ML041190195

CH-ODCM-001, Off-Site Dose Calculation Manual (Odcm).

ML041190195
Person / Time
Site:	Fort Calhoun
Issue date:	04/03/2003
From:	Shipman J Omaha Public Power District
To:	Office of Nuclear Reactor Regulation
References
EC 31353, WP10 CH-ODCM-0001
Download: ML041190195 (155)

Text

WP1 0 Fort Calhoun Station Unit No. I CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL

Title:

OFF-SITE DOSE CALCULATION MANUAL (ODCM)

FC-68 Number: EC 31353 Reason for Change: Updated to reflect 2002 Land Use Survey and added Table of On-Site Dose Estimates.

Requestor: J. Shipman Preparer: J. Shipman ISSUED: 04-03-03 3:00 pm R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 1 OF 134 TABLE OF CONTENTS PART I

1. DEFINITIONS ........................................... 6 2.' INSTRUMENTATION ...................................................... 9 2.1 Radioactive Liquid Effluent Instrumentation ... 9 2.1.1 Limiting Condition for Operation. 9 2.1.2 Surveillance Requirements. 9 2.2 Radioactive Gaseous Effluent Instrumentation .. 13 2.2.1 Limiting Condition for Operation .13 2.2.2 Surveillance Requirements .13 3.7 RADIOACTIVE EFFLUENTS . . .19 3.1. Radioactive Liquid Effluents .. 19 3.1.1 Concentration . .19 3.1.2 Dose from Radioactive Liquid Effluents .21 3.1.3 Liquid Radwaste Treatment .22 3.1.4 Liquid Holdup Tanks . ...........

....  ;-23 3.2 Radioactive Gaseous Effluents .. 24 3.2.1 Concentration .24 3.2.2 Dose - Noble Gases .28 3.2.3 Dose 131, 1-133, Tritium, and Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases) .29 3.2.4 Gaseous Radwaste Treatment .30 3.3 Uranium Fuel Cycle .. 32 3.3.1 Total Dose-Uranium Fuel Cycle .32

4. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ... 33 4.1 Monitoring Program .. 33 4.1.1 Limiting Condition for Operation 33 4.1.2 Surveillance Requirements .34 4.2 Land Use Survey .. 44 4.2.1 Limiting Condition for Operation .44 4.2.2 Surveillance Requirements 45 4.3 Interlaboratory Comparison Program .. 45 4.3.1 Limiting Condition for Operation .45 4.3.2 Surveillance Requirements .45

5. ADMINISTRATIVE CONTROLS . . .45 5.1 Responsibilities .. 45 5.1.1 FCS Chemistry Department .45 5.1.2 FCS Operations Department .45 5.2 Radioactive Effluent Reporting Requirements .. 46 5.2.1 Annual Radioactive Effluent Release Report .46 5.2.2 Annual Radiological Environmental Operating Report .47 5.2.3 Special Report .48 5.2.4 EPA 40 CFR Part 190 Reporting Requirements .48 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 2 OF 134 TABLE OF CONTENTS PART I 5.3 Change Mechanism ..................................................... 49 5.4 Meteorological Data .. 49 5.5 References .. 50

6. BASIS... 51 6.1 Instrumentation .5.1. 51 6.1.1 Radioactive Liquid Effluent Instrumentation .51 6.1.2 Radioactive Gaseous Effluent Instrumentation .51 6.2 Radioactive Effluents .52 6.2.1 Radioactive Liquid Effluents .52 6.2.2 Radioactive Gaseous Effluents .54 6.3 Radiological Environmental Monitoring ............................... .... 59 6.3.1 Monitoring Program . 59 6.3.2 Land Use Survey .59 6.3.3 Interlaboratory Comparison Program .59

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 3 OF 134 LIST OF TABLES PART I Table 1.2 - Frequency Notation ........................ 7 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation . . 8 Table 2.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation .......... 0 Table 2.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

.- 12 Table 2.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation .14 Table 2.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements ........  ; 18 Table 3.1 - Radioactive Liquid Effluent Sampling And Analysis .20 Table 3.2 - Radioactive Airborne Effluent Sampling And Analysis .25 Table 3.3 - Sampler Deposition/transportation Correction Factors .27 Table 4.1 - Radiological Environmental Monitoring Program .35 Table 4.2 - Radiological Environmental Sampling Locations And Media .37

'Table 4.3 - Detection Capabilities For Environmental Sample Analysis Lower Limit of Detection (LLD) .. 42 Table 4.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ... 43 LIST OF FIGURES PART I Figure 1 - Environmental Radiological Sampling Points .41 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 4 OF 134 TABLE OF CONTENTS PART II

1. EFFLUENT MONITOR SETPOINTS ....................................... 61 1.1 Liquid Effluents ............................................. 61 1.1.1 Liquid Effluent Radiation Monitors .............................. 62 1.2 Airborne Effluents . . . 66 1.2.1 Airborne Effluent Radiation Monitors 67........67... V 1.3 Simultaneous Release Pathways . . .73 1.3.1 Liquid Release Pathways .. 7 73.........

1.3.2 Airborne Release Pathway .. 7 75.........

2. EFFLUENT CONCENTRATIONS ...... : . ................................... 83 2.1 Liquid Effluent Concentrations ......................................... 83 2.2 Airborne Effluent Concentrations ....................................... 84

3. RADIOACTIVE EFFLUENT DOSE CALCULATIONS ............................ 85 3.1 Liquid Effluent Dose Calculations ....................................... 85 3.1.1 Doses from Liquid Effluent Pathways ............................. 86 3.2 Airborne Effluent Dose Calculations . . ................................... 89 3.2.1 Noble Gas ............................. 89 V 3.2.2 Radioiodine, Tritium, and Particulates .. 91 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases .......................... 93 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat K Milk . .96 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium .. 97 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation .. 97 7....

3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods ... 98

4. LOWER LIMIT OF DETECTION (LLD) . . . ............................ 100 R13

FORT CALHOUN STATION - CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 5 OF 134 LIST OF TABLES PART II Table 1 - Allocation Factors for Simultaneous Releases .............................. 77 Table 2- Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases .;01 Table 3 - Bioaccumulation Factors ............................................. 102 Table 4 - Highest Potential Exposure Pathways for Estimating Dose .................. 103 Table 5 - Stable Element Transfer Data ........................................... 104 Table 6 - Recommended Values for U to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data .............. ...................................... 105 Table 7 - Animal Consumption Rates ........................................... 105 Table 8 - External Dose Factors for Standing on Contaminated Ground .106 Table 9 - Inhalation Dose Factors for Adult .108 Table 10 - Inhalation Dose Factors for Teenager .111 Table 11 - Inhalation Dose Factors for Child ...................................-. 114 Table 12 - Inhalation Dose Factors for Infant .117 Table 13 - Ingestion Dose Factors for Adult .120 Table 14 - Ingestion Dose Factors for Teenager .. 123 Table 15 - Ingestion Dose Factors for Child .126 Table 16 - Ingestion Dose Factors for Infant .129 Table 17 - Recommended Values for Other Parameters .132 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure . 134 LIST OF FIGURES PART II Figure 1 - Exclusion and Site Boundary Map ....................................... 78 Figure 2 - Liquid Radioactive Discharge Pathways .................................. 79 Figure 3 - Liquid Radioactive Waste Disposal System ................................ 80 Figure 4 - Airbome Effluent Discharge Pathways ................................... 81 Figure 5 - Airbome Radioactive Waste Disposal System .............................. 82 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 6 OF 134 OFF-SITE DOSE CALCULATION MANUAL (ODCM)

1. DEFINITIONS Effluent Concentration Limit (ECL)

Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 1.

Channel Check A qualitative determination of acceptable operability by observation of channel behavior during normal plant operation. This determination shall, where feasible, include comparison of the channel with other independent channels measuring the same variable.

Channel Function Test Injection of a simulated signal into the channel to verify that it is operable, including any alarm and/or trip initiating action.

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

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

Purge-Purginq A means for the removal and replacement of gases within the containment building. U Source Check Verification of channel response when the channel sensor is exposed to a radioactive source.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 7 OF 134

1. DEFINITIONS (continued)

Venting A means for the reduction of pressure greater than atmospheric within the containment structure.

Site Boundary The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee.

Unrestricted Area Means an area at or beyond the Site Boundary access to which is neither limited or controlled by licensee.

Water Effluent Concentration (WEC)

Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.

Table 1.2 - Frequency Notation The surveillance intervals are defined as follows:

NOTATION TITLE FREQUENCY S Shift At least once per shift D Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days R Refueling At least once per 18 months P Prior to Prior to each release ' I I Performance within 24 hrs. I R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 8 OF 134

.-I Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation Technical Specification ODCM Implementing Step 5.16.1.a 2.1.1, 2.2.1 5.16.1.b 3.1.1 5.16.1.c Table 3.1, Table 3.2 5.16.1.d 3.1.2 5.16.1.e 3.1.2.B.1, 3.2.2.B.1 5.16.1.f 3.1.3.1, 3.2.4.1 5.16.1.g 3.2.1 k-I 5.16.1.h 3.2.2 5.16.1.i 3.2.3 5.16 .1j3.3.1 5.16.2.a 4.1.1 5.16.2.b 4.2.1 5.16.2.c 4.3.1 5.17 5.3, 5.2.1.d 5.18 5.2.1.d

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 9 OF 134

2. INSTRUMENTATION 2.1 Radioactive Liquid Effluent Instrumentation 2.1.1 Limiting Condition for Operation A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1.1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.1.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance with Section II of the Off-site Dose Calculation Manual.

APPLICABILITY: At all times ACTION:

1) With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

2) With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the action shown in Table 2.1.1. Restore inoperable effluent monitoring instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this inoperability was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-055, RM-054A, and RM-054B.

2.1.2 Surveillance Requirements A. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 2.1.2.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 10 OF 134 Table 2.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

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

a. Liquid Radwaste Effluent Line (RM-055) 1,5

b. Steam Generator Blowdown Effluent Line (RM-054 A and B) 1I 2, 5 I'-,

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line I 3

b. Steam Generator Blowdown Effluent Line 1 3

3. Radioactivity Recorders Ij

a. Liquid Radwaste Effluent Line I 4

b. Steam Generator Blowdown Effluent Line 1 4 1 If one of the two radiation monitors is inoperable, the activity of both blowdown lines shall be monitored by the operable monitor within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of inoperability by the Shift Manager, or the action steps of ACTION 2, Table 2.1.1 should be performed on the Ik-Steam Generator that is not being monitored.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 11 OF 134 Table 2.1.1 (continued)

Table Notation ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with applicable chemistry procedures.

2. At least two qualified individuals independently verify the release rate calculations.

ACTION 2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that grab samples are analyzed for principal gamma emitters at a sensitivity of 5.OE-07 pCi/gram:

1. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 pCi/gram dose equivalent 1-131.

2. At least daily when the specific activity of the secondary coolant is less than or equal to 0.01 pCigram equivalent 1-131. Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the flow rate is determined at least once per four hours during the actual release.

ACTION 4 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the radioactivity is recorded manually at least once per four hours.

during the actual release.

ACTION 5 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. "Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the'monitor during the check. If the effluent radiation monitor fails the source 'check, carryout the action(s) of the ODCM for the inoperable monitor or terminate the effluent release.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 12 OF 134 Table 2.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL INSTRUMENT CHANNEL CHECK SOURCE CHECK CALIBRATION FUNCTION TEST

1. Radioactivity Monitors Providing Alarm l and Automatic Isolation

a. RM-054A/054B D' R Q M

b. RM-055 R Q p

2. Flowrate Monitors

a. Steam Generator Blowdown D R 1 Visual Flowcheck Daily R13 CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC(((((( V

FORT CALHOUN STATION CH-ODCM-0001

'OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 13 OF 134 2.2 Radioactive Gaseous Effluent Instrumentation 2.2.1 Limiting Condition for Operation A. The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2.2.1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.2.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance with Section II of the Off-site Dose Calculation Manual.

APPLICABILITY: At all times ACTION:

1) With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

2) With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table 2.2.1. Restore inoperable effluent monitoring instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this inoperability was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-057, RM-043, RM-062, RM-063, and RM-052.

2.2.2 Surveillance Requirements A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 2.2.2.

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'-I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 14 OF 134 Table 2.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Auxiliary Bldg. Exhaust Stack (RM-052, RM-062)

a. Noble Gas 1 1,9, 11

b. Iodine and Particulate 1 2,9,11

2. Laboratory and Radwaste Processing Building Stack (RM-043) U

a. Noble Gas 1 3,9

b. Iodine and Particulate 1 4,9 U

3. Condenser Off Gas (RM-057)

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a. Noble Gas 1 5,9

4. Containment Purge Line (RM-050/51) U

a. Noble Gas 1 1, 6,9, 11,12

b. Iodine and Particulate 1 2,9, 11,12

5. Containment Pressure Relief Line (RM-050/51) _

a. Noble Gas 1 1,9,11

b. Iodine and Particulate 1 2,9,11 U

6. Containment Penetrations M72 and M74 (Integrated Leak Rate Test Depressurization Vent Path) N/A 10 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 15 OF 134 Table 2.2.1 (continued)

MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

7. Flow Rate Measurement Devices

a. Waste' Gas Discharge Header I 7

b. Auxiliary Building Stack I 7

c. Laboratory and Radwaste Processing Building Stack I .7

d. Containment Purge Line I 7

e. Containment Pressure Relief Line Annubar DIP 1 7

8. Radioactivity Chart Recorders

a. Auxiliary Building Exhaust Stack I 8

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 16 OF 134 Table 2.2.1 (continued)

TABLE NOTATION ACTION 1 If the Auxiliary Building Exhaust Stack Noble Gas Monitor is inoperable, releases from the containment pressure relief line and the containment purge line are to be secured in the most expeditious manner. Ventilation of the auxiliary building via the Auxiliary Building Exhaust Stack may continue provided grab samples are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (+25% maximum extension) and analyzed for principal gamma emitters. (See Table 3.2)

ACTION 2 If the Auxiliary Building Exhaust Stack Iodine and Particulate Sampler is inoperable, ventilation of the Auxiliary Building and releases from the gaseous waste discharge header, containment pressure relief line or the containment purge line may continue through the Auxiliary Building Exhaust Stack provided sample collection in accordance with Table 3.2 using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of inoperability by the Shift Manager.

ACTION 3 If the Noble Gas Monitor is inoperable, ventilation of the LRWPB may continue via the LRWPB stack provided grab samples will be taken once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (+ 25% maximum extension) and analyzed for principal gamma emitters. (See Table 3.2)

ACTION 4 If the Iodine and Particulate Sampler is inoperable, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the 1-/

declaration of inoperability, by the Shift Manager, in accordance with 1-01 Table 3.2.

ACTION 5 During power operation, when the condenser air ejector is in service, the condenser off gas discharge shall be monitored for gross radioactivity. If this monitor is inoperable, grab samples shall be taken once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (+25%

maximum extension) and analyzed for principal gamma emitters. (See Table 3.2)

ACTION 6 The release of airborne effluents from the Containment purge line will be secured if a noble gas monitor is unavailable to monitor the containment building atmosphere.

ACTION 7 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 17 OF 134 Table 2.2.1 (continued)

TABLE NOTATION ACTIION 8 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue

- -- provided the radioactivity level is recorded manually at least once per four hours during the actual release.

ACTION 9 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases-may continue uninterrupted during the performance of source checks provided -

the operator is stationed at the monitor during the check. If the effluent

'iradiation mOnitor fails the source check, carryout the Action(s) of the ODCM

- -. -for the inoperable monitor or terminate the effluent release; ACTION 10 Automatic release termination capability is not required provided manual isolation can be accomplished in accordance with the requirements of SE-ST-ILRT-0001. - - I ACTION 11 During the ventilation of airborne effluents from the Auxiliary Building Stack at least one Auxiliary Building Exhaust fan shall be in operation.

ACTION 12 IF containment purges are made without processing through at least one of the Containment Air Cooling and Filtering Units, and it is confirmed that one half of the annual dose objective listed in Section 3.2.2 will be exceeded

- during the calender quarter, a special report shall be submitted to the NRC as defined in Section 3.2.4 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 18 OF 134 Table 2.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE INSTRUMENT CHECKL CALIBRATION FUNCTION CHECK.

CHECK ~TESTCHK

1. Radioactivity Monitors Providing Alarm and Automatic Isolation .__

a. RM-043 D R Q M

b. RM-057 D R Q M

c. RM-062 D R Q M, P

d. RM-052' D R Q M, PI

2. Flowrate Monitors

a. RM-043 Sampler D R _

b. RM-062 Sampler D R

c. RM-052 Sampler D R -

d. Auxiliary Bldg Exhaust Stack D R _

e. Laboratory and Radwaste R Process Bldg Exhaust Stack Operations Check Air Flow Calibration

3. Environmental Monitors

a. RM-024 - Sample Station #29 M A '_

b. RM-025 - Sample Station #28 M A '

c. RM-026 - Sample Station #36 __

d. RM-027 - Sample Station #37 M A

e. RM-028 - Sample Station #38

f. RM-029 - Sample Station #39 _

g. RM-035 - Sample Station #1 __

h. RM-036 - Sample Station #2 M A

i. RM-037 - Sample Station #3 ----

j. RM-038 - Sample Station #4 M A 1I-,

k. RM-039 - Sample Station #5 _

I. RM-040 - Sample Station #32 M A 1 Required when RM-052 is sampling the Auxiliary Building Exhaust Stack.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 19 OF 134

3. RADIOACTIVE EFFLUENTS 3.1 Radioactive Liquid Effluents 3.1.1 Concentration A. Limiting Condition for Operation

1) The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR Part 20 for liquid effluents at site discharge. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limit specified in Technical Specifications 5.16.1.b. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 pCiml, total activity.

2) Technical Specification 5.16.1 .b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/ml total activity.

APPLICABILITY: At all times ACTION:

a) When the concentration of radioactive material released at site discharge exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.

B. Surveillance Requirements

.1) Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 3.1.

2) The results of the radioactivity analysis shall be used with the calculational methods in Part II of the ODCM to assure that the concentration at the point of release is maintained within the limits of Technical Specification 5.16.1.b.

3) Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred.' Analytical results shall be submitted to the Commission in accordance with Part I, Section 5.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 20 OF 134 Table 3.1 - Radioactive Liquid Effluent Sampling And Analysis A. Monitor & Hotel Waste Tanks Releases Sampling Frequency Type of Activity Analysis Lower Limit of Detection (LLD) (pCiml)

Each Batch Principal Gamrnma Emitters 2 5.OE-07 Each Batch 1-131 -. 1.OE-06 Monthly from One Dissolved Noble Gases Batch (Gamma Emitters) 1.OE-05 Monthly Composite 4 H-3 1.0E-05 Monthly Composite 4 Gross Alpha 1.0E-07 Quarterly Composite 4 Sr-89, Sr-90 5.OE-08 Quarterly Composite 4 Fe-55 1.OE-06 B. Steam Generator Blowdown Sampling Frequency Type of Activity Analysis Lower Limit of Detection (LLD) (pCi/ml) I Weekly Composite 4 Principal Gamma Emitters 2 5.OE-07 Weekly Composite 4 1-131 3 1.OE-06 Monthly Dissolved Noble Gases (Gamma Emitters) 1.OE-05 -

Monthly Composite 4 H-3 1.OE-05 Monthly Composite 4 Gross Alpha 1.OE-07 Quarterly Composite 4 Sr-89, Sr-90 5.OE-08 Quarterly Composite 4 Fe-55 1.0E-06 NOTES:

1 LLD is defined in Part 11of the ODCM.

2 The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with a LLD of 5.OE-06.

3 A weekly grab sample and analyses program including gamma isotopic identification will be initiated for the turbine building sump effluent when the steam generator blowdown water composite analysis indicates the 1-131 concentration is greater than 1.OE-06 pCilml.

4 To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 21 OF 134 3.1.2 Dose from Radioactive Liquid Effluents A. Limiting Condition for Operation

1) The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents shall be limited to the following:

a) During any calendar quarter: Less than or equal to 1.5 mrem to the total body and 5 mrem to any organ; and b) During any calendar year: Less than or equal to 3 mrem to the total body and 10 mrem to any organ.

APPLICABILITY: At all times ACTION:

a) If the dose contribution, due to the cumulative release of radioactive materials in liquid effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 5.2.3, within 30 days.

B. Surveillance Requirements

1) Cumulative dose contributions from liquid effluents for the current calender quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per quarter.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 22 OF 134 3.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation

1) The Liquid Radwaste Treatment System shall be OPERABLE, and appropriate portions of these systems shall be used to reduce the radioactive material in liquid wastes so that one half of the annual dose objective listed in ODCM Specification 3.1.2.A will not be exceeded in a calender quarter.

APPLICABILITY: At all times ACTION:

a) Every effort will be made to process all liquid waste, except from the hotel waste tanks, through the Filtration/Ion Exchange (FIX) system before entering the monitor tanks. If the radioactive liquid waste is discharged without processing and it is confirmed that one half of the annual dose objective will be exceeded during the calender quarter, a special report pursuant to Technical Specification 5.16, shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days of the end of the quarter during which the equipment or subsystem(s) were inoperable. This report shall include the following information:

1) Identification of equipment or subsystem(s) not operable and reasons for inoperability.

