 '9 0.02 0.0 0.29 WNW 0.0 0.0 0 0 0 0 0.03 0.16 0.19 0.14 0.01 0.53 NW 0.0 0.0 0.0 0 0 0.03 0.15 0.23 0.10 0.02 0-53 NNW 0.0 0.0 0.0 0.01 0.05 0.25 0.19 0.04 0.0 0.54 Sub-total 0.0 0.0 0.6 0.46 0.67 1 34 '.92 0.32 0.03 3.80 Total hours of valid observations 25482.0 Total hours of ground level release - 2832.4 Total hours of Stability Class D - 13904.1 Total hours of ground level Stability Class D 968 6 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 Effluent velocity = 12.60 m/s 600{207)

RETS Manual Revision 13 Page 196 7.3 (13 of 22) 'able SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class E (-0.5<Delta-T< 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 1 of 2 ground level release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-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 0.04 0 06 0.07 0.02 0.01 0.0 0.20 NNE 0.0 0.0 0.01 0.06 0 07 0 F 08 0.02 0.0 0.0 0.24 NE 0.0 0.0 0.01 0 06 0.06 0.05 0.01 0.0 0.0 0.19 ENE 0.0 0.0 0.02 0.04 0 03 0.01 0.01 0.0 0.0 O.ll 0.0 0.02 0.07 0. 02 0.01 0.0 0.0 0.0 E

ESE 0.0 0.0 0.0 4.02 0.08 0 07 0.03 '.0 0.0 0.0 0.12 0.20 SE 0.0 0.0 0.08 0.22 0 16 0.18 0.02 0.0 0.0 0.66 SSE 0.0 0.0 0.05 0.12 0.12 0.19 0.04 0.0 0.0 0.52 S 0.0 0.0 0.06 0 10 0.09 0.27 0.13 0.01 0.0 0.66 SSW 0.0 0.0 0.02 0.02 0 02 0.02 0.01 0.0 0.0 0.09 SW 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.0 0 02 WSW 0.0 0.0 0.01 0.05 0 02 0.03 0.02 0.0 0.0 0.13 W 0.0 0.0 0.01 0.06 0 05 0.05 0.01 0.0 0.0 0.18 WNW 0.0 0.0 0.0 0.01 0 Ol 0.04 0.02 0.01 0.0 0.09 NW 0.0 0.0 0.0 0.01 0 02 0.04 0.03 0 01 0.0 O.ll NNW 0.0 0.0 0.0 0.03 0 07 0.10 0.02 0.01 0.0 0.23 Sub-total 0.0 0.0 0.32 0.97 0 87 1.18 0.36 0.05 0.0 3.75 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class E - 7920.6 Total hours of ground level Stability Class E 957 '

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 600(207)

0 RETS Manual Revision 13 Page 197 Table 7.3 (14 of 22) .

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stability Class F (1.5 < Delta-T( 4.0 degrees C per 100 m)

Part 1 of 2 ground level release mode BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3 5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0 01 0.06 0.04 0.01 0.0 0.0 0.0 0.12 NNE 0.0 0.0 0.01 0.08 0.05 0.02 0.0 0.0 0.0 0.16 NE 0.0 0.0 0.01 0.03 0.03 0.0 0.0 0.0 0.0 0.07 ENE 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.0 0 0 0.06 E 0.0 0.0 0.01 0.04 0.0 0.0 0.0 0.0 0.0 0.05 ESE 0.0 0.0 0.02 0.02 0.0 0.0 0.0 0.0 0.0 0.04 SE 0.0 0.0 0.05 0.06 0.03 0.06 0.01 0.0 0.0 0.21 SSE 0.0 0.0 0 04 0.06 0.05 0.18 0.02 0.01 0.0 0.36 S 0.0 0.0 0.02 0.03 0.04 0.11 0.01 0.0 0.0 0.21 SSW 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.01 0.03 0.02 0.01 0.0 0.0 0.0 0.07 Sub-total 0.0 0.0 0.21 0.45 0.27 0.39 ,0.04 0.01 0.0 1.37 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class F 2385.0 Total hours of ground level Stability Class F 357.0 Meteorological facility: located 1;3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters

~ Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 600(207)

RETS Manual Revision 13 Page 198 7.3 (15 of 22) 'able SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)

Part 1 of 2 ground level release mode BROMNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5<< 12.5- 18.5-3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.02 0.04 0.0 0.0 0.0 0.0 0 0 0.06 NNE 0.0 0.0 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.11 NE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ENE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 E

ESE 0.0 0.0 0.01 0.0 0.0 0.0 '.0 0.0 0.0 0.01 SE 0.0 0.0 0 03 0.01 0.01 0.02 0.0 0.0 0 0 0.07 SSE 0.0 0.0 0.04 0.05 0.03 0.06 0.0 0.0 0.0 0.18 S 0.0 0.0 0 F 01 0.02 0.02 0.01 0.0 0.0 0.0 0.06 SSM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSM 0 0 0 0 0 0 0 0 0.0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 MNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNM 0. 0 0. 0 0.01 0.01 0.08 0.0 0.0 0.0 0.0 0.02 Sub-total 0.0 0.0 0 17 0.22 0.09 0.09 0.0 0.0 0.0 0.57 Total hours of valid observations 25482.0 Total hours of ground level release 2832.4 Total hours of Stability Class G 694.7 Total hours of ground level Stability Class G 151.7 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Mind speed and direction measured at the 10.42 meter level Effluent velocity = 12.60 m/s 600(207)

RETS Manual Revision .13 Page 199 Table 7.3 (16 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class A (Delta-T< -1.9 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-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 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 0.01 0.0 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WSW 0.0 0.0 0.0 0.0 0 0 0.0 0.0 0.0 0.0 0.0 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0 0 0.0 0.0 0.0 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 0.0 0.0 0.0 0.0 0.0 Sub-total 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class A 133.1 Total hours of elevated Stability Class A 5 '

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 600(207)

RETS Manual Revision .13 Page 200 Table 7.3 (17 of 22)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class B (-1.9 ( Delta-T< -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-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 0.0 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 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 0.01 0.01 0-0 0.0 0 0 0.0 0.0 0.02 SSE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 0 0.0 0.0 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 0.0 0.0 0.01 0.0 0.0 0.0 0.01 SW 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.01 WSW 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.02 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0~0 0.0 0.0 0.0 0.0 0.0 0.0 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 0 0.0 0.0 0.0 0.0 Sub-total 0.0 0 0 0.01 0.01 0.01 0.03 0.0 0.0 0.0 0.06 Total hours of valid observations 25482.0 Total hours of elevated releases - 22649.6 Total hours of Stability Class B 185.1 Total hours of elevated stability class B 21.8 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 600(207)

RETS Manual Revision,13 Page 201 Table 7 3 (18 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class C (-1.7 < Delta-T( -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Calm 0.6-1.4 1.5-3.4 3 '-

5.4 Wind Speed 5.5-7.4 (mph) 7.5- 12.5- 18.5-12.4 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 0.0 0.01 0.0 0.0 0.0 0.0 0.01 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 0.01 0.01 0.01 0.0 0.0 0.0 0.03 SE 0.0 0.0 0.02 0.05 0.01 0 0 0.0 0.0 0.0 0.08 SSE 0.0 0.0 0.0 0.04 0.0 0.0 0 0 0.0 0.0 0.04 S 0.0 0.0 0.01 0.01 0.0 0.0 0 0 0.0 0.0 0.02 SSW O.D 0.0 0.0 0.02 0.02 0 01 0.0 0.0 0.0 0.05 SW 0.0 0.0 0.0 0.05 0.05 0.02 0.01 0.0 0.0 0.13 WSW 0.0 0.0 0.0 0.0 0.03 0.05 0 Dl 0.0 0.0 0.09 W 0.0 0.0 0.0 0.0 0.01 0.03 0 02 0.02 0.0 0.08 WNW 0.0 0.0 0.0 0.0 0.0 0.02 0.02 0.0 0.0 0.04 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.01 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 0.03 0.18 0 14 0.14 '.07 0.02 0.0 0.58 Total hours of valid observations 25482.0 Total hours of elevated releases - 22649.6 Total hours of Stability Class C << 259.0 Total hours of elevated Stability Class C 152.7 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 600(207)

i RETS Manual Revision 13 Page 202 7.3 (19 of 22) 'able JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class D (-1.5 < Delta-T< W.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3,4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.12 0.40 0.62 1.49 0.87 0 12 0.0 3.62 NNE 0.0 0.01 0.13 0.46 0.72 1.88 0.91 0.05 0.0 4.16 NE 0.0 0.0 0.09 0.36 0.48 1.04 0.14 0.02 0.0 2.13 ENE 0.0 0.01 0.11 0.24 0.23 0.23 0.04 0.01 0.0 0.87 E 0.0 0.01 0.10 0.20 0.28 0.25 0.05 0.01 0.0 0.90 ESE 0.0 0.01 0.22 0.52 0.68 1.07 '0.16 0.0 0.0 2.66 SE 0.0 0.01 0.67 1.66 0.89 1.75 0.84 0.16 0.01 5.99 SSE 0.0 0.01 0.48 0.90 0.63 1.49 1.08 0.26 0.02 4.87 S 0.0 0.0 0.34 0.99 0.67 0.99 0.93 0.33 0.02 4.27 SSW 0.0 0.01 0.20 0.52 0.37 0.69 0.34 0.11 0 0 2.24 SW 0.0 0.01 0.24 0.79 0.43 0.49 0 32 0.05 0.0 2.33 WSW 0.0 0.02 0.16 0.51 0.57 0.57 0.27 '.08 0.0 2.18 W 0.0 0.0 0.07 0.36 0.80 1.34 0.55 0.16 0.01 3.29 WNW 0.0 0.0 0.09 0.33 0.48 1.25 0.94 0.32 0.01 3.42 NW 0:0 0.0 0.07 0.36 0.55 1.40 1.44 0.37 0.01 4.20 NNW 0.0 0.0 0.09 0.29 0.53 1.36 1.15 0.19 0-0 3.61 Sub-total 0 0 0.10 3.18 8.89 8.93 17 29 10 03 2.24 0.08 50.74 Total hours of valid observations - 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class D - 13904.1 Total hours of elevated Stability Class D 12935.5 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 600(207)

