ML20206A350
| ML20206A350 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/1998 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20206A324 | List: |
| References | |
| NUDOCS 9904280139 | |
| Download: ML20206A350 (440) | |
Text
{{#Wiki_filter:- - __ - e:. . y 3' _y' ' 3' ' ._p'; -- , . 4/g ,w
'[,' .7t' ,! f; 7; i } ',';
I; to'-
.a ,
-n :
s m;
- j' g IL Omaha Public Power /Distride me mn$
I; + Fort:Calhoun Station UniMa
. . - M%n.kH$,n$ 4 p,.
r g. +
, . [5 Ma M4 2f 6 #72 M E hl';;.wy %nual RepoiHt@gg@y%g g' s mn(('y,,.o iA M M@ y $ g$ 9 py 2n %me M_3 JEpt;;me s;
1m fem asw - $ $ q% l t_%m &w. l~ MwWagse%,s# g S _$ _ ,9 % 4y p@7 f7S 7_%A_TeehnicalLS isc_ifi
'SMEM~Sec tionf5;914sWj7s@ p P1Pfa#
s esp %Rgh
~gn i fer' m % p $p'
#AidJ,anine% ave # e!mame#w$G1p1 p a g g g g
' i vj e s % d y w w w3h9 e s q r d $998:to:Dsesnil hL S$w$khh@ne$y1fN
.m m.4 .
_. .. yg4 _-a% [ N - S E -- M ![ N h k ?D $ IJ
- g. .,g. x,'j
~ '
$$$$$. NLp@ n ' W a
h$ g .
- d. ,1TAMM N " h, j [ty .
G - hq
> . . , s ,n
- k. j '
9904200139 990420 PDR ADOCK 05000295 R PDR ;
[ Omaha Public Power District [ Fort Calhoun Station Unit No.1 [ Annual Report [ For Technical Specification [ Section 5.9.4.A F January 1,1998 to December 31,;1998: c ., t 3; ~ no . .
?
i -{ ; DEI,} W !:
***+ IIIIIIII$j)f;3
. c3.p p .g _ __ J
! +
4
~
PDR DO K 05000285 ' R PDR _
l l Omaha Public Power District Fort Calhoun Station Unit No.1 ; Annual Report For Technical Specifications, Section 5.9.4.A January 1, 1998 to December 31, 1998 DOCKET NO. 50-285 OPERATING LICENSE DPR-40
1 1 l Annual Radiological Effluent Release Report ! I l This report is submitted in accordance with Section 5.9.4.a of the Technical Specifications of Fort Calhoun Station Unit No.1, Facility ll Operating License DPR-40 for the period January 1.,1998 through December 31,1998. The Effluent Report is presented in the format l outlined in Regulatory Guide 1.21, Revision 1. In addition, this report provides the results of quarterly dose calculations performed in accordance with the Offsite Dose Calculation Manual. l Results are presented by quarter for the period January 1,1998 through December 31,1998. ; Further, description of any changes made during the preceding twelve j months to the Offsite Dose Calculation Manual and/or the Process Control l l Program for the Fort Calhoun Station are presented. PRC RECOMMENDS ' ,
\
APPROVAL gg 221999 SS ' (a mr LAManager-Fort Cal oun t tion I c gaWNUTES' l I I I
l Il lg TABLE OF CONTENTS Section Section Title
- l. 1.0 Introduction 1.1 Executive Summary l 2.0 Supplemental Information 2.1 Regulatory Limits 2.2 Effluent Concentration Limits I 2.3 Measurements and Approximations of Total Radioactivity 2.4 Estimation of Total Percent Error 1
l 2.5 Batch Releases 2.6 Abnormal Releases g 3.0 Gaseous Effluents 4.0 Liquid Effluents 5.0 Solid Wastes 6.0 Related Information 6.1 Operability of Liquid and Gaseous Monitoring ,3 Instrumentation E 6.2 Changes to Offsite Dose Calculation Manual j (ODCM) or Process Control Program (PCP) I 6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring 6.4 Noncompliance with Radiological Effluent Control g Requirements 6.5 Changes to Liquid and Gaseous Waste Treatment and Ventilation Exhaust Systems l 6.6 Meteorological Monitoring Program 6.7 Assessment of Doses ll. Quarterly Doses from Effluents, Offsite Dose Calculetion Manual ,I I
1 TABLE OF CONTENTS l lil. Radiological Effluent Releases, Technical Specification (5.9.4a) Table ill-1; Batch Liquid and Gas Release Summary Table lll-2; Abnormal Batch Liquid and Gaseous Release Summary i Table lll-3; Gaseous Effluents -Summation of All Releases g Table lll-4; Gaseous Effluent Releases - Batch Mode Table lll-5; Gaseous Effluent Releases - Continuous Mode Table Ili-C; L! quid Effluents - Summation of All Releases Table lil-7; Liquid Effluent Releases - Batch Mode l Table 111-8; Liquid Effluent Releases - Continuous Mode I'I IV. Dose From Gaseous Effluents - GASPAR ll Output Tables IV-A-1 to IV-A Receptor Dose Projections Table IV-B Dose Contributions at Unrestricted Area Boundary l Table IV-C ALARA Annual integrated Dose Summary l 1 Dose From Liquid Effluents - LADTAP 11 Output I V. Summary Dose Projections from Liquid Effluent Releases VI. Radioactive Effluent Releases-Solid Radioactive Waste, Technical Specifications (5.9.4.a) l Vll. ATTACHMENTS l
- 1. Offsite Dose Calculation Manual (ODCM) and g Process Control Program (PCP) Revisions g Technical Specifications (5.17.d and 5.18.d) l
- 2. Joint Frequency Distribution Wind Direction vs. Wind Speed by Stability Class and Meteorological Data
- 3. Annual Occupational Exposure Report, Technical Specification (5.9.1) j I
I
1.0 INTRODUCT.'ON l This Annual Radiological Effluent Release Report, for Fort Calhoun Station Unit No.1, is submitted as required by Technical Specification 5.9.4.a for the period January 1,1998 through I December 31,1998. 1.1 Executive Summary The Radioactive Effluent Monitoring program for the year I 1998 was conducted as described in the following report. Major efforts were made to maintain the release of radioactive effluents to the environment as low as reasonably achievable. Activity released increased from the previous year because 1998 was an outage year. l The total gaseous activity released for 1998 was 5308 Curies. This was an increase from the 2056 Curies I released in 1997. The increase in activity in 1998 was primarily due to 1998 being ar. outage year and due to more significant failed fuel at the cration. Dose contribution from gaseous effluents at the unrestricted area boundary was 6.87E 01 millirad maximum gamma air I dose, and 2.24E+00 millirad maximum beta air dose. This was an increase from the 1997 values of 2.19E-01 millirad and 7.13E-01 millirad respectively. Activity released l increased from the previous year because 1998 was an outage year and due to more significant failed fuel at the station. Total activity (excluding tritium, dissolved gases and alpha) released in 1998 in liquid effluents was 3.56E-01 Curies. This was lower than the previous years value of 4.02E-01 Curies. The total tritium activity released in 1998 in liquid effluents was 260 Curies. This was a decrease from the previous years value of 349 Curies. The calculated whole body dose due to liauid effluents l released in 1998 was 4.45E-01 mrem, up from the 1997 dose of 2.69E-01 mrem adult whole body dose at the site discharge from all sources. I g I-1
The Fort Calhoun Station meteorological system achieved a a cumulative recovery rate of 98.88% for the joint frequency l parameters required by Regulatory Guide 1.23 of wind speed, wind direction and delta temperature. There was one abnormal release during 1998. The release commenced on approximately April 24,1998 at 1750 during g a refueling outage when an ammonia smell was detected by u workers in Room 81 of the Auxiliary Building. An unmonitored release path was discovered that allowed containment air to be released into Room 81 A Copus l blower was attached to the secondary handholes of 'A' steam generator, drawing in ambient containment air and feeding it through the steam generator and out through disassembled valves YCV-1045A and YCV-10458 into Room 81. Containment integrity was not required at the time of the release. It is assumed the condition lasted for 540 minutes and was terminated on April 25,1998 at 0250 when E Operations secured the Copus blower. A Radiological aj Analysis was performed by Chemistry and calculations I showed that the release did not exceed Technical g Specification requirements. The total amount of radioactive , material potentially released was calculated as 4.64E-04 Curies. The ECL fraction was 6.6E-06 which is well below the 5 times ECL allowed by Technical Specifications. l Condition Report 199800906 was generated to document the event. l During 1998 there were 2 revisions to the ODCM. The first g change was issued on January 15,1998 and incorporated 3 the format of NUREG-0472, Radiological Effluent Technical Specifications for PWR's. This revision also included g changes in the way effluent radiation monitor alert and alarm E I setpoints are determined as well as several minor editorial changes. The second revision was issued on June 18,1998 and incorporated a change to the elemental iodine fraction g' per EA-FC-94-048 for gaseous effluent releases. No revisions were made to the Process Control Program. l l l 1 1-2 I
For 1998, the total volume of buried solid radwaste was 22.49 cubic meters, essentially unchanged from the 22.45 cubic meters of solid waste buried in 1997. The majority was due to shipments of spent resin. The total buried activity for 1998 was 7235.69 Curies,7235.62 of which came from spent resin. This value is up from the 1997 value of 90.50 Curies. Overall, the radh active effluent monitoring program was conducted in a manner to ensure the activity released and associated dose to the public was maintained as low as reasonably achievable. 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM Radiological Effluent Control Specifications applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections. 2.1.1 Fission and Activation Gases (Noble Gases). The release rate of radioactivo material in airbome effluents shall be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR 20 for airbome 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. 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 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 1. t 1-3
The air dose due to noble gases releaseri in gaseous effluents to areas at or beyond the site beundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than l
or equal to 20 mrad for beta radiation. 2.1.2 Dose - lodine-131, Radioactive Material in Particulate Form with Half Lives Greater than 8 Days (Other than Noble Gases) and Tritium _
- a. The dose to an individual or dose commitment g to any organ of an individualin unrestricted areas due to the release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airbome effluents shall not g exceed 7.5 millirem from all exposure g pathways during any calendar quarter.
- b. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airbome effluents shall not exceed 15 millirem from all exposure pathways during any calendar year.
I I l-4
2.1.3 Liquid Emuents 9 The release rate of radioactive material in liquid emuents 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 20 for liquid emuents 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 2.0E-04 pCi/ml, total activity. 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 emuents to unrestricted areas conforming to ten times 10 CFR 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 Ci/ml total activity. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid emuents released to unrestricted areas shall be limited to:
- a. During any calendar quarter: Less than or equal to 1.5 mrem to the whole body and less than or equal to 5 mrem to any organ, and
- b. During any calendar year: Less than or equal to 3 mrem to the whole body and less than or equal to 10 mrem to any organ.
l-5
I 2.1.4 Total Dose-Uranium Fuel Cycle The dose to any real individual from uranium fuel cycle sources shall be limited to 5 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 5 75 mrem) during each calendar year. 2.2 Effluent Concentration Limits (ECL) 2.2.1 Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of g 2.0E-04 pCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents. l 2.2.2 Gaseous Effluents The values specified in 10 CFR Part 20, Appendix B, I Column 1 are used as the ECL for gaseous radioactive effluents released to unrestricted areas. 2.3 Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 3.1 and 3.2 of Part I of the ODCM. I I I l-6
{: 2.3.1 Liquid Radioactive Effluents Each batch was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for the Monitor and Hotel Waste Tanks. Composite samples were analyzed monthly in the onsite laboratory for tritium and gross alpha radioactivity using liquid scintillation and [ proportional counting techniques respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory (Teledyne Brown Engineering.). A software program was developed and installed that can project the total body and critical organ dose contribution at the site boundary for each release and the percent contribution to the annual objective dose. [ For continuous releases from the Steam Generator blowdown, daily grab samples were obtained for { , weekly, monthly and quarterly composites, in proportion to the rate of blowdown. Samples were 1, analyzed using gamma spectroscopy techniques f weekly. Composites were also analyzed monthly in the onsite laboratory for tritium and gross alpha radioactivity using liquid scintillation and proportional (- counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90, [ and Fe-55 by a contract laboratory (Teledyne Brown t Engineering). f ( ( l-7 r L
s 2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For release of Waste Gas Decay Tanks, noble gas grab samples g were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the Containment Building, samples were taken using l charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analysis and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode. A software program was developed and installed that can project the total body and critical organ dose contribution at the site boundary for each release and the percent contribution to the annual objective dose. This program also adds the projected dose to the current actual dose totals in a temporary file, until it is updated with actual release data at the completion of a purge. For continuous effluent release pathways, noble gas is collected and analyzed weekly for gamma emitting radionuclides by gamma. Continuous release pathways were continuously sampled using charcoal and pa;ticulate filters and analyzed weekly for gamma emitting radionuclides using gamma spectroscopy. g Weekly particulate filters were analyzed for gross 5 alpha radioactivity in the onsite laboratory using proportional counting techniques. Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by an offsite laboratory (Teledyne Brown Engineering). l I l-8
2.4 Estimation of Total Percent Error The estimated total percent error is calculated as follows: Total Percent Error = (E 2 + E 22 + E 2 i 3 + ... + E 2)a n Where Eo = Percent Error Associated with each contributing parameter. Sample counting error is estimated by the Canberra Genie System Software for samples analyzed by gamma spectroscopy. This calculation can include the error associated with peak area determination, gamma ray abundance, efficiency and half life. Systematic error is estimated for gaseous and liquid effluent analyses and dilution and waste water volume. 2.5 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 111-1. 2.6 Abnormal Releases Abnormal Releases are defined as unplanned and unmonitored releases of radioactive material from the site. A summary of information for gaseous and liquid abnormal releases is included in Table 111-2. 3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 111-3,111-4 and lil-5. All radioactive material released in gaseous form are considered to be ground level releases.
- 4. 0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables lil-6, lil-7 and 111-8.
1-9
I 5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Section VI. 6.0 RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring instrumentation During the reporting period RM-057 the Condenser Off-Gas Radiation monitor was out of service for greater than 30 days. RM-057 was out of service from June 4,1998 to September 4,1998. The monitor was removed from service for an extended period of time for several reasons. Initially the monitor was providing erratic readings during operation. During troubleshooting it was discovered that the detector was corroded, resulting in the detector needing replacement. A spare detector was in the warehouse, but it was damaged l and not usable. A replacement detector and pre-amp were ordered from the vendor. However, there was a long lead l time for parts delivery since the parts hr.d to be manufactured. The parts arrived on site and the monitor was calibrated and retumed service. 6.2 Changes to the Offsite Dose Calculation Mary: 4DCM) or Process Control Program (PCP) During the reporting period there were 2 changes to the ODCM. The first change was issued on January 15,1998 and incorporated the format of NUREG-0472, Radiological Effluent Technical Specifications for PWR's. This revision also included changes in the way effluent radiation monitor alert and alarm setpoints are determined as well as several minor editorial changes. The second revision was issued on June 18,1998 and incorporated a change to the elemental iodine fraction per EA-FC-94-048 for gaseous effluent releases. No changes were made to the PCP. l-10 11
'6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring More weight was given to iodine releases in the organic form due to an engineering study. This study showed that less percentage of iodine in the elemental form is released. This results in lower estimated iodine doses to the unrestricted area. 6.4 Noncompliance with Radiological Effluent Control Requirements This section provides a list of any event that did not comply with the applicable requirements of the Radiological Effluent Controls given in the Offsite Dose Calculation Manual (ODCM). Detailed documentation conceming the evaluations and corrective actions are maintained onsite. 6.4.1 Abnormal Gaseous and Liquid Releases There was one abnormal release during 1998. The release commenced on approximately April 24,1998 at 1750 during a refueling outage when an ammonia smell was detected by workers in Room 81 of the Auxiliary Building. An unmonitored release path was discovered that allowed containment air to be released into Room 81. A Copus blower was attached to the secondary handholes of 'A' steam generator, drawing in ambient containment air and feeding it through the steam generator and out through disassembled valves YCV-1045A and YCV-1045B ir,to Room 81. Containment integrity was not required at the time of the release. It is assumed the condition lasted for 540 minutes and was terminated on April 25,1998 at 0250 when Operations secured the Copus blower. A Radiological Analysis was performed by Chemistry and calculations showed that the release did not exceed Technical Specification requirements. The total amount of radioactive material potentially released was calculated as 4.64E-04 Curies. The ECL fraction was G.6E-06 which is well below ? the 5 times ECL allowed by Technical Specifications. Condition Report 199800906 was generated to document the event. 1-11
- l 6.4.2 Failure to Meet Specified Sampling Requirements During 1998 there were no instances in which specified sampling requirements were not met.
6.5 Modifications to Liquid and Gaseous Waste Traatment and Ventilation Exhaust Systems 1 During the reporting period no design modifications were approved or implemented involving major changes to the l Liquid and Gaseous Waste Treatment Systemt. l 6.6 Meteorological Monitoring Program ' A summary of hourly meteorological data, collected during 1998, is retained onsite. This data is available for review by the Nuclear Regulatory Commission upon request. Joint Frequency tables are included in Section Vil, Attachment 2. Real time hourly meteorological data is used to calculate the annual air effluent dose to individuals. For quarterly estimates during ba year an annual average X/Q is used which is an aver W the highest X/Q's calculated for each of the previous. . fears. 6.7 Assessment of Doses 6.7.1 Doses Due to Liquid Effluents g Total body, skin, and organ dose for liquid releases were calculated in mrem for all significant liquid pathways using the annual configuration of the LADTAP ll program. The site discharge location was chosen to present a most conservative estimate of dose for an average adult, teenager, child and infant. l < A conservative approach is also presented by the { assumption that Omaha and Council Bluffs receive all ' drinking water from the Missouri River. The LADTAP 11 program in its annual configuration was also used to calculate the total body and organ doses for the population of 760,413 within a 50 mile radius of the plant. The results of the calculations are j listed in Section V. I
)
1-12
1 p. k The dose due to liquid effluents for total body and critical organ are also calculated quarterly using the methods in the ODCM, The results are listed in Section 11. 6.7.2 Doses Due to Gaseous Effluents Total body, skin and organ doses from ground releases were calculated in mrem to an average adult, teenager, child, and infant in each receptor using the annual configuration of the GASPAR 11 program. Also, the doses to the same groups, in units of mrad, due to gamma and beta radiation carried by air, were computed using GASPAR 11. The GASPAR ll program in its annual configuration was also used to calculate the ALARA integrated population dose summary for the total body, skin and organ doses in person-rem for all individuals within a 50 mile radius. The results of the calculations are shown in Section IV. The dose due to gaseous effluents for total body gamma and beta noble gas air dose are calculated quarterly using the methods in the ODCM with an annual average X/Q. The results are listed in Section ll. 6.7 3 Doses Due to 1-131, Tritium and Particulates with Half Lives Greater than 8 days. The doses due to 1-131, Tritium and Particulates with half lives greater than 8 days for total body and critical organ dose are calculated quarterly using the highest of infant or child dose fr ctors and an annual average X/Q. The results are listed in Section ll for inhalation, ground and food. 6.7.4 Direct Radiation Dose to Individuals and Populations Direct radiation doses attributed to the gamma radiation emitted from the containment structure were not obser/ed above local background at any TLD sample locations for this annual period. 1-13
6.7.5 40 CFR 190 Dose Evaluation ODCM Radiological Effluent Controls requires dose g evaluations to demonstrate compliance with n 40 CFR Part 190 only if calculated yearly doses exceed two times the annual design objectives for liquid and/or gaseous effluents. At no time during 1998 were any of these limits exceeded, therefore no evaluations are required, l I 1 I I l-14 l
)
1 I I l I SECTION ll QUARTERLY DOSES FROM EFFLUENTS
\
l l Offsite Dose Calculation Manual ! l l l l January 1,1998 - December 31,1998 11- 1 m
I Quarterly Dose Calculation Results January 1,1998 through December 31,1998 i i With the implementation of the Fort Calhoun Station Radiological Effluent Technical Specifications (RETS) on October 1,1985, radiation doses in the unrestricted area from liquid and gaseous effluents must be calculated on a quarterly basis in accordance with the Offsite Dose Calculation Manual (ODCM). These calculations are performed to ensure the annual dose limits delineated in Appendix i of 10 CFR 50 and implemented by RETS are not exceeded. If the results of the quarterly calculations exceed fifty percent (50%) of the annual limits of Appendix 1, actions are taken to l reduce effluents so that the resultant doses do not exceed the annual limits during the remainder of the year and a special report is submitted to l the Nuclear Regulatory Commission. This section presents the results of the quarterly dose calculations performed during the period January 1,1998 through December 31,1998. Details are shown as to the types, sources and resultant doses from the effluents, the annual limits and a comparison to the annual limits. The quarterly totals are well below the 50% annual dose acceptance criteria, in addition, the summation of the quarterly totals shows OPPD to be less that the annual limits and in compliance with the regulations and the ODCM. I I r l ll-2 l L
i FC-421 FORT CALHOUN STATION R5 CHEMISTRY FORM 1 E( QUARTERLY FORT CALHOUN CDMULATIVE DOSE CONTRIBUTION FIRST QUARTER FROM RADIOACTIVE EFFLU 1998, DOSE PROJECTIONS El I critical Organ I , I. Liquid Effluents: Batch: Total (mrem Dose Body) 3.08E-02 ' Dose (mremT 3.89E-02 ll m l 2.69E-04 3.16E-04 Continuous: . 3.92E-02 l Totals: 3.11E-02 ODCM Annual Obj: 3.00E+00 1.00E+01 l Percent of ODCM Annual Obj: i 1.04 t 0.39 % This Quarter: 0.39 % Year to Date: 1.04 t Total Body Gamma Total Body Beta II. Gaseous Effluents: Dose (mrad) Dose (mrad) 1.88E-01 5.65E-01 A. Noble Gas Air Dose: CDCM Annual Obj: 1.00E+01 2.00E+01 Percent of ODCM Annual Obj : ; 1.88 % 2.83 % l This Quarter: 2.83 % ) Year to Date: 1.88 % B. I-131, H-3, and Particulates Critical Organ with Half-lives > 8 Days: Total Body) Dose (mrem Dose (mrem) l 4.34E-05 4.77E-04 g Inhalation: 2.03E-04 6.79E-03 g Ground and Food: .. ... 2.46E-04 7.27E-03 Totals: , ODCM Annual Obj: 1.50E+01 1.50E+01 E Percent of ODCM Annual Obj : g,
.. .. ........._......-___ l O.00 t 0.05 t This Quarter: 0.00 t 0.05 t Year to Date:
Reviewedtby: i II-3
FORT CALHOUN STATION FC-421 CHEMISTRY FORM R5 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN SECOND QUARTER 1998, DOSE PROJECTIONS I. Liquid Effluents: Total Body Critical Organ Dose (mrem) Dose (mrem) Batch: 1.92E-01 2.59E-01 Continuous: 8.00E-05 1.28E-04 Totals: 1.92E-01 2.59E-01 ODCM Annual Obj: 3.00E+00 1.00E+01 Percent of ODCM Annual Obj: I This Quarter: Year to Date: 6.40 % 7.44 % 2.59 % 2.98 % I II. Gaseous Effluents: Total Body Gamma Dose (mrad) Total Body Beta Dose (mrad) A. Noble Gas Air Dose: 4 b9bbk 138b+bb ODCM Annual Obj: 1.00E+01 2.00E+01 Percent of ODCM Annual Obj: This Quarter: 4.09 % 6.90 % , Year to Date: 5.97 % 9.73 % ' B. I-131, H-3, and Particulates I with Half-lives > 8 Days: Total (mrem Dose Body) Critical Organ Dose (mrem) Inhalation: 6.87E-04 1.14E-01 I Ground and Food: 5.43E-03 1.93E+00 Totals: 6.12E-03 2.04E+00 ODCM Annual Obj: 1.50E+01 1.50E+01 Percent of ODCM Annual Obj: i ________ This Quarter: Year to Date: 0.04 % 0.04 % 13.63 % 13.68 % 1 Reviewed by: I 1 II-4
FORT CALHOUN STATION FC-421 I CHEMISTRY FORM R5 ) 1 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN THIRD QUARTER 1998, DOSE PROJECTIONS 1 l I. Liquid Effluents: Critical Organ
------------------- Total Dose (mrem Body) Dose (mrem) E
___________ ______________ g Batch: 4.56E-02 6.21E-02 Continuous: 0.00E+00 0.00E+00 Totals: 4.56E-02 6.21E-02 ODCM Annual Obj: 3.00E+00 1.00E+01 Percent of ODCM Annual Obj This Quarter: 1.52 % 0.62 % Year to Date: 8.96 % 3.60 % II. Gaseous Effluents: Total Body Gamma Total Body Beta Dose (mrad) Dose (mrad) A. Noble Gas Air Dose: 1.50E-03 o.82E-03 ODCM Annual Obj: 1.00E+01 2.00E+01 Percent of ODCM Annual Obj: This Quarter: 0.02 % 0.03 % Year to Date: 5.98 % 9.76 % B. I-131, H-3, and Particulates with Half-lives > 8 Days: Critical Organ Total Dose (mrem Body) Dose (mrem) Inhalation: 1.16E-05 1.16E-05 Ground and Food: 5.39E-05 5.39E-05 Totals: 6.55E-05 6'.55E-05 ODCM Annual Obj: 1.50E+01 1.50E+01 Percent of ODCM Annual Obj: This Quarter: 0.00 % 0.00 % Year to Date: 0.04 % 13.68 % Reviewed by: [/ 11-5
l 1 FORT CALHOUN STATION FC-421 CHEMISTRY FORM R5 I QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN FOURTH QUARTER 1998, DOSE PROJECTIONS i I. Liquid Effluents: Critical Organ
------------------- Total (mrem Dose Body) Dose (mrem)
I Batch: Continuous: 2.15E-02 4.53E-05 2.80E-02 4.53E-05 Totals: 2.15E-02 2.80E-02 ODCM Annual Obj: 3.00E+00 1.00E+01 [$$_$. _ $$$ _ I This Quarter: 0.72 % 0.28 % ! { Year to Date: 9.68 % 3.88 % u I II. Gaseous Effluents: Total Body Gamma Dose (mrad) Total Body Beta Dose (mrad) A. Noble Gas Air Dose: 2.04E-03 5.58E-03 ! ODCM Annual Obj: 1.00E+01 2.00E+01 I Percent of ODCM Annual Obj: This Quarter: 0.02 % 0.03 % Year to Date: 6.00 % 9.79 % I B. I-131, H-3, and Particulates with Half-lives > 8 Days: Total Body Critical Or an S$$$__I[$$ _S$$I_$[$___ Inhalation: -2.04E-05 2.29E-05 Ground and Food: I _____...____.__ Totals: 9.44E-05 1.15E-04 1.37E-04 1.60E-04 ODCM Annual Obj: 1.50E+01 1.50E+01 Percent of ODCM Annual Obj: I This Quarter: Year to Date: 0.00 % 0.04 % 0.00 % 13.68 % I Reviewedby:{7$kf) l II-6 I I
SECTION 111 RADIOLOGICAL EFFLUENT RELEASES Technical Specification (5.9.4a) Table 111-1 Table lll-2 Batch Liquid and Gas Release Summary Abnormal Batch Liquid and Gaseous Release Summary l Table 111-3 Gaseous Effluents - Summation of all Releases Table ill-4 Gaseous Effluent Releases - Batch Mode Table 111-5 Gaseous Effluent Releases - Continuous Mode Table lil-6 Liquid Effluents - Summation of all Releases Table ill-7 Table lil-8 Liquid Effluent Releases - Batch Mode Liquid Effluent Releases - Continuous Mode l Januay 1,1998 - December 31,1998 I I I m., g
r 9 r e 0 1 4 9 2 0
+
e 7 8 1 0 4 t 2 8 9 2 8 t 1 1 5 3 8 r 5 1 1 E r 2 4 1 3 a 2 3 a 0 5 4 _ u 6 u 7 _ Q 3 Q _ h 1 h _ t t 4 - 4 r 9 r e 8 7 2 6 0 0 e 6 6 5 2 8 t 2 0 6 3 1 + t 1 9 6 6 6 r 8 1 1 1 E r 1 4 2 2 a 3 3 a 8 5 4 Y u 6 u 6 R Q 3 Q A d 1 d M r r M 3 3 U S 8 9 E 9 1 S 1 r 8 r
- A e 3 2 7 8 5 0 e 9 4 9 2 7 1 E R t 7 4 0 3 + t 3 0 8 6 L E r 3 3 2 E r 1 0 3 6 1
a 7 1 4 a 2 7 2 1 E B u 1 3 u 9 - R M Q 2 Q I E . I E S C d 3 d U E n n I L 2 2 B O D A E T S H A G G U r 9 r O e 2 5 3 f 5 0 e 9 1 1 8 5 D R t 4 9 6 3 8 + t 1 0 1 6 3 N H r 6 1 1 E r a 2 4 1 1 A T a u 5 4 3 u 0 6 5 3 D Y Q 2 Q I R t 1 t U A s s Q U 1 1 I N L A J H + + - : C ) n
+ )
n
)
n )
- )
n T : i
)
n i sn
)
. i p i A ) m i m di ) m i m B
i n ( ( m ( om i / i n ( ( m ( m e e rs m e e ( s s s ei ( s s s a e a P m( a e a s e s e s e s e e l a l g e l a l s e e e nr s e e e a R l R i e a R l R e e rv e e l h R h ui l h R h e c c DR e c c - R t h t R t h t a c a wi s a c a s h B t B or e h B t B e c a l u c c a c t a B a F o r t a B a r s a s u b a u e B r r r ms o e B r o r o r o o s o o o ai S s a r S a r eM f f - l l e f o f d f d f d r t e l l l e f o f d d d l e o o o Sh A e o o o A R d i i i t R d i i i o r r r n s o r r r s h i e e e oo e h i e e e e c r P P P i t s c r P P P e a e - s a e t B a P e m e m e m t n l ui l e e t B a P e e m e m e m l e i i i i e i i i e f m T T T D s R f m T T T R o i a o i T m e m ee s T m e m d r u g u gl u r u g u i e l m a m a e o e l m a m u b a i r i rR e b a i r i q m t x e n e s m t x e n i u o a v i vf a u o a v i L N T M A M A o G N T M A M A S B. 5 - 1 2 3 4 6 1 2 3 4
4 R 0 0 0-E 0 T 0 + 0 E ' R E 0 A 0 0 U 0 0 Y Q R A M M 3 U R S 0 0 E 0 0 E T + + E S R 0 E 0 A A 0 0 0 E 0 L U 0 0 E Q - R S U O E _ 2- S 2 A _ I I R 0 4 0- - I G E 0 3-E D T 0 + 1 E E L N R 0 4 6 1 1 _ B A 1 _ A A U 0 0 4 _ T D Q I U - Q I L 1 H R C E 0 0 T T 0
+
0
+
A R 0 E 0 E _ B A 0 0 L U 0 0 A Q 0 0 M R O N B A i C d i C d e s e s - s a s a e s e e s e a e l e a l e l r l e r e y e y r i t r i t f v f v o i t o i t s r c r c _ d b e a s b e a i u q m l t a e s m l t a i u o a u o L N T G N T A B
TABLE III-3 GACL'OUS EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 1998 1st Ouart er 2nd Ouarter 3rd Ouarter 4th Ousrter A. Fission & Activation Gases Total Releast IC1): 1.54E+03 3.74E+03 1.23E+01 1.28E+01 Avg. Release Late for period (uC1/sec): 1.98E+02 4.75E+02 1.55E+00 1.61E+00 Percent of ODCM Limit (t): * * *
- Total Errors 3.31E+01 B. Zodines Total Release (C1): 1.10E-04 2.12E-02 0.00E+00 5.09E-07 Avg. Release Rate for period (uci/sec): 1.42E-05 2.70E-03 0.00E+00 6.41E-08 Percent of ODCM Limit (t): * * =
- Total Errors 3.47E+01 C. Particulates Total Release (C1): 1.42E-02 0.00E+00 0.00E+00 0.00E+00 Avg. Release Rate for period (uCi/sec): 1.83E-03 0.00E+00 0.00E+00 0.00E+00 Percent of ODcM Limit (t): * * *
- Total Errors 6.17E+01 Gross Alpha 4.04E-05 3.09E-05 5.53E-05 3.07E-05 Total Errors 2.0GE+01 D. Tritium Total Release (C1): 1.72E-01 2.08E+00 4.83E-02 8.45E-02 Avg. Release Rate for period (uCi/sec): 2.21E-02 2.65E-01 6.07E-03 1.06E-02 Percent of ODCM Limit (%): e . . .
Total Error 2.70E+01 NOTE:
- Applicable Limits are expressed in terms of Dose.
see section II of this report. I l l L III-4 c
TABLE III-4 ; GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 1998 Batch Mode Nuc7 ides (Ci) 1st Quarter 2nd Ouarter 3rd Ouarter 4th Ouarter Fission & Activation Gases Argon-41 2.41E-01 4.74E-02 2.09E-01 2.14E-01 Krypton-85 4.72E+01 2.36E+02 7.15E+00 2.57E+00 Krypton-85M 5.36E-01 2.60E-04 3.95E-03 7.95E-03 Krypton-87 3.05E-02 0.00E+00 0.00E+00 0.00E+00 Krypton-88 4.16E-01 1.80E-03 1.09E-03 6.10E-03 Xenon-131M 1.50E+01 7.69E+01 3.74E-02 8.81E-02 Xenon-133 1.11E+03 3.31E+03 3.93E+00 8.69E+00 Xenon-133M 1.10E+01 1.93E+01 4.98E-02 1.01E-01 Xenon-135 9.05E+00 2.13E+00 1.45E-01 2.39E-01 Totals for Period: 1.19E+03 3.65E+03 1.1ET+01 1.19E+01 Iodines Iodine-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Totals for Period 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha Tritium 1.72E-01 2.08E+00 4.83E-02 8.45E-02 Gross Mpha 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NOTE: Nuclides not displayed or reported as 0.00E+00 were determined to be below the Lower Limit of Detection (LLD) values. f I III-5 l
TABLE III-5 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 1998 Continuous Mode I Nuclides (Ci) 2st Ouarter 2nd Ouarter 3rd Ouarter 4th Ouarter Fission & Activation Gases Argon-41 0.00E+0., 0.00E+00 0.00E+00 0.00E+00 Krypton-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Krypton-SSM Krypton-87 5.64E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Krypton-88 2.57E-01 0.00E+00 0.00E+00 0.00E+00 Xenon-131M 4.27E+00 0.00E+00 0.00E+00 0.00E+00 1 Xenon-133 3.38E+02 9.01E+01 4.87E-01 8.46E-01 Xenon-133M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xenon-135 8.99E+00 0.00E+00 2.95E-01 6.45E-02 Totals for Period: 3.52E+02 9.01E+01 7.83E-01 9.11E-01 Iodines Iodine-131 i Iodine-133 Totals for Period: 7.26E-05 1 77E-05 1.10E-04 2.09E-02 3.00E-04 2.12E-02 0.00E+00 0.00E+00 0.00E+00 5.09E-07 0.00E+00 5.09E-07 i Particulates Totals for Period: 0.00E-00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 Gross Alpha 4.04E-05 3.09E-05 5.53E-05 3.07E-05 NOTE: Nuclides not displayed or reported as 0.00E+00 were detemined to be below i the Lower Limit of Detection (LLD) values. I I L 1 I h
r TABLE 111-6 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 1998 let Ouarter 2nd Ouarter 3rd Ouarter 4th Ouarter A. Fission & Activation Products Total Release (No Trititan, Gas, Alpha) (C1): 1.61E-02 2.12E-01 1.02E-01 2.63E-02 A q Diluted Concentration (uCi/ml): 4.47E-11 1.33E-09 2.82E-10 7.30E-11 Percent of Listit (t) 10 CFR 20, App. B = 1.0E-06 (%): 4.47E-03 1.33E-01 2.82E-02 7.30E-03 3 Total Errors 3.17E+01 B. Tritiust Total Release (Ci): 1.21E+02 6.38E+01 2.69E+01 4.86E+01 " Avg Diluted Concentration (uci/ml): 3.35E-07 4.01E-07 7.42E-08 1.35E-07 Percent of Limit (t) 10 CFR 20, App. B = 1.0E-03 (%): 3.35E-02 4.01E-02 7.42E-03 1.35E-02 Total Errors 2.7E+01 C. Dissolved & Entrained Gases Total Release (Cil: 8.68E-02 6.14E-02 1.02E-02 2.8BE-03 Avg Diluted Concentration (uci/ml): 2.40E-10 3.86E-10 2.81E-11 7.98E-12 Percent of Limit () g ODO4 = 2.0E-04 (%): 1.20E-04 1.93E-04 Total Errors 3.58E+01 1.41E-05 3.99E-06 g D. Gross Alpha Radioactivity Total Release (C1): 8.53E-04 3.84E-02 7.54E-03 9.60E-03 i Total Error: 2.06E+01 E. Voltane of Waste Released Prior to Dilution (Liters): 3.66E+07 1.89E+07 4.03E+07 4.04E+07 F. Volume of Dilution Water This Period (Liters): 3.61E+11 1.59E+11 3.62E+11 3.61E+11 l III-7
TABLE III-7 LIQUID EPTLUENTS JANUARY THROUGH DECEMBER 1998 Batch Mode Nuclides fei) 1st Quarter 2nd Quarter 3rd Quarter 4th Ouarter Tission & Activation Products Chromium-51 2.25E-04 1.66E-02 2.98E-03 2.14E-04 Manganese-54 1.24E-04 1.70E 03 2.78E-03 7.12E-04 1ron-55 0.00E+00 9.45E-03 1.44E-03 3.86E-04 Cobalt-57 0.00E+00 3.18E-05 3.95E-05 2.05E-05 Cobalt-58 6.12E-04 2.'2E-02 1.02E-02 2.96E-03 1ron-59 0.00E+00 1. Set-04 2.14E-05 0.00E+00 Cobalt-60 4.56E-04 5.32E-03 7.21E-03 2.96E-03 Einc-65 0.00E+00 3.30E 05 0.00E+00 0.00E+00 Bromine 82 0.00E+00 7.65E-06 0.00E+00 0.00E+00 Strontium-90 0.00E+00 0.00E+00 0.00E+00 4.29E-06 Yttrium 90 0.00E+00 0.00E+00 0.00E+00 4.29E-06 Niobium-95 1.17E-03 1.86E-02 2.18E-02 3.96E-03 Eirconium-95 5.48E-04 9.79E-03 1.02E-02 1.56E-03 Niobium-95M 0.00E+00 1.62E-05 4.58E-05 0.00E+00 Technetium-99M 0.00E+00 3.65E-05 0.00E+00 0.00E+00 Molybdenum-99 0.00E+00 3.65E-05 0,00E+03 0.00E+00 Eunanium-103 1.94E-05 5.97E-04 1.68E-04 8.07E-06 Rhodium-103M 1.94E-05 5.97E-04 1.68E-04 8.07E-06 Rhodium-106 0.00E+00 0.00E+00 6.59E-05 0.00E+00 Ruthenium-106 0.00E+00 0.00E+00 6.59E-05 0.00E+00 Cadmium-109 0.00E+00 1.18E-05 0.00E+00 5.37E-05 Silver-110M 5.83E-04 1.31E-02 8.51E-03 3.51E-03 I Tin-113 3.12E-05 5.POE-04 7.30E-04 1.51E-04 Tin-117M 0.00E+00 1.36E 05 0.00E+00 0.00E+00 Antimony-124 1.39E-04 3.13E-03 4.49E-04 3.87E-05 Antimony-125 8.33E-03 5.14E-02 2.35E-02 5.65E-03 Antimony 126 4.32E-05 I 0,00E+00 0.00E+00 0.00E+0C lodine-131 1.12E 04 1.85E-02 0.00E+00 0.00E+00 Tellurium-132 0.00E+00 5.38E-05 0.00E+00 0.00E+00 lodine-132 0.00E+00 3.04E-05 0.00E+00 0.00E+00 lodine 133 0.00E+00 6.88E-06 0.00E+00 0.00E+00 I Cesium-134 Cesium-136 Cesium-137 1.64E-03 0.00E+00 2.01E-03 1.43E-02 7.93E 04 1.28E-02 3.72E-03 0.00E+00 3.92E-03 1.47E-03 0.00E+00 1.83E-03 LanthaarJm-14 0 0.00E+00 1.21E-03 2.85E-05 9.56E 06 I Sarium-140 Cerium-141 Cerium-144 0.00E+00 0.00E+00 5.1FE-05 6.13E 05 8.44E-04 3.18E-03 0.00E+00 3.43E 05 2.05E-03 0.00E+00 0.00E+00 4.07E 04 L Praseodymium-144 5.15E 0s 3.18E-03 2.05E-03 4.07E-04 Promethium-149 0.00E+00 3.35E 04 0.00E+00 0.00E+00 Hafnium-181 0.00E+00 1.35E-04 7.64E-05 M cE+00 Totals for Periode 1.61E-04 2.12E-01 1.02E 01 2.63E-02 Dissolved & Entrained cases
~
Argon-41 0.00E+00 3.00E 06 7.74E-06 0.00E+00 Ezypton-85 1.23E-03 2.91E-02 9.25E-03 1.74E 03 Erypton-85M 0.00E+00 0.00E+00 0.00E+00 1.13E-06 Xenon-131M 1.65E-03 5.58E-03 0.00E+00 0.00E+00 Xenon 133 8.36E-02 2.66E-02 9.34E 04 1.13E-03 Eenon-133M 2.68E-04 3.44E-05 0.00E+00 0.00Ee00 Kenon-135 8.95E-05 3.19E-05 2.54E-06 4.02E-06 Totals for Period 8.68E-02 6.14E-02 1.02E-02 2.88E-03 other, Tritium and Alpha Tritium 1.20E+02 6.38E+01 2.69E+01 4.80E,01 Alpha 3.47E-04 3.72E-02 7.54E-03 0.33E-03 [ NOTE: Nuclides not displayed or reported as 0.00E+00 were determined to be below the Lower Limit of Detection (LLD) values. III-8 u ~
TABLE III-8 l LIQUID EFFLUENTS JANUARY TULOUGH DECEMBER 1998 Contmuous Mode Nuclides (C1) let Ouarter 2nd Ouarter 3rd Quarter 4th Ouarter Tission & Activation Products Chromium-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nanganese-54 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 Iron-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cobalt-57 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cobalt-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iron-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cobalt-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Eine-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadne-82 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 Strontium-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Yttrium-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Niobium 95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Eirconium-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Niobium-95M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Technetium-99M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Moly * " "-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ruthenium 103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rhodium-103M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rhodium-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Ruthanium-106 0.00E+00 0.00E+00 0.00E+00 0.00E*00 Cadmium-109 0.00E+00 0.00E+00 0.00E+00 0.00E+00 silver-110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tin-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tin-117M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Antimony-124 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Antimony 125 0.00E+00 3.10E-05 0.00E+00 0.00E+00 j Antimony-126 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Tellurium-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodine-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Iodine-133 0.f0E+00 0.00E+00 0.00E+00 0.00E+00 Cesium-134 2.67E-05 0.00E+00 0.00E+00 0.00E+00 Cesium-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cesium-137 0.00E+00 1.60E-05 0.0sE+00 0.00E+00 1.anthanum 140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sarium-1Ce 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cerium-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cerium-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Praseodymium-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 frrf.ethium-149 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mafnium-181 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Periods 2.67E-05 4.70E-05 0.00E+00 0.00E+00 l Dissolved & Entrained cases i Argon-41 0.00E+00 0.0cE+00 0.00E+00 0.00E+00 l Egypton-85 0.00E+0L 0.00E+00 0.00E+0J 0.00E+00 i Erypton-85M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f i Eenon-131M 0.00E.00 0.00E+00 0.00E+00 0.00E+00 Eanon 133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 , Eenon-133M 0.00E+00 0.00E+00 0.0CE+00 0.00E+00 Eenon-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l other, Tritium and Alpha Tritium 8.78E 01 0.00E+00 0.00E+00 5.43E-01 Alpha 5.06E-04 1.23E-03 3.00E+00 1.27E-03 NOTE: Nuclides not displayed or reported as 0.00E+00 were determined to be below the Lower Limit of Detection (LLD) values. III-9
I I I SECTION IV DOSE FROM GASEOUS EFFLUENTS l Technical Specification 5.9.4a l GASPAR ll OUTPUT January 1,1998 - December 31,1998 I I [ [ [ IV-1
I Radioactive Effluent Releases - First, Second, Third and Fourth Quarters 1998 I GASEOUS EFFL'JENTS Radioactive gaseous releases for the reporting period totaled 5.31E+03 Curies of inert gas. The gross gaseous activity release rates were 1.98E+02 Ci/sec for the first quarter,4.75E+02 Ci/sec for the second quarter,1.55E+00 Ci/sec for the third quanar, and 1.61E+00 Ci/sec for the fourth quarter. l Radioactive halogens and Particulates with half-lives greater that eight days released l during the reporting period totaled 3.55E-02 Curies. The halogen release rates were 1.42E-05 C1/sec for the first quarter,2.70E-03 pCi/sec for the second quarter, 0.00E+00 Ci/sec for the third quarter, and 6.41E-08 Ci/sec for the fourth quarter. The release rate for Particulates with half-lives greater than eight days were l 1.83E-03 pCi/sec for the first quarter, 0.00E+00 Ci/sec for the second quarter, 0.00E+00 pCi/sec for the third quarter and 0.00E+00 Ci/sec for the fourth quarter. Total radioactive tritium released during the reporting period totaled 2.38E+00 Curies. Gross alpha radioactivity released during the ' reporting period totaled 1.57E-04 Curies. I I IV-2
I I POTENTIAL DOSES TO INDIVIDUALS AND POPULATIONS l A. Potential Annual Doses to Individuals from Gaseous Releases Total body, skin, and organ doses from ground releases were calculated in mrem to an average adult, teenager, child, and infant using the annual configuration of the GASPAR 11 program. Results to each receptor are shown in Tables IV-A-1 through IV-A-40. Also, the doses to the same groups, Table IV-B-1, in units of mrad, due to gamma and beta radiation carried by air, were computed using GASPAR 11. In its annual configuration, GASPAR ll assumes that all release rates are entered in curies per year (Ci/yr). The inputs to GASPAR ll for the annual period from January 1,1998 through l December 31,1998 were as follows: (1) All gaseous effluents I (2) Entrained gases (Ar-41, Xe-131M, Xe-133M, Xe-133, Xe-135M, Xe-135, Kr-85M, Kr-87, and Kr-88) from liquid effluents. (3) Annual "X/Q's" at the actual receptor locations which are corrected for j open terrain and plume depletion are calculated according to Regulatory 'E Guideline 1.111. Also included are annual deposition rates corrected for the open terrain factor.