2) Action(s) taken to restore the inoperable equipment to operable status.

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

B. Surveillance Requirements

1) Dose due to liquid releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the ODCM , when Liquid Radwaste Treatment Systems are not fully OPERABLE.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 23 OF 134 3.1.3B 2) OPERABLE is defined as follows:

A filtration/ion exchange'(FIX) system will be utilized for processing liquid radwaste. The system con'sists of a booster pump, charcoal pretreatment filter, and pressure vessels containing

-organic/inorganic resins, which can be configured for optimum.

performance. The effluent from the FIX system is directed to the monitor tanks for release.

Waste filters (WD-17A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the 10 CFR Part 50 Appendix I dose design objective evaluation; therefore, the inoperability of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid pathways. The inoperability of waste filters will not be considered a'reportable event in accordance with the Action listed above.

3.1.4 Liquid Holdup Tanks Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

A. Limiting Condition for Operation

1) The quantity of radioactive material contained in each unprotected outdoor liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times ACTION:

-a) When the quantity of radioactive material in any unprotected outdoor liquid holdup tank exceeds 10 curies, excluding tritium and dissolved or entrained noble gasses, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 24 OF 134 3.1.4 B. Surveillance Requirements

1) The quantity of radioactive material contained in each outdoor liquid holdup tank 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 material is being added to the tank.

3.2 Radioactive Gaseous Effluents-3.2.1 Concentration A. Limiting Condition for Operation

1) The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limits specified in Technical Specification 5.16.1..g.

2) Technical Specification 5.16.1.g establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.

APPLICABILITY: At all times ACTION:

a) When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.

B. Surveillance Requirements

1) Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 3.2. The results of the radioactivity analysis shall be used to assure the limits in 3.2.1.A are not exceeded.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 25 OF 134 Table 3.2 - Radioactive Airborne Effluent Sampling And Analysis A. Gas Decay Tank Releases Sampling Frequency Type of Activity Analysis Lower Limit of Detection (LLD) (iiCi/ml) ' -

'I Prior to each release Principal Gamma Emitters 2 1.0E-04 B. Containment Purge Releases or Containment Pressure Relief Line Releases Sampling Frequency Type of Activity Analysis Lower Limit of Detection Sampling__________

FrequencTypeofActivityAnalysis(LLD) (pCilml)' -

Prior to each release Principal Gamma Emitters 2 1.OE-04 Prior to each release H-3 1.0E-06 C. Condenser Off Gas Releases 5 Sampling Frequency Type of Activity Analysis (LLD) (oeCi/mI)

Monthly 3 Tritium (H-3) 1.DE-06 Monthly Principal Gamma Emitters 2 1.0E-04 D. Auxiliary Building Exhaust Stack and Laboratory and Radwaste Building Exhaust Stack 5 nFc T Lower Limit of Detection Sampling Frequency Type of Activity Analysis _ (LLD) (pCVml) 1 Weekly (Charcoal Sample) 1-131 1.OE-12 Weekly (Particulates) Principal Gamma Emitters 2, 1-131, and Particulates with half-lives >

eight (8) days. 1.OE-11 Weekly (Noble Gases) Principal Gamma Emitters 2 1.OE-4 Monthly Composite 4 Gross Alpha 1.OE-11 Quarterly Composite (Particulates) Sr-89, Sr-90 1.OE-11 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 26 OF 134 Table 3.2 (continued)

NOTES:

I LLD is defined in Part II of the ODCM -

2 The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-1 33m, Xe-1 35, and Xe-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141.

Ce-144 for particulate emissions.

3 Required only when steam generator blowdown radioactivity for tritium (Table 3.1, Item B) exceeds 3.OE-03 pCi/milliliter.

4 Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media.

5 Particulate and Iodine samples shall be corrected for sampler deposition/transportation efficiency by using the approved software programs or by multiplying the activity obtained by the associated sampler multiplication factor (See Table 3.3).

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 27 OF 134 Table 3.3 - Sampler Deposition/transportation Correction Factors PARTICULATE IODINE SAMPLER SAMPLE DF ACTMULT'. - DF ACTMULT 1 RM-062 AB 0.411. 2.433 0.669 1.495.

RM-052 2 AB 0.638 1.567 0.653 1.531 RM-052 2 CONT 0.525 1.905 0.688 1.453 RM-051 CONT 0.624 1.603 0.714 1.401 RM-043 LRWPB 0.809 1.236 0.873 1.236 PORTABLE CONT 1.000 1.000 0.950 1.053 ACRONYM DEFINITIONS:

AB - Auxiliary Building Exhaust Stack CONT - Containment Building LRWPB - Laboratory and Rad Waste Processing Building DF - Deposition Factor ACTMULT - Activity multiplication factor to correct for sample loss.

1 ACTMULT factors are automatically determined using the appropriate analysis sequence file for the sample type.

2 Sampler can be used to monitor either the Containment or Auxiliary Building.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 28 OF 134 3.2.2 Dose - Noble Gases A. Limiting Condition for Operation

1) The dose or dose commitment to an individual in unrestricted areas from release of noble gases in airborne effluents 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.

APPLICABILITY: At all times ACTION:

a) Ifthe dose contribution, due to the cumulative release of noble gases in airborne effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 5.2.3, within 30 days.

B. Surveillance Requirements

1) The radiation dose contributions from radioactive noble gases in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the ODCM, on a quarterly basis. .

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 29 OF. 134 3.2.3 Dose 131,1-133, Tritium, and Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases)

A. Limiting Condition for Operation -

1) The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of 1-131, 1-133 Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be limited to the following:

a) During any calendar quarter: Less than or equal to 7.5 mrem to any organ; and b) During any calendar year Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times ACTION:

a) If the dose contribution, due to the cumulative release of 1-131, 1-133, Tritium, and radioactive materials in particulate form with half-lives greater than eight days, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC per Section 5.2.3, within 30 days.

B. Surveillance Requirements

1) The radiation dose contributions from 1-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part 11of the ODCM, on a quarterly basis.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 30 OF 134 3.2.4 Gaseous Radwaste Treatment A. Limiting Condition for Operation

1) In accordance with Technical specification 5.16.1 .f, the Waste Gas System and-the Ventilation Exhaust Systems shall be OPERABLE, and appropriate portions of these systems shall be used to reduce the radioactive material in gaseous wastes so that quarterly I '

objectives listed in ODCM Specifications 3.2.2.A and 3.2.3A will not be exceeded.

APPLICABILITY: At all times ACTION:

a) If radioactive gaseous waste is discharged without treatment and it is confirmed that quarterly dose objectives will be exceeded, a special report pursuant to Technical Specification 5.16, shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days of the end of the quarter during which the equipment or subsystem(s) were inoperable. This report shall include the following information:

1) Identification of equipment or subsystem(s) not operable and reasons for inoperability.

2) Action(s) taken to restore the inoperable equipment to operable status.

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

B. Surveillance Requirements

1) Dose due to gaseous releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the ODCM, when Waste Gas Systems and Ventilation Exhaust Systems are not fully OPERABLE.

l R13 A

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 31 OF 134 3.2.46 2) OPERABLE is defined as follows:

a) Waste Gas System The waste airborne radioactive material at Fort Calhoun -

Station is collected in the vent header where the gas compressors take suction, compress the gas and deliver-it to one of the four gas'decay tanks. The waste airborne radioactive material is treated in these gas decay tanks by holding for radioactive decay prior to final controlled release to the environs. In order to provide conformance with the dose design objectives, gas decay tanks are normally stored for approximately 30 days, with earlier release allowed to support plant operation only, and thus achieve decay of short half-life radioactive materials, e.g., l-131, Xe-133. If the radioactive airborne wastes from the gas decay tanks are discharged without processing in accordance with the above conditions, and it is confirmed that one half of the annual dose objective will be exceeded during the calendar quarter, a special report shall be submitted to the Commission pursuant to Section 3.2.4A.

b) Ventilation Exhaust Systems The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilation system. If the radioactive effluents are discharged without the HEPA filters, a special report shall be submitted to the NRC as defined in Action a) above.

The discharge from the gas decay tanks is routed through charcoal and HEPA filter unit VA-82. No credit was taken for the operation of hydrogen purge filters during the 10 CFR Part 50, Appendix I dose design evaluation and doses through the airborne effluent pathways were well below the design objectives. The unavailability of hydrogen purge filters will not be considered a reportable event.

The containment air is processed through at least one of the redundant containment HEPA and charcoal filters in the Containment Air Cooling and Filtering Units prior to purging. If the containment purges are'made without processing through one of the Containment Air Cooling and Filtering Units, and it is confirmed that one half of the annual dose objective will be exceeded during the calender quarter, a special report shall be submitted to the NRC as defined in Action a) above.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 32 OF 134 3.3 Uranium Fuel Cycle 3.3.1 Total Dose-Uranium Fuel Cycle A. Limiting Condition for Operation

1) The dose to any real individual from uranium fuel cycle sources shall be limited to < 25 mrem to the total body or any organ (except the thyroid, which shall be limited to < 75 mrem) during each calendar year.

APPLICABILITY: At all times ACTION:

a) With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.1.2.A, 3.2.2.A, or 3.2.3.A, calculations shall be made including direct radiation contribution from the plant and outside storage tanks to determine whether the above limits have been exceeded. If such is the case, in lieu of any other report required by Section 5.2, prepare and submit a Special Report to the Commission pursuant to Technical Specification 5.16 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(a)(4) and 20.2203(b), 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 calender year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in the violation of l_

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.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL, REFERENCE USE PAGE 33 OF 134 3.3.1 B. Surveillance Requirements Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillance requirements 3.1.2B, 3.2.26 and 3.2.3B and in accordance with the methodology and' parameters in Part II of.the ODCM.

4. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 4.1 Monitoring Program 4.1.1 Limiting Condition for Operation A. The Radiological Environmental Monitoring Program shall be conducted as specified in Table 4.1.

APPLICABILITY: 'Atlal times ACTION:

1) Analytical results of this program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 5.2).

2) If the level of radioactivity from calculated doses leads to a higher exposure pathway to individuals, this pathway shall be added to the Radiological Environmental Monitoring Program. Modifications to the program shall be reported in the Annual Radiological Environmental Operating Report to the Nuclear Regulatory Commission.

3) If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 4.4, and the activity is attributable to plant operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days from the end of the quarter (Section 5.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 4.3 for Lower Level of Detection (LLD).

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 34 OF 134 4.1.1A 4) Radiological environmental sampling locations and the media that is utilized for analysis are presented in Table 4.2. Sampling locations are also illustrated on the map, Figure 1. Details of the emergency TLD locations are contained in surveillance test CH-ST-RV-0009, Environmental Sample Collection - Emergency Planning Zone Dosimeters.

5) Deviations from the monitoring program, presented in this section and detailed in Table 4.2, are permitted if specimens are unobtainable due to mitigating circumstances such as hazardous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program, etc. If the equipment malfunctions, corrective actions will be completed as soon as practicable. If a person no longer supplies samples, a replacement will be made if possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to Section 5.2.

4.1.2 Surveillance Requirements The Radiological Environmental Monitoring Program (REMP) samples shall be collected and analyzed in accordance with Tables 4.1, 4.2, and 4.3.

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FORT CALHOUN STATION . .- CH-ODCM-Oi1 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 35 OF 134 Table 4.1 - Radiological Environmental Monitoring Program' Exposure Pathway Collection Site Type of Analysis 2 Frequency and/or Sample -

1. Direct Radiation A. Sixteen TLD indicator stations, Gamma dose Quarterly two background stationstotal of 18.

B. An Inner-ring of 16 stations, one Gamma dose during Site Replaced in each cardinal sector in the Area and General Annually general area of the unrestricted Emergencies only.

area boundary and within 2.5 miles.

C. An outer-ring of 16 stations, I in Gamma dose during Site Replaced each cardinal sector located Area and General Annually outside of the inner-ring, but no Emergencies only.

more distant than approximately 5 miles.

2. Air Monitoring A. Indicator Stations Filter for Gross Beta 3 Weekly

1. 3 stations in the general area Charcoal for 1-131 Weekly of the unrestricted area boundary Filter for Gamma Isotopic Quarterly composite

2. City of Blair of weekly filters

3. Desoto Township I

B. One background station

3. Water A. Missouri River at nearest Gamma Isotopic, H-3 Monthly downstream drinking water composite for intake. Gamma Isotopic Analysis B. Missouri River downstream near the mixing zone. Quarterly composite for H-3 C. Missouri River upstream of Plant Analysis*

- intake (background). -

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 36 OF 134 Table 4.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site Type of Analysis 2 Frequency and/or Sample

4. Milk 4 A. Nearest milk animal (cow or Gamma Isotopic and 1-131 Biweekly grazing I goat) within 5 miles season (May to October)

B. Milk animal (cow or goat) between 5 miles and 18.75 miles (background).

5. Fish A. Four fish samples within vicinity Gamma Isotopic Once per season of Plant discharge. (May to October)

B. One background sample upstream of Plant discharge.

6. Sediment A. One sample from downstream Gamma Isotopic Semiannually area on the station side of the Missouri River.

B. One sample from upstream of Plant Intake (background).

7. Vegetables or A. One sample in the highest Gamma Isotopic Once per season Food Products 5 exposure pathway. (May to October)

B. One sample from onsite crop field C. One sample outside of 5 miles (background).

NOTES:

I See Table 4.3 for required detection limits.

2 The Lower Limit of Detection (LLD) for analysis is defined in the ODCM in accordance with the wording of NUREG-0472, Rev. 3, Draft 7.

3 When a gross beta count indicates radioactivity greater than 1E-12 pCi/mI or 1 pCUM 3 , a gamma spectral analysis will be performed.

4 If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the plant, then vegetation shall be collected at the offsite location having the highest calculated annual average ground level D/Q. (Reference ODCM Part 2, Table 4 'Highest Potential Exposure Pathways for Estimating Dose")

5 Samples should be collected from garden plots of 500 ft2 or more. (Reference Reg. Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," Dec. 1975).

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C (( ( C C C (C FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 37 OF 134 Table 4.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Sample Distance from Direction Air Monitoring Vegetables Station ApproxmateCenter Collectosetro of (degrees dges Sector Sco TLD Water Milk Sediment Fish and Food No. ites Containment from true Airborne Airborne Products (miles) north) Particulate Iodine Onsite Station, 1 11 0-meter weather 0.53 293°/WNW P X

. tower Onsite Station, 2 adjacent to old plant 0.59 2070/SSW K X X X access road Offsite Station,-

Intersection of Hwy. 0.94 145°/SE G X I

75 end term access

. road 4 Blair OPPD office 2.86 30501NW Q X X X EOF Building, North 5 Omaha Power Station 14.9 153°/SSE H X 6 Fort Calhoun, NE City 5.18 150°/SSE H X 6 Hall .8 10SS H Fence around Intake 7 gate, Desoto Wildlife 2.07 102°/ESE F X

.. Refuge Onsite Station, 8 entrance to Plant Site 0.55 191°/S J X from Hwy. 75 ._..

3 0 /NW Q X Onsite Station. NW of 0.68 Plant

_ _. I__I__I_ ._I__- I R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 38 OF 134 Table 4.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Sample Distance from Direction Air Monitoring Vegetables Station Approximate Collection Center of (degrees Sector TLD Water Milk Sediment Fish and Food No. Sites Containment from true Airborne Airborne Products (miles) north) Particulate Iodine 10 onfteStation, W 0.61 2421/WSW M X 11 Offsite Station, SE of 1.07 139*1SE G X 3 0 S

____Plant 10 Metropolitan Utilities Dist., Florence 12 12 Treatment Plant 14.3 1540 /SSE H X North Omaha, NE _

West bank Missouri 13 River, downstream 0.45 1080/ESE F X X from Plant discharge _ _

0 14 Upstream from Intake 4 /N A Bldg, west bank of river __0__4_/NA____

15' 161 _ _ _ _ _ _

171 181 19' 20 Mohr Dairy 9.86 18601S J X 211 _

22 Fish Sampling Area, 0.08 601N A Missouri River (R.M. 645.0) I_ _

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(" C C (7 C C C (7 C ( ( ( ( t, ( (. ( ( 1, (' C (' ( ( ( ( ( (' ( ( ( ( ( ( ( ( (

( CC C C( ( C (C C ( (l C( Ci< (. C ( C ( (I C CC C C ( C C (3 ( .( ( ( C (C ( C FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 39 OF 134 Table 4.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Sample Distance from Direction Air Monitoring Vegetables Station Approximate Collection Center of (degrees Sector TLD Water Milk Sediment Fish and Food No. Sites Containment from true Airborne Airbome Products (miles) north) Particulate Iodine 23 Fish Sampling Area, 17.9 358°/N A X Missouri River (R.M. 666.0) _

24' _- _ ___

251 _

261 271 = ==_.=

283 Alvin Pechnik Farm 0.94 163°/SSE H X X X X 29 Ellis Acreage 0.74 182 0/S J X X X 30" 311.

30'. _______ ______ ____

32 Valley Substation #902 1- 9.6 221°lSW L X X X 33 Bansen Farm 0.7 203°/SSW K x2 I 341 - ______

35 Onsite Farm Field 0.52 11 80/ESE F _ X Offsite Station 36 Intersection 0.75 227"/SW L X Hwy 75/Co.Rd. P37 _ _

33 Offsite Station Desoto 15 40 5 37 Township 1.57 "I___SE G X_._XX__

I I R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 40 OF 134 Table 4.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Sample Distance from Direction Air Monitoring Vegetables Station Approximate Collecson Center of (degrees Sector TLD Water Milk Sediment Fish and Food No. Sites Containment from true Airborne Airbome Products (miles) north) Particulate Iodine Offsite Station 38 Intersection 0.93 2480/WSW M X Hwy 75/Desoto Lane 39 Offsite Station Hwy 75 1.18 261 01W N X

__ _ _ North of Co.Rd. P37 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ __ _ _ _ _

NOTES:

(1) Location is either not in use or currently discontinued and is documented in the table for reference only.

(2) When a milk sample Is not available at a location, a broad leaf (pasture grass) vegetation sample will be collected at that location as a substitute.

(3) Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part 1.

Section 6.3.2. and are monitored as such.

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FORT CALHOUN STATION PAH-ODCM-0o00 REFERENCE USE OFF-SITE DOSE CALCULATION MANUAL NGE 41 OF 134 Points*

Figure 1 - Environmental Radiological Sampling t23 CIRM 666.0)

/N A w, V

LA IR

/ \CALlfORNIA

-/,

uNcrilON. -I 929 K-FT.

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-32

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t I L E S S

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illustrated.

• Locations currently discontinued are not R13 K-

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 42 OF 134 rable 4.3 - Detection Capabilities For Environmental Sample Analysis Lower Limit of Detection (LLD)I 2. 3 Sample Units Gross H-3 Mn-54 Fe-59 Co 58, Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 Beta Co-60 Water pCiJL - 2.OE+03 1.5E+01 3.OE+Oi 1.SE+Oi 3.OE+01 1.5E+01 1.5E+01 1.OE+00 4 1.5E+01 1.8E+01 1.5E+01 Fish pCi/kg (wet) _ .. 1.3E+02 2.6E+02 1.3E+02 2.6E+02 _. _ _ 1.3E+02 1.5E+02 Milk pCIL ... --- 1.OE+00 1.5E+O1 1.8E+01 1.5E+01 Airborne Particulates or Gases pCI/m' 1.OE-02 . _ _ . .--- 7.OE-02 1.OE-02 1.OE-02 Sediment pCi/kg (dry) ._

_ 1.5E+02 1.8E+02 _ .

Grass or Broad s s s Leaf Vegetation/

Vegetables or Food Products pCiUkg ... ... ._ .. _ _ 6.OE+01 6.OE+01 8.OE+01 (wet) 1 This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable as Plant effluents, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Part]l, Section 5.2.

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

3 The LLD is defined in Part 11of the ODCM.

4 LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

5 1-131 analysis performed on broadleaf/pasture grass samples when milk is unavailable. Gamma isotopic analysis performed on food products/vegetables.

R13 C C C 7 ( (. C C C ( ( C( ( (. ( ( ( ( ( ( ( ( C ( ( . (. ( l ( ( ( . ( ( ( (

( C C (c ( ( C C (C ( C Cr ( ( ('C( (c ( C C C C ( (C C C C C ( C C. C (

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 43 OF 134 Table 4.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples Sample Units H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 Water pCIL 2.0E+04 1.OE+03 4.OE+02 1.OE+03 3.OE+02 3.0E1202 4.0E+02 4.0E+02 2.OE+00 2 3.0E+01 5.0E+01 2.OE+02 Fish pCIkg (wet) 3.OE+04 1.OE+04 3.OE+04 1.OE+04 2.OE+04 _ - 1.OE+03 2.OE+03 Milk pCI/L _ _ - 3.0E+00 6.OE+01 7.0E+01 3.0E+02 Airborne Particulates or pCVmrn 3- . _ _ _ _ _ - _ 9.OE-01 1.0E+01 2.OE+01 Gases Grass or Broad.'

Leaf Vegetatlon/

Vegetables or Food Products pCi/kg -  :- _1- - _ : _.1.E+02 1.0E+03 2.OE+03 -

(wet) - . . .

