Text

Annual Radioactive Effluent Release Report
	ML031270460
Person / Time
Site:	Callaway
Issue date:	04/29/2003
From:	Shafer D; AmerenUE
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ULNRC-04840
	Download: ML031270460 (192)
	v • d • e

Union Electric One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, AMO 63166-6149 314621.32z2 April 29, 2003 U. S. Nuclear Regulatory Commission Aftn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen:

wDmereu ULNRC-04840 U1f DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC Co.

FACILrTY OPERATING LICENSE 2002 ANNUAL RADIOACTIVE NPF-30 EFFLJENT RELEASE REPORT Please find enclosed the 2002 Annual the Callaway Plant. This report is Radioactive Effluent Release Report submitted in accordance with Section for Technical Specification. 5.6.3 of the Very truly yours, David Shafer Acting Manager, Regulatory Affairs BFWmlo Enclosure AOD9 I iE a subsidiary ofAmeren Corporation II

ULNRC-04840 April 29, 2003 Page 2 copy) cc: U. S. Nuclear Regulatory Commission (Original and 1 Attn: Document Control Desk Mail Stop P 1-137 Washington, DC 20555-0001 Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102 Mr. Gerhard K. Samide ANI Account Engineer Town Center, Suite 3005 29 S. Main St.

West Hartford, CT 06107-2445 Regional Administrator Department of Natural Resources Central Regional Office P.O. Box 176 Jefferson City, MO 65102-0176

2002 Callaway Plant Radioactive Effluent Release Report

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29:97a off t tatsti 1.0 Introduction ......................................... 1 2.0 Supplemental Information ........................................ 2 2.1 Regulatory Limits .2 2.2 Average Energy .3 2.3 Measurements and Approximations of TOTAL RADIOACTIVITY .3 2.4 Batch Releases .4 2.5 Abnormal Releases .4 3.0 Summary of Gaseous Radioactive Effluents ................... ...................... 5 4.0 Summary of Liquid Radioactive Effluents .............. ........................... 6 5.0 Solid Wastes ........................................ 7 6.0 Related Information ......................................... 7 6.1 Unplanned Releases .7 6.2 Changes to the Offsite Dose Calculation Manual .10 6.3 Major Changes to Radwaste Treatment Systems .10 6.4 Land Use Census Changes .10 6.5 Inoperability of Effluent Monitoring Instrumentation .10 6.6 Instances of Liquid Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits ............ 10 7.0 Meteorological Data ....................... 11 8.0 Assessment of Doses ....................... 13 8.1 Dose at the Site Boundary from Gaseous Effluents .13 82 Dose to the Member of the Public .13 8.3 Total Dose Due to the Uranium Fuel Cycle .14 8.4 Dose Due to Liquid Effluents .14 List of Tables 1A Annual Summation of Gaseous Releases 1B Annual Airborne Continuous and Batch Releases 2A Annual Summation of Liquid Releases 2B Annual Liquid Continuous and Batch Releases 3 Solid Waste and Irradiated Fuel Shipments 4 Cumulative Joint Frequency Distributions 5 Dose at the SITE BOUNDARY and Nearest Resident 6 Dose to the Member of the Public from Activities within the SITE BOUNDARY 7 Total Dose Due to the Uranium Fuel Cycle 8 Dose Due to Liquid Effluents i

I.o if dI fticn This report describes the Union Electric Co. Callaway Plant radioactiveeffluent releasesfor2002. It is submitted in accordance with Section 5.6.3 of the Callaway Plant Technical Specifications.

A summary of radioactiviy released in liquid andgaseous effluents and solid waste shippedfrom the Callaway Plant during the periodfrom January 1, 2002 to December 31, 2002 ispresented.

All liquid andgaseous effluents dischargedduring this reporting period complied wvit federal regulationsand the limits in the Offsite Dose CalculationManual (ODCM). Any exceptions are noted in this report.

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2.0 Supplemental Tnffoxnation 2.1 Regulatory Limits (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to The Radiological Effluent Control (REC) limits the following:

applicable to the release of radioactive material in liquid and gaseous effluents are provided below. a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, Fission and Activation Gases (Noble Gases) b. During any calendar year: Less than or equal to The dose rate due to radioactive noble gases 15 mrem to any organ.

released in gaseous effluents from the site to areas at and beyond the site boundary shall be Liquid Effluent limited to less than or equal to 500 mrem/yr to the The concentration of radioactive material total body and less than or equal to 3000 mrem/yr released in liquid effluents to unrestricted areas to the skin. shall be limited to ten times the concentrations The air dose due to noble gases released in specified in Appendix B, Table 2, Column 2 of gaseous effluents, from each unit, to areas at and I OCFR20 for radionuclides other than dissolved beyond the site boundary shall be limited to the or entrained noble gases. For dissolved or following: entrained noble gases, the concentration shall be limited to 2.OE-04 microcuries/ml total activity.

a. During any calendar quarter Less than or equal to 5 mrad for gamma radiation and less than or The dose or dose commitment to an Individual equal to 10 mrad for beta radiation and, from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or a. During any calendar quarter to less than or equal to 20 mrad for beta radiation. equal to 1.5 mrem to the total body and less than orequal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to Radioiodine, Tritium, And Particulates 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

The dose rate due to lodine-131 and 133, tritium and all radionuclides inparticulate form with Uranium Fuel Cycle Sources half-lives greaterthan eight (8)days released in The annual (calendar year) dose or dose gaseous effluents from the site to areas at and commitment to any Member of the Public due to beyond the site boundary shall be limited to less releases of radioactivity and to radiation from than or equal to 1500 mrem/yr to any organ. uranium fuel cycle sources shall be limited to less The dose to a Member of the Public from than or equal to 25 mrem to the total body or any lodine-1 31 and 133, tritium, and all radionuclides organ, except the thyroid, which shall be limited to in particulate form with half-lives greater than eight less than or equal to 75 mrem.

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2.0 Supplemental Informatioon Cantltued 2.2 Average Energy This requirement is not applicable to the Callaway Plant radiological effluent monitoring program since the release rate limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture.

2.3 Measurements and Approximations of Total Radioactivity Radionuclide concentrations in liquid and gaseous effluents were obtained by effluent sampling and radiological analysis in accordance with the requirements of Final SafetyAnalysis Report Table 16.11-1 and Table 16.11-4.

Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, Fe-55, and transuranic nuclides by an independent laboratory. Tritium and gross alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively.

The total radioactivity in effluent releases was

- determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.

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2.0 Supplemental Information Continued 2.4 Batch Releases Summary information relating to batch releases of gaseous and liquid effluents to the environment from the Callaway Plant during this year is presented below.

LiQUm UNITS JAN-JUN JUL-DEC Number ofbatch releases: 99 121 Total time period for batch releases: Minutes 44,527 52,301 Maximum time period forbatch releases: Minutes 1,028 515 Average time period for batch releases: Minutes 450 432 Minimum time period for batch releases: Minutes 365 275 Average Missouri River flow during periods of effluent release to the river1 : ft3 /sec 82,969 40,346 GASEOUS UNITS JAN - JUN JUL-DEC Number ofbatch releases: 38 36 Total time period for batch releases: Minutes 4,141 6,579 Maximum time period for batch releases: Minutes 2,273 2,437 Average time period for batch releases: Minutes 109 183 Minimum time period for batch releases: Minutes 23 24 I E-mail, S. Ternes, United States Department of the Interior- Geological Survey - Water Resources Division dated January 3, 2002 2.5 Abnormal Releases LIQUID GASEOUS

_ Numberof releases: I Numberof releases: 4 Total Activity released: 0 Total Activity released: 1.4 Curies 4

3.0 Summary of Gaseous Radloactive Eftluents The quantity of radioactive material released in gaseous effluents during the year is summarized in Tables lAand '1B. During 2002, all gaseous effluents were considered as ground level releases.

Gaseous effluents from the plant are continuously monitored.

Instrumentation provides on-line and grab sampling for iodine, particulates and noble gas.

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4.0 Summary of Liquid Radioactive Effluents The quantity of radioactive material released in liquid effluents during the year is summarized in Tables 2Aand 2B. During 2002, there was no continuous release of liquid effluent from the plant.

Liquid effluents from the plant are continuously monitored.

Shown is a liquid monitor shielded by lead to increase its sensi-tivity for sampling discharged water.

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5.0 s , 1 ik The quantities of radioactive material released of each nuclide listed in Table 3 was determined in shipments of solid waste for burial and

as the product of the fractional abundance and the irradiated fuel transported from the site during the

total curies shipped. Those nuclides which yearare summarized in Table 3. The total quantity : comprise at least 1%of the total activity for a and radioactivity reported in Table 3 for each : particular waste type are presented in Table 3.

waste type was for waste buried and includes wastes buried by waste reprocesses after volume reduction. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration 6.0 11 22 atei3n:zti m 6.1 Unplanned Releases of contamination leached from the sludge and were detected in the boiler water.

Unplanned releases are:

An investigation was performed to locate the

1) Inadvertent or accidental source of the contamination. No miss-positioned releases of radioactive material. valves or leaks were identified. The results of

2) Releases of radioactive material sampling different system components were via normal pathways without a inconclusive, but may indicate a small leak in the release permit, proper SLWE heat exchanger. During refueling authorization, or proper sampling operations, the concentration of radioactive and analysis. nuclides in the SLWE system can be a factor of 1000 times higher than normal operations. The

3) Releases which are conducted in size of the leak may be small enough to only be

- such a manner as to result in recognized when these high concentrations are significant deviation from the present. Increased monitoring was initiated in an requirements of the release attempt to identify the source of the contamination.

permit. No additional contamination was identified.

Auxiliary Boiler Contamination A 10CFR50.59 evaluation concluded that the resulting dose to a Member of the Public from the On April 10, 1998, during a refueling outage, release of radioactive material to the radioactivity was detected in the Auxiliary Boiler environment would be a small fraction of the feed water system. The boiler was flushed and regulatory dose limits. Therefore, continued cleaned several times in an attempt to operation of the Auxiliary Boiler would not pose decontaminate the unit. Small amounts of any significant safety or environmental concern.

contamination remained in the sludge. During subsequent operation of the boiler small amounts The Auxiliary Boiler was operated intermittently 7

6.0 bhtdT I-c 7I during 2002. The maximum total body dose to a reached 0 psig on 2/14/02, the release was Member of the Public from these releases was secured. The resultwas an unplanned release, 3.11E-04 mrem during 2002. This is negligible since WGDT "E"was released using a non compared to the quarterly and annual effluent conservative pre release permit (CAR control limits. The activity released from the 200201032).

Auxiliary Boiler during 2002 is included in Tables To prevent reoccurence, Health Physics 1A,1 B,5,6 and 7. Technical procedure HTP-ZZ-02007 was revised to open all WGDT pre release permits with a conservative end pressure of 0#.

Containment Equipment Hatch The total amount of radioactivity released during the unplanned release was 0.537 Curies. The Air samples taken outside of the Containment total body dose to a Member of the Public from Equipment hatch during RF012 indicated this release was 0 mrem.

reactor produced isotopes. The releases of radioactivity from the Containment Equipment hatch were quantified and documented in CAR Laundry Decontamination Facility Dryer 200207059. The total amount of activity Exhaust Monitor Failure released from the Containment Equipment hatch was approximately 0.852 Curies, primarily On 10/23/02 at 2210, the Laundry consisting of Tritium. Decontamination Facility (LDF) Dryer Exhaust The maximum total body dose to a Member of monitor (GL-RE-0202) sample pump was found the Public from these releases was 1.31 E-05 inoperable (CAR 200206618). Normally, dryer mrem during 2002. This is negligible compared operations are automatically secured when to the quarterly and annual effluent control limits. monitor vacuum is lost. However, in this instance, The activity released from the Containment the associated trip functions did not perform as Equipment hatch during 2002 is included in designed and dryer operation continued.

Tables 1A, 1B, 5,6, and 7. Immediately upon discovery, dryer operation was secured as per FSAR Table 16.11-5, the sample filter was analyzed, and the LDF release permit was closed.

Non Conservative WGDT Release Permit An investigation was conducted and it was determined that GL-RE-0202's sample pump had On 2/12/02, a discharge permit for Waste Gas inadvertently lost power due to a scheduled bus Decay Tank (WGDT) "E"was generated prior to outage. Surveillances were conducted on 10/24/

release. The initial termination pressure for the 02 to test the trip and/or logic functions associated WGDT release permit was set at 5 psig based on with the LDF dryer exhaust monitor. The tests plant operational needs. Itwas laterdetermined were completed satisfactorily.

plant operational needs required that WGDT "E" pressure be lowered to 0 psig vs. 5 psig indicated The total body dose to a Member of the Public on the pre release permit. On 2/12/02, the release from this release was 0 mrem.

of WGDT "E"was commenced using the original pre release permit. When WGDT "E" pressure 8

6.0 , ffc 'I" F f '

6.0 ftRflEtLfl Liquid Effluent Composite Sample FSAR Table 16.11-1 for each radionuclide except Inadvertantly Discarded for Sr-89. The LLD for Sr-89 was not achieved due to insufficient sample volume and its relatively A large portion of the third quarter liquid effluent short half-life of 50.52 days.

-4 composite sample was inadvertantly discarded The remaining transuranics listed in FSAR (CAR 200206136). A small portion of the sample was recovered from the composite bottle and sent Table 16.1 1-1 were not specifically analyzed for by Environmental Inc. due to insufficient sample to Environmental Inc. for analysis.

volume. However, since the sample was analyzed Miscommunication, poor assumptions, and forgross alpha, a conservative estimate of failure to follow written guidance contributed to the transuranic activity was made. Based on this error. Immediate corrective actions were taken to estimate, the liquid effluent concentration limits prevent reoccurence, such as Caution signs,

described in FSAR 16.11.1.1 were not exceeded.

coaching of personnel, and more detailed written instructions.

An investigation was conducted, focusing on all of the liquid discharges during 2002 through the third quarter. Each discharge was evaluated with respectto the nuclides present and the Post e' Dilution Concentration/ECL to determine and/or ensure the limits described in FSAR 16.11.1.1 were not exceeded. The results revealed that the average Post Dilution Concentration/ECL values for the 1st and 2nd quarters of 2002 were higher

. than the 3rd quarter. It was also determined that the discharges with higher Post Dilution/ECL values (approaching the limit equal to 1) were primarily influenced and/or due to the presence of H-3.

The first and second quarter composite results were reviewed for consistency and comparison to ensure the limits of FSAR 16.11.1.1 were not exceeded.

The liquid effluent composite sample results were returned from Environmental Inc. Midwest Laboratory on 11/22102. Due to the small sample volume, Environmental Inc. was only able to analyze the sample for Fe-55, Sr-89/90 and gross alpha at a 95% confidence level. The results indicated that Fe-55, Sr-89/90, and gross alpha were below detectable levels. Environmental Inc.

was able to achieve the required LLDs listed in 9

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6.0 T, rX .-IF tim 6.2 Changes to the Offsite Dose 6.4 Land Use Census Changes Calculation Manual No changes were identified that required a Changes were made to the Callaway Offsite change to the location of the nearest resident Dose Calculation Manual (plant procedure APA- yielding the highest calculated dose ZZ-01 003) during 2002. The manual was revised commitment.

to reflect the changes for OL 1218, Rev. 1; License Amendment no.152 allowing the Containment Equipment hatch and Emergency air lock to 6.5 Inoperability of Effluent remain open during refueling activities (FSAR CN- Monitoring Instrumentation 01-030 and CN-02-049). The amendment eliminated FSAR 16.11.2.4.1B and subsequently During 2002 all effluent monitoring deleted the core alteration setpoint value of 5.OE-3 instrumentation was OPERABLE within the uCi/cc forthe Containment Purge Monitors GT- limits specified in Radioactive Effluent RE-22 and GT-RE-33. The alarm setpoints for the Controls 16.11.1.3 and 16.11.2.4.

Containment Purge Monitors will be based on the methodology described in Section 3 of the ODCM. A copy of APA-ZZ-01 003 (ODCM) and 6.6 Instances of Liquid Holdup FSAR 16.11 is attached to this report. Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits 6.3 Major Changes to Radwaste All liquid tanks and waste gas decay tanks Systems were within limits specified in Radioactive During 2002, there were no major plant Effluent Controls 16.11.1 and 16.11.2 during modifications to the gaseous, solid, or liquid the reporting period.

radwaste treatment systems.

The following minor modification was made to the gaseous radwaste system during 2002.

Modification Package 98-2019 added a new ozone generator, monitor, and alarm to the Decontamination System. The new Ozone Generator has successfully passed it re-test and is ready for service. The future plan is to use the Ozone Generator for laundry processing.

Currently, Design Modification 01-1 001 has been initiated to permanently install a liquid waste processing (demineralization) system. The new system will eliminate the need for the Secondary Liquid Waste Evaporator. RFR22518Awas initiated to retire this evaporator.

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7.0 I da _3t The on-site meteorological data for this reporting period is presented in Table 4. All MET data was reviewed and validated by a boundary layer meteorologist. The data is presented as Cumulative Joint Frequency Distributions of wind speed and wind direction by atmospheric stability class for the 10 and 60 metertower elevations.

Valid data recovery for 2002 was greater than 90% for all required parameters. I Atime dependent intermittent offset was found between the primary and secondary tower I Om wind speeds. Subsequent investigation found that i the primarytowerwind speeds were frequently I being overestimated, by variable amounts, when I I

the tower strobe light automatically switched to - - I night mode. Electrical interference from the strobe I caused higher than actual wind speeds to be

- t recorded. Algorithms were developed to detect T t

the affected data periods. Secondary tower 1Om i I

wind speed data was substituted for the primary i i

tower 1Om level data. Upper level 60m and 90m iI data were adjusted based on measured offsets.

The efficacy of the correction method was verified by determination of 6 month period values of stability dependent wind speed power-law expo- Picturedis the Secondary Meteological nents for both previous (unaffected data) and Tower. This station obtains measurements at a corrected data. The results compared favorably. height of 10 meters, and provides backup data The strobe light operations were modified on 4/19/ for the Primary Meteological Tower readings at 02, which ended the interference. The 100% 10, 60 and 90 meters.

availability of the secondary tower 1Om wind speed data during the interference periods re- placed out of service (CAR 200205532). Similar sulted in no affected or corrected data being used problems were encountered in 2001 (CAR for the dose assessment calculations. The per- 200105528) and to prevent reoccurrences, bird cent of good data for the 10 meter wind speed for spikes have now been installed on the crossarms 2002 approached 100% after corrections. Plant of the anemometers.

corrective action document CAR 200202583 During the loop calibration surveillance in provides the details on this event. October, the Primary MET tower 1Om wind direc-During 2002, portions of the Primary Met Tower tion data was offset when the crossarm adapter 60 and 90 meter wind speed data were found to collar for the anemometer was inadvertently ro-be affected by the perching of large birds on the tated on the crossarm. The problem was discov-anemometers. The effects from this nuisance ered when a distinct offset was observed in the ranged from single 15 min periods being invali- data from the primary 1Om wind direction when dated to the anemometers being damaged and compared to the other 3 directional channels 11

7.0 Meteorological Data (continued)

(CAR 200300533). Discriminatory differential analysis, using all directional data obtained during well-mixed daytime periods of neutral stability, confirmed the offset to be a constant value (of about 46 deg). The primary 1Om wind direction data were subsequently corrected before disper-sion calculations were performed.

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8.0 2: :1:1: :F3t o :

Assessment of doses to the maximum exposed Cycle to any Member of the Public, the critical individual from gaseous and liquid effluents Member of the Public within the Site Boundary, released was performed in accordance with the and the Nearest Resident were each evaluated.

ODCM as described in the following sections. For all effluents released from the Callaway Plant DoseAt The NearestResident From during this year, the annual dose to the maximum Gaseous Effluent exposed individual was less than 1% of the Radiological Effluent Control Limits presented in The dose to the Nearest Resident was due to Section 2.1 of this report. plume exposure from noble gases, ground plane exposure, and inhalation and ingestion. Dose was calculated at the nearest actual residence with the most limiting atmospheric dispersion (based on 8.1 Dose at the Site Boundary from actual meteorological conditions for the year). It Gaseous Effluents was conservatively assumed that each ingestion The dose at the Site Boundary was due to pathway (meat, milk, and vegetation) existed at plume exposure from noble gases, ground plane this location. Dose was conservatively calculated exposure, and inhalation. Itwas conservatively assuming the child as the critical age group.

assumed that a hypothetical maximum exposed Dose from activities within the Site Boundary was individual was present at the Site Boundary negligible and not included in this calculation.

location with the most limiting atmospheric The doses to the Nearest Resident for 2002 are dispersion (based on actual meteorological presented in Table 5.

conditions forthe year). Dose was conservatively calculated using a child as the critical age group.

The dose from gaseous effluents at the Site Dose To The Member Of The PublicFrom Activities Within The Site Boundary Boundaryfor 2002 is presented in Table 5.

Based on the land use within the Site Boundary, the Member of the Public with the highest dose 8.2 Dose to the Member of the was a farmer. Dose from farming activities within the Site Boundary was due to direct radiation Public exposure, plume exposure from noble gases, The Member of the Public is considered to be a ground plane exposure, and inhalation. The real individual, not occupationally associated with current tenant farmer estimates spending 1100 the plant, who uses portions of the plant site for hours per yearworking within the Site Boundary recreational or other purposes not associated with area. Dose-was calculated using the adult as the plant operation. This individual's utilization of critical age group.

areas both inside and outside the Site Boundary Dose to the Member of the Public from activities was characterized for this calculation and is within the Site Boundary is presented in Table 6.

described in the ODCM.

To evaluate total dose from the Uranium Fuel 13

8.0 Assess of rut; 8.3 Total Dose Due to the Uranium Fuel Cycle Since there are no other Uranium Fuel Cycle facilities within 8 kilometers of the Callaway Plant, the total dose to the most likely exposed Member of the Public resulted from direct radiation exposure and radioactive effluents from the Callaway Plant itself.

The total dose to the Member of the Public (Table 7) was the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence. It was conservatively assumed that each food ingestion pathway exists at his residence and that the adult is the critical age group.

The total dose from the Uranium Fuel Cycle is presented inTable 7.

8.4 Dose Due to Liquid Effluents Dose due to liquid effluents includes contributions from the maximum exposed individual's consumption of fish and recreational activities. An adult was considered the maximum exposed individual inthis assessment.

Itis conservatively assumed that the hypothetical maximum exposed individual obtained his entire annual fish intake from near the plant discharge.

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hb7e IA ; a SzmErim of (a zs 1 1ck AllAirborneEffluents TAB LE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2,2002 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CURIES 1.22E+00 1.08E+00 20

2. AVERAGE RELEASE RATE FOR PERIOD uCt/SEC 1.57E-01 1.37E-01

3. PERCENT OF TECH SPEC LIMIT N/A N/A B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 0.00E+00 0.00E+00 l12311

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 0.00E+00 0.OOE+O l

3. PERCENT OF TECH SPEC LIMIT % N/A N/A C. PARTICULATES

1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 1.65E-04 8.69E-07 30 l

2. AVERAGE RELEASE RATE FOR PERIOD uCt/SEC 2.12E-05 1. lIE-07

3. PERCENT OF TECH SPEC LIMIT N/A N/A

4. GROSS ALPHA RADIOACTIVITY CURIES 8.51E-08 0.00E+00 D. TRITIUM I 1. TOTAL RELEASE l CURIES 1.69E+01 l 1.07E+01 l i14i1

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.18E+00 1.36E+00

3. PERCENT OF TECH SPEC LIMIT I N/A jN/A (a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page I of 1 15

1bl 1A 2 az 1 D 3 2 aSU M t i s AOf I1 AllAirborne Effluents Continued TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 3 AND 4.2002 THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CURIES l .40E+O00 2.09E+00 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC l 1.76E-01 2.63E-01

3. PERCENT OF TECH SPEC LIMIT % N/A N/A B. RADIOIODINES 1.TOTAL IODINE-131 CURIES 0.00E+00 3.34E-06 23

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 0.00E+00 4.20E-07

3. PERCENT OF TECH SPEC LIMIT 1 IN/A jN/A C. PARTICULATES

1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 7.79E-05 1.13E-04 30

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 9 80E-06 1.42E-05

3. PERCENT OF TECH SPEC LIMIT % N/A N/A

4. GROSS ALPHA RADIOACTIVITY CURIES 1.17E-07 2.94E-07 D. TRITIUM

1. TOTAL RELEASE CURIES I1.29E+01 12.28E+01 14

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.62E+00 2.87E+00

3. PERCENT OF TECH SPEC LIMIT I% IN/A I N/A (a) Safety AnalysLs Calculation 87-063-00, January 6, 1988 Page I of I

Mb1B enianwaAih ct+/-ruzs Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES. AND PARTICULATES QUARTERS 1 AND 2,2002 I.CONTINUOUS RELEASES I BATCH RELEASES I FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER ARTER I Q UARTER QUARTER

1. FISSION GASES XE-138 CURIES 1.20E1-01 O.OOE+00 1.48E-04 0.OOE-+00 AR-41 CURIES O.00E+00 O.OOE+00 4 44E-02 5.24E-02 XE-133 CURIES 2.63E-01 5.82E-01 1.95E-01 2.30E-01 XE-135 CURIES 5.82E-02 5.09E-02 1.61E-03 1.38E-03 XE-131M CURIES 0 OOE+00 1.62E-01 3 62E-08 0.00E-+00 XE-133M CURIES 0.00E+--00 0.00E+00 1.89E-03 7.90E-04 KR-85 CURIES 0 OOE+00 0.00E-+-00 5.37E-01 0.OOE+00 TOTAL FOR PERIOD CURIES 4.41 E-01 7.95E-01 7.80E-01 2.84E-01 2.IODINES 1-132 CURIES 0 OOE+00 0.00E+00 4.05E-09 0 00E-+-00 TOTAL FOR PERIOD CURIES 0.00E+00 O.OOE+00 4 05E-09 l0 00E+--00

3. PARTICULATES CS-134 CURIES 0.00E+.00 0.OOE+00 2.51E-05 3.24E-07 CS-137 CURIES 1.50E-06 2.34E-07 2.80E-05 2.54E-07 CE- 144 CURIES O.00E+00 0.00E+00 5 67E-08 0 OOE+00 CO-60 CURIES 0 OOE+00 O.OOE+00 6.82E-05 4.38E-08 SB-125 CURIES 0 OOE+00 O.OOE+00 4.20E-05 0.OOE+-00 CO-57 CURIES 0 00E+00 0.OOE+00 1.44E-09 0 OOE+00 CR-51 CURIES 0.00E+00 0.00E+00 0 OOE+00 7.26E-09 BA-139 CURIES 0 OOE+00 O.OOE+00 0.00E+00 5.86E-09 ALPHA CURIES 8.5 1E-08 0.OOE+00 0 OOE+00 0.0OE+00 TOTAL FOR PERIOD CURIES 1.58E-06 2.34E-07 1.'63E-04 6.35E-07 4 TRITIUM IH-3 CURIES 1.66E+01 1.03E+01 2.73E-01 4.08E-01 Page I of I v/1

Table lB SAa A Batch Releases, GroundLevel Releases Fission Gases, lodines, and Particulates TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES. IODINES, AND PARTICULATES QUARTERS 3 AND 4, 2002 CONTINUOUS RELEASES I BATCH RELEASES THI1RD FOURTH THIRD lFOURTEW lNUCLIDE UNITS OUARTER QUARTER QUARTER QUARTER

1. FISSION GASES XE-138 CURIES 0.00E+00 O.OOE+00 9.60E-05 O.OOE+00 AR-41 CURIES 0.OOE+00 0.OOE+00 5.86E-02 2.16E-01 XE-133 CURIES 7.99E-01 9.S1E-01 1.79E-01 5.70E-01 XE-135 CURIES 2.96E-01 1.77E-01 1.07E-03 8.18E-03 XE-131M CURIES 0.00E+0O 0.OOEO4-00 O.OOE+00 1.23E-04 XE-133M CURIES O.OOE+O0 2.24E-02 1.08E-04 1.79E-06 KR-85 CURIES O.OOE+00 0. OOE+00 O.OOE+00 1.05E-O1 KR-85M CURIES 1.22E-02 1.54E-03 O.OOE+OO 0.OOE+00 KR-87 CURIES 1.82E-02 2.31E-03 O.OOE+00 8.50E-05 KR-88 CURIES 3.39E-02 4.30E-03 O.OOE+0O O.OOE+00 TOTAL FOR PERIOD CURIES 1.16E+00 I.19E+00 2.39E-01 8.99E-01

2. IODINES I-132 CURIES O.OOE+-OO 8.71 E-05 O.OOE+00 6.02E-05 1-133 CURIES 0.OOE+00 O.OOE+00 2.08E-09 O.OOE+OO 1-131 CURIES O.OOE+00 2.43E-06 O.OOE+00 9.06E-07 TOTAL FOR PERIOD CURIES O.OOE+00 8.96E-05 2.08E-09 6.1 IE-05

3. PARTICULATES CS-134 CURIES 1.54E-06 2.02E-07 O OOE+00 5.12E-07 CS-137 CURIES 1.16E-05 7.64E-06 O.OOE+00 1.51 E-05 CE-144 CURIES O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 CO-60 CURIES 1.OOE-05 6.83E-06 2.30E-09 2.33E-05 SB-125 CURIES 5.45E-05 4.06E-05 O.OOE+00 0.OOE+00 CO-57 CURIES 0.OOE+00 0.00E+00 0.OOE+00 1.87E-08 CR-51 CURIES 0.OOE+00 O.OOE+00 O0.OOE+00 3.08E-06 BA-139 CURIES 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TC-101 CURIES O.OOEE+00 O.OOE+00 5.44E-09 0.OOE+00 MN-54 CURIES 1.86E-07 0.00E+00 0.00E+00 1.15E-07 CE-141 CURIES O.OOE+00 O.OOE+00 O.OOE+00 2.39E-08 Y-91NM CURIES O.OOE+00 O.OOE+00 O.OOE+00 9.83E-08 CO-58 CURIES O.OOE+00 4.83E-07 0.00E+00 9.24E-06 NB-95 CURIES 0.OOE+00 .OOE+00 0.00E+00 8.31 E-07 ZR-95 CURIES O.OOE+00 O.OOE+0O O.OOE+00 2.55E-07 RU-103 CURIES 0.OOE+00 O.OOE+00 O.OOE+00 4.26E-06 MO-99 CURIES O.OOE+00 O.OOE+00 O.OOE+00 3.20E-08 Page 1 of 2 IR

2W5e 1B SeniAm-M 7i 0r+/-?W1S I Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE IB (continued)

SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES. AND PARTICULATES QUARTERS 3 AND 4,2002 ICONTINUOUS RELEASES BATCH RELEASES l THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

3. PARTICULATES TC-99M CURIES 0.OOE+00 0 00E+00 0.OOE+00 3.20E-08 ALPHA CURIES 1.17E-07 2.94E-07 O.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 7.80E-05 5.60E-05 7.74E-09 5.69E-05

4. TRTIIUM H-3 CURIES 1.23E+01 Z2.15E+0I 5.64E-01 1.34E-+-00 Page 2 of 2 2WA 2A z 31 ,tia2 B of-w ea All Liquid Effluents TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS I AND 2,2002 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA] CURIES 5.50E-03 5.68E-03 20

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.04E-08 1.14E-08

3. PERCENT OF APPLICABLE LIMIT % NA N/A B. TRITIUM

1. TOTAL RELEASE

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD CURIES uCi/ML f 4.98E+02 9.37E-04 21 6E+02 4.33E-04 14

3. PERCENT OF APPLICABLE LIMIT % N/A N/A C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 7.7_1E-04 1.34E-03 27 1

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.45E-09 2.70E-09 D. GROSS ALPHA RADIOACTIVITY 1.TOTAL RELEASE CURIES 0.00E+00 0.OOE+00 l 29 1 E. WASTE VOLUME RELEASED (PRE-DILUTION) GAL 4.711E+06 4.46E+06 10 F. VOLUME OF DILUTION WATER USED lGAL 1.36E+08 I 1-27E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 1 of 1 20

2aim2A 2~zmticnafO id All Liquid Effluents TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4,2002 THIRD FOURTH ESTTOTAL TYPE OF EFFLUENT UNITS QUARTER I QUARTER IERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING m TRMUM, GASES, ALPHAI CURIES 1.19E-02 1.57E-0I 20

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.87E-08 2.55 E-07

3. PERCENT OF APPLICABLE LIMIT % N/A N/A B. TRITIUM

1. TOTAL RELEASE CURIES 2.01E+02 2.32E+02 141]

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.15E-04 3.77E-04

3. PERCENT OF APPLICABLE LIMIT % N/A N/A C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES l 8.80E-03 l 7.56E-02 1 32711 2.AVERAGE DILUTED CONCENTRATION 11 I UCML 1.38E-08 1.23E-07 DURING PERIOD D. GROSS ALPHA RADIOACTIVITY I. TOTAL RELEASE CURIES I 8.76E-06 l2.98E-03 29 I E. WASTE VOLUME RELEASED (PRE-DILUTION) lGAL I 5.66E+06 I 5.53E+06 10 I F. VOLUME OF DILUTION WATER USED lGAL I 1.63E+08 I 1.57E*-08 10 I

-v (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 1 of 1 21

Tabl 2B .iBr ia & i &

Totals for Each Nuclide Released TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 1 AND 2, 2002 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. ALL NUCLIDES H-3 CURIES 0.OOE+00 0.00E+00 4.98E+02 2.16E+02 SB-125 CURIES 0.OOE+00 0 00E+00 4.OOE-03 4.25E-03 SR-90 CURIES 0.OOE+00 0.OOE+00 1.26E-04 0.OOE+00 CE-.144 CURIES 0 OOE+00 0.OOE+00 1.38E-05 0.00E+00 CS-134 CURIES 0 OOE+00 0.OOE+00 3.32E-04 2.95E-04 CS-137 CURIES 0 00E+00 0.OOE+00 7.22E-04 7.61E-04 PR-144 CURIES 0 OOE+00 0.OOE+00 1.38E-05 0.00E+00 1-131 CURIES 0 OOE+00 0.OOE+00 1.22E-06 2.46E-06 CO-60 CURIES 0 00E+00 0.OOE+00 2.53E-04 2.82E-04 HF-181 CURIES 0.OOE+00 0.OOE-i-00 2.02E-06 1.60E-06 MN-54 CURIES 0 OOE+00 0.00E+00 3 65E-06 1.48E-05 CO-58 CURIES 0 0OE+00 0.00E+00 9.27E-06 5.69E-05 XE-133 CURIES 0 OOE+00 0.OOE+00 7.71E-04 1.34E-03 TC-99M CURIES 0 OOE+00 0.OOE+00 3.75E-06 0.OOE+00 BE-7 CURIES 0.OOE+00 0.OOE+00 2.02E-05 0.OOE+00 CM-242 CURIES 0 OOE+00 0.00E+00 1.84E-07 1.03E-05 CR-51 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.25E-05 TOTALS FOR PERIOD CURIES 0.OOE+00 0.OOE+00 4.98E+02 2. 16E+02 Page I of I

) .J

MIN 2B I2 Luipidzs &Batdi BO Totals for Each -Nuclide Released TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 3 AND 4,2002 CONTINUOUS RELEASES THIRD lFOURTH BATCH RELEASES I THIRD lFOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER 1.ALL NUCLIDES H-3 CURIES O.OOE+00 0.OOE+00 2.01E+02 2.32E+02 SB-125 CURIES O.OOE+00 O.OOE+00 1.07E-02 7.8lE-02 SR-90 CURIES O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 CE-144 CURIES O.OOE+00 O.OOE+00 .OOE+OO00 2.69E-05 CS- 134 CURIES O.OOE+00 O.OOE+00 1.90E-04 6.16E-04 CS-137 CURIES O.OOE+00 O.OOE+00 6.14E-04 1.90E-03 PR-144 CURIES .OOE++00 0.EOOE00 +.OOE+00 2.69E-05 1-131 CURIES O.OOE+00 O.OOE+OO00 .OOEO00 3.97E-05 CO-60 CURIES O.OOE+00 0.OOE+00 2.13E-04 1.74E-03 HF-181 CURIES O.OOE+OO O.OOE+00 1.07E-06 0.OE+00 MN-54 CURIES 0.OOE+0O O.OOE+00 O.OOE+00 5.89E-05 CO-58 CURIES O.OOE+00 .OOE+00 2.26E-05 6.65E-02 XE-133 CURIES O.OOE+00 O.OOE+00 8.71E-03 7.31E-02 TC-99M CURIES O.OOE+00 O.OOE+F O0.00E-i-00 2.58E-05 BE-7 CURIES O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CM-242 CURIES O.OOE+00 O.OOE+00 OOE+00 0 O.OOE+OO CR-51 CURIES O.OOE+00 0 OOE+00 1.72E-04 5.83E-03 NB-95 CURIES O.OOE+00 O.OOE+00 3.48E-06 1.08E-04 TE-129 CURIES O.OOE+00 0 OOE+00 4.98E-05 0 OE+00 XE-131M M.OOE÷00 CURIES 0.OOE+0 9.54E-05 O.OOE+00 CE-141 CURIES 0..+OO00 O.OOE+00 3.98E-06 O.OOE+00 ALPHA CURIES O.OOE+00 O.OOE+0O 8.76E-06 2.98E-03 XE-133M CURIES O.OOE+00 O.OOE+00 O.OOE+00 1.40E-03 XE-135 CURIES .OEO+00 O.OOE+00 O.OOE+00 1.06E-03 132 CURIES 0.00E+OO OOE+00 0 0 OOE+00 1.90E-04 SB-124 CURIES O.OOE+00 0 OOE+00 0 OOE+00 1.52E-03 MO-99 CURIES O.OOE+00 0 +OO+00 0 OOE+00 2.58E-05 NA-24 CURIES O.OOE+00 0 +OO+00 0 +OO+00 2.72E-05 ZR-95 CURIES 0.EOO+00 0 EOOE+00 .OOE+00 7.77E-05 CO-57 CURIES O.OOE+00 0 EOO+00 0 00E+00 4.61E-05 AG-A IOM CURIES O.OOE+00 O.OOE+00 0 OOE+00 2.79E-05 TOTALS FOR PERIOD CURIES 0.EOO+00 0.EOO+00 2.0 1E+02 2.32E+02 Page 1 of I 23

Table 3 Solid Waste & IrradiatedFuel Shipments 2002 A. SOLID WASTE BURIED (DOES NOT INCLUDE IRRADIATED FUEL)

1. TYPE OF WASTE PERIOD PERIOD EST. TOTAL UINITS JAN - JUN JUL - DEC ERROR ( 6) 3

a. Spent resins, filter m 17.63 12.71 sludges, evaporator Ci 192 .46 35.49 +/-25%

bottoms, etc.