- I (4) The production, intake and grazing fractions were as follows: 1.0 for leafy vegetables grown in garden of interest, 0.76 for produce grown in garden j of interest,0.5 for the pasture grazing season of the milk animal,1.0 for j pasture grazing season of the meat animal, and 8 g/m* for the air water (humidity) concentrations.
(5) All dose factors, transport times from receptor to individual, and usage factors are defined by Regulatory Guide 1.109 and NUREG-0172. (6) Site specific information, within five mile radius of the plant, on types of I receptors located in each sector was used. That is, if a cow was not present in a sector, then the milk pathway for that sector was not considered. If it was present, then the actual sector distance was used. l IV-3 l
I These inputs introduce a most conservative approach for the following reasons: (1) The open terrain and deposition corrections increase annual "X/Q's" by a factor ranging between 1.0 and 4.0 (2) The production, intake, and grazing fractions, as defined in the input 4 definition statement, represent the environment in an extremely conservative manner. gl B. Potential Semiannual Doses to Population from Gaseous Releases The GASPAR 11 program in its annual configuration was also used to calculate g the Al. ARA integrated population dose summary for the total body, skin, and g organ doses in man-rem for all individuals within a 50 mile radius. The population integrated dose is the summation of the dose received by all individuals and has units of man-thyroid-rem when applied to the summation of thyroid doses. The same inputs were used as in the individual case with the addition of the following: (1) A total population of 760,413 based on the 1990 census, was used to define the sector segments within a 50 mile radius of the plant. (2) Production of milk, meat, and vegetation are based on 1973 annual data for Nebraska as recommended by the Nuclear Regulatory Commission for use in GASPAR 11. l l I I lu E I
l ,l l 1 , liIIl l i11 lIl!1Il1l4 lll lll1 iiIil
+ : + - + : : + + : , +
_ _ _ - . - _ 5 .
- 2 _ 6 _ 5 _ - 5 _ 0 .
. 0 . 0 _ 0 _ 5 - -
N_E I K _ 5 _ 2 _
- E _
- - _ E -
E _ - - E 7 _ E - 2 ._ 1 6 - S _ 4 - 9 _ 2 . 9 _ 0 - - _ - . _ _ _ 1 _ _ 1 . 1 _ 2 _ 2 _ _ _ - _ . 2 _ . : _
+ e + - + + - + + + +
_ _ _ . - _ 5 - _ 3 . 6 _ 5 - - 5 _ 0 - _ 0 0 - 0 _ 5 0 - - - G _ - _. - - - - 0 - _ E - N _ E . E _ E - - . E _ 6 _ U _ O . 8 _ 7 _ E . 2 _ 1 - L _ 5 _ 2 _ 9 - _ 2 - 0 _ . - _ 1 - _ 4 - 1 _ 2 . - 2 _ -
. . _ . 2 - _ : -
+ - + : + : : + + : + +
_ - _ - : - . 3 _ D _ 3 _ 6 _ 3 - - 3 0 _ I _ 0 _ 0 _ 3 - 3 0 - - O _ - _ - _ - . 0 _- - . E _ R _ E - E . E . - - E _ 6 - Y _ 5 _ 8 - 2 . E - 9 _ 2 - H _ 4 0 _ 5 - 3 - T _ . . _ 2 - 1 - _ 4 - 1 _ 1 _ . - 1 . - _ _ _ - 1 . _ : -
+ : + - + : : + + : + +
_ . . - _ - 5 . _ 3 _ 6 . 5 0 _ Y _ 0 . 0 . 0 0 - - _ E _ - - - . - - - E . N _ E - E - E - - - E - 0 . oD 8 - 8 E - 9 - S I 5 7 _ 0 - 6 _6 _ N . _. - 0 - _ 1 . O K __4 4. 1 _ 2 - - 2 _ _ I _ - . : - T + - + : + : : + + : + + C . . - . - _ 5 -
' E - 3 . 6 5 _- - 5 _ 0 -
J _ 0 . 0 _- 0 _ 5 - 0 _ - - O R . - - - _ - _ 0 - _ E - R E . E - E _ E - - _ E _ 4 _ M P I V . 5 - 8 .
- 5 7 - E . 3 _ 5 _
5 - 0 . 4 _ _ E L _._ 44 - - - 7 - _ 1 - 1 S 1 . 2 - ' O - _ . - : _
- D + : + : + : : + + : + +
WA V 8 SD DA S E _ 3 _ 6 _
- 0 . 0 _
6 _ 0 _ 6 - - 0 - 5 I 9 - . 0 - - - E - V 9 AR N ._E . E _ E . - _ E I E 1 RL O _ 5 - 8 . 2 _ E _ 5 _ 1 - L LL B _ 4 WB A T L A U LI IM M _ 4 - 1 2 _ _ 8 -
- 2 9 -
0 4 _ _ 3 - N 3 + . + : + : : + + : + + N 20 - _ - _ r, - _ 5 - AS 0 - T . 3 5 _ _ 5 _ 0 - E E C _ 0 0 . 0 . 5 - 0 . - - M NR U E4 36 A _ - R _ E - E _
- _ - . 0 - - .
E _ - - E . E 7 O T_5 - 8 _ 2 _ E5 . H1 5. 7 - _ 4 . 5 _ 3 _ 4 ._ 1 . L 2 I . . . _ 3 _. 0 _ 1 . A .N = G . 4 . 1 . 2 . _ 2 . C = _ - - - 2 . : . M TNE OS ES E + : + : +
? : +
+ - +
_ 5 -
+
R L SO - 3 . 6 _ 5 - 5 _ 0 - O I 0 . 0 _ 5 . 0 - - FNM - _ - - E - O I8 D_RO RI Y_E D O D_ . E _
- _ 0 E _ -
4 _ E - 5 _ 3 - E _ 3 - M T5 A IAA_ B. _54
- 8 _
- 5 4 _ 1 _
. 5 .
2 1 _ C4 O LT A_MA TM T_4 -
+ :
+ : +
2 .
. : +
. 2
+ : +
2 -
+
A EA _ - - - : . _ _ M L A BG L_L_ Y A
- D _
T __ L D_A T _ N . I AA W .E . N _ E - I _ F . LADU __ EN - _ H L C E P UU NN NN TM H A.L . R _ U U . O . HA__T N C _ I _ _ N . W S AA P - P _ G _ I _ _ I l l lI\l ,
11j l!l lll!l lll l 1Ii1ll 1 ilII ill!l llJ
+ : + - + : : , , : , + _
. _ - _ - _ _ 5 . _.
_ 2 _ 5 4 _ _ 4 _ 0 . _. _ 0 _ 0 _- 0 4 . 0 _ - _ N _ - _ - _ - ._ 0 . - _ E _ I _ E _ E _ E _ - _ E _ 4 - K _ 2 _ 2 _ 0 _ E _ 7 _ 1 - S . 9 _ 1 _ 2 _ 1 _ 0 _ _ _ . _ _ 2 _ _ 6 _
._7 _ 1 1 _ _ 1 _ _
- . _ 1 . _ : _
+ : + : + : : + : + +
_ . _ : 4_ . 5 _ _ 2 . 6 _ 4 _. _ 4 _ 0 _ _ 0 . 0 _ 0 _ s _ 0 _ - _ G _ - - - _ - _ _ - _ E _ N _ E . E _ E . - u_E 0 . E _ 7 - _ 4 _ U.0 L.5 _ 6 . 2 _- 2 ._ 1 _ 2 _ 0 - 1 _
. G _
. 2 _ 9 _ 1 _ _ 1 _ _
- . - - 1 _ - : _
+ - + - + - - + + + +
_ . _ . - . _ 3 _ D . 2 _ 6 _ 3 3 _ 0 _ I _ 0 _ 0 _ 0 _.3 _.0 _ - _ O _ - _ - _ - _ 0 _ - . E . R _ E . E _ E . - . E . 9 _ Y - 5 . 6 _ 8 . E . 9 . 9 _ H . 4 _ 2 _ 6 _ 5 . . T _ . _ _ 9 _. 6 _ 6 _ 2 . 9 _ 5 _ _ 7 _ ._ _ _ - . 6 _ _ : -
+ : + : + : : + + : + +
_ - _ _ - _ _ 2 . 6 _ 4 _ _ 4 - 0 u EY_0 _ _ 0 .
. E -
0 _ 4 . 0 - -
- _ 0 E _ - _. E _ 7 _
- . E _ _
N D __ E 5 . 6 _ 9 _ E _ 4 _ 5 . S I _ . 2 _ 4 _ 0 _ 4 _ _ N K __2 4_. 9 _ _ _ 6 _ _ 8 _ O _ 1 . . 1 _ _ I _ _ - 1 . _ : - T + : + : + : : + + : + + C _ _ : _ . 5 - E ._ 2 _ 6 _ 4 ._ _ 4 _ 0 - J _ 0 _ 0 _ 0 _ 4 0 _ - O R - - _ - _ - _ 0 - _ E _- R E . E _ E _ E - - E . 2 _ P _ 6 _ 7 _.E - 9 _ 2 _ V I ._ 4 5 _ 2 - 3 _ 4 . 2 _ _ E L _ _ - - 4 . _ 8 _ 2 S _ 2 . 9 1 _ 1 _ _ O _ - _. _ _ : _
- D + : + : + - : + +: + +
A . . _ _ : _ _ 5 _ 6
- , S . 2 . 6 _ 5 _ _ 5 _ 0 _
V 8 SD _ 0 _ 0 _ 0 _ 5 - 0 . - _ - I 9 DA E _ - _ - _ - 0 - - . E V 9 AR N_E _ E _ E - E . 7 I E 1 RL O _ 5 _ 6 _ 8 . E ._5 _ 7 . L LL B _ 4 _ 2 _ 1 _ 6 _ 2 _ . B L LI _ _ . . _ 6 - _ 1 A A I M _ 2 _ 9 1 _ _- T U M - . . 1 - - : _ N 2 +: + : + : - + +: + + N 10 _ . . _ : _ _ 5 _ AS 0 - T _ 2 _ 6 . 4 _ _ 4 _ 0 _ E E C _ 0 _ 0 . 0 _ 4 _ 0 _ - _ NR E9 - _ - _ . 0 _ - _ E _ U O 71 A_E R _ E _ E - _ E _ 0 _ E _ 8 _ 2 _ H2E L N
- 3. 4 1
T.5 I . 4
. 6 _
2 _ 3 2 . 4 .
- 2 _
0 _ _ 6 - A .N = G _. 2 _ 9 - 1 - _ 1 _ - C = . - - 1 _ . : - OS E +: + : + : : + +: + + TNE ES . _ _ _ :
._ 4 _ 0 _
_ 5 _ R L SO . 2 - 6 _ 4 _ O I OD _ 0 _ 0 _ 0 _ 4 _ 0 _ - FNM - _ - _ - _ 0 _ - _ E O D_R_ Y ._ E - E _ E . - _ E _ 6 I2 T9 RI IA D.5 O
. 4
. 6 _
_ 2 _ 9 . E _ 0 - 0 2 . 3 . 2 - . A A B. _ _ _ . 7 _. 3 C1 O LT A_M TM A T_2 _
+: +
_ 9 _
+ : : +
1
- 1 _
+- +
1 _
+
A EA _ . . _ - _ _ _ BG _ . _ _ _ _ T _ L . _ T. _ D _ N . A L_L_ Y __ L N _ I C AA UU A_E W H _ M _ U _ AD
. D _
_ N _ LU.E E _ IL __ A H . N F ._ E NN T _ U _ O _ I _- P NN A_L _ R _ N . S AA P _P _ G _ I H A __ T ._ .C 1I l ill
,Il ll1il ,
n -
~ + - + : + .: + + : +
+
_ . _ _ : . _ 5 . _ 1 5 _ 4 _ _ 4 _ 0 . _ 0 _ 0 _ 4 _ 0 _ - .
- . - _ - _ 0 _ - _ E .
- N __EE I 0. E _ - _ E _ 5 K _ 4 8 . 7 _ E 0 _ 0 S 0 . 3 5 _ 9 4 _ _
. . _ 5 . _ 8 _
1 1 1 _ . 1 _ _
._ . 1 . _ : _
+ : + : + : : + + : + +
_ _ _ : _ _ 5 _ _.2 _ 5 _ 4 _ _ 4 _ 0 _ _ 0 _ 0 _ 0 _ 4 _ 0 _ - _ G _ - _ - _ - _ 0 _ - . E _ N _ E _ E _ E _ - _ E . 5 . U_3 _ 9 _ 3 _ 7 _ E _ 0 _ 0 . L _ 1 _ 5 _ 9 _ 4 _ _ _ _ _ _ 5 _ _ 8 _ _ 3 _ 1 1 _ _ 1 _
. _ _ 1 . : .
+ : + : + : : + + : + +
_ _ _ : . 3 5 3 _ _ 2 ._0 ._ D I __ 02 0 0 _ 3 _ 0 _ - _ O.E R Y
. E
. 3
- - _ 0 _ - _ E _
E _ - . E . 2 _ 0 _ E 1 . 2 _ H _. 22 1 _. 5 _ 7 0 - _ _ _ 1 - - 9 _ T ._ 3 _ 1 _ 7 - . -
+ : + : + : : +
_ ._9
+ : +
_ 4 -
+
Y2 5 _ 0 . 4 0 _.4 _ 4 _ 0 - _ 0 . - - N0E . E E - . - . - _ 0 _ - . E - E _ - _ E . 3 - 5 . E _ 9 . 1 - S
.N D.22._
I 3 1 .
. 9 _.
0 _ 1 _ 8 . 1 _ O . 1 . 1 _ _ 1 I K +._ 3 . . - 2 _ - : _ T : + : + : : + + : + + C _ _ _ : . 4 _ E _ 2 _ 5 _ 4 _. . 4 0 _
= J 0 _ 0 _ 0 _ 4 0 . -
_. - E _- O R P R.E E _ E _ _ 3 _
- _ 0 E _ - _ E 9 _ E 0 . 0 _
8 _ V __ 22 _ 1 I 7 _ 9 ._7 _ . E . 3 S O L.3 _
. 1 -
1 _ _ 8
. 1 .
_ 1
- .D + : + : + : : + + : + +
A _ . _ _ : . 5 - 7 S _ 2 . 5 _ 5 _ . 5 ._ 0 - V 8 SD . 0 . 0 . 0 - 5 . 0 _ - - - I 9 DA E - . - . - _ 0 _ - _ E . V 9 AR N_2 ._ E . 3E . E _ - . E _ 4 _ I E 1 RL O 6 _ E 7 _ 3 _ L LL B _ 2 1 5 . 9 _.9 _ _ B L LI _ . . . . 1 . _ 2 A A IM _ 3 1 . 1 - 2 . T U M . _ - 2 . : _
- N N
AS 10 0 - 2 + : + : + : : + _ 5 _
+ : +
5 .
+
NR E E1 E T.2-C 0 _ 0 _ 4 0 _ 4
- _ 0
. 4 0 . -
0 E _ U O b5 A ._ T_E.E R 2 . 3 _ _ E _ - _ E _. 2 _ 1 _ E _ 2 _ 1 _ H3 8. 5 - _ 2 _ 1 _ 6 _ 3 . 4 . _ L E 1 I _ _ _ _ 6 8 . A .N _ 1 _ 1 _ . C OS
=
E
=
G.3 _
+ 2 + : + : : +
. . 1 .
+
1
- +
+
TNE,L ES . - . _ . : . . 5 _ R SO 2 _ 5 . 4 _ 4 . 0 O I 0 _ 0 0 _ 4 0 . - _ FNM O D_ D Y - . - - _ 0 . - . E . O R D E . E E - _ E _ 6 I2 R_I O 2 3 _. 0 E _ 7 _ 2 T5 2 1 _ 7 . 5 . 5 _ . A C1 IAA_ A B.
. 1 _
_ 7 . _ 9 . O LT A_e Tp t T.3 + :
+ : + : : +
1
. 1 .
+
. 1 .
+ +
A EA _ _ . _ : _ _ - BG _ _ _ T L Y ._ _ _ D _ N A I L_L_ AA A W ._ _ D. _ N T_N.I F. L LU_E _ E
. LA C
E P UU NN NN TEU._O.HA_T H A M.U R AD N . H_.N. C I S AA P L_G P . I rll> lIII
, : + : + : : + , : + +
_ _ - _ : _ _ 6 _ _ 3 _ 7 . 5 _ _ 5 _ 0 _
. 0 _ 0 . 0 _ 5 _ 0 _ - _
N . - _ - _ - _ 0 _ - _ E _ I E _ E _ E _ - _ E _ 9 _ K _. 0 _ 0 _ 4 _ E _ 8 _ 3 _ S _ 3 _ 4 _ 4 _ 5 _ 2 _ _
. _ _ 4 _ _ 7 _
9 _ 7 _ 1 _ 1 _ _ _. . - . 1 . _ : _
+ : + : + : : + + : + +
. . _ . : _ _ 6 _
_ 3 7 _ 5 _ _ 5 _ 0 _ _ 0 0 _ 0 _ 5 _ 0 _ - _ G _ - _ - _ - _ 0 . - _ E _ N _ E _ E _ E _ - . E _ 9 _ U _ 2 _ 9 _ 4 _ E _ 8 _ 3 _ L _ 0 _ 0 _ 4 _ 5 _ 2 _ _ _ _ _ _ 4 _ _ 7 _ _ 3 _ 6 _ 1 _ 1 _ - _ - _ _ 1 ._ . : .
+ : + : + - : + + : + +
_ _ _ _ - . - 4 . D _ 3 _ 7 _ 4 _ . 4 - 0 _ I _ 0 _ 0 _ 0 _ 4 _ 0 - _ O _ - _ - _ - _ 0 _ - ._ E _ R _ E _ E _ E _ - _ E _ 8 _ Y _ 6 _ 9 _ 7 _ E _ 9 _ 0 _ H _ 8 _ 0 _ 5 _ 3 _ 8 _ _ T _ _ _ _ 0 _ _ 8 _ _ 2 _ 6 . 6 _ . 8 _ _
. _ - _ 8 . _ : -
+ : + : + : : + + : + +
_ _ . _ : _ _ 5 _ _ 3 _ 7 . 5 _ _ 5 _ 0 _ Y - 0 _ 0 _ 0 _ 5 _ 0 _ - _ E - - _ - _ - _ 0 _ - _ E _ N . E _ E _ E _ - _ E _ 2 _ D 6 _ 9 _ 7 - E _ 1 _ 0 . S I 8 _ 0 _ 7 _ 1 _ 7 _ N K _ _ _ _ 9 _ . 1 ._ O _ 2 _ 6 _ 1 . . . 1 . _ I _ . - _ 1 . _ : _ T +: + .+ * : + + : + + C _ . _ : _ _ 6 _ E . 3 _ 7 ._ 5 _ _ 5 _ 0 _ J . 0 _ 0 _ 0 _ 5 _ 0 _ - _ O R _ - _ - _ - . 0 _ - _ E _ R E _ E _ E _ E . - _ E _ 9 _ P V _ 6 _ 9 _ 4 _ E _ 4 _ 7 _ I _ 8 _ 0 _ 6 _ 2 _ 5 _ . E L _ . _ . _ 7 . _ 9 . 4 S . 2 _ 6 . 1 _ . 1 _ O - _ _ . 1 . - :
- D +: + : + : : + + : + +
A _ . _ : _ _ 6 _ 8 S _ 3 _.7 _ 6 _ 6 _ 0 _ V 8 SD _ 0 _ 0 _ 0 6 _ 0 _ - _ - I 9 DA E _ - _ - _ - . 0 _ - _ E _ V 9 AR N _ E _ E _ E . - _ E _ 5 _ I E 1 RL O _ 6 . 9 . 6 . E _ 0 _ 0 _ L LL B _ 8 . 0 . 3 - 1 _ 6 _ _ B L LI A T A U N IM M 3 _ 2 _ 6 .
+: + - + : : +
1 _ _ 9 _ 1 .
. 2 _
+ : +
_ 2 _
+
m N 20 _ _ _ . : _ _ 6 - AS 0 - T . 3 . 7 _ 5 _ 5 0 E E C . 0 . 0 _ 0 _.5 _ 0 ._ - NR E0 - . - _ - _ 0 _ - _ E . U 29 A R _. E _ E _ E _ - . E . 5 . O . T _ 6 _ 9 . 8 _ E . 0 H4E 6. 4 - . 8 _ 0 _ 4 9 . 3 _. 4 _. L N 1 I . _ _ 4 _ 7 _ A C .E
= G . 2 _ 6 _ 1 . 1 _ _
= . - . . 1 - _ : _
OS E +: + : + : : + + : + + TNE ES _ _ _ : _ 6 R L SO _ 3 _ 7 ._ 5 _ _ 5 _. 0 ._ O I OD _ 0 _ 0 _ 0 _ 5 _ 0 _ - _ FNM Y _ - _ - _ - _ 0 - - _ E _ O D_R_ D _ E _ E _ E _ - . E 5 _ - I2 RI O . 6 _ 9 _ 5 _ E _ 3 ._ 4 _ T8 . . 0 5 _ 0 _ A I A_ A B. _8 _
. . _ 6 _
4 _ _ 8 C4 A T_2 6 . 1 _ _ 1 _ _ O A_M - . _ . 1 . _ - _ LT TM +- + : + : : + + : + + A EA _ . . _ . _ _ _ BG _ . . _ _ _ T _ L A L_L_ Y_ A_E _
. D .
_ T _ _ D_N _ L _ N _ L _ A _ M I AA W _ N . LU _ E . I _ F _ C UU H _M _ U AD _ E . H _ N _ E NN P NN T __LU . O A_P R HA_T N _ _ C - I _ S AA P . G I _ _ . _ m m
s I q m
, : , : + : : + + : + +
_ _ _ _ : _ . 6 _ _ 2 . 7 _ 5 _ _ 5 . 0 _
, _ 0 . 0 _ 0 5 _ 0 - _
N _ - _ - . - 0 _ - E _
- I _ E . E . E _ - _ E _ 0
- K _ 5 . 3 2 _ E _ 4 _ 3 S _ 0 2 . 6 _ 3 _ 4 _ _
_ . _ 6 _ 8 _ _ 1 8 _ 1 _ _ 1 _
. _ _ 1 _ . - .
+ + : : + + : + +
4_ . . : _ _ 6 - _ 3 ._7 . 5 _ _ 5 _ 0 - _ _ 0 0 _ 5 . 0 _ - -
- _ - ._ - _ 0 - _ E G __E 0. E _
N E _ - E _ 0 _.
. 0 . 8 . 2 . E 4 _ 3
- U.4 L
. 7 .
6 3 . 6 _ 4 .
. 8
_ 3 6 _ 1 _ 1 . _- _ _ _ 1 _ . : .
+ : + : + : : + + : + +
_ _ : _ 4 _ D _ 3 _.7 4 _ _.3 _ 0 _
- I O
R _ 0 _ 0
. E _ E _
0 _ 4 _ 0 _ - .
- _ 0 _ - _ E .
E _ - _ E _ 4 _ Y . 2 _ 8 _ 3 _ E _ 1 _ 1 _ H . _ 7 4 . 0 _ 0 _ . _ T2 3 . i .
. 7 1 _
. _ 1 -
- 9 _
t _
. . . . 9 _ - : -
+ : + : + : : + + : + + -
. . : . _ 5
_ 3 ._7 5 _ 5 . 0 _. Y _ 0 . 0 0 5 _ 0 - _ E _ - . - . - 0 _ - E N . E . E . E . - E . 5 D 2 8 0 _ E 3 _ 1 _ S I 2 7 _. 0 _ 5 _ 9 _ _ N . . . . _ 1 _ . . 1 _ O I K.3 _
. 6 .
2 _
- 2 .
_ 1 . T + : + : , : + + : + +
- C E~
J _ 3 . 7 _ 0 _ 0 5 _ 0 _ 5 _ 0 _ - _ _ 5 ._0 _ 5 _ O R _ - _ - _ - . 0 _ - _ E R E . E _ E _ E - _ E _ 0 _.
.P V . 2 _ 8 _ 4 E . 4 . 1 _
I . 2 _ 7 _ 8 _ 4 . . .
- 5 E
S O L _ _ 3 _ 6 1 _ _ 9
- 1 .
._ 7
_ 1 _ 1 _
- D + : + : + : : + + : + +
A _ _ _ : _ 6 . 9 S . 3 _ 7 _. 6 _ _ 6 0 . V 8 SD . 0 _ 0 _ 0 _ 6 _ 0 . - _ -
- I E
9 9 1 RL DA AR E _ - _ - _ N ._ 2 _ 8 O E _ E .
- _ 0 E _ -
4 . E 4
- _ 8 _
- 2 .
V I L LL B 2 _ 7 ._ 5 . 7 . E ._ 9 3 - B L LI _ 1 . _ 2 - A A IM . 3 6 _ 1 ._ . _ 2 _ - T U M - _ - . 2 _ . : . N 3 +: + : + : : + + : + + N ,20 _ _ . . : _ 6 . AS 0 - 3 _ 7 5 5 _ 0 _ NR U O E E3 25 E T ._ 0 C A R _ E _ E . T _ 2 . 8 _ _ 0 0 5
- . 0 _ - - E _
E . - . E . 7 _ 6 . E . 6 _ 0 - - _ H5 8. 5 - _ 2 . 7 _ 6 _ 7 . 4 3_
.L .1 I . . 6 . 8 _
A .E -= G . 3 6 . 1 1 . C ~
- . . _ _ 1 . : -
OS E +: + : + : : + + : + + TNE . ES _ _ . . : . _ 6 SO
.. R L 3 _ 7 . 5 . 5 _ 0 O I OD 0 _ 0 . 0 5 0 _ - _
FNM O I9 D_R_ RI Y.E2-D O
. E
. 8 _
- 0 _ - . E _
E . - _ E . 0 _ 5 _ E1 5 _ T A 6. .A.L_ IA . 7 _ T2 7 _ 0 6 _ B. _ 8 . _ 9 . C4 . 3 6 1 . . 1 . . A.9 O . . . 1 _ . : - 9 LT TP +: + : + : : + + : + + A EA . _ _ _ : . . L B.G L.L_ Y _ . T. N A I C AA UU A.E W H M_U _ D _ _ N _ LUT.N_ID_A. AD L E E _ L _ F E NN _ O _ HA P S NN AA T.U A P . LP ._ G _ I R _ N T.CH.IN
!,lf1lj
E
+ : + : + : : + + : + +
. _ _ . : _ . 5 _
_ 2 _ 6 _ 5 _ _ 5 . 0 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ - _ N _ - _ - _ - _ 0 _ - _ E _ I _ E _ E _ E _ - _ E _ 6 _ K _ 1 _ 8 . 7 _ E _ 2 _ 1 _ S _ 5 _ 3 2 _ 9 _ 0 _ _ _ _ _ 2 _ . 1 _ _ 1 _ 1 2 _ _ 2 . _
. _ _. . 2 . _ - _
+ : + : + : : + + : + +
_ _ _ . : _ 5 _ _ 2 _ 6 _ 5 _ _.5 _ 0 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ - . G _ - _ - _ - _ 0 _ - _ E _ N _ E _ E _ U _ 4 _ 4 _ E _ - _ E _ 6 _ 7 _ E _ 2 _ 1 _ M L _ 9 . 1 _ 2 _ 9 _ 0 _ _
. _ . _ _ 2 _ _ 1 _
. 4 _ 1 _ 2 _ 2 _ _
. _ _ 2 . _ : _
+ - + .+ .: + + : + +
_ . _ : _ . 3 _ D _ 3 . 6 3 _ _ 3 0 _ I _ 0 _ 0 . 0 _ 3 _ 0 _. - _ O - _ - - _ 0 _ - _ E _ R E _ E E _ - . E 1 _ Y _ B . 4 _ 6 _ E _ 4 3 . H _ 6 . 1 _ 0 _ 0 _ 4 _ _ T _ _ _ _ 3 _ _ 1 _
. 4 _ 1 _ 1 _ . _ 1 _
. _ - . 1 . : _
+ - , : + : : + + : + +
_ . _ _ - . . 5 _ _ 3 . 6 _ 5 _ . 5 . 0 _ _ 0 _ 0 _ 5 _ 0 . - _ Y E __ 0- _ - _ - _ 0 _ - E _ E . - _ E _.2 _ S N_86 D I _ _ E _ E _ _ 4 _ _ 1 _ 1 . E _ 1 _ 6 _ 8 _ 3 _ 7 _ _ N K _ _ . _ _ 0 _ _ 1 _ O _ 4 _ 1 _ 2 _ _ 2 . _ I _ . . . 3 _ . : . I
+ : + : + : : + + : + +
C _ _ . _ - _ _ 5 _ E _ 3 _ 6 _ 5 _ _ 5 _ 0 _ J _ 0 _ 0 _ 0 _ 5 _ 0 . - _ O R _ - _ - _ - _ 0 _ - E _ R E . E _ E _ E . - _ E 5 _ P V . 8 _ 4 _ 8 . E _ 5 5 _ I _ 6 _ 1 _ 5 _ 2 _ 4 _ E L _ . _ _ 7 _ . 1 _ 6 S _ 4 . 1 2 _ _ 2 _ _ O - _ ._ . 2 . . : -
- D + : + + : + + : + +
A _ _ _ _ - _ _ 6 . 0
- , S . 3 _ 6 _ 6 _ _ 6 _ 0 _ 1 SD -
V 8 E 0 _ 0 _ 0 6 . 0 _ - _ V I 9 DA - 0 . - _ E _ 9 AR N _ E _ E _ E - E _ 2 _ I E 1 RL O _ 8 _ 4 _ 1 _.E 1 _ 3 _ L LL B _ 6 _ 1 _ 2 _ 0 _ 2 _ _ B L LI _ . _ . 1 _ _ 3 _ A A IM _ 4 . 1 . 2 . _ 4 _ T U M . _ - _ 3 _
+
N 3 + : + : + : : + + : + N 20 . _ _ _ : _ _ 5 _ AS 0 - T _ 3 _ 6 _ 5 _ _ 5 _ 0 _ E E C _ 0 _ 0 _ 0 _ 5 _ 0 _ - _ NR E1 A ._
- _ - _ - _ 0 _ - _ E _
U R E . - . E _ 7 _ 10 E _ E . O T _ B _ 4 2 . E . 5 _ 1 _ H6E 6. 8 - _ 6 _ 1 _ . 3 _. 5 . 0 _ . _ 3 _ 1 _ L S 2 I _ _ A .E = G _ 4 _ 1 2 _ _ 2 _ C = . _
+: + : + : : +
. _ 2 .
+ + +
OS E : TNE ES _ _ . - _ _ 5 _ R O L I SO _30 _ _0 6_ _. _ 5 _ _ 5 _ 0 _ 0 _ 5 _ 0 _ - _ M FNM O D_ D _ - _ - _ - _ 0 _ - _ E _ O I0 R_I R Y_E D O _ 8 _ 4 _ _ E _ E _ - _ E _ 4 _ 5 _ E _ 6 _ 3 _ T2 _ 6 _ 1 . 4 _ 2 _ 2 . _ A I A_ A B. _ _ . . _ 5 _ . 1 _ C4 A T_4 _ 1 2 _ _ 2 . O A_M . _ _ 2 _ LT TM +: , : + - : + + - + + A EA _ . . _ - . _ _ L A BG L_L_ Y A
. D _
T.N L D _ N L _ A _ T_ _ M AA W . E _ I _ F _ I C UU H _E . N _
.M _ U _ AD LU_E H __ IN. _ _
E P NN NN T .U _ O _ HA _ AL _ R _ N _ T_C _ S AA P P _ G _ I _ _ _ M M-
,3-.
, : , t + : : + + : +
. _ _ _ : . s_ 5 _
. 1 _ 5 _ 4 _ 4 _ 0 _
0 _ 0 _ 0 _ 4 ._0 _ - _ N.E I K . 1 . 3 _
. E _
- _ 0 _ - _ E _
E _ - _ E 2 _ E _ 6 1 _
._8 _
_ 3 _ 5 _ 4 _ 3 _ _ S ._ 0 . _ _ 5 _ _ 7 _ _ 1 . 2 . 1 _ _ 1 . _ _ _ . _ 1 . _ : .
+ : + : + : : + + : + +
_ _ _ _ : . . 5 _ _ 2 _ 5 . 4 _ . 4 _ 0 _ _ 0 _ 0 . 0 _ 4 0 _ - _ G _ - _ - _ - _ 0 _ - _ E _ U.E N . 9 L . 2 ._ 9 _ _ E _ 2 _ E _-.6_ 2 _ E _ 5 _ 4 _ 3 . B _ 1 _ 8 _ _ _ . . 5 _ . 7 _ _ 3 _ l' . 1 _ 1 _ _ _ _ . 1 _ _ : _
+ : + : + : - + + : +
. _ _ _ : _ 6_ 3
. 5 _ 3 _ _ 3 _ 0 ._
D I __ 02 0 _ 0 . 3 _ 0 _ - _ O _ - - _ - _ 0 _ - _ E . R _ E . E _ E _ - _ E _ 2 Y _ 2 2 _ 5 . E _ 2 _ 9 ._ H _ 9 _ 8 _ 8 _ . _ _ 2 ._ 8 . 8 _ T __3 1_ 1 . 7 _ _ 9 _ _ _ _ _ . 8 - _ : . _
+ : + : + : : + + : + +
. _ . _ : _ _ 4 _ -
. 2 _ 5 _ 4 _ _ 4 _ 0 . -
Y _ 0 _ 0 _ 0 _ 4 0 . - _ - E _ - _ - _ - . 0 _ - E _ - N _ E E _ E - - E 9 _ S D _ I _ 2 ._2 . 1 _ 9 _ 9 8 E . 3
. 4 . 8 ._ 0 N K _ _ . _ 0 . _ 1 O _ 3 _ 1 _ 1 _ 1 _
I _ _ . . 2 _ . : T + : + : + : : + + : + + C _ _ _ . : . _ 4 . E . 2 _ 5 _ 4 . . 4 _ 0 _ J . 0 _ 0 _ 0 . 4 _ P . - _ _ O R _ - _ - _ - . 0 _ - _ E _ R P E . E . E _ V . 2 . 2 _ E . - _ E _ 5 _ 4 E _ 4 0 _ - I . 1 _ 9 . 7 3 _ 6 _ - E L . _ . _ 1 . 7 S . 3 . 1 . 1 ._ 8 _ 1 - O . . . - 1 . . : - _
- D + : + : + : : + + : + + _
A- _ _ _ . : _.5 _ 5 . 1
, S _ 2 . 5 _ 5 _ 0 _ 1 -
V 8 SD _ 0 . 0 _ 0 5 _ 0 _ - _ - - I 9 DA E _ - . - . - . 0 _ - _ E _ V 9 AR N _ E . E . E - - . E . 7 _ I - E 1 RL O _ 2 2 . 0 _ E 7 . 2 . L LL B _ 1 9 . 5 . 2 ._8 . B L LI _ . . . _ 1 _ _ 2 . A. A IM _ 3 1 . 1 _ . 2 . . _ T. U M . _ - 2 . . : . N 2 + : + : + : : + + + + _ N - 10 _ _ _ . : . . 5 . AS NR E 0 - E4 E T_2- .._ 5-0 ___ C _ 4 _ 0 _ 4 _ 0 _ 4
- _ 0 _ - . E _
0 . U 53 A R __E 0. E _ E _ - . E 7 . 7 ._8 . O H7 L E.