1 A Non-routine report shall be submitted when more than one of the radionuclides listed above are detected in the sampling medium and:

Concentration 1 + Concentration 2 + Concentration 3 + 1.0 Reporting Level I Reporting Level 2 Reporting Level 3 When radionuclides other than those listed above are detected and are the result of Plant effluents, this report shall be submitted if the potential annual dose to a member of the general public is equal to or greater than the dose objectives of Part I, Section 3.1 and 3.2. 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.

2 If no drinking water pathway exists, the LLD of gamma Isotopic analysis may be used.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 44 OF 134 4.2 Land Use Survey 4.2.1 Limiting Condition for Operation A. A Land Use Survey shall identify the location of the nearest milk animal, nearest meat animal, nearest vegetable garden, and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The survey shall be conducted under the following conditions:

1) Within a one-mile radius from the Plant site, enumeration by door-to-door or equivalent counting techniques.

2) Within a Five-mile radius, enumeration may be conducted door-to-door or by using referenced information from county -

agricultural agents or other reliable sources.

APPLICABILITY: At all times ACTION:

a) If it is leamed from this survey that milk animals, vegetable gardens and resident receptors are present at a location which yields a calculated dose greater than 20% from previously sampled location(s), the new location(s) shall be added to the monitoring program. Milk and vegetable garden sampling location(s) having the lowest calculated dose may then be dropped from the monitoring program at the end of the grazing and/or growing season during which the survey was conducted and the new location added to the monitoring program. Modifications to the air monitoring locations, vegetable garden sampling locations, and milk sampling locations will be made as soon as practicable. The Nuclear Regulatory Commission shall be notified of modifications to the program in the Annual Radiological Environmental Operating Report (Section 5.2).

b) If it is leamed from this survey that a pathway for dose to a MEMBER OF THE GENERAL PUBLIC no longer exists, an additional pathway has been identified or site specific factors affecting the dose calculations for a pathway have changed, then this information should be documented in the Land Use Survey and the Annual Radioactive Effluent Release Report. This information can be used to increase the accuracy of the dose models for the Annual Radioactive Effluent Release Report as well as dose estimates performed during the reporting period (i.e., quarterly -

dose estimates).

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FORT CALHOUN STATION CH-ODCMOO001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 45 OF 134 4.2.2 Surveillance Requirements A. A land use survey shall be conducted once per 24 months between the dates of June 1 and October 1. The results of the land use survey.shall be submitted to the Nuclear Regulatory Commission in the Annual' Radiological Environmrental Operating Report (Section 5.2).

4.3 Interlaboratory Comparison Program 4.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission.

APPLICABILITY: At all times ACTION:

1) With analysis not being performed as required above, report the corrective actions'taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report (Section 5.2).

4.3.2 Surveillance Requirements A. The results of these analyses shall be included in the Annual Radiological Environmental Operating Report (Section 5.2).

5. ADMINISTRATIVE CONTROLS 5.1. Responsibilities 5.1.1 FCS Chemistry Department is responsible for the implementation and maintenance of the ODCM.

5.1.2 FCS Operations Department is responsible for the compliance with the ODCM in the operation of Fort Calhoun Station.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 46 OF 134 -

5.2 Radioactive Effluent Reporting Requirements The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Section I are complied with. These reports will meet the requirements for documentation of radioactive effluents contained in 10 CFR Part 50.36a; Reg. Guide 1.21, Rev. 1; Reg. Guide 4.8, Table 1; and Reg. Guide 1.109, Rev. 1.

5.2.1 Annual Radioactive Effluent Release Report A report covering the operation of the Fort Calhoun Station during the previous calendar year shall be submitted prior to May 1 of each year per the requirements of Technical Specifications 5.9.4.a. and 10 CFR Part 50.

The Radioactive Effluent Release Report shall include:

A. A summary of the quantities of radioactive liquid and airborne effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, Revision 1.

B. A summary of the meteorological conditions concurrent with the release of airborne effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1.

C. An assessment of radiation doses from the radioactive liquid and airborne effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 1. The assessment of radiation doses shall be performed in accordance with calculational l_

methodology of the Regulatory Guide 1.109, Revision 1.

D. Changes to the Process Control Program (PCP) or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period. Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed and shall indicate the date the change was implemented.

E. A list and description of abnormal releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

F. An explanation of why instrumentation designated in the ODCM Part I, Sections 2.1.1 and 2.2.1 was not restored to OPERABLE status within 30 days.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 47 OF 134 5.2.1 G. A description of any major design changes or modifications made to the Liquid and/or Gaseous Radwaste Treatment Systems or Ventilation Exhaust Systems during the reporting period.

H. An explanation of why the liquid and/or gaseous radwaste treatment systems were not OPERABLE, causing the limits of Specifications. .

3.1.3.A and 3.2.4.A to be exceeded.

5.2.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report for the previous one year of operation shall be submitted prior to May 1 of each year. This report contains the data gathered from the Radiological Environmental Monitoring Program. The content of the report shall include:

A. Summarized and tabulated results of the radiological environmental sampling/analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event that some results are not available, 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.

B. Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the plant operation and environment.

C. The results of participation in a NRC approved Interlaboratory Comparison Program.

D. The results of land use survey required by Section 4.2 E. The results of specific activity analysis in which the primary coolant exceeded the limits of Technical Specification 2.1.3. The following information shall be included:

1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded.

2) Results of the last isotopic analysis for radioiodine performed prior to exc6eding the limit, results of analysis while limit was exceeded

- ;and results of one analysis after the radioiodine activity was reduced'to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 48 OF 134 5.2.2E 3) Purification system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded.

4) Graph of the 1-131 concentration and one other radioiodine isotope _

concentration in micro-curies per gram as a function of time for the duration of the specific activity above the steadystate level, AND

5) The time duration when the specific activity of the primary coolant exceeded the. radioiodine limit.

F. A map of the current environmental monitoring sample locations.

5.2.3 Special Report If the limits or requirements of Sections 3.1.2A, 3.1.3A, 3.2.2A, 3.2.3A, 3.2.4A, 3.3.1A and/or 4.1.1A.3) are exceeded, a Special Report shall be issued to the Commission, pursuant to Technical Specification 5.16. This report shall include:

A. The results of an investigation to identify the causes for exceeding the specification.

B. Define and initiate a program of action to reduce levels to within the specification limits.

C. The report shall also include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the condition.

5.2.4 EPA 40 CFR Part 190 Reporting Requirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of dose from Specifications 3.1 .2.A, 3.2.2.A, or 3.2.3.A, calculations shall be made including direct radiation calculations, to prepare and submit a special report to the Commission within 30 days and limit the subsequent releases such that the dose to any real individual from uranium fuel cycle sources is limited to

< 25 mrem to the total body or any organ (except thyroid, which is limited to

< 75 mrem) over the calendar year. This special report shall include an analysis which demonstrates that radiation exposures to any member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 standard. The submittal of the report is to be considered a timely request and a variance is granted pending the final action on the variance request from the Commission.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 49 OF 134 5.3 Change Mechanism The ODCM is the controlling document for all radioactive effluent releases. It is defined as a procedure under the guidance of Technical Specification 5.8. Itwill.be revised and reviewed by the Plant Review Committee and approved by the Plant Manager in accordance with Technical Specification 5.17. All changes to the ODCM will be forwarded to the Nuclear Regulatory Commission during the next reporting period for the Annual Radioactive Effluent Release Report in accordance with the requirements of Technical Specification 5.17.

5.4 Meteorological Data The Annual Average X/Q is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. It is also the factor used in conjunction with the parameters and methodologies in Part II to determine unrestricted area dose on a quarterly bases or as needed. It is based on an average of the highest calculated sector X/Q values, using all 16 sectors for each of the three previous year Annual Radioactive Effluent Release Reports, and the XOQDOQ plume trajectory model. An additional 10 percent will be added to the average for unrestricted area dose estimates performed quarterly or as needed for conservatism. When calculating XIQ data for the Annual Radiological Effluent Release Report, if the highest calculated X/Q for the reporting period is observed to be greater than +/-10% of the Annual Average X/Q previously calculated, contact the Supervisor-System Chemistry for further instructions. This model conforms with the Nuclear Regulatory, Commissions Regulatory Guide 1.111.

Real time meteorological data will be utilized in the preparation of the Annual Radioactive Effluent Release Report. This data is used to calculate the joint frequency table, the dispersion coefficients and deposition factors in all 16 sectors.

These are used in the calculation of doses to individuals in unrestricted areas as a result of the operation of Fort Calhoun Station. The models used, GASPAR 2 and LADTAP 2, meet the intent of Nuclear Regulatory Commissions Reg. Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 50 OF 134 5.5 References Regulatory Guide 1.109, Rev. 1 - Calculation of Annual Dose to man from Routine Releases of Reactor Effluents for the purpose of evaluation compliance with _

10 CFR Part 50, Appendix I Regulatory Guide 1.1 11, Rev. I - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.

Regulatory Guide 1.1 13, Rev. 1 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the purpose of Implementing Appendix I.

Regulatory Guide 4.8, Environmental Technical Specification for Nuclear Power Plants.

NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.

NUREG-0472, Rev. 3 - Draft Radiological Effluent Technical Specifications for PWRs.

NUREG-1301 - Offsite Dose Calculation Manual Guidance.

Regulatory Guide 1.21, Rev. I - Measuring, Evaluating, and Reporting Radioactivity in solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.

Code of Federal Regulations, Title IO, Part 20 Code of Federal Regulations, Tide 10, Part 50 Code of Federal Regulations, Title 40, Part 190 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 Fort Calhoun Technical Specifications (Unit No. 1)

Updated Safety Analysis Report AR 12357, Implement Recommendations of Memo FC-0133-92, Part 1, Table 2.2.1 Action 4 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL' REFERENCE USE PAGE 51 OF 134'

6. BASIS 6.1 Instrumentation 6.1.1 Radioactive Liquid Effluent Instrumentation The Radioactive liquid effluent instrumentation is provided to monitor arid-control, as applicable, the releases of radioactive material in liquid effluents

'during actual or potential releases'of liquid effluents. The Alarm/Trip

- setpoints'for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual (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 De'sign Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

6.1.2 -Radioactive Gaseous Effluent Instrumentation The Radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual (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 Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 52 OF 134 6.2 Radioactive Effluents 6.2.1 Radioactive Liquid Effluents A. Concentration This specification is provided to ensure that the concentration of --

radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the _

Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e) to the population.

The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling isotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 53 OF 134 6.2.1 B. Dose This specification is provided to implement the requirements of Sections lI.A, LI.A and IV.A of Appendix 1,10 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 th'e guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept." as low as is reasonably achievable." Also, with fresh water sites with drinking water supplies which 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 Part II of the ODCM implement the requirements in Section III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in Part II of the ODCM for calculating the doses due to the actual release rates of radioactive material in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, 'Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix l," Revision 1, October 1977, and Regulatory Guide 1.1 13, 'Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix l," April 1977.

.C. Liquid Waste Treatment System' 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 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 specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10 CFR Part 50 and design objective and in Section ll.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section IIA of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 54 OF 134 6.2.1 D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

6.2.2 Radioactive Gaseous Effluents A. Concentration This specification, in conjunction with 3.2.2.A and 3.2.3.A, is provided to ensure that the dose at or beyond the Site Boundary from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limits specified in Technical Specifications 5.16.1.g. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. Because these concentrations are applied on an instantaneous basis and because of the overriding 10 CFR Part 50 Appendix I cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary, to annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR l Part 20.1301(a).

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 55 OF 134 6.2.2 B. Dose - Noble Gases.

This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, IQ CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section'll.B of Appendix I. The ACTION'statements provide the required operating flexibility and at the sare time'implement'the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data

.-such that the actual exposure of an individual through the appropriate pathways is unlikely.to be substantially underestimated. The dose calculation methodology anid parameters established in Part II of the ODCM for calculating the doses due to 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 of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.1 11, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July

, 1977. The ODCM equatioris provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 56 OF 134 6.2.2 C. Dose 131, Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section 1I.C:

of Appendix 1. The ACTION statements provide the required operatirig flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section 1Il.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the ODCM for calculating the doses due to 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 of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, Revision 1, October 1977 and Regulatory Guide 1.1 11, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for 1-131, radioactive material in particulate form with half lives greater than eight days (other than noble gases) and tritium are dependant on the existing radionuclide pathways to man in the areas at or 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 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.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 57 OF 134' 6.2.2 D. Gaseous Waste Treatment The OPERABILITY of the gaseous radwaste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.:The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable: This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10'CFR Part 50 and design objective and in Section II.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portion's of the systems were specified to ensure the design objectives set forth'in Section ll.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.

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- - l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 58 OF 134 6.2.2 E. Total Dose - Uranium Fuel Cycle This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d).

This requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mRems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mRems. 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 plant remains within twice the dose design objectives of Appendix I, 10 CFR Part 50, and if direct radiation doses ( including outside storage tanks, etc.) are kept small. The Special Report shall 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 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 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 Part 20.2203(a)(4) and 20.2203(b) is considered to be a timely request and fulfills the requirements 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. 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. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.

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FORT CALHOUN STATION CH-ODCM-0001-OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 59 OF 134 6.3 Radiological Environmental Monitoring 6.3.1 Monitoring Program The radiological environmental monitoring program required by this - -.

specification provides measurements of radiation and radioactive materials in those exposure pathways and for radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program was effective for at least the first three years of commercial operation. Following this period, program changes are initiated based on operational experience.

6.3.2 Land Use Survey This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this survey. The best survey information from door to door, aerial or consulting with local agricultural authorities, or equivalent, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the survey to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 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/iM2.

For milk, the survey is restricted to only milk animals (cow or goat) producing milk for human consumption. Air monitoring stations are strategically located to monitor the resident receptors who could potentially receive the highest doses from airborne radioactive material. Guidance provided in the Branch Technical Position and Technical Specification 5.16.2 is used to meet the intent of NUREG-0472.

6.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 60 OF 134 PART II CALCULATIONS R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 61 OF 134

1. EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents There are two liquid discharge pathways to the Missouri:River. These pathways originate with the radioactive liquid waste processing system (monitor or hotel tanks) and the steam generator blowdown system. Both of these pathways empty into the' circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathways and associated radiation monitors. Figure 3 depicts the methods of liquid effluent treatment.

The' flowrate for dilution water varies with the number of circulating water pumps in service, the number of raw water-pumps in service, and with the operation of the warm water recirculation. Some warm water from the condenser outlet is diverted from the circulating water discharge to upstream of the intake structure to help prevent ice from forming on the circulating water pump intakes during winter months.

The varying dilution flowrate and utilization of warm water recirculation is accounted for in the dilution calculations for monitor tank and stream generation releases.

Technical Specification 5.16.1.6 establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.100i-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCimI total activity.

The liquid effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

The liquid effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

Cs-1 37 is used to calibrate the liquid effluent monitors.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 62 OF 134 NOTE: If the annual average XIQ value exceeds 1.4E-04 sec/M3, consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.OE-09 pCi/mi at the unrestricted area boundary with 10% vapor/liquid separation. Contact the Supervisor-System Chemistry for further instructions.

1.1.1 Liquid Effluent Radiation Monitors A. Steam Generator Blowdown Monitors (RM-054A and B)

These process radiation detectors monitor the flow through the steam generator blowdown lines and automatically close the blowdown isolation valves if the monitor high alarm setpoint is reached. The monitor controls liquid effluent releases so that 10 times the 10 CFR Part 20 limit at the unrestricted area boundary of 1.OE-06 pCi/cc, is not exceeded at the site discharge.

The following calculations for maximum concentration and alarm setpoints are valid when steam generator blowdown is the only liquid release pathway. For simultaneous radioactive liquid releases of steam generator blowdown and monitor tank discharge, refer to Section 1.3.

The maximum allowable concentration in the blowdown line is calculated as follows:

CM = (1.OE-05 pCYlM/)(F) f Where:

1.OE-05 pCiml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).

F = Total dilution flow in the discharge tunnel (gpm).

(Normal flow is based on 1 circulating water pump at 120,000 gpm. Other flowrates may be used, as required.)

f = Blowdown flow rate (gpm). (Normal blowdown flow rate is based on 2 transfer pumps with a design flow of 135 gpm each, 270 gpm total. Other flow rates may be used, as required.)

CMA = Maximum allowable blowdown concentration (pCi/ml).

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 63 OF 134 NOTE: Setpoints may be"recalculated based on adjusted dilution flow and adjusted blowdowri flow.

1.1.1A The High Alarm Setpolnt (CPM):

Setpoint - 0.75 [((S) (CMAX)) + B]

Where:

0.75 = An administrative correction factor which includes the following:

15% tolerance to ensure radmonitor response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.

10%'tolerance to account for the difference in detector sensitivity for the range of isotopes detected.

S = Detector sensitivity factor (CPM/pCilml). (Sensitivity based on Cs-1 37).

B = Background (CPM)

CmA = Maximum allowable blowdown line activity (pCVml).

The Alert Setpolnt will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified.prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.

B. Overboard Discharge Header Monitor (RM-055)

This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of I.OE-06 pCi/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 64 OF 134 1.1.1 B The following calculations for maximum concentration and alarm setpoints are valid when Monitor Tank discharge is the only liquid release pathway. For simultaneous radioactive liquid releases of monitor tank discharge and steam generator-blowdown, refer to _

Section 1.3.

The maximum allowable concentration in the overboard discharge header is:

CM = (1.OE-05 pCi/rm) (F)

CMAX f Where:

1.OE-05 pCi/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).

F = Total dilution flow in the discharge tunnel (gpm).

(Normal flow is based on 1 circulating water pump at 120,000 gpm. Other flowrates such as raw water pump(s) may be used, as required.)

f = Maximum monitor tank discharge flow rate (gpm).

(Normal monitor tank maximum flow is 50 gpm.

Other flow rates such as raw water pump(s) may be used, as required.)

CMA= Maximum allowable activity in discharge header (PCi/ml).

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 65 OF 134 1.1.1 B The High Alarm Setpoint (CPM):

Setpoint =-0.75 [((St) (CMAX)) + B]

Where:

0.75 = An administrative correction factor which includes the following:

15% tolerance to ensure radmonitor VIAS response in accordance with License'Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.

10% tolerance to account for the difference in detector sensitivity for the range of isotopes detected.

Sr = Detector sensitivity factor (CPM/pCi/ml). (Sensitivity based on Cs-137).

CmA = Maximum allowable concentration in discharge header (pCi/ml).

B , = Background (CPM)

The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0.- It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint. -

• I.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 66 OF 134 1.2 Airborne Effluents There are three air effluent discharge pathways at the Fort Calhoun Station:

Condenser Offgas, Laboratory and Radioactive Waste Processing Building Exhaust Stack, and the Auxiliary Building Exhaust Stack. An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and.

controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5.

• Auxiliary Building - The Auxiliary Building Exhaust Stack receives discharges from the waste gas decay tanks, containment purge, containment vent systems and the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and iodine and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble gas monitoring and iodine and particulate sampling is provided by RM-052. Ventilation Isolation Actuation Signal (VIAS) is actuated by exceeding a monitor's alarm setpoint. Actuation of VIAS will isolate releases from containment and waste gas decay tanks. The Auxiliary Building Exhaust fans will remain in operation.

• Laboratory and Radioactive Waste Processing Building (LRWPB) - Noble gas monitoring and particulate and iodine sampling is provided by RM-043. This radiation monitor/sampler does not serve a control function.

• Condenser Off-Gas Monitors - Noble gas activity is monitored by RM-057. The condenser off-gas is discharged directly to the environment. Exceeding the high alarm setpoint on RM-057 will activate isolation of main steam to the Auxiliary Steam System.

Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.

The airborne effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than the concentrations specified _

in 10 CFR Part 20, Appendix B, Table 2, Column 1.

The airborne effluent monitoring instrumentation HIGH ALARM setpoints shall be -

established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than 5 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 67 OF 134 1.2.1 Airborne Effluent Radiation Monitors A. Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)

Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing thr6ug"h a particulate filter. and charcoal cartridge. The monitor controls airborne releases so that five'times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.OE-07 pCi/cc, based upon Xe-I 33, is not exceeded.

The Ventilation Isolation Actuation Signal is initiated when the high alarm setpoint is reached.

The following calculations for maximum release rate and alarm setpoint

-are valid when Auxiliary Building Exhaust Stack is the only airborne release pathway. For simultaneous airborne releases from Auxiliary Building Exhaust Stack, Condenser Off-gas and the LRWPB Exhaust Stack, refer to Section 1.3.

The maximum allowable release rate for stack airborne activity is calculated as follows:

Ram ,uCi/sec =.5E-06 pCi/cc x 1.OE+06 cc/rn xIQ sec/rn' Where:

2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).

x/Q sec/M3 = Annual average dispersion factor at the unrestricted area boundary from ODCM Part IITable 4 I .OE+06 cc/im' = Constant of unit conversion.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 69 OF 134 1.2.1 B. Condenser Off Gas Monitor (RM-057)

This monitor is located in the turbine building and monitors the condenser off-gas. The purpose of this monitor is to monitor the condenser off-gas discharges so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.OE-07 pCi/cc, based upon Xe-133, is not exceeded.

The following calculations for maximum release rate and alarm setpoint are valid when condenser off-gas is the only airborne release pathway.

For simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.3.

The maximum allowable release rate for condenser air ejector monitor is as follows:

Rmx pCl/sec = 2.5E-06 pCi/cc x I.OE+06 cc/m3 xIQ sec/m Where:

2.5E-06 piCVcc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).