3

b. Dry compressible waste, m 9.53 6.47 contaminated equipment, Ci 0.63 1.08 +/-25%

etc.

c. Irradiated components, 0 0 control rods, etc. Ci 0 0 +/-25%

d. Other 0 0 Ci 0 0 +/-2 5%

G2. . I E5TAT

'- rs OFA

- V MA.Jrno

,Ju1'r.

COHnuPOSITIONM (bv q'npe of Waste)

PERIOD JAN - JUN PERIOD JUL - DEC Nuclide % Abundance Curies 9 Abundance Curies

a. Ni-63 37.9 72.9 37.9 13.5 Co-58 15.7 3 0.2 15.7 5 . 6 Fe-55 15.2 29.3 15.2 5 .4 Co-60 13.7 2 6.4 13.7 4 .8 Zr-95 4.1 7.9 4.1 1.5 Mn-54 3.7 7.1 3.7 1.3 Nb-95 2.6 5.0 2.6 0 .9 H-3 1.7 3.3 1.7 0 .6 Sb-125 1.8 3.5 1.8 0 .6 Cr-51 1.4 2.7 1.4 0 .5 Cs-137 1.0 1.9 1.0 0 .4

b. Ni-63 53.0 0.3 3 53.0 0 .6 Co-60 17.8 0 .11 17.8 0 .2 Co-58 10.4 0 .07 10.4 0 .1 Fe-55 10.0 0.0 6 10. 0 0 .1 Mn-54 4.4 0.03 4.4 0 .05 Sb-125 2.3 O .0 1 2.3 0 .02 1ge of 2 24

Table 3 Solid Waste & Irradiated Fuel Shipments 2002

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Tvye of Waste) Cont.

PERIOD PERIOD JAN - JUN JUL - DEC Nuclide % Abundance Curies % Abundance Curies

c. None

d. None

3. SOLID WASTE DISPOSITION:

Number of Mode of Destination Class of Solid Type of Shipments Transport Waste Shipped Container 1* Cask ATC A LSA 1 Cask Barnwell, SC B LSA 1 Cask Barnwell, SC C LSA 2* Cask Alaron A LSA 2* Cask Studsvik A LSA 11* Truck Duratek A LSA

Sent to waste processors for volume reduction before burial.

4. SOLIDIFICATION AGENT:

None used.

B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shipments Mode of Transportation Destination 0

Page 2 of 2 25

2>hbJ 4 -- -r - c - dc a7 03ta Av tIa UrHawfllyAverage Mta Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:54.29 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00

% GOOD UNITS VALUES DATA Stability Class A-G E 96%

Total Precipitation CM. 8.86E+01 76%

10 Meter Level: Wind Speed Meter/Sec 2.98E+00 100%

Wind Direction Degrees 2.011E+02 100%

Wind Direction Variability Degrees 1.39E+01 100%

Reference Temperature Degrees C 1.31E+01 100%

Dewpoint Degrees C 6.03E+00 99%

60 Meter Level: Wind Speed Meter/Sec 5.03E+00 93%

Wind Direction Degrees 2.09E+02 93%

Wind Direction Variability Degrees 8.69E+00 99%

Dewpoint Degrees C NONE 0%

Temperature Difference 60 - 10 Degrees C 1.1 lE-01 96%

Page 1 of 1 26

2~7 4 [- - -~ 0 '-

lTtals nf Haws at EFit Riz & liz+/-ai Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1 -JAN-2002 00:00:00.00 to 31 -DEC-2002 23:00:00.00 Stability Class: A Wind Speed at 10.00 Meter Level (MPH) r F 1 r 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 12 4 0 0 0 19 NNE 6 21 2 0 0 0 29 NE 7 22 9 0 0 0 38 ENE 5 32 6 0 0 0 43 E 7 19 14 0 0 0 40 ESE .5 31 18 1 0 0 55 SE 13 73 33 2 0 0 121 SSE 10 112 54 22 0 0 198 S 16 85 64 39 1 0 205 SSW 12 91 87 14 0 0 204 SW 11 58 63 2 0 0 134 WSW 1 21 13 0 0 0 35 W 4 29 27 2 5 0 67 WNW 6 33 47 7 0 0 93 NW 4 14 34 5 0 1 58 NNW 3 11 26 5 1 0 46 TOT 113 664 501 99 7 1 1385 Hours of Calm Data: 0 Hours of Invalid Data: 1 Page 1 of 7 27

MW 4 e raak0icE E ta acts~z tals of CaK at; Ec i WISf 1 & 1 2 Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 3 1-DEC-2002 23:00:00.00 Stability Class: B Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 7 6 0 0 0 14 NNE 1 17 5 0 0 0 23 NE 2 11 6 0 0 0 19 ENE 5 13 3 0 0 0 21 E 3 5 6 0 0 0 14 ESE 3 1 3 0 0 0 7 SE 7 14 8 1 0 0 30 SSE 3 6 16 1 0 0 26 S 3 10 13 7 1 0 34 SSW 2 20 16 1 0 0 39 SW 4 16 7 1 0 0 28 WSW 3 8 11 1 0 0 23 W 1 10 5 4 1 0 21 WNW 2 16 9 3 0 0 30 NW 1 23 4 5 2 0 35 NNW 2 13 13 1 0 0 29 TOT 43 190 131 25 4 0 393

Hours of Calm Data: 0 Hours of Invalid Data: 0 Page 2 of 7

-11;>1

Mb 4 7ca locals of Iz at: +/- ing & dial Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: C Wind Speed at 10.00 Meter Level (MPH)

V V F I I 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 19 9 0 0 0 29 NNE 1 17 4 0 0 0 22 NE 2 13 3 0 0 0 18 ENE 3 13 3 0 0 0 19 E 4 6 6 0 0 0 16 ESE 2 8 4 0 0 0 14 SE I 10 5 0 0 0 16 SSE 4 11 13 8 0 0 36 S 2 9 14 7 1 0 33 SSW 0 12 12 4 0 0 28 SW 2 14 7 2 0 0 25 WSW 1 8 4 1 1 0 15 W 0 7 6 4 1 0 18 WNW 5 14 14 5 0 0 38 NW 1 19 16 1 0 0 37 NNW 1 7 15 0 1 0 24 TOT 30 187 135 32 4 0 388 Hours of Calm Data: 1 Hours of Invalid Data: 0 Page 3 of 7

-.114

2~ble4 - -- - - - - -- -- 7- ta taS af Hams at E+/-d Wfid O & B Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: D Wind Speed at 10.00 Meter Level (MPH)

T 7 7 7 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 10 54 58 20 0 0 142 NNE 14 51 45 1 0 0 ll.1 NE 23 84 21 7 0 0 135 ENE 13 51 31 1 0 0 96 E 9 37 30 0 0 0 76 ESE 8 34 32 5 0 0 79 SE 13 50 33 7 0 0 103 SSE 14 38 47 26 0 0 125 S 6 34 57 27 0 0 124 SSW 3 41 37 7 0 0 88 SW 11 54 22 6 0 0 93 WSW 6 22 20 4 0 0 52 W 7 37 30 21 4 0 99 WNW 13 71 47 18 0 0 149 NW 12 65 55 29 0 0 161 NNW 14 81 110 17 0 0 222 TOT 176 804 675 196 4 0 1855 Hours of Calm Data: 6 Hours of Invalid Data: 0 Page 4 of 7 30

2 e4 mttzo-c Wic 2 fram Qraiiwy ls f Hours at EXi2 WdS?

as & flzira2 Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00.00:00.00 to 3 1-DEC-2002 23:00.00.00 Stability Class: E Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 24 71 30 3 0 0 128 NNE 27 88 26 4 0 0 145 NE 60 69 6 1 0 0 136 ENE 33 50 3 0 0 0 86 E 32 31 8 0 0 0 71 ESE 20 42 20 3 0 0 85 SE 38 115 94 1 0 0 248 SSE 38 142 111 15 0 0 306 S 31 173 112 7 0 0 323 SSW 30 114 70 2 0 0 216 SW 23 85 44 1 0 0 153 WSW 34 48 25 3 0 0 110 W 40 81 51 3 0 1 176 WNW 37 75 32 2 0 0 146 NW 38 116 39 3 0 0 196 NNW 23 89 34 5 0 0 151 TOT 528 1389 705 53 0 1 2676 Hours of Calm Data: 20 Hours of Invalid Data: 11 Page 5 of 7 31

24 14z2bammIccdc Dta Q2+/-zw luls HO=rs at;& EW12 W ea &D I2 Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: F Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 26 13 0 0 0 0 39 NNE 30 21 0 0 0 0 51 NE 48 15 0 0 0 0 63 ENE 32 10 0 0 0 0 42 E 40 11 0 0 0 0 51 ESE 53 37 1 0 0 0 91 SE 46 121 8 0 0 0 175 SSE 50 167 6 0 0 0 223 S 30 118 19 0 0 0 167 SSW 21 72 6 0 0 0 99 SW 24 75 7 0 0 0 106 WSW 15 13 1 0 0 0 29 W 19 46 2 0 0 0 67 WNW 41 34 1 0 0 0 76 NW 38 22 0 0 0 0 60 NNW 12 25 0 0 0 0 37 TOT 525 800 51 0 0 0 1376 Hours of Calm Data: 28 Hours of Invalid Data: 14 Page 6 of 7 i 11

2WA 4 BData Iais cf bazs at EM+/- Kid s & DXzE +/-kn Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:56.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: G Wind Speed at 10.00 Meter Level (MPH)

T T I 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 39 5 0 0 0 0 44 NNE 59 12 0 0 0 0 71 NE 24 1 0 0 0 0 25 ENE 18 0 0 0 0 0 18 E 14 2 0 0 0 0 16 ESE 23 6 0 0 0 0 29 SE 31 29 4 0 0 0 64 SSE 47 48 6 0 0 0 101 S 21 7 0 0 0 0 28 SSW 13 12 0 0 0 0 25 SW 10 2 0 0 0 0 12 WSW 7 0 0 0 0 0 7 W 6 2 0 0 0 0 8 WNW 17 9 0 0 0 0 26 NW 23 16 0 0 0 0 39 NNW 38 13 0 0 0 0 51 TOT 390 164 10 0 0 0 564 Hours of Calm Data: 40 Hours of Invalid Data: 0 Hours of Good Data: 8732 = 99.7% of Total Hours Page 7 of 7

-1

.5-1

2hle 4 O eesqr7 zta Ca0izid 1ttls am = at E~+/- Win? & If Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: A Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 6 8 2 0 0 18 NNE 0 16 4 0 0 0 20 NE 1 16 12 0 0 0 29 ENE 1 20 11 0 0 0 32 E 2 19 10 2 0 0 33 ESE 2 12 18 8 0 0 40 SE 5 50 36 6 0 0 97 SSE 1 83 57 30 12 0 183 S 8 55 57 45 19 3 187 SSW 8 52 79 50 14 2 205 SW 4 40 64 47 6 0 161 WSW 2 9 17 9 0 0 37 W 3 12 27 12 3 5 62 WNW 3 14 25 35 11 1 89 NW 1 8 24 18 6 0 57 NNW 0 9 18 8 4 2 41 TOT 43 421 467 272 75 13 1291 Hours of Calm Data: 0 Hours of Invalid Data: 95 Page 1 of 7 UL

2a7 4 ---3lCg CE17 0ata Cbzf:mue Et7as afbrc at EXF Wing & 1izicn Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: B Wind Speed at 60.00 Meter Level (MPH)

- r I T 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2 8 0 0 11 NNE 1 11 11 0 0 0 23 NE 0 4 11 0 0 0 15 ENE 1 8 8 0 0 0 17 E 2 7 2 3 0 0 14 ESE 3 1 4 1 0 0 9 SE 0 13 4 4 0 0 21 SSE 3 4 8 9 1 0 25

_ 1 10 10 14 3 3 41 SSW 1 4 13 9 0 1 28 SW 0 7 13 6 1 0 27 WSW 2 7 9 8 1 0 27 W 2 3 6 2 0 3 16 WNW 0 9 7 10 5 1 32 NW 0 7 18 2 2 3 32 NNW 1 11 12 5 3 0 32 TOT 17 108 144 74 16 11 370 Hours of Calm Data: 0 Hours of Invalid Data: 23 Page 2 of 7 4,

2bW 4 ~~a-rok 7ca1ta cals ofHan at Eafi Wfal l& Drxiai Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: C Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 9 18 1 0 0 28 NNE 1 12 7 0 0 0 20 NE 0 9 6 0 0 0 15 ENE 1 8 6 2 0 0 17 E 0 7 7 2 0 0 16 ESE 0 5 2 2 0 0 9 SE 3 7 3 1 0 0 14 SSE 0 7 11 ii 4 0 33 S 0 4 10 12 5 2 33 SSW 1 4 7 7 3 0 22 SW 0 14 6 8 2 0 30 WSW 0 6 5 3 1 2 17 W 2 2 4 6 2 1 17 WNW 0 9 5 9 6 2 31 NW 1 7 18 12 2 0 40 NNW I 6 11 5 0 1 24 TOT 10 116 126 81 25 8 366 Hours of Calm Data: 0 Hours of Invalid Data: 23 Page 3 of 7 36

biiBe4 - 7 ta Is Af rons at Ed+/- Whnd & 2iria Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: D Wind Speed at 60.00 Meter Level (MPH)

- r r T 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 24 45 44 8 0 126 NNE 7 12 59 16 1 0 95 NE 4 34 71 10 0 0 119 ENE 3 24 52 11 0 0 90 E 5 17 44 4 0 0 70 ESE 4 17 31 18 4 0 74 SE 6 21 31 16 5 0 79 SSE 1 23 31 39 16 0 110 S 4 19 34 58 25 1 141 SSW 1 18 41 34 9 1 104 SW 2 17 41 24 6 1 91 WSW 3 12 22 16 5 0 58 W 3 16 29 10 16 14 88 WNW 6 24 46 49 19 3 147 NW 7 18 46 35 23 5 134 NNW 4 30 99 67 10 2 212 TOT 65 326 722 451 147 27 1738 Hours of Calm Data: 1 Hours of Invalid Data: 122 Page 4 of 7 37

2W52e 4 D; c- cI7 L7a Q2+/-izwe bt.als of a at Exh wizd & flPMwtiai Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: E Wind Speed at 60.00 Meter Level (MPH)

r

5 7 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 18 67 31 2 0 118 NNE 0 26 53 20 2 0 101 NE 4 38 61 9 1 0 113 ENE 2 30 50 1 1 0 84 E 0 22 36 3 0 0 61 ESE 2 22 39 15 2 0 80 SE 3 34 62 63 1 0 163 SSE 5 28 99 118 8 1 259

_ 8 29 118 145 9 0 309 SSW 3 17 87 139 18 0 264 SW 6 31 80 78 14 0 209 WSW 3 26 44 26 7 0 106 W 4 24 59 60 14 2 163 WNW 0 26 71 42 6 0 145 NW 4 36 78 47 4 0 169 NNW 2 34 71 35 2 0 144 TOT 46 441 1075 832 91 3 2488

- Hours of Calm Data: 2 Hours of Invalid Data: 217 Page 5 of 7 38

2b1.4 - e oaCj~rj k- 7tata

&2 ISofHas at .-Cf2 i; Elt; S Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 l4:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: F Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 7 20 3 0 0 33 NNE I 10 14 4 0 0 29 NE 4 13 19 3 0 0 39 ENE 3 6 44 10 0 0 63 E 3 5 31 4 0 0 43 ESE 3 12 56 6 0 0 77 SE 2 21 88 15 0 0 126 SSE 1 24 101 37 1 0 164 S 0 27 101 37 2 0 167 SSW 2 9 79 77 3 0 170 SW 0 8 51 48 1 0 108 WSW 2 12 36 17 0 0 67 W 2 6 17 16 1 0 42 WNW 0 14 18 30 0 0 62 NW 4 9 39 12 0 0 64 NNW 3 8 32 10 0 0 53 TOT 33 191 746 329 8 0 1307 Hours of Calm Data: 1 Hours of Invalid Data: 110 Page 6 of 7 44

be4 mtermX21OX&I Xta 7tals oCfEH at Eun Wizxi S &f i Union Electric - Callaway Plant Report Date/Time: 9-APR-2003 14:02:58.44 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2002 00:00:00.00 to 31-DEC-2002 23:00:00.00 Stability Class: G Wind Speed at 60.00 Meter Level (MPH) r 7 r 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 10 10 6 0 0 27 NNE 3 9 13 7 0 0 32 NE 2 15 31 6 0 0 54 ENE 0 14 32 10 0 0 56 E 0 7 20 2 0 0 29 ESE 0 12 24 5 0 0 41 SE 1 15 33 4 0 0 53 SSE 1 17 25 12 1 0 56 S 0 11 32 13 0 0 56 SSW 2 12 25 6 0 0 45 SW 0 2 12 7 0 0 21 WSW 0 4 7 0 0 0 11 W 2 4 5 0 0 0 11 WNW 2 2 3 1 0 0 8 NW 1 5 10 3 0 0 19 NNW 1 10 13 7 0 0 31 TOT 16 149 295 89 1 0 550 Hours of Calm Data: 0 Hours of Invalid Data: 54 Hours of Good Data: 8114 = 92.6% of Total Hours Page 7 of 7 4U ~

2hb7 5 at: the ,ite Ba aryl to t1 Frr -41t 22NEc f : +/- Ex = Gc"- 2 EE-+/- S TABLE 5 DOSE AT THE SITE BOUNDARY AND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS SITE BOUNDARY NEAREST RESIDENT LOCATION: 1.40 km SSW LOCATION: 2.90 km NNW AGE GROUP: CHILD AGE GROUP: CHILD ORGAN UNITS DOSE % LlMIT(a) DOSE % LIMIT(b)

1. GAMMA AIR DOSE

MRAD 2.82E-04 0.00 1.68E-04 N/A

2. BETA AIR DOSE

MRAD 3.27E-04 000 1.95E-04 N/A

3. WHOLE BODY *** MREM 7.18E-04 N/A 4.90E-04 N/A

4. SKIN *** MREM 9.48E-04 N/A 6.27E-04 N/A

5. BONE ** MREM 4.59E-04 N/A 1.5 IE-03 001

6. LIVER ** MREM 2.73E-03 N/A 1.32E-02 009

7. TOTAL BODY ** MREM 2.73E-03 N/A 1.2 IE-02 0 08

8. THYROID ** MREM 2.73E-03 N/A 1.22E-02 008

9. KIDNEY ** MREM 2.73E-03 N/A 1.23E-02 0 08 10 LUNG ** MREM 2.76E-03 N/A L.20E-02 0.08

11. GI-LLI ** MREM 2.73E-03 N/A l.19E-02 0.08

Dose from Noble Gases only

- Dose from Tritium. Radioiodines, and Particulates only

- - Dose from Noble Gases plus Ground Plane dose (a) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 10 mrad gamrnma air dose and 20 mrad beta air dose (b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 15 mrem to any organ from 1-131.1 -133, H-3 and particulate radionuclides with halflives greater than 8 days.

Page 1 of I 41

mibl 6 wseto tbo= 1Wk.-r cif the AbKic EmnAcivitLs within UimSite Em zy TABLE 6 DOSE TO THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY EFFLUENT DIRECT DIRECT TOTAL DOSE WITHIN RADIATION RADIATION DOSE THE SITE FROM THE FROM OUTSIDE FOR THE ORGAN UNITS BOUNDARY UNIT TANKS YEAR

1. SKIN MREM 1.12E-04 N/A N/A 1.12E-04

2. BONE MREM 1.52E-04 8.79E-03 9.88E-03 1.88E-02

3. LIVER MREM 7.59E-04 8.79E-03 9.88E-03 1.94E-02

4. TOTAL BODY MREM 8.19E-04 8.79E-03 9.88E-03 1.95E-02

5. THYROID MREM 7.59E-04 8.79E-03 9.88E-03 1.94E-02

6. KIDNEY MREM 7.59E-04 8.79E-03 9.88E-03 L.94E-02

7. LUNG MREM 7.65E-04 8 79E-03 9.88E-03 1.94E-02

8. GI-LLI MREM 7.59E-04 8.79E-03 9.88E-03 1.94E-02 Page 1 of I 42

77 a to th tnin Re1 Ca2 Qbi TAB LE 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OF THE PUBLIC)

DOSE FROM TOTAL DOSE DOSE AT THE ACTIVITIES TO THE RESIDENCE WITHIN SITE MEMBER OF ORGAN UNITS LOCATION BOUNDARY THE PUBLIC % LIMITS *

1. SKIN MREM 2.93E-04 1.12E-04 4.06E-03 0.00

2. BONE MREM 6.22E-04 1.88E-02 1.94E-02 0 08

3. LIVER MREM 7.81E-03 1.94E-02 2.72E-02 0.11

4. TOTAL BODY MREM 7.83E-03 1.95E-02 2.73E-02 0.11

5. THYROID MREM 7.45 E-03 1.94E-02 2.69E-02 0.04

6. KIDNEY MREM 7.50E-03 1.94E-02 2.69E-02 0.11

7. LUNG MREM 7.41E-03 1.94E-02 2.68E-02 0.11

8. GI-LLI MREM 7.43E-03 1.94E-02 2.69E-02 0.11

Annual dose limits from 40CFRI90.10(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

Page I of I 43

f l X , _E _ _

2W7e 8 rP Wm0 IC47

~er cfiR)RU Riblia)

TABLE 8 DOSE DUE TO LIQUID EFFLUENTS (MEMBER OF THE PUBLIC) 2002 ORGAN UNITS l DOSE LIMIT * % LIMIT

1. BONE MREM 1.59E-02 1000 1.59E-01

2. LIVER MREM 2.65E-02 1000 2.65E-01

3. TOTAL BODY MREM 1.96E-02 3.00 6 53E-01

4. THYROID MREM 2.07E-03 1000 2.07E-02

5. KIDNEY MREM 1.02E-02 10.00 1.02E-01

6. LUNG MREM 4.76E-03 10.00 4.76E-02

7. GI-LLIMREM 4.94E-03 1000 4 94E-02

Annual dose limits of APA-ZZ-01003, Section 9.4.1.1.

Page I of I AA

IAl APA-ZZ-01003 Rev. 013 UNION EL~ECTRIC CALLAWAY-PLANT OFF-SITE DOSE CALCULATION MANUAL c ISSUED SEPTEMBER 19, 2002 WORKING COPY OCT 1 7 2002 ACCOUNTA.LE I

APA-ZZ-01003 Revision 013 September 19, 2002 CALLAWAY PLANT ADMINISTRATIVE PROCEDURE APA-ZZ-01003 OFF-SITE DOSE CALCULATION MANUAL RESPONSIBLE DEPARTMENT HEALTH PHYSICS PROCEDURE OWNER HAROLD OSBORN WRITTEN BY JOHN KERRIGAN PREPARED BY JERRY ABERNATHY APPROVED BY 6%A ,.

DATE ISSUED 10-fl -C This procedure contains the following:

Pages 1 through 63 Attachments through Tables through Figures - through Appendices through Checkoff Lists . through This procedure has checkoff list(s) maintained in the mainframe computer.

Conversion of commitments to TRS reference/hidden text completed by Revision Number:

Non-T/S Commitments

I-APA-ZZ-0 1003 Rev. 013 RECORD OF REVISIONS

) 1 PURPOSE AND SCOPE I 2 LIQUID EFFLUENTS 2 2.1 LIQUID EFFLUENT MONITORS 2 2.2 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS 4 2.3 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS 5 2.4 DOSE DUE TO LIQUID EFFLUENTS 6 2.4.1 The Maximum Exposed Individual 6 2.4.2 Calculation Of Dose From Liquid Effluents 6 2.4.3 Summary, Calculation Of Dose Due To Liquid Effluents 7 2.5 LIQUID RADWASTE TREATMENT SYSTEM 7 2.6 DOSE FACTORS 7 3 GASEOUS EFFLUENTS 12 3.1 GASEOUS EFFLUENT MONITORS 12

) 3.2 GASEOUS EFFLUENT MONITOR SETPOINTS 13 3.2.1 Total Body Dose Rate Setpoint Calculations 14 3.2.2 Skin Dose Rate Setpoint Calculation 15 3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS 15 3.3.1.1 Dose Rate from Noble Gases 15 3.3.1.2 Dose Rate from Radionuclides Other than Noble Gases 16 3.3.2 Dose Due to Gaseous Effluents 17 3.3.2.1 Air Dose Due to Noble Gases -17 3.3.2.2 Dose Due to Radionuclides Other than Noble Gases -18 3.4 GASEOUS RADWASTE TREATMENT SYSTEM - 19 3.5 DOSE FACTORS 19 4 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 43 4.1 CALCULATION OF DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 43 4.1.1 Identification of the MEMBER OF THE PUBLIC 43 4.1.2 Total Dose to the Nearest Resident 43 APA-ZZ-01003 Rev. 013 RECORD OF REVISIONS 4.1.3 Total Dose to the Critical Receptor Within the SITE BOUNDARY 44 5 RADIOLOGICAL ENVIRONMENTAL MONITORING 47

5.1 DESCRIPTION

OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 47 5.2 PERFORMANCE TESTING OF ENVIRONMENTAL THERMOLUMINESCENCE DOSIMETERS 47 6 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERIC DISPERSION PARAMETERS 47 6.1 ATMOSPHERIC DISPERSION PARAMETERS 47 6.1.1 Long-Term Dispersion Estimates 47 6.1.2 Determination of Long-Term Dispersion Estimates for Special Receptor Locations 48 6.1.3 Short Term Dispersion Estimates 48 6.2 ANNUAL METEOROLOGICAL DATA PROCESSING 49 7 REPORTING REQUIREMENTS 56

) 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (COMN 2804) 56 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT (COMN 2805) 56 8 IMPLEMENTATION OF ODCM METHODOLOGY (COMN 2791) 57 9 RADIOACTIVE EFFLUENT CONTROLS (REC) 58 10 ADMINISTRATIVE CONTROLS 59 10.1 MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS 59 10.2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) (COMN 2815) 59 11 REFERENCES 60

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U-APA-ZZ-01003 Rev. 013 RECORD OF REVISIONS

) FIGURES FIGURE 4.1 ..................................... 46 TABLES TABLE 2.1 ...................................... 8 TABLE 2.2 .-..................................... 11 TABLE 3.1 ..................................... 20 TABLE 3.2 ..................................... 21 TABLE 3.3 - INHALATION PATHWAY ..................................... 23 TABLE 3.3 - MEAT PATHWAY ..................................... 25 TABLE 3.3 - GRASS-COW-MILK PATHWAY ..................................... 27 TABLE 3.3 - GRASS-GOAT-MILK PATHWAY ..................................... 29 TABLE 3.3 - VEGETATION PATHWAY ..................................... 31 TABLE 3.4 - INHALATION PATHWAY ...................................... 33 TABLE 3.4 - MEAT PATHWAY ..................................... - 35 TABLE 3.4 - GRASS-COW-MILK PATHWAY ..................................... 37 TABLE 3.4 - GRASS-GOAT-MILK PATHWAY ...................................... 39 TABLE 3.4 - VEGETATION PATHWAY ..................................... 41 TABLE 6.1 ..................................... 50 -

TABLE 6.2 ....... .51

) TABLE 6.3 .... ;-52 TABLE 6.4 .53 TABLE 6.5 .54 TABLE 6.6.55

- ii

APA-ZZ-01003 Rev. 013 RECORD OF REVISIONS Rev. No. 0 Date: March 1983 Rev. No. 1 Date: November, 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments.

Rev. No. 2 Date: March, 1984 Revised to incorporate NRC Staff comments Rev. No. 3 Date: June, 1985 Revised to incorporate errata identified by ULNRC00803 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land Use Census.

Rev. No. 4 Date: February, 1987 Minor clarifications, incorporated 31-day projected dose methodology. Change in the utilization of areas within the Site Boundary.

Rev. No. 5 Date: January, 1988 Minor clarifications, revised descriptions of liquid and gaseous rad monitors, revised liquid setpoint methodology to incorporate monitor background, revised dose calculations for 40CFRI90 requirements, Revised Table 6 and Figures 5.1A and 5.1B to refine descriptions of environmental TLD stations, incorporated description of environmental TLD testing required by Reg. Guide 4.13, revised Tables 1, 2, 4 and 5 to add additional nuclides, deleted redundant material from Chapter 6.

Rev. No. 6 Date: May, 1989 Revised methodology for calculating maximum permissible liquid effluent discharge rates and liquid effluent discharge rates and liquid effluent monitor setpoints, provided methodology for calculating liquid effluent monitors response correction factors, provided an enhanced description of controls on liquid monitor background limits, provided additional liquid and gaseous dose conversion factors and bioaccumulation factors (Tables 1, 2, 4 & 5),

provided description of the use of the setpoint required by Technical Specification 4.9.4.2 during Core Alterations, added discussion of gaseous and liquid monitor setpoint selection in the event that the sample contains no detectable activity, added minimum holdup requirements for Waste Gas Decay tanks, revised dispersion parameters and accompanying description per FSAR Change Notice 88-42.

APA-ZZ-01003 Rev. No. 0 Date: August, 1989 Radiological Effluent Technical Specifications were moved from the Callaway Plant Technical Specifications to Section 9.0, Radioactive Effluent Controls, of the ODCM as per NRC Generic Letter 89-01. At the same time, in order to formalize control of the entire ODCM, it was converted to APA-ZZ-01003, OFF-SITE DOSE CALCULATION MANUAL.

Rev. No. I Date: October, 1990 Revise Action 41 of Table 9.2-A to allow continued purging for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months as per Amendment 20 to operating license, issued 4/10/87.

Rev. No. 2 - -Date: May, 1991 Section 2.4.2 - Changed gross alpha analysis frequency from "each batch" to a monthly composite as per Table 9.3-A, and the Callaway Plant NPDES permit (reissued March 15, 1991).

-iv-

APA-ZZ-0 1003 Rev. 013 RECORD OF REVISIONS Rev. No. 3 Date: June,1993

) Deleted HF-RE-45 and LE-RE-59 as effluent monitors. Revised table numbering for consistency with those in Section 9.0, deleted redundant material, incorporated 1992 Land Use Census results, moved LLD description to Attachment 1,moved REC Bases to Attachment 2. Deleted reporting requirements for solid radwaste, which are described in APA-ZZ-01011, PROCESS CONTROL PROGRAM. Addressed compliance with 10 CFR20.1301.

Revised the dilution flow rate to allow values other than 5000 gpm, based on dilution flow monitor setpoint. Revised "MPC" terminology to "ECV". Added Action 46 to REC 9.2 to clarify actions for inoperable mid and high range WRGM Channels. Revised references to be consistent with the revised 10 CFR 20. Added Appendix A. Revised Action 41 of Rec 9.2 and the operability requirements of GT-RE-22/33. Incorporated the revised Ri values in Tables 3.2 and 3.3. Added Section 6.2 and Table 6.5.

Rev. No. 4 Date: September, 1994 Increased the minimum channels OPERABLE requirement of REC 9.2 for GT-RE-22 & 33 from 1 channel to 2 channels. Revised Action 41 and the Bases for REC 9.2 accordingly. Incorporated the operability requirements from Tech Spec 3.9.9 into the Action statement for clarity. (Refer to CARS 199401176).

Rev. No. 5 Date: February, 1995 Removed the REMP station locations. Removed particulate nuclides with a half-life of less than 8 days from Tables 3.2-3.4 and removed C14, p3 2 Ni63 Tel25m and from Tables 2.1, 2.2, 3.2, 3.3, and 3.4.- Changed the reporting frequency of the Effluent Release Report from semiannual to annual. Removed the meat, milk and Vegetable pathway dispersion parameters from Tables 6.1, 6.2, and 6.3, and clarified the applicability of the dispersion parameters and dose locations in Table 6.4. Relocated REC 9.1 and 9.2 to the FSAR. Revised footnotes 3 and 7 of Table 16.11-4 to require additional sampling of the Unit Vent in the event of a reactor power transient, only if the Unit Vent noble gas activity increases by a factor of 3 or greater. Added Section 4.1.3.1.3 for determination of dose due to the on-site storage of low level radioactive waste.

) Rev. No. 6 Date September, 1996 Section 2: Added dose factors (A,,)for Ag"l"', Np237, p Pu239n40 Pu241 Am241 Cm242 and Cm2 34n" to Table 2.1, and Bioaccumulation Factors (Bf,) for Ag, Pu, Am, and Cm to Table 2.2 due to a change in the liquid radwaste treatment process. Revised the description of the methodology for performing the 31 day dose projection in Section 2.5. Revised the maximum allowable background for HB-RE-18.

Section 3: Eliminated y91m and Tc?9m from Table 3A (Meat Pathway) due to a half-life of < 8 days. 'Substituted the phrase "more restrictive" in lieu of "lesser" in Section 3.2. Revised the definition of F. in equation 3.1. Added description of use of samples to verify dose rates in Section 3.3.1.2. Augmented the definition of q, in Section 3.3.2.1.

Edited equations 3.13 and 3.14 and added equation 3.15 to clarify dose calculations. Revised the methodology for performing the 31 day dose projection in Section 3.4.

Section 4: Strengthened the discussion of the reevaluation of assumptions in Section 4.1.3.

Section 6: Added new table 6.6 to describe the selection and use of dispersion parameters during the preparation of the Effluent Release Report. Updated Tables 6.1 and 6.2 to reference the 1995 Land Use Census. There were no changes in the receptor locations.

Section 8: -Replaced the reference to HDP-ZZ-04500 to a more generic reference to the plant operating procedures, due to change in organizational structure and responsibilities.