RETS Manual Revision -13 Page 203 Table 7.3 (20 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class E (-0.5 ( Delta-T< 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3 4 5 4 7 4 12 4 18 4 24 4 >24 5 Total N 0.0 0.0 0.13 0.22 0.31 0.80 0.15 0.0 0.0 1.61 NNE 0.0 0.0 0.15 0.24 0.39 1.04 0.28 0.0 0.0 2.10 NE 0.0 0.01 O.ll 0.25 0.39 0.88 0.18 0.0 0.0 1.82 ENE 0.0 0.0 0.20 0.21 0.33 0.39 0.10 0.0 0.0 1.23 E 0.0 0.0 0.09 0.24 0.30 0.55 0.06 0.0 0.0 1.24 ESE 0.0 0.01 0.29 0.58 0.86 1.10 0.09 0.01 0.0 2.94 SE 0.0 0.02 0.41 1.04 1.02 1.37 0.55 0.08 0.01 4.50 SSE 0.0 0.01 0.23 0.60 0.54 0.87 0.59 0.14 0.01 2.99 S 0.0 0.01 0.14 0.49 0.32 0.70 0.34 0.05 0.0 2.05 SSW 0.0 0.0 0.11 0.28 0.30 0.48 0.19 0.01 0.0 1.37 SW 0.0 0.01 0.17 0.27 0.28 0.29 0.09 0.0 0.0 1.11 WSW 0.0 0.01 0.12 0.25 0.24 0.28 0.06 0.0 0.0 0.96 W 0.0 0.0 0.09 0.19 0.26 0.34 0.05 0.0 0.0 0.93 WNW 0.0 0.0 0.06 0.13 0.11 0.20 0.04 0.01 0.0 0.55 NW 0.0 0.0 0.09 0.14 0.13 0.31 0.08 0.0 0.0 0.75 NNW 0.0 0.0 0.12 0.21 0.16 0.52 0 '6 0.0 0.0 1.17 Sub-total 0.0 0.08 2.51 5.34 5.94 10.12 3.01 0.30 0.02 27.32 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class E 7920.9 Total hours of elevated Stability Class E 6962.9 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 600(207)

RETS Manual Revision,13 Page 204 Table 7.3 (21 of 22)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class F ( 1.5 ( Delta-T< 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7 5- 12 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.03 0.08 0.06 0.34 0.05 0.0 0.0 0.56 NNE 0.0 0.0 0.04 0.06 0 11 0.42 0.21 0.0 0.0 0.84 NE 0.0 0.0 0.04 0.10 0.15 0.40 0.12 0.0 0.0 0.81 ENE 0.0 0.0 0.04 0 11 0.11 0.29 0.07 0.0 0.0 0.62 E 0.0 0.0 0.03 0.07 0.11 0.32 , 0 02 0.0 0.0 0.55 ESE 0.0 0.0 0.13 0.26 0.24 0.24 0.0 0.0 0.0 0.87 SE 0.0 0.0 0.13 0.38 0.30 0.19 0.0 0.0 0.0 1.00 SSE 0.0 0.0 0.09 0.11 0.12 0.14 0.03 0.0 0.0 0.49 S 0.0 0.0 0.08 0.11 0.13 0.21 0.03 0.0 0.0 0.56 SSW 0.0 0.0 0.04 0.12 0.14 0.24 0.01 0.0 0.0 0.55 SW 0.0 0.0 0.04 0.09 0.10 0.06 0.0 0.0 0.0 0.29 WSW 0.0 0.0 0.03 0.07 0.06 0.05 0.0 0.0 0.0 0.21 W 0.0 0.01 0.04 0.04 0.05 0.04 0.0 0.0 0.0 0.18 WNW 0.0 0.0 0.02 0.04 0 01 0 F 01 0.0 0.0 0.0 0.08 NW 0.0 0.0 0.03 0.04 0.03 0.02 0.0 0.0 0.0 0.12 NNW 0.0 0.0 0.02 0.02 0.04 0.10 0.0 0.0 0.0 0.18 Sub-total 0.0 0.01 0.83 1.70 1.76 3.07 0.54 0.0 0.0 7.91 Total hours of valid observations 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class F 2385.0 Total hours of elevated Stability Class F - 2028.0 Meteorological facility: located 1.3 tun 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 600(207)

RETS Manual ~

Revision 13 Page 205 7.3 (22 of 22) 'able JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stability Class G (Delta-T> 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT Part 2 of 2 elevated release mode January 1, 1977 December 31, 1979 Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-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 '2 0.06 0.01 0.0 0.0 0.09 NNE 0.0 0.0 0.01 0.02 0.04 O.ll 0.04 0.0 0.0 0.22 NE 0.0 0.0 0.02 0.02 0.03 0.12 0.02 0.0 0.0 0.21 ENE 0.0 0.0 0.0 0.02 0 02 0.07 0.02 0.0 0.0 0.13 0.0 0.0 0.0 0.02 0.01 0 04 0.0 0.0 0-0 0.07 E

ESE 0.0 0.01 0.05 0.15 0.07 0.01 '.0 0.0 0.0 0.29 SE 0.0 0.0 0.12 0.20 0.13 0.04 0.0 0.0 0.0 0.49 SSE 0.0 0.0 0.03 '.06 0.06 0.02 0.0 0.0 0.0 0.17 S 0.0 0.0 0.02 0.07 0.06 0.01 0 ' 0.0 0.0 0.16 SSM 0.0 0.0 0.0 0.02 0 02 0.06 0.0 0.0 0.0 0.10 SW 0.0 0.0 0.01 0.01 0.03 0.02 0' 0.0 0.0 0.07 WSV 0.0 0.0 0.01 0.0 0.0 0 0 0.0 0.0 0.0 0.01 W 0.0 0.0 0.01 0.0 0.01 0.0 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.02 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 0.01 0.01 0.0 0.01 0.0 0.0 0.0 0.03 Sub-total 0.0 0.01 0.31 0.60 0.50 0 57 0.09 0.0 0.0 2.08 Total hours of valid observations - 25482.0 Total hours of elevated releases 22649.6 Total hours of Stability Class G 694.7 Total hours of elevated Stability Class G 543.1 Meteorological facility: located 1.3 hn 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 600(207)

RETS Manual Revision 13 Page 206 Table 7.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose" mrem/yr per pCi/m3 mrad/yr per pCi/m3 DFBi DFSi DF~i DFBi 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+01 1.95E+03 Kr-87 5.92E+03 9 73E+03 6 17E+03 1.03E+04 Kr-88 1.47K+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 9.15K+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 3.12K+03 7 11E+02 3.36E+03 7.39E+02 Xe-135 1.81K+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 Ar-41 8.84E+03 2 69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109, Table B-l.

600(207)

RETS Manual Revision 13 Page 207 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 600(207)

RETS Manual Revision 13 Page 208 Table 7.6 BFÃ 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 0 10 55 35 85 670 1515 2615 10660 3690 p 5 15 65 55 915 2990 2230 3125 3420 p 5 25 45 88 4180 14180 6625 5385 12625 p 15 50 40 70 1310 4990 9615 13860 5425 0 30 10 40 945 1910 73405 75125 4610 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 SSW 0 60 75 175 845 5895 1270 1490 2535 SM 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 600(207)