X/Q sec/m 3 = Annual average dispersion factor at the unrestricted area boundary from ODCM Part II, Table 4 1.OE+06 cc/mr3 = Constant of unit conversion.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 68 OF 134 1.2.1A The High Alarm Setpolnt (CPM):

Stnt7 f( (RMAX) (S.) (60) B Setpoint [7 (Fv) (28317) Bj Where:

0.75 = An administrative correction factor which includes the

• following:

15% tolerance to ensure radmonitor VIAS response in

- accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.

10% tolerance to allow for the contribution of noble gases other than Xe-1 33 towards the total ECL fraction sum.

Sf = Detector sensitivity factor (CPMIpCi/cc). (Sensitivity based on Xe-133) 60 = Conversion (seconds to minutes).

28317 = Conversion factor (ft3 to cc).

Fv = Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum'flow rate is 122,500 cfm for 3 Auxiliary Building exhaust fans and 2 containment purge fans in operation.

Other flow rates may be used, as required.)

RKUx = Maximum Allowable Release Rate in pCisec B = Background (CPM)'

The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that'significant increases in activity will be identified, prior,to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint and VIAS actuation.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 70 OF 134 1.2.1 B The High Alarm Setpoint (CPM):

Set point = 0.75 (Rm~x) (S,) (60) +

ll(Fv) (28317)) l Where:

0.75 = An administrative correction factor which includes the following:

15% tolerance to ensure radmonitorVIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.

10% tolerance to allow for the contribution of noble gases other than Xe-1 33 towards the total ECL fraction sum.

Sf = Detector sensitivity factor (CPM/pCi/cc). (Sensitivity based on Xe-1 33) 60 = Conversion (seconds to minutes).

28317 Conversion factor (ft3 to cc).

Fv = Vent stack flow rate (SCFM). Default maximum flow rate is 4,755 scfm (3 vacuum pumps in hogging mode. Other flow rates may be used, as required.)

RMA = Maximum Allowable Release Rate in pCi/sec.

B = Background (CPM)

The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint and tripping of the auxiliary steam supply valve, RCV-978.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 71 OF 134 1.2.1 C. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Iodine and Particulate Sampler (RM-043)

RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-1 33 at the unrestricted area boundary:

The following calculations for maximum release rate and alarm setpoint are valid when the LRWPB Exhaust Stack is the only airborne release pathway. For simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.3.

The maximum allowable release rate for RM-043 is as follows:

RamppCilsec = 2.5E-06 pCi/cc x 1.0E+06 cc/M3 x/Q seC/rn 3 Where:

2.5E-06 pCi/cc 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-1 33).

X/Q Annual average dispersion factor at the unrestricted area boundary from the ODCM Part II, Table 4 1.OE+06 cc/M 3 = Constant of unit conversion R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 72 OF 134 NOTE: This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of the alarm.

1.2.IC The High Alarm Setpoint (CPM): _

Setpoint =

[(

0.75 X(RMAX) (S.) (60)

(Fv) (28317) J 1

j Where:

0.75 = An administrative correction factor which includes the following:

15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.

10% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.

S. = Detector sensitivity factor (CPM/pCi/cc). (Sensitivity based on Xe-1 33) 60 = Conversion (seconds to minutes).

28317 = Conversion factor (ft3 to cc).

Fv = LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.)

RmA,, = Maximum Allowable Release Rate in pCi/sec.

B = Background (CPM)

The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 73 OF 134 1.3 Simultaneous Release Pathways NOTE: If the annual average X/Q value exceeds 1.4E-04 sec/M 3 ,

consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.OE-09 pCi/ml at the unrestricted area boundarywith 10% vapor/liquid separation. Contact the Supervisor-System Chemistry for further instructions.

1.3.1 Liquid Release Pathways The liquid radiation monitors (RM-054A/054B and RM-055) control liquid releases so that ten times the 10 CFR Part 20 limit of 1.OE-06 PCimI for unidentified isotopes at site discharge is not exceeded. There are two liquid release pathways that contribute to the concentration at site discharge.

These are Steam Generator Blowdown and Monitor Tank Overboard Discharge Header. When more than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.1.1 so that unrestricted area concentration limits are not exceeded.

The calculations for the alarm setpoints for the liquid effluent monitors will be adjusted as follows:

CT= KOCMAX, + KI CMAXI C KO (1.OE-05 pCilmo (F) + K1 (1.OE-05 pCilmf) (F) fo fl Where:

Cr = Sum of individual maximum allowable concentrations for Steam Generator and Monitor Tank prior to dilution for simultaneous liquid releases (pCVml)

"CMAM =' Maximurm allowable concentration in Steam Generator blowdown Line (pCi/ml)

CMAI = Maximum allowable concentration in Monitor Tank Discharge Line (pCi/ml)

K0 = Allocation factor for Steam Generator (See Table 1)

K, = Allocation factor for Monitor Tank (See Table 1)

F = Total dilution flow in Discharge Tunnel (GPM) f0 = Steam Generator Blowdown flowrate (GPM) f, = Monitor Tank Discharge flowrate (GPM)

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 74 OF 134 1.3.1 The High Alarm Setpoint for Steam Generator Blowdown monitors, RM-054AN054B, will then be:

Alarm Setpoint (CPM) = 0.75 [(Ko Sf, Cm.4) + BO]

The High Alarm Setpoint for Monitor Tank Discharge Monitor, RM-055, will then be:

Alarm Setpoint (CPM) = 0.75 [(K S, CMAx) + B1J]

Where:

SfO = Detector Sensitivity factor for RM-054A/054B, CPM/(pCi/ml),

based on Cs-137.

S. = Detector Sensitivity factor for RM-055, CPM/(pCi/ml), based on Cs-1 37.

CMAO = Maximum allowable concentration in S/G Blowdown line.

(pCi/ml)

CMI = Maximum allowable concentration in MT Discharge line.

(pCVmI)

Bo RM-054A/054B background countrate. (CPM)

B. = RM-055 background countrate. (CPM)

K(, K, = Allocation factors. See Table 1.

The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 75 OF 134 1.3.2 Airborne Release Pathway The noble gas radiation monitors (RM-043, RM-057, and RM-062/RM-052) control airborne releases so that five times the 10 CFR Part 20 limits of 5.OE-07 pCi/cc for noble gases at the unrestricted area boundary is hot' exceeded. There are three pathways that contribute to the concentration at the unrestricted area boundary. These are the Auxiliary Building Exhaust-,

Stack, Condenser Off-gas, and the LRWPB Exhaust Stack. When more than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.1.1 to ensure that unrestricted area concentration limits are not exceeded.

The calculations for the alarm setpoints for the liquid effluent monitors will be adjusted as follows:

The maximum allowable release rates for simultaneous releases is:

3 3 Max. Release Rate = iKRmfx, = Ki 2C5E-06 uCl/cc I-i I-I x/Q sec/n Where:

Rm.) - RM-062/RM-052 release rate (pCVsec)

Rmus = RM-057 release rate (OCi/sec)

RMA = RM-043 release rate (pCi/sec)

X/Q Annual average dispersion factor at the unrestricted area boundaryfrom the ODCM Part II,Table 4 K,5- K3 = Allocation'factors. See Table 1.

2.5E-06 pCYicc = 5 timers'the 10 CFR Part 20 Limit at the unrestricted area boundary based upon Xe-133).

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 76 OF 134 1.3.2 The maximum release rate RmAx then:

(K,) (2.5E-06 pCi/cc) (K2) (2.5E-06 tjCiICc) ((K3) (2.5E-06 pCi/cc) 1.OE 06 cc R w x/Q sec/M3 x/Q sec/M3 xIQ sec/Mr 3 1E0 -

The High Alarm Setpoints for the noble gas monitors will then be:

RM-062/052 = 0.75 F( (RM~x) (Sf)(60)

K, Fv (28317) ) B 1

RM-057 = 0.75 K2 (RmAx) (St)(601) +BI RM-043 = 0.75 [(K3 (FR.)(28317)) + ]

Where:

0.75 = An administrative correction factor which includes the following:

• 15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.

• 10% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.

K, - K3 = Allocation factors. See Table 1.

Sf = Detector sensitivity factor.

Fv = Vent stack flowrate. (Condenser off-gas flowrate for RM-057, LRWPB Exhaust stack flow rate for RM-043, Auxiliary Building Exhaust Stack flow rate for RM-0621052).

RMAX = Maximum Allowable Release Rate in pCi/sec.

B = Monitor background count rate.

60 = Constant of unit conversion (60 seclmin).

The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 77 OF 134 Table I - Allocation Factors for Simultaneous Releases NOTE: The Fort Calhoun Station is capable of performing simultaneous airborne releases. The factors below may be adjusted to meet release requirements, provided that the sum of the Unrestricted Area Fraction Sum for all airborne releases remains less than or equal to 1.0. -

A. Allocation Factors for Simultaneous Airborne Releases

1. Auxiliary Building Exhaust Stack Total: 0.8C K, Noble Gases (RM-062 or RM-052) 0.7C lodine/Particulate/Tritium 0.1C Contributing Pathways:

a) Auxiliary Building 0.10 b) Containment Building 0.65 c) Waste Gas Decay Tanks 0.05

2. Condenser/Off Gas Total: 0.1CI K2 Noble Gases (RM-057) 0.05 Tritium 00 Contributing Pathways:

a) Condenser Off Gas 0.10

3. Laboratory and Radioactive Waste Building Exhaust Stack Total: 0.1CI k3 Noble Gases (RM-043) 0.05 Iodine/Particulate 0.0Oi Contributing Pathways:

a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airborne Release Total 1.00 NOTE: The Fort Calhoun Station is capable of performing simultaneous liquid releases. The factors below may be adjusted to meet release requirements provided that the sum of the Unrestricted Area Fraction Sum for all liquid releases remains less than or equal to 1.0.

B. Allocation Factors for Simultaneous Liquid Releases

1. K0 Steam Generator Releases  ! (RM-054A/054B) 0.30

2. K, Waste Liquid Releases (RM-055) 0.70 Liquid Release Total 1.00 R13

- - -- l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 78 OF 134 Figure 1 - Exclusion and Site Boundary Map K _ _ _- _ __ _ - _- _

Site N_

IOWA N I

\

I UNRESTRICTED a \

AREA BOUNDARY  %

I-'BRASKA \ ~RESTRICTED XAREA@

I NI MET FORT CALHOUN TOWER UNIT # 1 I

I l

`-ADMIN.

BLDG.

-TRAINING CENTER

/ UNRESTRICTED I AREA

( LIQUID EFFLUENTS DISCHARGE N (O AIRBORNE EFFLUENTS DISCHARGE " TO OMAHA 0 1(2 1 I I SCALE IN MILES EXCLUSION AND SITE BOUNDARY MAP R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 79 OF 134 Figure 2 - Liquid Radioactive Discharge Pathways "i RM-054A (I RM-0548

( RM-055 LIQUID RADIOACTIVE DISCHARGE PATHWAYS R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 80 OF 134 Figure 3 - Liquid Radioactive Waste Disposal System AUXIEIARY SYSTEMS REACTOR WASTECOOLANT PROCESS WASTE WASTEorr HOTEL WASTE Flor Drains Ecppwnt Brans Laundrg Waste Sump Flows RCLoop Oroains Shoaer rains Spent

• Vt

• o.

8aens ~ > Tanks liiTarks 553i cal. ( 1) 45,809 Gl. c 12e9 Cal.

I I I Waste Filtars 17 50 Merrons Oesmnralizer isisels 1 I6 Cu. Ft.

Owcoal Filter OOMo 6SCu. Ft.

(optional)

Tanks 6779 Cal.

Overboard Header Ito Riverl LIOUID RADIOACTIVE WASTE DISPOSAL SYSTEM R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 81 OF 134 Figure 4 - Airborne Effluent Discharge Pathways g RM-043 Noble Gas Monitor, and--

.Iodine & Particulate Sampler I

I I-LRWPB Laboratory LABORATORY AND RADIOACTIVE -WASTE PROCESSING BUILDING RM-062,052 Noble- Gas Monitor Iodine & Particulate Sampler I

RM-057 Noble Gas Monitor I .

CONDENSER OFFGAS  ; AUXILIARY BU1I LDING EXHAUST STACK Condenser .Al auxiliary Building Containment Ventilation Building Ventilation AIRBORNE - EFFLUENT DISCHARGE PATHWAYS -

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 82 OF 134 Figure 5 - Airborne Radioactive Waste Disposal System S.G.

Gas Holdup Tanks (4)

AIRBORNE RADIOACTIVE WASTE DISPOSAL SYSTEM R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL ;REFERENCE USE PAGE 83 OF 134

2. EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be'limited to the concentrations as specified'in 10 CFR Part 20, Appendix B; Table 2, Column 2. For batch releases (Monitor and Hotel' '

Waste Tanks and Steam Generators) and for continuous releases (Steam Generator Blowdown), the analyses will be performed in accordance with Part I, Table 3.1, and the concentration of each radionuclide at site discharge will be calculated, based on the following equation:

Radionuclide concentration at she discharge:

a, f i +f and E ,iwec,

1 Where:

Ai = concentration at site discharge for radionuclide (i), in pCilml.

a, = concentration of radionuclide (i) in the undiluted effluent, in PCimI.

f = undiluted effluent flowrate, in gpm.

F total diluted effluent flowrate in gpm.

weci = water effluent concentration limit for radionuclide (i) per 10 CFR Part 20, Appendix' B, Table 2, Column 2.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 84 OF 134 NOTE: In addition to the above defined method, Notes I through 4 of 10 CFR Part 20, Appendix B, will also be applicable.

2.2 Airborne Effluent Concentrations The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than Appendix B, Table 2, Column 1, values.

Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed:

To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used:

Ai = Ko Q. (X/Q) n Ai and A, 1 sir ECL, Where:

A, = Concentration of radionuclide (i) at the unrestricted area boundary K0 = Constant of unit conversion. (I.OE-6 m3 /cc)

ECLI = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(i))

Qj = The release rate of radionuclide (i) in airborne effluents from all vent releases (in pCi/sec.)

(X/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from ODCM Part II, Table 4 As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack, Laboratory and Radwaste Building Stack and condenser off gas will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20. Monitor indications (readings) may be averaged over a tme period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airborne effluent dose rate.

For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR Part 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 85 OF 134

3. RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Effluent Dose Calculations Three pathways for human exposure to liquid releases from FCS to the Missouri'River exists: 1) fish, 2) drinking water, and 3) Shoreline deposition. Fish are considered to be taken from the vicinity of the plan't discharge. The drinking water for Omaha is-'

located 19 miles downstream from FCS. The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be <14% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give the dose to an

-individual in unrestricted areas.

10 CFR Part 50, Appendix I restricts the dose to individuals in the unrestricted areas

-from radioactive materials in liquid effluents from the Fort Calhoun Station to the following limits:

• during any calendar quarter

<1.5 mrem to total body

<5.0 mrem to any organ and

• during any calendar year

< 3.0 mrem to total body

< 10.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.  ; -

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 86 OF 134 3.1.1 Doses from Liquid Effluent Pathways A. Potable Water Rap = 1100 ap F

X

=

QjD 8 jPjexp(-AXtP)

Where:

Rapj = is the total annual dose to organj) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem/yr.

Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in 9/yr. (Table 6)

MP = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless. (Table 17)

F = is the flow rate of the liquid effluent, in W/ sec.

Q. = is the annual release rate of radionuclide (i), in Ci/yr.

Dalpj = is the dose factor specific to a given age group (a),

radionuclide (i), pathway (p), and organ (j) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16)

Ai = is the radiological decay constant of radionuclide (i), in hr'.

tP = is the average transit time required for radionuclides to reach -

the point of exposure. For internal dose, tP is the total time elapsed between release of the radionuclides and ingestion of water, in hours. (Table 17) 1100 = Constant (pCi

• yr

• ft3/Ci

• sec

• L)

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL' REFERENCE USE PAGE 87 OF 134 3.1.1 B. Aquatic Foods Rapj = 1100 Uap j QB D8,exp(-4,t)-

F ii [P Where:

Rap = is the total annual dose to organ U)of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem/yr.

UOP = is a usage factor that specifies the Intake rate for an individual of age group (a) associated with pathway (p), in kg/yr.

(Table 6)

MP = is the mixing ratio (reciprocal of the dilution factor) at the point

-of harvest of aquatic food, dimensionless. (Table 17)

F = is the flow rate of the liquid effluent, in ft3 /sec.

Qj = is the annual release rate of radionuclide (i), in Ci/yr.

Bp' = is the equilibrium bioaccumulation factor for radionuclide (i) in pathway (p) expressed as the ratio of the concentration in biota (in pCikg) to the radionuclide concentration in water (in pCi/liter), in (pCilkg)/(pCilliter). (Table 3)

Daipi = is the dose factor specific to a given age group (a),

radionuclide (i), pathway (p), and organ 0), which can be used to calculate the' radiation dose from an intake of a radionuclide, in mremlpCi. (Tables 13-16)

Al =is the radiological decay constant of radionuclide (i), in hr'.

tP = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of food; in hours. '(Table 17) 1100 = Constant (pCi yr* ft3/Ci

• sec* L)

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1_

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 88 OF 134 3.1.1 C. Shoreline Deposits Rap 110=000 F QjTjpDip 1[exp(-AjtP)1[1-exp(-Ajtb)I Where:

Raps = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem/yr.

Uap = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p), in hrlyr. (Table 6)

MP = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 17)

W = is the shore-width factor, dimensionless. (Table 17)

F = is the flow rate of the liquid effluent, in ft3/sec.

Q. = is the annual release rate of radionuclide (i), in Ci/yr.

Tip = is the radioactive half life of radionuclide (i), in days.

Daipj = is the dose factor specific radionuclide (i) which can be used to calculate the radiation dose from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the real radionuclide concentration (in pCVm 2). (Table 8)

A1 = is the radiological decay constant of radionuclide (i), in hrW.

tp = is the average transit time required for radionuclides to reach the point of exposure, in hours. (Table 17) tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100

• pCi

• yr

• ft3)/(Ci

• sec

• L)]

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 89 OF 134 3.2 Airborne Effluent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents from the Fort Calhoun Station to the following limits:

• During any calendar quarter

<5 mrad-gamma air dose

<10 mrad-beta air dose and

• During any calendar year

<10 mrad-gamma air dose

<20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:

A. Doses from Noble Gases

1) Annual Gamma/Beta Air Dose from All Other Noble Gas Releases Dy(r,8) or DP(r,8) 3.17 x 104 S Q1,xIQ]D(r.8)(DFY. or DO:)

Where:

DFv,, DFO are the gamma and beta air dose factors for a

. uniform semi-infinite cloud of radionuclide (i),

in mrad-m 3 /pCi-yr. (Table 2)

Dv(r,d) or DO(r,6) - are the annual gamma and beta air doses at distance r, in the sector at angle e, from the discharge point, in mrad/yr.

Q. ~ is the annual release rate of radionuclide (i),

in Ci/yr.

[X/Q]D(r,) = is the annual average gaseous dispersion factor at distance r, in the sector at angle 0, in sec/m 3 . (Table 4) 3.17x104 = is the number of pCi per Ci divided by the number of seconds per year.

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I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 90 OF 134 3.2.1A 2) Annual Total Body Dose from All Other Noble Gas Releases Tn DT(r,8) = x(r,8)DFB_

Xi Where:

DFB, = is the total body dose factor for a semi-infinite cloud of the radionuclide (i), which includes the attenuation of 5 g/cm2 of tissue, in mrem-m 3 /pCi-yr. (Table 2)

Di (r,B) =is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle 0, in mrem/yr.

Xi(r,O) = is the annual average ground-level concentration of radionuclide (i) at distance r, in the sector at angle 0, in pCi/M3 . (Table 4)

S. =Shielding Factor (Table 17)

3) Annual Skin Dose from All Other Noble Gas Releases T n D,(r, ) = 1.11 Sax X1(r,8)DF'. + E x1(r,8)DFS, I.1 I-I Where:

DI(r,O) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle e, in mrem/yr.

DFS, = is the beta skin dose factor for a semiinfinite cloud of radionuclide (i), in mrem-m 3 /pCi-yr. (Table 2) 1.11 = is the average ratio of tissue to air energy absorption coefficients.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 91 OF 134 3.2.2 Radioiodine, Tritium, and Particulates 10 CFR Part 50, Appendix Irestricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to: .

• During any calendar quarter

<7.5 mrem to any organ and

• During any calendar year

<15 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas should be determined by the following expressions:

Radioiodine, Tritium, and Particulates (continued)

NOTE: In all cases, for releases of tritium, use the dispersion parameter for inhalation (XIQ).

A. Annual Organ Dose from External Irradiation from Radioactivity Deposited on the Ground Plane The ground plane concentration of radionuclide (i) at distance r, in the sector at angle e,with respect to the release point, may be determined by:

Cq(r.) [1Ox1O¶2] 6/r.6)Q1 [1 -exp(-Atb)]

Where:

= is the ground plane concentration of the radionuclide (i) at distance r, in the sector at angle 0, from the release point, in pCilm2 .