- 7. 5 1
T_1 I _ _ 2 _ 2 _ 9 _ 6 _ E 5 . 8
. 5 3 _
_ 7 _ A C .S
= G _ 3 . 1 . 1 . 1 _ ..
= _ . . . 1 . - : _
OS E. + : + : + : : + + : + + TNE ES . . . : _ _ 5 _ R L SO 2 . 5 . 4 _ 4 _ 0 O I _.0 . 0 . 0 4 _ 0 . - FNM WD_ _ - . - . ._0 _ - . E _
.O .R Y_E D . E .
E _ - _ E 8 _
._9 _
IM T A PI IAA_ O_1 B. _ 2 . 2 . 9 . 5 _ E _ 2 6 _ 9 _
. 6 _
5 -
. 8 _
C1 A T3 _ . 1 . 1 . _ 1 . _ O A_4 . . . 1 . . : _ LT TM + : + : + : : + + : + + A EA . . _ _ : . . _ BG _ . _ . T _ L Y _ . _ . ._ N . L_L_ A A I AA W
. D .
E . N . L T_N.ID_A LU_E _ E
. L
_ F . C E P UU NN NN TMO U.HA.T.C_IH_N. H ALR U
. . AD
. N S AA P P G . I _ . _ .
}
+ : + : , : : + + : +
_ _ _ _ : _ 5 ._ _ 1 _ 5 _ 4 _ 4 _ 0 _ _ 0 _ 0 0 _ 4 0 _ - _ _ - _ - - _ 0 _. - _ E _ N_E I 9 _ 5 _ E . E _ - _ E _ 6 _ 4 _ E _ 3 _ 9 _ K S ._ 2 _ 4 9 _ 6 _ 7 _ _ _ _ _ 9 _ _ 9 _ 1 _ 5 _ 1 _ _ 1 _ _
. 1 _ _ : _
+ : + + : : + + : +
_ _ : _ _ 5 ._ _ 2 _ 5 4 _. _ 4 _ 0 _ _ 0 _ 0 . 0 _ 4 _ 0 _ - _ G _ - _ - - 0 _ - _ E _ T _ E _ E E _. - _ E _ 6 _ _ 9 4 _ E _ 3 _ 9 _ U __ 23 _ 4 _. L 9 _ 6 _ 7 _ _ _ _ . . _ 9 _ _ 9 _ _ 4 . 4 1 _ _ 1 _ _ - _ 1 _ : _
+ : + : + : : + + - + +
_ _ _ . : _ . 2 _ D _ 2 _ 5 _ 3 _ _ 2 . 0 _ I _ 0 0 _ 0 _ 2 _ 0 _ - _ O _ - - . - _ 0 _ - _ E _ R _ E E _ - _ E _ 4 _ Y _ 1 ._ 9E ._ 6 _ E _ 5 _ 1 _ H_0 T.4 _ 4 . 4 _ 2 _ 3 _ _ 1 _ 9 _ . _ 1 _
. 1 .
2 _ _ 1 _
+ : + : + : - + + : + +
. _ . : _ _ 4 _
. 2 _ 5 4 ._ 4 _ 0 _
Y ._ 0- _ - . E N _ _ 0 0 . 4 E
- 0 . - _ E _
0 _ - _ E _ 9 _ M D _ 1E ._ 9E __ 1 . E _.3 _ 3 _ S I _ . 4 . 4 . 0 _ 3 _ _ N . 6 _ . 1 _ O K __4 0_ 4 _ 2 _ _ 2 _ I T C
+
+
- +
- +
. 2 _
+ : +
4 _
+ M E _ 2 _ 5 . 4 _ 4 _. 0 _
J _ 0 _ 0 0 4 _ 0 _ - _ O R _ - _ - - 0 _ - _ E _ R E _ E _ E E - _ E _ 4 _ _. 2 _.E . 0 _ 3 _ P E V_1 I L _ 0 _ 9 _ 4 _ 2 _ 4 . 1 _ _ 3 . . _ 1 _ 8 S _ 4 _ 4 _ 2 _ _ 2 _ _ O _ . . . 2 _ _ : _
- D + : + : + : : + + : + +
A . _ _ : _ _ 5 _ 2 S _ 2 _ 5 _ 5 _. _ 5 _ 0 _ 1 V 8 SD _ 0 _ 0 _ 0 _ 5 _ 0 _ - . - I 9 DA E _ - _ - _ - _ _ - _ E . V 9 AR _ E _ E 1 RL N __ 1E _ 9 _ O E 2 __E-0._ 7E __ 98 _ _ I L LL B _ 0 _ 4 . 9 _ 0 . 6 . _ B L LI _ _ _ 2 _ A A IM _ 4 - 4 1 - 7 _. 3 _. _ T U M _ - _ - 2 . _ : _ N 2 + : + : + : : + + : + + N 10 _ _ : _ 4 _ _. _.0 AS E 0 - E T_2 C A0 - . . 0 . 5 _ 4 _ 0 _ 4 _ 0 _ - _ _ 4 _ NR U O E7 48 R E _ E .
- _ 0 _ - _ E .
E _ - _ E . 1 9 _ E _ 5 . 0 ._ m H8E L S
- 2. 6 2
T_0 I _ _ 1 _ 9 _ 4 _ 9 _ 1 .
. _ 0 .
7 _ _ 1 _ A .S = G _ 4 _ 4 _ 1 _ 1 _ _ C = . _ . . 2 _ : _ OS E +: + : + - .+ + : + + TNE ES _ . _ _ : . . 4 _ R L SO _ 2 5 _ 4 _ _ 4 _ 0 _ O I _ ._0 _ 0 _ 4 _ 0 _ - _ - FNM O D_ D Y __E 0_ E _ - _ - _ - _ 0 _ - _ E O R D E _ - _ E . 5 _. R_I I9 T8 A C0 IA A O _ 1 _ 9 _ B. _0 4 _ 0 _ E _ 4 _ 1 1 _ 6 _ 9 _ 1 _ _ 1 _ m _ O LT A_A_ TM M T.4 _
+: +
_ 4
+ : : +
2 _
. 2 .
_ 1 _
+ : +
+
A EA . . _ . . _ _ L A I BG L_L_ AA Y _ A __ W N T.N L _ _ D _ T L __ AF __ N __ m C UU H _E M . U D ._. LADU ._ E E H _ . E NN C _ IN_ P NN T __ U A_P _ O _ L _ R . N H A __ T __ I _ _ S AA P _ G . I _ _ _ _ m m
l l! i ll J
+ : + : + : - + + : + +
_ _ _ - _ _ 6 _ 6 6 _ _3
.0 _ 0 _ 6 - 0
_ 6 0 - N __E 0_. E- -
- - _0 _ - _ E -
I E _ - . E _ 2 . K _6 _ 5 ._ 0 _ E . 7 _ 8 _ S _ 2 _ 4 . 4 _ 8 . 3 - _ _ _ _ . _ 4 . _ 4 _ _6 - 5 _ 9 _ _ 8 _ _
. _ _ . 9 _ _ . _
+ : + : + : a + + : + +
_ _ _ - . - 6 . _ 3 - 6 _ 6 . 6 _ . 0 . 0 6 - _ G N __- 0._ -E -- - 0 - - - E _ E . - _ E - 2 . 0 _ E - 7 _ 8 _ U L __05 _E9 4- -- _ 4 _ 8 - 3 _ _
- _ _ 4 _ . 4 _
_ 2 . 4 - 9 - - 8 . _ _ . _ _ 9 - . _
+ - + : + - : + + : + +
_ . _ _ : - _ 4 _ D . 3 _ 6 _ 4 _ _ 4 _ 0 _ I - 0 _ 0 _ 0 _ 4 . 0 - O - - _ - _ - _ 0 _ - _- E _. R _ E _ E . E . - - E - 2 _ Y - 4 _ 9 _ 6 E _ 8 - 6 _ 5 _.8 H_9 T_1.__ 44 -
- _ 5
- 1
- . _ 5 _
4 _ 6 _ _ _ _ - _.5 _ _ : _
+ - + : + : : + + : + +
_ - _ _ - - . 6 _ _ 3 6 _ 5 _ - 5 _ 0 _ _.0 _ 0 _ 5 - 0 - EY __ 0- _ - _ - _ 0 - - E _- N - E _ E _ E _ - _ E . 7 _ D - 4 _ 9 _ 7 _ E _ 3 _ S I . 9 _ 4 _ 1 _ 6 _ 1 ._ 7 _ N K _ . . _ 2 _ . _ 6 _ O - 1 _-4 - 1 _ _ 1 - _ I - - _ _ 1 _ - - - T + : + + - : + + : + +
~ C _ _ _ . : - _ 6 - - E _ 3 - 6 _ 5 . 0 _
J O R_0 _
. 0 _
0 _ 5 _ 0 - - _
- _ 0 . - - E .
M' R P E E _ V __9 E I L _ 4 _ 9 _ _ E _ _ 4 _ E - - - E . D . 8 . E - 2 _ 5 0 . 3 - 0 _ 1 - - 6 9 S _ 1 . 4 - 1 . _. O _ . - - 1 _ - - -
- D + - + : + * - + , : + +
MAV - 8 SD S _ 3 - 6 _ _ 0 0 _ 7 _ 0 _ 6 _ 0 - - _
. 6 _
6 0 ._ 3 1 I 9 DA E _ - - _ 0 _ - - E _ V 9 AR N _ E _ 3 _ E _ - _ E - 3 _ I E E 1 RL O _ 4 - 9 _ 7 _ E _ 1 _ 4 _ M L LL B _ 9 - 4 _ 4 _ 3 - 8 _ _ I B L LI _ _ _ _ 1 WA A IM _ 1 4 _ 9 _ 3 _- 1 _ T U M . . _ . 1 . - - - N 3 + : + : + : : + + - + + N 20 _ . - _ - _ _ 6 _ AS 0 - T_0 _ 3 _ 6 - 6 - 0 _
- NR U
O E E2 83 E C A_E R T _ 4 - 9 .
- E 0 .
0 _ 6 - 0 . - _
- _ 0 - - . E _
E _ - _ E 4 _ E _ 8 _.8 _ 6 _ H9 0. 3 - _ 9 . 4 _ 6 _ 3 . 4 . _ u L 1 I _ _ _ _ 7 . . 4 _ m A .S = G _ 1 _ 4 _ 9 _ _ 8 _ _ m C = . . _ _ 9 _ . - _ u OS E + : + : + .: + + : + + TNE ES _ . _ . : - _ 6 _ R L SO _ 3 . 6 _ 5 _ - 6 _ 0 _ O OD FNM O I D_R_ Y_0 D _ E _ E _ _ 0 _ 0 _ 5 - _
- _ 0 _ - - E _
E _ - _ E - 6 _
- I4 T7 A
C0 RI IAA_A O _ 4 _ 9 _ B. 9 _ 4 _ 2 - E _ 0 _ 5 _ 0 - 5 _
- 0 -
4 _
- 5 _
O LT A_M TM T_1 _
+ :
_ 4
+ : + : : +
1 -
- 1
+
9 _
. +
+
A EA _ . - : _ _ . BG _ . - _ _ L Y_ - _ D - N T _. A I L_L_ AA A _D - W __ E _N _ LU _ E __ IL - FA_ T_N L C E UU NN H _ M _U __ AD _ E - -HC_._ IN__- T _
- LU __ O _ H N A __ T P
S NN AA A.P P _R G _ I _ _ r i i
+ : + : + ::+ + : + ,
. . _ : _ _ 6 .
. 3 _.6 6 _ _ 6 _ 0 _
_ 0 _ 0 ._ 0 _ 6 _ 0 _ - _ N _ - _ - _ - . 0 _ - _ E _ I _ E _ E _ E - _ E_9 _ K _ 9 _ 2 _ 9 ._ E _ 6 _ 9 _ _ S _ 5 _ 2 _ 8 _ 2 _ 4 _ _ _ _ . _ 9 _ _ 1 _ _ 2 _ 1 . 3 _ 3 _ _ _ - _ 3 _ :
+ - + : + ::+ + : + +
. . _ - _ _ 6 _
_ 4 _ 6 _ 6 _ _ 6 _ 0 _ _ 0 _ 0 _ 0 _ 6 _ 0 _ - . . G _ - . - - _ 0 _ - _ E . N _ E . E E _ - _ E _ 9 . U _ 7 _ 0 - 9 _ E _ 6 _ 9 _ L _ 4 _ 0 . 3 _ 2 _ 4 _ _ _ _ . . 9 _ _ 1 _ _ 8 _ 1 _ 3 . 3 _ .
. . _ 3 . . - . _
+: + : + ::+ + : + + _
. _ : . _ 4 _
D . 4 _ 6 _. 4 ._ 4 _ 0 _ I 0 0 _ 6 _ 4 ._ 0 _ - _ O ._ - - _ - _ 0 _ - _ E _ R _ E . E _ E _ - _ E _ 1 _ Y _ 2 0 _ 8 _ E _ 4 _ H _ 0 0 _ 8 _ 0 _ 5 3 _.
. . 3 . _ 2 _
T_8 _
. 1 1
. 2 .
. 2 .
+: + - + ::+ + : + +
_ _ _ : . . 6 . 4 _ 6 _ 6 _ _ 6_ 0 . Y . 0 _ 0 _ 0 _ 6 _ 0 _ - . E _ - _ - _ - _ 0 _ - _ E _ N _ E _ E _ E . - _ E _ 9 _ D . 2 _ 0 _ 4 . E _ 8 _ 7 _ S I . 0 . 0 8 . 2 _ 6 _ _ N K . . 2 _ _ 2 _ O ._8 . 1 . 4 _ 4 _ _ I . _ _ _.5 _ _ : _ T +: + : + ::+ + : + + C _ _ _ : _ . 6 _ E _ 4 _.6 _ 6 _ _ 6 . 0 _ J . _ 0 _ 0 _ 6 _ 0 . - _ O - _ - _ - _ 0 _ - . E _ R R E _.E0_ E _ E - _ E . 8 _
._ E _ 1 _ _
P V _ 2 _ 0 __ 4 6 _ I _ 0 _ 0 4 _ 9 . E L _ _ _ . 6 ._ 2 _ 2 _ 0 S _ 8 _ 1 _ 4 _ . 4 _ _ 1 O _ . . _ 4 . _ : _
- D +: + : + :+ + : + +
A- . _ . . : _ . 7 _ 4
, S . 4 _ 6 . 7 . _ 7 . 0 _ 1 V 8 SD _ 0 _ 0 0 7 . 0
_. 0 . - V I 9 DA E _ - _ - - E _ I 9 AR N _ E _ E _ E _ - _ E . 6 _ E 1 RL O _ 2 _ 0 _ 9 _ E _ 3 . 8 L LL B _ 0 _ 0 . 8 _ 7 _ 4 _ B L LI . _ . _ 4 _ _ 5 _ A A IM . 8 _ 1 _ 3 - . 7 _ T U M .
+: +
+
- +
- 5 .
+ : + +
N 3 : NS 30 _ _ _ _ . _ 6 _
._0 AE N
R 0 -
- E E7 T_0 C
_ 4 _ 6 _ A _ - _ - _ _ 0 _ 6 _ _ 6 0 _ 6 _ 0 _ - _
- _ 0 _ - _ E _
U 83 R _ E _ E _ E _ - . E _ 1 _ O0 _ 2 . 0 _ 9 _ E . 1 _ 0 H1W L S 4 4 1 T_0 I _ ._ 0
. 9 _ 3 .
. _ 0 .
5 _ _ 2 _ A .S = G _ 8 _ 1 ._ 3 _ . 3 _ . C = . . . . 4 . . : . OS E +: + : + ::+ + - + + TNE ES _ . _ _ : . _ 6 _ R L SO _ 4 6 _ 6 _ 6 _ 0 _ O I _ _.0 _ 0 _ 6 0 _ - _ FNM O D D_ - _ - _ - _ 0 _ - _ E . O R Y D __E 0. E _ E _ - _ E . 0 . 1 . E _ 9 . 3 I5 RI O _ 2 . 0 _ T6 2 . 3 _ 8 _ B. _0 _. 0 _ A I A_ A _ 3 . . . 2 . C0 _ 1 _ 4 _ 3 . O A_M A T ._ 8 _ _ . 4 . : ._ LT TM +: + - + ::+ + : + , A EA BG _ _ _ _ L Y_ ._ D _ N _ T_ A L_L_ _ _ L A I C E AA UU NN A __ E _ N W H _ T H._O L D _ L U ._ ET ._ N __ L U _ GD _ A _ E T _ I _ F _ _ H _ N _ C _ I __ P NN A L . R _ M _ _ _ S AA P P . G _ I _ _ _ .
j {l)) 1 il. ll11 i!111Il,lI l1 i l ,ll !ll llilll l Jll1
+ : + : , . : + + : + +
_ . _ . _ _ 4 . _ 1 5 _- 4 _ _ 4 _ 0 _ _ 0 _.0 _ 0 _ 4 _ 0 _ - _ N _ - _ - . - _ 0 . - _ E _ I - E _ E . E _ - . E _ 6 _ K - 1 _ 1 _ 7 _ E _ 2 _ 1 _ S _ 5 - 3 _ 2 . 9 _ 0 _ _ _ - _ _ 2 _ _ 1 _ 1 . 3 _ 2 _ _ 2 _ ._ _ - _ - 2 _ _ - _
+ : + - + - : + + : + +
. . . : - . 4 .
._2 5 4 . _ 4 . 0 _
- 0 0 0 . 4 - _
G - - . - . - . 0 - - _ E . E E . - - E _ 6 . N __ 4E U 3 7 . E . 2 _ L _ 9 . 7 - 2 . 9 _ 0 . 1 ._
- _ - _ 2 _ . 1 _
- 4 _ 2 - 2 - _ 2 _ -
+ : + : + : : + + : + +
. _ _ _ . _ . 2 _
D _ 2 . 5 _ 2 . - 2 . 0 I _ 0 0 0 . 2 _ 0 _ - ._ O.E R Y
. E .
8 . 3 .
- - . 0 _ - _ E _
E _ - _ E _ 4 _ 9 _ E _ 7 _ 3 _ H ._ 7 _ 0 _ 3 _ 4 _ .
. _ . _ 3 - _ 1 _-
T __4 6_ 2 _ 1 - . 1 _ _ _ _ _ 1 .
+ : + : + : - + + : + +
- . _ . : - . 4 -
. 2 . 5 _ 4 _ - 4 . 0 -
Y_0 E _ 0 _ _ E _ 0 . 4 _ 0 - - -
- . 0 _ - _ E -
E . - _ E . 3 - N __ 8E _ 3 _ D 2 _ E _ 3 . 6 - CT S I _ 6 . 7 _ 8 - 4 . 7 _ - N K _ . . . - 0 . _ 1 - O _ 4 2 _ 2 - _ 2 - I - _ _ 3 - _ : ._
+ : + : + : . + + : + +
C . _ . - : _ . 4 - - E _ 5 . 4 _ _ 4 . 0 . J O R R2 E - E - E _ 0 _ 0 . 0 _ 4 _ 0 . -
- _ 0 - - _ E ._
E - - . E _ 6 _ M P V 3 _ I . 6 _ 7 _ 9 . E . 6 - 5 _ 5 . 3 . 4 - _ E L - _ _ . 7 _ 1 S - 4 _ 2 _ 2 . _ 2 _ - 1 O - . . . 2 _ . : - D +: + : + * : + + : + + EA
- . _ . - _ _ 5 . 5 - , S - 2 _ 5 _ 5 _ - 5 _ 0 . 1 V 8 SD - 0 _ 0 _ 0 _ 5 _ 0 _ - -
I 9 DA E . - _ - _ - _ 0 _ - - E V 9 AR N _ E _ E _ E _ - - E - 0 . I E 1 RL O _ 8 _ 3 _ 6 . E . 1 - 4 EB L A T L A U LL LI IM M B _ 6 _ 7 _ 2 2 2 _
- 8 _
_ 1
. 3 _
3
- 4 _
_ 3 . N 2 +- + : + : . + + : + + NS 10 - _ - - : . _ 4 _ AE 0 - T - 2 _ 5 4 _ . 4 _ 0 _ R E C - 0 . 0 _. 0 _ 4 . 0 _ - _ M N U E1 10 A-R - E _ E _
- . 0 . - _ E _
E . - _ E - 7 _ O1 3 . E - 5 _ 1 _ H1 L W
- 6. 8 2
T_8 I . 6
. 3 _
. 7
_ 3
- 5 _ 0 3 _
- 1 A
C .S
= G4 . 2 _ _ 2 - _
= . - 2 _ - - -
M TNE OS ES E +: +
* + .: +
+ . +
. 4 _
+
s R L SO . 2 _ 5 . 4 - _ 4 _ 0 _ O I . 0 0 - 0 . 4 - _ FNM O D_ . - ._ - - - _ 0 _ - - E _ O D_R RI Y_E D O _ 8 - 3 _ _ E _ E _ - . E _ 4 . 5 - E . 7 _ 3 . M I5 T7 A IA B. _6 _ 7 _ 4 _ 3 .
- 5 .
2 _ . .
. 1 -
C0 A_A_ T_4_ . 2. 2 _ . 2 . _ O AIT - 2 _ _ : . LT TI +: + : + : : + + : + + A EA _ - _ _ : . _ _ M L A BG L_L_ Y_ _ D T.N L
. D _ N _
_ T _ I C AA UU A_E W H _M _ U . _ N LU.E CH ._NI _ AD
. E _ L ._ FA_
I E NN P NN T.U _ A L__O R HA_T N M S AA P P G I _ . . - J l l11ll1
M
+ : , : , : + + : , +
_ _ _ _ - _ _ 5 _ _ 1 _ 5 _ 4 _ _ 4 _ 0 _ _ 0 _ 0 , 0 _ 4 _ 0 _ - _ N _ - _ - _ - _ 0 _ - _ E _ I _ E _ E _ E _ - _ E _ 6 _ K , 4 _ 7 _ 4 _ E _ 3 _ 9 . S . 2 _ 5 _ 9 _ 6 _ 7 _ . . _ _ _ _ 9 _ _ 9 _ _ 1 _ 2 _ 1 _ _ 1 _ . _ . _ _ 1 . . : .
+ : + : + .- + . + +
_ _ _ _ : 4_ _ 5 _ _ 2 _ 5 _ 4 _ _ 4 _ 0 _ _ 0 _ 0 _ 0 _ 4 _ 0 _ - _ G _ - _ - _ - _ 0 _ - _ E _ N _ E _ E _ E _ - _ E _ 6 _ U _ 0 _ 1 _ 4 _ E _ 3 _ 9 _ L _ 0 _ 1 _ 9 _ 6 _ 7 _ . _ _ _ _ _ 9 _ _ 9 _ _ 4 _ 2 _ 1 _ _ 1 _ _ _ _ _ _ 1 . _ : .
+ : + : , : : + + : + +
_ _ _ . : _ _ 2 _ D _ 2 _ 5 _ 3 _ 2 . 0 _ I _ 0 _ 0 _ 0 2 _ 0 . - _ O _ - _ - _ - 0 . - E _ R _ E _ E _ E - _ E ._2 _ Y _ 9 _ 1 _ 9 _ E 3 _ 1 _ H _ 7 _ 1 _ 0 _ 1 2 _ . T _ _ . _ 1 _ _ 1 . -
. 3 _ 2 . 9 _ _ 1 _
. . _ 1 _ . :
- + : + : - + + : + +
_ _ _ : _ _ 4 _ 2 _ 5 _ 4 _ _ 4 _ 0 _ - Y 0 _ 0 _ 0 _ 4 _ 0 _ - _ E _. - _ - _ - _ 0 _ - _ E _ N _ E _ E _ E _ - _ E _ 8 _ D _ 9 _ 1 _ 0 _ E _ 2 S I _ 7 _ 1 _ 4 _ 9 _ 3 _3 N K _ _ _ 5 _ _ 1 _ O . 3 2 . 2 _ . _ 2 _ _ I ,. . . _ 2 _ . : . T : + - + : : + + : + + C _ . _ _ : _ _ 4 _ E _ 2 _ 5 _ 4 . _ 4 _ 0 _ J _ 0 _ 0 _ 0 . 4 _ 0 _ - _ O R _ - _ - _ - _ 0 _ - _E _ R E _ E _ E _ E _ - _ E _ 3 _ P V _ 9 _ 1 _ 1 . E _ 9 _ 3 . I _ 7 _ 1 _ 2 . 3 _ 0 _ . E L _ _ _ . 3 _ _ 1 _ 3 S _ 3 _ 2 _ 2 _ _ 2 _ _ 1 O _ _ _ _ 2 . _ : _
- D +: + : + : . + + : + +
6 A _ _ _ . . _ 5 _
- , S _ 2 _ 5 _ 5 . _ 5 a_0 _ 1 V 8 SD _ 0 _ 0 . 0 _ 5 _ 0 _ - _ -
I 9 DA E _ - _ - - _ 0 _ - . E _ V 9 AR N _ E _ E E _ - . E . 4 _ I E 1 RL O _ 9 _ 1 9 _ E . 0 . 8 _ L LL B _ 7 _ 1 _. 8 _ 5 _ 6 . _ B A T L A U LI IM M _ 3 2 _ 1 . _ 6 _
. 2 .
_ 3 _ _ 2 _ _ M_ N 2 ,: + - + - + + : + + NS 10 . _ . _ : _ _ 4 _ AE 0 - T . 2 _ 5 _ 4 _ _ 4 _ 0 _ R E C . 0 _ 0 _ 0 _ 4 _ 0 _ - _ . N E0 A _ - _ - _ - _ 0 _ - _ E _ U 65 R _ E _ E _ E _ - _ E _ 0 _ O2 T _ 9 _ 1 _ 9 _ E _ 5 _ 0 _ H1W 1. 6 - _ 7 _ 1 _ 9 _ 1 _ 7 _ _ L S 2 I _ _ . _ _ 0 _ _ 1 _ A C OS W
=
E
=
G.3 _
+: + :
_ 2 _
+ : : +
1 _
. 2 .
. 1 _
+ : +
+
TNE ES _ _ _ . : . . 4 _ _ R L SO _ 2 _ 5 _ 4 . . 4 . 0 _ O I . 0 _ 0 . 0 . 4 . 0 _ - _ FNM O D_ D Y . - _ - - . 0 . - _ E _ O R D E _ E ._ E . - . E _ 4 _ I 4 R_I O 9 _ 1 _ 0 . E 4 _ 1 _
. 1 . 6 _.9 M T0 T7
_ 1 _ _ _ A I A_ A A B. _ . _ . _ 1 _ _ 1 _ C1 3 . 2 . 2 . _ 1 _ O A_M . . . 2 - ._ t _ LT TM +: + : + - : + + : + + A EA _ . BG _ _ _ _ _ T _ L T _ _ D _ N _ A L_L_ Y_ _ _ _ D _ L _ _ L _ A _ I AA UU A_E W H _ N _ _ N_I E _ F _ C E P NN NN T _M_U_LU
.U_O
.L R _ N AD _
H A __ T _ C E _ H _ N _ _ _ I _ S AA A_P _ G _ I P _ _ M
1 l )) lililI, )llI,l, l
+ . + : + : : + + : + +
_ _ : _ _ 4 _ _ 1 ._ 5 _ 4 ._ - 4 _ 0 _ _ 0 _ 0 _ 4 - 0 . - _ N_0 _ I _ E _ E -
- _ - _ - _ 0 . - . E _
E _ - . E _ 3 _ K _ 3 _ 3 - 9 _ E 1 _ 3 _ S _ 7 _ 4 - 5 _ 2 _.3 - _ _ - - . - 6 _ _ 1 _ _ 1 - 2 _ 2 _ _ 2 - _
. . . - 2 _ - : _
+ : + - + : . + + - + +
. _ _ : _ 4 _
_.2 5 _ 4 _ 4 _ 0 _ _ 0 _ 0 _ 4 0 . - -
- - - _ - _ 0 ._ - . E -
G __ 0- E - N E _ - - E . 3 - U_E L - 6 4 _ 0 - _ 0 _ 9 _ E . 1 . 3 _ 5 - 2 _ 3 _ _
- . _ - 6 _ _ 1 -
. 5 2 _ 2 - _ 2 _ -
. . - 2 _ _ : -
+ : + : + : : + + : + +
_ _ . _ : - D _ 2 _ 5 _ 2 _ . 2 - 0 _ I _ 0 _ 0 _ 0 _ 2 _ 0 _ - _ O _ - . - _ - _ 0 - - _ E _ R _ E . E _ E _ - - E _ 4 _ Y _ 5 - 0 _ 5 _ E - 9 . 5 - H _ 3 - 0 _ 2 _ 3 _ 6 . - T _ - . _ _ 5 _ _ 1 _ 2 _ 1 _ . _ 1 _ _
. - - . 1 . - : -
+ . + : + : : + + : + +
- _ - - : - _ 4 -
- 2 _ 5 . 4 - - 4 _ 0 -
Y . 0 _ 0 . 0 . 4 - - E _ - _ - . - _ 0 - - - E . N _ E _ E _ E _ - - E _ 6 . D . 5 _ 0 _ 2 _ E - 2 _ 8 - S I _ 0 _ 2 . 8 - 1 _ - N . _ - _ 1 O K ._. 5 3. 2 _ 3 - 4 _. 3 - _- M I T C
+
+ : +
- : +
- 3 _
+ - +
. 4 _
+
~ ' E _ 2 _ 5 . 4 _ 4 _ 0 - J _ 0 - 0 _ 0 _ 4 _ 0 _ - - O R _ - - _ - _ 0 _ - _ E . R E _ E _.E _ E _ - - E _ 9 _ M P V ._ 3 I 5 _ 0 _ _ 0 _ 6 _ E 7 _ 9 . 3 - 8 - _ E L . _ . . 1 . . 1 _ 3 S - 5 2 . 2 . . _ 2 _ _ 1 O - . . _ 3 _ _ : -
- D + : + : + .- + + - + +
MA V I 8 9 SD DA S E
. 2 . 5 .
. 0 0 .
5 . 0 - 5 . 0 _ - .
- - 0 . - _ E-
_ 5 _ 0 . _ 5 - 7 1 V 9 AR N _ E _ E . E - - E _ 1 - I E 1 RL O _ 5 . 0 . 0 E 5 . 9 . L LL B . - 6 ._5 _ 9 . . . 3 _. 0 MA B T L A U N LI I M M 2 5 _ 2 -
+ : + : +
2 -
+
- 6
- 3 _
+
._4 e
. _ 3 -
+
+
NS 10 _ _ _ _ : . 4 . AE 0 - T _ 2 _ 5 . 4 _ _ 4 _ 0 . R E C _ 0 - 0 . 0 _ 4 - _ M N U O3 E5 91 A R
. E . E _
- _ 0 - - - E_
E _ - - E 6 _ E T _ 5 . 0 . 4 - 3 - H1 9. 9 - _ _ 6 _ 8 _ 3 . . L 2 I _ 3 ._ 0 - . 6 _ _ 1 . A W = G . 5 _ 2 - 2 - _ 2 _ _ C . = . - - - 2 _ - : _ M TNE OS ES E + : + : + : - +
+ : +
. 4 _
+
R L SO _ 2 5 _ 4 _ 4 _ 0 _ O I _ 0 _-0 _ 0 _ 4 _.0 _ - - FNM D D_ O 'i _ - _ - . - _ 0 . - _ E . O R D_E _ E . E _ - . E _ 3 . I0 R_I O _ 5 _ 0 _ 0 _ E . 9 _ 5 . M T2 A I A_ B. . _ 3 _ 0 _ 8 _ 9 _ 8 5 _ . . _ 1 . C1 A . _ 2 _ 2 _ . 2 _ . O LT A_M A TM T.5 + : +
- +
- e
. 2 -
+ + : +
_ t .
+
A EA _ BG M L Y. . _ T-LNFA __ D _ _ T _ A I C L_L_ AA UU A.E W H M
- D _
. N _ LUL ._ E ._
U _ AD _ E _ H.N_ N I NN U E P NN T_L A . R . N O . HA.T _ C . I M S AA P _ P . G . I - . F \ ll
E E E
, - + : : - + + : + +
_ _ #_ . : _ _ 5 _
. 2 _ 6 _ _ 5 _ 0 _
4 _ 0 _ 0 _ 0 _ 4 _ 0 _ - _ _. - _ - _ - _ 0 _ - _ E _ N_E I K _ 0 . 3 _ _ E _ E _ - _ E _ 6 _ 9 _ E _ 7 _ 5 S _ 1 6 _ 0 _ 0 . _ 6 __ 5 _ _ 7 . 6 _ 1 _ 1 _. 9 _ _ _ . _ . 1 _ _ : .
+ : + : + : : + + : + +
_ _ _ _ : _ _ 5 . _ 2 _ 6 _ 4 _ _ 5 _ 0 _ 0 _ 0 _ 4 _ 0 _ - ._ N0 G - _ - _ - _ 0 . - _ E _ E _ E _ E _ - _ E _ 6 _ U.1 . 6 _ 9 _ E _ 7 _ 5 _
. 4 _ 0 _ 0 _ 6 _ _
L _. 3 _ . _ 1 _ 5 _ _ 2 _-5 _ 1 _ 9 _
. _ . _ 1 . - _
+ : + : + : + + : + +
_ _ . . _ 3 _ D _ 2 _ 6 _. 3 _ _ 3 0 _ I _ 0 _ 0 _ 0 _ 3 _ 0 . - _ O _ - _ - _ - _ 0 . - _ E _ R _ E _ E _ E _ - _ E _ 0 _ . Y _ 9 _ 6 _ 2 _ E _ 3 _ 3 _ H _ 1 _ 4 _ 1 _ 6 _ 9 _ . T _ _ _ 2 _ _ 6 . 2 _ 5 - 5 . _ 6 _ .
. _ _ . 6 . _ : _
+ : + 9 + .- + + : , +
_ _ _ _ : _ . 5 _ _ 2 . 6 _ 4 _ _ 4 . 0 _ Y E __ 0- . - _ N _ E _ E _
. 0 _ 0 _ 4 _ 0
- _ 0 _ -
E _ - _ E _ 5 _ _. E _ W D _ 9 _ 6 _ 4 _ E 0 _ 7 _ S I _ 1 _ 4 _ 3 _ 5 3 . _ N K _ _ _ _ 4 _ . 7 _ O _ 2 _ 5 _ 1 _ _ 1 _ . I . . . . 1 . - : . T + : + : + - : + + : + + C _ . _ _ : . _ 5 _ E _ 2 _ 6 _ 4 _ 4 _ 0 _ J _ 0 _ 0 _ 0 _ 4 ._0 _ - _ O R _ - _ - _ - _ 0 _ - - E _ R E . E _ E _ E _ - _ E . 3 _ P E V_1 I
. 9 _ 6 _
L _ . _ _ 4 . 4 _ E _ 7 2 _ 0 _ 1 _ 3 _ 4 _ 7 _ 4 S _ 2 - 5 _ 1 _ _ 1 _ _ 1 O _ . _ - 1 . . - _
- D +: + : + : : + + : + +
A- _ . : _ _ 5 _ 8 S _ 2 .. 6 _. 5 _ 5 _ 0 _ 1 V 8 SD _ 0 . 0 _ 0 _.5 _ 0 _ - _ - I 9 DA E _ - _ - _ - _ 0 _ - _ E _ V 9 AR N _ E _ E . E _ - _ E _ 0 _ I E 1 RL O _ 9 _ 6 . 6 _ E _ 3 _ 6 _ L B A L A LL LI IM B _ 1 _ 2 _ 5 _ 4 _ 0 1 _
. 9 _
. 4 _
0 _ 2 _ _ 1 _ g T U M . - _ . 1 - _ : . N 2 +: + : , : : + + .+ + NS 10 _ _ _ . : _ . 5 _ AE 0 - T_2 . 6 _ 4 _ 5 0 _ R E C _ 0 . 0 _ 0 ._4 _ 0 _. - _ N E5 _ - . - _ - _ 0 _ - _ E _ U O4 37 A_E R T _ 9 . 6 _
. E _ E _ - _ E _ 1 _
1 _ E _ 9 _ 6 _ H1W 2. 3 - _ 1 _ 4 _ 1 _ 2 _ 7 _ _ L N 1 I _ _ - 1 _ . 5 _ A W = G 2 . 5 _ 1 . _ 9 . _ C . = . . _ . 1 _ . : _ OS E +: + . + + : + + : + + TNE ES _ _ _ _ : _ _ 5 _ R L SO _ 2 _ 6 _ 4 _ _ 4 _ 0 _ O I _ 0 _ 0 _ 0 _ 4 _ 0 _ - _ FNM O D_ D _ - _ - _ O I1 R_I R Y_E D O _ 9 _ 6 _ _ E _
- _ 0 _ - _ E _
E _ - _ E _ 9 _ 7 _ E _ 8 _ 3 _ T3 IA B. _1 _ . 4 _ 1 _ 1 _ 0 _ _ A A . _ _ 2 _ _ 6 _ C2 O LT A_A_ TM M T_2+
- +
. 5 _
- +
1 _
+
_ 1 . _ 1 _
+ :
+
+
A EA _ _ . _ : . . BG _ _ . _ T _ L Y . _ ._ . D _ N _ A L_L_ . . T ._ L . L _ A _ I C AA UU A.E W H N D _ AD U __ L E . I _ F _ E NH _ N _ _M _ UO _ HA E NN P S NN AA T_U A_PL P R G . I N
. T C _ I .
. g
l ll>
- + : +: - + + : + +
4_ _ _ . - _ _ 5 . _ 2 _ 6 _ 4 . _ 5 _ 0 _ _ 0 _ 0 _ 0 . 4 . 0 _ - _ _ - _ - _ - . 0 . - _ E _ N_E I K _ 7 _ 6 _ _ E _ E . - . E _ 3 . 2 . E _ 9 _ 2 _ S _ 6 _ 8 _ 0 _ 3 _ 0 . _ _ _ _ 0 - . 5 _ _ 6 _ 7 1 . _ 9 _ _
. . - . 1 . - : _
+ : + : +: : + + : + + x
_ _ . _ : _ _ 5 _ _ 2 _ 6 4 _ _ 5 _ 0 _
. 0 _ 0 _. 0 _ 4 _ 0 . - _
- _ - _ - _ 0 . - . E _
G N ._ E _ E _ E . - _ E . 3 _ U _ 7 _ 8 _ 2 . E _ 9 _ 2 _ L _ 1 _ 4 _ 0 _ 3 . 0 _ . _ _ _ _ 0 _ _ 5 _ _ 2 6 _ 1 _ _ 9 _ _
. . _ _ 1 _ _ - -
+ : + - +- : + + - + +
_ _ _ : _ _ 3 _ D _ 2 _.6 _ 3 _ _ 3 _ 0 _ I _ 0 _ 0 _ 0 _ 3 _ 0 _ - _ O _ - _ - _ - _ 0 _ - _ E _ R _ E _ E _ E . - . E . 0 . Y _ 6 _ 8 _ 9 . E . 9 . 9 _ H _ _ 4 _ 7 _ 6 . 4 . _ 8 . 5 _ T __2 0_ -- 6 _ 4 _ _ 6 . _ _ . _ 5 _ _ : _
+ : + : +: : + + : + +
_ . _ _ _ 5 _ 2, . 6 _. 4 _ _ 4 _ 0 _ Y _ ( _ 0 _ 0 . 4 _ 0 _ - _ E _ - _ - _ - _ 0 _ - _ _ N _ E _ E _ E _ - 8 _ D _ 6 _ 8 _ 6 . E E __ 2 2 E-S I _ 0 _ 4 _ 2 _ 6 - 2 - N K . _ _ _ . 7 . O . 2 _ 6 _ 1 _ 3 _- 1 . _ M I T C
+ : + : +:
- +
- 1 _
+ : +
_ 5 _
+
E _ 2 6 4 _ _ 4 _ 0 _ J 0 0 0 _ 4 _ 0 _ - _ O R - _ - _ - _ 0 _ - _ E _ M R P E _ E _ E _ V _ 6 _ 8 _ I _ 0 _ 4 _ E _ - _ E _ 8 _ 6 _ E _ 0 _ 9 _ 1 _ 2 _ 1 _ . _ E L . _ _ 2 _ . 6 _ 5 S . 2 6 _ 1 - _ 1 . 1 O _ . . . 1 _ . : .