RETS Manual Revision 13 Page 209 Table 7.7 (1 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver t body thyroid kidney lung gi-lli H-3 1.58E-07 1.58E-07 1.58EW7 1.58EW7 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4. 26E&7 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E&6 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E&6 0.00E+00 O.OOE+00 O.OOE+00 1.08E-05 Cr-51 O.OOE+00 O.OOE+00 1 25EW8 7.44EW9 2 85EM9 1.80E-06 4.15E-07 Mn-54 O.OOE+00 4.95E-06 7 87E-07 O.OOE+00 1 23EW6 1.75E-04 9.67E-06 Mn-56 O.OOE+00 1.55E-10 2.29E-ll O.OOE+00 1.63E-10 1.18E-06 2.53E&6 Fe-55 3.07E-06 2.12E-06 4.93E-07 O.OOE+00 O.OOE+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 O.OOE+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 O.OOE+00 O.OOE+00 4.62E-05 3.93E-06 Co-58 O.OOE+00 1.98E-07 2.59E-O7 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 O.OOE+00 1.44E-06 1.85E-06 O.OOE+00 O.OOE+00 7.46E-04 3.56E-05 Ni-63 5 40E-05 3 '3E-06 1.81E-06 O.OOE+00 0.00E+00 2.23E-05 1 ~ 67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-ll 0.00E+00 O.OOE+00 7.00E-07 1.54E-06 Cu-64 O.OOE+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&6 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.6SE-13 O.OOE+00 5.27E-12 1.15E-07 2.04E-09 Zn<<69m 1.02E-09 2.45E-09 2.24E<<10 O.OOE+00 1.48E&9 2.38E-06 1.71E-05 Br-82 O.OOE+00 O.OOE+00 1.69E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.3OE-06 Br-83 O.OOE+00 0 00E+00 3.01E-08 0.00E+00 O.OOE+00 O.OOE+00 2. 90EW8 Br-84 O.OOE+00 0.00E+00 3. 91E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.05E-13 Br-85 O.OOE+00 0 ~ OOE+00 1 ~ 60E-09 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 0 OOE+00 1 ~ 69E-05 7.37E-O6 O.OOE+00 O.OOE+00 O.OOE+00 2.08E-06 Rb-88 O.OOE+00 4.84E-08 2.41E-08 O.OOE+00 O.OOE+00 O.OOE+00 4.18E-19 Rb-89 O.OOE+00 3.20E-08 2.12E-08 0.00E+00 O.OOE+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 O.OOE+00 O.OOE+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. 39EW5 Sr-92 8.43E-10 0.00E+00 3.64E-11 O.OOE+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 O.OOE+00 7.01E-09 O.OOE+00 0.00EWO 2.12E-05 6.32E-05 Y-91m '3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40EW7 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0 ~ OOE+00 O.OOE+00 2.13E-04 4.81E-05 Y-92 1.29E-09 O.OOE+00 3.77E-11 O.OOE+00 0.00E+00 l. 96EW6 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0 OOE+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6. 77E&6 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&6 6.54E-05 Nb-95 1.76E-06 9.77E-07 5 ~ 26E&7 0.00E+00 9.67E&7 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 O.OOE+00 8.18E-12 3.00EW7 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 O.OOE+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 O.OOE+00 1.35E-13 4.99EW8 1.36E-21 Ru-103 1.91E-07 0 ~ OOE+00 8.23E&8 O.OOE+00 7.29E&7 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E<<11 0 ~ OOE+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 O.OOE+00 1.09E-06 O.OOE+00 1.67E&5 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-O7 O.OOE+00 2.46E&6 5.79E-04 3.78E-05 600(207)

RETS Manual Revision 13 Page 210 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-06 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 O.OOE+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-O6 Te-127m 1.58E-06 7. 21E-07 1.96E-07 4.11E-07 5. 72E&6 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-ll 1.32E-10 6.37E-10 8. 14E&7 7.17E-06 Te-129m 1.22E&6 5.84E-07 1.98E-07 4.30E-07 4.57E&6 1.45E-44 4.79E-05 Te-129 6 22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-ll 2.42E-07 l. 96E-08 Te-131m 8.74E-09 5.45EW9 3.63E-09 6.88E-09 3.86E-OS 1.82E&5 6 '5E-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&8 2.02E-OS 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5 72E&7 1.68E&6 6.60E-07 1.42E-04 2.61E-06 O.OOE+00 9.61E-07 I-131 3.15E-06 4.47E&6 2.56E-06 1.49E-03 7.66E-06 O.OOE+00 7.85E-07 I-132 1 45E&7 4.07E-07 1.45E-07 1.43E-05 6.48E-07 O.OOE+00 5.08E-OS I-133 1.08E&6 1. 85E&6 5.65E-07 2.69E-04 3.23E-06 O.OOE+00 1.11E-06 I-134 8.05E-OS 2. 16E&7 7.69E-08 3.73E-06 3.44E&7 O.OOE+00 1.26E-10 I-135 3. 35E&7 8. 73E&7 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 O.OOE+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-O5 5.35E-05 O.OOE+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-OS 4.05E-08 0.00E+00 6.00E08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3. 21E-07 O.OOE+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-ll 9 '1E-15 4.20E-13 O.OOE+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0 ~ OOE+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-OS 2.17E-OS 5.73E-09 0.00E+00 O.OOE+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 O.OOE+00 O.OOE+00 7.91E-07 2.64E-07 Ce-141 2.49E-OS 1.69E-06 1.91E-07 O.OOE+00 7.83E-07 4.52E-05 1-50E-05 Ce-143 2.33E-OS 1~ 72E-08 1.91E-09 O.OOE+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E&4 1. 79K&4 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 O.OOE+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 O.OOE+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7. 62E&7 4.56E-OS O.OOE+00 4.45E-07 2.76E-05 . 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 O.OOE+00 O.OOE+00 3.63E-06 1.94E-05 Np-239 2.87E-OS 2. 82E&9 1.55E-09 0 OOE+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.

600(207)

RETS Manual Revision 13 Page 211 Table 7.7 (3 of 8)

. INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.59E-07 1.59E-07 1.59E-07 1.59EW7 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 6.09EW7 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 l. 72E&6 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.16E-05 Cr-51 O.OOE+00 O.OOE+00 1.69E-OS 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E>>06 O.OOE+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 O.OOE+00 2.12E-10 3.15E-11 O.OOE+00 2.24E-10 1.90E&6 7.18E&6 Fe-55 4. 18E&6 2.98E-06 6.93E&7 O.OOE+00 O.OOE+00 l. 55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E&6 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 O.OOE+00 1.18E-07 1.15E-07 O.OOE+00 0 ~ OOE+00 7.33E-05 3.93E&6 Co-58 O.OOE+00 2.59E-07 3.47E-07 O.OOE+00 O.OOE+00 1.68E-04 1.19E-05 Co-60 O.OOE+00 1.89E-06 2.48E-06 O.OOE+00 O.OOE+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 O.OOE+00 0.00E+00 3.84E-05 l. 77EW6 Ni-65 2.73E-10 3.66E-11 1.59E-11 O.OOE+00 O.OOE+00 1.17E-06 4.59E&6 C0-64 O.OOE+00 2.54E-10 1.06E-10 0 OOE+00 8.01E-10 1 ~ 39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0 '0E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-ll 8.07E>>13 O.OOE+00 7.53E-12 1.98E-07 3.56E-OB 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 O.OOE+00 2.28E-06 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Br-83 O.OOE+00 0 ~ OOE+00 4.30E-OS 0 ~ OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Br-84 O.OOE+00 O.OOE+00 5.41E-OB 0.00E+00 0 '0E+00 0.00E+00 0.00E+00 Br-85 O.OOE+00 0-OOE+00 2.29E-09 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2-38E-05 1.05E-05 O.OOE+00 O.OOE+00 0.00E+00 2.21E-06 Rb-88 O.OOE+00 6.S2E-OB 3 '0E-08 O.OOE+00 0.00E+00 0.00E+00 3.65E>>15 Rb-89 0.00E+00 4-40E-08 2.91E-OS O.OOE+00 0.00E+00 0.00E+00 4.22E>>17 Sr-89 5.43E-05 O.OOE+00 1.56E-06 O.OOE+00 0.00E+00 3 02E-04 4.64E-05 Sr-90 1.35E-02 O.OOE+00 8.35E-04 O.OOE+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-OB O.OOE+00 4.39E-10 0.00E+00 O.OOE+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.0SE-11 O.OOE+00 O.OOE+00 3.43E-06 1.49E-05 Y-90 3.73E-07 O.OOE+00 1.00E-OB 0 ~ OOE+00 O.OOE+00 3.66E-05 6 '9E-05 Y-91m 4.63E-ll O.OOE+00 1.77E-12 O.OOE+00 O.OOE+00 4.00E-07 3. 77E&9 Y-91 8.26E-05 0 ~ OOE+00 2. 21E&6 O.OOE+00 O.OOE+00 3.67E-04 5.11E-05 Y-92 1.84E-09 O.OOE+00 5.36E-11 0 ~ OOE+00 O.OOE+00 3.35E-06 2.06E&5 Y-93 1.69E-OB O.OOE+00 4.65E-10 O.OOE+00 0.00E+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-OB 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 OSE&7 0 ~ OOE+00 1.25E-06 9.39E&5 1. 21E&5 Nb-97 3.92E-ll 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2. 71E-07 Mo-99 O.OOE+00 2.11E-OB 4.03E-09 0 ~ OOE+00 5 '4E-08 1.92E-05 3 '6E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7 '0E-12 1.44E-07 7 66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 O.OOE+00 1.90E-13 8.34E-OB 1.09E-16 RQ-103 2.63E-07 O.OOE+00 1.12E-07 O.OOE+00 9 '9E-07 9 '9E-05 1.36E-05 Ru-105 1.40E-10 O.OOE+00 5.42E-11 O.OOE+00 1.76E-10 2 '7E-06 1.13E&5 Ru-106 1.23E-05 0 ~ OOE+00 1.55E6 O.OOE+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E&7 O.OOE+00 3.13E-06 8.44E-04 3.41E-05 600(207)