-Q, = is the annual release rate of radionuclide (i) to the atmosphere, in Cl/yr.

tb = is the time period over which the accumulation is evaluated, which is assumed to be 15 years (mid-point of plant operating life). (Table 17) 6^(r,6) is the annual average relative deposition of radionuclide (i) at distance r, in the sector at angle 0, considering depletion of the plume by deposition during transport, in m2 . Table 4 AX is the radiological decay constant for radionuclide (i), in yrl.

1.0x1 012 = is the number of pCi/Ci R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 92 OF 134 3.2.2A The annual organ dose is then calculated using the following equation:

D 6) = 8760 Sf C (r, B)DFGij I.'

Where:

C (r,e) is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle 0, in pCi/m 2.

DFG4 = is the open field ground plane dose conversion factor for organ d) from radionuclide (i), in mrem-m 2 /pCi-hr. (Table 8)

Dy(r,e) = is the annual dose to the organ 0) at distance r, in the sector at angle 6, in mrem/yr.

Sf = is the shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless. (Table 17) 8760 = is the number of hours in a year B. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide (i) at distance r, in the sector at angle 0, with respect to the release point, may be determined as:

X,(r8) = 3.17 x 104 Qj[XjQ]D(r,9)

Where:

Q. = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.

xi(r.6) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle 6,in pCi/M 3.

X/Q]D(r8) = is the annual average atmosphere dispersion factor, in sec/M 3 (see Reg Guide 1.111). This includes depletion (for radioiodines and particulates) and radiological decay of the plume. (Table 4) 3.17x104 = is the number of pCi/Ci divided by the number of sec/yr.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 93 OF 134 3.2.2B The annual dose associated with inhalation of all radionuclides to organ

() of an individual in age group (a), is then:

D. (r.) = R. X Xi (r.6{) DFA~a -

Where: '~

DW(r,B) = is the annual dose to organ () of an individual in the age group (a) at distance r, in the sector at angle 6, due to inhalation, in mrem/yr.

Ra = is the annual air intake for individuals in the age group (a),

in ml/yr. (Table 6)

DFAija = is the inhalation dose factor for radionuclide (i), organ (j),

and age group (a), in mrem/pCi. (Tables 9-12) 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A. Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium C'(rB) - drB) (( - XP(-AE/.)1 + [ - exp(-A/b))) exp(-A/)

I YAEI A Where:

Cv(r,0) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle 0, in pCi/kg.

di(r,6) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle 0, in pCi/M 2 hr.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 94 OF 134 3.2.3A The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6):

d#(r,G) = 1.1 x 10 86,(rO)Q, Where:

d,(r,B) = is the deposition rate of radionuclide (i).

5,(r,B) = is the relative deposition of radionuclide (i), considering depletion and decay, in mr2 (see Reg Guide 1.1 11).

(Table 4) 1.1 x1 o8 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760).

Q. = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 95 OF 134 3.2.3 B. For radioiodines, the model considers only the elemental fraction of the effluent:

d#(r,B) = 3.3 x i10 6,(r,B) Q, Where:

d, (r, 0) = The deposition rate of radioiodine (i).

3.3 x 107 = The number of pCVCi (11O2) divided by the number of hours per year (8760), then multiplied by the amount of radioiodine emissions considered to be elemental (0.5).

5, (r, 0) = The relative deposition of radioiodine (i), considering depletion and decay, in mi2 . (Table 4)

Q. = The total (elemental and nonelemental) radioiodine (i) emission rate.

r = is the fraction of deposited activity retained on crops, dimensionless. (Table 17)

AM = is the effective removal rate constant for radionuclide (i) from crops, in hrW.

XEi =)+AS -

X, = 0.0021/hr. (Table 17)

= is the time period that crops are exposed to contamination during the growing season, in hours. (Table 17)

Y., = is the agricultural productivity (yield) in kg (wet weight)/m 2 .

(Table 17) 13^, = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi! kg (wet weight) per pCikg dry soil. (Table 5)

= is the radiological decay constant of radionuclide (I), in hr1 tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life).

(Table 17)

P = is the effective 'surface density" for soil, in kg (dry soil)/m2 .

(Table 17) th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours. (Table 17)

Different values for the parameters te Y,, and t,, may be used to allow the use of the Equation for different purposes: estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle or goats. See Table 17.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 96 OF 134 3.2.3 C. Parameters for Calculating the Concentration of Radionuclide (i) in the Animal's Feed (Milk Cow, Beef Cow, and Goat)

C1(r,8) = f8 pL(r.8) - (1 - fC(r,0) + f (1-f )CS(r,8)

Where:

C, (r,G) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.

Cjr,6) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3C with th=O), in pCi/kg.

C~(r,E) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3C with th=90 days), in pCi/kg.

fp = is the fraction of the year that animals graze on pasture.

(Table 17)

f. = is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17) 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk C i(rO) = FmCi(r,8)QF exp(-Af)

Where:

C' (rO) = is the concentration of radionuclide (i) in milk, in pCilliter.

C' (rG) = is the concentration of radionuclide (i) in the animal's feed, in pCilkg.

Fm = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter.

(Table 5)

QF is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tf = is the average transport time of the radionuclide (i) from the feed to the milk and to the receptor (a value of 2 days is assumed). (Table 17)

AI = is the radiological decay constant of radionuclide (i), in days".

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 97 OF 134 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium

-CF(r,8)= FCV(r,8)QF exp(-At,) .

Where:

C' (r,O) = is the concentration of radionuclide (i) in meat, in pCi/liter.

Ff = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each kilogram of flesh, in days/kilogram. (Table 5) t is the average time from slaughter to consumption. (Table 17) 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.

CV(r,8) = 317 x 10 7 QI VQj (r'8) (0.75) (0.5) = 1.2 x 107 Q (xIQ] (V.8)

T 1H H Where:

CT(r, e) - is the concentration of tritium in vegetation grown at distance r, in the sector at angle 6, in pCUkg.

H = is the absolute humidity of the atmosphere at distance r, in the sector at angle 0, in g/m3 . H=8 gm/kg.

QT = is the annual release rate of tritium, in Ci/yr.

Ex

/Q](r,G) = is the atmospheric dispersion factor, in sec/M 3 . (Table 4) 0.5 = is the ratio of tritium concentration in plant water to tritium

• concentration in atmospheric water, dimensionless.

0.75 = is the fraction of total plant mass that is water, dimensionless.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 98 OF 134 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ () of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by:

Dja( ) = iDFI1 [UVf.C'(rt9) + UMLCAM(re) LfC(ro) + UtfC(re)

Where:

DP (r,B) = is the annual dose to organ 0) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr.

DFIjua = is the dose conversion factor for the ingestion of radionuclide (i), organ 0), and age group (a), in mrem/pCi.

Tables 13-16.

Uv., U, = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains); milk, meat, and leafy UaUt; vegetables, respectively for individuals in age group (a). (Table 6) fg = Fraction of ingested produce grown in garden of interest (Table 17) f, = Fraction of leafy vegetables grown in garden of interest (Table 17)

B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce)

Vegetation for Radionuclide (i) to Each Organ 0) and Age Group (a)

DP(r.8) - DF4Jp [UlfCL(r, ) . Uvf. vyrm]

la L a' Uafg ir.

Where:

D',(r,B) = is the annual dose from the ingestion of radionuclide (i) to organ (j) of an individual in age group (a)from dietary intake of atmospherically released radionuclides in vegetation, in mrem/yr.

DFIIja = is the dose conversion factor for the ingestion of radionuclide (i),organ 0), and age group (a), in mrem/pci.

Tables 13-16 UaLUV = are the ingestion rates of leafy vegetables and produce (non-leafy vegetables, fruits, and grains), for individuals in age group (a), in kg/yr. (Table 6)

C'L = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.

CVi = is the concentration of radionuclide (i) in and on produce, in pCi/kg.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 99 OF 134 3.2.7 C. Calculation Determinina the Inaested Dosse from Cow Milk for Radionuclide (i), Organ (j), and Age Group (a)

VDj(r1 6) - DF6#Ib[ '(r)]

Where:

D (r,B) = is the annual dose from the ingestion of radionuclide (i),

organ (j) of an individual in age group (a)from dietary intake of atmospherically released radionuclides in cow milk, in mremlyr.

DFI 5a is the dose conversion factor for the ingestion of radionuclide (i), organ 0), and age group (a), in mrem/pCi.

(Tables 13-16)

Um is the ingestion rate of cow milk for individuals in age group (a), in 0Iyr. (Table 6) is the radionuclide concentration in cow milk, in pCi/kg.

Equation 3.2.4 D. Calculation Determining the Ingested Dose from Meat for Radionuclide (i) to Organ (j) and Age Group (a)

D - (rG) -DF~g [aCr0)]

Where:

Dd(r,G) = is the annual dose from the ingestion of radionuclide (i),

organ 0) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr.

DFIja = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mremlpCi.

(Tables 13-16) uF

- is the ingestion rate of meat for individuals in age group (a),

in kg/yr. (Table 6)

= is the radionuclide (i) concentration in meat, in pCUkg.

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I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 100 OF 134

4. LOWER LIMIT OF DETECTION (LLD)

The lower limit of detection (LLD) for liquid and airborne effluent discharges and environmental samples referenced in Part I, Tables 3.1, 3.2, and 4.3 is defined as the v smallest concentration of radioactive material in a sample that will yield a net count, abbve system background, that will be detected with 95 percent probability with only 5 percent 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

• V

• D

• Y

• exp(-A^t Where:

LLD= the lower limit of detection as defined above, in either picoCuries or microCuries, per unit mass or volume as a function of the value of D Sb= the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute E = the counting efficiency, as counts per disintegration V = the sample size in units of mass or volume D = 2.22E+06 of disintegrations per minute per microCurie or 2.22 disintegrations per minute per picoCurie Y = the fractional radiochemical yield, when applicable A = the radioactive decay constant for the particular radionuclide a&t = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and at should be used in the calculation.

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

LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation at the LLD values for the specific type of analysis required. They will be performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample.

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 101 OF 134 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Nuclide P-Air' (Dft) lP-Skin2 (DFS,) y-Air` (Df() y-Body2 (DFB,)

Kr-83m -2.88E-04 l 1.93E-05 .7.56E-08 Kr-85m 1.97E-03 1.46E-03 i .23E-03 1.17E-03 Kr-85 1.95E-03 , 1.34E-03 1.72E-05. 1.61 E-05 Kr-87 -- 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 I .47E-02 Kr-89 1.06E-02 1.01 E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131 m 1.1IE-03 4.67E-04 1.56E-04 9.15E-05 Xe-133m ' 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 - 7.1 E-04 3.36E-03 - 3.12E-03 Xe-135 2.46E-03 -1.86E-03.- 1.92E-03 1.81 E-03 Xe-1 37 1.27E-02 1.22E-02 1.51 E-03 1.42E-03

, Xe-138- 4.75E-03 4.13E-03' 9.21 E-03 8.83E-03

. Ar-41 -3.28E-03 .2.69E-03 9.30E-03 "8.84E-03 I mrad- m3 -.

Pci - yr. -

2 mrem - m

• .. .pCi - yr 3 - 2.88E-04 = 2.88 x 104 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 102 OF 134 Table 3 - Bioaccumulation Factors (pCi/kg per pCi/liter)

FRESHWATER Element Fish Invertebrate H 9.OE-01 9.OE-01 C 4.6E+03 9.1 E+03 Na 1.0E+02 2.OE+02 P 1.OE+05 2.0E+04 Cr 2.OE+02 2.0E+03 Mn 4.OE+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.OE+01 2.0E+02 Ni 1.OE+02 1.OE+02 Cu 5.0E+01 4.OE+02 Zn 2.OE+03 1.0E+04 Br 4.2E+02 3.3E+02 Rb 2.OE+03 1.OE+03 Sr 3.OE+01 1.OE+02 Y 2.5E+01 1.OE+03 Zr 3.3E+00 6.7E+00 Nb 3.OE+04 1.OE+02 Mo 1.OE+01 1.OE+01 Tc 1.5E+01 5.OE+OO Ru 1.OE+01 3.OE+02 Rh 1.OE+01 3.OE+02 Te 4.OE+02 6.1 E+03 I 1.5E+01 5.OE+OO Cs 2.OE+03 1.OE+03 Ba 4.OE+00 2.OE+02 La 2.5E+01 1.0E+03 Ce 1.OE+00 1.0E+03 Pr 2.5E+01 1.OE+03 Nd 2.5E+01 1.OE+03 W 1.2E+03 1.OE+01 Np 1.OE+01 4.OE+02 R13

FORT CALHOUN STATION it CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 103 OF 134 Table 4 - Highest Potential Exposure Pathways for Estimating Dose NOTE: The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating dose.

Location Direction - Distance Q D/Q Exposure Pathway 2 2 from (rG) 22 Containment { r,) { r,)

__ _ __ __ _ __ _ _ _ _ _ (m iles) 2 (seclmn3) (m 2)

Direct Exposure Site WNW 0.70 1.04E-05 N/A Boundary Inhalation Site WNW 0.70 1.04E-05 N/A Boundary Ingestion Residence SSE 0.94 N/A 2.6 E-08 I 1 These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 2 year average, updated only upon a +10% change from the previous value. Ten percent (10%)

should be added to these values for dose estimates during the reporting periods.

2 The location is subject to change based on an annual evaluation and Is'utilized only for ingestion exposure pathway dose estimates. This location may differ from the highest ingestion exposure pathway for offsite air monitoring locations as determined by the Land Use Survey performed biennially In accordance with Part 1, Section 6.32.

R13

I

\_1 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 104 OF 134 Table 5 - Stable Element Transfer Data BN . Fm (cow) F, Element Veg./Soil Milk (d/l) - Meat (d/kg)

H 4.8E+00 1.0E-02 1.2E-02 C 5.5E+00 1.2E-02 3.1 E-02 Na 5.2E-02 4;OE-02 3.OE-02 P 1.1 E+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.OE-04 Fe 6.6E-04 1.2E-03 4.OE-02 Co 9.4E-03 1.OE-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.OE-03 Zn 4.OE-01 3.9E-02 3.OE-02 Rb 1.3E-01 3.OE-02 3.1 E-02 Sr 1.7E-02 8.OE-04 6.OE-04 Y 2.6E-03 1.0E-05 4.6E-03 Zr 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.OE-03 Tc 2.5E-01 2.5E-02 4.OE-01 Ru 5.OE-02 1.OE-06 4.OE-01 Rh 1.3E+1 1.OE-02 1.5E-03 Ag 1.5E-01 5.OE-02 1.7E-02 Te 1.3E+00 1.OE-03 7.7E-02 I 2.OE-02 6.OE-03 2.9E-03 Cs 1.OE-02 1.2E-02 4.OE-03 Ba 5.OE-03 4.OE-04 3.2E-03 La 2.5E-03 5.OE-06 2.OE-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.OE-06 4.7E-03 Nd 2.4E-03 5.OE-06 3.3E-03 W 1.8E-02 5.OE-04 1.3E-03 Np 2.5E-03 5.OE-06 2.OE-04 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 105 OF 134 Table 6 - Recommended Values for U to Be Used for the Maximum Exposed Individual in Lieu of Site -Specific Data Pathway Infant Child - Teen .Adult Fruits, vegetables, & grain (kg/yr) . 520 630 520 Leafy vegetables (kglyr) 26 42 -64 Milk (Q/yr) 330 330 400 310 Meat & poultry (kglyr) 41 65 -110 Fish (fresh or salt)(kg/yr) -- 6.9 16 21 Other Seafood (kg/yr) _ 1.7 3.8 5 Drinking water (Q/yr) 330 510 510 730 Shoreline recreation (hr/yr) 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAW Water (#/day)

Milk Cow 50 60 Beef Cattle - 50 50 Goats 6: 8 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 106 OF 134 Table 8 - External Dose Factors for Standing on Contaminated Ground (mremlhr per pCilm2 ) Page 1 of 2 ELEMENT TOTAL BODY SKIN H-3:_

C-14 _ _

Na-24 2.50E-08 2.90E-08 P-32 Cr-51 2.20E-10 2 60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.1 OE-08 1.30E-08 Fe-55 Fe-59 8.OOE-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.OOE-08 Ni-63 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.OOE-09 4.60E-09 Zn-69 Br-83 6.40E-11 9.30E-11 k'i Br-84 1.20E-08 I 40E-08 Br-85 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.OOE-09 1.OOE-08 Y-90 2.20E-12 2.60E-12 I' Y-91 M 3.80E-09 4.40E-09 Y-91 2.40E-1 1 2.70E-1 1 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.OOE-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.1OE-09 6.OOE-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.OOE-09 K'

k-I/

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FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 107 OF 134 Table 8 (continued) Page 2 of 2 ELEMENT TOTAL BODY SKIN Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 - :'

- Ru-1 06 -1.50E-09 - 1.80E-09 Ag-110M 1.80E-08 2.1OE-08 Te-125M .' - 3.50E-1 I 4.80E-11 Te-127M 1.10E 1.30E-12 Te-127 1.OOE-11 1.1OE-11

'Te-129M 7.70E-10 9.OOE-10 Te-129 71 0E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 - 2.OOE-09 1-130 , ,I1 AOE-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-48 2.OOE-08 1-133 3.70E-09 4.50E-09 1-134 - - .60E - 1.90E-08 1-135 1.20E-08 iA.40E-08 Cs-134' 1.20E-08 ,' 1.40E-08 Cs-136 ,-_1.50E408_;,=, 1.70E-08 Cs-1 37 4.20E-09 '4.90E-09

- Cs-138 2.10E48 2.40E-08

, Ba-139 2.40E-09 2.70E-09 Ba-140 2.1_0E-09 '_,_2.40E-O9 Ba-141 4.30E-09

• 4.90E-09

' 'Ba-142 ' 7.90E-09 - 9.OOE-09

'La-140 - 1.50E.08 - 1.70E-08 La-142 1.50E-08 1.80E-08

- Ce-141 5.50E-10.-' 6.20E-10

. Ce-143 2.20E-09 2.50E-09 Ce-144- 3.20E-10 . -. . 3.70E-10 -

Pr-143 , _- ,: -_

Pr-144 2.OOE-10 2.30E-10 Nd-147:  ; 1.OOE-09 1.20E-09 W-1B87, 3.10E-09 3.60E-09 Np-239 - - - 9.50E-10 1.1OE-09 R13

I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 108 OF 134 Table 9 - Inhalation Dose Factors for Adult (mrem per pCI Inhaled) Page 1 of 3 Nuclide Bone . Liver T. Body Thyroid Kidney Lung GI-LLI H-3 _ 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 _ 1.08E-05 _

Cr-51 --- 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 _ 4.95E-06 7.87E-07 - 1.23E-06 1.75E-04 9.67E-06 Mn-56 1.55E-10 2.29E-11 - 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 - - 9.01 E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 - - 1.27E-04 2.35E-05 Co-58 1.98E-07 2.59E-07 _ - 1.16E-04 1.33E-05 Co-60 _ 1.44E-06 1.85E-06 _ - 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81 E-06 _ - 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 - 7.OOE-07 1.54E-06 Cu-64 - 1.83E-10 7.69E-1 I 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 _ 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 - 5.27E-12 1.15E-07 2.04E-09 Br-83 _ _ 3.01 E-08 _ _ _ 2.90E-08 Br-84 - - 3.91 E-08 _ _ 2.05E-13 Br-85 - _ 1.60E-09 _ -

Rb-86 _ 1.69E-05 7.37E-06 _ 2.08E-06 Rb-88 4.84E-08 2.41 E-08 _ _ _ 4.18E-19 Rb-89 - 3.20E-08 2.12E-08 _ _ _ 1.16E-21 Sr-89 3.80E-05 _ 1.09E-06 _ _ 1.75E-04 4.37E-05 Sr-90 3.59E-03 _ 7.21 E-05 - _ 1.20E-03 9.02E-05 Sr-91 7.74E-09 _ 3.13E-10 _ _ 4.56E-06 2.39E-05 Sr-92 8.43E-10 _ 3.64E-1 I _ 2.06E-06 5.38E-06 Y-90 2.61E-07 _ 7.1 E-09 - 2.12E-05 6.32E-05 Y-91 M 3.26E-11 _ 1.27E-12 _ _ 2.40E-07 1.66E-10 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 109'OF 134 Table 9 (continued) Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-91 5;78E-05 _ 1.55E-06 _ - 2.13E-04 4.81E-05.

Y-92 1.29E-09 3.7.7E-11 - 1.96E-06 9.19E-06 Y-93 1.18E-08 _ 3.26E-10 l 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06, 6.77E-06 2.21 E-04, 1.88E-05 Zr-97 -1.21 E-08 2.45E-09 - 1.13E-09' 3.71 E-09 9.84E-06 6.54E-05 Nb-95 1.76E 9.77E-07, 5.26E-07 9.67E-07 6.31 E-05, 1.30E-05.