WYy l APA-ZZ-0 1003 Rev. 013 RECORD OF REVISIONS Section 9: (1) Eliminated 9.0.1 and 9.0.2 due to redundancy with Technical Specifications 3.0.1 and 3.0.2; (2) Revised Table 9.3-A to incorporate sampling and analysis requirements for TRU nuclides in liquid effluents; (3) Eliminated sampling of Fuel Building Exhaust from Table 16.11-4 and the associated footnotes due to redundancy with Unit Vent sampling; revised the continuous sampling requirements for the gaseous batch release points consistent with plant design; revised the H3 analysis frequency for Purges from weekly to "prior to each purge"; and, (4) Revised the air sampling station location criteria on Table 9.1 1-A and footnote # 1, and eliminated footnote #3 in order to be less generic and more descriptive of the parameters used in determining the station locations (See CARS 199502280).

Revised the location requirements for milk and vegetables. Revised description of use of baseline samples to trigger gamma isotopic analysis in footnote #4, revised requirement for location of downstream sample station in footnote #6.

Revised Surveillance Requirement 9.10.2.1 to eliminate liquid effluents from the surveillance. (5) Revised REC 9.5 and REC 9.9 to eliminate exceptions for partially tested effluents being released in excess of the respective limit.

Section 11: Added reference 11.14.13.

Attachment 2: Revised the Bases for REC 9.10 to support the elimination of liquid effluents from Surveillance 9.10.2.1.

The remaining changes are editorial in nature and have no technical impact.

(This revision implements CARS 199502055, CARS 199600167, CARS 199600961, CARS 199502280, and CARS 199600986).

Rev. No. 7 Date February, 1997 Section 9: (1) REC 9.5, "Liquid Radwaste Treatment System", Action statement: Eliminated reference to COMN 1161, (2) Table 9.11-A, items 4a (milk) and 4c (vegetation): revised to required control stations in the least prevalent wind direction. (See CARS 199700166)

Appendix A- revised the discussion relative to the appropriate gross alpha Effluent Concentration Value.

)

Rev. No. 8 Date May, 1997 Section 1: The Purpose and Scope was revised to describe the split of the ODCM into two sections per FSAR Change Notice 95-058. Section 2: Sections 2.2 and 2.3 were revised to clarify the use of nuclide- specific alpha activity vice gross alpha activity for setpoint determination. Section 2.5 was revised to-delete the description of the Liquid Radwaste Treatment System. Section 6:_ Tables 6.1, 6.2, and 6.3 were revised to reflect the results of the 1996 Annual Land Use Census. Section 7: The reportinig requirements for the Annual Radiological Environmental Operating Report and the Effluent Release Report were relocated to the FSAR per FSAR Change Notice 95-058.

Section 9: REC's and the supporting Attachments I and 2 were relocated to the FSAR per FSAR Change Notice 95-058. Appendix A: Appendix A was deleted. Editorial changes were made throughout the ODCM reflecting the relocation of the REC's to the FSAR.

Rev. No. 9 Date -March, 1998 Section 2.5: Revised projected liquid dose calculation to use previous 31 day cumulative doses.

Section 3. 1.1: Added GL-RE-202, Laundry Decon Facility Dryer Exhaust Monitor. Added action to be taken when the particulate and/or iodine grab sampler is not operable. Section 3.2: Added setpoint calculation for GL-RE-202.

Section 3.2.1 and 3.3.2.2: Changes were made to correct typographical errors and have no technical impact.

Section 3.4: Revised projected gas dose calculation to use previous 31 day cumulative doses.

Section 3.5: Removed the word secular from "secular equilibrium" since the equilibrium mode could be secular or transient depending on the isotope. Table 6.2: Added Laundry Decon Facility Dryer Exhaust to title of table since these will be the dispersion factors used for this release point.

-vi-

V, APA-ZZ-0 1003 Rev. 013 RECORD OF REVISIONS Rev. No. 10 - Date December 20, 1999 Section 3.1: Added explanation that GL-RE-202 only monitors particulate. Section 3.2: Changed Laundry Decon Facility Exhaust Monitor setpoint to less than or equal to'2000 cpm above equilibrium background with a maximum allowed background of 2000 cpm as calculated in HPCI 99-05. -Tables 6.1. 6.2, 6.3: Updated values as calculated in HPCI 99-02. Section 5.1: Defined how REMP sample locations were determined. Removed reference to Plant Operating manual since it no longer exists.

Rev. No. 11 Date December 22, 1999 Changes required to go from old Technical Specifications to Improved Technical Specifications. Technical Specification 4.9.4.2 changed to FSAR 16.11.2.4.1. Technical Specification 6.8.4.F changed to FSAR 16.11.4.

Technical Specification 6.8.1.F changed to Improved Technical Specification 5.4.1. Technical Specification 6.14 changed to Improved Technical Specification 5.5.1. Technical Specification 6.8.4.E changed to Improved Technical Specification 5.5.4. Technical Specification 6.9.1.6 changed to Improved Technical Specification 5.6.2.

Technical Specification 6.9.1.7 changed to Improved Technical Specification 5.6.3. Changed name of Annual Radiological Effluent Release Report to Effluent Release Report as stated in ITS. Added liquid releases are limited to 10 times the Appendix B, Table 2, Column 2 lirnits per FSAR CN 98-041 supporting implementation of ITS.

Rev. No. 12 Date December 01, 2000 Section 2.1 and 2.2.1: Updated 10CFR2O, Appendix B, Table II, Column 2 reference to the new 10CFR20 format.

Corrected typo for left, flow setpoint should be undiluted waste flow rate. Section 3.2.1: Corrected typo, default value for safety factor should be 0.1. Section 5.1: Updated crosscheck program used to EML since EPA program is no longer available. Section 6:2: Added vertical height of highest adjacent building used to perform concurrent year annual average atmospheric dispersion (X/Q) calculations and reference for this value. -This information should be documented in the ODCM. Added responsibility for validation-of meteorological data, since responsibility has changed from engineering to HPTS. Section 10.1.1: Revised to require a summary of Major Radwaste System changes to be included in the annual report. This'was done to be consistent with FSAR 16.11.5.2. 'Several changes were made throughout the procedure to correct typographical errors and have no technical impact.

Rev. No. 13 Date September 19, 2002 Section 3.2: Revised to imnplement the approved OL 1218, Rev. 1; License Amendment no. 152 allowing equipment hatch and emergency air lock to remain open during refueling activities (FSAR CN-01-030 and CN-02-049). The amendment eliminated FSAR 16.11.2.4.1B and subsequently deleted the core alteration setpoint value 5.0 E-3 pCi/cc for Containment Purge Monitors GT-RE-22 and GT-RE-33. The alarm setpoints for the Containment Purge Monitors will be based on the methodology described in Section 3 of the ODCM.

-vii-

APA-ZZ-01003 Rev. 013 OFF-SITE DOSE CALCULATION MANUAL PURPOSE AND SCOPE The OFF-SITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Program required by T/S AC 5.5.4 and FSAR 16.11.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Effluent Release Reports required by TIS AC 5.6.2 and T/S AC 5.6.3.

Compliance with the Radiological Effluent Controls limits demonstrates compliance with the limits of 10 CFR20.1301. (Ref. 11.1.1, 11.2.1,11.23.3)

The ODCM consists of two parts: FSAR Section 16.11 which contains the Radiological Effluent Controls (REC's), and APA-ZZ-01003, which contains the methodology and parameters used to implement the RECs.

APA-ZZ-01003 Rev. 013 2 LIQUID EFFLUENTS

) 2.1 LIQUID EFFLUENT MONITORS Gross radioactivity monitors which provide for automatic termination of liquid effluent releases are present on the liquid effluent lines. Flow rate measurement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown). Setpoints, precautions, and limitations applicable to the operation of the Callaway Plant liquid effluent monitors are provided in the appropriate Plant Procedures. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding ten times the Effluent Concentration Values (ECV) limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA. The calculated alarm and trip action setpoints for the liquid effluent line monitors and flow measuring devices must satisfy the following equation:

cf *C Where:

C = The liquid effluent concentration value (ECV) implementing REC 16.11. 1.1 for the site in (ACilml).

c = The setpoint, in (jiCi/ml), of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely related to the volumetric flow of the effluent line and directly related to the volumetric flow of the dilution stream plus the effluent steam, represents a value, which, if exceeded, would result in concentrations exceeding ten times the values of 10 CFR Part 20 Appendix B, Table 2, Column 2, in the UNRESTRICTED AREA.

f = The undiluted waste flow rate as trneasured at the radiation monitor location, in volume per unit time, but in the same units as F, below.

) F = The dilution water flow rate setpoint as measured prior to the release point, in volume per unit time. {If (F) is large compared to (f), then F + f _ F).

(Ref. 11.8.1)

If no dilution is provided, then c < C.

The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River. Normally, the dilution flow is obtained from the cooling tower blowdown, but should this become-unavailable, the plant water treatment facility supplies the necessary dilution flow via a bypass line. The limiting concentration which corresponds to the liquid radwaste effluent monitor setpoint is'to be calculated using methodology from the expression above.

Thus, the expression for determining the setpoint of the liquid radwaste effluent line monitor becomes:

- C(F +1f) c S ( (,uCi / ml) (2.2)

The alarm/trip setpoint calculations are based on the minimum dilution flow rate (corresponding to the dilution flow rate setpoint), the maximum effluent stream flow rate, and the actual isotopic analysis. Due to the possibility of a simultaneous release from more than one release pathway, a portion of the total site release limit is allocated to each pathway. The determination and usage of the allocation factor is discussed in Section 2.2. In the event the alarm/trip setpoint is reached, an evaluation will be performed using actual dilution and effluent flow values and actual isotopic analysis to ensure that REC 16.11.1.1 limits were not exceeded APA-ZZ-0 1003 Rev. 013 2.1.1 Continuous Liquid Effluent Monitors The radiation detection monitor associated with continuous liquid effluent releases is

) (Ref. 11.6.1, 11.6.2):

Monitor I.D. Description BM-RE-52 Steam Generator Blowdown Discharge Monitor The Steam Generator Blowdown discharge is not considered to be radioactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis. The sampling frequency, minimum analysis frequency, and type of analysis performed are as per FSAR TABLE 16.11-1.

2.1.2 Radioactive Liquid Batch Release Effluent Monitors The radiation monitor which is-associated with the liquid effluent batch release system is (Ref. 11.6.4):

Monitor I.D. Description HB-RE-18 Liquid Radwaste Discharge Monitor This effluent stream is normally considered to be radioactive. The sampling frequency, minimum analysis frequency, and the type of analysis performed are as per FSAR TABLE 16.11-1.

APA-ZZ-01003 Rev. 013 2.2 CALCULATION OF LIQUID EFFLUENT MONITOR SETPOINTS

) The dependence of the setpoint (c), on the radionuclide distribution, yields, calibration, and monitor parameters, requires that several variables be considered in setpoint calculations. (Ref. 11.8.1) 2.2.1 Calculation of the ECV Sum The isotopic concentration of the release(s) being considered must be determined. This is obtained from the analyses required per Table 16.11-1, and is used to calculate an ECV sum (ECVSUM):

ECVSUM = (a(C,)/(ECV))

i g. a, s, t, f (2.3)

Where:

Cg the concentration of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample.

237 239 4 0 4 241 242 24 Ca* = the concentration of Np , Pu23S, PU 2 , pu 1, Am , Cm , & Cm 4" in the quarterly composite sample.

Cs = the measured concentrations of Sr-89 and Sr-90 as determined by analysis of the quarterly composite sample.

Ct = the measured concentration of H-3 in the waste sample.

Cf* = the measured concentration of Fe-55 as determined by analysis of the quarterly composite sample.

ECVg, ECV,, ECVa, ECVf, ECVt - are ten times the limiting concentrations of the appropriate radionuclides from 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2x1 0-4 VCi/mil total activity.

For the case ECVSUM <1, the monitor tank effluent concentration meets the limits of REC 16.11.1.1

) without dilution and the effluent may be released at any desired flow rate. If ECVSUM > I then dilution is required to ensure compliance with the concentration limits REC 16.11.1.1. If simultaneous releases are occurring or are anticipated, an allocation fraction, N, must be applied so that available dilution flow may be apportioned among simultaneous discharge pathways. The value of N may be any value between 0 and I for a particular discharge point, provided that the sum of the allocation fractions for all discharge points must be <1.

2.2.2 Calculation of the Maximum Permissible Liquid Effluent Discharge Flowrate The maximum permissible liquid effluent discharge flowrate is calculated by:

fmax < (F + f ) (SF) (N) . (ECVSUM) (2.4)

Where:

fmax = maximum permissible liquid effluent discharge flowrate, (in gallons/minute);

fp = the expected undiluted liquid effluent flowrate, in gpm.

N = the allocation fraction which apportions dilution flow among simultaneous discharge pathways (see discussion'above)

SF = the safety factor; an administrative factor used to compensate for statistical fluctuations and errors of measurements This factor also provides a margin of safety in the calculation of the maximum liquid effluent discharge flowrate (fmax). The value of SF should be < 1.

F & ECVSUM, are previously defined.

The dilution water supply is furnished with a flow monitor which isolates the liquid effluent discharge if the dilution flow rate falls below its setpoint value.

In the event that fmax is less than fp, then the value of fmax is substituted into the equation for

-' f; and a new value of fmax is calculated. This substitution is performed for three iterations in order to calculate the correct value of fmax.

Values for these concentrations are based on previous composite sample analyses as required by FSAR Table 16.11-1.

APA-ZZ-01003 Rev. 013 2.2.3 Calculation Of Liquid Effluent Monitor Setnoint The liquid efflieiit monitors are NaI(TI) based systemsi and respond primarily to gamma

) radiation. Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides in the effluent:

c = BKG + ((Cg) +SF )=iCi/ml (2.5)

Where:

c = the monitor setpoint as previously defined, in (pCi/ml);

BKG = the monitor background prior to discharge, in (piCi/ml);

Cg and SF are as previously defined.

The monitor's background is controlled at an appropriate limit to ensure adequate sensitivity.

Utilizing the methodology of ANSI N13.10-1974 (Ref. 11.21), the background must be maintained at a value of less than or equal to 9E-6 pCi/ml (relative to Cs-I 37) in order to detect a change of 4E-7 pCi/ml of Cs-137. (Ref. 11.25).

In the event that there is no detectable gamma activity in the effluent or if the value of ((Cg)

SF) is less than the background of the monitor, then the monitor setpoint will be set at twice the current background of the monitor.

As previously stated, the monitor's response is dependent on the gamma emitting radionuclide distribution of the effluent. Accordingly, a new database conversion factor is calculated for each release based upon the results of the gamma spectrometric analysis of the effluent sample and the measured response of the monitor to National Institute of Standards and Technology (NIST) traceable calibration sources:

DBCFC = (D(Cj). (CMR) x (ECF) (2 6)

) DBCFc = the monitor data base conversion factor which converts count rate into concentration (pCi/mIl);

CMR the calculated response of the radiation monitor to the liquid effluent; ECF = the conversion factor for Cs-137, which converts count rate into concentration (ICi/mli).

Cg is as previously defined.

The new value of the DBCFC is calculated and entered into the monitor data base prior to each discharge. A more complete discussion of the derivation and calculation of the CMR is given in reference 11.14.7.

2.3 LIOUID EFFLUENT CONCENTRATION MEASUREMENTS Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at the time of release. To assure representative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection. The methods for mixing, sampling, and analyzing each batch are outlined in applicable plant procedures. The allowable release rate limit is calculated for each batch based upon the pre-release analysis, dilution flow-rate, and other procedural conditions, prior to authorization for release. The liquid effluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the pre-selected alarm/trip setpoint is exceeded. Concentrations are determined primarily from the gamma the liquid batch sample. For Sr89, 5r90, isotopic and H-3 analyses of243 Fe -Np , pu2s, Pu 240, Pu ; Am 1, Cm , & Cm 244, the measured concentrations from 55 237 239 241 24 242 the previous quarterly composite analyses are used until laboratory results become available.

Composite samples are collected for each batch release and analyzed in accordance with FSAR TABLE 16.11-1. The dose from liquids discharged as continuous releases is calculated by utilizing the last measured values of samples in accordance with FSAR TABLE 16.11-1.

APA-ZZ-0 1003 Rev. 013 2.4 DOSE DUE TO LIQUID EFFLUENTS

) 2.4.1 The Maximum Exposed Individual The cumulative dose determination considers the dose contributions from the maximum exposed individual's consumption of fish and potable water, as appropriate.-Normally, the adult is considered to be the maximum exposed individual. (Ref. 11.8.3)

The Callaway Plant's liquid effluents are discharged to the Missouri River. As there are no potable water intakes within 50 miles of the discharge point (Ref. 11.7.1, 11.6.6), this pathway does not require routine evaluation. Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from discharges to the Missouri River. Dose from recreational activities is expected to contribute the additional 5%,

which is considered to be'negligible. (Ref. 11.6.7) 2.4.2 Calculation Of Dose From Liquid Effluents The dose contributions for the total time period.

m At, 1=1 are calculated at least once each 31 days and a cumulative summation of the total body and individual organ-doses is maintained for each calendar quarter. Dose is calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS using the following expression (Ref. 11.8.3):

Dr== [AIT E At, Cil F] (2.12)

) Where:

DT = the cumulative dose commitment to the total body or any organ, -T,from the liquid effluents for the total period At, 1=1 in mrem.

At, = the length of the I the time period over which C; l and F I are averaged for all liquid releases, in hours. At , corresponds to the actual duration of the release(s).

Cl = the average measured concentration of radionuclide, i, in undiluted liquid effluent

-during time period At, from any liquid release, in (ptCi/ml).

AT = the site related ingestion dose commitment factor to the total body or any organ T for each identified principal alpha, gamma and beta emitter listed in FSAR TABLE 16.11-1, (in mrern/hr) per (pCifml). The calculation of the Ai.

'values given in Table 2.1 are detailed in Ref. 11.14.12, 11.14.13, and 11.14.5.

F, = the near field average dilution factor for Ci , during any liquid effluent release:

-F fmax (F+fmx)89.77 N

I.

APA-ZZ-01003 Rev. 013 Where:

fmax = maximum undiluted effluent flow rate during the release F = average dilution flow 89.77 = site specific applicable factor for the mixing effect of the discharge structure.

(Ref. 11.5.1)

The term Ci , is the undiluted concentration of radioactive material in liquid waste at the common release point determined in accordance with REC 16.11.1.1, Table 16.11-1, "Radioactive Liquid Waste Sampling and Analysis Program". -All dilution factors beyond the sample point(s) are included in the F l term.

The nearest municipal potable water intake downstream from the liquid effluent discharge point into the Missouri River is located near the city of St. Louis, Missouri, approximately 78 miles downstream. As there are currently no potable water intakes within 50 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual, or in dose estimates to the population. Should future potable water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates. (Ref. 11.6.6).

2.4.3 Summary. Calculation Of Dose Due To Liquid Effluents The dose contribution for the total time period m

E At l is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter. The projected dose contribution

) from liquid effluents for which radionuclide concentrations are determined by periodic composite and grab sample analysis, may be approximated by using the last measured value.

Dose contributions are determined for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS. Nuclides which are not detected in the analyses are reported as "less than" the nuclide's Minimum Detectable Activity (MDA) and are not reported as being present at the Lower Level of Detection (LLD) level for that nuclide. The "less than" values are not used in the dose calculations.

2.5 LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is described in Chapter FSAR 11.2 of the Callaway Plant FSAR.

The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system

-will be available for-use when liquids require treatment prior to their release to the environment.

OPERABILITY is demonstrated through compliance with REC 16.11.1.1. and 16.11.1.2.-

Projected doses due to liquid releases to UNRESTRICTED AREAS are determined each 31

-days. The prior 31 day period is used to calculate compliance. This may be modified as -

appropriate to account for changes in radwaste treatment which may have a significant effect on the projected doses.

2.6 DOSE FACTORS The dose conversion factors provided in Table 2.1 were derived from the appropriate dose conversion factors of Regulatory Guide 1.109, Table 2.2 and other sources as necessary (Ref: 11.14.5; 11.14.13 and 11.14.12) Non-gammaemitting nuclides not listed in FSAR TABLE 16.11-1 are not considered.

I APA-ZZ-01003 Rev. 013 TABLE 2.1

') INGESTION DOSE COMMITMENT FACTOR (Ai,) FOR ADULT AGE GROUP (mrem/hr) per (gCi/ml)

NmffLft Do= Liver Total Lung GT-LLU H-3 No Data 2.26E-01 2.26E-01 2.26E-01 2.26E-0 1 2.26E-01 2.26E-01 Be-7 1.30E-02 2.98E-02 1.45E-02 No Data 3.15E-02 No Data 5.16E+00 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-51 No Data No Data 1.27E+00 7.62E-01 2.8 lE-01 1.69E+00 3.20E+02 Mn-54 No Data 4.38E+03 8.35E+02 No Data 1.30E+03 No Data 1.34E+04 Mn-56 No Data 1.10E+02 1.95E+01 No Data 1.40E+02 No Data - 3.52E+03 Fe-55 6.57E+02 4.54E+02 1.06E+02 No Data No Data 2.53E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03 9.34E+02 No Data No Data 6.8 1E+02 8.13E+03 Co-57 No Data 2.09E+01 3.48E+01 No Data No Data - No Data 5.31 E+02 Co-58 No Data 8.94E+01 2.00E+02 No Data No Data No Data 1.8 1E+03 Co-60 No Data 2.57E+02 5.66E+02 No Data No Data No Data 4.82E+03 Ni-65 1.26E+02 1.64E+01 7.48E+0o No Data No Data No Data 4.16E+02 Cu-64 No Data 1.00E+01 4.69E+00 No Data 2.52E+01 No Data 8.52E+02 Zn-65 2.32E+04 7.38E+04 3.33E+04 No Data 4.93E+04 No Data 4.65E+04 Zn-69 4.93E+01 9.44E+O 1 6.56E+00 No Data 6.13E+01 No Data 1.42E+0O1

) Br-82 Br-83 No Data No Data No Data No Data 2.27E+03 4.04E+01 No Data No Data No Data -

No Data No Data No Data 2.60E+03 5.81 E+O I Br-84 No Data No Data 5.26E+01 No Data No Data No Data 4.13E-04 Br-85 No Data No Data 2.15E+00 No Data No Data No Data 0 Rb-86 No Data l .O1E+05 4.71E+04 No Data No Data No Data I.99E+04 Rb-88 No Data 2.90E+02 1.54E+02 No Data No Data No Data 4.00E-09 Rb-89 No Data 1.92E+02 1.35E+02 No Data No Data No Data 0 Sr-89 2.2 1E+04 No Data 6.35E+02 No Data No Data No Data 3.55E+03 Sr-90 5.44E+05 No Data 1.34E+05 No Data No Data No Data -1.57E+04 Sr-91 4.07E+02 No Data 1.64E+01 No Data No Data No Data 1.94E+03 Sr-92 1.54E+02 No Data 6.68E+00 -No Data No Data No Data 3.06E+03 Y-90 5.75E-01 No Data 1.54E-02 No Data -No Data No Data 6.10E+03 Y-91M 5.44E-03 No Data 2.1OE-04 No Data -No Data No Data- 1.60E-02 Y-91 8.43E+00 No Data 2.25E-01 No Data No Data No Data - 4.64E+03 Y-92 5.05E-02 No Data 1.48E-03 No Data No Data No Data 8.85E+02 Y-93 1.60E-01 No Data 4.42E-03 No Data No Data No Data 5.08E+03 Zr-95 2.40E-01 7.70E-02 5.21E-02 No Data 1.2 1E-0 I No Data 2.44E+02 Zr-97 1.33E-02 2.68E-03 1.22E-03 No Data 4.04E-03 No Data 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 No Data 2.46E+02 No Data -1.51E+06 Mo-99 No Data 1.03E+02 1.96E+01 No Data 2.33E+02 No Data - 2.39E+02 Tc-99M 8.87E-03 2.51 E-02 3.19E-01 No Data 3.8 1E-01 1.23E-02 I .48E-I01 Tc-101 9.1 lE-03 1.3 1E-02 1.29E-01 No Data 2.36E-01 6.70E-03 0 I

APA-ZZ-0 1003 Rev. 013 TABLE 2.1 (Cont'd)

) INGESTION DOSE COMMITMENT FACTOR (Ai,) FOR ADULT AGE GROUP (mrem/hr) per (pCi/ml)

N3iclift BDn= Lier Total Thyr Kidne GLLLI Ru-103 4.42E+00 No Data 1.90E+00 No Data 1.69E+01 No Data 5.17E+02 Ru-105 3.68E-01 No Data 1.45E-0 1 No Data 4.76E+00 No Data 2.25E+02 Ru-106 6.57E+01 No Data 8.32E+00 No Data 1.27E+02 No Data 4.25E+03 Cd-109 No Data 5.54E+02 1.94E+01 No Data 5.3 IE+02 No Data 5.59E+03 Ag-110m 8.83E-01 8.17E-01 4.85E-01 No Data 1.6 lE+00 No Data - 3.33E+02 Sn-1 13 5.66E+04 1.6 1E+03 3.26E+03 9.18E+02 No Data No Data 1.69E+05 Sb-124 6.69E+00 1.26E-01 2.65E+00 1.62E-02 No Data 5.21E+00 - 1.90E+02 Sb-125 4.28E+00 4.78E-02 1.02E+00 4.35E-03 No Data 3.30E+00 4.7 1E+0I Te-127m 6.47E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 No Data 2.17E+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 No Data 8.30E+03 Te-129M I .1OE+04 4.1 1E+03 1.74E+03 3.78E+03 4.60E+04 No Data 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+00 2.3 lE+01 1.26E+02 No Data 2.27E+01 Te-131M 1.66E+03 8.09E+02 6.75E+02 1.28E+03 8.2 1E+03 No Data 8.03E+04 Te-131 1.89E+01 7.88E+00 5.96E+00 1.55E+01 8.25E+01 No Data 2.67E+00 Te-132 2.4 1E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 No Data 7.38E+04 1-130 2.71E+0I 8.01E+01 3.16E+01 6.79E+03 1.25E+02 No Data 6.89E+01 I-131 1.49E+02 2.14E+02 1.22E+02 7.OOE+04 3.66E+02 No Data 5.64E+01

) 1-132 7.29E+00 1.95E+01 6.82E+00 6.82E+02 3.1 IE+01 No Data 3.66E+00 1-133 5.1OE+01 8.87E+01 2.70E+01 1.30E+04 1.55E+02 No Data 7.97E+01 1-134 3.811E+00 1.03E+01 3.70E+00 1.79E+02 1.64E+0I No Data 9.0 lE-03 I-135 1.59E+01 4.16E+01 1.54E+01 2.75E+03 6.68E+01 No Data 4.70E+01 Cs-134 2.98E+05 7.09E+05 5.80E+05 No Data 2.29E+05 7.62E+04 - 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 No Data 6.85E+04 9.39E+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 No Data 1.77E+05 5.89E+04 1.OlE+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 No Data 3.84E+02 3.79E+01 2.23E-03 Ba-139 9.29E-01 6.62E-04 2.72E-02 No Data 6.19E-04 3.76E-04 1.65E+00 Ba-140 1.94E+02 2.44E-01 1.27E+01 No Data 8.3 IE-02 1.40E-01 4.OOE+02 Ba-141 4.50E-01 3.40E-04 1.52E-02 No Data 3.16E-04 1.93E-04 2.12E- 10 Ba-142 2.04E-01 2.09E-04 1.28E-02 No Data 1.77E-04 1.1 9E-04 - 0 La-140 1.50E-01 7.53E-02 1.99E-02 No Data No Data No Data 5.53E+03 La-142 7.65E-03 3.48E-03 8.66E-04 No Data No Data No Data 2.54E+01 Ce-141 2.24E-02 1.5 1E-02 1.72E-03 No Data 7.03E-03 No Data 5.78E+01 Ce-143 3.94E-03 2.92E+00 3.23E-04 No Data 1.28E-03 No Data 1.09E+02 Ce-144 1.17E+00 4.88E-01 6.26E-02 No Data 2.89E-01 No Data 3.94E+02 Pr- 143 5.50E-01 2.2 1E-01 2.73E-02 No Data 1.27E-01 No Data 2.4 IE+03 Nd-147 3.76E 4.35E-01 2.60E-02 No Data 2.54E-0 1 No Data 2.09E+03 Eu-154 3.67E+01 4.52E+00 3.21E+00 No Data 2.16E+01 No Data 3.27E+03 Hf-181 3.99E-02 1.94E-01 1.80E-02 No Data 4.17E-02 No Data 2.21E+02 W-187 2.96E+02 2.47E+02 8.64E+0 1 No Data No Data No Data 8.09E+04

APA-ZZ-01003 Rev. 013 TABLE 2.1 (Cont'd)

) INGESTION DOSE COMMITMENT FACTOR (Ai.) FOR ADULT AGE GROUP (mrem/hr) per (pCi/ml)

Nuclid-e BRon LiAer Total GLILJ Baft Np-237 3.27E+04 2.84E+03 1.32E+03 No Data 9.85E+03 No Data 1.90E+03 Np-239 2.84E-02 2.80E-03 1.54E-03 No Data 8.72E-03 No Data 5.74E+02 Pu-238 5.69E+03 8.01E+02 1.43E+02 No Data 6.12E+02 No Data 6.1 IE+02 Pu-239 6.58E+03 8.87E+02 1.60E+02 No Data 6.78E+02 No Data 5.67E+02 Pu-241 1.38E+02 7.06E+00 2.78E+00 No Data 1.28E+01 No Data 1.17E+O1 Am-241 4.89E+04 1.72E+04 3.23E+03 No Data 2.43E+04 No Data 4.43E+03 Cm-242 1.23E+03 1.25E+03 8.19E+O1 No Data 3.72E+02 No Data 4.73E+03 Cm-243" 3.82E+04 1.44E+04 2.24E+03 No Data 1.05E+04 No Data 4.67E+03

Includes Pu-240 contribution

- Includes Cm-244 contribution APA-ZZ-01003 Rev. 013 TABLE 2.2 j BIOACCUMULATION FACTOR (Bf )

(pCi/kg) per (pCi/liter)

Bf; Element Fish (Freshwater)

H 9.0 E -01 Be 2.0E+00 Na 1.0E+02 Cr 2.0 E + 02 Mn 4.0 E + 02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+01 Y 2.5E+01 Zr 3.3 E+00 Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Ag 2.3 E + 00 Cd 2.0 E + 02 Sn 3.0 E + 03 Sb 1.0 E + 00 Te 4.0E+02 I 1.5 E+01 Cs 2.0E+03 Ba 4.0 E + 00 La 2.5E+01 Ce 1.0 E + 00 Pr -2.5E+01 Nd 2.5E+01 Eu 2.5E+01 Hf 3.3 E + 00 W 1.2E+03 Np 1.OE+01 Pu 3.5 E + 00 Am 2.5E+01 Cm 2.5E+01

" Values from Regulatory Guide 1.109, Rev. 1, Table A-I and References 11.14.4, 11.14.8, and 11.14.13.

APA-ZZ-01003 Rev. 013 3 GASEOUS EFFLUENTS

) 3.1 GASEOUS EFFLUENT MONITORS Noble gas activity monitors are present on the containment building ventilation system, plant unit ventilation system, and radwaste building ventilation system.

The alarm/trip (alarm & trip) setpoint for any gaseous effluent radiation-monitor is determined based on the instantaneous noble gas total body and skin dose rate limits of REC 16.11.2.1, at the SITE BOUNDARY location with the highest annual average X/Q value.

Each gaseous monitor channel is provided with a two level system which provides sequential alarms on increasing radioactivity levels. These setpoints are designated as alert setpoints and alarm/trip setpoints. (Ref. 11.6.3)

The radiation monitor alarm/trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents. It is not considered practicable to apply instantaneous alarm/trip setpoints to integrating radiation monitors sexisitive to radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. The exception is GL-RE-202. The only effluent released from the Laundry Decon Facility Dryer Exhaust is in the particulate form.

Conservative assumptions may be necessary in establishing setpoints to account for system variables, such as the measurement system efficiency and detection capabilities during normal, anticipated, and unusual operating conditions, the variability in release flow and principal radionuclides, and the time lag between alarm/trip action and the final isolation of the radioactive effluent. (Ref. 11.8.5) -FSAR Table 16.11-6 provides the instrument surveillance requirements, such as calibration, source checking, functional testing, and channel checking. -

3.1.1 Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated with continuous gaseous effluent releases are (Ref. 11.6.8, 11.6.9):

Monitor I.D. Description GT-RE-21 Unit Vent GH-RE-10 Radwaste Building Vent GL-RE-202 Laundry Decon Facility Dryer Exhaust Monitor Each of the above continuously monitors gaseous radioactivity concentrations downstream of the last point of potential influent, and therefore measures effluents and not inplant concentrations.

The unit vent monitor continuously monitors the effluent from the unit vent for gaseous radioactivity. The unit vent, via ventilation exhaust systems, continuously purges various tanks and sumps normally containing low-level radioactive aerated liquids that can potentially generate airborne activity. The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building, the access control area, the containment purge, and the condenser air discharge.

The unit vent monitor provides alarm functions only, and does not terminate releases from the unit vent.

The Radwaste Building ventilation effluent monitor continuously monitors for gaseous radioactivity in the effluent duct downstream of the exhaust filter and fans.-The flow path provides ventilation exhaust for all parts of the building structure and components within the building and provides a discharge path for the waste gas decay tank release line. These components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.

This monitor will isolate the waste gas decay tank discharge line upon a high gaseous radioactivity alarm.

-A

APA-ZZ-01003

-Rev. 013 -

The Laundry Decon Facility Dryer Exhaust Monitor continuously monitors the effluent of the dryer exhaust for particulate radioactivity during operation of the dryers. This effluent point is designed to release an insignificant quantity of radioactivity. The items to be placed in the dryers are typically washed before drying removing most of the radioactive material. The dryer effluent then passes through a HEPA-filter before being sampled and released.

The Laundry Decon Facility Dryer Exhaust Monitor will secure the dryers and exhaust fans and isolate the dryer effluent upon a high radioactivity alarm or for a monitor failure.

The continuous Unit Vent and Radwaste Building Vent gaseous effluent monitor setpoints are established using the methodology described in Section 3.2. Since there are two continuous gaseous effluent release points, a fraction of the total dose rate limit (DRL) will be allocated to each release point. Neglecting the batch releases, the plant Unit Vent monitor has been allocated 0.7 DRL and the Radwaste Building Vent monitor has been allocated 0.3 DRL. These allocation factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e., 1.0). -Therefore, a particular monitor reaching the setpoint would not necessarily mean the dose rate limit at the SITE BOUNDARY is being exceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the dose rate limit than was allocated to the associated monitor, and will necessitate an evaluation of both systems.

For a loss of all isokinetic sampling and/or all heat tracing for the Unit Vent or Radwaste-Building Vent grab samplers, one hour is allowed to restore a sampler to service. If sampling cannot be restored within one hour, all batch releases and ventilation not required for the operation of the plant should be secured. The best available sampling should be maintained during this period and normal sampling returned to service as soon as possible.

3.1.2 Batch Release Gaseous Monitors The radiation monitors associated with batch release gaseous effluents are (Ref. 1 1.6.9, 11.6.10,

) 11.6.11):

Monitor I.D. Description GT-RE-22 Containment Purge System GT-RE-33 GT-RE-10 Radwaste Building Vent The Containment Purge System continuously monitors the containment purge exhaust duct during purge operations for gaseous radioactivity. The primary purpose of these monitors is to isolate the containment purge system on high gaseous activity via the ESFAS.

The sample points are located outside the containment betveen the containment isolation dampers and the containment purge filter adsorber unit.

The Radwaste Building Vent monitor was previously described.

A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides. The alarm/trip setpoint(s) is adjusted accordingly to ensure that the limits of REC 16.11.2.1 are not exceeded.

3.2 GASEOUS EFFLUENT MONITOR SETPOINTS The alarm/trip setpoint for Unit Vent and Radwaste Building Vent gaseous effluent monitors is determined based on the more restrictive of the total body dose rate (equation 3.1) and skin dose rate (equation 3.3), as calculated for the SITE BOUNDARY.

The alarm trip setpoint for the Laundry Decon Facility Exhaust Monitor is set to less then or equal

-to 2,000 cpm above equilibrium background. The maximum allowed background is 2,000 cpm as discussed in reference 11.27.