t RETS Manual Revision 13 Page 212 Table 7.7 (4 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN bone 1 iver t body thyroid kidney lung gi-lli Sb-124 5.38E&6 9.92K&8 2.10E-06 l. 22E&S O.OOE+00 4.81E-04 4.98E-05 Sb-125 9.23E&6 1.01K-O7 2.15E-06 S.SOE-09 O.OOE+00 3.42E-04 1.24E-05 Te-125m 6. 10E-07 ?.SOK-07 8.34E-OS 1.75E-07 O.OOE+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02K-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 l.l4K-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1. 74K&6 l.?3K-07 2.81E-07 5.72E-07 6 49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4. X?K-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E$ 7 ~ 51M) 9 5.03EW9 9.06E-09 5 49E-08 2.97E-05 7.76E-05 Te-131 1. 97E-12 1.04K-12 6.30E-13 1.55E-12 7 72E-12 2.92E-07 1.89E-09 Te-132 4.50E-OS 3.63K-OB 2.74E-OB 3.07E-OB 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2 2iKW6 8 96E-07 1.86E-04 3.44E-06 0.00E+00 '.14E-06 I-131 4.43E-06 4. liK-06 3.30E-06 1.83E-03 1 ~ 05E-05 O.OOE+00 8.11E-07 I-132 1.99E-07 5.47K%7 1.97E&7 1.89E-05 8.65E-07 O.OOE+00 1.59E-07 I-133 1.52K&6 2.56E-06 7. 78E-07 3.65E-04 4.49E-06 O.OOE+00 1.29E-06 I-134 1.11E07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 O.OOE+00 2.55E-09 I-135 4.62E&7 1.18E-06 4.36EW7 7.76E-05 1.86E-06 0 'OE+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 O.OOE+00 1.38E-05 2.22E-06 1.36E&6 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-OB 1.07E-07 5 58E-08 O.OOE+00 8.28E-OS 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.1SE-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 O.OOE+00 2.85E&9 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 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3 92E-15 2.39E-07 5.99E-20 La-140 5.99E-OB 2.95E-OS 7.82E-09 0.00E+00 0 OOE+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-ll O.OOE+00 O.OOE+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+00 1.11E&6 7.67E-05 1.58E-05 Ce-143 3.32E-OB 2.42E-OB 2.70E-09 0 ~ OOE+00 1.08E-OB 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-OS O.OOE+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-OS O.OOE+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0 ~ OOE+00 O.OOE+00 5.92E-06 2.21E-05 Np-239 4.23E-OS 3.99E-09 2.21E-09 0 OOE+00 1.25E-OS 8.11E-06 1-65E-05 4

Reference:

Regulatory Guide 1.109, Table E-S.

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.

600(207)

RETS Manual Revision 13 Page 213 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&7 3.04E&7 3.04EW7 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E&6 1.82E&6 1.82E06 1.82E&6 1.82E-06 Na-24 4.35E-06 4.35E&6 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2. 67EW5 O.ODE+00 O.OOE+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&6 2.93E-07 Mn-54 O.OOE+00 1.16E&5 2.57E-06 O.OOE+00 2.71E06 4. 26E-04 6.19E-06 Mn-56 O.OOE+00 4.48E-10 8.43E-11 O.OOE+00 4.52E-10 3.55E&6 3. 33EW5 Fe-55 1.28E-05 6.80K&6 2.10E-06 O.OOE+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04K&6 4.51E-06 O.OOE+00 O.OOE+00 3.43E-04 1.91E-05 Co-57 O.OOE+00 2.44E-07 2.88E-07 O.OOE+00 O.OOE+00 1.37E-04 3.58E-06 Co-58 O.OOK+00 4.79E-07 8.55E-07 O.OOE+00 O.OOE+00 2.99E-04 9.29E-06 Co-60 O.OOE+00 3.55E-06 6.12E-06 O.OOE+00 0.00E+00 1. 91E&3 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 O.OOE+00 O.OOE+00 7.43E-05 1.71E-06 Ni-65 S.OSE-10 7.99E-ll 4.44E-Il O.OOE+00 O.OOE+00 2.21E-06 2.27E-05 C0-64 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 O.OOE+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 O.OOE+00 1.58E-11 3.84E-07 2.75E-06 Zn-69m 4.26E<<09 7.28E-09 8.59E-10 O.OOE+00 4.22E-09 7.36E&6 2.71E-05 Br-82 O.OOE+00 O.OOE+00 5.66E-06 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 0.00E+00 1.28E-07 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 6.84E&9 0.0DE+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 O.OOE+00 5.36E&5 3.09E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.16E-06 Rb-88 O.OOE+00 1.52E&7 9.90E-08 0.00E+00 O.OOE+00 O.OOE+00 4.66E-09 Rb-89 O.OOE+00 9.33EMS 7.83E-OS O.OOE+00 O.OOE+00 0 OOE+00 5.11E-10 Sr-89 1.62E-D4 O.OOE+00 4.66E-06 O.OOE+00 O.OOE+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-03 9.28E-05 Sr-91 3.28E-OS O.OOE+00 1.24E-09 O.OOE+00 0.00K+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 O.OOE+00 1.42E-10 O.OOE+00 O.OOE+00 6.49E-06 6.55E-05 X-90 1.11E-06 0.00E+00 2.99E-08 O.OOE+00 O.OOE+00 7.07E-05 7.24E>>05 Y-91m 1.37E-10 O.OOE+00 4.98E-12 O.OOE+00 O.OOE+00 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+00 6.59E-06 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 0.00E+00 6.46E<<06 6.46E-05 Y-93 5.04E-OS O.OOE+00 1.38E-09 0 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-OS 7.34E-09 4.32E-09 O.OOE+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 O.OOE+00 2.33E-06 1 66E&4 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 O.OOE+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00K+00 4.66E-OS 1.15E-OS O.OOE+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-ll 2.57E<<07 1.30E-06 Tc-101 2.19E-14 2 30E-14 2.91E-13 O.OOE+00 3.92E-13 .1.58E-07 4.41E-09 Ru-103 7.55E-07 O.OOE+00 2.90E-07 O.OOE+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 O.OOE+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-OS 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-05 600(207)

RETS Manual Revision 13 Page Table 7.7 (6 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled) 214'b-124 CHILD bone liver t body thyroid kidney lung gi-lli 1.55E-05 2.00E-07 5.41E-06 3.41E&8 O.OOE+00 8.76E-04 4.43E-05 Sb-125 2.66E-OS 2.05E-07 5.59EW6 2.46E-08 O.OOE+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-07 1.64E-06 1.72E-05 4.00E-04 1.93E&5 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. 22EW7 l. 71EW6 1.36E-05 4.76E-04 4.91E&5 Te-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1. 60EW8 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-ll 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-OS 7.37EW6 4.39EM3 2.13E-05 O.OOE+00 7.68E&7 I-132 5.72E-07 1.10E-06 5.07E&7 5.23E-05 1.69E-06 O.OOE+00 8.6SE-07 I-133 4.48E-06 5.49E-06 2. 08E&6 1.04E&3 9.13E-06 O.OOE+00 1.48E-06 I-134 3.17E-07 5.84E-07 2. 69E&7 1.37E-05 8.92E-07 O.OOE+00 2.58E-07 I-135 1.33E&6 2.36E-06 1. 12EW6 2.14E-04 3.62E-06 O.OOE+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 O.OOE+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-OS 4.62E-OS 3.14E-05 O.OOE+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 O.OOE+00 7.63E-05 2.81E-OS 9.78E&7 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E&8 Ba-139 4.98E-10 2.66E-13 1.45E-11 O.OOE+00 2.33E-13 1.56E-06 1.56K&5 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.7SE&5 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 O.OOE+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04EW8 O.OOE+00 O.OOE+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 O.OOE+00 O.OOE+00 2.35E-06 2.0SE-05 Ce-141 1.06E-OS 5.28E-06 7.83E-07 O.OOE+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E08 7.77E-09 0.00E+00 2.26E-08 3.12E-OS 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 O.OOE+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 O.OOE+00 8.11E-07 1.17E-04 2.63E&5 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 O.OOE+00 1.30E-06 8.87E-OS 2. 22E&5 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E&5 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E&5

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.