+ + +- : + + + +
mA V D SD S _ 2 _ 6 _ 6 _ _ 5 . _ 5 _ 0 . 9 1 I 8 9 9 DA AR NE _ 0 _ 0 _ E . - . - _ E _ 0 _ 5 _
- _ 0 _
E _ - _ E _ 0 _ u_E
- _ V I
E 1 EL O 6 8 _ 4 - E _ 0 _ 5 _ mLAT B L A U LL LI IM M B _ _ 0 _. 4 _ 2 _ 6 _ 9 9 _ _ 0 . 9 _ 4
- 1 _
_ 1 - _ 1 _ N 2 + : + : +- - + + : + + NS 10 _ _ . - _ . 5 _ _.6 m AE N R 0 -
- E E2 T_2 C
0 _ 0 _ _ 4 . . 5 . 0 _ 0 . 4 _ 0 . - _
- _ 0 _ - . E .
U O5 65 A_E R T_6 _ _ E _ 8_ _ E _ - _ E . 7 _ 5 _ E _ 1 . 2 _ H1 1. 3 - 0 4 _ 0 _ 6 _ 2 . _ L W 1 I _ _ _ 0 _ _ 5 _ m A .N = G_2 _ 6 _ 1 - _ 9 _ C = - . - 1 _ u OS E + : + : +: : + + : + + TNE ES . . . - - _ 5 _ R L SO _ 2 _ 6 4 . - 4 _ 0 _ O OD e FNM O I D_R_ Y_0- _ D_E _ E _ 0 . 0 . 4
- . 0 0 _ - _
._ - _ E _
E . - _ E _ 0 _ m m I5 RI C _ 6 - 8 0 . E _ 2 . 0 _ u T4 _ 0 . 4 . 1 . 3 _ 0 _ _ A I A_ A B. . . _ _ 1 _ _ 6 _ C2 A T2 . 6 . _ . 1 _ . 1 _ - O A_M _ 1 . . : - LT TM + : + : +: : + + : + +
- L A
A EA G B_L_ L Y_ _ D _ T L
._ N D_A L
_ T _ _ N _ A_ _ e m I C AA UU W H_E _ N O _LU.E _AD
- E _ I _ F _
_ H _ N _ m u m E P S NN NN AA T_M__U_HA.T A __P U P L _ R _N _ G_I C_I _ i 1 lllI
m
, : + : , : : , : , +
_ _ _ 4_ . . _ 5 _ _ 2 _ 5 _ 4 _ _ 4 _ 0 _ _ 0 _ 0 _ 0 _ 4 _ 0 _ - _ _ - _ - _ - _ 0 _ - _ E _ I N K S _ 0
._E 3__ E24 E _ - _ E _ 3 _
2 _ E _ 8 _ 2 . 2 _ 3 _ 0 _ _
. _ _ _ 2 . _ 6 _
8 _ 1 _ 1 _ . 1 _ _
. _ _ 1 . _ : _
4 : : , : : + + : + + 4_ _ _ : _ _ 5 _ _ 2 _ 5 _ 4 _ _ 4 _ 0 _ _ 0 _ 0 _ 0 _ 4 . 0 _ - _ ' G . - _ - _ - _ 0 - _ E _ N E . E _ E _ - E _ 3 _ U 2 . 7 _ 2 _ E _ 8 _ 2 _ L _ 1 _ 2 _ 3 _ 0 _ _ .
._ 6 _
_ _ 2 _ _ 6 _ _ 2 _ 1 _ 1 . _ 1 . _ _ . _ . 1 . . : .
, : + : , : : + + : +
. _ _ : _ _ 3 4_
D _ 2 _ 5 _. 3 _ _ 3 _ 0 _ I _ 0 _ 0 _ 0 _ 3 _ 0 _ - _ O _ - _ - _ - _ 0 _ - _ E _ R _ E _ E _ E _ - _ E _ 9 _ Y _ 8 _ 7 _ 6 _ E _ 0 _ 0 H _ 4 _ 1 _ 7 . 5 . 8 _ T _ _ . _ _ 0 _ _ 7 . _ 2 _ 1 _ 5 _ _ 7 _ _ _ . . _ 7 _ . : _
+ : + : + : : + + : + +
_ . _ _ : _ _ 5 _
. 2 5 _ 4 _ _ 4 _ 0 _
Y . 0 _.0 . 0 _ 4 _ 0 _ - . E . - _ - . - _ 0 _ - _ E . N . E _ E . E _ - _ E _ 9 _ D _ 8 _ 7 _ 1 _ E _ 6 _ 6 _ S I _ 4 . 1 _ 5 _ 2 _ 4 _ _ N K _ . _ _ 6 _ _ 8 _ O _ 2 1 _ 1 _ _ 1 _ _ I _ _. _ . 1 . _ : _ T + : + : + : - + + : + C _ _ _ . : . _ 5 #_ E _ 2 _ 5 _ 4 . 4 _ 0 _ J _ 0 _ 0 _ 0 ._ 4 0 _ - _ O R _ - _ - _ - _ 0 ._ - _ E _ R E _ E . E _ E _ - _ E _ 4 _ P E V_4 I L _ _ 8 . 7 _ _ 1 _ 8 _ E _ 1 _ 3 _ 3 _ 6 _ _ 4 . 3 _ _ 8 _ 6 S _ 2 _ 1 1 _ . 1 _ _ 1 O . . _. _ 1 _ . : _
- D + - + . + : : + + : + +
A _ _ . : . _ 5 _ 0 S _ 2 _.5 _ 5 _ 5 _ 0 _ 2 V 8 SD _ 0 _ 0 _ 0 _.5 _ 0 _ - _ - I 9 DA E _ - _ - _ - _ 0 - _ E _ V 9 AR N _ E _ E _ E _ - E _ 0 _ I E 1 RL O 8 _ 7 _ 9 _ E . 8 _ 8 _ L LL B ._4 _ 1 _ 1 _ 8 _ 2 _ _ B L LI _ _ . _ _ 6 _ _ 1 _ _ A A IM . 2 _ 1 _ 1 _ 2 _ _ _ T U M . _ . _ 1 . : _ N 2 + : + : + : : + + : + + - NS AE 10 0 - T . 2 _ 5 _ 4 _ _ 4 _ 0 _ _ 5 _ R E C 0 _ 0 _ 0 _ 4 _ 0 _ - _ N E5 A ._ - _ - - _ 0 _ - _ E _ U 92 R _ E E E _ - _ E _ 8 _ O6 . H1N L N
- 3. 4 1
T.8 I . 4 . 7 . 1 ._ 5 _ E . 0 _ 2 _ 6 _ 1 _ _ 2 _ . _ 6 . 2 _ A G . 2 . 1 _ C .N
= 1 _ _ 1 _ .
= _ . _ _ 1 . . : .
OS E + : + : + : : + + : + + TNE ES . _ _ _ : . . 5 . R L SO 2 _ 5 _ 4 _ 4 _ 0 . O I OD ._0 _ 0 _ 0 ._4 _ 0 _ - . FNM _ - _ - _ O I5 D_R_ RI Y_E D O _ 8 _ 7 _ _ E _
- _ 0 _ - _ E .
E _ - _ E . 6 . 1 . E _ 1 . 1 _ T0 IA B. .
. 4 _ 1 _ 3 . 5 _ _
A A _ _ _ 3 ._ 2 _ 7 _ C2 . O LT A_A_ TM M T.2 + : _ 1 _
+ : + : :
1 _
,. 1- .+
_ 1 _
+
+
A EA _ _ _ . _ _ BG _ . L A L_L_ Y_ _
._ D .
T __ L D _ N T_ _ I C AA UU A_E _ N . W H _ M _ U . AD LU_EN_I _ E
. H L _ A _
_ F _ _ N _ E NN T_U _ O . . _ I _ P NN A.L . R . N HA ._ T . C _ _ S AA P . P . G . I _ . _ _
I ' ] I
+ : , - + - : + + - +
_ 2 ._ 5 _ 4 _ _ 4 _ N_0 I _ _ 0 _
. E .
0 E 4 0 _ 0 . _ E _ K _E 2 2 7 _ E _ 6 _ S _ 9 1 _. 1 _ 8 _ 8 . _ _ _ _ 4 _ . _ 7 _ 1 _ 2 _ 3 .
. _ 2 _. _
+ : + : + : : + + : +
_ 2 _.6 . 4 . _ 4 _ _ 0 _ 0 0 4 _ 0 _ O _ - . - _. - _. 0 _ - _ N _ E _ E _ E _ - . E _ U _ 8 _ 6 _ 7 _ E . 6 _ L _ 5 _ 2 _ 1 _ 8 _ 8 _ _ _ _ _ 4 . _ _ 2 _ 9 _ 2 _ . 3 _ _ . - _ 2 . _
+ : + * + - . + + : +
D . 2 6 _ 2 _ _ 1 _ I 0 . 0 _ 0 _ 2 _ 0 _ O ._ - . - _ - _ 0 _ - _ R _ E E . E _ - _ _ Y _ 5 6 1 _ E _ 9E_ H _ 4 - 2 9 _ 4 . 3 _ T _ - . - 4 _ _ 2 . 9 . 5 - 1 _
. - _ . 7 . _
+ : + : + : : + + : +
_ 2 _ 6 _ 4 . _ 3 _ Y . 0 _ 0 _ 0 4 _ 0 _ E - _ - _ - 0 _ - _ N .E E _ E - _ E . D . 5 ._ 6 _ 5 ._E _ 7 _ S I _ 2 _ 2 _ 6 _ 0 _ K ._ 4 EE N _ _ _ 8 _ . _ O _ 2 _ 9 _ 5 _ _ 1 . I . _ _ . 6 - . T + : + : + - - + + + C _ _ . _ : _ _ 2 _ 6 _ 4 _ 4 _ J _ 0 _ 0 _ 0 _ 4 . 0 _ O R _ - - _ - _ 0 - _ R E _ E _. E _ E _ - ._ M P V _ 5 _ 6 _ I _ 4 _ 2 _ 7 _ E _ 5E __ 9 _ 3 _ 0 _ E L _ . _ . _ 0 _ _ 7 S _ 2 9 _ 3 - _ 8 _ 1 O . - - 5 . .
- D + : + : + : * + + - +
M' A V 8 SD S _ 2 _ 0 _ 0 _ _.6 _ 4 _ 0 _ 4 _ 0 _ _. 4 _
. 1 2
I 9 DA E _ - _ - _ - _ 0 _ - _ V 9 AR E _ E _ E _ - _ I E 1 RL N ._ 5 _ 6 _ O 6 _ E _ 7E __ MB L A T L A U LL LI IM M B . 4 _ 2 . _ 2 _ 9
+ : + : +
2 _ 2 _ _ 8 _ 1 _ . _ 4 _
,1 1
N 2 : : + : + NG 10 _ _ . _ : . _ AE 0 - T _ 2 _ 6 4 _ 4 _ V E C _ 0 _ 0 0 _ 4 _.0 _ M N U E9 71 A . - _ R . E _ E _ _ - _ 0 _ - _ E _ - _ E _ O7 _ 6 _ 5 _ E _ 3 _ H1E 3. 4 T- _. 45 _ 2 _ 6 . 9 . 2 _ L N 1 I _ _ _ . 9 . _ A C .N
= 9 _ 2 4 _
= G __ 2 _. - _.2 M TNE OS ES E + : + : + : : +
+ : +
R L SO 2 _ 6 _ 4 _ _ 4 O I 0 _ 0 _ 0 _ 4 _ 0 _ FNM O D_ D Y . - _ - _ - 0 _ - _ O R D _ E _ E _ E - _ E _ R_I O _ 5 _ 6 _ 0 _ E _ 4 _ M I2 T9 A I B. . _ 4 _ 2 _ 2 _ 5 _ 2 _ 8 _ C1 A_A_ A T.2 _ 9 _ 3 _ _ 6 _ O LT Ae Tt t
+ :
- + : : +
_ 3 _
+ : +
A EA 4_ _ _ : . _ M L A BG L_L_ Y A T __ N _ L _ L _ D_ AA _ E ._N I C UU NN W H - M _ D.TU_E _ H _ U __ E D _ E _ I _ E P NN T_L A_PU_R _ O _ G E A _ T _ C __ M S AA P _ G _ V _ _ _ F 1 i lllll
+ : + : + * - + : ,
_ _ . 4_ : _ _ _ 2 _ 6 . 5 _ _ 5 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ _ - . - _ - _ 0 _ - _ N_6E ._ E64 __ I K S _ 5 _ _ E _ - _ E _ 0 _ E _ 2 _ 4 _ 4 _ 8 . _ _ _ _ 0 _ _ 1 _ 1 _ 4 _ _ 7 ._
. _ _ . 5 - .
- + : + : : + + * +
4_ _ _ _ - _ _ _ 3 _ 6 _ 5 _ _ 5 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ G _ - _ - _ - _ 0 _ - . N _ E _ E _ E _ - _ E . _ 5 _ 0 _ E _ 2 _ U __ 05 _ 3 _ L 4 _ 4 _ 8 _ _ _ _ _ 0 _ _ _ 5 _ 1 _ 4 _ _ 7 _
. . . . 5 _ -
+ : + : + : : + + : +
D _ 3 _ 6 _ 3 . 2 _ I _ 0 _ 0 _ 0 . 2 . 0 _ O _ - _ - _ - _ 0 _ - _ R _ E _ E _ E _ - _ E _ 8 _ 5 _ 4 _ E _ 3 . Y ._ 7 _ 3 _ H 6 _ 9 _ 0 . T _ _ _ _ 0 _ _ _ 4 _ 1 _ 8 _ . _ 2 _
. . . 1 -
+
- +
- +
- : +
+ - +
_ 3 _ 6 _ 5 _ _ 4 _ _ 0 _ 0 _ 4 _ 0 _ Y E _. 0- _ - _ - _ 0 _ - _ _ E _ E _ - _ E N __ 8E _ D 5 _ 0 _ E _ 9 S I _ 7 _ 3 _ 9 _ 4 _ 7 N K . _ _ . _ 1 _ O _ 4 _ 1 _ 8 _ _ 1 . I . - 1 _ . T C
+ : + : + :
+
+ - +
M E _ 3 _ 6 _ 5 _ . 4 _ J 0 _ 0 _ 0 _ 5 . 0 _ O R ._ - _ - _ - _ 0 _ - . R E _ E _ E _ E _ - _ E . P _ 5 _ 2 _ E _ 9 V __ 78 I _ 3 _ 0 _ 4 _ 3 ._ E L _ _ _ _ 7 _ _ 8 S _ 4 _ 1 _ 7 _ _ 1 _ 1 O - _ . _ B - .
- D + : + : + : : + + : +
A _ _ . _ . _ _ 2
- , S 3 _ 6 _ 5 _ _ 5 _ 2 V 8 SD _.0 _ 0 _ 0 _ 5 _ 0 _ -
I 9 DA E _ - _ - . - _ 0 _ - _ V 9 AR N _ E . E . E - _ E I E 1 RL O _ 8 . 5 _ 3 ._ E _ 8 _ L LL B _ 7 . 3 _ 8 _ 5 _ 0 B L LI _ . , . 6 _ _ - A A I M _ 4 1 . 1 . _ 6 _ T U M _ .
+ : + - + : .
+
_ 2 . _ N 3 + : + NG 20 . _ _ _ : _ _ AE 0 - T_3 _ 6 _ 5 _ . 5 _ V E C __ 0- _ 0 _ 0 _ 5 _ 0 _ N E1 . - _ U O8 22 A_E R T _ 8 E _ 5 _
- _ 0 _ - _
E _ - _ E _ 9 . E _ 7 _ H1 7. 8 - _ 7 _ 3 _ 0 . 7 _ 3 _ L E 2 I _ _ _ _ 7 _ _ A .N C OS
=
E
=
G_4 _
+ :
+
_ 1 _
+ ?
5 _
- +
- 5 .
+
. 8 _
+
TNE ES _ _ _ _ - _ _ R L SO _ 3 _ 6 _ 5 _ _ 4 _ O I OD _ 0 _ 0 _ 0 _ 5 _ 0 _ FNM Y_E _ - _ - _ E
- . 0 . - _
O D_R_ U _ E _ - . E . I8 RI O _ 8 _ 5 _ 1 _.E 3 . T3 IA _ 3 _ 9 _ 3 _.1 M A B. __ 7 _ _ _ 0 _ . C3 O LT A_A_ A4 TP9 T_4 _ _ 1 _
+ : + : - +
5 _ _ 7 _
+
_ 1 .
+
A EA _ . _ _ : _ _ BG . _ _ _ _ _ L A L_L_ A _ D _ T_N L D_ L M I AA Y W ._ _ N _ TU _ E _ I _ C UU H ._ r,is_U _ ED _ E _ H __ E NN _ O _ GA _ P S NN AA T P _ *LA_? _ R . E _ G . V T_C_ k M
l i - jl I ;{
, : + : + - - + + : +
_ 3 _ 7 _ 5 _ _ 5 _ _ _ 0 _ 0 _ 5 _ 0 _
- _ - _ - _ 0 _ - _
N __E 0_ E _ I E _ - _ E _ K _ 0 _ 0 _ 1 _ E _ 4 _ S _ 3 _ 4 _ 6 _ 9 . 6 . _ _ _ _ 9 _ . _ 9 _ 7 _ 2 _ _ 4 .
- _ _ _ 2 - .
+ - + : + : : + + : +
_ 3 _ 7 _ 5 _ _ 5 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ G _ - _ - _ - _ 0 - _ _ E _ E _ E _ - _-E _ N_2 U L _ 0 _ 0 _ 9 _ 1 _ E _ 4 _ 6 _ 9 _ 6 _ _ _ _ 9 _ _ _ 3 . 6 2 _ 4 _ _ . 2 _ .
+ : + : + : : + + : +
_ 7 _ 3 _ 3 _ D __ 03 _ I 0 _ 0 _ 3 _.0 _ O _ - _ - _ - _ 0 _ - _ R _ E _ E _ E _ - _ E _ Y _ 6 _ 9 _ 0 _ _ H _ 8 _ 0 _ 9 _ E 1 __ 18 _ T_2 _ _ 6 _ _ _ 9 _ 3 _ . _ 9 _ _ 4 -
+ : + - + - - + + : +
_ 3 _ 7 _. 5 _. _ 5 _ _ 0 _ 0 _ 5 _ 0 _ Y __ 0- _ - _ E - _ 0 _ - . N _ E _ E . E . - _ E . D _ 6 _ 9 . 4 . E 8 _ S I 6 _ 7 _. 1 N O K8. 2 _ 6n.___ _ _ _ 8 - 4 _ . - 9 _ I _ _ _ . 5 - _ T + : + : + : : + + : + C _ _ . _ . E 3 _ 7 _ 5 . _ 5 _ W' J . 0 _ 0 _ 0 _ 5 _ 0 _ O R . - _ - _ - _ 0 . - _ R E E _ E _ E _ - E _ P V 6 _ 9 _ 0 _ E 0 _ I 8 _ 0 _ 8 _ 6 . 4 _ E L . _ _ _ 6 - _ 9 S . 2 _ 6 _ 3 _ - 7 _ 1 O . . _ _ 4 - .
- D + : + : + : : + + : +
MA V I 8 9 SD DA S _ 3 _ 7 _ _ 0 _ 0 . E _ - _ - _ 6 _ 0 _ 5 . 0 .
- _ 0 . - .
. 5 .
. 3 2
V 9 AR N _. 6E _ 9 _ _ E _ E _ - _ E . I E 1 RL O 7 _ E _ 5 . L LL B _ 8 _ 0 _ 2 _ 0 _ 7 _ MB A T L A U N LI IM M 3
. 2 _ 6 _
+ : + : +
8 _
+
. 1 .
2 _ _ 2 _
+ - +
NG 20 . _ _ _ - _ _ AE 0 - _ 7 - 5 _ _ 5 _ V T __ 3 M N U E0 29 E A0E _ E _. C R
. 0 . 0 . 5 _ 0 _
- . 0 _ - _
E _ - _ E _ O9 _ 9 _ 2 _ E _ 9 _ H1E 6. 4 T- __ 86 _ 0 _ 9 _ 2 . 8 _ L N 1 I _ _ _ _ 3 . A C .E
= G _ 2 _ 6 _ 2 _ 4 .
= _ . . _ 3 . _
M TNE R OS ES E + : + : + : : +
+ : +
L SO _ 3 . 7 _ 5 5 _ O I OD _ _ 0 _ 0 _.5 0 _ FNM D Y __E-0__ E- __ - _ 0 - _ O R D E _ - _. E _ R_I m I2 T8 A C4 IA A O _ 6 _ 9 _ B. _ _ 8 T2 _ 6 _ 0 9 _ E _ 1 _ 2 _ 9 _ 8 3 _ . _- 2 . O LT A_M A TM
+ : + : + : : +
_ 3 -
+ : +
A EA m L A I BG L_L AA Y_ A ._ W _ D _ _ N _ TU _ E _ T _ L _ N ._ IL . D_ C UU H M _ _ E . H U __ GA E D_ E P NN NN T __. E U _ O A_PL _. RG VE _ T ___ C .. _ m S AA P 1 1 lll1 }
_ 3 _ 7 _ _ 0 _ 0 _ 5 _ 0 _ 5 _ 0 _ _ 5 .
. E N - _ - _ - _ 0 _ - _
I E _ E . E _ - _ E _ _ K . 8 _ 9 . 6 _ E _ 0 _ S . 7 _ 7 _ 7 _ 6 _ 9 _ _ _ _ 1 _ _ _.9 _ 7 _ 2 _ 4 _ - _ _ . . 3 . _ _ + : + : + : - + + : + _ 3 . 7 _ 5 _ 5 _ 0 _ 0 _ 0 5 _ 0 ._ _ G _ - _ - _ - . 0 _ - _ E N _ E _ - _ E _ E-U_7 E ._ 1 _ 6 _.E _ 0 _ _ 4 _ 7 _ 6 _ 9 _ L ._ 1 _ _ 1 _
. 3 _ 6 2 _ . 4 _
. . . . 3 _ _
+ : + : + : : + + :
D I _ 3 _ 7 _ _ 0 _ 0 _ 3 0 _ 3 _ 0 _ _ 3 _ E O _ - _ - _ - _ 0 _ - _ R . E _ E _ E _ - _ E _ Y 0 _ 1 _ 1 _ E _ 7 _ H _.0 . 4 _ 1 _ 7 _ 6 _ T _ _ . _ 1 _ _ _ 3 6 _ 4 _ . _ 9 _ _ . _ . 5 _ .
+ : + : + - : + + : +
_ 3 _ 7 _ 5 _ _ 5 Y _ 0 _ 0 _ 0 _ 5 _ 0 _ E _ - _ - _ - _ 0 _ - . N _ E . E _ E _ - _ E . D _ 0 . 1 _ 0 _ E 8 _ S I _ _ 9 _ 9 6 _ N K _ 0 _. 4 _ . . 1 . _ O _ 3 _ 6 _ 4 . 9 _ I _ . _ _ 6 _ T + : + : + : : + + : . C _ . _ _ : . E _ 3 . 7 _ 5 _ . 5 ._ J _ 0 _ 0 _ 0 _ 5 _ 0 _ O R _ - _ - _ - _ 0 _ - _ R E E . E _ E _ - _ E _ - P V 0 1 _ 1 _ E _ 1 _ I _ 0 4 . 0 _ 2 _ 8 _ E L _ . . _ 9 _ . _ 0 S _ 3 _ 6 _ 4 _ _ 7 _ 2 O _ _ _ _ 4 ,. : +.
- D + : + : + : : +
A- _ _ _ _ : _ . 4 S . 3 _ 7 _ 6 _ _ 5 . 2 V 8 SD . 0 . 0 _ 0 _ 5 _ 0 . - I 9 DA E - - _ - _ 0 _ - _ V 9 AR N E E _ E _ - _ E _ I E 1 RL O . 0 1 _ 1 _ E . 9 _ L LL B 4 _ 7 _ 6 8 _ B L LI ._ 0 . _ . _ 2 _ A A IM _ 3 . 6 _ 8 _ . 2 _ M T U M . . _ _ 1 _ _ N 3 +: + : + : : + + - + NG 20 . _ . : . _ AE 0 - T ._ 3 . 7 _ 5 _ . 5 _ V E C _ . 0 . 0 _ 5 0 _ N ._ - U E5 01 A __E-0.. E-R
- _ 0 E . - _ E _
M O0 T _ 0 . 1 . 9 E _ 6 _ H2 7. 5 - _ 0 4 _ 0 0 _ 1 _ L 1 I . _ _ _ A ._ 5 C .E =
= G3 . 6 .
+: + : +
3
- 3 _
_ 5 _ OS E . + + : . TNE ES _ . _ . : _ . R L SO _ 3 . 7 5 _ 5 . O I . 0 . 0 0 5 _ 0 FNM D O D_ Y . - - - 0 _ - ._ O R D . E _. E E - _ E _ I4 R_I O 0 _ 1 _ 7 . E _ 5 . T9 0 _ 4 _ 4 . 0 _ 5 . A C4 IAA_A B. _ _ _ 6 _ 3 _
. 1 _
_ 6 . O A_M T ._ 3 _ _ . 4 _ _
+: + : + : : +
LT TM + : + _ L A EA BG Y_ _ _ T _ _ D _ A L_L_ A _ . L _ N _ L _
.E D_TU I AA W . . N _ E _ I _
C UU H M _ U _ ED _ E _ H _ E NN T .U _ O _ GA _ T _ _ P NN _L _ R C_ A_P _ E . S AA P _ G _ V . _ _
+ : + - + - : + , : +
2 . 5 _ 4 _ _ 4 _ N_0 _ I _ E _ E _
. 0 _
0 _ 4 _ 0 _
- _ 0 _ - _
E _ _ E _ K . 5 _ 2 _ 9 _ E" _ 7 _ S . 3 _ 9 . 2 _ 2 _ 0 _
. _ . . _ 6 _ _
_ 8 _ 1 . 2 _ _ 4 _ _ _ _ _ 2 _ _
+ : + : + : : + + : + _
_ 2 _ 5 _ 4 _ _ 4 _ _ _ 0 _ 0 _ 0 _ 4 _ 0 _ _ G . - _ - _ - 0 _ - _ N _ E _ E _ E - _ E _ U _ 2 _ 8 _ 9 E _ 7 _ L _ 7 _ 5 _ 2 ._2 _ 0 _ . _ _ . _ 6 _ _ _ 2 _ 1 . 2 _ . 4 _ - _ . . . 2 . _
+ : + : + : : + + : +
D _ 2 _ 5 1 _ _ 1 _ I _ 0 _ 0 ._ 0 _ 1 . 0 _ O - _ - _ - _ 0 . - _ _ R E _ E _ E _ - _ E _ Y . 8 _ 8 _ 1 _ E _ 7 _ _ H . _ 5 _ 0 _ 7 _ 3 _ _
. _ . 2 _ . _
T _. 25 1 _ 1 _ 2 .
. ._ _ . 1 . .
+ . + : + : : + + : +
_ 2 _ 5 _ 4 _ . 3 _ Y _ 0 _ 0 _ 0 _ 3 _ 0 _ _ E . - _ - _ - _ 0 _ - _ _ E _ E _ E - _ E _ . N D ._ 8 _ 8 _ 4 E _ 8 _ _ S I _ 5 _ 5 _ 5 . 1 _ 5 _ - N K _ _ . _ . _ 0 _ _ O _ 2 _ 1 _ 7 _ . _ 1 . I _ . . _ 1 _ . T + : + : + : . + + : + C _ _ . . : _ . E _ 2 _ 5 . 4 . _ 3 . J _ 0 _ 0 0 . 4 _ 0 _ O R _ - _ - - _ 0 . - _ R E _ E _ E _ E _ - . E _ P V _ 8 _ 8 _ 5 _ E _ 2 _ I _ 5 _ 5 _ 3 _ 5 _ 1 _ E L _ _ _ _ 9 _ . 1 S _ 2 _ 1 _ 5 _ 1 . 2 O _ _ _ 6 . _
- D 4 - + : + : : + + : +
A- , S 2 5 . 4 _. 4 _
. 5 2
V 8 SD ._0 . 0 0 _ 4 0 _ - I 9 DA E _ - _ - _. - . 0 - _ V 9 AR N _ E . E _ E . - E _ I E 1 RL O _ 8 . 8 _ 4 . E 1 _ L LL B . 5 . 5 . 1 . 9 1 _ B L LI . _ . . . 0 . . - A A IM _.2 _ 1 _ 2 . 7 - T U M _ - - . 3 ._ - N 2 + : + : + - - + + - + NG 10 . _ . . : _ AE 0 - T _ 2 _ 5 . 4 . ._ 4 _ V E C _ 0 _ 0 _ 0 _ 4 . 0 _ N E2 A _ - _ - _ - _ 0 - - _ U 54 R _ E _ E _ E _ - _ E _ O1 . B _ 8 . 0 _ E - 0 _ H2 L E
- 4. 4 1
T.5 I _
. 5 1 . 8 _
. 4 .
7 _ A .S = G_2 . 1 3 . - 4 _ C = _ . . 3 - . OS E + + + + + + - TNE ES _ _ _ R L SO _ 2 _ 5 . 4 4 _ O I OD _ 0 _ 0 0 _ 4 ._0 _ FNM _ - . - ._ - _ 0 _ - _ O I0 D_R_ RI Y_E D O _ 8 ._ 8 - E _ E _ - _ E _ 4 . E . 3 _ T8 _ 5 _ 5 - 0 . 4 . 1 _ A C1 IAA_ B. _ T_2_ _ 1
. . 9 _
4 . . . 8 _ O A_MA _ . _ 4 . _ LT TM + : + : + : : + + : + A EA _ . L B G_ Y ._ . . ._ _ A I L_L AA A _ _ D . W _ E _ N . TU_E _ I . T_N L _ LD ._ C UU H _ M . U _ _ E NN O _ E D __ E _ H C _. P S NN AA T.L A_P P
. U
. G R _
_ V GA.T E
+ : + : + : : + , : +
N_E I _ 1 _ 5 _ _ 0 0 _
. E 4 _
0 _ 4 . 0 _
- _ 0 _ - _
E _ - _ E _
. 4 _
K_2 S _ 9 _ 5 _ 4 _ 2 _ E _ 6 _ 5 _ 3 _
. . 0 _
2 _ _ 1 _ 5 . 3 . _ 6 _ _ _ . . 4 _ _
+ : + : + : : + 4 : +
_ 2 _ 5 _ 4 _ 4 _ 0 _ 0 _ 0 _ 4 _. 0 ._ G _ - _ - _ - _ 0 _ - _ N_3 U _ E _ E . L _ 2 _ _ 9 . E _ - _ E _ 2 . E _ 6 _ 5 . 3 _ 2 _ _ _ 4 _. . 0 _ _ _ 4 _ 4 _ 3 . _ 6 _ _ . _ _ 4 . _
+ - + : + : : + + : + .
D_2 5 _ 1 _ _ 1 _ I _ 0 . 0 . 0 _ 1 _ 0 _ O _ - . - . - _ 0 _ - _ R _ E E . E _ - _ E _ Y _ 1 ._ 9 . 5 _ E 1 _ H _
+
_ 4 T __4 0_. 4
+ :
+ : : +
8 _ 9 ._7 _ 5 _ 2 _ . _ 6 _
. 3 _
+ : +
_.2 5 _ 3 _ . 3 _ Y _ 0 _.0 _ 0 _ 3 0 _ E _ - _ - _ - _ 0 ._ - _ N _ E _ E _ E _ - _ E . D _ 1 _ 9 _ 4 _ E _ 5 . S I _ 4 8 _ 2 _ 9 . N O K.0 _
. 4 _ 4 _
1 _ _ 5 _ _ 3 I . . _ _ 2 _ . T + : + : + : : + + : + C _ _ _ _ i _ . E _ 2 _ 5 _ 3 _ _ 3 _ J _ 0 _ 0 . 0 _ 3 _ 0 _ O R _ - _ - . - _ 0 - _ R E _ E _ E . E _ - E _ P V _ 1 _ 9 . 2 _ E . 5 _ I _ 0 . 4 . 2 _ 3 _ 6 E L . . . _ 6 _ 2 S . 4 . 4 . 1 _ _ 2 2 O _ . . . 1 _ ._
- D + : + - + - : + + . +
A- _ _ _ . : . _ 6
, S _ 2 _ 5 _ 4 _ 3 _ 2 V 8 SD _ 0 _ 0 _ 0 _ 4 ._ 0 _ -
I 9 DA E _ - _ - _ - _ 0 _ - _ V 9 AR N _ E _ E . E _ - _ E _ I E 1 RL O _ 1 _ 9 7 _ E _ 2 _ L LL B _ 0 _ 4 ._ 0 _ 7 . 0 _ B L LI _ _ _ _ 7 . _ A A IM _ 4 _ 4 _ 6 _ . 2 _ T U M _ _ _ _ 8 _ . N 2 4. : + - + : : + + : + NG 10 _ _ _ - _ AE 0 - T _ 2 _ 5 _ 4 _ _ 4 ._ V E C _ _ 0 _ 0 _ 4 . 0 N E7 - _ - _ - . 0 _ - U 48 A R __E 0_ E _ E . - _ E _ O2 _ 9 _ 2 . E 6 _ H2E 2. 6 T- __ 01 _ 4 _ 8 . 6 0 _ L S 2 I _ _ . 4 . _ A .S = G _ 4 _ 4 5 8 _ C = - _ . 6 _ OS E + : + : + : : + + : + TNE ES . _ _ . - _ _ R L SO 2 _ 5 _ 4 . _ 3 _ O I ._0 _ 0 _ 0 . 3 _ 0 _ FNM O ,D_Y _ - _ - _ D - . 0 . - _ O R D _ E _ E _ E . - . E _ I9 R_I O . 1 . 9 . 0 _ E . 8 _ T8 0 4 6 A I A_ A B. _ . 5 ._ 0 7 ._ C0 T4 _ 4 . 8 _ . 1 _ O LT A_M A TM
+ : + : + : : +
_ 1 .
+ : +
A EA _ _ _ _ : _ _ G _ _ _ _ _ _ L Y _ _ _ . _ D _ A I B_L_ L AA A W _ E _ N D. TUT L _EN_L I _ C UU H _ M _ . ED _ E _ H _ E NN T _ U _ O U.GA _ T _ C _ P S NN AA A_L P _ _ R P _ G E V 1tL
l Il l l , 1l I:
]
+ : + - + : : + , : +
3 _ 6 - 5 _ _ 5 .
._0 _ 0 - 0 _ 5 _ 0 _
N _ - - - - - _ 0 _ - - I - E - E - E _ - _ E - K _ 6 . 5 - 0 - E _ 2 - S 4 - 7 - 5 _ 0 _
. - - - 9 - .
_ 6 . 5 . 1 _ . 3 .
- . _ _ 1 _ -
+ : + : + : : + + : +
6 . 5 _ _ 5 -
. 0 - 0 . 0 _ 5 - 0 _
G _ - . - . - _ 0 - - . E - E E _ - E . N ._ 5 - 9 U 0 - E _- 2 _ L - 0 _ 4 - 7 - 5 _ 0 -
- _ - - 9 _ .
- 2 . 4 - 1 _ 3 .
+ : + : + : : + + : +
D _ 3 - 6 . 2 - _ 2 - I - 0 _ 0 _ 0 2 D - - _ - _ - _ 0 - - -
- R - E _ E - E _ - - E _
Y . 4 5 - E H _ 9 - 4 - 8 7 - T1. . __ 4 - 2 -
- 5
+ : + : + : + + : +
3 . 6 - 4 - Y0 0 - 4 . 0 - E - - - - - - - 0 . - . N _ E . E - E - - . E _ D _ 4 . 5 _ 6 - E - 3 _ S I - _ 4 - 6 6 _ N - _ - 3 . - K __ 1 9 M O I T C E
- 4
+ : + : + - : +
3 . 6 _ 1 4 - 2 -
+ : +
- 4 _
J 0 . 0 _ 0 0 _ g O R R - - - - _ E - E - E _ E _- - - E - 0 - - _ P E V_9 I L - 9 _ 4 _ 4 - E 0 2 - 3 . 4 _ . 3 S . 1 _ 4 - 1 - . 2 . 2 O - _ - - 1 . -
+: + + +
MA V I D 8 9 SD DA S E _
- 3 _ 6
- 0 . 0 5 -
+
0 - 5 _ 0 .
- - 0 _ - -
+
_ 4 .
. 7 2
V 9 AR N . E . E - E - - E . I Ec 1 RL O - 4 . 9 7 _ E - 2 . ME B A T L A U LL LI IM M B _ 9 _ 1 . 4 -
. 4
+: + : + : : +
0 6 . _ 7 - 0 . _ 8 - 7 - N 3 + : + NG 20 . _ - - - - _.3 . 6 - AE V 0 - E CT_0 . 0 - 5 - 0 0 - M N U E2 83 A_E R _ E . E
- 0
- _ E -
O3 H2 L
- 0. 3 1
T_9 I _ _ 4 . 9 . 4 . 0 0 _ E _ 3 - 8 _ 3 _ 8 - A' .S = G.1 . 4 - 4 - _ 4 . C - . - . M TNE OS
=
ES E +: + : + : : +
+ : +
R L SO . 3 - 6 _ 5 - _ 4 _ F O I - 0 _ 0 - 5 _ 0 . FNM O D_ D Y - . - _ - _ 0 _ - - O I4 R_I R D O _E _. 0. E _ 4 . 9 _ E _ - . E - 8 _ E . 5 _ T7 I B.
- 9 _ 4 _ 6 _ 5 . 4 .
A _ - - 5 _ . n C0 O A_A_ AM A T1 - _ 4- - . 6 -
- 8 _
_ 1 . LT TM +: + : + : - + + : + A EA . - . : . - BG . - _ . . - t L Y - - . A L_L_ A _ D _ L L I AA W
- N - TU T ._ N . ID. E -
i C UU H ._ M E - U . ED - E _ H - E NN . O - _ P NN T ___U R _ AL G A _ T __ C _ E S AA P P _ G _ V _ - - l F 1 (!fjl
lil i li i1Ii1I l1l}'!< i111 i1 ll lll1l
+ .
+ : + - : + + - +
_ 8 - 7 . - 7 . 0 . 0 0 - N . - _ - _ - - - I . E - E . E - - - E - K _ 3 0 - E S _ 7 - 5 - 7 . 7 - 3 -
- - - - 3 - -
. 1 _ 7 - 4 - - 8
+ : + : + : : + + - +
- 5 _ 8 . 7 - 0 - 0 7 G . - - - - - 0 . - -
N . E - E _ E . - . E . U . 4 0 . E . 4 L . 6 . 2 7 3
. - - 3 - -
. 5 4 - . - - . 5 - -
+ : + : + : : + + : +
D 8 - 4 - - 4 . I - 0 _ 0 - 0 0 - O . - - - - - - - xE . E - E - - - E - x 5 . 2 - 5 - E - 9 . u.3 . 2 . 9 2 - T - . _ - 6 _ 3 - . - - - -
+ : + : + : : + + : +
8 - 6 - . 6 . Y - 0 0 6 . 0 . E - - - - . - _.0 - - - N - E - E E . - - E - D - 5 . 2 3 - E S I - 3 . 2 . 5 4 - N K - - . - 4 - - O 6 . 2 - I - - - - _
+ : + : + : : + + +
T - : . C - - - - . E - 5 . 8 - 6 . _ J - 0 . 0 - 0 _ 6 . O R - - - - . - . 0 - - - _ R E . E - E - E - - - E - - P V . 5 7 - E _ I . 3 - 2 - 6 6 . . E L . - - - 2 - - _ 4 S . 5 1 - _ 2 O . - - . 2 - -
- D + : + + : : + + : +
A . - - _ _ - 8 2
- , S 8 7 - V 8 SD 0 _ 0 0 -
V I 9 DA E - - - - - - . 0 - - . 9 AR N - E - E - E . - _ E I E 1 RL O 2 _ 1 E - 9 L B A T L A U N LL LI IM M 5 B - 3
. 5 -
+ :
+
2
+ : -
4 8 - 1 - 2 -
+ +
7
+
NG 40 - - _ - . - - AE 0 - T.50- _-0 -- -
- - 8 _ 7 - N U
O4 V E5 91 E C A_E R - f - 5 . 2 -
. E -
0 0 - E 7 _-E
- - E .