Mo-99 1.51E-08 2.87E-09 3.64E-08 1.14E-05 3.1 OE-05 Tc-99M- 1.29E-13 3.64E-13 4.63E-12 5.52E-12 9.55E-08 5.20E-07 Tc-101 - 5.22E-15 7.52E-15 7.38E-14 - - 1.35E-13 4.99E-08 1.36E-21 Ru-103" 1.91 E-07 - 8.23E-08 _ 7.29E 6.31 E-05 1.38E-05 Ru-105 9.88E-11 - 3.89E-11 - 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64 E-06 - 1.09E-06 -1.67E-05 1.17E-03 1.14E-04 Ag-1I OM. 1.35E-06 1.25E-06 7.43E-07 _ 2.46E-06 5.79E-04 3.78E-05 Te 125M.,4.27E-07. 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M -1.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04' 1.87E-05 Te-127 - i.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M i .22E-06 5.84E-07 -1.98E-07 4.30E-07 4.57E-06 1 .45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 9.61 E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 _ 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 _ 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 _ 1.1 E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 _ 1.26E-10 1-135 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 _ 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.1 OE-05 _ 3.59E-05 1.22E-05 1.30E-06 Cs-1 36 4.88E-06 1 .83E-05 1.38E-05 1.07E-05 1.50E-061 .46E-06 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 110 OF 134 Table 9 (continued) Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Cs-1 37 5.98E-05 7.76E-05 5.35E-05 - 2.78E-05 9.40E-06 1'.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 - 6.OE-08 6.07E-09 2.33E-,13 Ba-139 1.17E-10 8.32E-14 3.42E-12 - 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 - 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41 E-15 4.20E-13 _ 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 _ 2.86E-1 5 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 _ _ 1.70E-05 5.73E-05 La-142 8.54E- I 3.88E-1 1 9.65E-12 _ - 7.91 E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91 E-07 - 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91 E-09 - 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 - 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 - 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 - 8.81 E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 _ 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.1OE-10 _ _ 3.63E-06 1.94E-05 Np-239 2.87E-08 2.54E-08 1.55E-09 _ 8.75E-09 4.70E-06 1.49E45 11 1 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 11 i OF 134 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung .GI-LLI H-3 - 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08. 9.06E-08 C-1i4 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.019E-07 6.09E-07 6.09E-D7 Na-24 I .72E-06 1.72E-06 1.72E-06 1.72E-06 .1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 i - _ 1.16E-05 Cr-51 _ 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54_ - 6.39E-06 1.OSE-06 _ 1.59E-06 2.48E-04 8.35E-06 Mn 2.12E-10 3.15E-11 _ 2.24E-10 1.9OE-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 - - 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 _ 1.91 E-04 2.23E-05 Co-58 _- 2.59E-07 3.47E-07 _ 1.68E-04 1.19E-05 Co i .89E-06 2.48E-06 _ I.09E-03. 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 _ _ 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 1.17E-06 4.59E-06 Cu-64 :. 2.54E-10 1.06E-10 - 8.01 E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 _ 1.08E-05 I.55E-04 5.83E-06 Zn-69 6.04E-12 i1.15E-11 8.07E-13 7.53E-12 1.98E-07 3.56E-08 Br-83 - _ 4.30E-08 _ _ _

Br-84 5.41 E-08 - _

Br-85 _ _ 2.29E-09 - - - -

Rb-86 - 2.38E-05 1.05E-05 _ - 2.21E-06 Rb-88 . 6.82E-08 3.40E-08 - - - 3.65E-15 Rb-89 - 4.40E-08 2.91 E-08 - - - 4.22E-17 Sr-89. 5.43E-05 1.56E-06 _ 3.02E-04 4.64E-05 Sr-90 4.14E-03 - 8.33E-05 -' _ 2.06E-03 9.56E-05 Sr-91 1.1OE-08 _ 4.39E-10 - _ 7.59E-06 3.24E-05 Sr-92 1.19E-09 _ 5.08E-11 - _ 3.43E-06. 1.49E-05 Y-90 3.73E-07 - 1.OOE-08 3.66E-05 6.99E-05 Y-91 M 4.63E-11 - 1.77E-12 . 4.OOE-07 3.77E-09 Y-91 8.26E-05 - 2.21 E-06 - - 3.67E-04 5.11 E405 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 112 OF 134 Table 10 (continued) Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 1.84E-09 - 5.36E-1 I - 3.35E-06 2.06E-05 Y-93 1.69E-08 - 4.65E-10 - 1.04E-05 7.24E-.05 Zr-95 1.82E-05 5.73E-06 3.94E-06 - 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 '3.40E-09 1.57E-09 - 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 - 1.25E-06 9.39E-05 1.21 E-05 Mo-99 = 2.11 E-08 4.03E-09 _ 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 _ 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 _ 1.12E-07 _ 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 _ 5.42E-11 1.76E-10 2.27E-06 1.13E-05 Ru-1 06 1.23E-05 _ 1.55E-06 2.38E-05 2.01 E-03 1.20E-04 Ag-I1 OM 1.73E-06 1.64E-06 9.99E-07' 3.13E-06 8.44E-04 3.41 E-05 Te-125M 6.1 OE-07 2.80E-07' 8.34E-08 1.75E-07 _ 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127' 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.1 OE-10 1.40E-06 1.0 IE-05 Te-129M 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-1 1 4.12E-07 2.02E-07 Te-131M 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12' 7.72E-12 2.92E-07 1.89E-09' Te-1 32 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 - 1.14E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 8.11 E-07 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 _ 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 - 1.29E-06 1-134 1.IIE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 _ 2.55E-09 I

1-135,' 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 8.69E-07 Cs-134 6.28E-05 1.41 E-04 6.86E-05 4.69E-05' 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71 E-05 1.38E-05 2.22E-06 1.36E-06' Cs-137 8.38E-05 1.06E-04 3.89E-05 _ 3.80E-05 1.51 E-05' 1.06E-06 Cs-I38 5.82E-08 1.07E-07 5.58E-08 _ 8.28E-08 9.84E-09 3.38E-11 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 113 OF 134 Table 10 (continued) Page 3 of 3 Nuclide Bone Liver l T. Bodyl Thyroid Kidney Lung GI-LLI Ba-139 -1.67E-10 I1.18E-13' 4.87E12 - - 1.11 E-13 -8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 - 2.85E-09 2.54E-04 2.86E-05 Ba-141. 1.78E-11 1.32E-14 5.93E-13 ' 1.23E-14 4.11E-07 9.33E-1i Ba-142 ' 4.62E-12 4.63E-15 2.84E-13.

3 _- 3.92E-15 2.39E-07 5.99E-20 La-140 ' ' 5.99E-08 2.95E-08 7.82E-09 - 2.68E-05 6.09E-05 La-142 1;20E-1 0 5.31 E-11 1.32E-11I _ I .27E-06 1.50E-06 Ce-141 : 3.55E-06 2.37E-06 2.71 E-07  ; 1.11 E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 - 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 - 1.51 E-04 1.67E-03 '1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08' 3.86E-07 6.04E-05 2.67E-05 Pr-144. 5.37E-12 2.20E-12 2.72E-'13 ' 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 '6.41E-08 ' 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09' 1.22E-09' 4.29E-10 ' - 5.92E-06 '2.21 E-05 Np'-239 4.23E-08 3.60E-08 2.21 E-09 _ 1.25E-08 8.11 E-06 1.65E-05 L-I . ..

I R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 114 OF 134 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Page 1 of 3 Nuclide Bone -Liver: T. Body Thyroid Kidney Lung .GI-LL!

H-3 _ 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 C-14 9.70E-06 1.82E-06 .1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 _ _ _ 1.14E-05 Cr-51 - _ 4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 _ 1.16E-05 2.57E-06 _ 2.71 E-06 4.26E-04 6.19E-06 Mn-56 - 4.48E-10 8.43E-11 _ 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.1 OE-06 - 3.OOE-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 _ - 3.43E-04 1.91 E-05 Co-58 4.79E-07 8.55E-07 _ - 2.99E-04 9.29E-06 Co-60 _ 3.55E-06 6.12E-06 - - 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 - 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-1 1 4.44E-1 I --- - 2.21 E-06 2.27E-05 Cu-64 _ 5.39E-10 2.90E-10 _ 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 1.93E-05 2.69E-04 4.41 E-06 Zn-69 1.81 E-11 2.61 E-11 2.41 E-12 _ 1.58E-11 3.84E-07 2.75E-06 Br-83 - - 1.28E-07 ---

Br-84 - 1.48E-07 _

Br-85 - _ 6.84E-09 _

Rb-86 - 5.36E-05 3.09E-05 --- 2.16E-06 Rb-88 - 1.52E-07 9.90E-08 _ _ 4.66E-09 Rb-89 - 9.33E-08 7.85E-08 _ _ _ 5.11 E-10 Sr-89 1.62E-04 _ 4.66E-06 --- 5.83E-04 4.52E-05 Sr-90 1.04E-02 _ 2.07E-04 - _ 3.99E-03 9.28E-05 Sr-91 3.28E-08 _ 1.24E-09 _ 1.44E-05 4.70E-05 Sr-92 3.54E-09 _ 1.42E-10 --- 6.49E-06 6.55E-05 Y-90 1.11 E-06 - 2.99E-08 _ _ 7.07E-05 7.24E-05 Y-91M 1.37E-10 _ 4.98E-12 _ _ 7.60E-07 4.64E-07 Y-91 2.47E-04 _ 6.59E-06 - 7.1 OE-04 4.97E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 115 OF 134 Table 11 (continued) Page 2 of 3 Nuclide Bone Liver T. Body ' Thyroid Kidney Lung -GI-LLI Y-92 5.50E-09 1.57E-10 _ _ 6.46E-06 6.46E-05 Y-93 5.04E-08 - 1.38E-09 2.01 E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 1.61 E-05 6.03E-04 1.65E-5 Zr-97 5.07E-08 7.34E-09 4.3ZE-09 ' 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 - 2.33E-06 1.66E-04 1.OOE-05 Mo-99 - 4.66E-08 1.15E-08  : 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4_81E-13 9.41 E-13 1.56E-11 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91 E-13 - - 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 2.90E-07 - 1.90E-06 1.79E-04 1.21 E-05 Ru-105, 4.13E-10 _ 1.50E-10 - 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 _ 4.57E-06 - 4.972-05 3.87E-03 1.16E-04 Ag-1 bM 4.56E-06 3.08E-06 2.47E-06 5.74E-06 1.48E-03 2.71 E-05 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07, - 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71 E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E4-5 4.76E-04 4.91 E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 - 1.38E-06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 - 7.68E-07 1-132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E-06 - 8.65E-07 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 - 1.48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 - 2.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 - 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 - 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 _ 7.63E-05 2.81 E-05 9.78E-07 Cs-138 1.71 E-07 2.27E-07 1.50E-07 1.68E-07 1.84E-08 7.29E-08 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 116 OF 134 Table 11 (continued) Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 4.98E-10 2.66E-13 1.45E-11 - 2.33E-13 1.56E-06 1;56E-05 Ba-140 2.OOE-05 1.75E-08 1.17E-06 - 5.71 E-09 4.71 E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 - 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 - 7.87E-15 4.44E-07 7.41 E-10 La-140 1.74E-07 6.08E-08 2.04E-08 - _ 4.94E-05 6.1OE-05 La-142 3.50E-10 1.11E-10 3.49E-11 - - 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 - 2.31 E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 - 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 - 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 - 8.11 E-07 1.1 7E-04 2.63E-05 Pr-144 1.61 E-11 4.99E-12 8.1OE-13 - 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 - 1.30E-06 8.87E-05 2.22E-05 W-187 4.41 E-09 2.61 E-09 1.17E-09 - - 1. IIE-05 2.46E-05 Np-239 1.26E-07 8.14E-08 6.35E-09 - 2.63E-08 1.57E-05 1.73E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 117 OF 134 Table 12 - Inhalation Dose Factors for WIfant (mrem per pCI Inhaled) Page 1 of 3 Nuclide . Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 - 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32; 1.45E-03 8.03E-05 5.53E-05 .. -: _ _ 1.15E-05 Cr-51 _ _ 6.39E-08 4.11 E-08 9.45E-09 9.17E-06 2.55E-07

-Mn-54 - 1.81 E-05 3.56E-06 .- 3.'56E-06 7.14E-04 5.04E-06 Mn-56 -_ 1.1 OE-09 1.58E-10 . 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41 E-05 8.39E-06 2.38E-06 _ _ 6.21 E-05 7.82E-07 Fe-59 9.69E-06; .1.68E-05 6.77E-06 ._ 7.25E-04, 1.77E-05 Co-58 8.71 E-07 1.30E-06 - - 5.55E-04 7.95E-06 Co-60 - 5.73E-06 8.41 E-06, . 3.22E-03 2.28E-05 Ni-63 2.42E-04 1 .46E-05 8.29E-06 _ _ 1.49E-04' 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 _ - 5.80E-06 3.58E-05 Cu-64 _ 1.34E09 5.53E-100 _ 2.84E-09 6.64E-06.: 1.07E-05 Zn 1.38E-05 4.47E-05 2.22E-05 _ 2.32E-05 4.62E-04 3.67E-05 Zn-69 .3.85E-11 6.91 E-11 5.13E-12 - 2.87E-11 1.05E-06 9.44E-06 Br-83  : 2.72E-07 _ _ --

Br-84 _ 2.86E-07 - _ _

Br-85 . _ 1.46E-08 . - _

Rb-86. - -1.36E-04 6.302-05 - _ _ 2.17E-06 Rb-88 _ 3.982-07 2.052-07  : -; _ _ 2.42E-07 Rb-89. 2.29E-07 1.472-07 . _ 4.87E-08:

Sr-89 2.84E-04. - 8.15E-06 - 1.45E-03 4.57E-05

-Sr-90 1.11 E-02 _ 2.23E-04 -_ - 8.03E-03 9.36E-05 Sr-91 . 6.83E-08 . 2.47E-09 _  : 3.76E-05 5.24E-05 Sr-92 7.50E-09 - 2.79E- 10; . - 1.702-05 1.002-04 Y-90 . 2.35E-06 _ 6.30E-08 - - _ 1.92E-04 7.43E-05 Y-91M 2.91 E-10 _ 9.90E-12. _- - .1.99E-06 1.68E-06 Y-91 4.20E-04 ___-. 1.12E-05 _  : 1;75E-03 5.02E-05; R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 118 OF 134 Table 12 (continued) Page 2 of 3 Nuclide Bone Liver' T. Body Thyroid Kidney Lung GI-LLI Y-92 1.17E-08 _ . 3.29E-10 - 1.75E-05 9.04E-'05 Y-93 1.07E-07 _ 2.9.1E-09 - 5.46E-05 i.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 - 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 - 1.85E-08 7.88E-05 1.OOE-04v Nb-95 1.12E-05 4.59E-06 2.70E-06 - 3.37E-06 3.42E-04 9.05E-06 Mo-99 1.18E-07 2.31E-08 - 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-11 - 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 - 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 - 4.85E-07 - 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 - 2.93E-10 - 6.42E-10 1.12E-05 3.46E-05 Ru-1 06 6.20E-05 7.77E-06 7.61 E-05 8.26E-03 1.17E-04 Ag- I OM 7.13E-06 5.16E-06 3.57E-06 _ 7.80E-06 2.62E-03 2.36E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05. 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05' Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-1 32 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 - 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 - 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 - 1.36E-06 1-133 9.462-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 - 1.54E-06.

1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 - 9.21E-07 1-135 2.76E-06' 5.43E-06 1.98E-06 4.97E-04 6.05E-06 _ 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 _ 1.36E-04' 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 _ 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61 E-07 5.58E-07 2.84E-07 _ 2.93E-07 4.67E-08 6.26E-07 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 119 OF 134 Table 12 -(continued)

Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung lG-LLI Ba-1 39 1.06E-09 7.03E-1 3 3.07E-1 I - 4.23E-1 3 4.25E-06 3.64E-05 Ba-140 4.OOE-05 4.00E-08 2.07E-06 - 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 _ 1.36E-14 1.11 E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 _ 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-1 - - 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 - - 3.75E-06 3.69E-04 1.54E-05 Ce-143 - 2.09E-07 1.38E-07 1.58E-08 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E 8.65E-04 1.26E-04 - 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.OOE-05 3.74E-06 4.99E-07 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 - 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81 E-06 3.57E-07 , 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 - 2.83E-05 2.54E-05 Np-239 2.65E-07 2.13E-07 I1.34E-08 4.73E-08 4.25E-05 1.78E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 120 OF 134 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung - GI-LLI H-3 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 _ _ _ 2.17E-05 Cr-51 _ _ 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 _ 4.57E-06 8.72E-07 - 1.36E-06 _ 1.40E-05 Mn-56 _ 1.15E-07 2.04E-08 - 1.46E-07 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 - - 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91 E-06 - - 2.85E-06 3.40E-05 Co-58 _ 7.45E-07 1.67E-06 - - - 1.51 E-05 Co-60 _ 2.14E-06 4.72E-06 - - - 4.02E-05 Ni-63 1.30E-04 9.01 E-06 4.36E-06 - - - 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 - - - 1.74E-06 Cu-64 _ 8.33E-08 3.91 E-08 - 2.1 OE-07 - 7.1 OE-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 - 1.03E-05 - 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 - 1.28E-08 - 2.96E-09 Br-83 - _ 4.02E-08 _ - - 5.79E-08 Br-84 - _ 5.21 E-08 - --- 4.09E-13 Br-85 - 2.14E-09 - _ _

Rb-86 - 2.11 E-05 9.83E-06 - _ 4.16E-06 Rb-88 - 6.05E-08 3.21 E-08 - _ _ 8.36E-19 Rb-89 - 4.01 E-08 2.82E-08 _ _ _ 2.33E-21 Sr-89 3.08E-04 - 8.84E-06 _ 4.94E-05 Sr-90 8.71 E-03 - 1.75E-04 - 2.19E-04 Sr-91 5.67E-06 - 2.29E-07 - - 2.70E-05 Sr-92 2.15E-06 - 9.30E-08 _ _ - 4.26E-05 Y-90 9.62E-09 _ 2.58E-10 _ _ - 1.02E-04 Y-91M 9.09E-11 3.52E-12 - _ 2.67E-10 Y-91 1.41 E-07 _ 3.77E-09 _ _ - 7.76E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 121 OF 134 Table 13 (continued) Page 2 of 3 Nuclide Bone Liver T. Body_ Thyroid Kidney Lung GI-LLI Y-92 8.45E-10 . 2.47E-11i - - 148E-05.

Y-93' 2.68E-09 _ 7.40E-1 I - _ 8.50E Zr-95 - 3.04E-08 9.75E-09 6.60E-09 _ 1.53E-08 - 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 - 5.12E-10 _ 1.05E-04 Nb-95 - 6.22E-09 3.46E-09 1.86E-09 - 3.42E-09 - - 2.1OE-05 Mo-99 4.31 E-06 4 8.20E-07 - - 9.76E-06 9.99E-06 Tc-99M 2.47E-1 0 6.98E-1 0 8.89E-09 1.06E-08 3.42E-1 0 4.13E-07 Tc-101- 2.54E-10 3.66E-10 3.59E-09 - 6.59E-09 1.87E-10 1.1 OE-21 Ru-1 03 1.85E-07 7.97E-08 _ 7.06E-07 2.16E-05 Ru-1 05 1.54E-08 - - 6.08E-09 . 1.99E-07 _ 9.42E-06 Ru-106 - 2.75E-06 3.48E-07 _ 5.31 E-06 1.78E-04 Ag-i1OM 1.60E-07 1.48E-07 8.79E-08 _ 2.91 E-07 6.04E-05 Te-125M - 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 _ 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.5E-05 _ -2.27E-05 Te-127 - 1.1OE-07 3.95E-08 2.38E -8.15E-08 4.48E-07 - 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 - 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 - 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 - 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 - 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 - 7.71 E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 - 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 - 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 _ 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 - 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 - 2.51 E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 - 1.31 E-06 Cs-134 6.22E-05 1.48E-04 1.21 E-04 _ 4.79E-05 1.59E-05 2.59E-06 Cs-1 36 6.51 E-06 2.57E-05 1.85E-05 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 3.70E-05 1.23E-05 2.11 E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 8.01 E-08 7.91 E-09 4.65E-13 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 122 OF 134 Table 13 (continued) Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 9.70E-08 6.91 E-11 2.84E-09 - 6.46E--11 3.92E-11 1';72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 - 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71 E-08 3.56E-11 1.59E-09 - 3.31 E-1I 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 - 1.85E-11 1.24E-11 3.OOE-26 La-140 2.50E-09 1.26E-09 3.33E-10 - 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 - _ _ 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 - 2.94E-09 _ 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 - 5.37E-10 - 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 - 1.21 E-07 - 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 - 2.13E-09 - 4.03E-05 Pr-144 3.01 E-11 1.25E-11 I1.53E-12 - 7.05E-12 - 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 - 4.25E-09 _ 3.49E-05 W-187 1.03E-07 8.61 E-08 3.01 E-08 _ _ _ 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 - 3.65E-10 2.40E-05 I-R13

FORT CALHOUN STATION CH-ODCM-OO1 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE -PAGE 123 OF 134 Table 14- lngestion Dose Factors for Teenager (mrem per pCI Ingested) Page 1 of 3 Nuclide ,Bone Liver T. Body *Thyroid Kidney Lung GI-LLI H-3 - 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08' C-1 4. 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06, 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 ' 2.76E-04 1.71E-05 1.07E-05 _ - 2.32E-05 Cr-51 - 3.60E-09 2.OOE-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 - 5.90E-06 1.17E-06 _ 1.76E-06 _ 1.21 E-05 Mn-56 - 1.58E-07 2.81 E-08 _ 2.OOE-07 - . .04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 , - 1.70E-06 1.16E-06 Fe-59 5.87E-06: 1.37E-05 5.29E-06 - 4.32E-06 3.24E-05 Co-58. 9.72E-07 2.24E-06 . _ _ 1.34E-05 Co-60 _ 2.81 E-06 6.33E-06 - _ - 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.OOE-06 _ _ , 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 - , - 5.19E-06 Cu 1.15E-07 5.41 E-08 - 2.91 E-07 _ 8.92E-06 Zn-65 5.76E-06' 2.OOE-05 9.33E-06 . 1.28E-05 _ . 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09'  ; 1.83E-08 _ 5.16E-08 Br-83 - _ 5.74E-08 - . _ _

Br-84 _ - 7.22E-08 _ _ -

Br-85 . , 3.05E-09 ,- -_

Rb-86 - 2.98E-05 1.40E-05 . _ - 4.41 E-06 Rb-88 _ 8.52E-08 4.54E-08 _ , - 7.30E-1 5 Rb-89 . 5.50E-08 3.89E-08 - 8.43E-17 Sr-89 4.40E-04 _ 1.26E-05 - - , 5.24E-05 Sr-90 1.02E-02 - 2.04E-04' - - 2.33E-04 Sr-91 8.07E-06 3.21 E-07 - _.