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

600(207)

RETS'anual Revision 13 Page 215 Table 7.7 (7 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT bone liver t body thyroid kidney lung gi-lli H-3 4.62E-07 4. 62K&7 4.62E-07 4 62E-07 4. 62K&7 4 ~ 62E&7 4.62E-07 C-14 1.89E-05 3.79K-06 3.79E-06 3.79E-06 3.79E&6 3. 79E-06 3.79E-06 Na-24 7.54E-06 7.54K&6 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E&6 P<<32 1.45K&3 d .03K+05 5.53E-05 O.DOE+00 O.DOE+00 0 'OE+00 1 15E-05 Cr-51 0. ODK+00 O.OOKED 6.39E-08 4.11E-08 9.45E&9 9 '7E-06 2.55EW7 Mn-54 O.DOE+00 1. b 1K-05 3.56E-06 O.DOE+00 3.56E&6 7.14E-04 5.04E-06 Mn-56 O.DOE+00 1.10K-09 1.58E-10 O.DOE+00 7.86E-10 8 '5E-06 5.12E-05 Fe-55 1.41K-05 8.39K-06 2.38E-06 0.DOE+00 0.DOE+00 6 '1E-05 7.82E-07 Fe-59 9.69K-06 1.6SK&5 6.77E-06 O.DOE+00 0.DOE+00 7 '5E-04 1.77E-05 Co-57 O.DOE+00 4.65M)7 4.58E-07 O.DOE+00 O.DOE+00 2.71E-04 3.47E-06 Co-58 O.DOE+00 d.7lK-07 1.30E-06 O.DOE+00 0.DOE+00 5.55E-04 7.95E-06 Co-60 O.OOK~ 5. 73K&6 8.41E-06 O.DOE+00 0.DOE+00 3.22E-O3 2. 28E&5 Ni-63 2.42K-04 1.46K&5 8.29E-06 O.DOE+00 0.DOE+00 1.49E-04 1.73E-06 Ni-65 1.71K&9 2.03K-10 8.79E-11 0 DOE+00 O.DOE+00 5.80E-06 3.58EW5 C0-64 0. DOE+00 1 ~ 34K&9 5.53E-10 O.DOE+00 2 '4E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47K&5 2.22E-05 0.DOE+00 2.32E-05 4. 62E&4 3. 67K&5 Zn-69 3.85E-11 6.91E-11 5.13E-12 O.DOE+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98K&9 1.84E-OS 1 ~ 67E-09 D I ODE+00 7.45E&9 1. 91E-05 2.92E-05 Br-82 0.00K+00 O.DOE+00 9.49E-06 0.DOE+00 0.DOE+00 0.DOE+00 O.DOE+00 Br-83 0.00K+00 O.DOE+00 2.72E-07 O.DOE+00 0.DOE+00 0.DOE+00 O.DOE+00 Br-84 0.DOE+00 O.DOE+00 2.86E-07 0.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 Br-85 O.DOE+00 O.OOE+OD 1.46E-OS 0 DOE+00 0.DOE+00 0.DOE+00 O.DOE+00 Rb-86 O.DOE+00 1.36E-04 6.30E-05 O.DOE+00 0.DOE+00 0.DOE+00 2.17E-06 Rb-88 0.DOE+00 3.98E-07 2.05E-07 0 DOE+00 0 'OE+00 0 'OE+00 2.42E-07 Rb-89 O.OOE+OD 2.29E-07 1.47E-07 O.DOE+00 0.DOE+00 0.DOE+00 4.87E-OS Sr-89 2.84E-04 O.DOE+00 8.15E-06 O.DOE+00 0.DOE+00 1.45E-03 4.57E-05 Sr-90 2. 92E&2 O.DOE+00 1.85E-03 O.DOE+00 0.DOE+00 8.03E-03 9.36E-05 Sr-91 6.83E-OS 0.DOE+00 2.47E-09 O.DOE+00 0.DOE+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 O.DOE+00 2.79E-10 O.OOE+OD O.DOE+00 1.70E-05 1.00E-04 Y-90 2.35E-06 D I ODE+00 6.30E-OS O.DOE+00 O.DOE+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 O.DOE+00 9.90E-12 0.DOE+00 0.DOE+00 1.99K&6 1.68E-06 Y-91 4.20E-04 O.DOE+00 1.12E-05 O.DOE+00 O.DOE+00 1.75E-03 5.02E-05 Y-92 1. 17E-08 O.DOE+00 3.29E-10 O.DOE+00 0.DOE+00 1.75E-05 9.04E-05 Y-93 1.07E-07 O.DOE+00 2 '1E-09 Q.DOE+00 0.DOE+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0 ~ 00E+00 2. 22E&5 1.25E-03'.88E-05 1.55E-05 Zr-97 1.07E-07 1.83E<<OS 8.36E-09 O.DOE+00 1.85E&8 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 D I ODE+00 3.37E-06 3.42E-04 9 05E-06 Nb-97 2.44E-10 5.21E>>11 1.88E-11 0 'OE+00 4.07E-11 2 '7E-06 1.92E-05 Mo-99 O.DOE+00 1.18E-07 2.31E-OS O.DOE+00 1.89E-07 9.63E<<05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0 DOE+00 2.22E-ll 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 O.DOE+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 O.DOE+00 4.85E-07 O.DOE+00 3.03E&6 3.94E-04 1.15E-05 Ru-105 8.74E-10 O.OOE+00 2.93E-lo 0.DOE+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 O.DOE+00 7.77E-06 O.DOE+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 O.DOE+00 7 SDE-06 2.62E-03 2.36E-05 600(207)

RETS Manual Revision 13 Page 216 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-OS O.OOE+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 O.OOE+00 3.19E-04 9. 22E&6 Te-127m 1.19E&5 4.93E-06 1.48E&6 3.48E-06 2.68E-05 9 '7E-04 1.95E-05 Te-127 l. 59E-09 6.81E-10 3.49E-10 l. 32EW9 3.47E-09 7 39EW6 1.74E-05 Te-129m 1.01E-05 4 35E&6 1 59E&6 3.91E-06 2.27E-05 1 ~ 20E-03 4.93E-05 Te-129 5.63E-ll 2.48E-11 1.34E-11 4.82E<<ll 1.25E-10 2.14E-06 1.88E-05 Te-131m 7. 62E&8 3.93E-OS 2. 59E&8 6.38E-OS 1 ~ 89E-07 1.42E-04 8.51E-05 Te-131 1. 24E-ll 5.87E-12 3.57E-12 1 ~ 13E-11 2.85E-ll 1.47E-06 5.87E-06 Te-132 2.66EO7 1.69E-07 1.26E&7 1. 99E&7 7. 39E&7 2.43E-04 3. 15E&5 I-130 4.54E-06 9 91E-06 3. 98E-06 1.14E-03 1.09E-05 O.OOE+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&6 2.53E-06 8. 99E&7 21E-04 2.82E-06 O.OOE+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2. 54E&3 1.60E-05 O.OOE+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&6 4.97E-04 6.05E-06 O.OOE+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 O.OOE+00 4.03E-05 8 '0E-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-OS 6.26E07 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-OS 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 O.OOE+00 4.64E-14 2. 12EW6 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 O.OOE+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 '9E-10 6 '6E-11 O.OOE+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 O.OOE+00 3.75E-06 3.69E&4 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-OS O.OOE+00 4.03E-OS 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 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&5 Pr-144 3.42E-ll 1.32E<<ll 1.72E-12 O.OOE+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 O.OOE+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6 '4E-09 2. 23E&9 O.OOE+00 O.OOE+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 O.0OE+00 4.73E-OS 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.

600(207)

Ills

~ ~ ~ ~ ~ ~

Ill

RETS Manual Revision, 13 Page 218 Figure 7.2 NORMAL BUILDING VENTILATION ROOF FANS

~ r r ~ ~

~

~ r ~

~

+ ~

r

~

~ ~ ~

~ ~

~ ~ r ~ ~

%~

~

~ ry ~

~ ~ Refuel r Turbine Deck Floor RM 90-249 RM 90-261 RM 90-260 RM 90-262 From Primary coredrmtre Froca Pure ~ byrlrm Asbrre elo buldnb Turbine Building Control Reactor Building (Typical for each Unit) Bay (typical for each Unit) le boyb lrmrrernry errelallen)

" Used seasonally to control temperature 600 (207)

RETS'anual Revision 13 Page 219.

Figure 7.3 PLUME DEPLETION EFFECT (Page 1 of 4) 1.0 0.9 0.9 0.7 Z 0.8 5

0.6 Z

O 6 O.d 0.1 0.1 '1.0 1.0.0 100.0 'ROOA t wM0 vnnval. olstnNca t tut.oMETEns) t'tenn Oepleaon Etteet too Ciennd Leeot tlotoooeo thll hlnteopheite Slob9ly Cloooeo) 600(207)

RETS Manual Revision 13 Page 220 Figure 7.3 PLUME DEPLETION EFFECT

{Page 2 of 4) 1.0 SS 0.0 IIEVtnaL ru 0.8

" 0.>

VIIS'fh0L 0.8 Ih.a ,CI

> 0.0 O

g 0.C 03 O.S 0.1 0.1 1.0 ~ 10.0 '100.0'00.0 I'LVMESnhvEL DISTANCE [IIILOMETEnS) ~

tlun>> Depletion Ellsct lor 30ennelesrer lLettersrlsnots I'srquSI Stsblllty Clsrrt:

600(207)

RETS Nanual Revision 13 Page Figure 7.3 PLUNE DEPLETION EFFECT of 4) 221'.0 (Page 3 STASLE IE F,DI 0.9 HEUTDAL w 0.0 Dl

" O.T VHSTASLE QLP,C g

> O.S D

0.3 0.3 0.1 1.0 10.0 100.0 30 0 I'LVME 1IIAVELDISTANCE Ill)oblETEIIS}

I'lonrt Dtrr40on Elltcl Ior 00trr Dtlttrtr Il.~ lrtrr donort TtrooSI SltbOltrr Cltrr) 600(207)

RETS Manual Revision 13 Page 222 Figure 7.3 PLUME DEPLETION EFFECT (Page 4 of 4) 1.0

0.9 NEU2hAL (D) sss O.d UNStABLE (A,B,C1 0.2 12 SEABLE E,P,O NDDEPL YION z O.d I N INC Ip 0sl O

g O.d ss 0.2 0.2 0.1 0.1 1.0 10.0 1008) 200.0 PLUME ThAVELDldlANCE IKILDMETEhd)

Plssnse Dtldsslon Elect lsss 100m hsssssts 1Leltsss dsnolt Pwsqssld Slsbdlsy Clsss) 600(207)

RETS Manual Revision 13 Page 223 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 100

~ ~

C

10 0.1 1.0 10 100 PLUME TftAVELDlSTANCE [fjllLOMETEftS)

Vcr tical Sta>>daitl Deviatio>> of Material i>> a Plu>>re {Letters der>ote Pasqulll Stability Class) 600(207)

RETS Manual Revision 13 Page 224 Figure 7.5 RELATIVE DEPOSITION (Page 1 of 4) 10 3 10+

tr:

LU n.