H2W 9. 9 *
- - 3 . 2 - 8 . 4 - 0 -
L S 2 I - . - . - 7 - - A .S G - 5 . 6 .. 7 - . 1 -
=
C = - - - 8 _ - OS E + : + - + : + + - + TNE ES - - - _ - - R L SO . 5 - 8 6 _ O I OD . 0 - 0 _ 0 0 - FNM D Y- - . - - - _ 0 - - - O R D - E - E - E - - - E - I2 T0 A C2 R_I IA A O 2 - B. -
- 3 -
2 - 6 1 1 -
._5 E 4
. 2 -
4 - O LT A_E A T T.5 + :
+ : + : : +
- 1 .
+ :
+ -
A EM . - . - : - . BG . - . - - . L A I L_L AA Y.. A.E W
- D.TU N
T L NDL -
- E - I -
C UU H - MU . ED _ E - H - . E P S NN I MA N T - AL U.R P - P . G _ V O - GA . _ E . T.C .
- f1!ll 1l11l1
l1
+ : , : , : + + : +
2 _ 6 . 5 _ 4 _ _. . 0 . 0 _ 5 0 _ N __7 _ I
- _ 0 E _ -
K _ S _ 0 . 6 E.2E _ 1 _ E 5 3 5 E_ 1
. . 7 . _
3 6 . 8 . _ 1 _ _ . 9 _ .
+ : + : + : : + + : +
. 3 _ 6 5 . . 4 .
G0 N E
. 0 .
E 0 . 5 . 0 . E
- 0 U_8 . 5 _ 1 . E _ 1 E..
L_9 . 9 _ 5 _ 4 _ 5 8 _ _ 3 _ _ 7 .
. 1 5
. . - _ 9 _ .
+ : + : + : : + + : +
3' _ 6 _ 2 _ D.0 I
. 0 _ 0 . 2 . 0 _
- . 0 _ - _
. 2 _
O_E R Y _ ._ 5 _ E _ E . - _ E _ 8 _ E _ 9 . H ._45 .. 4 _ 4 _ 8 _ 1 . T.9 . _ 5 _ 3 3 4 . _ 8
+ : + : + : : + + : +
. 3 ._6 . 4 _ 4 _
Y E0 NE _ E . _ 0 _ 0 E
- . 0 _ - _
4 _ 0 _
- _ E D 5 _ 5 7 E _ 7 S I . 4 ._ 6 . 5 _ 5 .
N O K4 9 . 5 _ 2 5 _
. 5 I . . ._ . 3 . .
T + : + : + : : + + : + C _ . . _ : . E _ 3 _ 6 . 4 . 4 J _ 0 _ 0 0 . 4 0 . O _ - _ - ._ 0 R P R_E E . E _
. 5 _
E 1 - E _ 8 . E _ V I __ 45 4 - 9 - 7 _ 9 E L _ - . 4 _ 5 S _ 9 5 . 1 . _ 3 . 2 O . . - 2 . _
- D + : + : + : : + + : +
A- . _ . . : . - 9
. S _ 3 _ 6 _ 5 . 4 - 2 V 8 SD _ . 0 _ 0 4 0 . -
I 9 DA - - . - _.0 _ - V 9 AR E N_5 __E 0 E . E . - _ E I E 1 RL 5 E . 6 . L B L LL LI O_4 B
. 4 0
4 7 . 0 4 . A A IM _ 9 _.5 _ 7 . 2 _ T U M . _ . _ 1 . _ N 2 + : + : + : : + + : + NG 20 . . _ _ : _ . AE 0 - T.3 . 6 _ 4 _ _ 4 . V E 0 _ 0 _ 4 . 0 N E2 C ._ A 0-U O5 36 R.E T5 _.5 E- __
. E3- _ 0 . -
E _ 3 E.. H2 3. 1 - 4 _ 4 _ 1 7 . 7 _ L W 5 I . . _ 2 . _ A .S C OS
=
E
=
G9 + : + _. 5
- + : : +
1 1
+ : +
1 _ TNE ES . . . : . _ R L SO . 3 6 n . . 4 _ O I _ 0 . O 4 0 FNM D O D_ - - . - 0 _. - O R Y __E 0 E _ D E . - _ E I1 R_I O5 . 5 _ 6 . E _ 2 T4 4 . 4 . 4 . 8 _ 9 A C1 I A_ A A B.
. . 7 _
O LT A_M TP T.9 + : + _. 5
- + : : +
1 1
+ : +
2 . A EA . . . : _ . BG . ._ . _ Y L A L_L_ A . D . T.NE L
. . D L
I C E AA UU NN HE W TU
. N _ TU U_ED.T E .
I H_ M . ._ R O GA. ._ E C._ P S NN AA A.P P L
. G.V . . .
i.
+ : + : , : : , + : ,
_ 2 . 5 4 _ _ 4 _ _ 0 . 0 _ 0 _ 4 _ 0 _ N _ - _ - _ - _ 0 _ - _ I _ E _ E _ E _ - _ E _ K _ 9 _ 8 _ 8 _ E _ 0 _ S _ 5 _ 5 _ 0 _ 8 _ 7 _ _ _ _ _ 3 _ _
. 7 _ 1 _ 2 _ _ 3 _
+ :
+ : +
- : ,2
+
_ 2 . 5 _ 4 ._ . 4 _
. 0 . 0 _ 0 _ 4 _ 0 _
G . - - _ - _ 0 _ - _ N . E ._ E _ E _ - _ E _ 8 _ E _ 0 _ U _ 8 _ 0 __ L _ 4 _ 3 0 _ 8 _ 7 _ _ _ _ _ 3 _ _ _ 2 _ 1 _ 2 _ . 3 _ _ _ _ _ 2 . _
+ : + : - : + 4 : +
_ _ 4_ _ : D _ 2 _ 5 _ 2 . _ 1 I _ 0 _ 0 _ 0 . 1 _ 0 . O _ - _ - _ - . 0 _ - . R _ E _ E _ E . - _ E . Y _ 5 _ 0 _ 1 . E _ 6 . H _ 3 . 3 _ 3 . 5 _ 9 . T _ . _ _ 0 _ . _ 2 . 1 . 8 _ _ 1 _ _ _ _ 1 _ _
+ : + : ,. .- + + : +
._2 _ 5 _ 4 _ _ 3 _
Y_0- __ -0 __ E N _ E _ E _ 0 _ 4 _ 0 _
- _ 0 _ - _
E _ - . E _ D _ 5 _ 0 _ 2 _ E 4 _ S I _ 3 _ 3 _ 4 _ 4 3 _ N O K_2 _ _ 1 _ _ _ 5 . 6 _ . _ 1 _ I T : + : + : -
,8
+ : +
C 4_ _ . : . _ E _ 2 5 . 4 . 4 . J _ 0 _ 0 . 0 _ 4 ._0 . O R _ - _ - . - . 0 _ - . R E _ E _ E _ E . - _ E _ P V . 5 _ 0 _ 1 . E _ 1 _ I _ 6 ,. 6 _ 6 _ E L _._ 32 _ 13 __. 4 _ 9 _ _ 9 _ 6 S 2 O _ _ _ . 5 _ _
- D +: + : + : : + + . +
A . _ - _ - _ _ 0
- , S . 2 _ 5 . 4 _ _ 4 _ 3 V 8 SD . 0 _ 0 _ 0 _ 4 . 0 _ -
I 9 DA E _ - _ - _ - _ 0 . - . V 9 AR N _ E _ E _ E _ - . E . I E 1 RL O _ 5 _ 0 _ 7 _ E _ 7 . L LL B _ 3 _ 3 _ 7 _ 5 _ 8 . B L LI _ _ _ _ 5 _ . A A IM _ 2 _ 1 _ 1 _ . 5 T U M . _ _ _ 2 . N 2 +: + : + : - + + : + NG 10 . _ _ _ - _ _ AE 0 - T . 2 _ 5 _ 4 _ _ 4 _ V E C _ 0 _ 0 _ 0 _ 4 _ 0 _ N E2 A _ - _ - _ - _ 0 _ - _ U 20 R _ E . E _ E _ - _ E _ O6 T _ 5 0 _ 5 _ E _ 3 _ H2W 3. 4 - _ 3 ._3 _ 7 _ 9 _ 2 _ L S 1 I . . _ _ 0 . _ A W = G _ 2 1 _ 2 _ . 4 _ C . = _ . . 3 _
+ + : +
OS E +: + + : : TNE ES _ . . _ : . . R L SO _ 2 _ 5 . 4 . . 4 . O I . 0 _ 0 . 0 . 4 . 0 . FNM O D D_ Y _ - _ - . - E ._ 0 - _ _.E _ O R D _ E _ E . - I3 R_I O_35 _ 0 3_ . 3 _ E _ 6 _ 5 . 0 _ 0 _ T2 _ _ A C1 I A_ A B. . _ 1 _ 3 .
. 3 _
_ 7 _ O LT A A_M T T.2 +- + : +
- 4 _
+ + : +
A EA _ _ _ - . _ BG _ _ _
._D _
L Y_ _ _ T. A L_L_ . D _ L . N _ L _ I C AA UU A_E W H _ M ._ N .
. TU_E _ _ I _
E NN T_U _ O ED_E U_GA_T_C _ H _ P NN . L _ R _ E S AA A.P P _ G _ V _ .
,! L
1 , e -
, : + : , t : + + : +
. 4 _
N1 .E
. 4 .
0 _50 0 4 0 0 _ I . E _ . E . - _ K 3 3 0 E _ E 4 __ S 7 . 4 _. 7 7 _ 3
. _ . 3 _
.1 2 _ 4 _ 8
. . 5 .
+ : + : + - : + + : +
_ 2 . 5 _ 4 . _ 4 _ _ 0 0 _ 0 4 . 0 _ - - . 0 G_E N_4 U
. E 0
E 0 E . 4 . E L6 0 7 _ 7 . 3 . _ 3 - 5 2 . 4 _ 8 . _ _ . . 5 . .
+ : + : + : : + + : +
D2 5 1 - 1 _. I 0 . 0 0 _ 1 0 _ O - . - . - - 0 - . R E.E . E . - E Y 5 . 0 _ 7 . E . 0 ._ H . 0 2 _ 0 . 0 _ T3 5 2 1
. 6 .
3 . _ 1 .
+ : + : + : : + + : +
_ 2 5 3 _ 3 Y . 0 0 . 0 _ 3 0 . E - _ - . - _ 0 . - . N E _ E . E _ - E _ D _ 5 _ 0 3 _ E 2 . S I _ 3 . 0 1 . 8 3 N O I K5 . _ 2 _ 1 _.1 4
. 2 -
T + : + : + : : + + : + C _ . _ _ : . - E . 2 . 5 _ 4 . . 3 - J O R R0 E E _ E 0 _ 0 . 3 . 0 . E
- 0
- E P V5 . 0 7 . E . 4 .
I 3 . 0 5 _ 9 . 7 E . _ _ 0 . 7 S L ._ 5 . 2 _ 8 _ _ 1 _ 2 O . . - _ 1 - _
- D + : + : + : : + + : +
A _ . . _ : _ _ 1
- , S _ 2 . 5 . 4 _ _ 4 . 3 V 0 SD _ 0 0 0 _ 4 _ 0 . -
I 9 DA E _ - _. - _. - _ 0 _ - . V 9 AR N_E _ E _ E . - . E I E 1 RL O_5 _ 0 _ 1 . E . 9 ._ L LL _ 0 _ 7 1 9 _ B L LI B __ 3 _ . 9 . A A IM _ 5 _ 2 . 2 . . 8 - T U M _ _ . - 3 . - N 2 + : + : + : : + + : + NG 10 _ _ . : _ - AE 0 - . _ 5 N V E5 E T.2 C A0 - ._ -0 ._ 4 0 4 _ 0 0 _ - _ _ 4 U 91 R EE _ E - _ E - O7 . 5 0 . 2 . E _ 5 H2 L
- 9. 9 2
T.3 I .
. 0 7 5 _
4 _ 1 _. A W . 2 . C OS
. =
E
=
G.5 + : + 5 .
. 6 .
_ 9 .
- + : : + + : +
TNE ES . . . : . _ R L SO 2 5 _ 4 _ 3 _ O I OD . 0 0 0 4 _ 0 . FNM Y . - - - . 0 . - . O D_R_ D E E . E _ - . E . O I0 T2 A RI IAA_ B. 5 3 0 0 _. 2 _ 9 _ 1
. 3 E_53 _ .
C1 A O LT A_4 TP9 T.5 + : 2 .
+ : + : : +
6 . _ 8 . _ 1
+ :
A EA _ . _ : . r. BG . . . . L A I L_L_ AA Y. A.E W
. D _
_ T L NLD. . I . C UU H . _. N _ TU E NN T.U.U_ED M.O _ GA . . C E . P S NN AA A P L_GR VE P _ ET_H . 11 ,
, : , : + : : + , : +
_ 2 _.6 _ 4 _ _ 4 _ _ 0 _ 0 _ 0 . 4 _ 0 _ N _ - _ - _ - 0 _ - _ I _ E _ E _ E _. - _ E _ K _ 2 _ 2 _ 9 _ E _ 9 _ S _ 6 _ 1 _ 2 _ 8 _ 2 _ _ _ _ _ 4 _ _ 4 _ 4 _ 1 _ . . 2 _ _ . . 1 _
, - + : + : : + ,. : ,
_ 2 _ 6 _ 4 ._ _ 4 _.
. 0 _ 0 _ 0 _ 4 _ 0 _
G . - _ - _ - _ 0 _ - _ N _ E _ E _ E _ - _ E _ U_5 L _ 0 _ 9 _ _ 3 9 _ E _ 9 _ 2 _ 8 _ 2 _ _ 4 _ _ _ 1 . 3 _ 1 _ _ 2 _ _ _ . _ 1 _ _
+: + : + : : + + : +
. 2 _ 6 _ 2 _ . 2 _
D.0 I O _ 0 _ 0 _ 2
- _ 0 0 _
R ._E _ E E _ - _ E _ Y _ 2 _ 9 ._ 7 _ E _ 1 . H _ 4 _ 3 _ 1 _ 4 _ 1 T_1 _ _ 3 _ 2 _ 7 _ 2 . _ 5 .
+: + : + : : + + :
_ _ _ _ : _ 4_ _ 2 _ 6 _ 4 _ _ 4 _ Y E N 0 E 0 E 0 _ 4 _ 0 _
- _ 0 _ -
E _ - _ E W D _ 2 _ 9 _ 2 _ E _ 2 . S I _ 4 _ 3 _ 4 _ 8 _ 8 _ N K _ _ _ _ 0 _ _ O _ 1 _ 3 _ 2 _ _ 4 _ I . . . - 3 _ . T +: + : + : : + + : + C _ . _
- _ .
E 2 _ 6 4 _ _ 4 . J . 0 . 0 0 _ 4 _ 0 _ O R - . - _ - . 0 _ - _ R E ._E . E _ E . - _ E _ P V 2 9 _ 5 _ E _ 3 _ I 4 3 . 9 . 1 _ 8 . E L _ . _ . 4 _ _ 8 S _ 1 . 3 _ 1 _ _ 3 _ 2 O _ _ _ - 2 .
- D +: + : + : - + ,. - +
A-V 8 SD S _ 2 _ 6 _ _ 0 _ 0 _ 5 _ 0 _ 5 _ 0 _ _ 4 _
. 2 3
m I 9 DA E _ - - _ - _ 0 _ - _ V 9 AR N _ E E E _ - _ E _ I E 1 RL O _ 2 . 9 ._ 1 _ E _ 3 _ L LL B _ 4 _ 3 _ 6 _ 6 _ 5 _ B L LI _ _ _ _ 6 _ _ A A IM . 1 _ 3 _ 4 _ . 1 _ T U M . . . _ 6 _ . N 2 +: + : + : : + + : + NG 20 . _ _ : _ _ AE 0 - T ._ 2 _ 6 _ 4 _ _ 4 _ V E C_0 _ 0 _ 0 _ 4 _ 0 _ N E4 - _ - _ - . 0 _ - _ U 44 A R ._ E _ E _ E . - . E _ O8 . _ 9 _ 7 . E . 3 _ H2W L N
- 0. 2 8
T.2 I . 4 _ 3 _ 4 . 6 . 4 . A . W . 1 ._ 6 2 C OS
=
E
=
G.1 +: + : + _ 3 _
- a
- 1 _
+ + : +
TNE ES _ _ . . : _ . R L SO _ 2 _ 6 _ 4 _ _ 4 _ O I _ 0 _ 0 _ 0 _ 4 _ 0 _ FNM D O D_ Y _ - . - _ - _ 0 _ - _ O R D _ E . E _ E _ - _ E _ I0 R_I O _ 2 . 9 _ 7 _ E _ 7 _ T7 IA B. _4 _ . 3 _ 6 _ 8 1 _ A A _ _ 9 _ C2 4 I T A_A_ TM M T_1 _
+: +
3 _
+ : : +
1 _ _ 1 .
. 3 _
+ : +
A EA _ _ _ _ : . _ BG _ . _ _ . _ L Y _ . . D _ A L_L_ AA A_E ._ N _ W _ D _ T_N L L _ I C UU NN H .M _ U _ T .U _ O _ TU_E ED E _ I _ H _ E P S NN AA A.L _ R _ P . P _ G _ V GA_T_C E
ill , ' lllll ll
, : + : + : : + + . ,
_2 . 6 _ 4 _ _ 4 _ _ 0 0 _ 0 _ 4 _ 0 _ N _ - - _ - _ 0 _ - _ I _ E _ E _ E _ - . E _ K _ 2 _ 1 _ 4 _ E 5 _ S _ 2 . 8 _ 4 _ 4 5 _ _ . _ _ 6 _ _ 5 5 _ 1 _ 2 _ _ _ . 1 . -
, : + : + : : + + - +
. 2 _ 6 . 4 _ _ 4 _.
. 0 _ 0 0 . 4 _ 0 _
G _ - _ - - _ 0 _ - _ N _ E _ E E _ - _ E _ U . 0 _ 9 _. 4 _ E _ 5 _ L 7 _ 7 _ 4 _ 4 _ _ _ _ 6 _. 5 _ 1 _ 4 _ 1 _ _ 2 _ _ - . 1 _ .
+ : + : + : : + + : +
D _. 2 _ 6 _ 2 _ _. 2 _ I _ 0 _ 0 _ 0 _ 2 _ 0 _ O _ - _ - - _ 0 _ - _ R _ E _ E E _ - _ E _ Y _ 1 _ 9 . 6 _ E _ 0 _ H . _ 7 . 0 _ 5 _ T6 1 _ 4 _ 3 _ .
- 8 _
2 7 _ _ _ . 3
+ - + : + : : + + : +
_ 2 _ 6 _. 4 _ 4 _ Y _ 0 _ 0 _ 0 _. 4 _ 0 _ E _ - _ - _ - _ 0 _ - _ N _ E _ E _ E _ - _ E _ D _ 1 _ 9 _ 3 _ E _ 2 _ S I _ 6 _ 7 _ 0 _ 1 _ 1 _ N K _ _ _ _ 9 _ . O _ 1 _ 4 _ 3 _ . 6 M E I T C
+
._2
+ : + - : +
_ 6 _ 4 _
. 3 .
+
_ 4 . 4 J O R R_0 _ E _ E _ E _ _ 0 _ 0 _ 4 _ 0
- _ 0 _ -
E _ - _ E _ M P E V I L _ __ 61 _ 9 _ 7 _ 7 _ E _ 3 _ 3 _ 6 _ 7 . _ 9 _ .
'9 S _ 1 _ 4 2 _ 4 2 O . . . 2 _
- D + : + : + : : + + - +
MA V 8 9 SD DA S E _ 2 _ 6 _ _ 0 _ 0 _ 5 ._ 0 _ 5 _ 0 _ _.4 _ _ 3 3 I 9 AR E _ E _
- _ 0 _ - _ V E _ - _ E _ I E 1 RL O N _._1. 6__ 9 7_ 0 _ E _ 6 _
m' L B A T L A U N LL LI IM M 2 B
+
_ 1 - 4 _
- +
+ : : +
5 _ 9 _ 1 _ 6 _ _ 3
. 9 .
_ 2 .
+ : +
NG 20 . _ _ _ : . _ AE 0 - _ 6 _ 4 _ . 4 _ V T __ 2 M N U
- E E6 67 C_0 A_E R
_ E 0 _ 0 . 4 _ 0 _
- . 0 _ - _
E . - _ E _ O9 H2 L W 9
- 0. 2 T_6 I _
_ 1 _ 9 7 . 8 6 _ 9 _ E . 5 _ 0 _ 7 _ A N = G _ 1 _ 4 1 _ . _ 2 _ C . = _ _ _ _ 1 _ . M TNE OS ES E +: + : + - : +
+ : +
R L SO _ 2 _ 6 . 4 . 4 _ O I OD _ 0 _ 0 _ 0 _ 4 0 _ FNM Y _ - _ - _ - _ 0 _. - _ O D_R_ D _ E _ E _ E _ - _ E _ m A I8 T6 C2 RI I A_ A_A_ O _ 1 _ 9 B. _6 T_1 _ 4 _ 7 _. 7 _ E _ 9 _ 9 1 _ _ 5 _ _ 3 _
. 3 _
7 _ O AM _ _ _ . 2 . _ LT TM + . + : + : : + + : + A EA _ _ . : . m L A BG L_L_ Y A_
._ ND __
_ T L _. N_LD __ I AA W TU _ E _ I _ C UU H _E M_U _ ED _ 7 . H _ E NN O _ . _ P NN T _ U ._ R _ EG A __ AL T_C m S AA P P . G _ V _ _ j T n l(l'll
M
+ -
+ + + : : , + : ,
_ 2 _ 6 _ 5 _ _ 5 _ - _ 0 _ 0 _ 0 _ 5 _ 0 _ N _ - _ - _ - _ 0 _ - _ I _ E _ E _ E _ - _ E _ K _ 7 _ 6 _ 9 _ E _ 6 _ S _ _ 9 _ 1 . 9 _ _ 7 ._ 4 _ . _ 7 _
. 1 _ 2 _ 4 _ 8 _
_ _~ _ 5 _ .
,. : + : + : : + + : +
_ 3 _ 6 _ 5 _ 5 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ G _ - _ - . - _ 0 _ - _ N . E _ E . 2 _ - _ E . U . 6 . 3 . 3 _ E _ 6 . L _ 7 . 0 . 9 _ 1 _ 8 _ . _ 7 _ _ 5 2 . 4 _ _ 8 .
+: + : +
- : ,5
+ - +
. 3 . 6 _
2 _
. 2 _
M D.0 I O . - _ -
. 0 0 _ 2 . 0 _
- _ 0 . - _
R _ E _ E . E _ - . E _ Y _ 5 _ 3 _ 0 _ E . 5 _ H _ 4 0 _ 3 3 . 0 _ T _ _ 6 . _ _ 5 _ 2 _ 1 . _ 3 _ _ _ _ _ 1 . _
+: e + : : + + : +
_ 3 6 4 _ _ 4 _ Y _ E _ N _ 0 E _ E . 0 0 _ 4 . 0 .
- _ 0 . - _
E _ - E _ M D _ 5 _ 3 7 _ E ._0 _ S I _ 4 _ 0 1 _ 3 _ 4 _ N K _ _ _ . _ 5 _ . O _ 5 _ 2 _ 1 _ . _ 2 I _ _ _ _ 1 _ _. T +: + + : + + + : + C _ . _ : _ E _ 3 6 _ 5 ._ _ 4 ._ J . 0 0 _ 0 _ 4 _ 0 _ O R . - . - . - . 0 _ - _ R E . E E . E - _ E _ P . 5 _.3 E _ 1 _ E V.4 I L . 0 3 9 . 3 _
. 1 _
8 . 0 S . 5 _ 2 . 8 . _ 1 3 O . . _ 1 _ ._
- D +: + : + : : + + : +
4 A . _ _ . : _ _
- , S 3 _ 6 _ 5 . _ 5 _ 3 V 8 SD 0 _ 0 _ 0 _ 5 _ 0 _ -
I 9 DA E . - _ - . - _ 0 _ - . V I 9 AR N . E _ E . E _ - _ E . E 1 RL O 5 _ 3 . 6 _ E . 5 . L LL B 4 _ 0 . 7 _ B _ B L LI . _ . _ 9 ._ 1 _ A A IM _ 5 _ 2 . 2 _ _ 9 _ T U M _ . _ _ 3 _ _ N 3 +: + : + : : + 4 : + NG 20 _ _ . _ : _ AE 0 - T _ 3 _ 6 . 5 _ _ 5 _ V - E C _ _ 0 . 0 _ 5 _ 0 _ N U O0 E5 93 A R __E 0_ T _ 5 _ 3 _ E _
- _ 0 _ - _
E _ - _ E . 3 _ E _ 8 . m H3W 0. 9 - _ 4 _ 0 _ 0 _ 1 _ 6 . L N 3 I _ _ _ _ 8 _ . A .N = G _ 5 _ 2 . 6 _ _ 9 . C = _ . _ _ 6 _ OS E +: + : + : : + + : + TNE ES _ _ _ _ + _ . R L SO _ 3 _ 6 _ 5 _ _ 4 . O I OD _ 0 . 0 _ 0 _ 5 _ 0 . FNM Y _ - E
- _ - _ 0 _ -
E _ - _ E O D_R_ D _ E I4 RI O _ 5 3 5 . E _ 1 . T1 . 4 0 _ 2 . 0 _ A IAA_ B. . _ . 7 _ 4 ._ C4 A . 7 _ 1 _ O A_M T.5 +: + _. 2 _
+
._ 8
+
+ : +
LT TM : : : A EA _ . _ _ BG _ . _ _ _ L Y _ . . T _. _ D _ A L_L_ A _ . D . L _ N _ L _ AA W _ E . N _ E _ I _ I C UU H M _ TU_E ED _ H _ E P S NN NN AA T A P
. L
.P U _ O U.GA_T.C
. R . E
. G . V
1
+ .+ : + : : + + : +
_3 _7 _ 6 . _ 6 _ 0 0 6 _ 0 N _ - _0-
- ._0 _ -
I _E E _ E _ - _ E _. K_8 S _ 4 - 1 _ 8 _ 7 _ E _ 6 _ 9 _ 6 _ _ 3 . 8 _
. 9 _ 7 _ 3 _ . _ 2 -
_ _ . _ 2 _ -
+ : + - + : : + + : +
. 0 3
_.0 7 6 _. - . _ 6 _ 0 _ 6 _ 0 _ G - _ - _. - _ 0 - - . N _- E _ E E _ - _ E - U _ 9 _ 4 _- 7 _ E - 6 L _ 1 _ 4 _ 9 _ 6 _ 8 _ _ _ _ _ 3 _ .
- 3 6 _ 3 _ _ 2
. ._ . . 2 _ -
+ : + : + .: + + : +
D - 3 _ 7 _ 4 _ I . 0 . 0 _ 0 _ 4 _ 0 O _ - _ - _ - _ 0 _ - _- R - E _ E _ E _ - - E _ Y - 2 _ 4 . 9 _ E - 5 _ H _ 0 _ 4 8 _ 6 - 0 _ T- . - _ 3 - -
- 3 . 6 1 _ - . ._ . 1 . .
+ : + : + : - + + : +
_ 3 _ 7 . 6 _ _ 6 _ _ 0 0 _ 6 Y __ 0- - - E _- - . 0 - - - N.E - E _ E _ - - E - 2 - 4 _ 3 _ E S D I _. _ 4 _ 9 _ 5 _ 8 _ N 1 - O I K __3 0_ . 6 _ 4 - _ . . 3 _ - T + : + : + - - + + + + C _ . _ - _ _ E _ 3 ._7 . 6 _ _ 6 _ J _ 0 _ 0 0 6 _ 0 . g' O R P R _ - _ - E _ E _ E . _ 4 _ E 3
- 0 . - -
- . E -
E . 7 - V I __ 02 _ 4 _ 5 _ 2 . 4 _ E L . _ _ _ 8 _ 1 S - 3 . 6 . 4 _ 3 - gA O 3 - . - - 2 . _
- D + : + : + : : + + : +
_ _ _ . : _ - 5 S _ 3 _ 7 _ 7 _ 7 - 3 V 8 SD _ 0 0 0 _ 7 0 _ - I 9 DA E _ - - - _ 0 - _ V 9 AR N _ E E E _ - - E . I gA E L B T 1 L A U RL LL LI IM M B O 2 0 _ _ 3 _ 6 . 4 4 _ 4 _ E 9 3 _ _ 7 - 0 _ 3 _ 2 - .
- 6 _
NF 3 +- + : + : - + + : + NE 20 _ _ - : - _ AE 0 - T _ 3 _ 7 _ 6 _. _ 6 - g N U B E9 11 E C A R _ E . E _ 0 _ 0 _ 0 _ 6 _ 0
- _ 0 _ - _
E . - - E _ O1 4 _ 1 _ E 2 - H3 7. 5 T- ._ 20 _- 4 _ 1 _ 5 _- L 1 I _ _ _ . _ 4 _ 9_ A .E = G _ 3 _ 6 _ 4 _ _ 2 _ C = . _ _ _ 2 _ - OS E + : + : + : : + + : + TNE ES _ _ . _ : - _ R L SO - O I _ 3 _ 7 _ 0 - 0 _ 6 - 0 _ 6 - 0 .
- 6 .
FNM D O D_ Y - - _ - _ - _ 0 - - . g O I1 T9 R_I R D O _. E 2 _ _ E _ 4 _ 4 E _ - . E 9 _ E _ 1 2 1 _ 2 A . I A_ B. _ 0 .
. 6 -
C4 A T3 - . 6 . . 4 - 3 . O LT A_M A TM +: + : + : : + _ 2 .
+ : +
A EA . _ _ . : . _ BG _ _ . _ _ L Y . . _ A L_L_ A D T ._ _.LD_ L I C AA UU W.E ._ N _. U ._E N_ I _ H _ M _ TD E _ _ E NN T _ . C . P NN _U ROU . E._ A A _ T __ . H S AA A_PL.G P . M _ _ . l\
+ : , : , . : , , :
_ 2 , 6 , 6 _ _ 6 _ _ 0 , 0 , 0 _ 6 _ 0 _ N_E _ E . I
- _ 0 _ - _
E . - _ M K _ 3 _ 9 _ 9 . E _ E 5 __ S _ 0 _ 7 _ 0 _ 4 _ 9 _ _ _ _ _ 4 _ . _ _ 1 _ 1 _ 4 _ _ 2 _
+ : , : , : . ,2 ,_ :
_ 3 _ 6 _ 6 _ _ 6 _ _ 0 _ 0 _ 0 _ 6 _ 0 _ G _ - _ - _ - _ 0 _ - _ N _ E _ E _ E _ - _ E _ U_7 _ 7_ _ 9 _ E _ 5 _ L _ 3 4 _ 0 _ 4 _ 9 _ _ _ _ _ 4 _ _ _ 3 _ 1 _ 4 _ _ 2 _
. _ _ . 2 _ .
+ : , : , : : + , :
D_3 _ 6 I _ 0 _ 0 . 4 _ 0 _ 4 _ 0 _ _ 4 _ M O _ - _ - - _ 0 _ - _ R _ E _ E E _ - _ E _ Y _ 9 _ 7 6 _ E _ 4 _ H _ 1 _ 4 2 _ B . 6 _ T _ _ _ _ 0 . . _ 3 _ 1 _ 4 _ _ 4 _
. _ _ _ 3 _ _
+ : + : , : : + + :
_ 3 _ 6 _ 6 _ _ 6 _ _ 0 _ 0 _ 6 _ 0 _ Y __ 0- _ - _ E - _ 0 _ - _ N _ E _ E _ E _ - _ E _ D _ 9 _ 7 _ 0 _ E _ 4 _ S I _ 1 _ 4 _ 3 _ 4 _ 2 _ N O I K_3 _ _ 1 _ 6 _ _ 2
. 4 _
_ 5 _ T + : + - ,. : : + + : C _ _ _ _ - ._ E _ 3 _ 6 _ 6 _ ._6 _ J _ 0 _ 0 _ 0 _ 6 _ 0 _ O R _ - _ - _ - _ 0 _ - _ R E _ E _ E _ E _ - _ E _ P E V_1 I L _ _ 9 _ 7 _ 4 _ B _ E _ 5 _ 3 _ 9 _ _ 4 _ 3 _ 2 S _ 3 _ 1 _ 5 _ _ 4 _ 3 O _ _ _ . 3 _ _
- D + : + : + : : + + . +
A _ _ _ _ : _ _ 6 S _ 3 _ 6 _ 7 . _ 6 _ 3 V I 8 9 SD DA _ 0 _ 0 _ E _ - _ - _ 0 . 7 _ 0 _
- . 0 _ - _ V
- M 9 AR N _ E _ E _ E _ - . E _ I E 1 RL O _ 9 _ 7 . 0 _ E . 9 _
L LL B _ 1 _ 4 . 0 _ 8 _ 3 _ B L LI _ . _ _ _ 4 _ _ A A IM _ 3 _ 1 _ 9 _ _ 1 . T U M _ . . _ 7 _ . NF 3 + : + : + : : + + : + NE 20 _ _ _ _ : _ _ AE 0 - T_3 _ 6 _ 6 _ _ 6 _ B E C _ 0 _ 0 _ 0 _ 6 _ 0 _ N E7 A _ - _ - _ - _ 0 _ - _ U O2 H3 94
- 7. 5 R _
T_1 E _ 9 _ 7 _ E _ 4 _ E . - _ E _ 3 _ E _ 8 _ 4 _ 5 _ 0 _ M L E 1 I _ _ _ _ 6 _ _ A .S = G.3 _ _ 1 _ 4 _ _ 3 _ C = . . . 2 _ _ OS E +2 + : + : : + + - + TNE R L ES SO _ 3 _ 6 _ 6 _ _ 6 _ M O I _ 0 _ 0 _ 0 _ 6 _ 0 _ FNM O D_ D _ - _ - _ O I5 R_I R Y_E D O _ 9 _ 7 _ _ E _
- _ 0 _ - _
E _ - _ E _ 3 _ E _ 5 _ T7 _ 1 _ 4 . 8 _ 0 _ 7 _ A I A_ B. _ _ . _ 0 _ _ C4 O LT A_M A TM A T_3 .
+ : +
_ 1 .
+ : :
4 _
+
. 3 _
_ 3 _
+ : +
A EA _ _ _ _ : _ . BG _ _ _ _ _ _ L A I L_L_ AA Y ._ A.E W D _ N _ T_N L U _ E _ _ D __ L_ I M C UU 3 . M _ _ E _ _ E NN 2r . U. _ U O _. AA T D_ T _ C H__ P NN . . _ R _ E _ _ S AA ?v 'E . G _ M _ _ _
l I m 6 , : + e + _.2 _ 6 _ 0 _ 0 N _ - _ - _ I _ E _ E _ K _ 7 _ 5 _ S _ 2 _ 6 6 _ 8 0 _ 6 . 0 _
- _ 0 _ - _
E _ - _ E _ 6 _ E _ 9 _ _ 8 _
+ .+
_ 6 _ 3 _ _ . _ _ 2 _ _ _ 2 9 _ 8 _ _ 6 _
. - . 5 . .
+ : + : + : - + + : +
_ 3 _ 6 6 _ _ 6 _ _ 0 _ 0 ._ 0 _ 6 _ 0 G _ - - _ - _ 0 _ - N _ _. E _ E _ - _ E 1 _ 5 _ 6 _ E _ 9 ._ U L __ E 4 _ 9 _ 8 _ 8 _ 3 _ MT _ _ . _ 2 _ _ 7 7 _ 8 _ _ 6 _
. _ 5 _ .
+ : + + - - + + : +
D _ 3 _ 6 _ 3 3 _ I _ 0 - 0 _ 0 _ 3 _.0 _ O _ - - _ - _ 0 _ - _ R . E _. E _ E _ - _ E Y . 2 _ 5 _ 8 _ E _ 9 H _ 0 _ 9 _ 2 . 5 _ 4 _ _ 7 _ 7 _- 2 _- 6 _ 2 _ _ . _ _ 1 . .
+ : + : + - : + + : +
._3 _ 6 _ 5 . _ 5 _
M Y_0 E N _ E _ E _ _ 0 _ 0 E 5 _ 0 _ 0 _ - _
- _ E _
D _ 2 _ 5 _ 7 ._E . 7 _ S I . 0 _ 9 _ 0 _ 0 . 8 - N K . _ _ _ 5 _ - O _ 7 _ 7 _ 2 _ _ 1 - M I T +
. + : + : : +
. _ 1 .
+ : +
C _ _ . _ : _ _ E _ 3 _ 6 _ 5 _ _ 5 _ J _ 0 _ 0 _ 0 _ 5 _ 0 _ O R _ - _ - _ - _ 0 _ - _ m R P E E _ V_0 I _ E __ 5E _ 2 _ 9 _ _ E _ - _ E _ 8 _ E _ 9 - 5 9 _ 3 _ L _ 0 _ _ 3 S _ 7 _ 7 _ 1 _ . 1 _ 3 O . . . . aA
. 1 -
- D + : + : + : - + + : +
_ _ _ _ : _ _ 7 S _ 3 _ 6 _ 6 _ _ 6 _ 3 V 8 SD _ 0 _ 0 _ 0 . 6 _ 0 _ - I 9 DA E _ - _ - _ - _ 0 _ - _ V 9 AR _ E _ E _ - _ E _ I E RL N __ 2E _ 5 _ eB 1 O 4 _ E _ 6 _ L LL B _ 0 _ 9 _ 8 _ 2 _ 4 _ L LI _ . . _ . _ 0 _ _ A A IM _ 7 . 7 _ 4 _ . 7 _ T U M . _ _ _ 4 . _ NF 2 + : + : + : : + + : + NE 20 _ . _ _ - . AE 0 - T _ 3 _ 6 _ 5 _ . 6 e N U O3 B E0 22 9 E C A R 0 E _ 0 _ _ E . _ 5 _ 0 _ 6 _ 0 _ E 7
- _ 0 _ - _
- . E _
._E _ 6 _
H3E 1 T- __ 02 . 9 _ 0 _ 9 _ 0 _ L S 3 I _ . . . _ _ 3 _ _ A .S = G7 _ 7 . 1 _ - 7 _ e C TNE R OS
=
ES E +: + _.5
+ : : +
_ 6 -
+ : +
L SO 3 _ 5 . _ 5 - O I OD _ 0 _ 0 _ 0 6 _ 0 _ _.0 i FNM Y _ - _ - _ - . - _ O D_R_ D _ E _ E _ E _ - . E _ I2 RI O _ 2 _ 5 _ 8 _ E 7 _ T8 _ 0 _ 9 . 2 _ 0 _.0 _ A IAA_ B. _ . _ _ . 3 _ _ n C1 O LT A_M TM A T ._ 7
+: +
_ 7 _
+ : : +
1 .
. 8 _
_ 1 _
+ : +
A EA _ _ . _ - _ BG _ _ _ _ _ L A I L_L_ AA Y_ A __ W _ D _ TN L
. D_ L R C UU H _E ._ U N __ TDU_E _.
. E I _
E NN _M _ H_ P S NN AA T.U __RG __ AA_T_C_ A.PL P _ O _ E M R 1 l
E
, : , : : : , , : +
_ _ 4_ _ : _ _ _ 4 _ 7 _ 7 _ _ 7 _ I 0 _ 0
, 0 _ 7 _ 0 _
- _ 0 _ - _
E _ - _ E E N __ 3E K __ 1 _E 8 _ E _ 4 S _ 8 _ 6 _ 2 _ 6 _ 6 . _ _ . . 3 _ . _ 5 _ 4 2 . _ 1 _
+ : ,
- + : : ,
. 1 _
, : +
E 4 _ 7 _ 7 _ _ 7 _ _ 0 _ 0 _ 7 _ 0 _ G - _ - _ - _ 0 _ - _ N _.E 0_ E _ U _ 1 _ 0 _ E _ - _ E _ 8 _ E _ 4 _ E L . 9 _ 8 _ 2 _ 6 _ 6 _ _ _ _ 3 _ . 1 _ 3 _ 2 _ _ 1 .