_ 3.66E-05 Sr-92 3.05E-06; 1;30E-07 _ - - - . 7.77E-05 Y-90 1.37E-08 _ 3.69E-10 - _ 1.13E-04 Y-91 M 1.29E-10 _ 4.93E-12  ;- - - 6.09E-09 Y-91 2.01 E-07 I 5.39E-09 J _ 8.24E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 124 OF 134 Table 14 (continued) Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 1.21 E-09 _ 3.50E-1 _

- - _ 3.32E-05 Y-93 3.83E-09 _ 1.05E-10 - _ _ 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 - 1.91 E-08 _ 3.OOE-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 - 7.11 E-10 - 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51 E-09 - 4.42E-09 _ 1.95E-05 Mo-99 6.03E-06 1.15E-06 - 1.38E-05 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 - 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 - 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 _ 1.09E-07 - 8.99E-07 - 2.13E-05 Ru-105 2.18E-08 _ 8.46E-09 - 2.75E-07 - 1.76E-05 Ru-106 3.92E-06 _ 4.94E-07 - 7.56E-06 - 1.88E-04 Ag-11 OM 2.05E-07 1.94E-07 1.18E-07 - 3.70E-07 - 5.45E-05 Te-1 25M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 _ - 1.13E-05 lll Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 - 2.41 E-05 j

Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 - 1.22E-05 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 - 6.12E-05 Te-1 29 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 2.45E-07 Te-131 M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 - 9.39E-05 Te-1 31 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 - 2.29E-09 Te-132 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 - 7.00E-05 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 _ 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 _ 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 3.18E-07 1-133 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 _ 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 - 5.10E-09 1-135 6.1 OE-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 _ 1.74E-06 I-Cs-134 8.37E-05 1.97E-04 9.14E-05 - 6.26E-05 2.39E-05 2.45E-06

'1-Cs-136 8.59E-06 3.38E-05 2.27E-05 _ 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 5.07E-05 1.97E-05 2.12E-06 U

Cs-1 38 7.76E-08 1.49E-07 7.45E-08 1.1 OE-07 1.28E-08 4.76E-11 R13 I'-,

1_

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE, PAGE 125 OF 134 Table 14 (continued) Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Ba-139 1.39E-07 9.78E-11 4.05E-09 9.22E-11 6.74E-11 1.24E-06 Ba-140.. 2.84E-05 3.48E-08 1.83E-06 _ 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01IE-11 2.24E-09 _ 4.65E-11 3.43E-11 1.43E-13 Ba-I42 2.99E-08 2.99E-11 1.84E-09 _ 2.53E-11. 1.99E-11 9.18E-20 La140 l 3.48E-09 1.71E-09 4.55E-10 - 9.28E-05 La-142 1.79E-10 7.95E-11 1.98E-11 ., - 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 . 4.18E-09 - 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.912-1 0 7.67E-00 - 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 _ 1.72E-07 -_ 1.75E-04 Pr-143 1.31 E-08 5.23E-09 6.52E-10 _ :3.04E-09 4.31 E-05 Pr-144: 4.30E-11 1.76E-11 2.18E-12 1.01 E-11 - 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11 E-10 . - 5.99E-09 - 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 - 3.22E-05 Np-239 . 1.76E-09 1.66E-10 9.22E-11 5.21 E-10 _ 2.67E-05 I- - 1 I---

R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 126 OF 134 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Page 1 of 3 Nuclide Bone Liver ; T. Body Thyroid Kidney Lung Gl-LLI H-3 _ 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 C-14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 _ _ 2.28E-05 Cr-51 _ _ 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 _ 1.07E-05 2.85E-06 - 3.OOE-06 - 8.98E-06 Mn-56 _ 3.34E-07 7.54E-08 - 4.04E-07 _ 4.84E-05 Fe-55 1.15E-05 6.1 OE-06 1.89E-06 - - 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05' 1.33E-05 - - 7.74E-06 2.78E-05 Co-58 _ 1.80E-06 5.51 E-06 - - - 1.05E-05 Co-60 _ 5.29E-06 1.56E-05 - - - 2.93E-05 Ni-63' 5.38E-04 2.88E-05 1.83E-05 - - - 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 _- - 2.56E-05 Cu-64 - 2.45E-07 1.48E-07 _ 5.92E-07 - 1.15E-05 \_j Zn-65 1.37E-05 3.65E-05 2.27E-05 - 2.30E-05 - 6.41 E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 _ 3.84E-08 - 3.99E-06 Br-83 _ _ 1.71 E-07 _

Br-84 _ 1.98E-07 - -

Br-85 _ _ 9.12E-09 - - _

Rb-86 _ 6.70E-05 4.12E-05 - - - 4.31 E-06 Rb-88 _ 1.90E-07 1.32E-07 - - - 9.32E-09 Rb-89 1I.17E-07 1.04E-07 --- - - 1.02E-09 Sr-89 1.32E-03 3.77E-05 - - - 5.11 E-05 Sr-90 2.56E-02 _ 5.15E-04 - - _ 2.29E-04 Sr-91 2.40E-05 _ 9.06E-07 - - - 5.30E-05 Sr-92 9.03E-06 _ 3.62E-07 - - - 1.71 E-04 Y-90 4.11 E-08 - 1.10E-09 - - _ 1.17E-04 Y-91M 3.82E-10 _ 1.39E-11 - - 7.48E-07 Y-91 6.02E-07 11.61 E-08 - _ 8.02E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 127 OF 134 Table 15 (continued) Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI,-LLI.

Y-92 3.60E-09 ' 1.03E-10 _ 1.04E-04 Y-93 1.14E-08 3.13E-10 - - 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 ., 3.65E-08 2.66E-05 Zr-97 6.99E-09 1.01 E-09 5.96E-10 - 1.45E-09 _ 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 - 8.23E-09 - 1.62E-05 Mo-99 -, 1.33E-05 3.29E-06 _ 2.84E-05 - 1.10E-05 Tc-99M 9.23E-10 1.81 E-09 3.OOE-08 -- 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 ' 1.91 E-08 5.92E-1O0 3.56E-09 Ru-103 7.31 E-07 _ 2.81 E-07 _ 1.84E-06 _ 1.89E-05'-

Ru-105 6.45E-08 2.34E-08 - 5.67E-07 4.21 E-05 Ru-106 1.17E-05 - 1.46E-06 , 1.58E-05 _ 1.82E-04 Ag-11OM 5.39E-07 3.64E-07 2.91 E-07 - 6.78E-07 _ 4.33E-05 Te-'125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 _ _ 1.1OE-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 _ 2.34E-05 Te-127 4.71 E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 _ 1.01 E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 - 4.36E-07 Te-132 1.01 E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-05 - 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 - 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 - 1.54E-06 1-132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 - 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 - 2.95E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 - 5.16E-07 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 - 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.1 OE-05 - 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 - 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 - 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01 E-07 - 2.23E-07 2.40E-08 1.46E-07 R13

FORT CALHOUN STATION CH-ODCM-O001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE128 OF 134 Table 15 (continued) Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 4.14E-07 2.21 E-10 1.20E-08 _ 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31 E-05 7.28E-08 4.85E-06 _ 2.37E-08 4.34E-08 4.21 E-05 Ba-141 2.OOE-07 1.12E-10 6.51 E-09 - 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 - 5.09E-11 3.70E-11 1.14E-09 La-140 1.01 E-08 3.53E-09 1.19E-09 _ - - 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 - - 3.31 E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 - 8.68E-09 - 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 - 1.59E-09 - 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11 E-07 - 3.61 E-07 - 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 - 6.39E-09 - 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 - 2.11 E-11 - 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 - 1.24E-08 - 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 _ - - 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 - 1.09E-09 - 2.79E-05 i

11--

11-1.

,.I R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 129 OF 134

- Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GL-LLI H 1.76E-07 _.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E7.06 Na-24 1.01E-05 1.01E-05 1.01 E-05 1.01 E-05 1.01E-05 1.01 E-05 1.01 E-05 P-32 1.70E-03 1.O0E-04 ;6.59E-05 -_ - 2.30E-05 Cr-51 _ _ 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.1 E-07 Mn-54 _ 1.99E-05 4.51 E-06  ; 4.41 E-06 7.31 E-06 Mn-56 = 8.18E-07 1.41 E-07 _ 7.03E-07 _ 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 _ 4.36E-06 1.14E-06 Fe-59' 3.08E-05 5.38E-05 2.12E-05 1.59E-05 2.57E-05 Co-58 _ 3.60E-06 8.98E-06 _ _ _ 8.97E-06 Co-60 1.08E-05 ,2.55E-05 -_ - 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 _ 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 _; - - 4.05E-05 Cu-64 - 6.09E-07 2.82E-07 _ 1.03E-06 1.25E-05 Zn-65 1.84E-05 6.31 E-05 2.91 E-05 _ 3.06E-05 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 _ 6.98E-08 _ 1.37E-05 Br-83 _- 3.63E-07 - - _ .

Br-84 3.82E-07.  : _

Br-85  : 1.94E-08 ,_ .

Rb-86 1.70E-04 8AOE-05 _ _ _ 4.35E-06 Rb-88 . 4.98E-07 2.73E-07 - _ _ 4.85E-07 Rb-89 _ 2.86E-07 1.97E-07 ._ 9.74E-08 Sr-89 2.51 E-03  ;-__ 7.20E-05 _ 5.16E-05 Sr-90 2.83E-02 _ 5.74E-04 _ - _ 2.31 E-04 Sr-91 5.OOE-05 -, 1.81 E-06 .- - 5.92E-05 Sr-92 . 1.92E-05 _- 7.13E-07 , 2.07E-04 Y-90 8.69E-08 - 2.33E-09 - :_ 1.20E-04 Y-91M 8.10E-10 _ 2.76E-11 . _ _ 2.70E-06 Y-91 1.13E-06 _ 3.01E-08 _ _ - 8.10E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 130 OF 134 Table 16 (continued) Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 7.65E-09 _ 2.15E-10 _ _ 1;46E-04 Y-93 2.43E-08 6.62E-1 0 - _ I.92E-04 Zr-95 2.06E-07 5.02E-08. 3.56E-08 - 5.41 E-08 _ 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.i6E-09 - 2.56E-09 _ 1.62E-04 Nb-95 4.20E-08 1.73E-08 I .00E-08 - 1.24E-08 _ 1.46E-05 Mo-99 _ 3.40E-05 6.63E-06 - 5.08E-05 - 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.1 OE-08 - 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 - 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 4.95E-07 - 3.08E-06 - 1.80E-05 Ru-1 05 1.36E-07 _ 4.58E-08 - 1.OOE-06 - 5.41 E-05 Ru-106 2.41 E-05 _ 3.01 E-06 2.85E-05 - 1.83E-04 Ag-11 OM 9.96E-07 7.27E-07 4.81 E-07 _ 1.04E-06 - 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 - 1.11 E-05 Te-1 27M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 - 2.36E-05 Te-127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 _ 2.1 OE-05 Te-129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 - 5.97E-05 Te-129- 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 - 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 - 1.03E-04.

Te-1 31 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 - 7.11 E-06 Te-1 32 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 - 3.81 E-05 1-130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 - 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 - 1.51 E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 - 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 - 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 - 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 - 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.1 OE-05 - 1.81 E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 5.38E-05 1.1 OE-05 2.05E-06 Cs-137 5.22E-04 6.11 E-04 4.33E-05 _ 1.64E-04 6.64E-05 1.91 E-06 Cs-1 38 4.81 E-07 7.82E-07 3.79E-07 _ 3.90E-07 6.09E-08 1.25E-06 R13

FORT CALHOUN STATION , Is. CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 131 OF 134 Table 16 (continued) Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Ba-139 8.81E-07 5.84E-10 2.55E-08 - 3.51 E-10 3.54E-10; -5.58E.-05 Ba-140 1.71 E-04 1.71 E-07 8.81 E-06 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91 E-10 1.34E-08 _ 1.75E-10 1.77E-10. 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 _ 8.81 E-11 9.26E-11 7.59E-07 La-140 2.11 E-08 8.32E-09 2.14E-09 - 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 _ 6.86E-05 Ce-141 7.87E-08. 4.80E-08 5.65E-09 - 1.48E-08 - 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 2.86E-09 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 - 4.93E-07 1.71 E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 . 1.13E-08 .4.29E-05

Pr-144 2.74E-10 1.06E-10 1.38E-11 . 3.84E-11 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 -2.19E-08 l _ 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 - _ _ 3.69E-05 Np-239 1.11 E-08 9.93E-10 5.61 E-10 _ 1.98E-09 2.87E-05 R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 132 OF 134 Table 17 - Recommended Values for Other Parameters Page 1 of 2 Parameter Symbol Definition - Values fg Fraction of ingested produce grown in garden of 0.76 interest.

fe Fraction of leafy vegetables grown in garden of 1.0 K_}

interest.

P Effective surface density of soil (assumes a 240 kglm2 15 cm plow layer, expressed in dry weight) r Fraction of deposited activity retained on crops, 0.25 leafy vegetables, or pasture grass 1.0 (iodines) 0.2 (other particulates)

Sf Attenuation factor accounting for shielding 0.7 (maximum individual) provided by residential structures 0.5 (general population) th Period of long-term buildup for activity in 1.31 x 105 hr sediment or soil (nominally 15 years) te Period of crop, leafy vegetable, or pasture grass 30 days (grass-cow-milk-man exposure during growing season pathway) 60 days (crop/vegetation-man

__ pathway) tf Transport time from animal feed-milk-man 2 days (maximum individual) provided by residential structures 4 days (general population) th Time delay between harvest of vegetation or crops and ingestion:

• For ingestion of forage by animals Zero (pasture grass) 90 days (stored feed)

• For ingestion of crops by man I day (leafy vegetables and max. individual feed) 60 days (produce and max.

individual) 14 days (general population)

The fraction of daily feed that is pasture grass 1.0 while the animals graze on pasture.

MP The mixing ratio at the point of withdrawal of Site Discharge 7.14 drinking water. M.U.D. Intake 30.8 fp Fraction of the year that animals graze on 0.5 pasture.

R13

FORT CALHOUN STATION . .- CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 133 OF 134 Table 17 (continued) Page 2 of 2 Parameter .

Symbol Definition Values Environmental transit time, release to receptor 12 hrs. (maximum) -

. (add time from release to-exposure individual I day (maximum individual) . .

- point to minimums shown for distribution) 1 day (general population) 7 days (population-sport fish doses)

-10days (population-commercial fish doses) t, - Average time from slaughter of meat animal to 20 days

. . consumption

.1 YAgricultural productivity by unit area (measured 0.7 kg/M 2 (grass-cow-milk-man in wet weight) . . pathway) 2.0 kg/M2 (produce or leafy vegetable ingested by

__ _ man)

W Shore-width factor for river shoreline 0.2 X. Rate constant for removal of activity on plant or 0.0021 hr1 leaf structures by weathering (corresponds to a

._ 14-day half-life)

R13

FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 134 OF 134 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure NOTE: The Dose Estimates are based on normal public activities conducted within the Fort Calhoun Station Site Boundary.

Estimated Individual Dose Estimated Total CombineW Distance Rate (mR/hour) Annual Dose (mRem) 2 Location Direction from Containment Direct Inhalation Direct Inhalation (miles) Exposure (Critical Exposure (Critical (Total Body) Organ') (Total Body) Organ')

Firing Range 200° 0.24 4.08E-05 9.67E-06 5.08E+00 1.20E+00 Bum Pad 2410 0.33 1.95E-05 4.63E-06 1.41E-01 3.34E-02 On-Site Farming 118° 0.52 2.12E-05 5.03E-06 2.38E-02 5.64E-03 On-Site Farming 2000 0.51 1.03E-05 2.45E-06 2.30E-02 5.50E-03 On-Site Farming 3080 0.50 2.77E-05 6.64E-06 4.66E-02 1.12E-02 Site Maintenance 145° 0.20 1.18E-04 2.84E-05 5.50E-02 1.33E-02 Admin Bldg Site Maintenance 1800 0.20 1.45E-04 3.50E-05 6.78E-02 1.64E-02 Training Center 1 Critical organ doses are based on adult thyroid.

2 Estimated totals are based on summation of all individual doses for members of the General -

Public while within the Fort Calhoun Station site boundary.

I'.

U U

(IJ-R13 IJ U

J

SECTION VII ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21)

January 1, 2003 - December 31, 2003 VII-2

JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA A. Meteorological Data Recovery Data availability from the on-site weather tower for the period January 1, 2003 through December 31, 2003 was less than the previous 12 months. The regulatory guide recovery was met with a cumulative recovery rate of 96.47% from the meteorological tower with the remaining 3.53% provided by the National Weather Service. The following table is a.

summary of the parameters and their respective recovery rates for the period.

Hourly meteorological data used to replace missing tower'data for the period January 1, 2003 through December 31, 2003 originated at Eppley Airfield Weather Station, 'a branch of the National Weather Service. The hourly data was treated in accordance with monthly correction factors and a proceduralized Pasquill-Turner transformation which utilizes solar angle, time of day, cloud cover, and wind speed to'determine the Pasquill Class.

The tabulations of the Weather Tower Data for the period January 1, 2003 through December 31, 2003 look appropriate for the season indicated.

The Pasquill Classes observed for the twelve-month period are detailed below.

Pasquill Class A B C D E F G Total

% Obs. 10.08 8.37 6.58 32.99 24.33 10.55 7.11 100 The data when corrected and/or supplemented by synthetic data derived from the National Weather Service brought the recovery rate up above that required for maintaining adequate recovery as specified by the Nuclear Regulatory Commission. Recovery of synthetic and actual data requires a minimum recovery rate of 90% for the period.

On the basis of the data and its cross-checks, the weather data as amended is completely valid for use in tabulating reactor vent releases.

VII-3

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY UNSTABLE (delta T/ delta z < -1.9)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL A -

WIND SPEED (mph) AT 10-m:LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 . 24.0 +24.0 Total N 9 31 11 1 0 0 52 NNE 11 21 5 0 0 0 37 NE 7 20 11 1 0 0 39 ENE 15 29 7 0 0 0 51 E 7 15 5 4 0 0 31 ESE 2 22 4 2 0 0 30 SE 1 13 23 5 1 0 43 SSE 2 19 40 25 1 0 87 S 1 17 59 28 3 0 108 SSW 3 28 51 11 1 0 94 SW 5 18 19 1 0 0 44 WSW 5 19 3 2 0 0 29 W 10 22 1 0 0 0 33 WNW 13 22 2 0 0 0 37 NW 11 19 36 14 0 1 81 NNW 4 27 44 11 1 0 87 Total 106 342 321 105 7 1 882 Number of Calms 1 Number of Invalid Hours 0 Number of Valid Hours 883 K,

VII-4 i

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY UNSTABLE (-1.9 <= delta T/ delta z <= -1.7)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL B . .