- 13 -

APA-ZZ-01003 Rev. 013 3.2.1 Total Body Dose Rate Setpoint Calculations

) To ensure that the limits of REC 16.11.2.1 are met, the alarm/trip setpoint based on the total body dose rate is calculated according to:

Slb < DtbRtbFsFa (3.1)

Where:

Stb = the alarm/trip setpoint based on the total body dose rate (pCi/cc).

Dtb = REC 16.11.2.1 limit of 500 mrem/yr, conservatively interpreted as a continuous release over a one year period.

Fs = the safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement. (For example, Fs = 0.5 corresponds to a 100% variation.) Default value is Fs = 0. 1.

Fa = the allocation factor which will modify the required dilution factor such that simultaneous gaseous releases may be made without exceeding the limits of REC 16.11.2.1.

Rtb = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (ptCi/cc) per (mrem/yr) to the total body, determined according to:

Rth = C * [(X/Q) Z K, Qi] (3 2)

Where:

C = monitor reading of a noble gas monitor corresponding to the sample radionuclide concentrations for the release. Concentrations are determined in accordance with

) FSAR TABLE 16.11-4. The mixture of radionuclides determined via grab sampling of the effluent stream or source is correlated to a calibration factor to determine monitor response. The monitor response is based on concentrations, not release rate, and is in units of (pCi/cc).

X/Q = the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY in (sec/m 3 ). Refer to Tables 6.1, 6.2 and 6.4.

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mremlyr) per (,pCi/m3 ). (Table 3.1)

Ql = rate of release of noble gas radionuclide, i, in ([tCi/sec).

Qi is calculated as the product of the ventilation path flow rate and the measured activity of the effluent stream as determined by sampling.

APA-ZZ-01003 Rev. 013 3.2.2 Skin Dose Rate Setnoint Calculation'

) To ensure that the limits of REC 16.11.2.1 are met, the alarm/trip setpoint based on the skin dose rate is calculated according to:

Ss < DsRFsFa (3.3)

Where:

Fs and Fa are as previously defined.

Ss = the alarm/trip setpoint based on the skin dose rate.

Ds = REC 16.11.2.1 limit of 3000 mrem/yr, conservatively interpreted as a continuous release over a one year period.

Rs = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, in (pCi'cc) per (mremnyr) to the skin, determined according to:

Rs = C *[(/Q) E(L, + 1 1 Mj Q, (3.4)

Where:

L = the skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem/yr) per (pCi/m 3).

1.1 = conversion factor: 1 mrad air dose = 1.1 mrem skin dose.

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad/yr) per (pCi/m3 ).

C, (X I Q) and Qi are previously defined.

) 3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS 3.3.1 Dose Rate from Gaseous Effluents The following methodology is applicable to the location (SITE BOUNDARY or beyond) characterized by the values of the parameter (X/Q) which results in the maximum total body or skin dose rate. In the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable release values. (Ref. 11.8.6)

The factors Ki, Li, and Mi relate the radionuclide airborne concentrations to various dose rates, assuming a semi-infinite cloud model.

3.3.1.1 Dose Rate from Noble Gases The release rate limit for noble gases is determined according to the following general relationships (Ref. 11.8.6):

Dtb = lKj((XQ)Qi)1 < 500mrem/yr (3.5)

Ds= [(L, + 1.1 M,)((X/Q)Q,)] < 3000 mremlyr (3.6)

Where:

Qi = The release rate of noble gas radionuclides, i, in gaseous effluents, from all vent releases in (,tCi/sec).

1.1 = Units conversion factor; I mrad air dose = 1.1 mrem skin dose.

Li, M., K;, (X / Q), Dtb & Ds are as previously identified.

- 15 -

APA-ZZ-01003 Rev. 013 3.3.1.2 Dose Rate from Radionuclides Other than Noble Gases The release rate limit for Iodine-131 and Iodine-133, for tritium, and for all radioactive materials in particulate form with half lives greater than 8 days is determined according to (Ref. 11.8.7):

D, =E RI[ EQj Q,

1500 mrem /yr (3.7)

Where:

Do = Dose rate to any critical organ, in (mrem/yr).

R = Dose parameter for radionuclides other than noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem/yr) per (PCi/m 3 ).

Q = The release rate of radionuclides other than noble gases, i, in gaseous effluents, from all vent releases in (gCi/sec).

(X / Q) is as previously defined.

The dose parameter (Ri) includes the internal dosimetry of radionuclide, i, and the receptor's breathing rate, which are functions of the receptor's age. -The child age group has been selected as the limiting age group. All radiodines are assumed to be released in elemental form (ref. 11.8.7).

Ri values were calculated according to (Ref. 11.8.8):

Ri = K (BR) DFA1 (3.8)

Where:

K = Units conversion factor: 1E06 pCi/pCi BR = The breathing rate. (Regulatory Guide 1.109, Table E-5).

DFAi = The maximum organ inhalation dose factor for the ith radionuclide, in (mrem/pCi).

The total body is considered as an organ in the selection of DFAi. (Ref. II. 11.5 and 11.14.4)

The results of periodic tritium, iodine and particulate samples of the Unit Vent and Radwaste Vent are used to verify the dose rate limit was not exceeded for the period during which the samples or composite samples were obtained.

APA-ZZ-01003 Rev. 013 3.3.2 Dose Due to Gaseous Effluents

) 3.3.2.1 Air Dose Due to Noble Gases The air dose at the SITE BOUNDARY~due to noble gases is calculated according to the following methodology (Ref. 11.8.9):

During any calendar quarter, for gamma radiation:

Dg = 3.17E-08 l[M, (X/Q) qj

5 mrad (3.9)

During any calendar quarter, for beta radiation:

Db = 3.17E-08 [N, (X/Q) q] *10 mrad (3.10)

During any calendar year, for gamma radiation:

Dg = 3.17E-08 [M 1(X/Q)q,] *lOmrad (3.11)

During any calendar year, for beta radiation:

Db = 3.17E-08 [ N, ( q I *20 mrad

)xQ) (3.12)

Where:

Dg = Air dose in mrad, from gamma radiation due to noble gases released in gaseous effluent.

Db = Air dose in mrad, from beta radiation due to noble gases released in gaseous effluents.

N = The air dose factor due to beta emissions for each identified noble gas radionuclide, i, in (mrad/yr) per (jgCiCm 3 ).

q = The releases of noble gas radionuclides, i, in gaseous effluents, for all gaseous releases in

(,uCi). Releases are cumulative over the calendar quarter or year as appropriate.- q, is calculated as the product of the ventilation flow rate and the measured activity of the effluent stream as determined by sampling.

3.17E-08 = The inverse of the number of seconds per year.

X I Q & M; are as previously defined.

APA-ZZ-0 1003 Rev. 013 3.3.2.2 Dose Due to Radionuclides Other than Noble Gases The dose to a MEMBER OF THE PUBLIC from Iodine-1 31 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY, is calculated according to the following expressions:

During any calendar quarter:

Ej Dij

7.5 mrem (3.13)

During any calendar year:

Ej DijS 15 mrem (3.14)

For each pathway, j, (i.e., for inhalation, ground plane, meat, cow- milk, goat- milk, and vegetation) Dlj is calculated according to the expression:

Do = 3.17E-8 A,Ri,;j [Wj qj] (3.15)

Where:

Do = Dose in mrem, to a MEMBER OF THE PUBLIC from radionuclides other than noble gases, from pathwayj, received by organ I (including total body).

R ,, = The dose factor for each identified radionuclide, i, in m2(mrem/yr) per (1Ci/sec) or (mrem/yr) per (pCi/m 3 ) as appropriate, for the pathway j, and exposed organ 1, appropriate to the age group of the critical MEMBER OF THE PUBLIC receptor.

Wi = (X /Q ) for the inhalation and tritium pathways, in (sec/m3 ). Refer to Tables 6. 1, 6.2, and 6.4 for applicability.

Wi = (DiQ) for the food and ground plane pathways, in (meters&2). Refer to Tables 6.1, 6.2 and 6.4 for applicability.

(D/ Q) = the average relative deposition of the effluent at or beyond the SITE BOUNDARY, considering depletion of the plume during transport.

qi = The releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases, i, in gaseous effluents, for all gaseous releases in ([pCi) Releases are cumulative over the calendar quarter or year as appropriate.

q, is calculated as the product of ventilation flow rate and the measured activity of the effluent stream as determined by sampling.

3.17 E-08 = The inverse of the number of seconds per year.

X / Q is as previously defined.

For the direction sectors with existing pathways within 5 miles from the site, the appropriate R I,ij values are used. If no real pathway exists within 5 miles from the center of the building complex, the cow-milk Rjjj value is used, and it is assumed that this pathway exists at the 4.5 to 5.0 mile distance in the limiting-case sector. If the R I,ij for an existing pathway within 5 miles is less than a cow-milk R I,ij at 4.5 to 5.0 miles, then the value of the cow-milk R jjj at 4.5 to 5.0 miles is used. (Ref. 11.8.9)

Although the annual average relative concentration(X / Q) and the average relative deposition rate ( IQ)are generally considered to be at the approximate receptor location in lieu of the SITE BOUNDARY for these calculations, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residence with the highest value of (X / Q) . (Ref. 11.8.9) The Total Body dose from ground plane deposition is added to the dose for each individual organ. (Ref. 11. 11.3)

- 18 -

APA-ZZ-01003 Rev. 013 3.4 GASEOUS RADWASTE TREATMENT SYSTEM

) The gaseous radwaste treatment systemnand the ventilation exhaust system are available for use whenever gaseous effluents require treatment prior to being released to the environment. The gaseous radwaste treatment system is designed to allow for the retention of all gaseous fission products to be discharged from the reactor coolant system. The retention system consists of eight (8) waste gas decay tanks. Normally, waste gases will be retained for at least 60 days prior to discharge. These systems will provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA.

The OPERABILITY of the gaseous radwaste treatment system ensures this system will be available for use when gases require treatment prior to their release to the environment.

OPERABILITY is demonstrated through compliance with REC 16.11.2.1, 16.11.2.2, and 16.11.2.3.

Projected doses (gamma air, beta air, and organ dose) due to gaseous effluents at or beyond the SITE BOUNDARY are determined each 31 days. The prior 31 day period is used to calculate compliance. This may be modified as appropriate to account for changes in radwaste treatment which may have a significant effect on the projected doses.

3.5 DOSE FACTORS The dose conversion factors provided in the following tables were derived from the appropriate dose conversion factors in Regulatory Guide 1.109 and other sources as necessary (Ref. 11.14.9 and 11.14.11). Per USNRC guidance, particulate nuclides with a half-life of less than 8 days are not considered (Ref: 11.24). Y-90, La-140, and Pr-144 are included because the jparent half-life is greater than 8 days, and equilibrium is assumed. Non-gamma emitting nuclides not listed in FSAR TABLE 16.11-4 are also not considered. -(COMN 43121)

APA-ZZ-01003 Rev. 013 TABLE 3.1 DOSE FACTOR FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor M i Ni Radionuclide (mrem/yr) per (pCi/m3 ) (mrad/yr) per (plCi/m 3 ) (mrad/yr) per (plCi/m3) (mrad/yr per (pCi/m3)

,M

_ t-E __X Kr-83m 7.56 E-02 1.93 E+01 2.88 E+02 Kr-85m 1.17E+03 1.46E+03 1.23 E+03 1.97 E+03 Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04 Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03 Kr-89 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90T 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 Xe-13 Im 9.15 E+01 4.76 E+02, 1.56 E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133' 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 Xe-135m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 Xe-137 1.42 E+03 1.22 E+04 1.51 E4-03 1.27 E+04 Xe-138 8.83 E+03 4.13 E+03 9.21 E+03 4.75 E+03 Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 20

APA-ZZ-0 1003 Rev. 013 TABLE 3.2 PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Ground Plane Pathway (ni 2 mrem/yr) per ([tCi/sec)

NUCLIDE TOTAL BODY SKIN Be-7 2.24E+07 3.21E+07 Cr-51 4.66E+06 5.51E+06 Mn-54 1.39E+09 1.63E+09 Fe-59 2.73E+08 3.21E+08 Co-57 2.98E+08 4.37E+08 Co-58 3.79E+08 4.44E+08 Co-60 2.15E+10 2.53E+10 Zn-65 7.47E+08 8.59E+08 Rb-86 8.99E+06 1.03E+07 Sr-89 2.16E+04 2.51E+04 Y-90 5.36E+06 6.32E+06 Y-91 1.07E+06 1.21E+06

) Zr-95 2.45E+08 2.84E+08 Nb-95 2.50E+08 2.94E+08 Ru-103 1.08E+08 1.26E+08 Ru-106 4.22E+08 5.07E+08 Ag-110m 3.44E+09 4.01E+09 Cd-109 3.76E+07 1.54E+08 Sn-1 13 1.43E+07 4.09E+07 Sb-124 8.74E+08 1.23E+09 Sb-125 3.57E+09 5.19E+09 Te-127m 9.17E+04 1.08E+05 Te-129m 1.98E+07 2.3 IE+07 21

APA-ZZ-01003 Rev. 013 TABLE 3.2 PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Ground Plane Pathway (m 2mrem/yr) per ([tCi/sec)

NUCLIDE TOTAL BODY SKIN 1-130 5.51E+06 6.69E+06 1-131 1.72E+07 2.09E+07 1-132 1.25E+06 1.47E+06 1-133 2.45E+06 2.98E+06 I-134 4.47E+05 5.3 lE+05 1-135 2.53E+06 2.95E+06 Cs-134 6.85E+09 8.OOE+09 Cs-136 1.51E+08 1.71E+08 Cs-137 1.03E+10 1.20E+10 Ba-140 2.05E+07 2.35E+07 La-140 1.47E+08 1.66E+08 Ce-141 1.37E+07 1.54E+07 Ce-144 6.96E+07 8.04E+07 Pr-144 4.35E+07 5.OOE+07 Nd-147 8.39E+06 1.01E+07 Eu-154 2.21E+10 3.15E+10 Hf-181 1.97E+08 2.82E+08 22

1' APA-ZZ-01 003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES

-Inhalation Pathway (mrem/yr) per (ptCi/m 3 )

Nndift Be=n Miver Total Lun L GELLI Bod~y H-3 ND 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 Be-7 8.47E+02 1.44E+03 9.25E+02 ND ND 6.47E+04 2.55E+03 Cr-51 ND ND 1.54E+02 8.55E+O1 2.43E+O1 1.70E+04 1.081E+03 Mn-54 ND 4.29E+04 9.5 IE+03 ND 1.OOE+04 1.58E+06 2.29E+04 Fe-55 4.74E+04 2.52E+04 7.77E+03 ND ND 1.1 IE+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 ND ND 1.27E+06 7.07E+04 Co-57 ND 9.03E+02 1.07E+03 ND ND 5.07E+05 1.32E+04 Co-58 ND 1.77E+03 3.166E+03 ND ND 1.1 IE+06 3.44E+04 Co-60 ND 1.31E+04 2.26E+04 ND ND 7.07E+06 9.62E+04 Zn-65 4.25E+04 1.13E+05 7.03E+04 ND 7.14E+04 9.95E+05 1.63E+04 Rb-86 ND 1.98E+05 1.14E+05 ND ND ND 7.999E+03 Sr-89 5.99E+05 ND 1.72E+04 ND ND 2.16E+06 1.67E+05

) Sr-90 1.0IE+08 ND 6.44E+06 ND ND 1.48E+07 3.43E+05 Y-90 4.1 IE+03 ND 1.1 lE+02 ND IND 2.62E+05 2.68E+05 Y-91 9.14E+05 ND 2.44E+04 ND ND 2.63E+06 1.84E+05 Zr-95 1.90E+05 4.1 8E+04 3.70E+04 ND 5.96E+04 2.23E+06 6.1 IE+04 Nb-95 2.35E+04 9.18E+03 6.55E+03 ND 8.62E+03 6.14E+05 3.70E+04 Ru-103 2.79E+03 ND 1.07E+03 ND 7.03E+03 6.62E+05 4.48E+04 Ru-106 1.36E+05 ND 1.69E+04 ND 1.84E+05 1.43E+07 4.29E+05 Ag-i lOm 1.69E+04 1.14E+04 9.14E+03 ND 2.12E+04 5.48E+06 1.OOE+05 Cd-109 ND 5.48E+05 2.59E+04 ND 4.96E+05 1.05E+06 2.78E+04 Sn-113 1.13E+05 3.12E+03 8.62E+03 2.33E+03 ND 1.46E+06 2.26E+05 Sb-124 5.74E+04 7.40E+02 2.00E+04 i1.26E+02 ND 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 ND - 2.32E+06 4.03E+04 Te-127m 2.49E+04 8.55E+03 3 .02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-129m 1.92E+041 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 23 -

APA-ZZ-0 1003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Inhalation Pathway (mrem/yr) per ([tCi/m 3 )

Nu~Ii& BO= Lier Total Thyrohl Li GLL1 Rody 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 ND 5.1 1E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 -ND 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 ND 3.20E+03 I-133 1.66E+04 2.03E+04 7.70E+03 - 3.85E+06 3.38E+04 ND 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 ND 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 ND 4.44E+03 Cs-134 6.5lE+05 1.O1E+06 2.25E+05 ND 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 ND 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 ND 2.82E+05 1.04E+05 3.62E+03 Ba-140 7.40E+04 6.48E+01 4.33E+03 ND 2.1lE+01 1.74E+06 1.02E+05 La-140 6.44E+02 2.25E+02 7.55E+O1 ND ND 1.83E+05 2.26E+05 Ce-141 3.92E+04 1.95E+04 2.90E+03 ND 8.55E+03 5.44E+05 5.66E+04 Ce-144 6.77E+06 2.12E+06 3.61E+05 ND 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 ND 3.OOE+03 4.33E+05 9.73E+04 Qr-144 5.96E-02 1.85E-02 3.00E-03 ND 9.77E-03 1.57E+03 1.97E+02 4d-147 1.08E+04 8.73E+03 6.81E+02 ND 4.81E+03 3.28E+05 8.21E+04 Eu-154 1.O1E+07 9.21E+05 8.40E+05 ND 4.03E+06 6.14E+06 1.lOE+05 Hf-181 2.78E+04 1.O1E+05 1.25E+04 ND 2.05E+04 1.06E+06 6.62E+04 24

APA-ZZ-01003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway (m2 mrem/yr) per (iCi/sec)

Nudidc Bne Limer Total ILLJ H-3 ND 2.34E+02 2.34E+02 2.34E+02 2.341E+02 2.34E+02 2.34E+02 Be-7 7.38E+03 1.26E+04 8.07E+03 0.OOE+00 1.23E+04 0.OOE+00 7.OOE+05 Cr-51 0.OOE+00 O.OOE+00 8.80E+03 4.8 81+03 1.331E+03 8.92E-I03 4.67E+05 Mn-54 O.OOE+00 8.02E+06 2.14E+06 O.OOE+00 2.25E+06 - .OOE+00 6.73E+06 Fe-55 4.58E+08 2.43E+08 7.52E+07 0.OOE+00 0.OOE3+00 I1.37E+08 4.50E+07 Fe-59 3.77E+08 6.1 OE+08 3.04E+08 O.OOE3+00 I1.77E+08 6.35E+08 0.OOE3+00 O.OOEtOO O.OOE+00 4.85E+07 Co-57 O.OOE+00 5.92E+06 1.20E+07 0.OOE+00 1.64E+07 5.03E+07 0.OOE3+00 0.OOE+00 0.OOE3+00 9.59E+07 Co-58 Co-60 0.00E+00 6.94E+07 2.05E+08 -0.OOE3+00 0.OOE+00 O.OOE3+00 3.84E+08 Zn-65 3.76E+08 1.00E+09 6.23E+08 o.OOE+o6 6.3 1E+08 O.OOE+00 1.76E+08 Rb-86 0.00E+00 5.77E+08 3.55E+08 0.OOE3+00 0.00E+00 O.OOE+00 3.7 1E+07 Sr-89 4.82E+08 .003E+00 1.38E+07 0.OOE+00 O.OOE-I00 0.OOE+00 1.87E+07 Sr-90 1.04E+10 0.00E+00 2.64E+09 O.OOEtOO 0.OOE3+00 0.OOE3+00 1.40E+08 0.0 OE+00 0.OOE+~00 0.OOE+00 5.49E+08 I Y-90 1.93E+05 O.OOE+00 5.166E+03 Y-91 1.80E+06 O.OOE+00 4.82E+04 O.OOE3+00 O.OOE+00 0.00OE+00 2.40E+08 Zr-95 2.67E+06 5.86E+05 5.22E+05 O.OOE+O0 8.391E+05 0.OOE2+00 6.1 IE+08 Nb-95 4.26E+06 1.66E+06 1.18E+06 0.OOE+00 I1.56E+06 0.001E+00 3.07E+09 Ru-103 1.55E+08 0.OOE+00 5.96E+07 0.OO3+O00 3.90E1I-08 0.00E+00 4.01E+09 Ru-106 4.44E+09 0.00E+00 5.54E+08 O.OOE-I00 6.OOE+09 O.OOE+00 6.911E+10 Ag-110m 8.40E+06 5.67E+06 4.53E+06 0.OOE+00 'l .06E+0 7 O.OOE+00 6.75E+08 Cd-109 0.OOE+00 1.911E+06 8.84E+04 0.OOE+00 1.70E+06 O.OOE3+00 6.18E+06 Sn-113 2.18E+09 4.48E+07 j1.24E+08 3.3 1E+09 0.OOE+00 0.OOE3+00 1.54E+09 Sb-124 2.93E+07 3.80E+05 1.03E+07 6.46E+04 0.OOE3+00 I1.62E3+07 1.83E+08 Sb-125 2.85E+07 2.20E+05 5.97E+06 2.64E3+04 0.OOE+00 1.59E+07 6.81 E+07 Te-127m 1.78E+09 4.78E+08 2.1 lE+08 4.251E+08 5.0713+09 O.OOE+00 1.44E+09 Te-129m 1.79E+09 5.OOE+08 2.78E+08 5 .781E+08 -5.26E+09 0.OOE3+00 2.19E+09 1-130 3.06E-06 6.18E-06 3.18E-06 6.80E-04 9.231E-06 0.OOE3+00 2.89E-06 I

- 25

APA-ZZ-0 1003 Rev. 013

-TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES 2Meat Pathway (m mrem/yr) per (gCi/sec)

Nnd~id-c BQne Liver Total Thyroid Kidney GLLI Body 1-131 1.66E+07 1.67E+07 9.47E+06 5.51E+09 2.74E+07 O.OOE+00 1.48E+06 1-132 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 5.70E-01 7.05E-01 2.67E-01 1.3 IE+02 1.17E+00 0.OOE+00 2.84E-01 1-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 1-135 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Cs-134 9.23E+08 1.5 lE+09 3.20E+08 O.OOE+00 4.69E+08 1.68E+08 8.17E+06 Cs-136 1.62E+07 4.46E+07 2.89E+07 0.OOE+00 2.38E+07 3.54E+06 1.57E+06 Cs-137 1.33E+09 1.28E+09 1.89E+08 0.OOE+00 4.16E+08 1.501E+08 8.OOE+06 Ba-140 4.39E+07 3.85E+04 2.56E+06 O.OOE+00 1.25E+04 2.29E+04 2.22E+07 La-140 3.33E+02 1.177E+02 3.93E+01 O.OOE+00 O.OOE+00 O.OOE+00 3.25E+06 Ce-141 2.22E+04 1.1IE+04 1.65E+03 O.OOE+00 4.86E+03 O.OOE+00 138E+07 Ce-144 2.32E+06 7.27E+05 1.24E+05 O.OOE+00 4.02E+05 O.OOE+00 1.89E+08 Pr-143 3.34E+04 l.OOE+04 1.66E+03 O.OOE+00 5.43E+03 O.OOE+00 3.61E+07 Pr-144 5.63E+02 1.74E+02 2.83E+01 O.OOE+00 9.21E+01 O.OOE+00 - 3.75E+05

) Nd-147 1.17E+04 9.48E+03 7.34E+02 0.OOE+00 5.20E+03 0.OOE+00 1.50E+07 Eu-154 1.12E+07 1.01E+06 9.20E+05 0.00E+00 4.43E+06 O0.OOE+00 2.34E+08 Hf-181 4.77E+06 1.74E+07 2.15E+06 O.OOE+00 3.53E+06 0.OOE+00 6.41E+09 26

I APA-ZZ-0 1003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES -

) OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m 2 mrem/yr) per (jiCi/sec)

Nuclid Limr Total Kidney !GL-LLI H-3 O.OOE+O0 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 Be-7 7.50E+03 1.28E+04 8.20E+03 0.OOE+OO 1.25E+04 0.OOE+00 7.12E+05 Cr-51 O.OOE+OO O.OOE+00 1.02E+05 5.66E+04 1.55E+04 1.03E+05 5.40E+06 Mn-54 O.OOE+OO 2.10E+07 5.599E+06 O.00E+00 5.89E+06 O.OOE+O0 1.76E+07 Fe-55 1.12E+08 5.94E+07 1.84E+07 0.OOE+O0 O.OOE+O0 3.36E+07 l.1OE+07 Fe-59 1.20E+08 1.95E+08 9.70E+07 0.OOE+00 O.OOE+OO 5.64E+07 2.03E+08 Co-57 0.OOE+O0 3.84E+06 7.78E+06 0.OOE+O0 0.OOE+O0 0.0OE+O0 3.15E+07 Co-58 O.OOE-+O0 1.21E4+07 3.72E+07 O.OOE+OO O.OOE+O0 O.OOE+00 7.08E+07 Co-60 0.00E+O0 4.32E+07 1.27E+08 O.OOE+00 O.OOE+O0 O.OOE+OO 2.39E+08 Zn-65 4.14E+09 1.lOE+10 6.86E+09 0.00E+O0 6.95E+09 O.OOE+OO 1.94E+09 Rb-86 0.OOE+O0 8.78E+09 5.40E+09 0.OOE+00 0.OOE+O0 O.OOE+OO 5.65E+08 Sr-89 6.63E+09 O.OOE+O0 1.89E+08 0.OOE+00 O.OOE+00 O.OOE+0OO- 2.57E+08

) Sr-90 Y-90 1.12E+1 I 3.38E+03 0.OOE+00 0.OOE+00 2.84E+10 9.05E+0l 0.OOE+O0 0.OOE3+00 0.OOE+O0 0.OOE+O0 O.OOE+O0 O.OOE+OO O.OOE+OO 1.51 E+09 9.62E+06 Y-91 3.9 1E+04 0.OOE+O0 1.04E+03 0.OOE+O0 O.OOE+OO 5.20E+06 O.OOE+00 Zr-95 3.84E+03 8.43E+02 7.5 lE+02 O.OOE+00 1.21E+03 0.OOE+00 8.80E+05 Nb-95 3.72E+05 1.45E+05 1.03E+05 O.OOE+O0 1.36E+05 O.OOE+OO 2.68E+08 Ru-103 4.29E+03 O.OOE+00 1.65E+03 0.OOE+O0 1.08E4+04 O.OOE+IOO 1.1 lE+05 9.25E+04 O.OOE+00 1.15E+04 0.OOE+00 1.25E+05 0.OOE+00 1.44E+06 Ru-106 2.09E+08 1.41E+08 1.133E+08 0.OOE+00 2.631E+08 O.OOE+00 1.68E+10 Ag-lOrm Cd-109 0.00E+00 3.86E+06 1.79E+05 3.45E+06 O.OOE+00 1.25E+07 Sn-1 13 6.1lE+08 1.26E+07 3.48E+07 9.29E+08 0.OOE+0O 0.OOE+0O 4.32E+08 1.09E+08 1.411E+06 3.81E+07 2.40E+05 0.00E+O0 6.03E+07 6.80E+08 Sb-124 Sb-125 8.7 1E+07 6.72E+05 1.83E+07 8.07E+04 O.OOE+O0 4.86E+07 2.08E+08 2.08E+08 5.61E+07 2.47E+07 4.988E+07 5.94E+08 O.OOE+OO 1.69E+08 Te-127m 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 O.OOE+00 3.3 lE+08 Te-129m 27

4 APA-ZZ-01003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway 2

(m mrem/yr) per ([tCi/sec)

Nudlid BRne Lerf Total Lung Gl-LLI 1-130 1.73E+06 3.50E+06 1.80E+06 3.85E+08 5.23E+06 O.OOE+00 1.64E+06 1-131 1.30E+09 1.31E+09 7.46E+08 4.34E+11 2.15E+09 O.OOE+O0 1.17E+08 1-132 6.92E-01 1.27E+00 5.85E-01 5.90E+01 1.95E+00 O.OOE+OO 1.50E+00 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.54E+07 O.OOE+OO 8.57E+06 1-134 O.OOE+0O O.OOE+0O O.OOE+O0 O.OOE+0O O.OOE+O0 O.OOE+00 O.OOE+O0 1-135 5.41E+04 9.74E+04 4.61E+04 - 8.63E+06 1.49E+05 O.OOE+0O 7.42E+04 Cs-134 2.27E+10 3.72E+10 7.84E+09 O.OOE+O0 1.15E+10 4.14E+09 2.OOE+08 Cs-136 1.O1E+09 2.78E+09 1.80E+O9- O.OOE+O0 1.48E+09 2.21E+08 9.78E+07 Cs-137 3.23E+10 3.09E+1O 4.56E+09 O.OOE+00 1.O1E+10 3.62E+09 1.93E+08 Ba-140 1.17E+08 1.03E+05 6.84E+06 O.OOE+O0 3.34E+04 6.12E+04 5.94E+07 Ce-141 2.19E+04 1.09E+04 1.62E+03 O.OOE+O0 4.79E+03 O.OOE+00 1.36E+07 La-140 1.78E+02 6.23E+O1 2.1OE+O1 O.OOE+00 O.OOE+OO O.OOE+00 1.74E+06 Ce-144 1.62E+06 5.09E+05 8.67E+04- O.OOE+00 2.82E+05 O.OOE+O0 1.33E+08 Pr-143 7.19E+02 2.16E+02 3.57E+O1 O.OOE+O0 1.17E+02 O.OOE+00 7.76E+05 Pr-144 5.04E+00 1.56E+00 2.53E-O1 O.OOE+00 8.24E-01 O.OOE+00 3.35E+03 Nd-147 4.45E+02 3.61E+02 2.79E+O1 O.OOE+O0 1.98E+02 O.OOE+0O 5.71E+05 Eu-154 9.43E+04 8.48E+03 7.75E+03 O.OOE+O0 3.73E+04 O.OOE+00 1.97E+06 Hf-181 6 44E+02 2.35E+03 2.9 lE+02 O.OOE+O0 4.76E+02 O.OOE+00 8.66E+05 28

. t APA-ZZ-01 003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (R1) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m 2 mremlyr) per ([iCi/sec)

Numdidc Bifl Liver Total Thyroid GL1:LU H-3 O.OOE+O0 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 Be-7 9.OOE+02 1.53E+03 9.84E+02 O.OOE+00 1.50E+03 O.OOE+OO 8.55E+04 Cr-51 O.OOE+OO O.OOE+00 I.22E+04 6.79E+03 1.85E+03 1.24E+04 6.48E+05 Mn-54 O.OOE+00 2.52E+06 6.71E+05 O.OOE+00 7.06E+05 O.OOE+O0 2.1 lE+06 Fe-55 1.45E+06 7.72E+05 2.39E+05 O.OOE+0O 0.OOE+00 4.36E+05 1.43E+05 Fe-59 1.56E+06 2.53E+06 1.26E+06 O.OOE+00 O.OOE+O0 7.34E+05 2.64E+06 Co-57 O.OOE+O0 4.61E+05 9.33E+05 O.OOE+00 O.OOE+O0 O.OOE+00 3.78E+06 Co-58 O.OOE+00 1.46E+06 4A6E+06 O.OOE+O0 O.OOE+00 0.OOE+00 8.50E+06 Co-60 0.OOE+00 5.19E+06 1.53E+07 O.OOE+00 O.OOE+00 O.OOE+O0 2.87E+07 Zn-65 4.97E+08 1.32E+09 8.23E+08 O.OOE+00 8.34E+08 O.OOE+00 2.32E+08 Rb-86 O.OOE+00 1.05E+09 6.48E+08 O.OOE+O0 O.OOE+00 O.OOE+00 6.78E+07 Sr-89 1.39E+10 O.OOE+00 3.97E+08 O.OOE+00 O.OOE+00 O.OOE+00 5.39E+08 Sr-90 2.35E+I 1 O.OOE+00 5.95E+10 O.OOE+00 O.OOE+00 0.OOE+OO 3.16E+09 Y-90 4.06E+02 O.OOE+00 1.09E+O I O.OOE+00 O.OOE+00 O.OOE+00 1.15E+06

,) Y-9 1 4.69E+03 O.OOE+O0 1.25E+02 O.OOE+O0 O.OOE+00 O.OOE+00 6.25E+05 Zr-95 4.60E+02 1.O1E+02 9.01E+01 O.OOE+00 1.45E+02 O.OOE+00 1.06E+05 Nb-95 4.46E+04 1.74E+04 1.24E+04 O.OOE+00 1.63E+04 O.OOE+00 I 3.21E+07 Ru-103 5.14E+02 O.OOE+OO 1.98E+02 O.OOE+OO 1.29E+03 O.OOE+O0 1.33E+04 Ru-106 1.II E+04 O.OOE+00 1.3 8E+03 O.OOE+00 1.50E+04 O.OOE+00 1.73E+05 Ag-I lOm 2.5 1E+07 1.69EI07 1.35E+07 O.OOE+00 3.15E+07 O.OOE+00 2.01E+09 Cd-109 O.OOE+00 4.64E+05 2.15E+04 O.OOE+0O 4.14E+05 O.OOE+00 1.50E+06 Sn-i 13 7.33E+07 1.51E+06 4.18E+06 1.1IE+08 O.OOE+00 O.OOE+00 5.18E+07

-Sb-124 1.30E+07 1.69E+05 4.57E+06 2.88E+04 O.OOE+00 7.24E+06 8.16E+07 Sb-125 1.05E+07 8.06E+04 2.19E+06 9.68E+03 O.OOE+00 5.83E+06 2.50E+07 Te-127m 2.50E+07 6.73E+06 2.97E+06 5.98E+06 7.13E+07 O.OOE+00 2.02E+07 Te-129m 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.57E+07 O.OOE+00 3.98E+07 1-130 2.08E+06 4.20E+06 2.16E+06 4.62E+08 6.27E+06 O.OOE+00 1.96E+06 1-131 1.57E+09 1.57E+09 8.95E+08 5.21E+I I 2.58E+09 1.40E+08 1-132 8.30E-01 1.53E+0O 7.02E-O1 7.08E+01 2.34E+00 O.OOE+00 1.80E+00 29

APA-ZZ-01003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (mnmrem/yr) per (pCi/sec)

Nuclide Bone Li3er Total Thyroid LunLIg GlL Body 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO 1.03E+07 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-135 6.49E+04 1.17E+05 5.53E+04 1.04E+07 1.79E+05 O.OOE+OO -8.90E+04 Cs-134 6.80E+10 1.12E+11 2.35E+10 O.OOE+OO 3.46E+10 1.24E+10 6.01E+08 Cs-136 3.04E+09 8.35E+09 5.40E+09 O.OOE+OO 4.45E+09 6.63E+08 2.93E+08 Cs-137 9.68E+10 9.27E+10 1.37E+10 O.OOE+OO 3.02E+10 1.09E+10 5.80E+08 Ba-140 1.4 1E+07 1.23E+04 8.21E+05 O.OOE+OO 4.01E+03 7.35E+03 7.13E+06 La-140 2.14E+01 7.47E+00 2.52E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.08E+05 Ce-141 2.63E+03 1.31lE+03 1.95E+02 O.OOE+OO 5.75E+02 O.OOE+OO 1.63E+06 Ce-144 1.95E+05 6.1 lE+04 1.04E+04 O.OOE+OO 3.38E+04 O.OOE+OO 1.59E+07 Pr-143 8.63E+01 2.59E+01 4.28E+OO O.OOE+OO 1.40E+O1 O.OOE+OO 9.31 E+04 Pr-144 6.05E-01 1.87E-01 3.04E-02 O.OOE+OO 9.89E-02 O.OOE+OO 4.03E+02 Nd-147 5.34E+O1 4.33E+01 3.35E+OO O.OOE+OO 2.37E+O1 O.OOE+OO 6.85E+04 Eu-154 1.13E+04 1.02E+03 9.29E+02 O.OOE+OO 4.47E+03 O.OOE+OO 2.37E+05 Hf-181 7.73 E+O 1 2.81 E+02 3.49E+O1 O.OOE+OO 5.72E+O1 O.OOE+OO 1.04E+05 30