. _ _ _ 1 . _
+ : , : + : 2 + + : +
_ 4 _.7 _ D_0 I O _ - _ - _ _ 0 _ 4 _ 0 _ 5
- _ 0 _ - _
4 _. 0 ._ R _ E _ E _ E _ - _ E _ Y _ 0 _ 0 _ 9 _ E _ 9 _ H . _ 8 0 _ 8 _ 1 _ T8 1 _ 3 _ _ 1 _ _ 8 _ . _ _ 1 _ E
. _ _ _ 7 _ .
- + : + : : , + : +
4_ . _ - _ _ 4 7 _ 7 _ _ 7 Y _ 0 _ 0 _ 0 _ 7 _ 0 E _ - _ - _ - _ 0 _ - ._ _ N _ E _ E _ E _ - _ E _ D _ 0 _ 0 _ 6 _ E _ 4 _ S I _ 8 _ 8 _ 9 _ 0 _ 5 _ N K _ _ . . 0 . _ O _ 1 . 3 . 7 . 7 _ I _ _ _ 6 _. _ T + : ,. : + : - + + : + C _ _ _ _ : _ _ E _ 4 _ 7 _ 7 _ _ 7 _ J _ 0 _ 0 _ 0 _ 7 . 0 _ O R _ - _ - _ - _ 0 _ - _ R E _ E _ E _ E _ - _ E _ P E V_0 I L_8 _ 0 _ _ 8 _ 9 _ E 5 _ 5
. _ 0 .
3 _ 2 _ E-4 S . 1 _ 3 _ 5 _ . 5 _ 3 O _ . _ _ 4 _ _ _ - D + : + .
. : : + + : ,
_ A _ _ . _ : _ 8 S _ 4 _ 7 7 _ 7 _ 3 V 8 SD _ 0 _ 0 0 _ 7 _ 0 _ - I 9 DA E _ - _ - _ - _ 0 _ - _ V 9 AR N _ E _ E _ E _ - . E _ I E 1 RL O_0 _ 0 _ 2 . E _ 7 _ L LL B _ 8 _ 8 _ 3 _ 2 _ 5 _ B L LI _ _ _ _ 9 . _ A A IM _ 1 _ 3 _ 2 _ . _ 3 _ T U M . _ . . 1 _ _ NF 4 + : + : + : : + + : + _ NE 30 _ _ _ . : _ _ AE T _ 4 _ 7 _ 0 - 7 . _ 7 _ - B E C _ 0 _ 0 _ 0 _ 7 _ 0 _ N E9 _ - _ - _ U 10 A_E R _ E _
- _ 0 _ - _
E . - _ E _ O4 H3 L
- 0. 3 1
T_8 1 _ _ 0 _ 0 . 8 . 5 . E _ 6 _ 1 _ 9 _ 9 _
. _ 8 _ . _
A C .S G_1
= _ _ 3 3 _ _ 1 _
= _ ._ . 1 . _
OS E + : + : + + + : + TNE R L ES SO _ 4 _ 7 _ 7 _ _ 7 _ _ E O I _ 0 _ 0 _ 0 _ 7 _ 0 _ FNM D O D_ Y _ - . - _ - _ 0 _ - _ O R D _ E . E _ E _ - _ E _ I0 R_I O _ 0 _ 0 _ 8 _ E _ 8 _ _ T0 _ 8 _ 8 _ 1 . 0 _ 6 _ A C2 IAA_A B. _ .
. 3 _
4 _
. 8 _
_ 3 _ O A_M T ._ 1 . _ _ IT TM + - + : + : : + + : + A EA _ _ . _ : _ _ G _ _ _ _ . _ _ L A I B_L_ L AA Y_ A_ W _ D _ _ N _ T.N L U.E _
. . D _
. L _
I . C UU M _ U _ TD _ H _ E NN H __U E T_L _ O _ AA ET_C _ P NN _ R . E S AA A_P P _ G _ M
~_
) !l1 1 l1l!lll lll1lll llI,1lllll1 1lll I1
+ : , : + : : + + - +
_ 4 _ 8 _ 8 _ . 8 _ _ 0 _ 0 _ 0 _ 8 _ 0 _ N _ - _ - _ - _ 0 _ - _ I _ E _ E _ E _ - _ E _ K _ 3 _ 5 _ 5 _ E _ 7 _ S _ 7 _ 5 _ 7 _ 2 _ 8 . _ _ _ _ 0 _ _ _ 1 _ 7 _ 6 _ _ 4 _ _ . _ _ 4 _ _
+ : + : + : - + + - +
_ 5 _ 8 _- 8 _ _ 8 _ _ _ 0 _ 0 _ 8 . 0
- _ - _ - _ 0 _ - _-
G N __ E 0_ E _ E _ - _ E _ U4 _ 2 _ 5 _ E _ 7 _ L 6 _ 2 _ 7 _ 2 _ 8 _
. _ _ _ 0 _ _
5 _ 6 _ 6 _ _ 4 - _. . . . 4 . -
+ : + : + : + + : +
D _ 5 _.8 _ 5 . 5 _ I _ 0 _ 0 _ 0 _.5 0 _ O _ - _ - _ - _ 0 _- - _ R _ E _ E _ E _ - _ E _ Y _ 5 _ 2 _ 8 _ E _ 5 _ H _ _ 2 _ 7 _ 9 _ 9 - _ _ 2 . T __5 3_ 6 _ 1 _ 1 - _ . . . 1 _. -
+ : + + : : + + - +
_ 5 _.8 . 7 _ Y _ 0 _ 0 0 . 7 0 E _ - _ - _. - . 0 _- - _. N _ E _ E _ E _ - E _ 3 D _ I _ 5 _ 2 _ 0 _ E _- 5 _ 3 _ 2 _ 6 _ 6 _ 4 _ N K _ _ _ _ 1 _ _ O _ 5 _ 6 1 _ . 1 - I _ _ _. _ 1 - T + : + : + : : + + - + C _ _ _ _ : . _ E . 5 _ 8 _ 7 _ . 7 . J . 0 _ 0 _ 0 _ 8 _ 0 - O R - _ - - - _ 0 _ - R E _. E _ E _ E _ - . E _- P V _ 5 _ 2 . 2 _ E . 7 .
~ I _ 3 _ 2 _ 3 _ 0 - ~
E L _ _ 2 _. _ 4 _ - 5 S . 5 _ 6 _ 1 _ _ 1 - 3 O - . . - 8 . -
- D + - + : : : + + : +
mA V 8 SD DA S _.0 _ 0 5 _ 8 . 4_ 8 _ 0 - 8 _ 0 _ _ 8 - _ 9 3 I 9 E _ - _ - - - 0 _ - V 9 AR _ E _ E - - _ E I E 1 RL N __ 5E _ 2 _ O 9 . E _ 4 L LL B _ 3 _ 2 _ 7 _ 5 - 8 _- mA B T L A U NF LI IM M 5 _ 5 - 6 _
+: + . ,
- : +
_ 1 _ . - 3 _ . - 5 _ _ 3 .
+ : +
NE 40 _ _ _ _ AE 0 - _ 8 _ 8 _- - __ 8 E T __ 05 _ 0 _ C _- m N U O5 B E5 91 A _ - _ - _ R _ E . E _ T_5 2 _ 0 _ 8 -
- _ 0 _
E _ - _ E - 8 _ E 0 9 H3W 9. 9 - _ 3 _.2 _ 1 _ 9 _-3 _- L S 2 I _ _ _ . _ 8 _ . _ A C .S
= G_5 _ 6 _ 8 _ _ 5 _
m TNE R OS L
=
ES SO E
+: +
_ 5 . 8 .
+ : : +
8 _ _ 4 _
+ : +
_ 8 _ r O OD FNM O I D_R_ Y_0 _ D _ E _ E _. _ 0 . 0 _ 8 _ 0 _
- . 0 _ - _
E . - _ E _ I2 RI O _ 5 _ 2 _ 6 _ E _ 1 _ T0 - 2 _ 9 _
\
A C2 IAA_ B. _3 _ 8 _ 3 _ 2 _ T5 . _ 6 _ 9 _ _ 8 O A_A4 _ _ . 6 . _ Tf9 i LT +: + : + : : + + : + A EA _ _ _ - : _ _ BG _ . _ - _ _ L _ D_ t
.A L_L_ Y_ _ _
L A_E T _. _ EN _.I L __ I AA W . D N __ U 1 C UU H _M . _ TD _ E _ H _ E NN _O P S NN AA T_U_RU_AA.T_C L A ._ P _ G.M P _ E
, . 'I !!
, : + : , : : , + : +
_ 1 _ 5 _ 5 _ _ 5 _ _ 0 _ 0 _ 0 _ 5 _ 0 _ N _ - _ - _ - _ 0 _ - _ I _ E _ E . E _ - _ E _ K _ 9 _ 2 . 4 _ E _ 5 _ S _ 1 5 6 _ 7 _ 3 _ 7 _ _ s _ 1 _ 2 _ 4 _
. 3 _ u
+ -
- + : : +
_ 2 .
+ : +
a
. 2 _ 5 _ 5 _ _ 5 _
. 0 _ 0 _ 0 _ 5 _ 0 _
G _ - _ - _ - _ 0 _ - _ N _ E _ E _ E _ - _ E _ U _ 8 _ 7 _ 4 _ E _ 5 _ L _ 8 _ 0 _ 6 _ 7 _ 3 _ _ . _ _ _ 7 _ _ _ 3 _ 2 _ 4 _ _ 3 _ _ . 2 _ .
+ : ,. : ,. : : + + : +
D _ 2 _ 5 _ 3 _ _ 3 _ I _ 0 _ 0 _ 0 _ 3 _ 0 _ O _ - _ - _ - _ 0 _ - _ R _ E _ E . E _ - _ E _ x _ 8 _ 7 . 7 _ E _ 1 _ i _ 6 _ 0 r _ 9 . 2 _ 5 _ T _ _ _ . 3 _ _ _ 3 _ 2 _ 5 _ . 6 _
. _ _ . 4 . _
+ : + . + : : + + : +
_ 2 _ 5 _ 5 _ _ 5 _ - Y _ 0 _ 0 _ 0 _ 5 _ 0 _ E _ - _ - . - _ 0 _ - _ N _ E _ E . E _ - _ E _ D _ 8 . 7 . 4 _ E _ 6 _ S I _ 6 . 0 _ 7 _ 9 _ 5 _ N K _ . _ . 2 _ _ O _ 3 _ 2 _ 7 . _ 6 _ I . _ . _ 5 _ _ T + : + : 4 : - + + - + C . _ _ : _ . E _ 2 _ 5 _ 5 _ _ 5 _ J _ 0 _ 0 _ 0 _ 5 _ 0 _ O R _ - _ - _ - _ 0 _ - _ R E _ E _ E _ E _ - _ E _ P V _ 8 _ 7 _ 5 _ E _ 1 _ I _ 6 _ 0 _ 4 . 3 _ 3 _ E L _ _ _ . 2 _ . 6 S _ 3 _ 2 _ 6 . _ 5 3 O _ _ . _ 4 .
- D + : + : + : : + + - +
A _ _ _ _ . _ . 0
- , S _ 2 _ 5 _ 5 _ _ 5 _ 4 V 8 SD _ 0 _ 0 _ 0 _ 5 _ 0 _ -
I 9 DA E _ - _ - _ - _ 0 _ - _ V 9 AR N _ E _ E . E _ - _ E _ I E 1 RL O _ 8 _ 7 . 6 _ E _ 5 _ L LL B _ 6 _ 0 _ 2 _ 5 _ 9 _ B L LI _ _ _ _ 0 _ _ A A IM _ 3 . 2 . 1 _ _ 1 _ T U M . . - . 1 . _ NP 2 + : + : + : : + + : + NE 10 _ . _ _ : _ _ AE 0 - T _ 2 5 _ 5 _ _ 5 _ B E C _ 0 0 _ 0 _ 5 _ 0 . N E9 A _ - . - _ - _ 0 _ - . U 52 R _ E . E _ E _ - _ E _ O6 T _ 8 . 7 _ 2 _ E _ 2 _ H3 L A C W
.S
- 0. 6 2
=
=
- _ 6 . 0 _
I _ G_3 . 2 . 1 ._ 0 _ 6 _ 5 _ . _ 3 _
. 3 _
5 _ s TNE OS ES E + : + : + : : +
+ : +
m u R L SO _ 2 _ 5 _ 5 . _ 5 _ O FNM O I OD D_R_ _ 0 _ 0 _ Y _ - _ - _ D _ E E _ 0
- ._0 5 _ 0 _
E _ - _ E _ I5 RI O _ 8 7 _ 8 _ E 6 _ T8 _ 6 _ 0 _ 6 _ 5 ._4 _ A C0 IAA_A B. _ _ _ _ 5 _ _ T3 - _ 2 . _ 5 _ 4 _ O A_M _ . 3 _ LT TM + : + : + : . + + - + A EA _ _ _ _ : _ _ m L A B_G_ LL Y _ A_ _ T_ _ D _ m I I C AA UU W _ E _ N _ H _ M _ U _ _ D _ U_N_L L _ TD _ E _ H _ E _ I _ E NN T_U _ O _ AA _ T _ C _ P NN _ L _ R _ E S AA A_P P . G _ M lo
j ,lllll1 i
]1 I ill1)11Il4l I.!l llll l
]
, : + : , : : + + - +
_ 3 _ 6 _ 6 _ _ 6 _ _ 0 _ 0 _ 0 - 6 _ 0 _ N - _ - _ - _ 0 _ - . I E _ E _ E _ - _ E _ _ 2 _ 2 _ E _ 5 _ K S _. 92 _ 4 _ 1 _ 6 _ 2 _ _ _ _ . 8 _ _ _ 7 _ 1 _ 3 _ _ 2 _
. - . _ 1 _ .
+ : + - + - + + : +
_ 3 _ 6 _ 6 _ _ 6 _ _ 0 _ 0 _ 0 _ 6 _ 0 . G _ - _ - _ - - 0 _ - . N_E . E _ E _ - _ E _ _ 7 _ 2 - E _ 5 _ U __ 58 _ 1 _ L 1 . 6 _ 2 _ _ _ . - . _ 8 _ _ 2 _ 1 - 3 _ . _ 2 _ _. . - _ 1 - _
+ : + : + : : + + : +
D _ 3 _ 6 4 _ _ 4 _ I _ 0 _ 0 0 _ 4 _ 0 _ O _ - _ - . - _ 0 _ - _ R _ E _ E _ E _ - _ E - Y _ 5 _ 7 _ 7 _ E _ 8 - _ 1 _ 3 _ 4 _ 6 - H __ 4 T_2 _ .
. 1 _
3 _ _ 4 _ _ 2 -
- 3 .
+ : + - + : - + + - +
_ 3 _ 6 - 6 _ . 6 . Y - 0 _ 0 _ 0 _ 6 _ 0 _ E _ - _ - . - _ 0 _ - _ S N_5 D I _ _ E _ E _ 4 _ 1 _ _ 7 _ E _ - _ E - 7 _ E _ 7 - 8 _ 9 _ 0 - N K _ _ _ _ 2 _ - O _ 2 _ 1 _ 4 _ _ 4 - I . _ . . 3 _ - T + + - + : : + + - +
- C _ _ _ . : _ .
E _ 3 _ 6 _ 6 . . 5 _ r J _ 0 _ 0 _ 0 . 6 . 0 _ u s O R P R _ - _ - _ E _ E _ E _ V _ 5 _ 7 _
- _ 0 _ - .
E _ - _ E . 4 _ E _ 6 . I _ 4 _ 1 _ 1 . 9 _ 3 _ E L _ _ _ . . 6 _ _ 7 S 2 _ 1 _ 4 _ _ 3 _ s u 3 O D +
+ : +
* +
_ 2 -
+ : +
s A _ _ _ : _ _ 1 S _.3 _ 6 _ 7 _ . 6 _ 4 V 8 SD _ 0 . 0 _ 0 _ 7 _ 0 - - I 9 DA E _ - _ - _ - _ 0 _ - _ V 9 AR N . E _ E _ E _ - _ E _ a m E L 1 RL LL B O . 5 _ 7 - _ 4 _ 1 _ 3 . E _ 0 _ 1 _ 3 _ 1 _ I u B A L A LI IM
- 2 _ 1 _
7 _ _ 9 _ _ 1 _ T U M - _ _ _ 5 . _ NP 3 +: + : + : - + + : + s NE 20 - . . _ - _ _ AE 0 - T _ 3 _ 6 _ 6 _ u B E C _ 0 _ 0 _ 0 . 6 _ 0 . _ 6 . a N U E9 71 A_E R _ E _
- . 0 _ - -
E _ - _ E - O7 H3W 3. 4 T_5 4 _ 7 _ _ 1 _ 9 _ E _ 5 _ 3 - 2 _ 3 _ m m L A S W 1
=
I _ G . 2 _ 1 _ 3 _
. 0 _
_ 2 _ C a TNE OS
. =
ES E
+: + : + : : +
_ 2 .
+ : +
R L SO _ 3 _ 6 - 6 _ _ 6 _ O I _ 0 _ 0 _ 0 _ 6 _ 0 _ e FNM O O D_ D R Y_E D _ E _
- _ 0 _ - _
E _ - _ E _ m i I5 T0 R_I O _5 _ 7 _ 1 _ 1 _ E _ B _ 7 . 1 _ 8 _ A AI A_ B. _. 4 - _ _ 3 _ _ C3 T_2- _ 1 _ 3 _ _ 2 . O A_MA - _ - 2 _ _ LT TM +- + : + : : + + : + e A EA BG L Y _ _ _ T_ _ _ D_ wS A L_L_ I C AA UU A W __ E _ D H _M _ N __ L _ _ T)U ._ E _ H _ N_L E I _ E NN T _U _ O P NN AA A P __ PL _ _ U_AM_T_C R _ E G _ M o 4
M
+: +: +: - + , : +
2 _ 6 _ 6 _ _ 6 _ 0 . 0 _ 0 _ 6 _ 0 _ N . - . - _ - _ 0 _ - _ I . . E _ E _ - _ E _ _E K_E S 1 . 6 _ 5 . 7 _ 1 9 . 2
. _ 5
_ 6 _ 2 _ _ 1 _.1 _ 5 _ . 4 _
. _ _ . 3 . _
+: +: ,: : + + : +
_ 6 _ _30- ___06- _._ _ 6 _ 0 _ 6 _ 0 _
- _ 0 _ - _
G N ._ E . E _ E . - _ E _ U _ 4 . 5 _ 1 . E _ 6 _ L _ 9 . 4 _ 9 . 2 _ 2 _
. _ . 5 _ _
._4 . 1 _ 5 . _ 4 _
. . . . 3 _ _
+: +: +: : + + : +
D_3 I _ _ 6 . 0 _ 0 . O _ - _ - _ 4 _ 0 _ 4 _ 0 _
- _ 0 _ - _
_ 4 _ R _ E _ E _ E - . E _ Y _ 8 _ 5 _ 0 ._ E . 7 . H _ 6 _ 4 . 2 _ 4 . 5 . T _ _ . _ 0 . _ 4 _ 1 . 4 _ . 4 _ _ _ _ 3 . .
+: +: +: : + + : +
_ 3 _ 6 _ 6 6 . Y _ 0 0 . 0 . 0 . E _ - _0 _ E _ E
- - 0
- ._E _
N D __ 8E _ 5 _ 7 6 _ 1 _
. 4 0 _- 5 S
N I _ K _ 6 8 _ _92 _ _ 6 . O . 4 . 1 _ I . _ _ _ 5 _ . T +: +: + : - + + : + C _ _ . _ - _ _ E _ 3 _ 6 . 6 _ _ 6 _ J _ 0 _ 0 _ 0 _ 6 _ 0 _ O R _ - _ - _ - _ 0 _ - _ R E _ E _ E _ E _ - _ E _ P V . 8 _ 5 _ 7 _ E _ 3 _ I _ 6 _ 4 _ 1 _ 5 _ 6 _ E L _ _ _ . 5 _ _ 8 S _ 4 . 1 _ 7 . _ 5 _ 3 O . . _ _ 4 . -
- D +: +: +- : + + : +
. : _ . 2 A S 3 ._6 _
7 _ 6 . 4 V 8 SD _.0 . 0 _ 0 ._ 7 _ 0 _ - I 9 DA E _ - . - _ - _ 0 _ - _ V B _ - _ E _ I 9 AR N _ E _ E _ E 1 RL O _ 8 _ 5 _ 4 _ E _ 6 _ 3 L LL B _ 6 _ 4 _ 8 . 5 _ _ B L LI _ _ _ . _ 3 . _ A A IM _ 4 . 1 . 8 _ . 1 _ T U M - _ . _ NF 3 +: + .+ : : + + : + NE 20 _ . . _ : _ _ AE 0 - T _ 3 _ 6 _ 6 _ _ 6 _ B E C _ _ 0 _ 0 _ 6 _ 0 _ N U E1 10 A_0-R _ E _ E _ _ - _ - _ 0 _ - . E . - _ E . O8 8 _ 5 _ 4 E _ 9 H3 6. 8 T- ._ 6 _ 4 _ 2 ._ 2 . 3 _. L 2 I . _ _ _ 7 . . A W = G4 _ 1 __ 6 _ 4 . C . = . _ 3 ._ _ OS E +: +: + : - + + : + TNE ES _ _ _ _ : - _ P L SO . 3 _ 6 _ 6 _ - 6 _ O I OD . 0 _ 0 _ 0 . 6 - 0 _ FNM Y . - . - _ E _ E
- 0
._ E _
O D_R_ D _ E - RI O _ 8 ._5 _ 3 _ E _ 4 _ I0 T3 A IAA_ B. 6 _ 4 _ 6 _ 7 _ _ 0 . 0 _ M C3 A T_4 _ 1 _ 6 . . 5 _ O A_E _ _ _ . 4 _
+ .+
LT T! +: +: + : : + A EA _ . _ _ : L BG Y . T_N _ _ D _ M A I C L_L_ AA UU AE W H . M
. ._ D _
_ N _ L U . E _ I _ _ U _ TD . E . H _ _ L _ E NN _ O _ AA . T . C _ P S NN AA T_U A_P P L _ R
. G _E M
M i
) . llil{lIllll1il lil1i iiII1' I ! lll
\IIll1Illll1 1l
+ - , : + : : + : +
_ . _ 4_ _ _ 2 _ 6 5 _ _ 5 _ _ 0 _ 0 . 0 _ 5 _ 0 _ N . - _ - . - _ 0 . - _ I E _ E _ E _ - . E _ K 1 _ 5 _ 7 _ E . 8 _ S 4 _ 9 _ 7 _ 6 _ 2 . _ _ _ 0 _ . _ 4 _ 3 _ 1 _ _ 1 . _ _ _ . 1 _ .
+ : + : + : - + + : +
2 _ 6 _ 5 _ _ 5 _ 0 _ 0 _ 0 _ 5 . 0 _ G . - _ - _ - _ 0 . - _ N _ E _ E _ E _ - _ E _ _ 6 _ 7 _ E _ 8 _ U __ 3 L_4 _ 1 _ 3 _ 2 _ 7 1 _ _ 6 . 0 _ 2 _ 1 -
- _ _ . 1 _ -
+ : + - + : : + + : +
_ 6 _ 4 _. . 3 _ D I __ 02 _ 0 _ 0 _ 4 . 0 _ O _ - _ - _ - 0 . - _ R _ E _ E _ E - _ E _ Y _ 6 _ 6 _ 2 . E _ 3 _ H _ _ 2 _ 5 . 7 _ 0 _ _ _ . 8 _ T __1 3_ 3 _ 9 _ 1 _ _ _ _ _.6 _ -
+ : + : + : : + + - +
_ 2 _ 6 _ 5 _ 5 _ Y _ 0 _ 0 . 0 5 _ 0 _ E _ - _ - . - _ 0 _ - _ N _ E _ E _ E _ - _ E _ D _ 6 _ 6 _ 6 8 _ 9 _ S I _ 3 _ 2 _ 2 5 _ 7 _ N K - _ _ _ 4 _ _ O - 1 _ 3 _ 2 _ _ 1 _ I - . _ _ 1 _ . T + : + : + : : + + : +
- C _ _ _ _ : _ _ - E _ _ 6 _ 5 _ _ 5 _
J 0 _ 0 _ 0 _ 5 _ 0 _ g O R P R ___. E E _ E2_
- _ - _ - _ 0 _ - _
E _ - _ E _ E V_3 I L _ 6 _ 6 _ 2 _ 0 6 _ E _ 9 . _ 9 _ _ 2 _ 5 9 S _ 1 _ 3 . _ 1 _ 2 gA 3 O . . _ 1 _ .
- D + : + : + : : + + : +
_ _ _ : _ _ 3 S _ 2 _ 6 _ 6 ._ _ 6 _ 4 V 8 SD _ 0 _ C _ 0 _ 6 _ 0 . - I 9 DA E _ - _ - _ - _ 0 _ - _ V AR 9 _ E _ E _ - _ E _ I N O __ 6E _ 6 _ gB E L A T 1 L A U RL LL LI IM M B _ 3 _ 2 _ 1 _ 3 . 9 _ E _ 7 _ 9 _ 6 _ 1 _
. 1 .
6 _ _ 3 0 NF 2 +: + : + : : + + - + NE 20 . _ . _ : _ _ AE 0 - T . 2 . 6 5 _ . 5 _ g N U B E3 E C _ 0 . 0 AE _ - _ - _ 0 _ 5 . 0 _
- _ 0 - _
73 R _ E _ E _ - _. E _ O9 _ 6 _ 5 _ E _ 1 _ H3W 6. 2 T- _. 6 _ 0 _ L N 7 I _3 _ _ 2 _ 8 _ 1 . 3 _ A . W G1 - _ 3 _ 1 _ . . 1 _ g C OS
=
E
=
+: + : + : : +
. - . 1 -
+ : +
TNE ES _ _ _ _ - _ _ R L SO _ 2 _ 6 . 5 _ _ 5 _ O I _ 0 _ 0 . 0 _ 5 0 _ FNM O D_ D Y _ - _ - _ - _ 0 - . O R D _ _ E _ E . -: _ E _ R_I _E I4 T7 A I A_ A O_3 B. _ 6 _ _ 2 6 _ 4 _ ' _ 5 _ 9 _ 8 _ _ 1 _ 4 _ A C2 O LT A_M TM T_1 _
+: +
_ 3 _
- +
1 _
- : +
_ 1 .
. _ 1 .
+ :
+
A EA _ _ . . : _ _ BG _ _ _ _ _ _ L Y_ . A I L_L_ AA A_ W _E _ D _ _ N _ T_N L
. D_
I _ _ U _ TDU _ EE _.H L_ C UU E NN H __ M P S NN AA T_L A_P P U _ O _ _ R _ E _ G _ M A A __ T _ C i ll.
a
+ : + : , : : , + . +
_ _ _ . . _ #_ 7 _ _ 4 _ 7 _ 7 _ _ 7 _ 0 _ _ 0 _ 0 _ 0 _ 7 _ 0 _ - _ N _ - _ - _ - _ 0 _ - _ E _ I _ E _ E _ E _ - _ E _ 1 _ K _ 7 _ 8 _ 8 _ E _ 9 _ 5 _ S . 2 _ 6 _ 0 _ 1 _ 2 _ _
- _ _ _ 7 _ _ 6 _
- 2 _ 1 _ 2 _ _ 4 _ _
. _ . . 2 _ _ : .
+ : + : + : : + + : + +
_ _ _ _ : _ . 7 _ _ 5 _ 7 _ 7 _ _ 7 . 0 _ _ 0 _ 0 _ 0 _ 7 _ 0 . - _ G _ - _ - - _ 0 . - _ E _ N _ _ E E _ - . E _ 1 _ U_E L _ 4 _ 3 1 _ 8 _ 8 _ E 0 . 1 ._ 9 _ 5 _ _ 7 _ 1 _ 2 7 _ 2 .. 6 _ _ 4 .
. . _ . 2 _ _ : _
+ : + : + : : + + : + +
D _ 5 _ 7 _ 3 _ _ 3 _ 0 _
. 3 _ M I _ 0 _ 0 _ 0 _ 3 . 0 _ - _
O _ - . - _ - _ 0 . - _ E _ R _ E . E _ E _ - _ E _ 6 _ Y _ 2 _ 8 _ 9 . E 0 _ 2 _
._ 4 T_0 H _
_ 7 _ 1 _ 3 _ 0 1 _
. 2
_ 7 _
. 3 _
_ 8 .
. _ _ _ 1 . _ :
+ : + : + : : + + : + +
_ _ _ _ : _ _ 5 . _ 5 _ 7 _ 6 _ _ 5 _ 0 _ Y_0 E N E ._E _
. 0 _
0 _ 5 _ 0 _ - _
- _ 0 _ - _ E _
E _ - _ E _ 0 _ D 2 _ 8 _ 0 _ E . 3 _ 0 _ S I . 0 _ 3 _ 9 _ 4 . 7 _ _ N K _ _ _ . 0 _ _ 3 _ O _ 7 _ 1 _ 5 . _ 1 _ I T +
+ : +
- : +
_ 1 _
+ : +
+ M C _ _ _ . : _ _ 5 .
E _ 5 _ 7 _ 6 _ 5 _ 0 . J 0 _ 0 _ 0 _.6 _ 0 _ - . O R ._ - _ - _ - _ 0 . - _ E . R E _ E . E _ E _ - E _ 8 _ P V_20._ I _ 8 _ 3 _ 3 . E 5 . 7 . 0 7 _ 5 _ M E L . _ _ . 1 _ _ 2 _ 0 S . 7 _ 1 . 3 . _ 1 _ _ 4 O . _ _ . 6 - . - _
- D +: + : + - : + + : + +
A - . . . . _ 5 _ 4 S - 5 7 _ 6 _ _ 5 _ 0 _ 4 V 8 SD _ 0 _ 0 _ 0 _ 6 _ 0 _ - _ - I 9 DA E _ - _ - _ - _ 0 _ - _ E _ V 9 AR N _ E . E _ E _ - _ E _ 3 _ I E 1 RL O _ 2 . 8 _ 2 _ E . 2 _ 1 . L LL B _ _ 3 _ 1 . - B L LI _ 0 _. 3 _ _ 2 _. 0 . 2 - A A IM _ 7 _ 1 _ 2 _ _ 1 - T U M _ - _ - 4 . : - N 4 +: + : + : : + + : + + NW 40 _ . _ _ : . _ 6 _ AO 0 - T _ 5 _.0 _ 7 _ 6 _ . 6 _ 0 . C E C _ 0 0 _ 6 . 0 _ - . N E0 A _ - _ - _ - _ 0 . - _ E _ U 22 R _ E _ E _ E _ - . E _ 5 _ O0 H4 L
- 9. 1 3
T_0 I _ _ 2 _ 8 . _ 3 9 _ E . 5 _ 5 _ 0 _ 4 . _ 4 3 ._ 1 _ A _. 1 _ C .S = G _ 7 _ 1 1 _ _ TNE R OS L
=
ES SO E _ 5 _ 7 _
+: + : + : - +
6 . _ 1 -
+ : +
. 6 _. 0 5 .
+ m O I OD _ 0 _ 0 _ 0 6 0 _ - ._
FNM Y _ - _ - _ - 0 - _ E _ O D_R_ D _ E _ E . E . - . E _ 7 _ I6 RI O _2 _ 8 . 1 . E 7 _ 1 _ T7 _ 0 _ 3 . 1 . 4 _.2 _ _ A I A_ B. _ _ . _ 4 _ _ 1 . C2 O LT A_M A TM A T_7 _
+: + : +
_ 1 . 2 .
- : +
_ 3 _ _ 6 _
+ : +
+
A EA . . _ _ : _ . _ BG _ _ _ K _ . . T _ L Y _ _ _ _ . D _ N . A L_L_ A _ _ D _ IL I AA W _E _ N _ MU _ E LT_N __I L AF .. C UU D _ E _ HN _ E NN H T _U_M_UO ___ WA __T__C__I P NN O _ S AA A __ P P L __ G R _ C _ _ _ _
M M
- a. _
S 4 _ T N 9 _ E . U 5 L S F N D S F O A D E I R A T L R _ S A L L U C I L O I M I E F M _ M S AY I C 1 GR E 0 0 _ A P - 0 . MD S E + ON 7 E _ RU L 8 4 E O A 2 B C 6 S I 2 NA N OE H IR C TA E - U T - BD E IE Y S E RT B O S TC D O NI D D OR E 8 R CT R 9 I R S I 9 A I EE U 1 A SR Q A ON E , M A DU R 1 M T 3 A E G B R E Y Y 1 B R R M A A MB V I E C E D D N U O D N U O 5 4 V B B I E O E E ML B A T T 8 9 9 T I S T I S 1 M M U U M M M 1 Y I X A I X A R M M A U 1 N A N J U O R H O L F A M C L A T U R N O N F A M M M l lll !
+ : : + - - + : : + : + : - + : . + :
_ 1% _.5% _ 4% _ 3% _ 4% . 4% _ 1 _ _ 01 _ 01 _ 07 _ 04 _ 09 _ 08 _ 0 _ _ - _ - 0 _ - 1 _ - 3 _ - 0 _ - - _ N_E 3 I _ E . E K _ 99 _ 40 _ 10 _ 50 _ 20 _ 30 _ 3 _ _ E . _ E _ E 0 ._ E _ S _ 79 _ 4 _ 4 _ 6 _ 1 _ 7 _ 8 _ 4 _ 4 _ 8 _ 1 _ 4 _ 3 _ 4 _
+ : : + : : + : : + : : + : : + - : + : +
_ 1% _ 5% _ 4% _ 3% _ 4% _ 4% _ 1 _ _ 08 _ 03 _ 04 _ 06 _ 01 _ 08 _ 0 _ G _ - 4 _ - 0 _ - 6 _ - 2 . - 3 _ - 2 _ - _ ' N _ E _ E _ E _ E . . E _ E _ E _ U _ 87 _ 50 _ _ 10 _ 51 _ 20 _ 1 _ 3_ 0 7 _ 1 3. . L _ 29 _ 6 4 _ 6 _ _ 1 _ 3 _ 8 _ 1 _ 4 3 _ 1 _
) + : : + :: + :: + :: + :: + - : + : +
M . _ _ _ _ _ . _ E D . 1% _ 5% . 2% _ 3% _ 1% . 2% 1 _ R I _ 07 _ 01 _ 09 _ 04 _ 03 . 06 ._0 _
- O _ - 2 _ - 0 _ - 0 _ - 4 . - - 8 _ - _
N R _ E _ E _ E _ E . E 3 _. E . _ E _ O Y _ 96 . 50 _ 19 _ 31 . 48 _ 04 _ 2 _ _ 5 S H _ 12 . 6 1 _ 5 _ 65 _ 2 R E T_1 _ _ _ 3 _ 4 _ 6 _ 2
. 2
. 4 _
M SP . _ _ _ _ . - - N( + : : + : : + : : + . : + - : + : : + : + O _ _ _ _ _ . _ _ IY _ 1% . 5% _ 3% _ 3% _ 3% _ 4% 1 _ TR Y _ 03 . 03 _ 05 06 _ 04 _ 09 _ 0 . CA E _ - 9 . - 0 _ - 8 ._ - 3 _ - 4 _ - . EM _ E _ E _ E _ E _ E _ E . _ E _ JM OU N_95 D I _ 19 _ _ 50 6 _.0 50 _ 8 1 _ 81 _ 60 _ _ 6 _ 7 _ 4 . 8 _ 2 . RS P K_1 _ _
. 3
_ 1 _ 1 _ 1
. 4
_ 1 _ ES E _ _. _ _
+ : . + : - + : : + .: + : : + : - + : +
M SO _ _ _ _ . OD _ 1% _ 5% _ 4% _ 3% _ 3% _ 4% _ 1 D _ 08 _ 03 _ 08 _ 06 _ 00 _ 06 _ 0 N R _ - 4 _ - 0 _ - 7 _ - 3 _ - 0 _ - 3 _ -
,O E _ E _ E _ E . _ E _ E _ E . E _
8I V . 96 _ 50 _ _ 40 _ _71 _ 312 _ 90 3 . 3 . _2 9T I . 19 _ 6 6 6 _ _ _ 9A L _ _ _ . _ . _ 1L _ 1 _ 3 _ 9 . 1 _ 1 - 4 _-1 _ 1 U . _ _ . _ -
+ : - + : : + : : + : + - LP + : : + : : + : :
C AO _ _ _ _ _ . _ . 6
- UP _ 1% _ 5% _ 5% _ 5% _ 4% . 5% 1 . 4 V N _ 07 _ 03 _ 08 _ 01 _ 07 _ 04 ._0 . -
I ND E _ - 2 . - 0 . - 0 _ - 0 _ - 5 _ - 0 _ - . V AE N _ E . E . E _ E _ E _ E _ E _ I E T O _ 99 _ 50 40 . 20 _ 90 _ 50 _ 0 _ L NA B _ 19 _ 6 _. 4 . 2 _ 7 . 0 _ 2 _ UR B A T OG HE _ 1
. 3
_ 9 _ 1
. 6 5
_ 1 _ M LT + : : + : : + : : + : : + : : + : - + :+ AN _ _ _ . 4% . 3% . 4% _ 4% _ 1 _ CI T _ 1% _ 5% C 04 _ 03 00 06 05 _ 02 _ 0 _ TL A - 1 _ - 0 . - 7 - 3 _. - 4 _ - 3 _ - _ RA R . E _ E E . E _ E _ E _ E _ OU T _ 97 _ 50 ._90 . 61 _ 40 _ 80 _ 2 . FN - _ 19 _ 6 . 5 . 6 _ 5 _ 8 _ 2 N I _ _ _
._1.
A G_1 _ 3 _ 8 _ 5 _ 3 _ 1 A + : : + : : + : : + : : + - : + : : + :+ R _ . . _ . _ _ _ A _ 1% 5% _ 4% _ 3% 4% _ 4% _ 1 _ L _03 03 _ 04 _ 06 _.01 03 _ 0 _ A Y _ - 8 . 0 _ - 7 _ - 3 _ - 7 ._ - 3 _ - _ D _ E . E _ E . E - E _ E _ E _ O _ 9C . 50 _ 101 _ 61 . 20 7_ 10 _1 3 __ B. _ 19 _ 6 _ 6 2 _ M
. 9 _ 1 _ 8 . 4 _ 1 _
T_1 _
+ :
_ 3
- + : :
+ - : + - . + : : + : : + :+
_. _ _ K _ _ _ Y _ _ _ ._ L _ _ _ _ D _ I _ L _ A.E W H . M N U _ L
. A
. T
. E
_M _ T
. A _
_ i _ T . U . O . H . G _W . A _ _
. L R . N . E _ O . E _ w_
A.P P G . I . V _ C _M _
- _
M
l I I I SECTION V I DOSE FROM LIQUID EFFLUENTS LADTAP 11 OUTPUT Technical Specification 5.9.4a January 1,1998 - December 31,1998 I I I [ [ r V-1 r
I Radioactive Effluent Releases - First, Second, Third, and Fourth Quarters 1998 LIQUID EFFLUENTS During the reporting period, a total of 3.56E-01 Curies of radioactive liquid materials less tritium, dissolved noble gases, and alpha were released to the Missouri River at an average concentration of 4.32E-10 Ci/mL. This represents 4.32E-02% of the limits specified in Appendix B to 10 CFR 20 (1.0E-06 Ci/mL for unrestricted areas), g 260 Curies of tritium were discharged at an average diluted concentration of n 2.36E-07 pCi/mL or 2.36E-02% of ECL (1.0E-03 pCi/mL). Gross alpha radioactivity released during the reporting period total 5.64E-02 Curies. Dilution water during the period amounted to 1.24E+12 liters, while radioactive liquid waste volume was 1.36E+08 litera. l I I I I V-2 I
i A. Potential Annual Doses to Individuals from Liquid Releases Total body, skin, and organ mrem for liquid releases were calculated for all significant liquid pathways using the annual configuration of the LADTAP ll program. The inputs to LADTAP ll for the annual period from January 1,1998 through l December 31,1998 were as follows: (1) All liquid effluents were as described in Section IV except for entrained l noble gases (Ar-41, Xe-131M, Xe-133M, Xe-133, Xe-135M, Xe-135, Kr-85M, Kr-87, and Kr-88) l (2) An average plant discharge rate of 679.0 cubic feet per second (CFS) was utilized for 1998. The average discharge rate during releases was 467.0 cubic feet per second (CFS). (3) Dilution factors (inverse of the mixing ratios) were computed based on I Regulatory Guide 1.113 (equation 7 in Section 2.a.1 of Appendix A) for a one dimensional transport model. I (4) A drinking water transport time of 6.6 hours to the Omaha intake and 7.0 hours to the Council Bluffs intake for the ALARA doses was used. A transport time of 0.0 was used from the plant to thc discharge site. (5) A shorewidth factor of 0.2 was used. l (6) All dose factors, transport times from receptor to individual, and usage factors are defined by Regulatory Guide 1.109 and NUREG-0172. The discharge site was chosen to present the most conservative estimate of mrem dose for an average adult, teenager, child, and infant. A conservative approach is also presented by the assumption that Omaha and Council Bluffs I receive all drinking water from the Missouri River. B. Potential Annual Doses to Population from Liquid Releases The LADTAP ll program in its annual configuration was also used to calculate to total body and organ doses for the population of 760,413 within a 50 mile radius p of the plant. The same input was used as in the individual cases with the addition L of the following: b n V-3
I (1) Dilution factors and transport times for the pathways of sport fish, commercial fish, recreation and biota were calculated based on a distance of two miles downstream as approximately the distance to the nearest recreation facility - DeSoto National Wildlife Preserve. (2) The total fish harvest for both sport and commercial purposes was calculated using an average commercial fish catch for Nebraska. I O 1 V-4
. e * . * * * * * * * * *
- e * * *
- e *
- e *
- 4 * * * . * . *
- 4 .e e t e
e
.t e
t t 4 4 _ 4
- _
6
- _
4
- 9 Y
- 9 T e 4 I I I e
. I I V e 4 I I I I I I I e
. I I T
.e e I 1
I I C A I D
. 1 I S e . 1 I I I I I A T 5 N e 4 1 I R I 8 O
- 4 1 I D 9 I
- F U 1 S
- _
O L N S *
. F R H O I
- _
F E C M
. S I
- _
. PP E E B N T M
- _
. P P S O A A O
- _
P P A D I R R C
- _
.e P F E I C B G 9 * . . PPPPPP L U O S E Y 9 * . E Q N T T R - e 9 R I - O N N O R 9 _
AAAAA L I E I T A 4 _ 4 A A M X T M A M e A A O S A C S S L - 6 A A R T V E S M U 9 4 5 AAAAA F N J E E G . .