LU I-tL 0 10-~

I-tis 0

LU .

O LU tt:

10-0

'0"7 0.1 1.0. 10.0 100 0 200 0 I'LUME TRAVEL DISTANCE (KILOMETEFlS1 ftelativc Dei)osition for Grounti-t.eval Releases (AII Atrnosplr'eric Stabilit'f CIasses) 600(207)

RETS Nanual Revision 13 Page Figure 7.5 RELATIVE DEPOSITION (Page 2 of 4) 10 3 225'0+

NSTABLE (A NEUTAA NEUT RA tD

. STABL STAB E {E,F.G) 10 6 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TAAVELDISTANCE lKII OlyIETEAS) ftelatlve Deposition for 30.io nclecses (Letters denote Pasqulll Stability Clast) 600(207)

RETS Manual Revision 13 Page 226 Figure 7.5 RELATIVE DEPOSITION (Page 3 of 4) 104 UNSTABLE (A,B 10-6 NEUTR AL ( D) rl:

W U ST BLE tl LU EUTRAL l-K zo 10-6 l-r/7 0

UJ O

. LU I-Ul K

STAB LE (E,F,G) 10 0 0.1 1.0 10.0i 100.0 200.0 l LUME TRAVEL DlSTANCE (K(LOMETERS)

Relative Deposition for 60<a Relenses (Letters denote Pnsquflf Stability Class) 600(207)

RETS'anual Revision 13 Page 227.

Figure 7.5 RELATIVE DEPOSITION

{Page 4 of 4)

UNSTABLE (A,B,C 10-B K

LU l- TBAL (D ill K

LU LU l-LL:

10 0 I-7LJ O

LU O

LU I-LlJ STABLE {E,F,G)

NO DEPLET lON 10-7 10 0 0.1 1.0 10.0 100.0 200.0 PLUME TAAVELDISTANCE tKILOMETEAS)

Aelative Deposition lor 100 ln fleleases tLettcrs denote Pasqtlill Stallility Class) 600(207)

RETS Manual Revision 13 Page 228 SECTION 8.0 TOTAL DOSE 600(207)

RETS Manual Revision 13 Page 229 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 vill 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 to 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 is 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, the 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 i

to the limit in Control 3.2 3, e., 75 mrem per year to determine compliance.

600(207)

RETS Manual Revision 13 Page 230 SECTION 9.0 ENVIRONMENTAL MONITORING PROGRAM 600(207)

RETS Manual Revision 13 Page 231 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, direct 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.

9.3 LAND USE CENSUS A 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.

600(207)

RETS Manual Revision 13 Page 232 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-I, IM>>2, once per 7 days. Perform gamma isotopic LM-3, WW, 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 a d 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-89, locations as air Sr-90 once per year 4

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 600(207)

RETS Manual Revision 13 Page 233'able 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)

I Dr in'king 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 days once per 92 days.

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 .

b 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.

600(207)

RETS Manual Revision 13 Page 234 Table 9.1 (3 of 5)

EKlIRONMENTAL 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 locationc 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 86) 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) 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 .

The surface water control sample shall be considered a control for the drinking water sample.

600(207)

RETS Manual Revision 13 Page 235 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 600(207)

RETS Manual Revision 13 Page 236 Table 9.1 (5 of 5)

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

~Sem 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 & 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) 600(207)

RETS Manual Revision 13 Page 237 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or Samples Number a Station Sector (Miles) Control (C) Collected+

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 IA-7 W 2.1 I AP, CF~ S 5 RM-1 M 31.3 C AP~ CF~ S 6 RM-6 E 24.2 C AP, CF~ S 7 LM-a N 1.0 I AP, CF, S 8 IM-2 NNE 0.9 I AP~ CF~ S 9 IM-3 ENE 0.9 I AP,CF,S 10 XMW NNW 1.7 I AP,CF, S 11 LM-6 SSM 3.0 I APg CF~ S 12 Farm B NNW 6.8 I M 13 Farm Bn N 5.0 I M, M 18 Farm Gl MSM 35 C M, V 22 Well 86 NW 0.02 I W 23 c 282.6 I PM 24 TRM 303.0 12.0 25 TRM 259.6 34 'd C I

PW 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 0.3d I SD 32 TRM 288.78 5.22d I SD 33 TRM 277.98 16.02d I SD 34 Farm Be 28.8 C M 36 Farm T 3.2 I V 37 TRM 297.0 Od C SD Wheeler Reserv oir I/C F0 CL (TRM 275-349)

Guntersville Reservoir (TRM 349W24) 70 TRM 259-8 34 2d PW See Figures 9.1, 9.2, and 9.3 Sample codes:

AP = Air particulate filter S ~ Soil SD ~ Sediment CF = Charcoal Filter SM ~ Surface Water CL ~ Clams F = Fish V = Vegetation PM = Public Water M ~ Well Mater M ~ Milk TRM = Tennessee River Mile Miles from plant discharge (TRM 294)

Also used as a control for public water 600(207)

RETS Manual Revision 13 Page 238 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 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 5.2 Off 41 NE-1 0.8 42 NE-2 5.0 Off 43 ENE-2 6.2 Off 44 E-1 0.8 45 E-2 5.2 Off 46 ESE-1 ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-1 SE 0.5 49 SE-2 SE 5,4 Off 50 SSE-1 SSE 5.1 Off 51 S-l 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 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 62 W-2 W 4.7 Off 63 WW 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.

600(207)

RETS Manual Revision 13 Page 239 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS l

WITHIN MILE OF THE PLANT S48.76 SS.76

~ 8 NE SOS.75 39 ~ 41'8.26 ENE WNW 28'00') 78.76 28 1.26

~ 44

/i x o gROWNS FLURRY

't 46 10 1.26 258.7 6 ~UgLPP,R PLANT ~

48 ESE 12S.76 2S8.26 SW 148.26 21S.75 SSE SSW 6 188.7 6 Scaie 0

600(207)

RETS Manual Revision 13 Page 240 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT 11.24 bib,lb 1'13 42.14 btb tb I IW 42 44.24 002.15 k,C(

WIIW Wr r. ~ e

~ 10 86 1 ~ .14 2b 1.2 38. 84

(

480web FEII

~ 82 IIIICLSAIIPL III

~ 101.24 255.15 I ~

~+yQT SSS 4r WSW 11 122.1 5 6

22b.25 61 685 44.24 212.14 62 44% SCAM SSW 0 0.5 INLSS 145.15 lb 1.25 600(207)

S n

RETS Manual Revision 13 Page 241 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT 34$ .75 t tas 32$ N5 33.rd w twcttuao suer>

303.rd

+AYETTa~

34 2$ 1.2

<LORQlg 6 rs.rs

~ 2 VSCl! arne 43 15 57 25$ .75 tOtas RVSI mug il8 32$ .2 NA~g 123.rd 213.rd 14IL25 IO 0 1$

19145 1 55.75 600(207)

RETS Manual Revision 13 Page 242 RETS MANUAL Section IV PROCESS CONTROL PROGRAM PCP IV-1 600(207)

RETS Manual Revision 13 Page 243

1.0 INTRODUCTION

1.1 ~Sco e This Process Control Program (PCP) is applicable to radioactive waste solidification and dewatering of wet solid radioactive wastes generated aa a result of the operation and maintenance of Browns Ferry Nuclear Plant. This PCP is not applicable to the treatment of mixed wastes.

1. 2 ~Pur I~

The PCt provides those controls necessary to ensure that disposal criteria are met by BFN processing techniques, or by vendor supplied systems, if used for dewatering or solidification.

2 0 DEFINITIONS 2.1 Absorb - To take liquid in through pores, or as if through pores or interstices of a material.

2.2 Absorbent - Media or material used to absorb liquid.

2.3 Batch - An isolated quantity of waste to be processed having constant physical and chemical characteristics.

2.4 Container - The primary receptacle in which processed wastes (dewatered, solidified or absorbed) are. packaged for disposal.

2.5 Dewatered - Wet solid wastes which have had excess water removed.

2.6 Free Liquid - Uncombined liquid not bound by the solid matrix of the solid waste mass; capable of flowing.

2.7 Homogeneous Of uniform composition; the waste is uniformly distributed throughout the container.

2.8 Liquid waste - For the purposes of this PCP, any aqueous or non-aqueous radioactive liquid- which requires solidification or absorption before disposal. This may include oils, chemitals, water or other liquids unsuitable for in-plant clean-up or treatment.

IV-2 600(207)

RETS Manual Revision 13 Page 244'.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.1 & 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-3 600(207)

RETS Manual Revision 13 Page 245

'.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 (RNCU), 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 filt'er 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 stabilized. 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 t:he 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.