@w .X APA-ZZ-01003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (R1 ) FOR RADIONUCLIDES

.) OTHER THAN NOBLE GASES Vegetation Pathway (m2mrem/yr) per (liCi/sec)

Nuhlid-c Bone Limr Total Thyroid H-3 ND 4.01E+03 4.01E+03 4.01E+03 4.0 1E+03 4.01E+03 4.0 1E+03 Be-7 3.388E+05 5.76E+05 3.70E+05 O.OOE3+00 5.65E+05 0.OOE+O0 3.2 1E+07 Cr-51 O.OOE+00 0.OOE+00 I.17E+05 6.501E+04 1.78E+04 1.191E+05 6.21E+06 Mn-54 O.OOE+00 6.65E+08 1.77E+08 0.OOE3+00 1.86E+08 0.OOE3+00 5.58E+08 Fe-55 8.01E+08 4.25E+08 1.32E+08 0.OOE3+00 O.OOE+00 2.401E+08 7.87E+07 Fe-59 3.98E+08 6.43E+08 3.20E+08 0.OOE3+00 O.OOE+00 I1.871E+08 6.70E+08 Co-57 O.OOE+00 2.99E+07 6.04E+07 O.OOE3+00 0.OOE+00 0.OOE+O0 2.45E+08 Co-58 O.OOE+00 6.44E+07 1.97E+08 0.OOE+~00 0.OOE+00 O.OOE3+00 3.76E+08 Co-60 0.OOE+00 3.78E+08 1.12E+09 0.OOE3+00 O.OOE+00 0.OOE3+00 2.10E+09 Zn-65 8.13E+08 2.177E+09 1.35E+09 0.OOE+00 1.36E+09 0.OOE+00 3.80E+08 Rb-86 O.OOE+00 4.52E+08 2.78E+08 0.OOE3+00 0.OOE+00 0.OOE3+00 2.91E+07 Sr-89 3.60E+10 0.OOE+00 1.03E+09 0.OOE+00 O.OOE+00 O.OOE3+00 1.39E+09 Sr-90 1.24E+12 0.OOE+00 3.15E+I I 0.OOE3+00 0.OOE+00 O.OOE3+00 1.67E+10 Y-90 3.01E+06 O.OOE+00 8.04E+04 0.OOE+00 0.OOE+00 O.OOE+00 8.56E+09

) Y-91 1.86E+07 - 0.OOE+00 4.99E+05 0.OOE3+00 O.OOE+00 0.OOE+00 2.48E+09 Zr-95 3.86E+06 8.48E+05 7.55E+05 0.OOE+00 1.211E+06 0.OOE3+00 8.85E+08 Nb-95 7.48E+05 2.911E+05 2.08E+05 - .OOE+00 2.74E+05 0.OOE3+00 5.39E+08 Ru-103 1.53E+07 O.OOE+00 5.90E+06 O.OOE3+00 3.86E+07 0.OOE+00 3.97E+08 Ru-106 7.45E+08 0.OOE+00 9.30E+07 0.OOE+00 1.011E+09 O.OOE3+00 1.16E+10 Ag- lOnm 3.21E+07 2.17E+07 1.73E+07 - .OOE+00 4.04E+07 0.OOE3+00 -2.58E+09 Cd-109 0.OOE+00 2.45E+08 1.14E+07 * .OOE+00 2.18E+08 0.OOE3+00 7.94E+08 Sn-13 1.58E+09 3.25E+07 9.OOE+07 2.40E+09 O.OOE+00 0.OOE3+00 1.12E+09 Sb-124 -3.52E+08 4.57E+06 1.23E+08 -7.77E;05 0.OOE+00 1.95E+08 2.20E+09 Sb-125 4.99E+08 3.85E+06 1.05E+08 4.63E+05 O.OOE+00 2.78E+08 1.19E+09 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.OOE3+00 1.07E+09 Te-129m 8.4 1E+08 2.355E+08 1.3 lE+08 2.71E+08 2.47E+09 0.OOE3+00 1.03E1+09 I-130 6.16E+05 1.24E+06 6.41E+05 I1.37E3+08 1.86E+06 0.OOE3+00 5.82E+05 1-131 1.43E+08 1.44E+08 8.17E+07 4.761E+10 2.36E+08 0.OOE3+00 1.28E+07 31

APA-ZZ-01003 Rev. 013 TABLE 3.3 CHILD PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Vegetation Pathway (m2mrem/yr) per (plCi/sec)

Nuclide Bone Liver Total- - Tid Kne Lung GLLl I 1.70E+02 7.80E+O1 7.87E+03 2.60E+02 O.OOE+OO 2.00E+02 I-132 9.23E+OI 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 O.OOE+OO 1.76E+06 I-133 2.89E-04 1.33E-04 6.65E-03 4.42E-04 O.OOE+O0 1.92E-04 1-134 1.56E-04 1.13E+05 5.33E+04 9.98E+06 1.73E+05 O.OOE+00 8.59E+04 I-135 6.26E+04 2.93E+09 2.63E+10 5.55E+09 O.OOE+00 8.15E+09 I A2E+08 Cs-134 1.60E+10 1.80E+07 2.27E+08 1.47E+08 O.OOE+00 1.21E+08 7.96E+06 Cs-136 824E+07 2.29E+10 3.38E+09 O.OOE+O0 7.46E+09 2.68E+09 1.43E+08 Cs-137 2.39E+10 2.43E+05 1.62E+07 O.OOE+00 7.90E+04 1.45E+05 I .40E+08 Ba-140 2.77E+08 1.18E+04 3.96E+03 ,O.OOE+00 O.OOE+00 O.OOE+00 3.28E+08 La-140 3.36E+04 4.08E+08 3.27E+05 4.86E+04 0.OOE+O0 1.43E+05 O.OOE+OO Ce-141 6.56E+05 3.98E+07 6.78E+06 O.OOE+00 2.21E+07 I O.OOE+0O 1.04E+10 Ce-144 1.27E+08 1.46E+05 4.37E+04 7.23E+03 O.OOE+00 2.37E+04 O.OOE+O0 1.57E+08 Pr-143 2.44E+03 3.97E+02 O.OOE+OO 1.29E+03 O.OOE+OO -5.25E+06 Pr-144 7.88E+03 4A8E+03 O.OOE+00 3.18E+04 O.OOE+O0 9.17E+07 Nd-147 7.15E+04 5.79E+04 1.50E+07 1.37E+07 O.OOE+O0 6.57E+07 O.OOE+O0 3.48E+09 Eu-154 1.66E+08

.) 4.90E+05 1.79E+06 2.21E+05 O.OOE+OO 3.63E+05 O.OOE+00 -6.59E+08 Hf-181

?

32

A

. . r.

APA-ZZ-01003 Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Inhalation Pathway (mrem/yr) per (iiCi/m 3 )

Nudid-c Lbcr - Total GILLU BMI H-3 ND 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 Be-7 4.27E+02 9.688E+02 4.70E+02 ND ND 4.2 1E+04 5.35E+03 Cr-5I ND ND I.OOE+02 5.95E+01 2.28E+0 1 1.44E+04 3.322+03 Mn-54 ND 3.96E+04 6.30E+03 ND 9.84E+03 - 1.40E+06 7.74E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 ND ND 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 ND ND 1.02E+06 1.88E+05 Co-57 ND 6.92E+02 6.71E+02 ND ND 3.70E+05 3.14E+04 Co-58 ND 1.58E+03 2.07E+03 ND ND 9.28E+05 1.06E+05 Co-60 ND 1.15E+04 1.48E+04 ND ND 5.97E+06 2.85E+05 Zn-65 3.24E+04 1.03E+05 4.66E+04 ND 6.90E+04 8.64E+05 5.34E+04 Rb-86 ND 1.35E+05 5.90E+04 ND ND ND 1.66E+04 Sr-89 3.04E+05 ND 8.72E+03 ND ND 1.40E+06 3.502+05 Sr-90 9.92E+07 ND 6.10E+06 ND ND 9.60E+06 7.22E+05

) Y-90 2.09E+03 ND 5.61E+01 ND ND 1.70E+05 5.06E+05 Y-91 4.62E+05 ND 1.24E+04 ND ND 1.70E+06 3.85E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 ND 5.42E+04 1.77E+06 1.50E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 ND 7.74E+03 5.05E+05 1.042+05 Ru-103 1.53E+03 ND 6.58E+02 ND 5.83E+03 5.05E+05 1.1 OE+05 Ru-106 6.91 E+04 ND 8.72E+03_ ND 1.34E+05 9.36E+06 9.12E+05 Ag- lOnm 1.08E+04 11.OOE+04 5.94E+03 ND 1.97E+04 4.63E+06 3.02E+05 Cd-109 ND - 3.67E+05 1.3 lE+04 ND 3.57E+05. 6.83E+05: 5.82E+04 Sn-I 13 5.72E+04 2.18E+03 4.39E+03 1.24E+03 ND 9.44E+05 1.18E+05 Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 ND 2.48E+06 4.06E+05 Sb-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 ND 1.74E+06 1.0lE+05 Te-127m 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1-130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 ND 7.69E+03 1-131 2.52E+04 3.582+04 2.05E+04 - 1.19E+07 6.13E+04 ND 6.28E+03 33

APA-ZZ-01003 Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Inhalation Pathway (mrem/yi) per-( Ci/m3 )

Nucidec Bone Limer Total Kidne LungLI Rody 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 ND 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 ND 8.88E+03 1-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 ND 1.01E+OO I-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.1IE+04 ND 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 ND 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.1OE+05 ND 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.21E+05 4.28E+05 ND 2.22E+05 7.52E+04 8.40E+03 Ba-140 3.90E+04 4.90E+01 2.57E+03 ND 1.67E+01 1.27E+06 2.18E+05 La-140 3.44E+02 1.74E+02 4.58E+O1 ND ND 1.36E+05 4.58E+05 Ce-141 1.99E+04 1.35E+04 1.53E+03 ND 6.26E+03 3.62E+05 1.20E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 ND- 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 - ND 2.16E+03 2.81 E+05 2.00E+05 Pr-144 3.0IE-02 1.25E-02 1.53E-03 ND 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.1OE+03 3.65E+02 ND 3.56E+03 2.21E+05 1.73E+05 Eu-154 5.92E+06 7.28E+05 5.18E+05 ND 3.49E+06 4.67E+06 2.72E+05 Hf-181 1.41E+04 6.82E+04 6.32E+03 ND 1.48E+04 6.85E+05 1.39E+05 34

APA-ZZ-01003 Rev. 013 TABLE 3.4 ADULT-PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Meat Pathway (m2mrem/yr) per (gCi/sec)

Nndidg BDnM Liver Total GELLU Rody H-3 ND 3.25E+02 3.25E+02 3.25E+02 3.25E+02 3.25E+02 3.25E+02 Be-7 4.57E+03 1.04E+04 5.07E+03 ND 1.11OE+04 ND 1.81E+06 Cr-51 ND ND 7.04E+03 4.2 1E+03 1.55E+03 9.34E+03 1.77E+06 Mn-54 ND 9.17E+06 1.75E+06 ND 2.731E+06 ND 2.8 1E+07 Fe-55 2.93E+08 2.02E+08 4.72E+07 ND ND 1. 13E+08 1.16E+08 Fe-59 2.65E+08 6.24E+08 2.39E+08 ND ND 1.74E+08 2.08E+09 Co-57 ND 5.63E+06 9.36E+06 ND ND ND 1.43E+08 Co-58 ND 1.82E+07 4.08E+07 ND ND ND 3.69E+08 Co-60 ND 7.51 E+07 1.66E+08 ND ND ND 1.41E+09 Zn-65 3.56E+08 1.13E+09 5.1 IE+08 ND 7.57E+08 ND 7.13E+08 Rb-86 ND 4.87E+08 2.27E+08 ND ND ND 9.60E+07 Sr-89 3.01E+08 ND 8.65E+06 ND ND ND 4.83E+07 Sr-90 1.24E+10 ND 3.05E+09 ND ND ND 3.59E+08

) Y-90 1.21E+05 ND 3.24E+03 ND ND ND 1.28E+09 Y-91 1.13E+06 ND 3.02E+04 ND ND ND 6.23E+08 Zr-95 1.87E+06 6.00E+05 4.06E+05 ND 9.42E+05 ND 1.90E+09 Nb-95 3.15E+06 1.75E+06 9.43E+05 ND 1.73E+06 ND 1.06E+10 Ru-103 1.05E+08 ND 4.531E+07 ND 4.01E+08 ND 1.23E+10 Ru-106 2.80E1+09 ND 3.54E+08 ND 5.40E+09 ND 1.81E+1I Ag- lOnm 6.68E+06 6.18E+06 3.67E+06 ND 1.2 IE+07 ND- 2.52E+09 Cd-109 ND 1.59E+06 5.55E+04 ND 1.52E+06 ND 1.60E+07 Sn-i 13 1.37E+09 3.88E+07 7.86E+07 -2.22E+07 ND ND- 4.09E+09 Sb-124 1.98E+07 3.74E+05 7.84E+06 4.79E+04 ND -- 1.54E+07 - 5.61E+08 Sb-125 - 1.91E+07 2.13E+05 4.54E+06 1.94E+04 ND 1.47E+07 2.10E+08 Te-127m 1.l1E+09 3.98E+08 1.36E1+08 2.85E+08 4.53E+09 ND 3.74E+09 Te-129m 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 ND 5.7 1E+09 I-130 2.12E-06 6.27E-06 2.47E-06 5.3 IE-04 9.78E-06 ND 5.40E-06 1-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 ND 4.06E+06

}

35

APA-ZZ-01003 Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Meat Pathway (m 2mrem/yr) per (jCi/sec)

Nuclid BDon Liver Total ThIiA GILLI 1-132 O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+.OO O.OOE+OO ND O.OOE+OO I-133 3.67E-01 6.39E-01 1.95E-01 9.38E+O1 1.1l1E+OO ND 5.74E-O1 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 O.OOE+OO ND O.OOE+OO 1-135 O.OOE+OO O.OOE+OO O.OOE+0O O.OOE+OOO O.OOE+OO ND O.OOE+OO Cs-134 6.57E+08 1.56E+09 1.28E+09 ND 5.06E+08 1.68E+08 2.74E+07 Cs-136 1.20E+07 4.76E+07 3.42E+07 ND 2.65E+07 3.63E+06 5.40E+06 Cs-137 8.71E+08 1.19E+09 7.8lE+08 ND 4.04E+08 1.34E+08 2.31E+07 Ba-140 2.87E+07 3.61E+04 1.88E+06 ND 1.23E+04 2.07E+04 5.91E+07 La-140 2.21E+02 1.IlE+02 -2.94E+O1 ND ND ND 8.18E+06 Ce-141 1.40E+04 9.49E+03 1.08E+03 ND 4.41E+03 ND 3.63E+07 Ce-144 1.46E+06 6.09E+05 7.82E+04 ND 3.61E+05 ND 4.92E+08 Pr-143 2.1OE+04 8.40E+03 1.04E+03 ND 4.85E+03 ND 9.18E+07 Pr-144 3.52E+02 1.46E+02 1.79E+O1 ND 8.24E+O1 ND 5.06E-05 Nd-147 7.07E+03 8.17E+03 4.89E+02 ND 4.77E+03 ND 3.92E+07 Eu-154 8.02E+06 9.86E+05 7.O1E+05 --ND 4.72E+06 ND 7.144E+08 Hf-18 1 3.01E+06 1.46E+07 1.35E+06 ND 3.14E+06 ND 1.66E+10 36

APA-ZZ-01003 Rev. 013 1 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) . OTHER THAN NOBLE GASES -

Grass-Cow-Milk Pathway (m mrein/yr) per (pCi/sec)

Nuclide Blnn Lier Total di~ 'GhLLI Body H-3 ND 7.63E+02 - 7.63E+02 7.63E1+02 7.63E+02 7.63E+02 7.63E+02 Be-7 1.63E+03 3.72E+03 1.811E+03 ND 3.93E+03 -ND 6.45E+05 Cr-SI ND ND 2.86E+04 1.7 IE+04 6.30E+03 3.79E+04 7.19E+06 Mn-54 ND 8.42E+06 1.61E+06 -ND 2.50E+06 ND 2.58E+07 Fe-55 2.51E+07 1.74E+07 - 4.05E+06 ND ND - -9.68E+06 --9.96E+06 Fe-59 -2.97E+07 6.98E+07 2.68E+07 ND ND 1.95E+07 2.33E+08 Co-57 ND 1.28E+06 2.133E+06 ND ND ND 3.25E+07 Co-58 ND 4.72E+06 1.06E+07 ND ND ND 9.56E+07 Co-60 ND 1.64E+07 3.62E+07 ND ND ND 3.08E+08 Zn-65 1.37E+09 4.37E+09 1.97E+09 ND 2.92E+09 ND 2.75E+09 Rb-86 ND 2.60E+09 1.21E+09 ND ND ND 5.12E+08 Sr-89 1.45E+09 ND 4.17E+07 ND ND ND 2.33E+08 Sr-90 4.68E+10 ND 1.15E+10 ND ND ND 1.35E+09

) Y-90 7.43E+02 ND 1.99E+01 ND ND ND 7.87E+06 Y-91 8.59E+03 ND 2.30E+02 ND ND ND 4.73E+06 Zr-95 9.44E+02 3.03E+02 2.05E+02 ND 4.75E+02 ND 9.59E+05 Nb-95 9.65E+04 5.37E+04 2.89E+04 ND 5.3 1E+04 ND 3.26E+08 Ru-103 1.02E+03 ND 4.39E+02 ND 3.89E+03 ND 1.19E+05 Ru-106 2.04E+04 ND 2.58E+03 ND 3.94E+04 ND 1.32E+06 Ag-llOm 5.82E+07 5.39E+07 3.20E+07 ND -1.06E+08 ND -2.20E+10 Cd-109 ND 1.13E+06 3.95E+04 -ND 1.08E+06 ND 1.14E+07 Sn-I 13 1.34E+08 3.811E+06 7.73E+06 2.188E+06 -ND ND - 4.02E+08 Sb-124 2.57E+07 4.86E+05 1.02E+07 6.24E+04 ND 2.00E+07 7.31E+08 Sb-125 2.04E+07 2.28E+05 4.87E+06 2.08E+04 ND 1.58E+07 2.25E+08 Te-127m 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 -ND 1.54E+08 Te-129m 6.02E+07 2.25E+07 9.53E+06 2.07E+07 2.5 1E+08 ND 3.03E+08 1-130 4.21E+05 1.24E+06 4.9 1E+05 1.05E+08 1.94E+06 ND 1.07E+06 1-131 2.97E+08 4.25E+08 2.43E+08 1.39E+I I 7.28E+08 ND 1.12E+08 37

APA-ZZ-01003 Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (i 2 mrem/yr) per (gCi/sec)

Nudide Bne= Limr Total Tyodide Lung i 1-132 1.65E-01 4.42E-01 1.55E-01 1.55E+01 7.04E-O1 ND 8.30E-02 1-133 3.88E+06 6.75E+06 2.06E+06 9.92E+08 1.18E+07 ND 6.07E+06 I-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND O.OOE+OO 1-135 1.29E+04 3.37E+04 1.25E+04 2.23E+06 5.41 E+04 ND 3.81E+04 Cs-134 5.65E+09 1.35E+10 1.1OE+1O -0 ND 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.48E+08 ND 5.79E+08 7.93E+07 - 1.18E+08 Cs-137 7.38E+09 1.01E+10 6.61E+09 ND 3.43E+09 1.14E+09 1.95E+08 Ba-140 2.69E+07 3.38E+04 1.76E+06 ND 1.15E+04 1.93E+04 5.54E+07 La-140 4.14E+01 2.09E+OI 5.51E+OO ND ND ND 1.53E+06 Ce-141 4.85E+03 3.28E+03 3.72E+02 ND 1.52E+03 ND 1.25E+07 Ce-144 3.58E+05 1.50E+05 1.92E+04 ND 8.87E+04 ND 1.21E+08 Pr-143 1.58E+02 6.34E+01 7.83E+OO ND 3.66E+OI ND 6.92E+05 Pr-144 1.1OE+OO 4.58E-01 5.61E-02 ND 2.58E-O1 ND 1.59E-07

) Nd-147 9.42E+01 1.09E+02 6.5 1E+OO 2.07E+03 ND ND 6.36E+O I 1.39E+04 ND ND 5.23E+05 2.11 E+06 Eu-154 2.37E+04 2.91 E+03 Hf-181 1.42E+02 6.92E+02 6.41E+01 ND 1.49E+02 ND 7.87E+05 38

. , - 1-41 APA-ZZ-01003 Rev. 013

- TABLE 3.4 ADULT PATHWAY DOSE FACTORS (Ri) FOR RADIONUCLIDES

, OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m 2 mrem/yr) per (gCi/sec)

Nucide BDne Limer Total Thyroid Kidney -GL-LLI Roady H-3 ND 1.56E+03 1.56E+03 1.56E+03 1.562+03 1.56E+03 1.56E+03 Be-7 1.96E+02 4.47E+02 2.17E+02 ND 4.72E+02 ND 7.74E+04 Cr-51 ND ND 3.43E+03 2.05E+03 7.56E+02 4.56E+03 8.632+05 Mn-54 ND 1.01E+06 1.93E+05 ND 3.01E+05 ND - 3.10E+06 Fe-55 3.27E+05 2.262+05 5.26E+04 ND ND 1.26E+05 1.30E+05 Fe-59 3.87E+05 9.08E+05 3.48E+05 ND ND 2.54E+05 3.03E+06 Co-57 ND 1.54E+05 2.56E+05 ND ND ND 3.90E+06 Co-58 ND 5.66E+05 1.27E+06 ND ND ND 1.15+07 Co-60 ND 1.97E+06 4.35E+06 ND ND ND 3.70E+07 Zn-65 1.65E+08 5.24E+08 2.37E+08 ND 3.51E+08 ND 3.30E+08 Rb-86 ND 3.122+08 1.45E+08 ND ND ND 6.15E+07 Sr-89 3.05E+09 ND 8.75E+07 ND ND ND 4.89E+08 Sr-90 9.84E+10 ND 2.41E+10 ND ND ND 2.842+09 Y-90 8.92E+01 ND 2.39E+00 ND ND ND 9.46E+05

) Y-91 1.03E+03 ND 2.76E+01 ND ND ND 5.68E+05 Zr-95 1.13E+02 3.63E+01 2.46E+Ol ND 5.70E+01 ND - 1.15E+05 Nb-95 1.16E+04 6.45E+03 3.47E+03 ND 6.37E+03 ND 3.912+07 Ru-103 1.22E+02 ND 5.27E+01 ND 4.67E+02 ND - 1.432+04 Ru-106 ' 2.45E+03 ND 3.1 OE+02 -ND 4.73E+03 ND 1.59E+05 Ag-ll0m 6.99E+06 6.47E+06 3.84E+06 ND 1.27E+07 ND 2.64E+09 Cd-109 ND 1.36E+05 4.74E+03 ND 1.30E+05 ND 1.37E+06 Sn-1 13 1.6 1E+07 4.58E+05 9.28E+05 - 2.62E+05 -ND ND 4.83E+07 Sb-124 3.09E+06 5.84E+04 1.23E+06 - 7.50E+03 ND 2.41E+06 8.78E+07 Sb-125 2.46E+06 2.74E+04 5.84E+05 2.50E+03 ND 1.89E+06 2.70E+07 Te-127m 5.50E+06 1.97E+06 6.70E+05 1.41E+06 -2.23E+07 ND -1.84E+07 Te-129m 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 ND 3.64E+07 1-130 5.05E+05 1.49E+06 i 5.88E+05 1.26E+08 2.32E+06 ND 1.28E+06 1-131 3.56E+08 5.09E+08 2.92E+08 - 1.67E+l I 8.72E+08 ND 1.342+08 1-132 1.98E-01 5.29E-01 1.85E-01 1.85E+01 8.43E-01 ND 9.95E-02 39

APA-ZZ-0 1003 Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway M2 (m mrem/yr) per (pCilsec)

Nuclid ___ Livr Total Thyid Lung GL-LLI Boady 1-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41E+07 ND 7.27E+06 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND O.OOE+OO I-135 1.54E+04 4.04E+04 1.49E+04 2.67E+06 6.48E+04 ND 4.57E+04 Cs-134 1.70E+10 4.04E+10 3.30E+10 ND 1.31E+1O 4.34E+09 7.07E+08 Cs-136 7.91E+08 3.12E+09 2.25E+09 ND 1.74E+09 2.38E+08 3.55E+08 Cs-137 2.22E+10 3.03E+10 1.99E+10 ND 1.03E+10 3.42E+09 5.87E+08 Ba-140 3.23E+06 4.06E+03 2.12E+05 ND 1.38E+03 2.32E+03 6.65E+06 La-140 4.97E+00 2.51 E+OO 6.62E-O1 ND ND ND 1.84E+05 Ce-141 5.82E+02 3.94E+02 4.46E+O1 ND 1.83E+02 ND 1.50E+06 Ce-144 4.30E+04 1.80E+04 2.3 1E+03 ND 1.07E+04 ND 1.45E+07 Pr-143 1.90E+O I 7.61E+00 9AOE-O1 ND 4.39E+OO ND 8.3 1E+04 Pr-144 1.33E-01 5.50E-02 6.74E-03 ND 3.1OE-02 ND 1.911E-08 Nd-147 1.13E+01 1.31 E+O I 7.82E-O1 ND 7.64E+OO ND 6.28E+04 Eu-154 2.84E+03 3.49E+02 2.49E+02 ND 1.67E+03 ND 2.53E+05

_) Hf-181 1.71E+O1 8.31E+O 1 7.70E+OO ND 1.79E+O1 ND 9.46E+04 40

APA-ZZ-0 1003 Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Vegetation Pathway (m 2mrem/yr) per (pCi/sec)

Nunlidc Bone Liicr Total Thyroid Lung GILLI Body H-3 ND 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 Be-7 9.24E+04 2.1 IE+05 1.03E+05 ND 2.23E+05 ND 3.66E+07 Cr-51 ND ND 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 Mn-54 ND 3.13E+08 5.97E+07 ND - 9.31 E+07 ND 9.59E+08 Fe-55 2.1OE+08 1.45E+08 3.38E+07 ND ND 8.08E+07 8.3 1E+07 Fe-59 1.26E+08 2.96E+08 1.14E+08 ND ND 8.28E+07 9.88E+08 Co-57 ND 1.17E+07 1.95E+07 ND ND ND 2.97E+08 Co-58 ND 3.07E+07 6.89E+07 ND ND ND 6.23E+08 Co-60 ND 1.67E+08 3.69E+08 ND ND ND 3.14E+09 Zn-65 3.17E+08 1.01IE+09 4.56E+08 ND 6.75E+08 ND -6.36E+08 Rb-86 ND 2.19E+08 1.02E+08 ND ND ND 4.33E+07 Sr-89 9.97E+09 ND 2.86E+08 ND ND ND 1.60E+09 Sr-90 6.05E+1 1 ND 1.48E+ 1 ND ND ND 1.75E+10 Y-90 7.67E+05 ND 2.06E+04 ND ND ND 8.14E+09 Y-91 5.1 IE+06 ND 1.37E+05 ND ND ND 2.8 1E+09 Zr-95 1.17E+06 3.77E+05 2.55E+05 ND 5.91 E+05 ND 1.19E+09 Nb-95 2.40E+05 1.34E+05 7.19E+04 ND 1.32E+05 ND 8.1IE+08 Ru-103 4.77E+06 ND 2.06E+06 ND 1.82E+07 ND 5.57E+08 Ru-106 1.93E+08 ND 2.44E+07 ND 3.72E+08 ND 1.25E+10 Ag-11Om 1.05E+07 9.75E+06 5.79E+06 ND 1.92E+07 ND 3.98E+09 Cd-109 O.OOE+OO 8.36E+07 2.92E+06 ND 8.00E+07 ND 8.43E+08 Sn-113 4.16E+08 1.18E+07 2.40E+07 6.75E+06 ND ND 1.25E+09 Sb-124 1.04E+08 1.96E+06 4.1 IE+07 2.51E+05 ND 8.07E+07 2.94E+09 Sb-125 1.37E+08 1.53E1+06 -3.25E+07 1.39E+05 ND 1.05E+08 1.50E+09 Te-127m 3.49E+08 1.25E+08 4.26E+07 8.92E+07 - 1.42E+09 ND 1.17E+09 Te-129m 2.51E+08 9.38E+07 3.98E+07 8.64E+07 1.05E+09 ND 1.27E+09 1-130 3.93E+05 1.16E+06 4.57E+05 9.8 1E+07 1.81E+06 ND 9.97E+05 1-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 ND 3.05E+07 41

- I

, 'S APA-ZZ-01003:

Rev. 013 TABLE 3.4 ADULT PATHWAY DOSE FACTORS (RI) FOR RADIONUCLIDES

) OTHER THAN NOBLE GASES Vegetation Pathway (m 2mrem/yr) per (pCi/sec)

Nuclide ROM Limer Total Thyri Lng GELLI 1.54E+02 5.40E+01 5.40E+03 2.46E+02 ND 2.90E+Ol 1-132 5.77E+01 3.63E+06 1.1lE+06 5.33E+08 6.33E+06 ND 3.26E+06 I-133 2.09E+06 9.69E-05 2.63E-04 9.42E-05 4.56E-03 4.19E-04 ND 2.30E-07 1-134 1.02E+05 3.77E+04 6.74E+06 1.64E+05 ND 1.15E+05 1-135 3.90E+04 4.67E+09 1.IIE+10 9.08E+09 ND -3.59E+09 1.19E+09 1.94E+08 Cs-134 4.27E+07 1.69E+08 1.21E+08 ND 9.38E+07 1.29E+07 1.91E+07 Cs-136 8.70E+09 5.70E+09 ND 2.95E+09 9.81E+O8 1.68E+08 Cs-137 6.36E+09 1.61E+05 8.42E+06 ND 5.49E+04 9.24E+04 2.65E+08 Ba-140 1.29E+08 7.98E+03 2.11E+03 ND ND ND - 5.86E+08 La-140 1.58E+04 1.97E+05 1.33E+05 1.51E+04 ND 6.19E+04 ND 5.1OE+08 Ce-141 3.29E+07 1.38E+07 1.77E+06 ND 8.16E+06 ND 1.1 1E+10 Ce-144 6.26E+04 2.51E+04 3.1OE+03 ND 1.45E+04 ND 2.74E+08 Pr-143 2.03E+03 8.43E+02 1.03E+02 ND 4.75E+02 ND 2.92E-04 Pr-144 3.33E+04 3.85E+04 2.3 1E+03 ND 2.25E+04 ND 1.85E+08

) Nd-147 4.85E+07 5.97E+06 4.25E+06 ND 2.86E+07 ND 4.32E+09 Eu-154 1.40E+05 6.82E+05 6.32E+04 ND 1.47E+05 ND 7.76E+08 Hf-181 42

APA-ZZ-01003 Rev. 013 4 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES

) 4.1 CALCULATION OF DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES The annual dose or dose commitment to a MEMBER OF THE PUBLIC for Uranium Fuel Cycle Sources is determined as:

a) Dose to the total body and internal organs due to gamma ray exposure from submersion in a cloud of radioactive noble gases, ground plane exposure, and direct radiation from the Unit, onsite storage of low-level radioactive waste, and outside storage tanks; b) Dose to skin due to beta radiation from submersion in a cloud of radioactive noble gases, and ground plane exposure; c) Thyroid dose due to inhalation and ingestion of radioiodines; and d) Organ dose due to inhalation and ingestion of radioactive material.

It is assumed that total body dose from sources of gamma radiation irradiates internal body organs at the same numerical rate. (Ref. 11.12.5)

The dose from gaseous effluents is considered to be the summation of the dose at the individual's residence and the dose to the individual from activities within the SITE BOUNDARY.

Since the doses via liquid releases are very conservatively evaluated, there is reasonable assurance that no real individual will receive a significant dose from radioactive liquid release pathways. Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiation are considered in determining compliance to 40 CFR 190 (Ref. 11.12.3).

There are no other Uranium Fuel Cycle Sources within 8km of the Callaway Plant.

4.1.1 Identification of the MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC is considered to be a real individual, including all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site for recreational or other purposes not associated with the plant (Ref. 11.4 and 11.8.10).

Accordingly, it is necessary to characterize this individual with respect to his utilization of areas both within and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions which could be reevaluated if necessary to demonstrate continued compliance with 40 CFR 190 through the use of more realistic assumptions (Ref. 11.12.3 and 11.12.4).

The evaluation of Total Dose from the Uranium Fuel Cycle should consider the dose to two Critical Receptors: a) The Nearest Resident, and b) The Critical Receptor within the SITE BOUNDARY.

4.1.2 Total Dose to the Nearest Resident The dose to the Nearest Resident is due to plume exposure from' noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident.

It is assumed that direct radiation dose from operation of the Unit and outside storage tanks, and dose from gaseous effluents due to activities within the SITE BOUNDARY, is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q.

The location of the Nearest Resident in each meteorological sector is determined from the Annual Land Use Census conducted in accordance with the Requirements of REC 16.11.4.2.

APA-ZZ-01003 Rev. 013 4.1.3 Total Dose to the Critical Receptor Within the SITE BOUNDARY

) The Union Electric Company has entered into an agreement with the State of Missouri Department of Conservation for management of the residual lands surrounding the Callaway Plant, including some areas within the SITE BOUNDARY. Under the terms of this agreement, certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, sightseeing, etc.) but recreational use is excluded in an area immediately surrounding the plant site (refer to Figure 4.1). Much of the residual lands within the SITE BOUNDARY are leased to area farmers by the Department of Conservation to provide income to support management and development costs. Activities conducted under these leases are primarily comprised of farming (animal feed), grazing, and forestry (Ref. 11.7.2, 11.7.3, 11.13, and 11.13.1)

Based on the utilization of areas within the SITE BOUNDARY, it is reasonable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities within the SITE BOUNDARY-is due to exposure incurred while conducting his farming activities. The current tenant has estimated that he spends approximately 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months per-year working in this area (Ref. 11.5.5). Occupancy of areas within the SITE BOUNDARY is assumed to be averaged over a period of one year.

Any reevaluation of assumptions should consider only real receptors and real pathways using realistic assumption, and should include a reevaluation of the occupancy period at the locations of real exposure (e.g. a real individual would not simultaneously exist at each point of maximum exposure).

4.1.3.1 Total Dose to the Fanner from Gaseous Effluents The Total Dose to the farmer from gaseous effluents is calculated for the adult age group using the methodology discussed in Sectioni 3, utilizing concurrent meteorological data at the farmer's residence and historical meteorological data from Table 6.1 for activities within the SITE BOUNDARY. These dispersion parameters were calculated by assuming that the farmer's time is equally distributed over the areas farmed within the SITE BOUNDARY, and already have the total occupancy of 1100 hour0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months s/year factored into their value (Ref. 11.5.6).

The residence of the current tenant is located at a distance of 3830 meters in the SE sector. The gaseous effluents dose at the farmer's residence is due to plume exposure from Noble Gases and the ground plane, inhalation, and ingestion pathways. For conservatism, it is acceptable to assume that all of the ingestion pathways exist at this location.

It is assumed that food ingestion pathways do not exist within the SITE BOUNDARY, therefore the gaseous effluents dose within the SITE BOUNDARY is due to plume exposure from Noble Gases and the ground plane and inhalation pathways.

4.1.3.1.1 Direct Radiation Dose from Outside Storage Tanks The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radioactive materials, and constitutes the only potentially significant source of direct radiation dose from outside storage tanks to a MEMBER OF THE PUBLIC (Ref. 11.6.14, 11.6.15, 11.6.16 and 11.6.17).