. A L O S T E C * -
4 S L N R S S R
- V
. A E P P P A Y . e . A S S R D e . A TTTTT O R E L A : .
e A D E : S A F E , N e e a W E O C O L N U t
. N O T D I C O R t . O P A G N U T e DDDD I D O O N G F e D D T R , L I N O 9 . D D A A N 8 O S . I 4 4 D D I E O 9 I I S H E 6 . DDDDDD D L I 9 D V S T e . A C S 1 A I . A A t . R U I R D U W D e e AAAAA N V L e . A A F E A e e
A A O N R U e A A I N
. AAAAA N N e O A 4 .e I 4 e L T N e . L A U . L U O
- L L t i
- LLLLLL A L
- e
. V A e . E C e . T e 9 R .
4 O 4 F .
. 4 .e e e
e 4 * * * * * * * * * * * * . * * *
- 4 * * * * * . * *
- e + * * * .
M M 1 3 4 6 6 1 1 4 4 5 6 1 I 0 0 0 0 0 0 I 0 0 0 0 0 0 L - - - - - - L - - - - - - LEEEEEE LE EEEEE
- 6 3 6 3 1 7 - 9 9 5 4 2 0 I 9 3 1 2 1 9 I 3 1 4 2 2 4 G G 1 1 1 2 1 1 1 9 6 1 6 1 M
3 4 4 6 6 3 3 4 4 5 6 2 0 0 0 0 0 0 0 0 0 0 0 0 G - - - - - - G - - - - - - NEEEE8E U7 0 6 3 1 1 L2 2 1 2 1 3 NE EEEEE U9 0 5 4 2 0 L6 7 4 2 2 1 M 8 9 1 2 1 9 9 6 6 1 6 1 2 4 4 6 6 2 2 4 4 5 6 2 Y0 0 0 0 0 0 Y0 0 0 0 0 0 E - - - - - - E - - - - - - NEEEEEE N EEE3EE I D8 9 6 3 1 9 K 4 9 1 2 1 5 D2 0 5 4 2 6 I K 5 3 4 2 2 6 M 2 9 1 2 1 2 2 76 1 6 2 2 2 0 0
) = ) =
E R E R K O K O A T A T T 3 3 4 6 6 3 C T 3 3 4 5 6 3 C ND0 0 0 0 0 0 A NO0 0 0 0 0 0 A I I - - - - - - F I I - - - - - - F OEEEEEE OE EEEEE RR4 1 6 3 1 6 H RR9 7 5 4 2 2 H AY 5 8 1 2 1 4 EH YT3 2 1 2 1 6 T D I W AY 2 2 4 2 2 2 EH YT3 2 6 1 6 6 T D I W m R E R E E R E R P O P O H H M S M S 6 E Y E Y - R D2 3 4 6 6 2 R D2 4 4 5 6 2 V MO0 0 0 0 0 0 MO0 0 0 0 0 0 ( ( B - - - - - - B - - - - - - EEEEEE E EEEEE E_AL0 3 6 3 1 3 61 1 2 1 7 _L9 8 5 4 2 4 EA1 5 4 2 2 3 S T S TT . OO5 1 1 2 1 5 OC 3 7 6 1 6 3 DT DT )
)
R R H H ( 0 0 0 0 0 ( 0 0 0 0 0 E 0 6 0 0 0 E 0 6 0 0 0 M M 2 3 4 6 6 2 I 4 8 0 0 0 2 4 4 5 6 2 I 4 8 0 0 0 R0 0 0 0 0 0 T2 1 R 0 0 0 0 0 0 T2 1 E - - - - - - E - - - - - - VEEEEEE VE EEEE E I 6 5 5 4 2 2 I 7 1 6 3 1 0 L4 2 1 2 1 6 L6 2 4 2 2 8 7 1 1 2 1 7 7 9 6 3 6 7 N N O S O I 3 8 3 3 3 I 3 8 3 3 3 T E T U7 0 7 7 7 U7 0 7 7 7 L 3 S L 3 I I S 2 4 4 6 6 2 D 0 2 4 4 5 6 2 D 0 0 0 0 0 0 0 0 0 0 0 0 E E - - - - - - D E - - - - - - N5EEEEE NE EEEEE S O 2 7 6 3 1 5 O3 0 5 4 2 1 _ B 1 8 1 2 1 1 B3 8 4 2 2 4 O . 4 1 1 2 1 4 R 4 1 6 1 6 4 r E
) G )
R R T Y A Y
/ /
L 4 4 R 0 0 0 0 0 N 4 4 R 0 0 0 0 0 0 0 U N 0 0
- H, 1 0 2 2 2 E N - - H, 6 0 7 7 7 I E E R2 3 1 1 1 I E E R1 1 6 6 6 D K 4 4 Y 7 E K 0 0 Y 5 S 3 3 / S 5 5 /
A G T G K 1 1 K 7 7 ( ( E E G G A A S S U U E E E E GNG GNG GNG GNG _ Y NI NG NI NG Y NI NG NI NG A I LI N I LI N A I LI N I LI N W KEMI L KEMI W KE MI L K E MI HHNR MTA HNR MT H HNR MTA HNR MT TS I OI AT S I OI A TS I OI AT S I OI A AI RHWOO I RHW O AI RHWO O I RHW O P FDSSBT FDSSB P FDSSBT FDS S B
l l 2 3 4 6 6 2 0 3 0 3 I 0 0 0 0 0 0 I 0 0 0 0 L - - - - - - L + - + - LEEEEEE LE E E E
- B 5 5 0 0 3 - 0 3 0 3 I 9 4 3 6 3 1 I 0 3 0 3 G G 4 1 1 2 1 *i 0 1 0 1 3 3 4 6 6 3 0 3 0 3 0 0 0 0 0 0 0 0 0 0 G - - - - - - G + - + -
NEEEEEE NEEE E U1 8 5 0 0 3 U0 7 0 7 L6 2 3 6 3 0 L0 2 0 2 7 1 1 2 1 9 0 1 0 1 2 3 4 6 6 2 0 3 0 3 Y0 0 0 0 0 0 Y0 0 0 0 E - - - - - - E + - + - NEEEEEE NEE E E D2 0 5 0 0 7 D0 9 0 9 I 1 4 3 6 3 2 K I K 0 3. 0 3 2 1 1 2 1 2 0 1 0 1 2 2 0 0
) = ) =
E R E R K O K O A "r A T R D0 303 04 60 6 03 0 C T 0 3 0 3 C I A ND0 0 0 0 A I I - - - - - - F I I + - + - F OEEE E EE OEEE E RR 8 4 5 0 0 6 H RR0 8 0 8 H AY3 1 3 6 3 6 T 3 T EH D AY0 3 0 EH . D YT3 5 1 2 1 8 I YT0 7 0 7 I W W R E R E E R E R P O P O H H M S M S E Y EY 7 RD2 3 4 6 6 2 RD0 3 0 3 - MO0 0 0 0 0 0 MO0 0 0 0 V ( B - - - - - - ( * - + - EEEEE E EE EE E_L A2 4 4 5 0 0 9 _BL0 8 0 8 M S T 3 3 6 3 3 OO1 1 1 2 1 1 DT EA0 2 0 2 ST OO0 1 0 1 DT
) )
R R H ( H 0 0 0 0 0 ( 0 0 E0 6 0 0 0 M 2 3 4 6 6 2 R0 0 0 0 0 0 M I 4 8 0 0 0 T2 1 0 3 0 3 E0 6 M I 4 8 E - - - - - - R0 0 0 0 T2 1 E + - + - VE EE EEE VEEEE I 5 0 5 0 0 4 I 0 2 0 2 L6 8 3 6 3 8 L0 9 0 9 M 6 1 1 2 1 6 C 0 1 0 1 N O I 3 8 3 3 3 I 3 8 T T T c I 7 0 7 7 7 U7 0
- L 3 S L 3 I I 2 4 4 6 6 2 D E 0 4 0 4 D S 0 0 0 0 0 0 0 0 0 0 E - - - - - - S E + - + -
E NEEEEEE F S O5 7 5 0 0 2 B3 1 3 6 3 4 0 NEEE E O0 0 0 0 B0 4 0 4 D O 5 5 1 2 1 5 0 5 0 5 D n D
'R Y
T N
)
R Y
/ /
L .4 4 R 9 0 0 0 0 A 0 0 R 0 0 0 0 0 0 I N - - H. 6 0 4 4 4 F "T * + H, 0 0 I E E R 1 1 1 1 EE R 3 n H C K S 7 5 7 5 Y
/
G K 5 N I F S 0 0 0 0 Y
/
G 3 1 1 ( 0 0 K ( E E G G o A S U A S U E E g GNG GNG GN G o Y A W NI NG I LI N KE MI L NI NG I LI N KEMI Y A W NI I L K EL N I K HHNRMTA HNRMT HHNRA HN TS I OI AT S I OI A TS I OT SI AI R HW OO I RHWO AI R HO I R 1 PFDSSBT FDS SB PFDST FD lil 1l
0 2 4 5 6 0 0 2 3 5 5 0 I 0 0 0 0 0 0 I 0 0 0 0 0 0 L + - - - - + L + - - - - + LE EEEEE LEEEEEE
- 3 9 3 3 3 7 - 1 3 1 8 4 5 I 1 I 0 8 7 0 5 0 G 4 0 4 6 . 4 G 1 4 8 1 8 1 1 2 4 9 4 1 M_
2 2 4 5 6 2 2 2 3 5 5 2 0 0 0 0 0 0 0 0 0 0 0 0 G - - - - - - NEEEEEE U3 6 3 3 3 8 G - - - - - - NE EEEEE U8 6 1 8 4 2 M L0 0 70 5 6 L0 8 4 6 .1 9 6 2 8 1 8 8 7 2 4 9 4 9 1 2 4 5 6 1 1 2 3 S 5 1 Y0 0 0 0 0 0 Y0 0 0 O 0 0 E - - - - - - E - - - - - - NEE E EEE D1 8 3 3 3 3 NEEEEEE D4 5 1 B 4 1 I 8 0 4 6 1 1 I 8 2 7 0 5 1 K K 1 3 8 1 8 2 1 2 4 9 4 2 2 2 0 0
)
E K R O
= )
E K R O
=
M A T A T T 2 2 4 5 6 1 C T 2 2 3 5 5 1 C ND0 0 -0 0- A ND0 0 0 0 0 0 A I I F I I - - - - - - F OEEEEEE OEE EEEE RR B 0 3 3 3 5 H RR 0 2 1 8 4 0 H AY5 8 4 6 1 1 T AY4 1 7 0 5 0 T EH D EH D YT2 8 8 1 8 1 I YT2 7 4 9 4 1 I W W
- R E R E E R E R P O P O H H M S M S
- EY EY RD1 2 4 5 6 1 RD1 2 3 5 5 1 8 MO 0 0 0 0 0 0 MO0 0 0 0 0 0 -
( B - - - - - - ( B - - - - - - V EEE EEE EEEEE E L9 B 3 3 3 5 L3 3 1 8 4 1 E_A 0 1 4 E_A S T 33 7 0 5 6 S T . OO4. 4 3 841 6 N 8 4 OO2 2 4 9 4 2 O DT DT ) I ) T R R A H H ( C ( 0 0 0 0 0 0 0 0 0 0 O E0 E 0 0 0 0 0 L 1 2 4 5 6 1 M.0000 I 4 2 0 0 0 1 2 3 5 5 1 M I 4 2 0 0 0 D R0 0 0 0 0 0 T2 1 R 0 0 0 0 0 0 T2 1 E E - - - - - - E - - - - - - T VEEEE E E VEEEE E E C I 5 1 3 3 3 3 I 9 5 1 8 4 3 E L5 8 7 0 5 9 L L4 7 4 6 .1 8 E 5 3 8 1 8 5 5 2 4 9 4 5 S N N O S O I 0 0 0 0 0 I 0 0 0 0 0
- T E T U1 1 1 1 1 U1 1 1 1 1 L S L -
I I S 1 3 4 5 6 1 D O 1 3 3 5 5 1 D
- 0 0 0 0 0 0 0 0 0 0 0 0 E E - - - - - - D E - - - - - -
NEEE EEE NE EEEE E O 6 6 1 8 4 7 S O1 7 3 3 3 8
- O B0 7 4 6 1 0 B1 .57052 3 5 8 1 8 3 R 3 5 4 9 4 3 D E
) G )
R R T Y A Y
/ /
L U N I 4 0 E 4 0 E R 0 0 0 0 0 H, 1 0 2 2 2 R2 3 1 1 1 N E N I 3 0 E 3 0 E R 0 H, 6 4 0 0 0 0 0 7 7 7 R 1 1 6 6 6 m G D K 1 1 Y 7 E K 8 8 Y 5 H S 8 8 / S 4 4 / C A G T G S 9 9 K 5 5 K ( ( I D E E E G G T A A I S S S U U S I E E E E N GNG GNG GNG GNG O Y N I NG NI NG Y NI NG NI NG I A I LI N I L I N A I LI N I LI N T W KE MI L K E MI W K E MI L K E M I A HHNR MTA HNR MT H HNR MTA HNR MT C TS I OI AT S I OI A TS I OI AT SI OI A 4 AI RHW OO I RHW O AI R HW O O I RH W O 1 P FDS SBT FDS SB P FDS SB T FDS S B
' l ll)I l llll 1 2 4 5 6 1 0 2 0 2 I 0 0 0 0 0 0 I 0 0 0 0 L - - - - - - L + - + -
LEEEEE E LEEEE
- 3 8 4 0 9 9 - 0 0 0 0 I 6 4 8 9 4 0 I 1 1 0 . 0 .
G3.4. 9 1 9 4 G 0 4 0 4 2 2 4 5 6 2 0 2 0 2 0 0 0 0 0 0 0 0 0 0 G - - - - - - G + - + - NEEEEEE NEEEE U6 5 4 1 9 1 U0 2 0 2 L5 9 8 . ?. 4 6 L0 9 0 9 53 9 1 9 9 0 3 0 3 1 2 4 5 6 1 0 2 0 2 Y0 0 0 0 0 0 Y0 0 0 0 E - - - - - - E + - + - NEEEEE E NE E E E D5 3 4 0 9 9 D0 7 0 7 I 3 9 I 0 2 0 2 K 5 . 8 . 4 9 K . 1 4 9 1 9 1 0 4 0 4 2 2 0 0
) = ) =
E R E R K O K O A T A T T 2 1 4 5 6 1 C T 0 1 0 1 C ND0 0 0 0 0 0 A ND0 0 0 0 A I I - - - - - - F I I + - + - F O E E EE EE OF E E E RR7 1 4 0 9 7 H RR 0 2 0 2 H AY 4 6 8 9 4 8 T 3 T EH D AY EH 0 3 0 . D YT2 1 9 1 9 1 I YT0 2 0 2 I W W
- R E R E E R E R P O P O H H M S M S
- E Y E Y 9 R D2 2 4 5 6 1 R D0 2 0 2 -
M O0 0 0 0 0 0 MO0 0 0 0 ( B - - - - - - ( B + - + - V E E EEE E EEEE
- 3 4 0 9 3 L0 3 0 3 E_L ST A0 6 1 . 8 9 4 3 EA0 9 0 9 S T N OO9 4 9 1 9 1 OO0 3 0 3 O DT )
DT I ) T R R A H H C ( 0 0 0 0 0 ( 0 0 O E0 0 0 0 0 E 0 0 L M M 1 2 4 5 6 1 I 4 2 0 0 0 0 2 0 2 I 4 2 D R0 0 0 0 0 0 T2 1 R 0 0 0 0 T2 1 E E - - - - - - E + - + - T VEEEEEE VE EEE C I 5 6 4 0 9 2 I 0 1 0 1 E L8 5 8 9 4 4 L0 9 0 9 L E 4 5 9 1 9 5 0 5 0 5 S N N O O I 0 0 0 0 0 I 0 0
- T T M*
U1 1 1 1 1 U1 1 L S L I I 1 2 4 5 6 1 D E 0 2 0 2 D S 0 0 0 0 0 0 0 0 0 0 E - - - - - - S E + - + - E NEE EEE E N E E E E O 1 9 4 0 9 8 0 O0 6 0 6 W* S B 9 5 8 9 4 0 B 0 6 0 6 D O 3 1 9 1 9 4 0 1 0 1 D
) T )
R R D Y N Y
/ /
L 3 3 R9 0 0 0 0 A 0 0 R 0 0 0 0 0 0 H, 6 6D I N - - 0 4 4 4 F N + + H. 0 0
. I E E R 1 1 1 1 I E E R 3 G H K 4 4 Y 5 N K 0 0 Y 3 H S 1 1 / S 0 0 /
C C G I G S 1 1 K ( 0 0 K I ( E E E G G T A A I S S S U U U C S I N O I Y A GNG E N I NG I LI N GNG NI NG I LI N E Y A GN NI I L E G N I T W K EMI L K E MI W K EL K A HHNRMTA HNR MT H HNR A HN C TS I OI AT SI OI A TS I OT S I O AI RHWOO I RHWO AI R HO I R 1 L P FDSSB T FDS S B P FDS T FD l t llll!
i M 4 5 0 0
+ +
E E 4 0 2 6 1 7
= =
N N O O I I T T A A
- 1 2 2 1 L - 2 3 3 2 L
- I 0 0 0 0 U - I 0 0 0 0 U
- L - - - - P - L - - - - P
- LEEEE O - LEEEE O
- - 6 9 6 2 P - - 4 S 2 7 P 0 4 1 9 - I 8
- I
- G 5 5 3 5
- G 4. 52305 6
- 2 3 3 2 R - 3 4 4 3 R
- 0 0 0 0 H 0 - 0 0 0 0 H 0
- G - - - - 0 - G - - - - 0
- NEE EE 2 + - NEE E E 2 +
- U9 9 2 6 0 E - U2 5 8 0 0 E
- L3 2 4 3 + 0 - L4 3 4 4 + 0
- E 2 - . E 2
- 2 4 5 3 8 - 2 4 5 3 0
* - 6 2 - 4 2
- = - =
- 2 2 2 2 1 D - 3 3 3 3 2 D
* - Y0 0 0 0 L - Y0 0 0 0 L
- E - - - - F I - E - - - - F I
- NEEEE O H - NEEEE O H
* - D7 2 0 9 C - D5 3 2 0 C
) I 1 1 5 7 E I 2 1 5 9 E MK M )MK E
M S E 7 1 1 9 I 7 1 1 9 I E R T R T S - O ND3 4 3 3 G 0 ND4 5 4 4 G 0 D OI 0 0 0 0 N 0 OI 0 0 0 0 N 0
+ 0 S O - - - - I
- S O - - - - I 1
N R R EE EE S E RREEE E S E O EY2 3 5 6 S 0 EY4 9 5 8 S 0 I P H2 8 4 5 E 2 P H9 9 1 7 E 2 V T ( T C ( T C O O A L U E S Y 6 8 1 8 R P 5 N
= E S Y 4 6 1 6 R
P 5 N
=
P OD 1 2 3 1 E OD2 3 4 2 E OM DO0 0 0 0 D E D E D. BO0- -0 0 P E - B - - - - O T O T R - EEEE V . EEEE O N - - L2 1 0 5 F - L4 3 9 7 F ON - A6 4 8 8 . A6 4 8 8 I O - T S T . S TS - O1 1 8 1 E O1 1 8 1 E P R - T D 0 . T D 0 ME - U 0 - U 0 UP - 1 2 2 1 L + - 2 3 3 2 L + S - 0 0 0 0 C E - 0 0 0 0 C E N - R - - - - N 0 R - - - - N 0 O - E EEEE I 9 .- EEEEE I 9 C H
- V6 9 3 7
- I
- L 1 3 7 9 )
- 2 R +
0 6
=
. V8 3 8 1
- I
. L 1 4 7 0 )
- 2 R +
0 6
=
M S - 2 3 4 2 HE T . 23 4 3 HE T I - ( 9 L . ( 1 L F - E6 U . E4 U
- 1 2 2 1 M D - 2 3 3 2 M D
- 0 0 0 0 I *. A . 0 0 0 0 I 2 A
* - E - - - - T . E - - - - T
- NEEEE . NEEE E
- O9 2 1 7 4 O1 4 6 9 4
* - B 1 . 9 8. 7 0 B2 9 8 7 0
- + ) . + )
- 1 1 3 1 HE R - 1 1 3 1 HE R
* - C0 Y - C0 Y
- T3 / - 7 3 /
4 3 3 4 E0 0 0 0 G * + + + A C7 G K ( 6 5 5 6 E0 0 0 0 G + + + + A C7 G K ( M AEEEE AEEEE S0 2 3 0 0 N S3 5 1 6 0 N U1 1 9 3 N0 O U73 0 4 N0 O O + I T O + I 6 7 4 .7 I E T S 3 4 3 4 I E T T 0 U3 L P M U E V R T0 U3 L P M U M T I 7 S A I 7 S S D N H D N E P O P O V U R C L U R C R O E A O E A R G L I R G L H GTADL A C GTADL A LNLA U R LNL A U T EUEI T D E EUEI T D R GDEHU I V M GDEHO AATCT I V O AATC'I M P N I O N I S O D C O D Y I T A C N I E Y I T A C N I E m A O G A 4 G W L A W I A H HHHH R HHHHH R TS S SS E TS S S S E AI I I I V AI I I I V P FFFF A P FFFF A 0
m m m m m m
- ) )
e Y Y T T I I L L I I C C
- 1 2 2 1 A - 2 3 2 2 A 1 1 1 2 0 3 m - I 0 0 0 0
- L - - - -
- LEEEE F
T
- I 0 0 0 0
- L - - - -
- LEEEE F
T I 0 L - LE I 0 0 0 0 L - - - + LE EE E I 0 L - LE
- - 2 2 4 0 N - - 8 0 4 6 N - 6 - 3 7 4 5 - 9
- I 5 7 0 5 E - I 0 4 1 6 E I 0 I 8 0 1 1 I 9
- G M - G M G , G G
, - 2 27 3 T - 4 4 1 5 T 4 9 1 6 1 1
- A - A
- E - E
, - 1 2 2 1 R - 2 3 2 2 R 1 2 3 2 2 3
- 0 0 0 0 T2 - 0 0 0 0 T2 0 0 0 0 0 0
- G - - - - 0 - G - - - - 0 G - G - - - - G -
NE8EE U7 9 2 9 R + OE NEEEM
- U6 1 1 R +
VE NE U1 N EE EE U7 8 8 2 N E U9 L7 9 2 5 F0 6 L8 2 0 1 P 0 6 L0 L7 5 0
.7 L9
- * - R 1 1 6 2 - 2 3 1 4 R 3 4 8 1 6 1 r - H2 - H2
- = - =
* - 1 2 2 1 4 D - 2 3 2 2 4 D 1 1 2 2 1 3
- Y0 0 0 0 2 L - Y0 0 0 0 2 L Y0 Y0 0 0 0 Y0
- E - - - - I - E - - - - I E - E - - - - E -
* - NEEEE GH - NEEEE GH NE NE E EE NE
- D0 6 1 0 NC - D8 0 0 3 NC D 5 D 3 3 1 5 D9
- S E
) I E
MK 9 1 8 8 1 2 6 2 I D U
)
MK E I 0 5 1 5 3 3 1 4 I D U I K 2 3
)
M E I K 4 2 0 9 1 2 3 1 I K 9 1 S R L R L R O - C - C - D ND1 2 1 1 N2 ND2 2 2 1 N2 D1 N D2 3 3 2 D3 OI 0 0 0 0 I 0 OI 0 0 0 0 I 0 I 0 O I 0 0 0 0 I 0 m
- N SO - - - - ( + SO - - - - ( + O - S O - - - - O - 1 b RREEEE m E RREEEE E R E R R EEE E R E1 -, I BY9 3 1 6 R0 EY0 6 0 4 R0 Y0 E Y 1 7 9 2 Y9 -
T p H1 5 4 2 H6 PH4 0 9 3 H6 H6 P H 1 5 5 5 H9 V P ( T ( T T ( T T M 5 6 2 8 1 2 8 1 3 1 1 2 9 1 1 2 1 1 U E 0 = E 0 = E S 3 Y +N S Y + N Y S Y Y N 0D1 2 2 1 EE OD2 3 2 2 EE D1 O D1 2 2 1 93 O m C R DO0 0 0 0 B - - - - EEEE
. L5 5 0 3 6 E 0 T DO0 0 0 0 B - - - -
EEEE L8 4 5 0 0 E 1 T O0 B - E D O0 0 0 0 B - - - - E EEE O0 B - E 3 3 L2 - L3 2 6 9 L9 E . A1 2 5 0 = - A4 6 0 9 = A5 - A2 8 7 6 A9 T - T E - T E T - T T A - O2 2 6 3 M - O3 3 1 4 M V3 - O3 2 1 3 O1 W . T I 2 - T I 2 1 - T T
- N O
I 1 2 2 1 0 0 0 0 R - - - - T0 + TE I 0 2 3 2 2 0 0 0 0
- R - - - -
T0 TE
+ 1 0
1 2 2 1 0 0 0 0 3 0 I 0 R - - R - - - - R - T E EEEE S 7 - EEEEE S 7 EE - E EEEE EE A - V9 4 5 4 N - V1 4 2 7 N V0 - V1 8 5 4 V 9 L - I 2 7 7 4 A3 - I 7 4 4 5 A3 I 0 - 3 7 4 9
,- U P
L R = - L R = L - I L Y I L 9 22 8 3 TT - 3 4 1 5 TT 4 - 4 6 9 5 A 1 c O - L - L - D P . U - U - / 2 3 2 2 D - 3 4 3 2 ,D 2 - 1 2 2 1 L 0 0 0 0 0 A - 0 0 0 0 A 0 - 0 0 0 0 0
* . E - - - - - E - - - - E - H - E - - - - 0 E +
NEEEE 1 - NEEEE 1 NE C - NE EE E NE O 6 4 1 0 0 - O6 4 5 7 0 O7 T - O8 4 1 3 3 O0 B5 3 5 6 3 52 6
+
E 8 0 R
)
B7 6 0 0 5 8 4 1 3
+
E
)
B6 7 A C B3 8 6 5 2 3 7 3
=
B 0 0 1 R T - N Y - Y R - O 8 7 7. 8 3/ 7 6 6 7 3/ 8 O 5 4 3 5 E I 1 E0 0 0 0 = L E0 0 0 0 = L E0 P E0 0 0 0 S T E1 G + + + + N( G + + + + N( G + S G + + + + O P G + AEEEE - S9 1 8 9 U3 5 4 7 O I N TO UI AEEEE S9 9 7 4 U2 4 0 9 O I N TO AE S 8 U0 S E AEEE E S 2 2 5 6 U2 4 8 4 D M M U S AE S6 U8 UI D U N 1 1 2 1 LT 2 2 4 2 LT 2 U 1 1 9 1 I O 2 I P I P - L T C DM DM - C I U U - N . R R S S S - L I . T E N F N - A . T P O F P O LPT E P E A P U R C U U R C AUO SS U R R W U _ O R GTADL LNLA EUEI T E G 5 0 L
+ A EU 9 D L
B L I O R GTADL LNLA EUEI T E G 4 0 L
+ A EU 0 D TOT CR
*I GL EEM U
EO SD O DA P
- O
- R
. GTADL E
G LNL A E H P S L A U O R GL A EUE I T O D ET A H GDEHO AATCT 2 I V C N GDEHU AATC'I 7 I V VGU I AC AE P N
- GDE HO
- AATCT R
D I V GO AT A 5 I U 8 I T E Y I M = D O = D A NL H D O NN C NN L A . N OI - O I U T . I R .GGGG I R GGGG I M G D . - E YNNNN TE E YNNNN TE UYN 1 - Y E Y I hI I I I AG I AI I I I AG CAI - . A G A L MKKKK LA L WKK KK LA - W K - .W A WR P HNNNN UR P HNNNN UR - HN E - H HHHH R H E P TI I I I P E P TI I I I P E - TI T TS S S S E TT U ARRRR OV U ARR RR OV - AR O AI I I I V AA S PDDDD P A S PDDDD PA - PD N - P FFFF A P M d , !<
M M M 3 3 D D0 D0
- I I - I - _
) OE ) OE ) OE _
MR 5 MR 1 MR 0 E Y9 E) 6 E Y8 _
- RH RH RH
- T3 - T7 - T3 R
N N N O O O H S S S S 2 E R R R 0 1 S E E E 0 O P P + - D 2. (P Y ( Y ( Y E V 0 D1 D3 D3 0 N EO0 EO0 EO0 0 O I T A
= SB -
FO WDL5 S A9 E S B - O DL1 A6 E S B - O DL0 A8 E 0 M-L T T T - U O3 O7 O3 E M P T T T I O P T N T 0 0 0 0 0 1 0 O I L0 0 0 0 0 0 0 I S A + + + + + + + T 1 NTEEE E EEE A R 0 R R AO3 2 5 5 6 4 0 E R H N - I E H N I H N I RT7 8 9 5 T 1
.9 7 C 1 K9 1 K 1 K 9 8 4 8 4 3 8 E 0 S5 0 S 0 S R -
E E E 4 0 0 0 7 7 7 G E 6 E
=
6 E L0 0 2 0 0 0 0 A0 0 0 0 G 0 0 0 N * + - + + + + M-M 7 M 7 M 7
- 0 R E E E E EE E I 0 I 0 I 0 +E9 7 9 6 4 6 8 _
T E + T E + T E + ET0 1 1 0 5 0 0 _
- GE G E GE 0 X _
T A0 T A0 T A0
- R 0 E3 6 1 2 1 2 3 _
I S1 I S 1 I S 1 . S U S U S U A 1 _ N 4 N 4 N 4 E A A A Y G N R T G N R T G R T
- R E
N O
=
I I N M I P I L0 0 0 0 0 1 0 _ M I M T A T A0 0 0 0 0 0 0 T I I A T S I N + + + * + + + _ W W O OD LREE E EEE E S L S L B L I A I E 4 6 4 9 2 4 2 _ PU P U PU BR DT6 6 9 4 6 7 6 _ M UP M UP M UP M N _ A OO A OO A OO O I 6 2 4 6 2 3 5 E RP E R P E RP T - R 0 G R 0 G R 0 G L L E T 0 L T 0 T 0 . S + EA S + EA S + EA S . GT E GT E GT O - E _ AU N 0 AO N 0 N 0 AOT D _ W 3 T W O 3 T W O 3 E O _ D 7 D 7 D 7
- T _
A _
- = E - = - = R N N N N N G N N B O O YI O O YN O O YG E TN .
I I AL I I AI I I AN
- T AO _
T T T WE T T T WM T T WI A RE R ON _ A t HR A I HM A U HT T HEA K COK C L TO C L TI C L TA O S V UAEU 4S C RC O I Ah O I AW O I AO I I N1 L D PS L D P S L D PB
- B FI AMRHD
[ [ Fort Calhoun Station Unit No.1 [ ( CH-ODCM-0001 OFF-SITE DOSE CALCUl.ATION MANUAL
Title:
{ OFF-SITE DOSE CALCULATION MANUAL (ODCM) [ . [ FC-68 Number 48368 [ R= son for Change: To incorporate the format of NUREG-0472, Radiological Effluent Technical Specifications for PWRs ( Contact Person: J. Shipman f {
~
{ ISSUED: 01-15-98 9:30 am RB
I FORT CALHOUN STATION i CH-ODCM-0001 I OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 1 OF 129 TABLE OF CONTENTS PARTI Page . 1. D E F I N IT I O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l 2. IN 2.1 STR U ME NTATI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radioactive Liquid Effluent instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2.1.1 I 2.2 2.1.2 Limiting Condition for Operation : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Radioactive Gaseous Effluent Instrumentation . . . . . . . . . . . . . . . . . . . . . . ...... I 2.2.1 2.2.2 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
. Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 I 3.
RAD IO ACTIVE E FF L U E NTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 3.1.1 Concentration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 I 3.1.2 3.1.3 Dose from Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . 24 Liquid Waste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1.4 Liquid Holdup Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 I 3.2 Radioactive Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . .27. . . . . . 3.2.1 Concentration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2.2 Dose - Noble G as . . . . . . . . . . . . . . . . . . . . .. ... .. .. ... .. .. .. 31 ... .... l 3.2.3 3.2.4 Dose - l-131, Particulates, Tritium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 Gaseous Radwaste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 3.3 Uranium Fuel Cycle .............................. l 1 3.3.1 Total Do se . . . . . . . . . . . . . . . . . . . . . .. .. .. ... .. .. ... .. .. .. ... .. .. ..35 ....... l4. RADIOLOGICAL 4.1 Monitoring Program . ENV!RONMENTAL
. . . . . . . . . . . . . . . . . . . . . . . . . . .MONITORING
. . . . . . . . . . . . . . . . . . . .PROGR 36 4.1.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 I 4.2 4.1.2 Surveillance Requirements . . . . . . . . . . . . . . . . .
La nd U s e S u rvey . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .46 4.2.1
. . . 37 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 4.2.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4.3 Interlsboratory Comparison Program . . . . . . . . . . . . . . . . . . . . . . . .... . . . .. . . .47 . . . . 47 4.3.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 4.3.2 Sunteillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . I 5. 5.1ADMINISTRATIVE C ONTR O _L. S . .. .. .-... Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
. . . . 47 .
l 5.1.1 5.1.2
. . . . . . . . 47 FCS Chemistry Department . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 FCS Operations Department . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 l ouss RB
1 FORT CALHOUN STATION CH-ODCM-0001 g . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 2 OF 129 TABLE OF CONTENTS (Continued) PARTI ! Page 5.2 Radioactive Emuent Reporting R9quirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 5.2.1 Annual Radioactive Emuent Release Report . . . . . . . . . . . . . . . . . . . . . . 48 5.2.2 Annual Radiological Environmental Operating Report . . . . . . . . . . . . . . . 49 5.2.3 Special Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 5.2.4 EPA 40 CFR Part 190 Reportin 5.3 Change Mechanism . . . . . . . . . . . . . . . g Requirements . . . . . . . . . . . . . . . . . . . 50) 5.4 Meteorological Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. .. .. .. .. .. .. .. .. .. .51
. 51 5.5 References / Commitment Documents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
. l l
- 6. B6.1A S I S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '
In strumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1.1 ..... Radioactive Liquid Emuent Instrumentation . . . . . . . . . . . . . . . . . . . . . . . 53 j 6.1.2 6.2 Radioactive Gaseous Emuent instrumentation . . . . . . . . . Radioactive Emuents . . . . . . . . . . . . . . . . . . . . . . . .. .. .. ... .. .. .. ... .53 6.2.1 Radioactive Liquid Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 6.2.2 6.3 Radioactive Gaseous Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . Radioactive Environmental Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 6.3.1 Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 6.3.2 Land Use S urvey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 ) 6.3.3 Interlaboratory Comparison Program . . . . . . . . . . . . . . . . . . . . .. .61 . . . . . 60 l'
)
Il t
. - - - - - - . . . . - . --. . )
4 01/98 I R6
1 I FJRT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 3 OF 129 LIST OF TABLES I PARTI l 1.2 Frequency Notation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1.3 I 2.1.1 Radiological Effluent Controls Program Technical Specification implementation . . 9 Radioactive Liquid Effluent Monitoring instrumentation . . . . . . . . . . . . . . . . . . . . . 11 l 2.1.2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 13 2.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . 15 2.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance g Re quire m ents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3 .1 Radioactive Liquid Effluent Sampling And Analysis . . . . . . . . . . . . . . . . . . . . . . . . 22 I 3.2 Radioactive Airborne Effluent Sampling ano Analysis Program . . . . . . . . . . . . . . . 28 I { 3.3 Sarupler Deposition / Transportation Correction Factors . . . . . . . . . . . . . . . . . . . . . 30 4.1 Radiological Environmental Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . . . 38 4.2 Radiological Environmental. Sampling Locations and Media . . . . . . . . . . . . . . . . . 40 4.3 Detection Capabilities for Environmental Sample Analysis (LLD) . . . . . . . . . . . . . 44 4.4 Reporting Levels for Radioactivity Concentrations in Environmental Samples . . . 45 l I LIST OF FIGURES l PARTI l1 Environmental Radiological Sampling Points . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 I m e. R8
i l FORT CALHOUN STATION l CH-ODCM-0001 g . OFF-SITE DOSE CALCOLATION MANUAL REFERENCE USE PAGE 4 OF 129 TABLE OF CONTENTS PART 11 i
,l Page l 1.
E 1.1 FFL U ENT M O N ITO R S ETP OI NTS . . . . . . . . . . . . . . . . . . . . . . . . . . Liquid Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 1.1.1 Liquid Effluent Radiation Monitors . . . . . . . . . . 1.2 Airbome 1.2.1 Effluents . . . . . . . . . . . . . . . . . . . . . . ....................
. . . . . . . . . . . . . . . 68 .......
1.3 Airbome Emuent Radiation Monitors . . . . . . . . . . . . . . . . . Simultaneous Release Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69 1.3.1 Liquid Release Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 1.3.2 Airbome Release Pathways . . . . . . . . . . . . . . . . . . . . . . . ........ . . . . . . . . 77
. . . 75
- 2. EFFLUENT 2.1 C'ONC ENTRATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Liquid Effluent Concentrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 Airbome Effluent Concentrations . . . . . . . . . . . . . . . ........... . . . . . . . . . 86 ....... 3. RADIOACTIVE EFFLUENT DOSE CALCULATIONS ........... 3.1 Liquid Effluent Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . .. .. .. .. .. .. .. .. .. .. .87 . 87 3.1.1 Doses from Liquid Effluent Pathways . . . . . . . . . . . . . . . . . . . 3.2 Airbome 3.2.1 Effluent Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2.2 N oble G as . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 ....... ....... Radioiodines, Particulates, Tritium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 3.2.3 Concentrations of Radionuclides in Food and Ve Atmospheric Releases . . . . . . . . . . . . . . . . . . . . getation from 3.2.4 ................... 96 s Parameters for Calculating Radionuclide Concentrations in Milk . . . . . 100 3.2.5 Parameters for Calculating Radionuclide Concentr Excluding Tritium . . . . . . . . . . . . . . . . . . . . . ................
. . . . .ations in Cow100 Meat, 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation . . . . . 101 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Food . . 101 4.
L OWE R L IMIT O F D ETECTIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I I I R8
I FORT CALHOUN STATION CH-ODCM-0001 rI OFF-SITE DOSE CALCULATION MANUAL REEEEENCESEE PAGE 5 OF 129 LIST OF TABLES y I B PARTil i Page ! 1 Allocation Factors for Simultaneous Releases. . . . . . . . . . . . . . . . . . . . . . . . . . . . g2 Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases . . . . . . . . . . . . . . . 105 3 I 4 Bioaccumulation Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations . 107 I5 Stable Element Transfer Data . . . . . . . . . . . . . . . . . . . . . . . . . 6 Recommended Values for U,, to be Used for the Maximum Ex in Lieu of Site Specific Data . . . . . . . . . . . . . . . . . . . . . . . . . . . posed Individual
. . . . . . . . . . . . . . . . . . . 1 09 7 Animal Consumption Rates . . . . . . . . . . . . . . . .