WIND SPEED (mph) AT 10-m.LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 12 71 25 3 0 0 113 NNE 10 28 2 1 0 0 41 NE 2 23 3 0 0 0 28 ENE 7 16 4 0 0 0 27 E 4 25 8 0 0 0 37 ESE 1 17 16 4 0 0 38 SE 1 10 6 4 2 0 23 SSE 0 18 25 20 0 0 63 S 3 15 27 16 6 0 67 SSW 0 22 *- 16 7 1 0 46 SW 1 13 9 2 1 0 26 WSW 6 8 4 3 0 0 21 W 4 6 2 0 0 0 12 WNW 7 17 2 1 0 0 27 NW 5 17 20 26 1 0 69 NNW 3 40 37 12 3 0 95 Total 66 346 206 99 14 0 731 Number of Calms 2 Number of Invalid Hours 0 Number of Valid Hours 733 VII-5

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL C -

WIND SPEED (mph) AT 10-m:LEVEL Wind 1.0- 4.0-; 8.0- 13.0- 19. 0 - '-'-

Direct 3.9 7.9 12. 9 18. 9 24.0 +24.0 Total N 20 50 29 1 0 0 108 NNE 9 25 2 0 0 0 36 NE 12 18 1 0 0 0 31 ENE 5 21 0 0 0 0 26 E 6 13 3 0 0 0 22 ESE 6 11 5 4 0 0 26 SE 2 9 12 7 0 1 32 SSE 5 7 11 10 2 0 35 S 1 12 22 4 0 1 40 SSW 2 8 19 5 0 0 34 SW 1 12 5 1 1 0 20 K,~

WSW 1 2 2 2 0 0 7 W 1 8 2 0 0 0 11 WNW 1 12 2 0 0 0 15 K,-

NW 6 11 21 7 1 0 47 NNW 6 33 39 7 1 0 86 Total 84 252 175 48 5 2 566 Number of Calms 10 Number of Invalid Hours 0 Number of Valid Hours 576 VII-6

Omaha Public Power District

-Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS NEUTRAL (-1.5 < delta T/ delta z <= -0.5)

PERIOD OF RECORD:. .JAN 2003 - DEC 2003

.PASQUILL D WIND SPEED (mph) AT 10-mILEVEL Wind 1.0- 4.0- 8.0- 13 . 0- 19.0-

Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 78 188 83 3 0 0 356 NNE 54 66 14 1 0 0 135 NE 49 38 4 0 0 0 93 ENE 38 55 10 1 0 .0 104 E 28 74 31 1 0 0 134 ESE 29 69 29 12 1 0 140 SE 12 65 36 24 7 0 144 SSE 13 64 110 56 3 0 246 S 17 61 I 99 I 91 9 0 277 SSW 13 42 45 i 35 4 0 139 SW 10 35

• 18 6 2 0 71 WSW 17 19 3 4 0 0 43 W 28 30 7 1 0 0 66 WNW 28 31

• 15 2 0 0 76 NW 24 90 136 64 5 0 319 NNW 53 237 194 61 2 0 547

. Total 491 1164 - 834 362 33 0 2884 Number of Calms 6 Number of Invalid Hours 0 .

Number of Valid Hours: 2890 VII-7

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL E .

WIND SPEED (mph) AT 10-m LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 40 17 9 0 0 0 66 NNE 22 11 7 0 0 0 43 NE 16 4 4 0 0 0 25 ENE 32 7 6 0 0 0 45 E 41 27 2 0 0 0 70 ESE 41 45 1 0 0 0 87 SE 39 114 45 12 2 0 212 SSE 22 104 111 50 5 10 302 S 29 59 100 58 7 0 255 SSW 20 35 52 57 4 0 168 SW 16 16 37 24 13 0 107 WSW 24 20 14 3 0 0 62 W 46 26 10 0 0 0 84 WNW 112 46 10 0 0 0 171 NW 82 130 47 8 0 0 268 NNW 51 73 37 4 1 0 166 Total 633 734 492 216 32 10 2117 Number of Calms 14 Number of Invalid Hours 0 Number of Valid Hours 2131 VII-8

.Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL F WIND SPEED (mph) AT 10-m.LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0- -

Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 10 3 1 0 0 0 15 NNE 11 0 0 0 0 0 13 NE 11 1 0 0 0 0 14 ENE 11 0 0 0 0 0 12 E 19 4 0 0 0 0 24 ESE 32 35 0 0 0 0 69 SE 74 91 18 0 0 0 185 SSE 41 34 2 0 0 0 80 S 24 22 12 0 0 0 58 SSW 18 10 13 1 0 0 48 SW 25 9 12 7 0 0 60 WSW 34 5 5 1 0 0 50 W 57 3 2 0 0 0 67 WNW 115 9 0 0 0 0 131 NW 54 21 0 0 0 0 76 NNW 18 4 0 0 0 0 22 Total 554 251 65 9 0 0 879 Number of Calms 45 Number of Invalid Hours 0 Number of Valid Hours 924 VII-9

v-Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY STABLE (delta T/ delta z > 4.0)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL G .

WIND SPEED (mph) AT 10-m.LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 13 0 0 0 0 0 25 NNE 8 0 0 0 0 0 9 NE 16 0 0 0 0 0 17 N-ENE 22 0 0 0 0 0 26 E 35 0 0 0 0 0 38 ESE 77 13 0 0 0 0 91 v SE 84 19 2 0 0 0 105 SSE 55 8 2 0 0 0 68 S 38 4 0 0 0 0 46 SSW 25 7 6 0 0 0 43 SW 26 3 1 0 0 0 36 WSW 20 1 0 0 0 0 30 W 28 0 0 0 0 0 35 WNW 25 1 0 0 0 0 32 NW 7 0 0 0 0 0 7 NNW 15 0 0 0 0 0 15 Total 494 56 11 0 0 0 561 Number of Calms 62 Number of Invalid Hours 0 Number of Valid Hours 623 Hours Accounted For: 8760 VII-10

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY UNSTABLE (delta T/ delta z < -1.9)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL A WIND SPEED (mph) AT 10-m.LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 0.10 0.35 0.13 0.01 0.00 0.00 0.59 NNE 0.13 0.24 0.06 0.00 0.00 0.00 0.42 NE 0.08 0.23 0.13 0.01 0.00 0.00 0.45 ENE 0.17 0.33 ,0.08 0.00 0.00 0.00 0.58 E. 0.08 0.17 0.06 0.05 0.00 0.00 0.35 ESE 0.02 0.25 0.05 0.02 0.00 0.00 0.34 SE 0.01 0.15 0.26 0.06 0.01 0.00 0.49 SSE 0.02 0.22 0.46 0.29 0.01 0.00 0.99 S. 0.01 0.19 -0.67 0.32 0.03 0.00 1.23 SSW 0.03 0.32 0.58 0.13 0.01 0.00 1.07 SW 0.06 0.21 0.22 0.01 0.00 0.00 0.50 WSW 0.06 0.22 0.03 0.02 0.00 0.00 0.33 W 0.11 0.25 0.01 0.00 0.00 0.00 0.38 WNW 0.15 0.25 0.02 0.00 0.00 0.00 0.42 NW 0.13 0.22 0.41 0.16 0.00 0.01 0.92 NNW 0.05 0.31 -0.50 0.13 0.01 0.00 0.99 Total 1.21 3.90 3.66 1.20 0.08 0.01 10.07 Percent of Calms 0.01 Percent of Invalid-Hours 0.00 Percent of Valid Hours 10.08 VII-11

11 Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY UNSTABLE (-1.9 <= delta T/ delta z <= -1.7)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL B-WIND SPEED (mph) AT 10-m: LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 0.14 0.81 0.29 0.03 0 .00 0 .00 1.29 NNE 0.11 0. 32 0. 02 0.01 0.00 0.00 0.47 NE 0. 02 0.26 0. 03 0.00 0. 00 0.00 0.32 ENE 0.08 0. 18 0. 05 0.00 0.00 0.00 0.31 E 0.05 0.29 0. 09 0.00 0.00 0.00 0.42 ESE 0. 01 0. 19 0. 18 0.05 0.00 0.00 0.43 SE 0.01 0. 11 0.07 0.05 0. 02 0.00 0.26 SSE 0.00 0.21 0.29 0.23 0.00 0. 00 0. 72 S 0. 03 0. 17 0.31 0.18 0.07 0. 00 0. 76 SSW 0. 00 0.25 0. 18 0. 08 0.01 0. 00 0. 53 SW 0.01 0. 15 0. 10 0. 02 0.01 0 . 00 0.30 WSW 0.07 0 .09 0. 05 0. 03 0.00 0 . 00 0.24 W 0.05 0 . 07 0. 02 0. 00 0.00 0 . 00 0. 14 WNW 0.08 0. 19 0. 02 0. 01 0.00 0. 00 0.31 NW 0.06 0 . 19 0.23 0.30 0.01 0 . 00 0.79 NNW 0. 03 0.46 0.42 0. 14 0.03 0 . 00 1.08 Total____0.75___3_95__2.35___1.13___0.1____0.00___8.34_

Total 0.75 3.95 2.35 1.13 0.16 0.00 8.34 Percent of Calms 0.02 Percent of Invalid Hours 0.00 Percent of Valid Hours 8.37 VII-12

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY UNSTABLE:(-1.7 .: delta T/ delta z <= -1.5)

PERIOD OF RECORD: JAN 2003 -DEC 2003

- PASQUILL C WIND SE-m.LEVEL SPEED (mph) AT Wind 1.0- 4.0- -: 8.0- 13.0- 19.0-Direct 3.9 7.9 '12.9 18.9 24.0 +24.'0 Total N 0.23 0.57 0.33

• 0.01 0.00 0.00 1.23 NNE 0.10 0.29 0.02 I0.00 0 .00 O . 00 0.41 NE 0. 14 0.21 0.01 0.00 0.00 0. 00 0.35 ENE 0.06 0.24 0'.00 0.00 0.00 0.00 0.30 E 0.07 0.15 0;'03 *0.00 0.00 0.00 0.25 ESE 0. 07 0.13 0.06 0 . 05 0.00 0.00 0.30 SE 0'.02 0 . 10 0. 14 0.08 0.00 0.01 0.37

-SSE 0.06 0.08 0.13 0. 11 0.02 0.00 0.40 S 0.01 0.14 0.25 0.05 0.00 0. 01 0.46 SSW 0.02 0.09 0.22 0.06 0.00 0.00 0.39 SW 0.01 0.14 0.06 00. 01 0. 01 0. 00 0.23

.WSW 0.01 0.02 0.02 0.02 0.00 0 . 00 0.08 W 0 .01 0. 09 0.02 0.00 0.00 0. 00 0. 13 WNW 0 .01 0.14 0.02 0 .00 0'.00 0.00 0.17 NW 0.07 - 0. 13 0.24 0. 08 0.01 0 . 00 0.54 NNW 0 . 07 0.38 0.45 0.08 0.01 0 .00 0.98 0.02____6.4___

Total 0.96 2.88 2.00 0.55 0.06 0.02 6.46 Percent of Calms 0.11 Percent of Invalid Hours- 0.00 Percent of Valid'Hours 6.58 VII-13

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT NEUTRAL (-1.5 < delta T/ delta z <= -0.5)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL D WIND SPEED (mph) AT 10-m: LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 0.89 2.15 0. 95 0. 03 0.00 0. 00 4.06 NNE 0.62 0.75 0. 16 0 . 01 0.00 0. 00 1.54 NE 0.56 0.43 0. 05 0 . 00 0.00 0. 00 1.06 ENE 0.43 0. 63 0. 11 0.01 0.00 0. 00 1.19 E 0.32 0. 84 0.35 0.01 0.00 0. 00 1. 53 ESE 0.33 0.79 0.33 0. 14 0.01 0. 00 1.60 SE 0.14 0.74 0.41 0.27 0.08 0. 00 1. 64 SSE 0. 15 0.73 1.26 0. 64 0.03 0. 00 2.81 S 0. 19 0.70 1. 13 1. 04 0.10 0. 00 3 . 16 SSW 0. 15 0.48 0.51 0.40 0.05 0. 00 1.59 SW 0 .11 0.40 0.21 0.07 0.02 0 . 00 0.81 WSW 0. 19 0.22 0. 03 0. 05 0.00 0. 00 0.49 W 0.32 0.34 0.08 0. 01 0.00 0. 00 0.75 WNW 0.32 0.35 0.17 0. 02 0.00 0 . 00 0.87 NW 0.27 1. 03 1.55 0.73 0.06 0. 00 3. 64 NNW 0.61 2.71 2.21 0.70 0. 02 0. 00 6.24 Total 5.61 13.29 9.52 4.13 0.38 0.00 32.92 Percent of Calms 0.07 1-j Percent of Invalid Hours 0.00 Percent of Valid Hours 32.99

'-.4 VII-14

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)

PERIOD OF RECORD: JAN 2003 - DEC 2003

- PASQUILL E -

WIND SPEED (mph) AT 10-m LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct .3.9 7.9 .12.9 18.9 24.0 +24.0 Total N 0.46 0.19 - 0.10 0. 00 0. 00 0. 00 0.75

• NNE 0.25 0.13 0.08 0. 00 00. 00 0.00 0.49

,NE 0.18 0.05 0.05 0. 00 0.00 0.00 0.29 ENE 0.37 0.08 0.07 0. 00 0. 00 0. 00 0.51 E 0.47 0.31 0.02 0.00 0.00 0.00 0.80 ESE 0.47 0.51 0.01 0.00 0.00 0.00 0.99 SE 0.45 1.30 0.51 0. 14 0.02 0.00 2.42 SSE 0.25 1.19 1.27 0.57 0. 06 0.11 3.45 S 0.33 0.67 1.14 0.66 0.08 0.00 2. 91 SSW 0.23 0.40 0.59 0.65 0.05 0.00 1. 92 SW 0.18 0.18 0.42 0.27 0.15 0.00 1.22 WSW 0.27 0.23 0.16 0. 03 0.00 0.00 0.71

,W 0.53 0.30 0.11 0.00 0.00 0. 00 0. 96 WNW 1.28 0.53 0.11 0.00 0 . 00 0 .00 1.95 NW 0.94 1.48 0.54 0.09 0. 00 0.00 3. 06 NNW 0.58 0.83 0.42

• 0.05 0. 01 0.00 1.89 Tota_____7_23__8.38___5__62__2.47__0.37___0.11___24.17_

Total 7.23 8.38 5.62 2.47 0.37 0.111 24.17 Percent of Calms 0.16 Percent of Invalid Hours 0.00 Percent of Valid Hours 24.33 VII-15

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL F '-I WIND SPEED (mph) AT 10-m:LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0-Direct 3.9 7.9 12.9 18.9 24.0 +24.0 Total N 0. 11 0. 03 0.01 0.00 0.00 0 .00 0. 17 NNE 0. 13 0. 00 0.00 0. 00 0 .00 0. 00 0. 15 NE 0. 13 0. 01 0.00 0. 00 0.00 0 .00 0.16 ENE 0. 13 0. 00 0. 00 0.00 0.00 0.00 0.14 E 0.22 0. 05 0.00 0.00 0.00 0. 00 0.27 ESE 0.37 0.40 0.00 0.00 0. 00 0. 00 0.79 SE 0. 84 1.04 0.21 0.00 0.00 0.00 2 . 11 SSE 0.47 0.39 0. 02 0.00 0.00 0. 00 0. 91 S 0.27 0.25 0.14 0.00 0.00 0.00 0. 66 SSW 0.21 0. 11 0.15 0. 01 0.00 0 .00 0.55 SW 0.29 0. 10 0.14 0.08 0.00 0. 00 0. 68 WSW 0.39 0.06 0.06 0 .01 0.00 0 .00 0.57 W 0. 65 0. 03 0. 02 0.00 0.00 0. 00 0.76 WNW 1.31 0.10 0.00 0. 00 0.00 0.00 1.50 NW 0. 62 0.24 0.00 0. 00 0.00 0. 00 0. 87 NNW 0.21 0.05 0.00 0.00 0.00 0. 00 0.25 Total 6.32 2.87 0.74 0.10 0.00 0.00 10.03 Percent of Calms 0.51 Percent of Invalid Hours 0.00 Percent of Valid Hours 10.55 k'.;

VII-16

Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY STABLE (delta T/ delta z > 4.0)

PERIOD OF RECORD: JAN 2003 - DEC 2003 PASQUILL G WIND SPEED (mph) AT 10-m LEVEL Wind 1.0- 4.0- 8.0- 13.0- 19.0--

Direct 3.9 7.9 12. 9 18.9 24.0 +24.0 Total

_____________ 0.00--- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

N 0.15 0.00 0.00 0.00 0. 00 0 .00 0.29 NNE 0.09 0 . 00 0.00 0.00 0 . 00 0 .00 0.10 NE 0.18 0.00 0. 00 0 . 00 0 .00 0.00 0 . 19 ENE 0.25 0.00 0.00 0.00 0.00 0.00 0.30 E 0.40 0. 00 0.00 0. 00 0. 00 0.00 0.43 ESE 0.88 0. 15 0 . 00 0. 00 0.00 0.00 1. 04 SE 0.96 0.22 0. 02 0.00 0.00 0.00 1.20 SSE 0.63 0.09 0. 02 0. 00 0.00 0.00 0.78 S 0.43 0. 05 O . 00 0.00 0. 00 0.00 0. 53 SSW 0.29 0. 08 0.07 0.00 0 .00 0 .00 0.49 SW 0.30 0.03 ,0.01 0.00 0.00 0.00 0.41 WSW 0.23 0 .01 :0. 00 0 .00 0.00 0.00 0.34 W 0.32 0.00 .- 0.00 0. 00 0.00 0.00 0.40 WNW 0.29. 0 .01 0. 00 0. 00 0.00 0.00 0.37 NW 0.08 0. 00 0. 00 0. 0 0 0. 00 0. 0 0 0. 08 NNW 0.17 0. 00 ,0.00 0.00 0 .00 0.00 0. 17 Total 5.64 0.64 0.13 0.00 0.00 0.00 6.40 Percent of Calms 0.71 Percent of Invalid Hours O.00 Percent of Valid Hours 7.11 Percent of Hours Accounted For: 100.00 VII-17

I Joint Frequency Distribution 2003 FCS Tower Data N

11.87 10.03 I

III II II W II

---

r------ ------------ E II II 10.18 9.82 S

Calms excluded.

1 4 8 13 i9 24 Rings drawn at 5% intervals.

Wind flow is FROM the directions shown.

Wind Speed ( Miles Per Hour) No observations were missing.

VII-18

SECTION VII ATTACHMENT 3 ANNUAL OCCUPATIONAL EXPOSURE REPORT Technical Specification 5.9.1.b January 1, 2003 - December 31, 2003 VII-19

ccc ccc ccc ( C C C (7 C C (7 ( C ( ( C (7 C C (7 (

FORT CALHOUN STATION Date: 10-FEB-2004 13:56 OMAHA PUBLIC POWER DISTRICT P. 0. BOX 550 FT. CALHOUN, NE. 68023-0550 LICENSE: DPR-40 Regulatory Guide 1.16 Information End of Year Report 2003 Number of Personnel

> 100 mrem Total man-rem

• Work and Job Function Station Utility Contractor Station Utility Contractor REACTOR OPERATIONS AND SURVEILLANCE MAINTENANCE AND CONSTRUCTION 0.649 0.176 0.005 0.283 0.031 0.001 OPERATIONS 24.638 0.000 0.000 6.297 0.000 0.000 HEALTH PHYSICS 7.505 0.000 15.212 3.809 0.000 3 .918 SUPERVISORY 2. 144 0.000 0.316 0.445 0.000 0.163 ENGINEERING 1.353 0.000 1.000 0.403 0.000 0.224 ROUTINE MAINTENANCE MAINTENANCE AND CONSTRUCTION 35.023 20.688 125.991 15.187 9.697 45.079 OPERATIONS 2.817 0.000 0.000 0.868 0.000 0.000 HEALTH PHYSICS 11.514. 0.000 16.578 6.722 0.000 4 .692 SUPERVISORY 16.599 0.000 7.962 5.511 0.000 1.825 ENGINEERING 8.687 0.000 1.660 2.081 0.000 0.272 INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION 13.313 7.530 14.304 6.615 3.268 5.370 OPERATIONS 0.029 0.000 0.000 0.006 0.000 0 000 HEALTH PHYSICS 1.535 0.000 12.459 0.928 0.000 2.671 SUPERVISORY 3.259 0.000 1. 893 1.911 0.000 0.736 ENGINEERING 1.135 0.000 59. 977 0.169 0.000 36.419 SPECIAL MAINTENANCE MAINTENANCE AND CONSTRUCTION 0.839 0.128 23.848 0'421 0.040 4.230 OPERATIONS 0.146 0.000 0.000 0.020 0.000 0.000 HEALTH PHYSICS 0.789 0.000 0.563 0.492 0.000 0.180 SUPERVISORY 1.106 0.000 2.048 0.486 0.000 0.587 ENGINEERING 0.750 0.000 4.088 0.106 0.000 2.048 VII-20

Regulatory Guide 1.16 Information End of Year Report 2003 Number of Personnel

> 100 mrem Total man-rem

• Work and Job Function Station Utility Contractor Station Utility Contractor WASTE PROCESSING MAINTENANCE AND CONSTRUCTION 0.088 0.034 0.057 0.039 0.012 0.013 OPERATIONS 0.000 0.000 0.000 0.000 0.000 0.000 HEALTH PHYSICS 1.139 0.000 1.003 0.613 0.000 0.129 SUPERVISORY 0. 034 0.000 0.002 0.013 0.000 0. 001 ENGINEERING 0.000 0.000 0. 001) 0.000 0.000 0.000 REFUELING MAINTENANCE AND CONSTRUCTION 6.268 7.443 34.796 2.707 2.126 23.472 OPERATIONS 0.377 0.000 0.000 0.084 0.000 0.000 HEALTH PHYSICS 1.517 0.000 3.184 0.865 0.000 0.786 SUPERVISORY 4.631 0.000 1.044 1.849 0.000 0.361 ENGINEERING 1. 122 0.000 0.004 0.152 0.000 0.001 Totals MAINTENANCE AND CONSTRUCTION 56.180 36.000 199.000 25.252 15. 174 78.165 OPERATIONS 28.007 0.000 0.000 7.275 0.000 0.000 HEALTH PHYSICS 24.000 0.000 49.00(1 13.429 0.000 12.376 SUPERVISORY 27.773 0.000 13.271 10.215 0.000 3.673 ENGINEERING 13.047 0.000 66.729 2.911 0.000 38.964 Grand Totals 149.007 36.000 328.000 59.082 15.174 133.178

• The man-rem totals include dose only from individuals receiving more than 100 mrem throughout the year at the site.

VI1-21