Direct radiation dose from the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures, which is 450 meters from the RWST. -

The RWST is a right circular cylinder approximately, 12 meters in diameter, 14 meters in height with a capacity of approximately 1,514,000 liters (Ref. 11.6.17). The walls are of type 304 stainless steel and have an average thickness of .87 cm. (Ref. 11.14.1).

The direct radiation dose from the RWST is calculated based on the tank's average isotopic content and the parameters discussed above, considering buildup and attenuation within the volume source. Appropriate methodology for calculating the dose rate from a volume source is given in TID-7004, "Reactor Shielding Design Manual" (Ref. 11.17). The computer program ISOSHLD (Ref. 1.18, 11.19 and 11.20) will normally be utilized to perform this calculation.

APA-ZZ-01003 Rev. 013 4.1.3.1.2 Direct Radiaion Dose from the Reactor

) The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC has been determined to be 7E-2 mrads/calendar year, based on a point source of primary coolant N-1 6 in the steam generators. This source term was then projected onto the inside surface of the containment dome, taking credit for shielding provided by the containment dome and for distance attenuation. No credit was allowed for shielding by other structures or components within the' Containment Building. The number of gammas per second was generated and then converted to a dose rate at the given distance by use of ANSI/ANS-6.6. 1, "Calculation and Measurement of Direct and Scattered Gamnma Radiation from LWR Nuclear Power Plant 1979",

which considers attenuation and buildup in air. The final value is based on one unit operating at 100% Power. The distance was determined to be 367 meters, which is approximately the closest point of the boundary of the Owner Controlled Area fence which is not obscured by significant plant structures (Ref. 11.14.3).

The maximum direct radiation dose from the Unit to the farmer is thus approximately 9E-3 mrads per year, assuming a maximum occupancy of 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months per year.

4.1.3.1.3 Direct Radiation Dose From On-Site Storage Of Low Level Radioactive Waste The on-site storage area for radioactive wastes is located Plant Southwest of the radwaste building and consists of a concrete pad enclosed by a fence. The storage area is bounded on two sides by the radwaste building. The area is also partially bounded on a third side by the Discharge monitoring tanks dike system.:The radioactive wastes are stored in this area using high integrity containers (HIC) inside Onsite Storage Containers (OSC) and LSA type storage containers. The HIC has the highest potential for containing significant amounts of radioactive material, and constitutes the only potentially significant source of direct radiation from on-site radioactive waste storage.

Direct radiation dose from the HICs to a MEMBER OF THE PUBLIC is determined at the

) nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures.

The HICs typically are right circular cylinders approximately 1.7 meters in diameter and 1.8 meters in height. The HICs are stored inside OSCs which typically are constructed of concrete with additional shielding as necessary to minimize external doses. The individual parameters (e.g., dimensions,- shielding material, etc.) for each OSC will be accounted for in the calculations.

The direct radiation dose from the On-Site Storage area is the summation of the individual calculated HIC doses based on the HIC isotopic contents and the OSC design parameters, considering buildup, attenuation, and shielding. Appropriate methodology for calculating the dose rate is given in Safety Analysis Calculations ZZ-293 and ZZ-3 10. The computer program MICROSHIELD (Ref. 11.24) will normally be utilized to perform this calculation.

APA-ZZ-01003 Rev.

46

APA-ZZ-01003 Rev. 013 5 RADIOLOGICAL ENVIRONMENTAL MONITORING

)

5.1 DESCRIPTION

OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is intended to act as a background data base for preoperation and to supplement the radiological effluent release monitoring program during plant operation. Radiation exposure to the public from the various specific pathways and direct radiation can be adequately evaluated by this program.

Some deviations from the sampling frequency may be necessary due to seasonal unavailability, hazardous conditions, or other legitimate reasons. Efforts are made to obtain all required samples within the required time frame. Any deviation(s) in sampling frequency or location is documented in the Annual Radiological Environmental Operating Report.

REMP sampling locations that use meteorological sectors and or distance from the plant site were verified as described in reference 11.28.

Sampling, reporting, and analytical requirements are given in FSAR Tables 16.11-7, 16.11-8, and 16.11-9.

Airborne, waterbome, and ingestion samples collected under the monitoring program are analyzed by an independent, third-party laboratory. This laboratory is required to participate in the Environmental Measurements Laboratory Quality Assessment Program (EML) or an equivalent program. Participation includes all of the determinations (sample medium - -

radionuclide combination) that are offered by EML and that are also included in the monitoring program.

5.2 PERFORMANCE TESTING OF ENVIRONMENTAL THERMOLUMINESCENCE DOSIMETERS

) Thermoluminescence Detectors (TLD's) used in the Environmental Monitoring Program are tested for accuracy and precision to demonstrate compliance with Regulatory Guide 4.13 (Ref. 11.16).

Energy dependence is tested at several energies between 30keV and 3MeV corresponding to the approximate energies of the predominant Noble Gases (80, 160, 200 keV),-Cs-137 (662 keV),

Co-60 (1225 keV), and at least one energy less than 80 keV. Other testing is performed relative to either Cs-137 or Co-60. (Ref 11.14.10) 6 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM ATMOSPHERIC DISPERSION PARAMETERS 6.1 ATMOSPHERIC DISPERSION PARAMETERS The values presented in Table 6.1 and Table 6.2 were determined through the analysis of on-site meteorological data collected during the three year period of May 4, 1973 to May 5, 1975 and March 16, 1978 to March 16, 1979. --

6.1.1 Long-Term Dispersion Estimates The variable trajectory plume segment atmospheric transport model MESODIF-II (NUREGI-CR-0523) and the straight-line Gaussian dispersion model XOQDOQ (NUREG/CR2919) were used for determination of the long-term atmospheric dispersion parameters. A more detailed discussion of the methodology and data utilized to calculate these parameters can be found elsewhere (Ref. 11.6.12).

The Unit Vent and Radwaste Building Vent releases are at elevations of 66.5 meters and 20 meters above grade, respectively. Both release points are within the building wake of the structures on which they are located, and the unit Vent is equipped with a rain cover which effectively eliminates the possibility of the exit velocity exceeding five times the horizontal wind speed. All gaseous releases are thus considered to be ground-level releases, and therefore no mixed mode or elevated release dispersion parameters were determined (Ref. 11.5.2).

A . APA-ZZ-0 1003 Rev. 013 6.1.2 Determination of Long-Term Dispersion Estimates for Special Receptor Locations

) Calculations utilizing the PUFF model were performed for 22 standard distances to obtain the desired dispersion parameters. Dispersion parameters at the SITE BOUNDARY and at special receptor locations were estimated by logarithmic interpolation according to (Ref. 11.6.13):

X = XI (d/d 1 ) (6.1)

Where:

B =In (X2 IX) In (d2 I d,).

X1, X2 = Atmospheric dispersion parameters at distance d1 and d2 , respectively, from the source.

The distances di and d2 were selected such that they satisfy the relationship.

d1 <d<d 2 6.1.3 Short Term Dispersion Estimates Airborne releases are classified as short term if they are less than or equal to 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months during a calendar year and not more than 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months in any quarter. Short term dispersion estimates are determined by multiplying the appropriate long ternmdispersion estimate by a correction factor (Ref. 11.9.1 and 11.15.1):

F =(Ts / Ta) (6.2)

Where:

Ts = The total number of hours of the short term release.

Ta = The total number of hours in the data collection period from which the long term diffusion estimate was determined (Refer to Section 6.1).

Values of the slope factor (S), are presented in Table 6.3.

Short term dispersion estimates are not applicable to short term releases which are sufficiently random in both time of day and duration (e.g., the short term release periods are not dependent solely on atmospheric conditions or time of day) to be represented by the annual average dispersion conditions (Ref. 11.8.1).

6.1.3.1 The Determination of the Slope Factor(S)

The general approach employed by subroutine PURGE of XOQDOQ (Ref. 11.15.1) was utilized to produce values of the slope of the (X/Q) curves for both the Radwaste Building Vent and the Unit Vent. However, instead of using approximation procedures to produce the 15 percentile (X/Q) values, the 15 percentile (X/Q) value for each release and at each location was determined by ranking all the 1-hour((X/Q)1 ) values for that release and at that location in descending order.

The (X/Q)l value which corresponded to the 15 percentile of all the calculated (X/Q) values within a sector was extracted for use in the intermittent release (X/Q) calculation.

The intermittent release (X/Q) curve was constructed using the calculated 15 percentile (X/Q) i and its corresponding annual average (XIQ)a. A graphic representation of how the computational procedure works is illustrated by Figure 4.8 of reference 11.15.1. The straight line connecting these points represents (X/Q) I values for intermittent releases; ranging in duration from one hour to 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months . The slope (S) of the curve is expressed as:

-log ((X/Q)1 I(XQ)a) (6 3)

Iog(Ta /T 1 )

or S -(log (XIQ) 1 - log (X/Q)a) (6.4)

- logTa - log T APA-ZZ-01003 Rev. 013 6.1.4 Atmospheric Dispersion Parameters for Farming Areis within the SITE BOUNDARY The dispersion parameters for farming areas within the SITE BOUNDARY are intended for a

) - narrow scope application: That of calculating the dose to the current farmer from gaseous effluents while he conducts farming activities within the SITE BOUNDARY.

For the purpose of these calculations, it was assumed that all of the farmer's time, approximately 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months per year, is spent on croplands within the SITE BOUNDARY, and that his time is divided evenly over all of the croplands. Fractional acreage/time weighted dispersion parameters were calculated for each plot as described in reference 11.5.6. The weighted dispersion parameters for each plot were then summed (according to type) in order to produce a composite value of the dispersion parameters which are presented in Tables 6.1 and 6.2. These dispersion parameters therefore represent the distributed activities of the farmer within the SITE BOUNDARY and his estimated occupancy period.

6.2 ANNUAL METEOROLOGICAL DATA PROCESSING The annual atmospheric dispersion parameters utilized in the calculation of doses for demonstration of compliance with the numerical dose objectives of 10 CFR 50, Appendix 1, are determined using computer codes and models consistent with XOQDOQ (Ref. 1.15). These codes have been validated and verified by a qualified meteorologist prior to implementation.

Multiple sensors are utilized to ensure 90% valid data recovery for the wind speed, wind direction, and ambient air temperature parameters as required by Regulatory Guide 1.23. The selection hierarchy is presented in Table 6.5.

The vertical height of the highest adjacent building (V) used to perform concurrent year annual average atmospheric dispersion (XIQ) calculations is 169.16 meters (Ref. 11.29).

Meteorological Data is periodically verified to ensure valid data is being collected. Health Physics is responsible to ensure this review is performed.

)

APA-ZZ-01003 Rev.

TABLE 6.1 HIGHEST ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS UNIT VENT DISTANCE X/Q X/Q SECTOR (METERS) X/Q DECAYED/ DECAYED/ D/Q LOCATION (b)

UNDEPLETED DEPLETED (sec/rn) (sec/m ) (sec/mr) (m 2 )

NNW 2200 l.OE-6 9.9E-7 8.5E-7 4.3E-9 SITE BOUNDARY(a)

NNW 2897 6.7E-7 6.6E-7 5.6E-7 X2.6E-9 Nearest Residence (c) (d)

SE 3830 2.5E-7 2.5E-7 2.1E-7 .IE-9 Farmer's Residence(c)

N/A N/A 2.6E-7 2.6E-7 2.4E-7 1.3E-9 Farming Areas within the Site Boundary (c) (e)

(a) Values given are from FSAR TABLE 2.3-82 (b) Data from 1998 Land Use Census (c) Values derived from FSAR TABLE 2.3-82, using the methodology presented in Equation (6.1) (Ref. 11.5.6)

(d) All pathways are assumed to exist at the location of the nearest resident.

for use in (e) These values were derived for a narrow scope application. Extreme caution should be exercised when determining their suitability other applications.

Building Shape Parameter (C) = 0.5 (Ref. 11.5.3)

Vertical Height of Highest Adjacent Building (V) = 66.45 meters (Ref. 11.5.3) 50

APA-ZZ-01003 .,

Rev. 013 TABLE 6.2 HIGHEST ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS RADWASTE VENT AND LAUNDRY DECON FACILITY DRYER EXHAUST DISTANCE X/Q ' XIQ LOCATION (b) SECTOR (METERS) X/Q - DECAYED/ DECAYED/ D/Q, UNDEPLETED DEPLETED (Sec/ (sec/m, =sec/m)(

SITE BOUNDARY(a) NNW 2200 1.3E-6 1.3E-b 1.lb-O 1 r-y 4.o 2897 8.5E-7 8.5E-7 7.1E-7 2.6E-9 Nearest Residence (c) (d) NNW SE 3830 3.OE-7 3.OE-7 2.4E-7 1.lE-9 Farmer's Residence(c)

N/A N/A 3.5E-7 3.5E-7 3.2E-7 1.3E-9 Farming Areas Within Site Boundary (c) (e)

(a) Values given are from FSAR TABLE 2.3-84, (b) Data from 1998 Land Use Census (c) Values derived from FSAR TABLE 2.3-81, using the methodology presented in Equation (6.1) (Ref. 11.5.6)

(d) All pathways are assumed to exist at the location of the nearest resident.

(e) These values were derived for a narrow scope application. Extreme caution should be exercised when determining their suitability for use in other applications.

Building Shape Parameter (C) = 0.5 (Ref. 11.5.3)

Vertical Height of Highest Adjacent Building (V) = 19.96 meters (Ref. 11.5.3) 51

.1 APA-ZZ-01003 Rev. 013 TABLE 6.3 SHORT DISPERSION PARAMETERS (a) (c)

Slope Factor(s)

Location (b) Sector Distance Unit Vent Radwaste Building Vent Site Boundary S 1300 -.328 -.320 Nearest Residence (d) NNW 2897 -.264 -.268 (a) Reference 11.5.3 (b) Data from 1998 Land Use Census (c) Recirculation Factor = 1.0 (d) All pathways are assumed to exist at the location of the nearest resident.

52

APA-ZZ-01003 Rev. (

TABLE 6.4 APPLICATION OF ATMOSPHERIC DISPERSION PARAMETERS Dose Pathway Dispersion Parameter Controlling Age Group Rec Controlling Location Noble Gas, x/Q, decayed/undepleted N/A 16.11.2.2 Site Boundary Beta Air & Gamma Air (2.26 day half-life)

Noble Gas, x/Q, decayed/undepleted N/A 16.11.2.1 Site Boundary Total Body & Skin (2.26 day half-life)

Inhalation x/Q, decayed/depleted Child 16.11.2.1 Nearest Resident (8 day half-life) 16.11.2.3 Site Boundary Ground Plane Deposition D/Q N/A 16.11.2.3 Nearest Resident

,Ingestion pathways D/Q* Child 16.11.2.3 Nearest Resident

For H-3, x/Q, decayed/depleted is used instead of D/Q (Ref. 11.11. 1).

53

APA-ZZ-01003 Rev. 013 TABLE 6.5

) METEOROLOGICAL DATA SELECTION HIEARCHY Parameter Primary First Second Third Alternate Alternate Alternate Wind Speed lOm Pri lOm Sec 60m Pri 90m Pri Wind Direction lOm Pri lOm Sec 60m Pri 90m Pri Air Temperature lOm Pri lOm Sec Wind Variability lOin Pri lOm Sec 60m Pri 90m Pri Temp Different 60-lOm Pri 90-lOm Pri 90-60 Pri Dew Point lOm Pri Precipitation Im Pri (a) Pri indicates primary tower

) (b) Sec indicates secondary tower

- -54

APA-ZZ-01003 N.-

Rev. 013 Table 6.6 Application of Atmospheric Dispersion Parameters: Radioactive Efuent Release Report Dispersion Parameter Controlling Dispersion Values Controlling Location Dose Pathway

~Age Group x/Q, decayed/undepleted N/A Concurrent Site Boundary Noble Gas, (2.26 day half-life) Nearest Resident Beta Air & Gamma Air Dose x/Q, decayed/undepleted N/A Concurrent Site Boundary Noble Gas, (2.26 day half-life) Nearest Resident Total Body & Skin Dose Concurrent Farmer's Residence Historical Inside Site Boundary D/Q N/A Concurrent Site Boundary Ground Plane Deposition Dose Nearest Resident, Concurrent Farmer's Residence Historical Inside Site Boundary x/Q, decayed/depleted Child Concurrent Site Boundary Inhalation Dose (8 day half-life) Nearest Resident Adult Concurrent Farnher's Residence Historical Inside Site Boundary D/Q* Child Concurrent Site Boundary Ingestion Dose Pathways Nearest Resident Adult Concurrent Farmer's Residence Historical Inside Site Boundary

For H-3, x/Q, decayed/depleted is used instead of D/Q (Ref. 11.11.1).

APA-ZZ-01003 Rev. 013 7 REPORTING REOUIREMENTS

) 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL'OPERATING REPORT (COMN 2804)

The reporting requirements for the Annual Radiological Environmental Operating Report have been relocated to FSAR 16.11.5.1.

7.2 RADIOACTIVE EFFLUENT RELEASE REPORT (COMN 28005 The reporting requirements for the Radioactive Effluent Release Report have been relocated to FSAR 16.11.5.2.

A)

I-APA-ZZ-01003 Rev. 013

) 8 IMPLEMENTATION OF ODCM METHODOLOGY (COMN 2791)

The ODCM provides the mathematical relationships used to implement the Radioactive Effluent Controls. For routine effluent release and dose assessment, computer codes are utilized to implement the ODCM methodologies. -These codes are evaluated in accordance with the requirements of plant operating procedures to ensure that they produce results consistent with the methodologies presented in the ODCM. Plant procedures implement the ODCM methodology.

APA-ZZ-0 1003 Rev. 013 9 RADIOACTIVE EFFLUENT CONTROLS (REC)

The Radioactive Effluent Controls have been relocated to FSAR 16.1 1, -"Offsite Dose Calculation Manual Radioactive Effluent Controls". The former ODCM REC numbers appear on each of the REC's in the FSAR, and may be used as a cross-reference between the previous and the current numbering system if necessary.

APA-ZZ-01003 Rev. 013 10 ADMINISTRATIVE CONTROLS

) 10.1 MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS 10.1.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. A summary of the change MUST be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the On-Site Review Committee (ORC). On site documentation MUST contain:

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

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

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

4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from' those previously predicted in the License application and amendments thereto;

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

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

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

8) Documentation of the fact that the change was reviewed and found acceptable by the ORC.

b. Changes to the Radwaste Treatment Systems Shall become effective upon review and approval by the ORC.

10.2 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) (COMN 2815) 10.2.1 All changes to the ODCM shall be completed pursuant to T/S AC 5.5.1 and approved as per APA-ZZ-00101, "Preparation, Review, Approval and Control of Procedures".

10.2.1.1 All changes shall be approved by the ORC prior to implementation.

10.2.2 Review for each revision of the ODCM must include, as a minimum, the Health Physics, and Quality Assurance Departments.

10.2.3 A complete and legible copy of each revision of the ODCM that became effective during the last-annual period shall be submitted as a part of, or concurrent with that years Radioactive Effluent Release Report pursuant to T/S AC 5.5.1.

APA-ZZ-0 1003 Rev. 013 11 REFERENCES 11.1 Title 10, "Energy", Chapter 1, Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402.

11.1.1 Statements of Consideration, Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, Subpart D, page 23374.

11.2 Title 10, "Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S.

Government Printing Office, Washington, D.C. 20402.

11.2.1 10 CFR 50.36 a (b) 11.3 Title 40, "Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S.

Government Print Office, Washington, D.C. 20402.-

11.4 U.S. Nuclear Regulatory Commission, "Technical Specifications Callaway Plant, Unit NO. I",

NUREG-1058 (Rev. 1), October 1984. Section 5.4.1 11.5 COMMUNICATIONS 11.5.1 LetterNEO-54, D. W. Capone to S.:E. Miltenberger, dated January 5, 1983; Union Electric Company correspondence.

11.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values", J. H. Smith (Bechtel Power Corporation), to D. W. Capone (Union Electric Co.), dated February 27, 1984.

11.5.3 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Electric Co.), dated February 9, 1984.

11.5.4 Reference Deleted 11.5.5 Private Communication, H. C. Lindeman & B.F. Holderness, August 6, 1986 11.5.6 Calculation ZZ-67, "Annual Average Atmospheric Dispersion Parameters", April 1989.

11.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report.

11.6.1 Section 11.5.2.2.3.1 11.6.2 Section 11.5.2.2.3.4 11.6.3 Section 11.5.2.1.2 11.6.4 Section 11.5.2.2.3.2 11.6.5 Section 11.5.2.2.3.3 11.6.6 Section 11.2.3.3.4 11.6.7 Section 11.2.3.4.3 11.6.8 Section 11.5.2.3.3.1 11.6.9 - Section 11.5.2.3.3.2 -

11.6.10 Section 11.5.2.3.2.3 =

11.6.11 Section 11.5.2.3.2.2 - -

11.6.12 Section2.3.5 11.6.13 Section 2.3.5.2.1.2 -

11.6.14 Section 9.2.6 11.6.15 Section 9.2.7.2.1 -

11.6.16 Section 6.3.2.2 11.6.17 Table 11.1-6 11.6.18 Deleted

-60

APA-ZZ-0 1003 Rev. 013 11.6.19 Deleted 11.6.20 Deleted 11.6.21 Deleted 11.6.22 Table 2.3-68 11.7 Union Electric Company Callaway Plant Environmental Report, Operating License Stage.

11.7.1 Table 2.1-19 11.7.2 Section 2.1.2.3 11.7.3 Section 2.1.3.3.4 11.7.4 Section 5.2.4.1 11.7.5 Table 2.1-19 11.8 U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specification forNuclear Power Plants", USNRC NUREG-0133, Washington, D. C. 20555, October 1978.

11.8.1 Pages AA-I through AA-3 11.8.2 Section 5.3.1.3 11.8.3 Section 4.3 11.8.4 Section 5.3.1.5 11.8.5 Section 5.1.1 11.8.6 Section 5.1.2 11.8.7 Section 5.2.1 11.8.8 Section 5.2.1.1 11.8.9 Section 5.3.1 11.8.10 Section 3.8 11.8.11 Section 3.3 11.9 U.S. Nuclear Regulatory Commission, -"XOQDOQ, Program For the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG-0324, Washington, D. C. 20555. -

11.9.1 Pages 19-20 Subroutine PURGE 11.10 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, U. S. -

Nuclear Regulatory Commission, Washington, D. D. 20555, July, 1977.

11.10.1 -Section c.l.b 11.10.2 Figures 7 through 10 11.10.3 Section c.4 - -

11.11 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 1I, Revision I,.U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, October 1977.

11.11.1 Appendix C, Section 3.a 11.11.2 Appendix E, Table E-15 11.11.3 Appendix C, Section 1 11.11.4 Appendix E, Table E-11 v- V -

APA-ZZ-0 1003 Rev. 013 11.11.5 Appendix E, Table E-9 11.12 U. S. Nuclear Regulatory Commission, "Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.

C. 20555, January 1980.

11.12.1 Section 1,Page 2 11.12.2 Section IV, Page 8 11.12.3 Section IV, Page 9 11.12.4 Section III, Page 6 11.12.5 Section III, Page 8 11.13 Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 21, 1982.

11.13.1 Exhibit A 11.14 MISCELLANEOUS REFERENCES 11.14.1 Drawing Number M-109-0007-06, Revision 5 11.14.2 Callaway Plant Annual Environmental Operating Report (updated annually) 11.14.3 UE Safety Analysis Calculation 87-001-00 11.14.4 Calculation ZZ-48, "Calculation of Inhalation and Ingestion Dose Commitment Factors for the Adult and Child", January, 1988 11.14.5 HPCI 89-02, "Calculation of ODCM Dose Commitment Factors", March, 1989 11.14.6 Deleted

) 11.14.7 HPCI 88-10, "Methodology for Calculating the Response of Gross Nal(TI) Monitors to Liquid Effluent Streams", June, 1988 11.14.8 Calculation ZZ-57, "Dose Factors for Eu-154", January, 1989 11.14.9 Calculation ZZ-78, Rev. 2, "ODCM Gaseous Pathway Dose Factors for Adult Age Group",

July, 1992.

11.14.10 HPCI 88-08, "Performance Testing of the Environment TLD System at Callaway Plant", August, 1989.

11.14.11 - Calculation ZZ-250, Rev. 0, "ODCM Gaseous Pathway Dose Factors for Child Age Group and Ground Plane Dose Factors", September, 1992.

11.14.12 UOTH 83-58, "Documentation-of ODCM Dose Factors and Parameters", February, 1983.

11.14.13 Calculation HPCI 95-004 (Rev. 0), "Calculation of Liquid Effluent Dose Commitment factors (Ajd for the Adult Age Group", June, 1996.

11.15 U. S. Nuclear Regulatory Commission, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2919,

- September 1982, Washington, D. C. 20555 11.15.1 Section 4, "Subroutine PURGE", pages 27 and 28 11.16 Regulatory Guide 4.13, "Performance, Testing, and procedural specifications for

-Thermoluminiscence Dosimetry: Environmental Applications "(Revision 1), July 1977;

-USNRC, Washington, D. C. 20555 11.17 TID-7004, "Reactor Shielding Design Manual", Rockwell, Theodore, Ed; March 1956.

11.18 BNWL-236, "ISOSHLD - A computer code for General Purpose Isotope Shielding Analysis",

--Engel, R. C., Greenberg, J., Hendrichson, M. M.; June1966 11.19 - BNWL-236, Supplement 1, "ISOSHLD- II: Code Revision to include calculation of Dose Rate from Shielded Bremstrahlung Sources", Simmons, G. Li,'et al; March 1967 v-n

?A _. IC APA-ZZ-01003 Rev. 013 11.20 BNWL-236, Supplement 2, "A Revised Photon Probability Library for use with ISOSHLD- 111",

Mansius, C. A.; April 1969.

) 11.21 ANSI N13.10-1974, "Specification & Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents"; September, 1974 11.22 Nuclear Regulatory Commission Generic Letter 89-01, "Guidance for the Implementation of Programmatic Controls for RETS in the Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989 11.23 NRC Answers to 10 CFR 20 Implementation Questions 11.23.1 Letter, F. J. Congel to J. F. Schmidt, dated December 9, 1991.

11.23.2 Internal USNRC memo, F. J. Congel to V. L. Miller, et al, dated April 17, 1992.

11.23.3 Letter, F. J. Congel to J. F. Schmidt, dated April 23, 1992.

11.23.4 Letter, F. J. Congel to J. F. Schmidt, dated September 14, 1992.

11.23.5 Letter, F. J. Congel to J. F. Schmidt, dated June 8, 1993.

11.24 USNRC Inspection Report 50483/92002(DRSS) Section 5, page 5.

11.25 HPCI 96-005, "Calculation of Maximhum Background Value for HB-RE-1 8".

11.26 EGG-PHY-9703, "Technical Evaluation Report for the evaluation of ODCM Revision 0 (May, 1990) Callaway Plant, Unit 1", transmitted via letter, Samual J. Collins (USNRC) to D. F.

Schnell (UE), dated July 12, 1996.

11.27 HPCI 99-005, "Calculation of Setpoint for GL-RE-202".

11.28 HPCI 99-001, "Documentation of REMP Procedure Changes".

) 11.29 "Technical Specifications for Callaway Plant Meteorological Data Software" r 01

,? f.

I_

(

a .- -i -

r = I CALLAWAY - SP 16.11 I OFFSITE DOSE CALCUALATION MANUAL

) (ODCM 9.0) 1RAnTOACTTVE, EFFLTUNT CONTPOT.S

16. 11. 1 LIQUID EFFLUENT 16.11.1.1 LIQUID EFFLUENTS CONCENTRATION

- LIMITING CONDITION FOR OPERATION (ODCM 9.3.1)-

The concentration of radioactive-material released in liquid effluents to UNRESTRICTED AREAS-(see Figure 16.11-1) shall be limited to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, for radionuclides or other than dissolved or entrained noble gases. -For dissolved entrained-noble gases, the-concentration shall be limited to 2 x 10-4 microCurie/ml total activity.

APPTTCABTT.TTY: At all times.

ACTTON:

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

b. The provisions of Sections 16.0.-1.3 and 16.0.1.4 are not

) applicable.

1 s 1 1 1 1 1 SUTRVEITT.T.ANCE REQUIREMENTS (ODCM 9.3.2)

Radioactive liquid wastes shall -be sampled and analyzed according to the sampling and analysis program of Table 16.11-1.

The results of the radioactivity analysis shall be used in accordance with the methodology-and parameters in the ODCM to assure that the concentrations at the-point of release are maintained within the limits of Section 16.11.1.1.

16.11-1 Rev. OL-11 5/00

- _ =.

_- I , - . - QF

CALLAWAY - SP

, 1 1 1

BARSES

) This section is provided to ensure that the concentrationto effluents of radioactive materials released in liquid waste in UNRESTRICTED AREAS will be-less than 10 times the concentration This Appendix B. Table 2, Column 2 to 10 CFR 20.1001-20.2402.

of limitation provides additional assurance that the levels AREAS

,radioactive materials in bodies of water in UNRESTRICTED design will result in exposures within: -(1) the Section II.A CFR Part 50, to a MEMBER OF-THE objectives of Appendix I, 10 PUBLIC, and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for dissolved or entrained the noble gases is based upon the-assumption that Xe-135 is was controlling radioisotope ,and its-MPC in air (submersion) the converted to an equivalent-concentration in water using methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials-in of limits liquid waste samples are tabulated in terms of the lower detection (LLD's).

16. 11-2 Rev. OL-11 5/00

CALLAWAY - SP 16.11.1.2 DOSE FROM LIQUID EFFLUENTS -

) -LIMITING CONDITION FOR OPERATION (ODCM 9.4.1)

'The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid-effluents released, from each unit, to UNRESTRICTED AREAS-(see Figure 16.11-1)-shall be limited:

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

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

APPTTCARTT.TTV: At all times.

ACTTON:

a. With the calculated dose from-the release of radioactive materials in liquid effluents exceeding any of the above-limits, prepare and submit-to the Commission-within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions-that have been-taken to reduce the releases and the-proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act.*

b. The provisions of Sections 16.0.1.3 and 16.0.1.4 are not applicable.

The requirements of ACTION a.(1) and (2)'are applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge. In the case of river-sited plants this is 3 miles downstream only.

- 16.11-3 Rev. OL-11 5/00

CALLAWAY - SP 16.11.1.2.1 SURVEILLANCE REQUIREMENTS (ODCM 9.4.2)

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

16.11.1.2.2 BASES This section is provided to-implement the requirements of Sections II.A and IV.A-of Appendix I,^10'-CFR Part 50. The'Limiting Condition for Operation implements the guides set forth in Section II-.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix.I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be-kept-"as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies-that can be potentially 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 Part-141. The dose calculation methodology and parameters in the-ODCM implement the, requirements in Section III.A of' Appendix I which specify that-conformance with the guides-of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The--

equations specified in the'ODCM-for calculating the doses due to-the actual release rates of radioactive materials in liquid effluents are consistent'with--the methodology provided in -

-Regulatory Guide 1.109, "Calculations of Annual Doses to Man-from Routine Releases of Reactor Effluents with 10 CFR Part 50, Appendix I", Revision 1, October-1977 and Regulatory Guide-1.113,-

"Estimating Aquatic and Dispersion of Effluents from accidental and Routine Reactor Releases for the Purpose-of Implementing -

Appendix I", April 1977.

Thefreporting requirements of Action(a) implement the requirements of 10CFR20.2203.

-16.11-4 - Rev. OL-9 5/97

CALLAWAY - SP 16.11.1.3 RADIOACTIVE LIQUID -EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR -OPERATION (ODCM 9.1.1)

The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11-2 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Section

-16.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these

'channels shall be determined-and adjusted in accordance with'the methodology and parameters in'the ODCM.

APPT.TCARTTTTV: At all times.

ACTTON:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than-required by the above,'immediately suspend the release of radioactive

--liquid effluents monitored by the affected-channel, or declare the channel inoperable.'

b. With less than the minimum-number of radioactive-liquid effluent monitoring instrumentation channels OPERABLE," take the-ACTION shown in Table 16.11-2. Restore the-inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive-Effluent Release Report, pursuanit tio-Technical Specification 5.6.3, why this inoperability was-not corrected within the time

) specified. -

c. 'The provisions of Sections 16.0.1.3'and 16.0.1.4 are-not applicable.

16.11.1.3.1 SURVEILLANCE REQUIREMENTS _ _-_-

(ODCM 9.1.2)

-Each radioactive liquid-effluent monitoring-instrumentation channel shall be demonstrated OPERABLE-by performance 'of the

-CHANNEL -CHECK,- SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL I OPERATIONAL TEST at-the frequencies shown in Table 16.11-3.

-16.-11'.1.3.2 'BASES - --

The radioactive-liquid effluent monitoring instrumentation is-provided to monitor-and control, as applicable, the releases of radioactive materials in'liquid effluents-during actual-:or - -

potential releases of liquid effluents.- Th6 Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance-with-the methodology and parameters in the ODCM to ensure that the-alarm/trip will-occur prior__to-exceeding the 16.11-5 -Rev. OL-ll 5/00

S -= -

CALLAWAY - SP 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.

-16.11-6 Rev. OL-12

-11/01

CALLAWAY - SP LIQUID RADWASTE TREATMENT SYSTEM

) 16.11.1.4 LIMITING CONDITION FOR OPERATION (ODCM 9.5.1)

The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity 'when the projected doses-due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see-Figure 16.11-1) would exceed 0.06 mrem to the whole body or I 0.2 mrem to any organ in a 31 day period.

APPT.TCARTT.TTY: At all times.

ACTTON:

I. With radioactive'liquid waste being discharged in excess of the above limits:and the Liquid Radwaste Treatment'-Systems are not being fully utilized, prepare and submit to-the Commission within 30 days a Special Report that includes the following I information:

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

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

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

II. The provisions of Sections 16.0.1.3 and 16.0.1.4-are not applicable.

1r 11 1 A I qTTEPUTV.TT.T.AWCF -REOUIREMENTS (ODCM 9.5.2) 16.11.1.4.1.a a Doses due to liquid releases from-each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

I 16.11-7 -Rev. OL-11 5/00

CALLAWAY - SP

) 16.11.1.4.1.b The installed Liquid Radwaste Treatment'System shall be considered OPERABLE by meeting Sections 16.11.1.1-and 16.11.1.2.

16.11.1.4.2 BASES The OPERABILITY-of the Liquid-Radwaste- Treatment System ensures that this system will be-available for use whenever liquid effluents require-treatment prior to release to the environment.-

The requirement that-the appropriate portions-of this-system be used when specified provides assurance that the releases of radioactive materials in liquid effluents-will be kept-"as low as is reasonably achievable". This section implements the requirements of-10 CFR Part 50.36a, General Design'Criterion 60-of Appendix A to 10-CFR Part-50 and "the design objective given in Section II.D of Appendix I-to 10-CFR'Part 50. The specified limits governingthe use of-appropriate portions of3theLiquid ,

Radwaste Treatment System were specified as a-suitable fraction of the dose design objectives set forth--in'Section-II.A-of Appendix I I, 10 CFR Part 50, for liquid-effluents.

-16.11-8 Rev. OL-12 11/01

CALLAWAY - SP 16.11.1.5 LIQUID HOLDUP TANKS (3/4.11.1.4) LIMITING CONDITION FOR OPERATION

-(3.11.1.4)

The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 150 Curies, excluding-tritium-and dissolved or entrained noble gases:

a. Reactor Makeup Water Storage Tank,

b. Refueling-Water Storage-Tank,

c. Condensate Storage Tank,--and

d. Outside temporary tanks, excluding demineralizer vessels-and the liner being used to solidify radioactive waste.-

APPT.TCILRTTYTTV: At all times.

ACTTON:

a. With the quantity of radioactive material in-any of the above listed tanks exceeding-the above limit, immediately suspend all additions of radioactive material to the tank, within -48 hours reduce the-tank contents to within the limit, and describe the events leading-to this condition in the next Radioactive Effluent-.Release Report, pursuant to Technical Specification 5.6.3.

b. The provisions of Sections 16.0.1.3 and 16.0.1.4-are not applicable.