600(207)

RETS Manual Revision 13 Page 246 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 TttA 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-5 600(207)

RETS Manual Revision 13 Page 247 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/ lit Control Quality assurance audits are conducted by the BFN site Quality Assurance organisation, and by the TVA Division of Nuclear Quali.ty 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

'gents are established which meet the standards for waste form and free liquid cri.teria.

6.3 T~rainin 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 be reestablished through completion of retraining, and approval of the Radwaste Group Supervisor.

IV-6 600(207)

RETS Manual Revision 13 Page 248

'.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.

(RIMS OL44 870211 808 and SL44 871016 807), and Attachment 1 and 2.

IV-7 600(207)

RETS Manual Revision 13 Page 249

-gt g21T 9 0 ~ ~".

L44. gq 081 j. 808 5H i57S Lookout Ploce FH8 1 l 887.

V.S. Hucleor Regulatory Commission Attn'ocumon( Control Desk Office oE Nuclear Roue'tor Regulation Washington, D.C. 20555 Atte>>tlont llr. D. B. Huller In the llutter of the Docket Nos 50-259 Tennessee Valley Authority 50-'260 50-296 BAOWHS FEBAX fNCl EAB PLANT (BFH) - PROCESS CONTROL PBOCBAH FOll DEHIHERALIZER RESIN DEWATEAIHC I ~,

Demlnerullxor resii) devuterlng is performed at SFN using equlpmcnt fabricated by TVA to meet Chem-Nuclear Systems; Inc., (CHSI) equipment spociflcations.

SFN hus adopted the operating methodology outlined by CHSI ln a topical roport (CHSI-DW-11118-01-P) titled, "CHSI Dewaterlng Con'trol process Co'ntainers:

Topical Report." HRU accepted this topical report for reference by license uppllcu>>ts in o let(et.'.fE'om C. O. Thomas (NBC) to l. K. Poppe (CNSI) .dated Juno 11, 1985.

f The enclosure provided information required by NBC to revieu applicabiligy of tho report to specific licenseoi as outliilod in the associa'ted.safety, evoluatlon. We request that NRd review the enclosed information and provido approval for use of this repor't as i process control program as defined in thd.

Audiological Effluent Teclinical Specification (RETS) amendmont (TVA BFH TS-221, doted September 30, 1986). It is further requested that NRC approval of the process control program coincide Mlth the BETS implementation date or that the submittal be accepted on an interim basis until approval of tho progrnm is flillulixed.

~~

If you hove ony questions concerning this request ~ please call I; V; Tonty at (205) 729-2677.

Very t.ruly yours, TEHHESSEE Vh( tg'gX AUTllOAITX

+d~ Htgnid Nz Zgn6leY y ~ ~

B. Qrldley, Safety. and licensing Diroctor'uclear Fnc losuro cc! See pogo 2 Dt-8 600(207)

RETS'anua1 Revision 13 Page 250 .

V.S. Nuclear HcSulatory Commission FEB 111Ã7 cc (Enclosure) I V.S. Nuclear hegulatory Conmission Region II Attn't. J. Nelson Crace,'egional Administrator 101.IIarletta Street, NM, Suite 2900 A'tlanta, Coors,io 30323.

IIr. C. E. Cears Brow~d Ferry Pro)ect IIonager V.S. Nuclear Regulatory Conmisslon 1920 Norfolk hvonue Ilaryland 20814

'ethesda, Ilr. C. Cs 'Sech, Dl.rector TVA Projects V.S: Hucleor Regulatory Commission 101 Harlo'tto St. ~ INf Suite 2900 Atlanta, Ceorgla 30323 BroMns Ferry Resident InsPector Drome Ferry Nuclear Plant P.O. Box 311 Athens, Alabama 35611

'cIIJII)(Enclosure)!

JUMtl VT! SJL RIBS, IIR 4N 72h-C R. M. Cantrell, M12 h12 C-K E. S. Cl>rlstenbury, Ell B33 C-K M. II. Ilannum, BR 1N 76B-C R.. I. gevis, Broens Ferry II. J.'lay, BFN - Licensliig .

D. R. Nichols, LP 5N 3028-C .

R. C. Parker, LP 4N 45A-C II. P. Pomrehn; Broms Ferry L. J. Rieles, BR 5S 144X-'C C. C. Robqri.son, LP 58 S3E-C R. K. Soiberling, 716C-C D. L. Mllliemsq M10 B85 C-K 0519c Dt-9 600(207)

RETS 'Manual Revision 13 Page 251

'NCLOSURE 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.

1. 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. Mhen 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 IV-10 600(207)

RETS Manual Revision 13 Page 252'pecified 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 vith 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 vith 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 vaste pa'ckaging 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 vith 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 devatering system is located inside the radvaste packaging room (see figure 1). Any leaks or spills vill 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 vill not ~rovide 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-ll 600(207)

RETS Manual Revision 13 Page 253

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 gC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.

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, 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&1-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-12 600(207)

RETS Hanual Revision 13 Page 254 FIGURE 1 gegarenca: Browne Farry FSAR 9.2 , ) b

~ ~ ~e 104 fl.. 3 Irr:..

+ oooe 0 e a e eve a ~ ~

iioogiotol 29(t.

Cue ~ Oi<<alar g

~ f Aalfareoe Clianl- ~ ~

Dion. Oa4l4!a Hiic{oar gillcn 16 ft.

~

Syria m ~

~ e ~

la'e ~ ~ ~

f

~ ~

~ t+ I ~

~ ~

~e

~

i ~

0 EVc (Nil)

Haste Packaging Room Layout for Chem Nuclear system Plan Elevation IV-13 565'00(207)

RETS'anual Revision 13 L 44 8 Y 3. 0 3. 6. 8 0 7 Page 255 .

Stl 1528 Lookout Place OBT <g Ioo 0'.~. 'ttuclear Regulatory Commission AT Ht Document Control Desk .

ttasttlngtan, D.C. 20555 Centlemcn!

In the 'ttatter of ) Docket ties, 50-259 Tennessee Valley Authority ) 50-260

'50-296 BRONtS PERRY HUCLEAR FLAltT (BElt) PROCESS CotrrROL PROCRAtt FOR DaunERALI"ER RESIlt DEMATv~C By letter f om ma ta D. p.. ttuller.dated E'ebruary'l, 1987, TVA desc ibad its process cant ol program far demlneralixer resin deuatering and requested, tlRC ta review and apprave Lt aa descri.bed i.n that letter. This resin. de~atering process ~as tLae-consuming. Chem-Huclear Systems Inc. (CJSI) has since improved this process by developing the RDS-IOOO, Rapid De&tering System, far accelerating the de~atering process. The thne savings in this.dewatering process All allo~ BF'H.ta accammod*'ts,i.ts spent resip Canal'axedgur'ng pouer pmduction. TVA"ihtendl ta bnplement'the RDS-10dO" praca'ss,before Unit 2 rqstar>>. Therefore, thiN submittal. supersedes tea.february..11< 19Sg letter..

Canscquenc}y, T'lA hai elected nat to answer ttRd's retfuest for additional information from J. h. Xvolinski to S. A. @hite dated July 21, 1987 concerning BElt's current de~atering process in i'separate submittal. tto~ever, these itens are addressed it> the enclosures to this latter for the'RbS-1000 system.

Deminerallxer resin dentering ~ill be performed at BE't1 using CtfSZ equipmant.

The operating methodology outlined by CHSI in topical reports DM-11118-01-P-A, "CtlSI De>staring Control process Containers Topical lteport" and RDS-25506-01-P, "RDS-1000 Radioactive ttaste Dewatering System" Mill be used.

HRC accepted CJSI. Tbpical Repor>> DM-11118-Ol-P-A for reference by license i

applicants la letter fram C. 0. Thomas (HRC) to L K. Poppe (CHSZ) dated June 1', 1985. CJSZ Topi.cal ttepart RDS-25506<<0I-P vas submitted to HRC by CSSI for approval by letter from M- B. ltouse (CHSI) ta R. L. Emch (HRC) dated Larch 26, 1987 and a nonproprietary copy is enclosed ta this latter (enclosure 2). These cJsI topical reports vill form the basis ef thi BE'V demb>erali "er resin devater&g pracess and system. provides information requi.red by HRC to review appl.iaability of the rcport to specifi.c Licensees as outlined in the safety evaluation for CttSZ Topical Report DL'1118-01-P-A. Procedures far 'thi.s no~ process and system ar'e ecticduled tc b internally approved by October 1987 ~ TVA requests that tttt0 review 'ttie ancloeed lnfarmatS.oa end provide approval, Within this sane tbneframo, far use of this report as a pracess control, program as defined itt, ttIa 8N tectmlcal spec3.flcttlan 6-'9 " "- "'

IV-14 600(207)

RETS Manual Revision 13 Page 256 1QQi U S Nuclear Regulatory Concnissicin OCT y6 Zf youu have ave any questions oonoernJing . this request, please telephone J. L.. Turner at (205) 729-2853.

~

I~

~

~ ~

CFP. 170.'2.

~

Enclosed is a cheek for the 5150 revieM f ee required by 10 Very t~ly'ours, TBNtESSEE V 4'Y AUTNOHI~

R. idley, D . eater Nuolear'ioecming and Regulatory Affai.rs Subsori.bed ag3 a~orn to +fore me

~ aa on this /~ada of ~~1987 c.