16.11.1.5.1- SURVEILLANCE-REQUIREMENTS -

(4.11.1.4)

The quantity of radioactive material contained in each of the above listed tanks shall-be determined-to be within'the above limit by-analyzing a representative sample of the-tank's contents at least once per 7-days when radioactive materials are being -

added and within 7 days following any addition of radioactive material to-the tank. -The-provisions of Sections 16;-0.2.2 and-16.0.2.3 are applicable, -however the allowed surveillance interval extension-beyond 25%-shall-not-be exceeded. These tanks-are also covered by Administrative Controls-Section 5.5.12.---

16.11.1.5.2 BASES The-tanks listed above-include all those outdoor radwaste tanks that are not surrounded by liners, dikes,- or walls capable of holding the tank contents _and-that do not have tank overflows and surrounding area drains connected-to the Liquid Radwaste Treatment

-System.

Restricting the quantity of -radioactive material contained in the specified tanks provides-assurance thatin the event of an

- ~ 16.11-9 Rev. OL-ll 5/00

CALLAWAY - SP uncontrolled release of the tanks' contents, the resulting concentrations would be less than the-limits of 10CFR Part 20.1-20.602, Appendix B,-Table II, -Column_2, (redesignated at 56FR23391, May 21, 1991) at the--nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

)

1G.11-10 Rev. OL-9 1- 5/97

j CALLAWAY - SP 16.11.2 CARROUTS EFFIETJFNT 16.11.2.1 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION OF OPERATION (ODCM 9.6.1)

The dose rate due to radioactive materials released-in gaseous effluents from the site to areas at and beyond-the SITE BOUNDARY (see Figure 16.11-2) shall be limited to the following: l

a. For noble-gases: Less than-or equal to 500 mrems/yr to- the whole body and less than-or equal to 3000 mrems/yr to the skin, and

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

APPT.TCARTTTTV: At all times.

ACTTON:

a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to-within the above limit(s).

b. The provisions of Sections 16.0.1.3 and 16.0.1-.4-are-not applicable.

16.11.2.1.1 SURVEILLANCE REQUIREMENTS -

(ODCM 9.6.2) 16.11.2.1.1.a -

The dose rate due to noble gases-in gaseous effluents-shall-be -

determined to be-within the above limits in accordance with the methodology and parameters in the-ODCM.

16.11.2.1.1.b -

The dose rate due to Iodine-131 and 133, tritium and all -

radionuclides-in particulate -form with half-lives greater than 8B

-days in gaseous effluents-shall-be determined to be-within the

-above-limits--in'accordance with the methodology and-parameters in

-16.11-11. Rev. OL-11 5/00

CALLAWAY --SP the ODCM by obtaining representative sample6 and performing analyses in accordance with-the sampling and-analysis program specified in Table 16.11-4.

16.11.2.1.2 BASES This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units =

on the site will be within the annual dose limits of 10OCFR Part 20 to UNRESTRICTED AREAS. The dose'rate-limits are'the doses associated with the concentrations'of 10CFR Part 20.1-20.601, Appendix B, Table II, Column 1. These limits provide reasonable assurance-that radioactive material discharged in gaseous

,effluents will not result in the exposurelof-a-MEMBER'OF THE PUBLIC-in an-UNRESTRICTED AREA, either within-or outside the SITE BOUNDARY, to annual average-concentrations exceeding the dose '

limits specified in 10 CFR Part-20 10 CFR 20.1301.f For MEMBERS OF.

THE PUBLIC who may at times be -within:the-SITE BOUNDARY,,the occupancy of-that MEMBER OF-THE PUBLIC will usually be_

sufficiently low to compensate for any-increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of --

calculations for-such MEMBERS OF THE PUBLIC,-with the-appropriate occupancy factors, shall be given in'the ODCM.- The specified release rate limits restrict,- at all times,'the corresponding gamma and beta dose rates above background to a-MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY'to less than or equal to 500 mrem/year to the whole body or-to less than or equal to'3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose-rate above background to a child via the inhalation'pathway to less-than or equal to 1500 mrems/year. -

The required detection capabilities for radioactive materials in gaseous waste-samples are tabulated in'terms of-the lower'limits of detection (LLD's).

The requirement for-additional sampling of the Unit Vent following a reactor power transient is provided to ensure that-the licensee -

is aware of and properly accounts for any-increases in the release-of gaseous effluents due-to-spiking-whichmay occur as a result of the-power transient.- Monitoring the-Unit Vent for increased noble gas activity-is appropriate-because it'is-the release point for -

any increased activity'which may result from'the power transient.

16.11-12 - - Rev. OL-9 5/97

CALLAWAY - SP

) Since the escape rate coefficients for the noble gas nuclides is equal to or greater than the escape rate coefficient for-iodine 4

and the particulate nuclides " , it is reasonable to assume that the RCS spiking behavior of. the noble-gas nuclides is similar to that of-the particulate and iodine nuclides.- Considering the effects of iodine and particulate partitioning, plateout on plant and ventilation system surfaces, and 'the 99!k efficiency of the Unit Vent HEPA filters and charcoal absorbers, it is reasonable to assume that the relative concentrations of the noble gas nuclides will be much greater than those of the iodine and particulate nuclides. Therefore, an increase in the iodine and particulate RCS activity is-not an appropriate indicator of-an increase in the Unit Vent activity,-and it' is appropriate to monitor the Unit-Vent effluent activity as opposed to the RCS activity as an indicator of-the need to perform post-transient sampling. In addition,-it is appropriate to monitor the noble-gas-activity due to-its relatively greater concentration in the-Unit Vent.

)

Cohen, Paul, Water Coolant Technology' of Power Reactois, Table 5.19, page 198. American Nuclear Society.

1980.

5 NUREG-0772, "Technical Bases for Estimating Fiss'ion Product Behavior During LVWR Accidents", Silberberg, 4, editor, USNRC; Figure 4.3, page 4.22. June, 198e1. - -

16.11-13 -- Rev. OL-9

.- 5/97

CALLAWAY-- SP 16.11.2.2 DOSE-- NOBLE GASES LIMITING CONDITION OF OPERATION (ODCM 9.7.1)

The air dose due to noble gases released-in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-2) shall be limited to the following:

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

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

APPT.TCARTT.TTV: At all times.

ACTITN:

a. With the calculated air dose'from radioactive-noble gases in gaseous'effluents exceeding-any of the above limits, prepare and submit-to-the Commission within.30 days a Special Report -

that-identifies the cause(s) for exceeding the limit(s) and defines the corrective actions--that have been taken-to reduce the releases-and the proposed corrective actions to be taken to assure that subsequent'releases will be in compliance with the '

above limits.

b. The provisions of Sections 16-.0.1.3 and 16.0.1.4 are not-applicable.

16.11.2.2.1 'SURVEILLANCE REQUIREMENTS (ODCM 9.7.2)

Cumulative dose contributions for the current calendar'quarter and currentcalendar yearfor noble gases shall be determined in-accordance with the methodology-and parameters in the ODCM-at least once per-31 days.

16.11-14 Rev. OL-11 5/00

CALLAWAY - SP

)

16.11.2.2.2 BASES This section is provided to implement the requirements of Sections II.B, III.A, and IV.A of-Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation implements the guides set forth in Section'II.B of Appendix I.- The-ACTION statements provide the required operating flexibility-and at the same time implement the guides set forth in Section -IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low-as is reasonably achievable".

The Surveillance Requirements implement the requirements in of Section III.A of Appendix I that conformance with the guides Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a-MEMBER OF THE PUBLIC through appropriate pathways in unlikely to-be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses-due to the actual release-rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109; "Calculation-of Annual Doses to Man from Routine Releases on Reactor Effluents for the Purpose 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. The ODCM-equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmosphericconditions.

The reporting requirements of -Action(a)-implement the requirements of 10CFR20.2203.

16.11-15 Rev. OL-9 5/97

- CALLAWAY - SP 16.11.2.3 DOSE>- IODINE-131 AND 133, TRITIUM, AND RADIOACTIVE MATERIAL IN-PARTICULATE FORM

) 'LIMITING CONDITION-OF OPERATION (ODCM 9.8.1)

The dose to a MEMBER OF-THE-PUBLIC from Iodine-131 and 133, tritium, and all radionuclides- in-particulate form with half-lives' greater than 8-days in gaseous effluents released,' from each unit, to areas at and beyond the SITEBOUNDARY (see Figure 16.11-2) shall be limited to the following:

a. During any calendar quarter: Less than-or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less-than or equal to 15 mrems to any organ.

APPT.TcARTT-TTV: At all times.

ACTTON-

a. With the calculated dose fromthe'release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days,- in gaseous effluents-exceeding any of the above limits, prepare-and submit-to-the-Commission--

within 30 days a Special Report that identifies the cause(s)l for exceeding the limits and defines the-corrective actions that have been taken to reduce the'releases and the proposed corrective actions to be taken to assure that subsequent releases will be in complianceiwith-the above limits.

b. The provisions of Sections 16.0.1.3 and 16.0.1.4 are not applicable.

16.11.2.3.1- SURVEILLANCE REQUIREMENTS (ODCM 9.8.2)

Cumulative dose contributions for the current-calendar quarter and current calendar year for'Iodine-131 and 133, tritium,: and

- radionuclides in particulate form -with-half-lives greater than 8

-days shall be determined in accordance with the-methodology and parameters -in the--ODCM at least once-per 31 days. '

16.11-16 - - Rev. OL-11 5/00

-CALLAWAY --SP 16.11.2.3.2 BASES This-section-is provided to -implement the requirements of Sections II.C,.-III.A, and IV.A-of Appendix-I, 10-CFR Part 50. The Limiting Conditions-for Operation are-the guides-set forth in Section II.-C of Appendix I. The ACTION statements provide the required operating flexibility and-at the same time implement the guides set forth in Section IV.A'of Appendix I to-assure that-the release

-of radioactive material in gaseous-effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The ODCM calculational methods specifiedlin the Surveillance Requirements

-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 a MEMBER-OF THE PUBLIC through appropriate pathways is-unlikely-to be substantially underestimated. The ODCM calculational methodology and-parameters for calculating the doses due to the actual release rates of-the'subject-materials are-consistent-with the methodology provided in Regulatory Guide, 1.109, "Calculation of Annual-Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 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 controls-for Iodine-131-, and 133, tritium, and radionuclides-in particulate form with half-lives greater than 8 days are dependent upon the, existing radionuclide pathways to man, in the areas at

--and beyond the SITE BOUNDARY. 'The pathways-that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, -(2) deposition of -

radionuclides onto green leafy -vegetation with-subsequent consumption by man,=(3) deposition'of radionuclides-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.

-The reporting-requirements of Action(a) -implement the -requirements of 10CFR20.2203.

-16.11-17 - - - Rev. OL-11 5/00

OCT-03-2002 -MNR- U- CbRp. WC.- ; P.01 r ,- S CALLAWAY- SP 16.11.2.4 RADIOACTIVE GASEOUS EFFLUENT-MONITORING (314.3.3.10) INSTRUMENTATION-LIMITING CONDITION FOR OPERATION (ODCM 9.2.1)-

The radioactive gaseous effluent monitoring instrumentation channels shown-in Table 16.11-5 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of-Section 16.11.2.1 are not-exceeded. -The Alarm/Trip Setpoints-of these channels meeting-Section-16.11.2.1shall be determined and adjusted in accordance with the-methodology and parameters-in the ODCH.

APPT.T2ICART.TV: As -shown in Table-16.11-5.

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint--less conservative than re ired by tha-above, immediatelyfU- Ai>ww

-D declare the channel noperabe. -

p, With less than the-minimum number of radioactive-gaseous

-effluent noni;toring instrumentation qhannels OPERABLE,ta e the ACTION-shown in Table-16.11-5. -Restore the inoperably instrumentation to-OPERABLE status within-the time specified-in-the ACTIOIf, or exilain in the next Radioaqtive Effluent

- Release Report,,-purs ant'to Technical Speciftcdition 5.6.3 -why X this inoperability was not corkeeted-.Within the timei specified. ' - - . a:

c. The-provisions of Sections:16.0.1.3 and 16.0.1.4 are not' applicable..

16.11.2.4.1 SURVEXLLANCE REQUIREMENTS (ODCN 9.2.2) --- - ' -

a. Each radioactive gaseous effluent monitoring instrumentation l C9o channel shall-b4 demonstrated OPERABLE by performance of the CHAN.NELCHECK, -OURCE CHECK,-CHANNEL CALIBRATION and CHANNEL -

OPERATIONAL-TESW at the frequencies shown -inTable 16.11-6.

Pre4 o 5 tr IqVt(--2a c

$c yingCa co ,eG-R-33 L va seat Tgi /r. Cesstha en f/

16.-11.2-.4.2 BASES -

The radioactive gaseous effluent monitoring 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 instru-ments:shaellbe-calculated and'adjusted-in -

accordance with the-methodology and parameters in the ODCM to ensure that the alarm/trip will-occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation-is consistent with the-requirements -of -General 16.11-18 - Rev. OL-11

-5/00-

- OCT-03-2002' 16:04 O-AEREN UE CORP. UtC., SER P. 02 CALLAWAY - SP

) -Design Criteria 60, 63, and 64 of Appendix Ato 10 CFR Part 50.

used to show The-sensitivity-of any-noble gas activity-monitor compliance-cwith the-gaseous effluent release-requirements of Section 16.11.2.1 shall be such-that concentrations as low as 1 x

- rgWANOI-03 0 10' ICi/cc are measurable.

Ci le e

)

c F-

~~ 2,-007?

)

I@

I.

16.11-19 Rev. OL-l1

'5/00

INSERT G 1 01'

)

The monitors GT-RE-22 and GT-RE-33 are only required for automatic containment purge isolation in MODES 1 through 4. For plant conditions during CORE ALTERATIONS and during movement of irradiated fuel within containment, the function of the monitors is to alarm only and the trip signals for automatic actuation-of CPS maybe bypassed. Based on the guidance provided in Regulatory Guide 1.97 concerning monitoring requirements for containment or purge effluent, the monitors GT-RE-22 and GT-RE-33 do not need to meet the single failure criterion for an Alarm function only during CORE ALTERATIONS or during movement of irradiated fuel in containment: One instrumentation channel at a minimum is required for the alarm only'function during refueling activities.

)

CALLAWAY - SP

) INTENTIONALLY BLANK I

)

-16.11-20 Rev. OL-l1 5/00

CALLAWAY - SP 16.11.2.5 GASEOUS RADWASTE TREATMENT SYSTEM

) LIMITING CONDITION OF OPERATION (ODCM 9.9.1)

The VENTILATION EXHAUST-TREATMENT-SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the -

projected doses in 31 days due to gaseous effluent-releases, from each unit,- to areas at and beyond-the-SITE BOUNDARY (see Figure 16.11-2) 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.

APPT.TCARTT.TTV: At all times ACTTON I. With radioactive gaseous-waste being discharged without treatment-and in excess of the above limits, prepare and -

submit to the Commission within 30 days a Special Report that-includes the following information:

1) Identification of-any -inoperable equipment or~subsystems, and the reason for the inoperability, -

2) Action(s) taken to restore-the inoperable equipment to OPERABLE status, and

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

II. The provision of Sections 16.0.1.3 and 16.0.1.4-are not applicable.

16.-11-21 Rev. OL-l1

- 5/00

CALLAWAY - SP

) 16.11.2.5.1 SURVEILLANCE REQUIREMENTS (ODCM 9.9.2)

16. 11. 2.5; 1.a Doses due-to gaseous releases-from-each-unit to areas at and

-beyond the SITE BOUNDARY-shall be proj-ectedat least once per 31 days in accordance with the methodology and parameters in the ODCM.

16.11.2.5.1.b The installed VENTILATION EXHAUST-TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEMS shall be considered OPERABLE by meeting Sections 16.11.2.1 and 16.11.2.2 or 16.11.2.3.

16.11.2.5.2 BASES The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST-TREATMENT SYSTEM ensures that the system will be available for use whenever-gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems-be used, when specified,--provides -

reasonable assurance that the releases of radioactive materials in gaseous effluents will. be kept "as low as is reasonably achievable". This control implements the requirements of 10 CFR

,) Part 50.36a, General Design-Criterion 60 of Appendix A to 10 CFR -

Part 50, and the design objectives given in Section-II.D of Appendix I to 10 CFR Part 50. §The specified limits governingxthe use of appropriate portions of the systems were specified as a-suitable fraction of the-dose design objectives set forth in Sections II.B and II.C of Appendix I,-10 CFR Part 50, for gaseous effluents.

Ir 16.11-22 Rev. OL-9 5/97 I -

i

CALLAWAY - SP 16.11.-2.6 EXPLOSIVE GAS MIXTURE

'LIMITING CONDITION FOR OPERATION -

The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited-to less than or equal to 3% by volume whenever-the hydrogen concentration exceeds 4%-by volume.

APPT.TCARTT.TTV: At all times.

ACTTDN:

a. With the concentration of'oxygen in the WASTE GAS HOLDUP-SYSTEM greater than 3% by-volume but less than-or equal-to 4%

by volume, reduce the-oxygen concentration to the above-limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen -

concentration greater than 4% by volume, immediately suspend all additions of-waste gases to the-system-and reduce the concentration'on oxygen to less than or equal to'4% by volume, then take ACTION a. above. ----

c. The-provisions of Sections 16.0.1-.3 and 16.0.1.4 are not applicable.

16.11.2.6.1 SURVEILLANCE REQUIREMENTS . -

'The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall-be determined to be within the-above limits-by continuously monitoring the waste gases-in-the WASTE GAS HOLDUP SYSTEM with the hydrogen-and-oxygen monitors required-OPERABLE by -

Section-16.11.2.7. The'provisions of Sections 16.0.2;2 and 16.0.2.3 are applicable, however'-the allowed surveillance interval extension-beyond 25% shall not be exceeded. This system is also'

'covered by Administrative'Controls'Section 5.5.12.

16.11.2.6.2 BASES

'This specification is provided to ensure that the concentration of potentially-explosive gas mixtures contained in the WASTE GAS -

HOLDUP SYSTEM'is'maintained below'the'flammabilit'y limits of hydrogen and oxygen. Automatic-control features-are included in the system to prevent the hydrogen and oxygen concentrations from

'reaching these flammability-limits. These automatic' c-ontrol features include-isolation of the source of hydrogen and/or - -

oxygen. Maintaining the-'concentration of hydrogen and oxygen below their flammability limits provides-assurance that the releasesof-radioactive materials will-be controlled in conformance-with the requirements of'General.Design Criterion 60 of Appendix A to 10 CFR Part 50. -

16.11-23 Rev. OL-11

-- 5/00

CALLAWAY - SP

) 16.11.2.7 WASTE GAS HOLDUP SYSTEM RECOMBINER EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION outlet oxygen At least-one hydrogen and both the inlet and each WASTE .GAS explosive gas-monitoring instrument-channels for with their Alarm/Trip HOLDUP SYSTEM recombiner shall be OPERABLE "FEED H2 4%/FEED-02 3%" and Setpoints (with-the exception of-the of set to ensure that the limits "FEED H2 4%/FEED-02 4%" alarms)

Section 16.11.2.6 are not exceeded.

APPTTCA1RTT.TTY: During WASTE GAS-HOLDUP SYSTEM operation.-

ACTTON:

operation of

a. With an outlet oxygen monitor channel inoperable, provided grab samples are taken and the system may continue analyzed at least once-per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

the inlet

b. With both oxygen or both-hydrogen channels or-both channels for one recombiner oxygen and inlet hydrogen monitor supply to the recombiner. Addition inoperable,-suspend oxygen system may continue provided grab samples of waste gas-to-the hours during are taken and analyzed at least; 1) once per 4 mechanical or chemical degassing-in-preparation for plant shutdown and 2) once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations.

operation of the--

c. With the inlet oxygen analyzer-inoperable, the -inlet Hydrogen is maintained

) system may continue provided If inilet Hydrogen is greater thans4%, suspend less than 4%.-

Addition of waste gas to the system oxygen to the recombiner.

and analyzed at may continue provided grab samples-are taken mechanical or chemical least; 1) once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during and 2) degassing-operations in preparation for plant shutdown once per 24 hours during other operations.

not The provisions of Sections 16.0.1.3 and-16.0.1.4 are d.

applicable.

SURVEILLANCE REQUIREMENTS -

16.11.22.7.1 applicable, The provisions of Sections 16.0.2.2 and 16.0.2.3-are interval extension beyond 25%

however the allowedsurveillance This system is also covered by

-shall-not be exceeded.

Administrative Controls Section 5.5.12.-

monitoring

-Each-waste gas-holdup system recombiner explosive-gas OPERABLE by_-

instrumentation channel shall be-demonstrated performance of: - -

-a. A CHANNEL CHECK at least once per 24-hours, -

days, and

b. An CHANNEL OPERATIONAL TEST at least once per 92 with the use

c. -A CHANNEL CALIBRATION at least-once-per 92 days of standard gas samples containing a nominal-

-16.11-24 - - Rev.-OL-11 5/00

CALLAWAY -- SP

1) One volume percent hydrogen, 'balance nitrogen and four volume-percent hydrogen, balance nitrogen for the hydrogen-monitor, and

2) One-volume-percent oxygen,' balance nitrogen, and four

- volume percent oxygen, balance nitrogen for the inlet oxygen monitor,--and-

3) 10-ppm by volume oxygen, balance nitrogen and 80 ppm by volume oxygen, balance-nitrogen for the outlet oxygen monitor.

16.11.2.7.2 BASES Mechanical 'degassing operation' is defined as the transfer of gas from the Volume Control Tank (VCT) to-the Waste Gas Holdup System when establishing a-nitrogen blanket on the VCT in preparation for

-a plant~shutdown. Chemical 'degassing~operation' is the process-of adding hydrogen peroxide to the RCS after the VCT hydrogen blanket has been replaced with'nitrogen-per the Mechanical degassification-process and theRCS~hasbeen reduced to less than 180 0 F.- Both Mechanical and Chemical degassification may lead to

-an explosive gas mixture-in the Waste Gas Holdup System, thus requiring the more restrictive 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sampling. Other operations require 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sampling. ' - ' -

The "FEEDH2 4%/FEED 02 3%" AND-"FEED H2 4%/FEED 02 4%" alarms are not required to be OPERABLE.- These alarms result from the- --

combination of inlet Hydrogen-and inlet- Oxygen-analyzer outputs while the FSAR only addresses OPERABILITY of each separate analyzer.-Only the individual alarms and control functions associated-with-each analyzer are to be used-to determine its operability. These alarms-and control functions-are sufficient to ensure that the requirements'of Section 16.-11.'2.6 are not -

exceeded.

-16.'11-24a Rev. OL-11 5/00

CALLAWAY- SP 16.11.2.8 GAS STORAGE TANKS

) LIMITING CONDITION FOR OPERATION The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 2.5 x 10C Curies of noble gases (considered as Xe-133 equivalent).

APPTTCARTTTTY: At all times.

ACTTON:

a. With the quantity of radioactive material in any gas storage tank exceeding-the above limit,--immediately suspend all additions of radioactive'material to the tank and, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3.

b. The provisions of Sections 16.0.1.3 and 16.0.1.4 are not applicable.

16.11.2.8.1 SURVEILLANCE REQUIREMENTS

) The provisions of Sections 16.0.2.2 and 16.0.2.3 are applicable, however the allowed surveillance interval extension beyond 25%

shall not be exceeded. This system is also covered by Administrative Controls Section 5.5.12.

The quantity of radioactive material contained in each gas storage tank shall be determined to-be within the above limit at least once per 18 months.

16.11.2.8.2 BASES The tanks included in this specification are those tanks for which the quantity of radioactivity'contained is not limited directly or indirectly by another Technical Specification. Restricting-the quantity of radioactivity contained in each-gas storage tank provides assurance that in the event of an-uncontrolled release of -

the tank's contents, the resulting whole body exposure-to a MEMBER OF THE PUBLIC at the nearest-SITE BOUNDARY will-not exceed 0.5 rem. This is consistent with-Standard Review-Plan 11.3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Due to a Waste-Gas System Leak or Failure," in NUREG-0800, July 1981.

16.11-25 Rev. OL-12 11/01

CALLAWAY - SP 16.11.3 mOT6T. DOSE 16.11.3.1 TOTAL DOSE LIMITING CONDITION FOR OPERATION (ODCM 9.10.1)

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

APPT.TrARTT.TTV: At all times.

ACTTON:

a. With the calculated doses from the release of radioactive materials in gaseous effluents exceeding twice the limits of Section 16.11.2.2a, 16.11.2.2b, 16.1l.2.3a, or 16.11.2.3b, calculations should be made including-direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 16.11.3.1-have been exceeded. If such is the case, prepare and submit to the Commission within 30 days a Special Report that defines thel corrective action to be taken to reduce subsequent release to prevent recurrence of exceeding the above limits-and includes the schedule for achieving conformance with-the above limits.

) This Special Report, as defined in 10-CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the-release(s) covered by this report. It shall also-describe levels of radiation and concentrations of radioactive materialinvolved,- and the-cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not-already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of-40 CFR Part 190.

Submittal of the report is considered a-timely request, and a variance is granted until staff action on the request is complete.

16.11-26 Rev. OL-l1 5/00

CALLAWAY - SP

b. The provisions of Technical Specifications 16.0.1.3 and 16.0.1.4 are not applicable.

16.11.3.1.1 SURVEILLANCE REQUIREMENTS (ODCM 9.10.2) 16.11.3.1.1.a Cumulative dose contributions from gaseous effluents shall be determined in accordance with Sections 16.11.2.2.1, and 16.11.2.3.1, and in accordance with the methodology and parameters in the ODCM.

16.11.3.1.1.b Cumulative dose contributions from direct radiation from the units and from radwaste storage-tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirements is applicable only-under conditions set forth in ACTION a. of Section 16.11.3.1.

16.11.3.1.2 BASES This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301.

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

For the purposes of the Special Report, it may be assumed that-the dose commitment to the MEMBER OF-THE PUBLIC from other uranium fuel cycle sources-is negligible,-with the-exception that dose contributions from other nuclear fuel cycle facilities at the same 16.11-27 e Rev. OL-9 5/97

CALLAWAY - SP site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR 20.2203, is considered to be a timely-request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 16.11.1.1 and 16.11.2.1. An individual is not considered a MEMBER OF THE-PUBLIC during any period in which he/she is-engaged in carrying out any operation that is part of the-nuclear fuel cycle.

There are three defined effluent release categories: 1.) Releases directly to the hydrosphere; 2.) noble gas releases to the atmosphere; 3.) radioiodine and particulate, releases to the atmosphere. For each effluent release category, it is assumed in the dose calculations that an individual with the highest dose potential is the receptor. In general, the adult is considered to be the critical age group for liquid effluents, and the -child age group is the most limiting for radioiodine-and particulates in gaseous effluents. Thus, it is 'highly unlikely or impossible for the same individual to simultaneouslyzreceive the highest-dose via all three effluent categories. For'most reactor sites, it is also unlikely that all different potential dose pathways would contribute to the dose to a-single real individual. Since it is difficult or impossible to-continually determine actual food use

) patterns and critical age group, for calculational purposes, assumptions are made which tend to maximize-doses. Any refinement in the assumptions would have the effect of reducing the-estimated dose. For radionuclides released to the hydrosphere, the degree of overestimation in most situations is such that no individual will receive a significant dose. These conservative assumptions generally result in an overestimation of dose by one or two orders of magnitude. Since thesebassumptions are reflected-'in the Radiological Effluent Controls -limiting radionuclide-releases to design objective'individual'doses,-no offsite individual is likely to actually receive a significant dose. Since the doses from liquid releases are very conservatively evaluated, there is reasonable assurance that no real--individual will receive a significant dose from radioactive'liquid release pathway.

Therefore, only doses to individuals via airborne pathways and 16.11-28 Rev. OL-9 5/97

CALLAWAY - SP dose resulting from direct radiation need to b? considered in determining potential compliance to 40 CFR 190 The reporting requirements of Action(a) implement the requirements of 10CFR20.2203.

)

l NUREG-0543, "Methods for Demonstrating LWR compliance Nvith the EPA Uranium Fuel Cycle Standard (40 CFR 190)", Congel, F. J., Office of Nuclear Reactor Regulation USNRC. January, 1980. pp. 5-8. -

16. 11--2 Rev. OL59

- 5/97

CALLAWAY - SP 16.11.4 RADTOTO9TVAT. ENVTRONMNTT. MONTTORTNG(

16.11.4.1 MONITORING PROGRAM LIMITING CONDITION OF OPERATION (ODCM 9.11.1)

The Radiological Environmental Monitoring Program shall be conducted as specified in Table 16.11-7.

APPT.TCARTT.TTV: At all times.

ACTTON:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 16.11-7, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting-the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting'levels of Table 16.11-8 when averaged over any calendar quarter, prepare and submit-to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so-that the potential annual dose* to a MEMBER OF THE PUBLIC is less-than the calendar year limits-of Sections 16.11.1.2, 16.1l.2.2, or 16.11.2.3. When more than one of the radionuclides in -Table 16.11-8 are detected in the-sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + 1.0 reporting level (1) reporting (2)

When radionuclides other-than those in Table 16.11-8 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 from all radionuclides is equal to or greater The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

- 16.11-30 Rev. OL-11 5/00

CALLAWAY - SP than-the calendar year limits of Sections316.11.1.2, 16.11.2.2

) or 16.11.2.3. 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, required by Technical Specification 5.6.2.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 16.11-7,

-identify specific locations for obtaining replacement samples

-and add them within 30 days to the Radiological Environmental Monitoring Program". The specific locations from which samples were unavailable may then- be deleted from the monitoring program. In the next Annual!Radiological Environmental Operating Report include the-revised figure(s) and-tables reflecting the new sample location(s) with-supporting information identifying the cause of the unavailability of samples and-justifying the selection of new location(s) for obtaining samples.

d. When LLDs specified in Table 16.11-9 are unachievable due to uncontrollable circumstances,-(such as background fluctuations, unavailable-small sample sizes, the presence-of interfering nuclides, etc.) the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

) e. The provisions of Sections 16.0.1.3 and 16.0.1.4 are not applicable.

16.11.4.1.1 SURVEILLANCE REQUIREMENTS (ODCM 9.11.2)

The radiological environmental monitoring samples-shall be collected pursuant to Table 16.11-7 -and shall be analyzed pursuant to the requirements of Table 16.11-7 and the detection capabilities required by Table 16.11-9.

Excluding short term or temporary unavailability.

16.11-31 Rev. OL-12 11/01

CALLAWAY - SP 16.11.4.1.2 BASES The Radiological Environmental Monitoring Program required by this REC provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to; the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix-I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations 6ftradioactive materials and levels-of radiation are not higher than expected on the basis of-the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1,-November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample -

analyses are tabulated in terms of the lower limits of detection (LLD's). The LLD's required by Table 16.11-9 are considered.

optimum for routine environmental measurements in industrial laboratories.

)

16.11 Rev. OL-9 5/97

CALiLAWAY - SP 16.11.4.2 LAND USE CENSUS'-

) LIMITING CONDITION OF OPERATION (ODCM 9.12.1)

A Land Use Census shall be conducted and shall identify within a distance'of 8 km (5 miles) the location in each of the 16 meteorological sectors of the-nearest milk animal, the nearest residence and the nearest garden* of greater than 50m 2 (500 ft2 )

producing broad leaf vegetation. The Land Use Census shall identify water intakes constructed within 10 river-miles' downstream of the plant discharge point.

APPTTCARTT.TTV: At all times.

ACTTNlL:

a. With a Land Use Census-identifying a location(s) that yields a calculated dose or dose commitment greater than the values-currently being calculated-by Section 16.11.2.3.1, identify the new location(s) in the next Radioactive Effluent Release Report, 'pursuant to Technical-Specification 5.6.3.

b. With a Land Use Census identifying a-location(s) that yields a calculated dose or dose-commitment (via the same-exposure -

pathway) 20% greater'than at a location from which samples are currently being obtained in accordance with Section 16.11.4.1, add the new locationts) within 30 days to the Radiological

) Environmental Monitoring Program except for vegetation samples which shall-be added to the-program before the -next growing:

season. 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-the next Annual Radiological Environmental Operating-Report'include the revised figure(s) and tables reflecting the new sample location(s) with information supporting the-change in sample-location.

c. With a Land Use Census identifying-a water intake within 10 river miles downstream of-the plant discharge-point, implement the appropriate waterborne or ingestion sampling required by Table 16.11-7.

d. The provisions of-Sections 16.0.1.3 and 16.0.1.4 are-not applicable.

Broad leaf vegetation sampling of at least three different kinds of vegetation maybe performed at the SITE BOUNDARY in each to two different direction sectors with the highest predicted D/Q's in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 9.1 1-A, Part 4.c shall be followed, including analysis of control samples.

16.11-33 Rev. OL-12 11/01

I CALLAWAY - SP A) 16.11.4.2.1 SURVEILLANCE REQUIREMENTS (ODCM 9.12.2)

The Land Use Census shall be conducted during the growing season at least once per 12 months using that information which will

~provide the best results, such as, but not limited to, door-to-door survey, aerial -survey, or by consulting local agriculture authorities and/or residents. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant-to Technical Specification 5.6.2.

I 16.11.4.2.2 BASES This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY-are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if-required by the results of this -

census. Information that will provide the best results, such as door-to-door survey, aerial-survey, 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 50im2n 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 vegetables assumed in-Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% 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/in2 .

16.11-34 Rev. OL-11 5/00

CALLAWAY - SP N

16.11.4.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION OF OPERATION -

(ODCM 9.13.1)

Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program-that has been approved by the USNRC.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a-recurrence tothe Commission in the Annual Radiological'Environmental Operating Report pursuant to Technical Specification 5.6.2.

b. The provisions of Sections 16.0.1.3 and 16.0.1.4 are not applicable.

16.11.4.3.1 SURVEILLANCE REQUIREMENTS (ODCM 9.13.2)

The Interlaboratory Comparison Program shall be described in the plant procedures. A summary of the results obtained as part of the above required Interlaboratory Comparison Program-shall be included in the Annual Radiological Environmental Operating Report

) pursuant to Technical Specification 5.6.2; -I I

16._11.-4.3.12 BASES The requirement for participation in'an approved Interlaboratory Comparison Program is provided to'ensure that independent'checks on the precision and accuracy of the measurements of-radioactive material in environmental'sample matrices are performed as part -of the quality assurance program for environmental monitoring in-order to demonstrate that the results are valid for the purpose-of Section IV.B.2 of Appendix I to.10 CFR Part 50.

16. 11-35 Rev. OL-l1 5/00

CALLAWAY - SP 16.11.5 ADMINISTRATIVE CONTROLS 16.11.5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (ODCM 7.1)

Routine Annual Radiological Environmental-Operating Report covering the operation of the unit'during the previous calendar year shall be submitted prior to May 1 of each year.

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

The reports shall include the results of-Land Use Census required by Section 16.11.4.2. It shall-also include-a listing of new locations for environmental monitoring identified by the Land Use Census pursuant to Section 16.11-.4.2.

The Annual Radiological Enivironmental'Operating Report' shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to Section 16.11.4.1, as well as -

summarized tabulated results of these analyses .and measurements in the format of the table in the-Radiological Assessment Branch '

Technical Position, Revision 1,-November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The.missing-data-shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a-summary-'

description of the radiological'environmental'monitoring'program; at least two legible maps covering all sampling-'locations keyed to a table giving distances and directions from the centerline of one reactor; the results of-licensee participation in the Interlaboratory Comparison Program and the corrective action being taken if the specified program is not being performed as required by Section '16.11.4.3; -reasons for.not conducting'the Radiological Environmental Monitoring Program as required by-Section '16.11.4.1 and discussion'of all'deviations from'the sampling schedule of-One map shall covper stations near the SITE BOUNDARY; a second shall include the more distant stations.

16.11-36 Rev. OL-9 5/97

CALLAWAY - SP Table 16.11-7, discussion of environmental sample measurements that exceed the reporting levels of-Table 16.11-8, but are not the result of the plant-effluents, pursuant to Section 16.11.4.1; and discussion of all analyses in which the LLD required by Table 16.11-9 was not achievable. ^

I h 1 1 .5. -1.-1 BASES The reporting requirement for the Annual Radiological Environmental-Operating Report is provided to ensure compliance with Technical Specification 5.6.-2. This requirement-was I relocated from the Offsite Dose-Calculation Manual to FSAR Chapter 16.