'P Notary publlo Qy Commission Expires

~ ~~ ~

~

.i~~

~ ~

~

Enclosures'o (Enokosures)!

Ilr. C. C. Zeoh, Assi.stant Direotor Regional Inspections Divisi.on of TVA Pro)eots Office of Speoial Pro)eats U.S. Nuclear Regulatory'onti.salon Region II Suite 2900 101 i!arietta St., HM, Atlanta, Cnorgia 30323 Kr. J. h. Zualinski, Assi.stant Dirictor for Pro)eats Di.vision 'of. TVA Pro)eats Of floe of Speoial Pro)eats V.S. Nuolear Regulatory Ccmanlssion 4350 East-Meet tlighmy Et "4 322 Sethesda, )maryland 20814 Brogans Ferry Resident Inspeotor Brows Ferry Nuolear Plant Route 2, P..O. Box 311 Athens i Alabama 35611 IV-15 600(207)

RETS Manua1 Revision 13 Page 257 U.S. Bualear Regulato' C olnm salon Qg) aa (Enclosures)!

!4r. C.. C.

C tech. Assistant Director t Reegionel lnePeetions Division ~ F DA Projects Otfiae ~ F SPeeL ~ 1 Projects .

U,S. I!uelear begulatory Commis o ss'on Region IZ

.. 101 IIarietta tt.. IM, u Lte 2900

~ S

'tlanta, Ceergia 30323 ..g Sale!Y Fiant Iir. J. l. ?veLLnsIIL P~ sis tant Director .

Brogans Ferry Y!Ic! et f or Projects DLvision ~ F TYA Projects Office of 5Peeial Projects OU 20 '87 U.S. IIua lear We gulatory u a Cormnlssion East Meat ItighMay I l4 IIIFO EI:M 322 Betbesda, Naryland 0 20814 I

~ ~

1 ~ ~

~ oo 4

~

Br'dms Ferry Res/dent::Inspeator n>u

!Bra'Mns Ferg .nuclear 2'lant u!e ~

~

~ Q ~

Route 2, P.O., box. 311 ~ ~

Athens, Alibaea 35611 JDMI JLT! KBL!CEL II.S ca (Enalosbres)!

C 0 RIHg, Ifg A}I 72A-C C. E. Ayers, LP 6U 25D-C E. S. Christenbury, E11 B33 C-K M. Il. Ilannu!a, .BR 1II 77B-C T. A. Zppolito Bet Bethesd'a lJ.censing Offi.an H. C Kasanas, LP @II 45II;C ~

J. A. Kir}!ebo 'IIL2 A12 C-K II J Hay, Brains Ferry C R }Iullee) BR $ S 168A-'C D. R. ILahols, BR 5S 100A-C Il. P. Pomre mrehn, Broms Ferry S. J. Sad.th,'LP 68 38A-C D. L. MLlliams, M10 B85 C-K IV-16 600(207)

e RETS Manual Revision,13 Page 258 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-OPO32, "Setup and Operating Procedure for the RDS-1000 Unit" and CNSI Procedure FO-OP-035, "Setup and Operating Procedure for Dewatering Pre-Coat Media in a 21-300 I.incr Using the RDS-1000" will be used.

1. EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORTS DW-11118&1-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; 20 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 SCEND 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-17 600(207)

RETS Manual Revision 13 Page 259 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 vill 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-1S 600(207)

RETS Manual Revision 13 Page 260

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 gA 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 gA 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-19 600(207)

BETS Hanual Revision 13 Page 26l FIGURE 2 llcfcr'enco: 'rowns l~rry Q oc Qil.ocnl l>>n (>>r ress>>io e>>>>tr>>l p>>>>gl FSaA 0.2 )b 'ig ri>>>>C CO>>I1CCtl>>ll Ift>>>>ll a>>il llltS-Iuuu ul ld l>>en( l>>>>

Qillli.'>>cat l>>>>

~

(9 lllC laiaL l>>>> (alter>>ace) ~

~ ~

~ ~ ~ ~ ~

~

fl. 3

~

10'I-fn.'O

~~

4444%00404 Ae+e%%4 4 e OO&eO 0 g s4eOOOO

~0 Mno Ogeeutst NollollA Ai i

~y

~

11<tlcl< 1 ll .ll.

IPo Haste Packaging Room Layout for Chem Nuc1ear System Plant Elevation 565'nnf IV-20 en71

RETS'anual Revxsxon 13 ti Ittt~~ Page 262 .

4 vrtITED sT'Tas NLJCLKAR RCCULATORY COMMISSION TTA5HINC ZO)). b C XOSSS Qftt+tlna end Sartl!

ar~!cr tt 1)'4~

't

~ ~ ~ ~ ~ ~ ~

'ocket 1(os. 50-259/260/296 Hay 6, 1968 'NY1 t wein. lL rrc+

Hr, S, A, Mh)te Hanaqer of 11ucl eat'ot)er Tennessee Ya I l ey Author) ty tCI

.611 38'ookout Place

~

1101 Harket Stree:

Chattattooqa, Tennessee 37402-2801

~ ~

t'ien t

) ~ r o~ I

Dear Hr. White:

SUBJKCT: IRTERIH APPAOYAL OF BAOM11S FKRAY PROC.SS CORTROL PROGRAH (T.'C 64700, 64701, 64702) fte have comofeted our revfex of the Broxns Ferry revised procesi contwl proqram (PCP} submf::ed xith your letter dated Octooer 15, 1987.

ln tire Broxns Ferr') PCP for. )mplement)nq the requ)rements of Sec:Ion 6.9 c the Technical Specff)catfons, the licensee has reftfrenced the folloxfnq

. vendor's i)cans)nq topical reports:

~ ~

l.'i'-11118401-P-A; Chem-Ruclear. Syst'ems'nc., CllSl Oexater)pq'Cont."ol .

.Process Con.afneri Topical Report.

~ ~

Z. RQS-25506-01-P; Chem-lluclear Sysiern, Inc., ROS-1000 Rad)oact)ve Ltaste Oetraterfnq Svster,"., Aev. 0.

Tooical Aeoor: llo. 1 aftove has been approved by the staff itfd accettted for referencfno )n future licensfnq attolica:)ons. The rema)n)nq tdpical reoor-.

(11O, 2) IS under revieX by the tlAC Staff. The RAC Staff'S rex)etl Of thfS too)ca I reoorz has qenerated ouest)ons reou)r)no the vendor of. the process (Chem-lluclear Svstems Inc.) to provide resttonses. The vendor responses trere submitted to thri 11ACr by letter dated Harch 31, 1988. The staff's preliminary <<

reviex of these resttonses has )nd)cat+d that th)s topical report )s acceptable for meet)nq tlie requ)rehents In Sec.)on 11.4 of Standard Rev)ex )'lan (SRP) and 10 CFR 61.

Based on our rev)ext'e find the rev)sed PCP for 8roxns Feint. Url)ts 1 2 and 3 acceotable as an Inter)m approval effective unt)l 'the llRC staff comp/etes

)ts'. reviex of the topfcirl report (Reference 2) descr)bed above:.: You may .-

proceed'xfth solid)ficatfon of rad)oac"fve wastes and dexater)nq of spent resin fn accordance xith the rev)sed Srot)ns Perry PCP. The basttfs for acceptance are conformance to the 1)censee's PCP to Branch Tejltgfcal Posft)on ETSB 11-3) SAP Sec.fon If.4, and to the requirements Q Section 6.9 of the Techni ca Speci f I ca tf ons.

~e 1

IV-21 600(207)

RETS Manual Revision 13 Page 263 Hr. S. A. Mhite Hay 6, 1988

~ I~

Jf vou have any ouestlons concerninq this issue, please contac: your Pro'e:

Hanaoer, G. Gears at 301-49Z-0767; S incere ly,

);.4,) 4.~

Robert A. Hermann, Acting Assistant Direc.-"r TVA Projects Division Office of Special Projects cc: See next paoe IV-22 600(207)

0 RETS Manual Revisi'on 13 Page 264 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.

l. 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.

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 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).

600(207)

RETS Manual Revision 13 Page 265 2 'TTACHMENT 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.

l. 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) w'ill 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 ~ater supply.

IV-24 600(207)

RETS Manual Revision 13 Page 266

4. WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement. Samples or smears, as appropriate, of standard vaste streams are sent offsite for analysis. An inferential measurement program is then established whereby concentrations of radioisotopes vhich 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 vaste 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.

IV-25 LAST PAGE 600(207)

ML18036B185

Contents

Text

SUBJECT:

References:

References:

System Design

System Design

References:

References:

References:

References:

References:

References:

References:

Reference:

Reference:

Reference:

Reference:

Reference:

1.0 INTRODUCTION

3.0 REFERENCES

Reference:

Reference:

Reference:

Dear Hr. White:

Navigation menu

ML18036B185

Text

SUBJECT:

References:

References:

System Design

System Design

References:

References:

References:

References:

References:

References:

References:

Reference:

Reference:

Reference:

Reference:

Reference:

1.0 INTRODUCTION

3.0 REFERENCES

Reference:

Reference:

Reference:

Dear Hr. White:

Navigation menu

Search