)

16. 11-37 Rev. OL-1l 5/00

CALLAWAY - SP 16.11.5.2 RADIOACTIVE EFFLUENT RELEASE REPORT (ODCM 7.2)

Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous-calendar year shall be submitted prior to May 1 of each year.

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

The Radioactive Effluent Release Report shall include-an annual summary of hourly meteorological'data collected over the previous calender year. This annualssummary may be either in the-form-of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability*

This report shall also include an-assessment of the radiation doses due to the radioactive-liquid and gaseous effluents released from the unit during the previous calendar year. This report shall also include an assessment of-the radiation doses-from radioactive liquid and gaseous effluents to MEMBERS OF-THE'PUBLIC due to their activities inside-the SITE BOUNDARY (Figures 16.11-1 and 16.11-2)- during the report period using historical average atmospheric conditions. 'All assumptions used in-making these assessments, i.e., specific activity, exposure time and location, shall be included in these-reports.- The meteorological conditions concurrentwith the time of: release--of radioactive-materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. Assessment of radiation-doses shall be performed in accordance with'the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent-Release Report shall include-an assessment of radiation doses to the most likely exposed-MEMBER OF THE PUBLIC from reactor-releases and other nearby uranium fuel In lieu of submission with the Annual Radioactive Effluent Release Report, Union Electric has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

- 16.11-38 Rev. OL-11 5/00

CALLAWAY - SP cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."- Doses to the MEMBER OF-THE PUBLIC shall be calculated using the methodology and parameters of the ODCM.

The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the- site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Report shall include a summary description of any major changes made during the year-to any Liquid or Gaseous Treatment Systems,-pursuant to Offsite Dose Calculation Manual. It shall also include a listing of new -

locations for dose calculations identified by the Land Use Census pursuant to Section 16.11.4;2.

Reporting requirements for changes to Solid Waste Treatment Systems are addressed in APA-ZZ-01011, PROCESS CONTROL'PROGRAM (PCP).

The Radioactive Effluent Release Report shall also include the following information: An explanation-as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified, and a description-of the events leading the liquid holdup tanks'or gas storage tanks exceeding the limits of Section 16.-11.1.5 or 16.11.2'.8.

The Radioactive Effluent Release Report shall include as-.part of or submitted concurrent with, a complete and legible copy of all revisions of the'ODCM that occurred during the-year pursuant of Technical Specification 5.5.1. l Solid Waste reporting is addressed in APA-ZZ-01011, PROCESS CONTROL PROGRAM (PCP).

16.11.5.2.1 - BASES The reporting requirement for the Radioactive'-Effluent Release Report is provided to-ensure compliance with Technical Specification 5.6.3. -This requirement-was relocated from the Offsite'Dose Calculation Manual to FSAR Chapter 16.

16.11-39 Rev. OL-11 5/00

CALLAWAY - SP TTThT.r!7IM1. I -1 RM)>TOLE'lTVF! TT01JTTD UARg1:! RAMPDTING AN ANAL.YSTS PROMRAM

1. Discharge-Monitor Tanks (Batch Release) (2)

SAMPLING MINIMUM TYPE OF -LLD (1)

FREQUENCY(7) ANALYSIS ACTIVITY (ACi/ml) I FREQUENCY ANALYSIS ..

Prior to Prior to Principal Gamma - SE-7 Each Batch Each Batch- Emitters (3)

I-131 1E-6 I Dissolved and 1E-5 Entrained Gases (Gamma Emitters)

H-3 1E-5 Monthly Gross Alpha 1E-7 Composite (4)

Quarterly Sr-89, Sr-90 SE-8 Composite Fe-55 1E-6 (4)

Np-237 SE-9 Pu-238 5E-9 Pu-239/240 5E-9

) Pu-241 5E-7 5E-9 Am-241 Cm-242 5E-9

- Cm-243/244 -5E-9

2. Steam-Generator Blowdown (Contin ous Release) (5)

-SAMPLING MINIMUM TYPE OF LLD (1)

FREQUENCY(7) ANALYSIS -ACTIVITY -(pCi/ml) I FREQUENCY ANALYSIS Daily Grab Daily- Principal Gamma SE-7 Sample (6) Emitters (3)

I-131 1E-6 I Dissolved and - 1E-5 Entrained Gases-(Gamma Emitters)

H-3 -1E-5 Monthly - Gross Alpha 1E-7 Composite -

(4) .

Quarterly Sr-89, Sr-90 5E-8

- Composite Fe-55 - 1E-6

._ (4)

Rev. OL-12 11/01

CALLAWAY-- SP TALE 16-.11-1 --(Sheet 2)

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

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

LLD= 4.6 6 Sb ExVx2.22E6xYxexp(-AAt)

Where:

LLD = the "a priori"-lower limit of detection (microCuries 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),

2.22E6= the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, X. = the radioactive decay constant for the particular radionuclide (sec-1), and At = the elapsed time between-the-midpoint of the sample collection period,-,and the time of counting (sec)-. -For-batch releases, At=o. -

Typical values of E,- VY, and At should be used in the calculation. - --

It should be recognized that the LLD-is defined as-a "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.- Analyses shall be Rev. OL-12 11/01

CALLAWAY - SP

) lETALlE 16.11-1 (Sheet 3)

TABLE NOTATIONS performed in such a manner that the stated LLD's will be achieved under routine conditions.

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

discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

(3)The principal gamma emitters for which the LLD control applies include the following-radionuclides: 1Mn-54, Fe-59, Co-58, Zn-65, Mo-99,-Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to 'be considered.

Other gamma peaks that are identifiable, together with those of the above'nuclides, shall also be-analyzed and reported in the Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June '1974.

(4)A composite sample is one in which the quantity of-liquid sampled is proportional to the 'quantity of liquid waste discharged and in which the-method of sampling employed results ina specimen that-is representative of the liquids released. Prior to analysis, all samples-taken for the

) composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.

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

(6)Samples shall be taken-at the initiation of-effluent flow and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter while the release is occurring. To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent-stream discharge volume. The-ratio of sample volume to effluent discharge volume shall be maintained constant for all-samples taken for the composite sample.

(7)Samples shall be representative of the effluent release.

Rev. OL-11 5/00

CALLAWAY - SP TABLE 16.11-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM INSTRUMENT CHANNELS OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Discharge 1 31 Monitor (HB-RE-18)

b. Steam Generator Blowdown 1 32 Discharge Monitor (BM-RE-52)

2. Flow Rate Measurement Devices

a. Liquid Radwaste Blowdown 1 34 Discharge Line (HB-FE-2017)

b. Steam Generator Blowdown 1 34 Discharge Line (BM-FE-0054)

c. Combined Cooling Tower Blowdown 1 - 34

) and Bypass Flow (FEDB1006, FEDB1101)

3. Discharge Monitoring Tanks (DMT's)

Level

a. DMT A(HB-LI-2004) 1 33

b. DMT B(HB-LI-2005) 1 33 ACTION-STATEMENTS ACTION 31 - With the number of channels OPERABLE less-than required by the Minimum-Channels OPERABLE requirement,-effluent releases via this pathway may continue for up to 14 days provided that prior to initiating-a-release: -

a. At least two independent samples are analyzed in accordance with Section 16.11.1.1.1, and

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

Otherwise, suspend release of radioactive effluents via this pathway.

Rev. OL-9 5/97

CALLAWAY - SP TABLE 16.11-2 (Continued) 3 ACTION STATEMENTS ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may 'continue for up to 30 days provided grab samples are analyzed for principal gamma emitters and I-131 at a-lower limit of detection as specified in Table 16.11-1: I

a. At least once per-12 hours when the specific activity of the-secondary coolant is greater than 0.-01 micro-Curie/gram DOSE EQUIVALENT I-131, or

b. At least once per 24'hours when the specific activity of the secondary-coolant is less than or-equal to 0.01 micro-Curie/gram DOSE EQUIVALENT I-131.

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue-for up to 30odays provided the volume discharged is determined by alternate means.

ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels- OPERABLE requirement, effluent releases via this pathway may continue for up -to 30 days 4

provided the flow rate is-estimated at least once per hours during actual releases. Pump performance curves generated in place-may be-used to estimate flow.

Rev. OL-9 5/97

CALLAWAY - SP TART.r 16 11-1 R~nTorcrT~vV T.T~jTTn VrFT.tUrNT MCONT'rTOTNr. TNqTRtJMRNrArTnN qtTRVrTTT.ANCE TrVQtTRVMrNTS I

CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL CHECr CrHEK CAT.TRRATTOM TVST TNSTRITMVEN

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid-Radwaste Discharge D P R(2) Q(1)

Monitor (HB-RE-18)

b. Steam Generator Blowdown D M R(2) Q(1)

Discharge Monitor (BM-RE-52)

2. Flow Rate Measurement Devices

a. Liquid Radwaste Blowdown D (3) N.A. R N.A.

Discharge Line (HB-FE-2017)

b. Steam Generator Blowdown D(3) N.A. R N.A.

Discharge Line (BM-FE-0054)

)j c. Combined Cooling Tower Blowdown and Bypass Flow D(3) N.A. N.A.

(FEDB1006, FEDB1101)

3. Discharge Monitoring Tanks (DMT's) Level

a. DMT A(HB-LI-2004) Prior to N.A. R N.A.

release (4)

Prior to N.A. R N.A.

b. DMT B(HB-LI-2005) release (4)

TAnT.V NOT'TTONS (1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control-room alarm annunciation occur as appropriate if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm/Trip Setpoint (isolation and alarm), or

b. Circuit failure (alarm only), or

c. Instrument indicates a downscale failure (alarm only), or

d. Instrument controls not set in operate mode (alarm only).

Rev. OL-ll 5/00

CALLAWAY - SP TABLE 16.11-3 (Sheet 2)

RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS (2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards-obtained from the National Institute of Standards and-Technology (NIST) or using-standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall perrit calibrating the system over its intended range'of energy, measurement range, and establish monitor response to a solid calibration source.' For subsequent-CHANNEL CALIBRATION, NIST traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has-been calibrated by relating it to equipment that was previously (within 30 days)'calibrated by the same geometry and type of source standard traceable to NIST. -

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

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

)

Rev. OL-9

-I 5/97 -

CALLAWAY - SP TAB P I1JT1 1-4 HADn~ozerTyr GASEOUS EFFLUENTS SAMPLITNG AND ANAL.YSIS PRnGRAM

1. Waste Gas Decay Tank SAMPLING MINIMUM TYPE OF ACTIVITY ANALYSIS LLD (1)

FREQUENCY (9) ANALYSIS (pci/ml)

FREQUENCY Prior to each Prior to each Principal Gamma Emitters- 1IE-4 release- grab tank particulate, iodine, noble gas (2) sample . _

Continuous See footnote 8 -

- _ -2. Containment Purge or Vent SAMPLING MINIMUM TYPE OF ACTIVITY ANALYSIS LLD (1)

FREQUENCY (9) ANALYSIS (pCi/ml)

FREQUENCY _

Prior to each Prior to each Principal Gamma Emitters- IE-4 release- grab release particulate, iodine, noble gas (2) sample __ H-3(oxide) I1E-6 Continuous See footnote 8

13. Unit Vent (3)

) SAMPLING FREQUENCY (9)

MINIMUM ANALYSIS TYPE OF ACTIVITY ANALYSIS LLD (1)

(VCi/ml)

FREQUENCY --

Monthly- grab Monthly (3) (4) Principal Gamma Emitters- 1E-4 sample (3)(4) particulate, iodine, noble gas (2)

_ H-3(oxide) 1E-6 Continuous (6) Weekly (7) I-131 1E-12 I-133 lE-10 Principal Gamma Emitters- lE-11 particulate nuclides only (2)-

Monthly Gross Alpha lE-11 Composite =

Quarterly Sr-89, Sr-90 lE-11 Composite - -

Rev. OL-10 11/98

CALLAWAY - SP rART.E 16.11-4 (Sheet 2)

4. Radwaste Building Vent

-.SAMPLING MINIMUM' TYPE OF ACTIVITY ANALYSIS -LLD (1)

FREQUENCY (9) ANALYSIS l (Pci/ml)

FREQUENCY - I grab Monthly Principal Gamma Emitters- 1E-4 Monthly-sample particulate, iodine, noble gas-(2)

Continuous (6) Weekly (7) I-131 IE-12 I-133 lE-10 Principal Gamma Emitters- lE-1l particulate nuclides only (2)

Monthly - Gross Alpha lE-l1 Composite '

Quarterly Sr-89, Sr-90 lE-1l

_ Composite .

5. Laundry Decontamination Facility Dryer Exhaust MINIMUM TYPE OF ACTIVITY ANALYSIS LLD (1)

SAMPLING FREQUENCY (9) ANALYSIS (PCi/ml)

FREQUENCY I Continuous (6) Weekly (7) - Principal Gamma Emitters- -1E-11 particulate nuclides only (2)

Monthly (10) Gross Alpha 1E-11

) Composite Quarterly (10) Sr-89, Sr-90 lE-11 Composite

6. Containment ILRT 1epressurization (Post-test Vent)

SAMPLING MINIMUM TYPE OF ACTIVITY ANALYSIS LLD (1)

FREQUENCY (9) ANALYSIS (PCi/ml)

FREQUENCY- _

Prior to each Prior to each Principal Gamma-Emitters- 1E-4 release- grab release particulate, iodine, noble gas (2) sample = M-3(oxide)- - 1E-6 Rev. OL-l1

. 5/00

CALLAWAY - SP TABLE 16.11-4 (Sheet 3)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95i probability with only 5t probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD = 4.66 Sb E

ExVx 2.22E6 xYx exp(-A~t)

Where:

LLD = the "a priori" lower limit of-detection (microCuries'-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),

) 2.22E6= the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive-decay constant for the particular radionuclide (sec 1), and At the elapsed time between the midpoint of the sample collection-period, and the-time of counting (sec).

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

It should be recognized that the LLD is defined as a -'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.- Analyses shall be performed in such-a manner that the stated LLD's will be achieved-under routine conditions.

Rev. OL-10 11/98

CALLAWAY - SP--

rARTA.I.-1 1-4. (Sheet 4)

TABLE NOTATIONS (2) The principal gamma emitterssfor which-the LLD specification

- applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases.

This list does not mean that only these nuclides are to be considered. Anynuclide-which-is identified in the sample and which is also listed in the ODCM gaseous effluents dose factor tables, shall be'analyzed and reported in the Radioactive Effluent Release Report.

(3) If the Unit Vent noble gas monitor (GT-RE-21B) shows that the effluent activity-has increased (relative to the

-pre-transient activity) by more than-a factor of 3 following a reactor shutdown, startup, or a thermal power change which exceeds-15% of the rated thermal-power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, samples shall-be obtained and analyzed for noble gas, particulates and iodines. This sampling shall continue to be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for a period of 7 days or until the Unit Vent noble gas monitor no longer indicates a factor of-3 increase in Unit Vent noble gas activity, whichever comes first.

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

(5) Deleted.

(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the-time period covered by each dose or dose rate calculation made in-accordance with Sections 16.11.2.1, 16.11.2.2,'and 16.11.2.3.

(7) Samples shall be changed at least-once'per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or removal'from the sampler. When -sampling is performed in accordance with footnote 3 (above), then the LLD may be

-increased by a factor of 10.

(8) Continuous sampling of this batch release-pathway is included -in the'continuous sampling performed for the corresponding continuous release pathway.

(9) Samples shall be representative of the effluent release.

(10) Required-only if Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137,- Ce-141, or Ce-144 are detected in principle gamma emitter analyses.

Rev. OL-11 5/00

,% OCT-02-20e2 15:22 AMIEREN UE CORP.- NUC.- SERV P.06 CALLAWAY - SP BAUM= PEELI~nt5~~FTEN'?3-MpNTrT132 rTuqptm '=Tn MINIMU1* CHANNELS 111SIRUMMT U1ER&BIE &APPT.ThRXTr.jTY sACvTO2H

1. Unit Vent System

a. Noble Gas Activity Monitor 1 At all times 40,46

- Providing Alarm (GT-RE-21)

b. Iodine Sampler I At all times 43

c. Particulate Sampler 1 , At all times 43

d. Unit Vent-rlow Rate 1 -

e- Particulate and 1 Radioiodine Sampler Plow Rate Monitor

2. Containment Purge System MODES 1,2,3,4 and.

during CORE ALTERATIONS or movement of irradiated fuel within the containment FSAOR C9 c. Particulate Sampler 1 MODES 1,2,3,4 and- 43 during CORE ALTERATIONS or movement of irradiated fuel within the containment -

d. -Containment Purge -NA Ventilation Flow Rate N/A N/A e.-Particulate and C I. -MODES 1,2,3,4 and 43 Radioiodine Sampler Flow during CORE ALTERATIONS Rate Monitor or movement of irradiated fuel 'within

- the containment

3. Radwaste.Building Vent System

a. Nobile Gas Activity i At all times . 38,-40 Honitor-Providing Alarm and Autoomatic Termination of Release (GR-RE-loQ Rev. OL-12 11/01

FSPAcd INSERT A

)

a. Noble Gas Activity Monitor

- Providing Alarm and 2 MODES 1, 2, 3,-and 4. 41 Automatic Termination of Release (GT-RE-22, GT-RE-33)

- Providing Alarm function 1 During CORE ALTERATIONS 42 only (GT-RE-22, GT-RE-33) or movement of irradiated fuel within the containment

,)

CALLAWAY - SP PART.R 1 h;-t 1-- (Sheet 2)

)

b. Iodine Sampler 1 At all times, 43

c. Particulate Sampler 1 At all times 43

d. Radwaste Building Vent N/A N/A N/A Flow Rate

e. Particulate and 1 At all times 43 1 Radioiodine Sampler Flow Rate Monitor

4. Laundry Decontamination Faciliy Dryer Exhaust

a. Particulate Monitor 1 When the dryers are 47 operating

b. Particulate Monitor Flow 1 When the dryers are 47 Rate Meter operating

c. Dryer Exhaust Ventilation NA NA NA Flow Rate

)

Rev. OL-12 11/01

OCT-,04-2002 -11:54 A'MEREN] IE CORP. tUC. SERV P.G6

"_-s, -e-~toe. vo-a. u-Htj.HWH-Y i-t-I 800 348 0139 P20 CAL.LAW4AY - SP ACTION~3B - Wth the number of low rango ehannels OPgRABLt Levu than requirod'by the Minimurr Channoils OPERABLU reguxdxent, the ciortexnte of the tank(s) may be releaeed to'the nrvironmnejt for 'up to 14 daya provided that prior to Initiating-the release:

a. A.t least two independent iDamples of the tank's contents are analy -zd, Andl

b. A~t leaat t'.o technically.q'ualified mneribera of the Ea cility staff

indeendcntl~y verify the -releaoe rate calculatione and d.Lccharge valve lineup.

Otherwico, cuaspond release of x~adioactixa e~fflueentu via thic pathway-4CTXON 39 - DaletcA.

ACTXOU 40- With the niurrber of low xange channels OPERABPLE leups than rcqjuired by

%he Hinzimumch effluent releages V".-

L. pah may contin;uea for up to 30 daysrye ab Gamplea are taken at least once per 12-1houre and th4 snle analyzed_.

for radioactivity within 241houru.,

ACTION 41 - ~ Z U With the numiber of channe1r. OMMAfLE one lesc than required by the H-inimurn Channels aPEMMEL requiremnent, rxeator6 tho af fected channel. .

to OPERABLE status with 4 hurs _If the~inoperable channel La no AcoA~ g ro oart v4ri et1aM a Co~jei-,n tee.1r.I W~trcioh o hne3. O _lPALR less th nrciusred b 'the ATO 43- With the number of channeIs OPJ~L ls tai +/-n ie b h Hiniminim Cannelas OP5P.ABL~ re'qulemrn t fI~ctXl Q iat d Ce

.af~ectdpati~a m f rotnadi foaiv efftou0entsvia ticepathw ee cont~inuousl.y coletd with Auxiliary sanipling eq~uipmentaes gure" d in Table 16-11-4.

ACTION 44 Deleted.

ReV. OL~-12 11 /01

' r CALLAWAY - SP rAnT.r E1 1 - C- (Sheet 4)

ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements.

ACTION 46 - For midrange and high range channels only - with the number of OPERABLE channels less than required-by the Minimum-Channels OPERABLE requirement, take the action specified in Section 16.3.3.4, ACTION C.

ACTION 47 - With the number of channels OPERABLE less than required by the Minumum Channels OPERABLE requirement, immediately suspend the release of radioactivite effluents via this pathway.

I Rev. OL-10 11/98

U I CALLAWAY u SP TABLE 16.11-6 (Sheet 2)

d. Radwaste Building Vent Flow Rate N.A. N.A. R (4) N.A. At all times D N.A. R N.A. At all times

e. Particulate and Radioiodine Sampler Flow Rate Monitor

4. Laundry Decontamination Facility Dryer Exhaust

a. Particulate Monitor NA D A Q(5) When the~dryers are operating

b. Particulate Monitor Flow Rate D NA A NA When the dryers are Meter operating

c. Dryer Exhaust Ventilation Flow NA NA R (4) NA When the dryers are I operating Rate Rev. OL-10 11/98

CALLAWAY - SP

.11-i (Sheet 3)

(1) The CHANNEL OPERATIONAL TEST shall also (3) The initial CHANNEL CALIBRATION shall be I demonstrate that automatic isolation of this performed using one or more of the reference pathway and control room alarm annunciation (gas or liquid and solid) standards certified occur as appropriate if any of the following by the National Institute of Standards &

conditions exists: Technology (NIST) or using standards that have been obtained from suppliers that participate

a. Instrument indicates measured levels above in measurement assurance activities with NIST.

the Alarm/Trip Setpoint (isolation and These standards shall permit calibrating the alarm), or system over its intended range of energy, measurement range, and establish monitor

b. Circuit failure (alarm only), or response to a solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable

c. Instrument indicates a downscale failure standard (gas, liquid, or solid) may be used; (alarm only), or or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was

d. Instrument controls not set in operate mode previously (within 30 days) calibrated by the (alarm only). same geometry and type of source standard traceable to NIST.

(2) The CHANNEL OPERATIONAL TEST shall also (4) If flow rate is determined by exhaust fan I

demonstrate that control room alarm annunciation occurs if any of the following status and fan performance curves, the conditions exists: following surveillance operations shall be performed at least once per 18 months:

a. Instrument indicates measured levels above a. The specific vent flows by direct the Alarm Setpoint, or measurement, or

b. Circuit failure, or b. The differential pressure across the exhaust fan and vent flow established by the fan's

c. Instrument indicates a downscale failure, or "flow-AP" curve, or

c. The fan motor horsepower measured and vent

d. Instrument controls not set in operate mode. flow established by the fan's "flow-horsepower" curve.

(5) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this I pathway and the shutdown of the dryers occur as appropriate if any of the following conditions exists:

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

b. Monitor failure.

Rev. OL-ll 5/00

I!

- )

CAILAWAY - SP TABLE 16.11-7 PADTOT101TCATA TENVTRONMENTAT. MONTTORTNr PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY AmNDOR .CAMPL.E T.OCATTONS (1) COT.T.rTTON RTC nr ANAT.Y.,T.

1. Direct Radiation 2) Forty routine monitoring stations Quarterly Gamma dose quarterly either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of sixteen stations, onejin each meteorological sector in the general area of the SITE BOUNDARY; An outer ring ofrstations, one in each meteorological sector in the 6- to 8-km (3 to 5 mile) range from the site;,and Eight stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

Rev. OL-12 11/01 r

CALLAWAY - SP TABLE 16.11-7 (Sheet 2) ]l 1AnTOTOGTnAT. gNVTPONMFN'TAT. Mt1NTTPoTNa PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY ALNfl /OR .< MPT.I LOCATIONS (1) CrT.T.rWCTOTN WWotTNCY OF INALYTS 2., Airborne' Samples from five locations; Radioiodine and Particulates Three samples from close to the continuous sampler 1-131 SITE BOUNDARY locations, in operation with sample analysis weekly.

different sectors, with high collection weekly, or calculated annual average ground more frequently if Paw-41-111atiE .CRampl1r: Gross level D/Qs. required by dust loading. beta radioactivity analysis following filter change 4)

One sample from the.vicinity of a and gamma isotopic community located near the plant analysis(5 ) of composite (by with a high calculated annual location) quarterly. '

average ground level D/Q.

One sample from a location in the vicinity of Fulton, MO.

Rev. OL-12 11/01

CAILLAWAY - SP TABLE 16.11-7 (Sheet 3)

RAnTOTmOGTCAT. RNVTPON~MTFNAT, MONVPOmTNm PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATHWAY On ANALT.VATIS MOT.T.1VrTTON WRQUNCY A/N iOIR SAMPT.rW T.ATTnNsl(1

3. Waterborne One sample upstream Composite sample over Gamma isotopic(5) and tritium

a. Surface (6)

One sample downstream 1-month period (7). analysis monthly Samples from one or two sources Quarterly Gamma Isotopic(5) and tritium

b. Ground analysis quarterly

,onlyvif likely to be affected(8 areas'where the hydraulic gradient or As there are no ground water'sources used for drinking or irrigation purposesi-n is currently not included as part of recharge properties are suitable for contamination, the ground waterborne pathway the Callaway Plant Radiological Environmental Monitoring Program.

One sample of each of one to three Composite samVle over I-131 analysis on each

c. Drinking erIocl'7-weeK wnen +/-

2-week perloa-' when I- compua.r- winen rue4 %.LWt:

of the'nearest water supplies within 10 miles downstream that 131 analysis is calculated for the consumption I' could be'affected by its performed, monthly s of the water'is greater than 1-discharge. composite otherwise. mrem per year( 9 ). Composite I I I for gross beta and gamma One sample from a control isotopic analysesO monthly.

'location. . Composite for tritium analysis quarterly.

discharge point, the drinking water pathway As there are no drinking water'intakes within 10, miles downstream of the Monitoring Program. Should the is currently not included as part of the Callaway Plant Radiological Environmental of the discharge point, the program annual Land Use Census identify water intakes within 10 river miles downstream will be revised to include this pathway.

Rev. OL-12 11/01

A, ,, I.

CALLAWAY - SP TABLE 16.11-7 (Sheet 4)

I T

RAnlTOTfl(TrAT. TENVTRONMENTAT. MONhT ORTNr. PRO(TPAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY COT.T.rr-TTON FQtN!Y Or ANTAT.VS ANTn /OR RAMPT.r TLDCATTONS(1)

d. Sediment from One sample from downstream area Semiannually Gamma isotopic analysis(5) I shoreline with existing or potential semiannually recreational value ,

4. Ingestion a., Milk Samples from milking animals in Semimonthly when animals Gamma isotopic(5 ) and I-131 three different meteorological are on pasture, monthly analysis semimonthly when sectors within 5 )am (3 mile); at other times animals'are on pasture:.

distance having the highest dose monthly at other times I,,

potential. If there are none, then one sample from milking animals in each of three different meteorological sectors between 5 to 8 km (3 to 5 mile) distance where doses' are calculated to be 9

greater than 1 mrem per yr.( ) I One sample from milking animals at' a control location, 15 to 30 km (10 to.20 mile) distance and in the least prevalent wind direction.

Due to the lack of milking animals which satisfy these requirements, the milk pathway is currently not included as part of the Callaway Plant Radiological Environmental Monitoring Program. Should the Annual Land Use Census identify the existence of milking animals in locations which satisfy these requirements, then the program will be revised to include this pathway.

Rev. OL-12 11/01 I

Ii

I@

CALLAWAY - SP TABLE 16.11-7 (Sheet 5) I -.

RATlTOLTOOTCAT. VNVTROTNRNTAT. MONT OPTG P1ROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLE SAMPLING AND TYPE AND FREQUENCY ATNn IflPAMPLR t'T.T.T=

QV ANAT.VSCTSC TOCiATTQNR(1)

b. Fish One sample of each commercially Sample in season, or Gamma isotopic analysis(5 ) on and recreationally important semiannually if they are edible portions species in vicinity of plant not seasonal discharge area.

One sample of same species in areas not influenced by plant discharge.

c. Food Products One sample of each principal At time of harvest( 1 0 ) Gamma isotopic analysis(5) on class of food products from any edible portion I

area that is irrigated by water in which liquid plant wastes have been discharged.

I I . ..

As there are no areas irrigated by water in which liquid plant wastes have been discharged within 50 miles downstream of the discharge point, this sample type is not currently included as part of the Callaway Plant Radiological Environmental Monitoring Program. Should the annual Land Use census identify irrigation water intakes within 10 river miles downstream of the discharge point, the program will be revised to include this sample type.

Rev. OL-12 11/01

II I II)

CALLAWAY - SP TABLE 16.11-7 (Sheet 6)' I PAflTOTOGTAT. 1yNVTRONMT1NTAT. MONTogPTjn PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE SAMPLING AND, TYPE AND FREQUENCY EXPOSURE PATHWAY c0N..W. FQTTrNr!Y RTO fW ANAT.YSTS ANODOR SAMPT.VW Samples of three different kinds Monthly when available Gamma isotopic (5) and I-131

c. Food Products of broad leaf vegetation if analysis available grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed One sample of each of the similar Monthly when available Gamma isotopic (5) and 1-131 broad leaf vegetation grown 15 to, analysis 30 km (10 to 20 mile)' distant in, the least prevalent,wind direction if milk sampling is not performed Rev. OL-12 11/01

I CALdLAWAY - SP TABLE 16.11-7 (Sheet 7)

TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one unit, and additional description where pertinent, shall be provided for each and every sample location in Table 16.11-7 in a table and figure(s) in the appropriate plant procedures.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due-to hazardous conditions, seasonal -

unavailability,-malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, 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 documented in the Annual Radiological Environmental Operating Report pursuant-to Technical Specification 5.6.2.

It is recognized that, at times,'it may not-be possible or practicable to continue to obtain samples of the media-ofchoice at the most desired location or time. In these instances suitable specific-alternative media and locations may be chosen for the particular -

pathway in question and apprbpriate'substitutions made within 30 days in the Radiological Environmental Monitoring Program. Submit in the

) next Annual Radiological Environmental Operating Report-documentation for a change including the-revised-figure(s) and table reflecting-the new location(s) with-supporting information identifying the-cause of-the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

The-selection of sample locations should consider accessibility of sample site, availability'of power,-wind direction frequency, sector population, equipment-security, and the presence of potentially adverse environmental conditions (such as.unusually dusty conditions, etc.).

(2) One or more instruments, such as a pressurized ion chamber, for -

measuring and recording dose rate continuously may be used in place of, or-in addition to, integrating dosimeters.- For-the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor;'two or more -phosphors in a packet are'c6nsidered as two or more'dosimeters. Film badges shall not be-used asedosimeters for measuring direct radiation. -The number of direct radiation monitoring -

stations may be reduced according to geographical limitations; e.g., at an ocean site,-some sectors will be-over water'so that the number-of dosimeters may-be reduced accordingly. The frequency of analysis or readout for TLD systems will-depend upon the characteristics of-the specific system used and should be selected to obtain-optimum dose information with minimal fading. - -

Rev. OL-12

- - 11/01

) CALLAWAY - SP TABLE 16.11-7 -(Sheet 8)

TABLE NOTATIONS (3) Deleted.

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

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

(6) The "upstream sample" shall-be taken at a-distance beyond significant influence of the discharge. The "downstream"-sample shall be taken in an area near the downstream edge of the mixing zone.

(7) In this program, composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

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

(9) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

(1O)If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and-root food products.

Rev. OL-12 11101

CALLAWAY SP

. ~~TABLE 1.18 ENVIRONMENTAL SAMPLES REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN REPORTING LEVELS FISH MILK FOOD PRODUCTS WATER AIRBORNE PARTICULATE oci/elA (i3Ci/kq. wet)l ANALYSIS m e OR GASES (pCi/mkL (pCi/kqc.

we t) b H-3 20,000.

1,000 30,000 Mn-54 400 10,000 Fe-59 1,000 30,000 Co-58 300 10,000 Co-60 Zr-Nb-95** 400 3 100 2 0.9 1-131 .

1,000 60 1,000 30 10 Cs-134 2,000 70 2,000 50, 20 Cs-137 300 Ba-La-140

200 convert to units of (aj Multiply the values in this table by IE-9 to LlCifml.

this table by lE-9 to convert to unitssof tCi/g.

(b) Multiply the 'values in samples, a value of 30,000 pCi/e may be used.

For drinking water samples. This is 40 CFR Part 141 value. For surface water Total activity, parent plus daughter activity.

Rev. OL-9 5/97

I

/

CALLAWAY - SP TABLE 16.11-9 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (LLD) (1), (2), (3)

LOWER LIMIT OF DETECTION SURFACE DRINKING AIRBORNE MILK FOOD WATER FISH SEDIMENT WATER PARTICULATE (rCi/tLa PRODUCTS (pCi/kc.

jpcie La ciie La tyCi/kg, ANALYSIS OR GASES (pCi/mIj (ICi/kcL wetihb 4dCvia lwet~a Gross Beta 4 4 0.01, H-3 3000 2000 15 15 130 Mn-54

'30 260 Fe-59 1 30 15 15 130 Co-58,60 15 15 Zr-Nb-95**

0.07 1 60 1-131 , 1000 is1 15 15' 130 60 150 Cs-134 15 0.05 18 80 180 18 18 0.06 150 Cs-137 15 15 Ba-La-140 15 tiCi/ml.

(a) Multiply the values in this table by IE-9 to convert to units of Multiply the values in this table by 1E-9 to convert to units of RCi/g.

(b)

Total activity, parent plus daughter activity I I I Rev. OL-9 5/97

CALLAWAY - SP TABLE 16.11-9 (Continued)

TABLE NOTATIONS to be considered.

(1)This list does not mean that only these nuclides are of the listed Other peaks that are identifiable, together-with those Annual

- nuclides, shall also be analyzed and reported in the

-Radiological Environmental Operating Report.

dosimeters used (2)Required detection capabilities for thermoluminescent with the for environmental measurements shall be in accordance 1977.

recommendations of Regulatory Guide-4.13, Revision 1, July as the (3)The LLD is defined, for purposes of these specifications, that will smallest concentration of radioactive material in a sample above system background, that will be detected with yield a net count, concluding that a 95V probability with only 5% probability of falsely

'blank observation represents a "real" signal.

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

LLD= -4:66 Sb E xV x 2.22E6 x Y x exp(-AAt)

Where:

LLD = the "a priori" lower limit of detection (microCuries 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),

2.22E6 = the number of'disintegrations per minute per microCurie, Y the fractional radiochemical yield, when applicable,

= the radioactive decay constant for the particular 1

radionuclide (sec ), and At -the elapsed-time'between the end of-the sample collection period, and the time of counting (sec).

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

It should be-recognized that the LLD-is defined as a 'a'priori" (before the fact) limit representing-the capabilityof a measurement--system and

- not as an "a posteriori" (after the fact) limit'for a particular the measurement. Analyses shall be performed in suchta manner that stated LLD's will be achieved under routine-conditions. -

Rev. OL-9 5/97

- -_- I ," - - - - . -

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, ' *-UIO CALLAWAg PAN I.. - -~~ ~ BOUNDARYAFO SITE

-SITE BOUNDARYFO LIQUID EFFLUENTS - -

FIGURE 16.11-1 I

l

REFORM WIL LIFE ARiA ? EAK.USE3-25-46,HUNTERS -ON FALL WEEKENDS. -

THE AREA IS CONTROLLED BY THE MISSOURI DEPARTMENT OF - .

CONSERVATION. ACTIVITIES ARE .

PERMITTED ONLY IN SPECIAL

-DESIGNATED AREAS AND AMPING I3 NOT PERMITTED, PLANT SITE PERIPHERAL AREA . *.

FENCED PLANT AREA - j RESTRICTED AREA COUNDARY .I .

- (BITE BOUNDARY FOR OA3EOL! f* -

EFFLUENT) - -*

R AREA CLOSED TO PUBLIC USE

ULNRC-04840, Annual Radioactive Effluent Release Report

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5.1 DESCRIPTION

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ULNRC-04840, Annual Radioactive Effluent Release Report

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