.............................109 8
External Dose Factors for Standing on Contaminated Ground . . . . . . . . . . . . . . .... 110 9 inhalation Dose Factor for Adult . .........................................112 10 inhalation Dose Factor for Teenager . . . . . . . . . .............. .............. 114 11 inhalation Dose Factor for Child . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 inhalation Dose Factor for Infant . . . . . . . . . . . . ...................... ...... 118 l 13 Ingestion Dose Factor for Adult . . . . . . . . . . . . . . . ..... ................. ... 120 I 14 Ingestion Dose Factor for Teenager . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Ingestion Dose Factor for Child . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 124 16 Ingestion Dose Factor for infant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126 17 Recommended Values for Other Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I g mee I RB
FORT CALHOUN STATION . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 6 OF 129 l LIST OF FIGURES PART11 Page 1 Exclution and Site Boundary Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80 2 Liquid Radioactive Discharge Pathways . . . . . . . . . . . . . . . '. . . . . . . . . . . . . . . . . . . . . . 81 3 Liquid Radioactive Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 82 4 Airbome Effluent Discharge Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 l 5 l Airborne Radioactive Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 l 1 l l l l I
. I I
mee, I RB
~ ----
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 7 OF 129
- 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 compariso 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)dose. occupational of the Public means any individual except when that individual is receiving Ooerable - Operability A system, subsystem, train, component or device shall be OPERABLE or have I OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication, or other I cuxiliary 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) l Puroe-Puroino A means for the removal and replacement of gases within the containment building. [ Source Check ' Verification of channel response when the channel sensor is exposed to a radioactive cource. [ 01 /98 R8
I FORT CALHOUN STATION CH-ODCM-0001 g OFF-SITE DOSE CALCUl.ATION MANUAL RFFERENCE USE PAGE 8 OF 129 3
- 1. DEFINITIONS (Continued)
Ventina A means for the reduction of pressure greater than atmospheric within the containment structure. Unrestricted Area Means an area, access to which is neither limited or controlled by licensee. Water Effluent Concereiration (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 hours 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
,,,,,f R8 l'
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 9 OF 129 Table 1.3 " Radiological Effluent Controls Program Technical Specification implementation" Technical Soecification ODCM imolementina SjA2 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 5.16.1.4 3.1.2.8.1, 3.2.2.B.1 5.16.1.f 3.1.3.1, 3.2.4.1 5.16.1.g 3.2.1 5.16.1.h 3.2.2 5.16.1.i 3.2.3 I 5.16.1.] 3.3.1 l 5.16.2.a 4.1.1 5.16.2.b 4.2.1 I 5.16.2.c 4.3.1 l 5.17 5.3, 5.2.1.d 5.18 5.2.1.d I . I [ 01/9B t R8
I FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL BEEgBghlCE USE PAGE 10 OF 129
- 2. INSTRUMENTAIlQN_
2.1 Radioactiva Liquid Effluent Instrumentation
, 1 2.1.1 Limiting Condition for Operation A. The radioactive liquid emuent 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 11 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 emuents monitored by the affected channel or declare the channel inoperable.
- 2) With less than the minimum numberof radioactive liquid emuent 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-0548.
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.
i 01/98 I' R8
FORT CALHOUN STATION i CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 11 OF 129 Table 2.1.1 " Radioactive Liquid Effluent Monitoring Instrumentation" l B _ INSTRUMENT MINIMUM CHANNELS OPERABLE ACTION 1. Radioactivity Monitors Providing Alarm and Automatic I Termination of Release. a. l Liquid Radwaste Emuent Line (RM-055) 1 1, 5 b. Steam Generator Blowdown Effluent Line l (RM-054 A and B) 1' 2, 5 l 2. Flow Rate Measurement Devices
- c. Liquid Radwaste Effluent Line 1 3 I b.
Steam Generator Blowdown Effluent Line 1 3 1 3. Radioactivity Recorders l a. Liquid Radwaste Effluent Line 1 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 hours of the declaration of inoperability by the i Shift Supervisor, or the action steps of ACTION 2, Table 2.1.1 should be performed on the Steam Generator that is not being monitored. I [ 01/98 R8
1 1 FORT CALHOUN STATION CH-ODCM-0001 g
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 12 OF 129 Table 2.1.1 (Continued) .
Table Notation l ACTION 1 I 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: l 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 5.0E-07 pCi/ gram: 1. At least once'per 12 hours when the specific activity of the secondary coolant is greater than 0.01 pCl/ 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 pCl/ gram 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 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...Jf the emuent radiation l monitor fails the source check, carryout the action (s) of the ODCM for the inoperable monitor or terminate the emuent release. l 01/98 I I R8
N 1 9 02 8 E0MO 01 F 8 9
/
R C3 1 0 D1 M OE HG E CA 2 S MP "s t n e KA CE EL m HE _ p e CR , ir M u q EO e CT R RR e UO c OIR M n a S P ll e v r M S u n T o S L E m i t a E T t n NN e NO Q o _ m AI _ HC T mS E U i t u r s n C N U E F gN C E i t n r o g e. s a R i n N e O l gER E F M t n o I T A t e r o e R r o u B l R R R i r p g l f f l E A s r d i C h u q 4 gLA i L e i h 2 n U v L _ i t N i t c EK w NC gM A i d o a NE AH D
- D d
t e e N a H C C l p O I R
" m EA OL T
2
- o c
e I U 1 c r y b C 2 o l EL i i t ga t B a s e s t a D u A l b inm 4 r r m S C a T d o 5 0 o e n k c k vu i t N E T N t
/ i n en e c uS E yoA A e uO M t
i r 4 5 o Gwo h c h i vP d 5 5 M md w C hD U t csn r an 0- 0- e aw o L E H ao o M t eo l e M a F c dotimi T r t l r R t i R SB ES S nr a u l I w a
- N aoao l o u o RMAI s l
RF I a b. l F a. i s S F . V A 1 %O 2 '
FORT CALHOUN STATION CH-ODCM-0001 g OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 14 OF 129 E 2.2 Radioactive Gaseous Emuent Instrumentation 2.2.1 Limiting Condition for Operation A. The radioactive gaseous emuent 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 11 of the Off-site Dose Calculation Manual. APPLICABILITY: At all times i ACTION:
- 1) With a radioactive gaseous emuent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive gaseous emuents monitored by the affected channel or declare the channelinoperable. *
- 2) With less than the minimum number of radioactive gaseous effluent i 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.
l 2.2.2 Surveillance Requirements I 1 A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL lj CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 2.2.2. l I I 01/98 I, R8 )
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 15 OF 129 Table 2.2.1 " Radioactive Gaseous Effluent Monitoring instrumentation" MINIMUM INSTRUMENT CHANNELS OPERABLE ACTION
- 1. Auxiliary Bldg. Exhaust Stack (RM-052, RM-062)
- a. Noble Gas 1 1,9,11
- b. lodine and Particulate 1 2,9,11
- 2. Laboratory and Radwaste Processing Building Stack-(RM-043)
- a. Noble Gas 1 3, 9
- b. lodine and Particulate 1 4, 9 3.
Condenser Off Gas (RM-057)
- c. Noble Gas 1 5, 9
- 4. Containment Purge Line (RM-050/51)
- c. Noble Gas 1 1,6,9,11,12
- b. lodine and Particulate 1 2,9,11,12
- 5. Containment Prassure Relief Line (RM-050/51)
- c. Noble Gas 1 1,9,11
- b. lodine and Particulate 1 2,9,11 ,
l6. Containment Penetrations M72 and M74 (Integrated _ Leak Rate Test _ D; pressurization Vent Path) N/A 10 I I L_ 01/98 R8
1 FORT CALHOUN STATION CH-ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 16 OF 129 Table 2.2.1 (Continued) MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 4
- 7. Flow Rate Measurement Devices
- a. Waste Gas Discharge Header 1 7
- b. Auxiliary Building Stack 1 7
- c. Laboratory and Radwaste Processing Building Stack 1 7
- d. Containment Purge Line 1 7
- e. Containment Pressure Relief Line Annubar D/P 1 7
- 8. Radioactivity Chart Recorders
- a. Auxiliary Building Exhaust Stack 1 8 I
I m ee Re 'I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USEPAGE 17 OF 129 Table 2.2.1 (Continued) TABLE NOTATION ACTION 1 ' if the Auxiliary Building Exhaust Stack Noble Gas Nionitor 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 gmb samples are taken once per 8 hours (+25% maximum extension) and analyzed for principal gamma emitters. (See Table 3.2) ACTION 2 If the Auxiliary Building Exhaust Stack lodine 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 hours of the declaration of inoperability by the Shift Supervisor.
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 l 24 hours (+ 25% maximum extension) and analyzed for principal gamma emitters. (See Table 3.2) ACTION 4 ' l ff the lodine and Particulate Sampler is inoperable, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment i:. initiated with!n 2 hours of the l declaration of inoperability, by the Shift Supervisor, in accordance with Table 3.2. ACTION 5 l 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 hours (+25% l maximum extension) and analyzed for principal gamma emitters. (See Table 3.2) The release of airbome effluents from the Containment purge line will be l ACTION 6building secured if a noble gas monitor is unavailable to monitor the containment atmosphere. ACTION 7 F With the number of channels OPERABLE less than reguired by the Minimum L - Channels'OPERABD: req 0iremiInt,~6ffluehfr~eleashs~mip continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release. [ 01/98 R8 _ _ _ _ _ _ _ _ _ _ - - . - A
FORT CALHOUN STATION CH-ODCM-0001 g
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 18 OF 129 E Table 2.2.1 (Continued)
_ TABLE NOTATION ACTION 8 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, emuent 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 uninternJpted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor falls 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 SS-ST-ILRT-0001. 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 01/98 l RB
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 19 OF 129 Table 2.2.2 " Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements" CHANNEL SOURCE CHECK 2 CHANNEL FUNCTION INSTRUMENT PRIOR TO CHECK CALIBRATION TEST RELEASE
- 1. Radioactivity Monitors Providing Alarm and Automatic isolation
- a. RM-043 D R Q -
- b. RM-057 D R Q -
- c. RM-062 D R Q P l d. RM-052 D R Q P
- 2. Flowrate Monitors
- a. RM-043 Sampler D R -
- b. RM-062 Sampler D R -
l c. RM-052 Sampler D R - - I d. Auxiliary Bldg Exhaust Stack D R - -
- e. Laboratory and I Radwaste Process Bldg Exhaust Stack D R -
Operations Check Air Flow Calibration
- 3. Environmental Monitors
- c. RM-035-40 M A
[ ' Required *Hin RM-052 is sarbpling t'he Auxiliary Building Exhaust Sta5k.
~
~
2 A Source Check must be completed within 24 hrs prior to release. b 01/ 98 m R8
FORT CALHOUN STATION I CH-ODCM-0001 g . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 20 OF 129 E
- 3. RADIOACTIVE EFFLUENTS 3.1 Radioactive Liquid Effluents 3.1.1 Concentration A. Limiting Condition for Operation t
- 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, i 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 2.0E-04 pCl/ml, total activity.
- 2) Technical Specification 5.16.1.b establishes the administrative l
control limit on concentration of radioactive material, other than I 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.OE-04 pC1/mi total activity. APPLICABILITY: At all times { ACTION: l i a) When the concentration of radioactive material released at site discharge exceeds the above lirnits, appropriate corrective actions shall be taken immediately to restore concentrations g within the above limits. E B. Surveillance Requirements 1) Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 3.1. g
'"~ 2)
~ ' ~ The results of the radioactivity analysis shall be used with the
~
calculatio6al methodiin Pait 11 of the ODCid to assure that the concentration at the point of release is maintained within the limits of Technical Specification 5.16.1.b. 01/98 I I R8 l
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEERENCE USE PAGE 21 OF 129 3.1.18 3) Records shall be maintained of the radioactive concentrations and volume before dilution of each batch ofliquid 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. I I I l - l I e [ ~' 01/96 RB
FORT CALHOUN STATION I CH-ODCM-0001 g OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 22 OF 129 E Table 3.1 " Radioactive Liquid Effluent Sampling And Analysis" g A Monitor & Hotel Waste Tanks Raleases
' Lower Limit of Type of Sampling Frequency Activity Analysis Detection (LLD) -
(pCl/ml) ' Each Batch Principal Gamma Emitters 2 5.0E-07 Each Batch I-131 1.0E-06 Monthly from One Dissolved Noble Gases. Batch (Gamma Emitters) 1.0E-05 Monthly Con,posite
- H-3 1.0E-05 Monthly Composite d Gross Alpha 1.0E-07 Quarterly Composite d Sr-89, Sr-90 5.0E-08 garterly Composite d Fe-55 1.0E-06 B. Steam Generator Blowdown Lower Limit of Type of Sampling Frequency Activity Analysis Detection (LLD)
(pCi/ml) ' Weekly Composite d Principal Gamma Emitters 2 5.0E-07 Weekly Composite d 1-131 8 1.0E-06 Monthly Dissolved Noble Gases (Gamma Emitters) 1.0E-05 3 E Monthly Composite
- H-3 1.0E-05 Monthly Composite d Gross Alpha 1.0E-07 Quarterfy Cc6 posite d Sr-89, Sr-90 5.0E-08 Quarter 1y Composite d Fe-55 g 1.0E-06 I
e,,,, I RB I
FORT CALHOUN STATION CH-ODCM-0001 , OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 23 OF 129 Table 3.1 (Continued) NOTES: LLD is defined in Part ll of the ODCM. 8 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 5.0E-06. I
- A weekly grab sample and analyses program includin., gamma isotopic identification will be initiated for the turbine building sump effluent when the steam generator blowdown water l composite analysis indicates the 1-131 concentration is greater than 1.0E-06 pCi/ml.
d 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. I I I I I I I
-e em ,
01/98
l i FORT CALHOUN STATION CH-ODCM-0001
- OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 24 OF 129 l
l 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 during any calendar l year shall not exceed 3 millirems to the total body and 1Q millirems to any oroan. l
- 2) The dose or dose commitment to an individual in unrestricted areas j from radioactive materials in liquid emuents chring any calendar l quarter shall not exceed 15 millirems to the total body and 5 millirems to any oroan
. APPLICABILITY: At all times ACTION:
a) The radiation dose contributions from radioactive materials in liquit.' effluents released at site discharge shall be determined, in accordance with the methodology and parameters in Part 11 of the ODCM, on a quarterly basis. If the dose contribution, due to the cumulative release of liquid effluents averaged over a calendar quarter, exceeds one-half of the annual design objectives, the following course of actions shall be taken: (1) Make an investigation to identify the causes for such releases. (2) Define and initiate a program of action to reduce such releases to the design levels. (3) Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, identifying the causes and describing the proposed program of action to reduce such releases to the design levels. B. Surveillance Requirements
- 1) Cumulative dose contributions from liquid emuents. for the current
~
calender uarter i and the current calendar year shall be determined in accordance with the methodology and parameters in Part 11 of the ODCM at least once per quarter. l 01/98 i g R8 5
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 25 OF 129 3.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation i 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 l dose objective listed in ODCM Specification 3.1.2.A will not be exceeded in a calender quarter. l APPLICABILITY: At all times ACTION:
~
a) Every effort will be made to process all liquid waste, except I from the hotel waste tanks, through the Filtration /lon Exchange (FIX) system before entering the monitor tanks. If the radioactive liquid waste is discharged without processing and I 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 I 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 l . following information: (1) Identification of equipment or subsystem (s) not l operable and reasons for inoperability. (2) Action (s) taken to restore the inoperable equipment I 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 I least once per quarter, in accordance with +he methodology and
. . parameters _infart 11 of_the_ODCM .wheo Liquid Radwaste Treatment Systems are not fully OPERABLE.
01/98 , L R8 Ilii.. . .
FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 26 OF 129 3.1.3B 2) OPERABLE is defined as follows:
A filtration / ion exchange (FIX) system will be utilized for processing liquid radwaste. The system consists 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-178) are used only on those occasions when considered ne:,essary, 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 tankr. 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) I 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 o. f radioactive material to .the. tank and within 48 l 01/98
. l R8 l
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 27 OF 129 3.1.4 B. Surveillance Requirements
- 1) The quantity of radioactive material contained in each outdoor s
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 I radionuclides does not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To l g support plant operations, Supervisor-System Chemistry rnay . increase this limit up to the limits specified in Technical p Specification 5.16.1.g.
- 2) Technical Specification 5.16.1.g establishes the administrative 1 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 I Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For nob'e 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: I a) When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate l 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 samp_ ling an_d 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.
01/98 R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL gggM3ENCE USE PAGE 28 OF 129 Table 3.2 " Radioactive Airbome Effluent Sampling And Analysis" A. Gas Decay Tank Releases Lower Limit of Type of Sampling Frequency Detection (LLD) Activitly Analysis (pCi/ml) ' Prior to each release Principal Gamma Emitters 2 1.0E-04 B. Containment Purge Releases or Containment Pressure Relief Line Releases s Lower Limit of Type of Sampling Frequency Detection (LLD) Activity Analysis (pCi/ml) ' Prior to each release Principal Gamma Emitters 2 1.0E-04 Prior to each release H-3 1.0E-06 C. Condenser Off Gas Releases ' 9 Lower Limit of Type of Sampling Frequency Detection (LLD) Activity Analysis (pCi/ml) ' Monthly
- Tritium (H-3) 1.0E-06 Monthly Principal Gamma Emitters 2 1.0E-04 I
01/98 I' i , R8
I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 29 OF 129 Table 3.2 (Continued) D. Stack Auxiliary 8 Building Exhaust Stack and Laboratory and Radwaste Building Exhaus I ' Lower Limit of Type of 'I Sampling Frequency Activity Analysis Detection (LLD) (pCl/ml) ' Weekly (Charcoal Sample) 1-131 1.0E-12 Weekly (Particulates) Principal Gamma Emitters , 2 g - I-131, and Particulates with half-lives > eight (8) days. 1.0E-11 g Weekly (Noble Gases) Principal Gamma Emitters 2 1.0E-4 I Monthly Composite
- Gross Alpha 1.0E-11 l
Quarterly Composite (Particulates) Sr-89.' Sr-90 1.0E-11 I NOTES: LLD is defined in Part 11 of the ODCM l8 The principal following gamma emitters for which the LLD specification applies exclusively ar radionuclides: s Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous l
- cmissions 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. Required only when steam generator blowdown radioactivity for tritium (Table 3.1, i cxceeds 3.0E-03 pCi/ milliliter. F I' s requency requirement may be satisfied using weekly gross alpha results from particulate mpling media. I 5 Pcrticulate and lodine samples shall be corrected for sampler deposition / transportation efficiency by using the approved software programs or by multiplying the activi.ty obtained by the associated sampler multiplication factor (See Table 3.3). I 01/98 R8
FORT CALHOUN STATION I CH-ODCM-0001 g OFF-SITE DOSE CALCULATION MANUAL REFERENCE USEPAGE 30 OF 129 5 Table 3.3 " Sampler Deposition / transportation Correction Factors" g SAMPLER PARTICULATE IODINE SAMPLE DF ACTMULT' DF ACTMULT 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. ACTMULT for the samplefactors type. are automatically determined using the appropriate analysis seq 3 Sampler r7n be used to monitor either the Containment or Auxiliary Building. I I RB lI
l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 31 OF 129 3.2.2 Dose - Noble Gases A. Limiting Condition for Operation
- 1) During any calender yean Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
I
- 2) During any calender quarten Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta I radiation.
APPLICABILITY: At all times
- ACTION:
a) If the dose contribution, due to the cumulative release of noble gases in airborne effluents averaged over a calendar quarter i exceeds one-half of the annual design objectives, the following course of actions shall be taken: (1) Make an investigation to identify the cause for such 1 release rates. (2) Define and initiate a program of action to reduce such I releases to design levels. I (3) Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, I identifying the causes and describing the proposed program of action to reduce dose contributions. B. Surveillance Requirements l
- 1) The radiation dose contributions from radioactive noble gases in l airbome effluents shall be determined, in accordance with the methodologies and parameters of Part 11 of the ODCM, on a quarterly basis.
. ... . . .. ....-- . ... .. - . - - - - - - - - - - - ~ ~ - - - - - - -
[ c l 01/98 T RB
i FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 32 OF 129 3.2.3 Dose - lodine-131, Radioactive Material in Particulate Form with Half-Lives l Greater than 8 Days (Other than Noble Gases) and Tritium 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 l-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall not exceed 7.5 millirems in any calender quarter and 15 millirems frora all exposure pathways during any calendar year.
APPLICABILITY: At all times ACTION: a) If the dose contribution, due to the cumulative release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents averaged over a calendar quarter exceeds 3 one41alf of the annual design objectives, the following course ' of actions shall be taken: (1) Make an investigation to identify the cause for such release rates. 1 (2) Define and initiate a program of action to reduce such releases to design levels. (3) Submit a special report, pursuant to Technical g Specification 5.16, within 30 days from the end of the E1 quarter during which the release (s) occurred, identifying the causes and describing the proposed program of action to reduce dose contributions. j i B. Surveillance Requirements j
- 1) The radiation dose contributions from I-131, Tritium, and radioactive materials in particulate fomi with half-lives greater than eight days (excluding noble gases) in airbome effluents shall be
- ' determined, in accordance with the inethodologi.es and parameters of Part"Il 3f tiie"ODCM, on a quarterly basis.
g 01/98 I I R8
I FORT CALHOUN STATION CH-ODCM-0001 - OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 33 OF 129 3.2.4 Gaseous Radwaste Treatment A. Limiting Condition for Operation I 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 one half of the annual dose objectives listed in ODCM Specifications 3.2.2.A and 3.2.3A will not be exceeded. i 1 APPLICABILITY: At all times l l _ ACTION: l a) If radioactive gaseous waste is discharged without treatment and it is confirmed that one half of the annual dose objective will be exceeded during the calender quarter , a special report I 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 ' I subsystem (s) were inoperable. This report shall include the following information: I (1) Identification of equipment or subsystem (s) not operable and reasons for inoperability. I (2) Action (s) takeri to restore the inoperable equipment to operable status. (3) Summary description of action (s) taken to prevent a I- recurrence. B. Surveillance Requirements
- 1) Dose due to gaseous releases shall be projected frequently and at I least once per quaner, in accordance with the methodology and parameters in Part 11 of the ODCM, when Waste Gas Systems and Ventilation Exhaust Systems are not fully OPERABLE.
I . -- - - I - l .
I FORT CALHOUN STATION CH -ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 34 OF 129 3.2.4B 2) OPERABLE is defined as follows: a) Waste Gas System The waste airbome 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 airbome 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 l radioactive materials, e.g.,1-131, Xe-133. If the radioactive ! airbome wastes from the gas decay tanks are discharged without processing in accordance with the above conditions, and it is confirmed thet 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 j Section 3.2.4.A. - 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-G2. 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 airbome effluent pathways were well below the design objectives. The unavailability of hydrogen purge filters will r ot 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 Fi the containment purges aredema.itering Units prior to purging.E If without processing through 5 one of the Containment Air Cooling and Filtering Units, and it is
-- --- confirmed 1 hat onsTialf'6f thu hhnus!'d6s~e' objective will be' E exceeded during the calender quarter, a special report shall be E submitted to the NRC as defined in Action a) above.
I R8
FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL REFER _ENCE USE PAGE 35 OF 129 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 525 mrem to the total body or any organ (except the thyroid, which shall be limited to 5 75 mrem) during each calendar year.
APPLICABILITY: At all times ACTION: I 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 I 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 I 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 I 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 I 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 I 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 I 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 re,iease jI condition resulting in the violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisbns of 40 j CFR Part 190. Submittal of the report is considered a timely
- request, and a variance is granted until staff actign on.the request is complete.
01/98 R8
I FORT CALHOUN STATION . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 36 OF 129 I I 3.3.1 B. Surveillance Requirements Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillance requirements 3.1.2.B, 3.2.2.B and 3.2.3.B and in accordance with the methodology and parameters in Part 11 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: At all 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.
- 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 1 and submitted to the Nuclear Regulatory Commission within 30 i days from the end of the quarter (SectP n 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). l; l
4)
' "~ ~
Radiological environmental sampling locations and the media that is utilized for analysis are presented in Table 4.2. Sampling locations are also illus_trated on the map, Figure 1. Details of the l emir ~gency TLD locations are contained in the Radiological Emergency Response Plan. l' 01/98 R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 37 OF 129 4.1.1 A 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 complete 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 A. The Radiological Environmental Monitoring Program (REMP) shall be collected and analyzed in accordance with Tables 4.1, 4.2, and 4.3. 1 - I I I I [ . F 01/98 R8
lk FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE PAGE USE 38 OF 129 g Table 4,1 " Radiological Environmental Monitoring Program" F=T = e Pattmey ander Sample r % sne
- Type of Anahrais 8 Fraaim
- 1. Direct Rarti=#wvi A. Ten TLD hdicator stations, two control Gamme does stehens, totalof 12. Quarterty -
B. An inner-nng of
- 16 stations, one Gamma done durin g Sne Arne and g - in
.,each - RW Annually urvestncned arms boundary and wahin 2.5 mess. W C. An outer-ring of 16 stabons,1 h each !
Gamma dose dunng Site Area and cardmalsectorlocated outade of the Repsaced Annually General Emergenoes only, inner-ring, but no tre datant than appronometely5 miles. '
- 2. Air L T=vs A. Irwarmear Stabons FBler for Gross Beta ' Weeldy
- 1. 3 stabone h the generalarea of Charcoal for1-131 Weeldy d .o. - .
- 2. Cay of Blair Fater for Gamma iv Quartertycomposte of weeldy filters B. Two t% stabons
- 3. Water A.
Masourt RW at nearest downstroom Gen.u isotopc, H-3 dnniong waterintake. Monthly composte for Gamma lectope B. Anaheis Masouri Rher downstroom nearthe l mbang zone. I Quarter 1y composite C. Mmeouri Rher upstroem of Plant 61take for H-3 Analysm
- (beckground)
- 4. Mak
- A. Nearest fatnity cow when avadable or Gamma isotopc and 1-131 one dairy farm wthin 5 rnees, S-s-~. .;;y gramp season B. One dairy farm between 5 muss ard (Mayto October) 18.75 mass (" a '
G. F~mh A. Four fah samples within vicenty of Plant Gamma lar*v I decharge. Once perseason (Mey to October) B. One background semple upstroem of Plant discharge. - B
- 6. Sechment A. One sample frorn downstroom area on Gamma isotopic Semannumpy the station side of the Mesouri Rher.
B. One sample fmm upstream of Plant intala (background).
- 7. Vegetables or Food A. One sample b the tughest exposure Products
- Gamma teatopc Once per season pathway (Mayto October)
B. One sempie outside of 5 miles W-01/98 I R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL ggggg,EEP,,g,LI,ggPAGE 39 OF 129 Table 4.1 (Continued) NOTES: See Table 4.3 for required detection limits. ' 2 the wording of NUREG-0472. Rev.)3, Draft 7.The Lower Limit of Det Whenspectral gamma a gross betawill analysis count gridicates be performed. radioactivity greater than 1E-12 pCl/mi or' be collected, when available.When milk samples are not available, a broad le l 5 Details of Response Planthe Emergency TLD Stations are contained in the Radiological Eme 2 Samples should be collected from garden plots of 500 ft o . 1 I I I ~ l i I L
~
[ m 01/98 R8
8 9 1 9 / 02 s 1 0 01 Moedh o 8 0 F teF -- e R gd MO en VaP C 0 D4 OE HG h C PA l F a tr e m ee S k E M
"a i
d e r e M l M e d W X A n lo l e c n D M o L X X X X X X X L T X X X X g E h S U I p m M a e E S me o n bd X X X X C %.
,. k o X M-l N A E
a.
- u,.
R /. A E -. O k et e F E A na E - ou r l bic X X X X X M R d r t ir AaP r - g R l e )
- ansh 2 tmloet r l eo 4 n eg o er n 3' 8' 5' 3' 7'
- g * *
- e r r em pi 9 0 4 0 5 4 1 0 0' 0' 0 6' N
e p D (d re 2 2 1 3 1 1 0 1 8 1 3 1 5 2 3 5 g 1 1 T A I L A U emt N l a o r n e A iex mf mne)s 5 6 5 g M o r ciu na 0 0 0 8 0 3 7 8 0 6 0 7 9 0 N p pat s e (m t r f 4 2 0 1 0 0 7 1 _ O AiC D - I NA T n g_ OLU I l r e t o tr l I o c g o e l o t a n , _ a H .t T ALC l t o5 f m e e s n e g eg c7 o P l ie na _ n 0
- cd ea qr o erm r
hio ty i C eu m. ny f o w f o DlP TA "J..in o l 1 1 e, es tnfo e c t l r ot a E hs e n R f t nw W s E st en SC ce _ t e,H w ieE l n I.d i N, S N,. S, o e eE gS .r _e n f f o gw N, ie nm s m N, I NE o - w i c c 6a d D he n dI n f ioo 6 n o Ul a e a US %C o t a a
^
5o u uM _ k m l P d o o t - H ~ 7o i l t o a s _.Tarh _ r St n r P gP lh rW t e . OO u e 0" 0 e m HD eh e o s le ne l ea lep l e y. s t ws e feHc l O r Seh Fa C a el o co ns Su eS ll en t tt e sn e nt 8 le l J eth cO n L Ow nd Ol o f Ofoac i e Om t r o ee na na en na f e 1 ro ro AE B EO F FD l OP OP OP l l f O rFN l CIT r T S- @gne ab RF ;. iem u I 2 3 4 5 6 7 8 9 0 1 2 OF SSN 1 1 1 FO i ill }l} Ii} :
j i' l) ) I 1 l 1IlllIi 8 9 1 9 / 1 2 s s 0 1 led o 8 b o M mF t e aF gd dr X X X R M0 en Va P X X C1 D4 OE HG A h is
- P F X dr o
im d X X e S k il
- M X X X X X i
a d r e e
,ta X M X X X X d
n W A n io t a D c L o T L E v i. S ;; U v. e E S l men oi C ; e
. 9 i bd r N
e.. 6 A lo w E ;;.
- R k "L.
E r. ir el e ~ F E A ml e ~ E i s ou bic R
?. ir r t Aa A- P r -
R ,
)
. nsh r 2 .oet *
- 4 J. oeg crtieo n 6 5 3'
- 4 *
- 6 le 0 4 3 5 3 0 7 9 7 8 i em r 1 3 5 0 1 5 1 6 6 b
a mD(dor 1 1 2 3 1 2 2 0 1 8 3 1 9 2 L T A f A U emt N t a r o ne A nf n )s r ietne r ciB 5 4 2 0 5 0 6 M o na(m 0 9 1 1 8 4 8 3 4 6 MNO 7 7 patn r ptso 0 0 1 O 3 0 3 9 6 6 6 0 2 7 2 2 0 AiC D M. 'M. R R I T NA OLU r, e v r UAL I it
'eg TC .
Rn a il r eve ki r u * * *
;n . uP af ' .f a
TA 1is
.t o o sm t
nok l l e ge dR e r a e m m r a m r a SC I ce so w l A r r a
=lleit ir f mn oe e Be A F F F o S I
M sI
- s. er g NE t 1 n
m lpy li * . r r k b 'm rd US i%C k n ae e r p e ms a e t r a O s n el
'a oW i n p i y
r y lr ry
;v
;i
,k i
m h e h e c OO bt se t s nh r ew sr g. F h D -
-,t F o
D a n D e le D
.i
,r u
mt er So u E F a r lc W e l e Wy HD ewc ois t pd t i m P P
- = e o
s r le n h r p he Sc hs z n Wdd p l L AE UB l S O :D M i F l y M o J a s FM i a FM l a e L
+ l S
t e h J o J n e CIT NOF T TS - RF FO ,l
; .ne yiob SS N tam t u r
3 1 4 1 5 1 6 1 7 1 8 1 9 1 0 2 2 1 2 2 3 2 4 2 5 2 6 2 7 2 l I l1
8 9
/
1 9 s 1 0 02 ledo ls B 01 0 F b o e aF u ' R t e d od X X X X X MO gn e Va P r C2 D4 OE E HG ho C PA l F E t n e m ee S M t lu M M l"e d e r e M ll M i e d n W l lu A s e u n e l b u s M e D a c L o T s L a g E n 0 n o S U R p m e l l e c M e a E S me oi n l t l bd X ie C ia n 4 A r o t N e m 4 i l .a yd t M E m
- l ne R
n ot c y. E i w " ne ot ln f ir el e l a op . F E A ml e l ec e a cm E R l ig a c o ir Aa o u bic r t X me rb fo 5 nd n e rh et e m l o P i t f n l d lel np e eo r e d R . iom.l l o e 4 2
. net
.ovr cr eg n oo
)t 4
0 7 5 9' 7 d d i es sde ensl rRdhI ooiu e eoi e cl r m d e l.W .
,i r en r 6
1 9 1 0 2 0 2 1 2 0 2 fo e l dr oe I
,D (d ro deef e gl b t
o . T g f L mvub nooleht A fof ai cen a r ee se c l . U el temt pddt n h N ero en eon noahl o A mt m )e d e s 9 5 lorb yd l ee oc a M i ens che O 7 7 1 9 7 i vt pletn r (m 0 0 1 1 0 Bc a,u e t o n r nl e N pee : O AiC D c.lesmm el e u I 0c neUos cE T Rl dt. NA do ede n a ote ad nl lp OLU I 2 me yb nLnf l ao T ALC - n 'nn 0 0 h as odh wIdet r leeveeo o uun o 8 g o n n T A t s ce e
- le pt b n oe s SC let l
o S F k m m r o l i e m r o on c e em NE f n S j@:j F dl e b C r s y' r h a n ee ib US! 4 i c e k e e te I i rl up I! l i I' OO P R e se n e s S y n e qm ees HD L hv l A E. E d l e B o e n e e t r ot s ee 0 1 2 A H V B nNs AE nnoe CIT giel l negnn e r E eoa TS l peb mgm ne 6 pnl ss mhgcc e e ee R F- eiu e 2 9 2 0 3 1 3 2 3 3 3 :SWVtt e o ee OF SSN s e FO t o)2 ((()) N((3)45 1
)
II ll \
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 43 OF 129 Figure 1 a 23 (RM 666.8) J N 15 44 ~0 MIlC CALIFORNIA JUNCTION BLAIR l 31 , *. - * - A6 'q:' g g, i 22
- 13 )
t % FORT 2, % mE,,7,E, j l CALHOUN 24 .
. . ) .11 k 7 l
STATION 3 31
- 28 i *15
\
/
7 - .. l 3 =P j F1. CAte . 4 i ,, , / 133
. ) *20 75 5*12_.
/ .m.
u 01/98 R8
8 9 1 / 9 0 1 19 4 + 0 1 0 02 1 E
+ 8 01 a
- E - - -
- 0 F B
- 5. 5. R
. 1 1 MO e C4 7 1 2 1 2 2 h D4 3 0
+
0
+
0
+ G 0
+
1 0 t f . OE '- 1 s
- E 8
E E E- E E
+ o2 e5 HG - C 1
. 5. 8.
1 1
- 0. 8 1.
0 s on C PA '
)
1 8 h o t t i h e D 2 h ce t L L 4 3 1 1 0
+
0
+
1 0
+
2 0-2 0
+
1 0
+
t iwS, i h t E ( s
- E E E E E E rI et w 5 3 e n C 5 0 5 0 h ra i
o 1 1 1 1 1 6 t eP g n c a t c e 0 0 2 1 t, ot o dr E t 1 0 0 0 sna t o e 3 E
+
- E
+ 0-E
+ t nu c
c D 1 l 0 0 0
- E e s a f 0 ur n t
o 1 1 7 6 l f f p e t u i e M i 1 t r b m 5 0 no ap l l i 9- + a L E - l e h r b - - - - P R s e N 5 1 s ag n t s n M w e# e o l b ar m L s 5 9-1 0
+ npae r e
i s y Z r E 5 i t nO el u s a M l 1 d a e a i t e ne m n r E A 1 2 am l a S e 5 4n 0 E 4 0
+
t an h o t n e M U ler Z 0 E 6
- - - - t i s v r
m n E i 3 2 k n o e aE r C S el pa i v N E l a 80
, 1 0
2 0 ri eg c n e M 56 + + r R n t E h o o oo E - - - - t l Oio f E e CC 5 3 d F m .d E R n o 1 1 1 2 d eR r l a u e s s m i r 9 0 0 ea r v 5- + + d u e n in s t e E E - - - - nn e E o r F 3 0 2 6 oA ce eh i s m o e F bt d 2 oi n 1 t s 4 0 0 t n 5- + + d e e ee L A i i l i t M n E 5 1 E 3
- - - - r ar spo t
c s e n m U b 1 e e i N a p d r m. u3 A a 3 0 l icd un l o 1 . g M C 3- + na m4 M H E - - - - - ed r e C N n 0 s e ed D O i o 2 ez h yl hi u t O t rG e g I T c t yn a foy h NA e s l na r t OLU t e sa ot 2 0 oe so et f o D r e - ll a i I
- - E- - -
t a b l l TC " GB 0 h o eug l t r ae t AL - 1 t s p a g TA 3 nla a aR P SC 4 el l cf o n s mhsa i g g g n NE e it n LI W0e d
'm i&) pt)e o n s d e
US l b iU I C Cw i C
/
l y t o i t in g i' , C Cr ns c e OO a p p( p p p( d Cw p( sd e eg t a f e HD T ei ed d L ol c dn s AET i r d r s du de n CI e o a o oc t ts n em r T S l p s e B r / n s ed u i l s v e i um qo i t t io e R F- m a ela n e r o ol sb r o hb Ta ec Rr e h OF S r e cu i s e m s taaP T vtc n t FO t a hs k ae d e i sf eed aaggo WF i W Wu PG rS G1e. eeo r vVF
l 1
-m o e ao
- a. i
$ n, 4 8 I = l i _ m gQ N n f* W om ov 5 5 8 5 -
n
=
a E
? ? E jg z9W I G &
o G e o = o a w o s w
= = =
Eu.a:.e.c g o '< a 5 e
*$gg
, - n - ow C ? *
- E 8 G Omf l
y e g "e - e se a e a g 3 y
.saa "eEs
@ 8 g GEE n f .--. $
l w n . g o 3 2 I W~ I W n g '
@ g 2585m 6 a 85m l @
u
> EbjE c E o S o
- E x4 see=e c
e f g I I e ' e s v. I l li! 1 o I W % "
- a. b c N
- OVS .E E C e }n E un $ I I
- Rg l .9 ,
I l .4 a3 ="?B s .e_a o 3 Wf h w m
- o"
- o h
- m .9 -
+
g l m ,5 E W l l I 3 't 43V). U z , ~ , ~ N ..- - IE W W a.
=
.o 2
6 o g n O Q e I l i O V somc$. Em.9k W .9 c @W~3e a; - IM v a- 3 ? m , e E Vrm= esta
*uE*
8 s 8 8 I l I a s B . gmag I = E o E= z> a e~
, e
=
8 s -- e 1* 0 d -W W I I I 5 _E m " I z m# e - y .e s g.s E g-a
- B -
7
=
sn a C O l 'oz- g 5 &s
+
y I I I
' c 5jg8 .
s = c=- l P E E@#= E y ? iii s <q Nl55? j
- N ' I I I E - $$$g" o
< s o
s
& E
-se- -
e w jd s o a
=_ - U.g d >aE
" g -
g sa. w. w 3 u.c 2 V Egweg= V .-g bb B ] gg cg cw W E e . ,E a ggj$ os Ze EE no SE w aw3 e" * <e Gny%& Ra ?s o g g . v. s. e B; d- i h e8 s i?E] -
i FORT CALHOUN STATION Ii CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE PAGE USE 46 O 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 nearest meat animal, nearest vegetable garden, and the nearest residence in each of the 16 cardinal sectors within a distan 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 teamed from this survey that milk animals are present at a locationlocation which syields a calculated dose greater than from previo sampled ! monitoring progra(m)., the new location (s) shall be added to the The sampling location (s) having the lowest calculated dose may then be dropped from the monitoring prograrr at the end of the grazing and/or growing season during which the survey was conducted and the new location added to the ; i monitoring program. Also, any location (s) from which milk can no ' longer be obtained may be dropped and replaced if practicable from the monitoring program and the Nuclear Regulatory Commission shall be notified in the Annual Radiological Environmental Operating Report (Section 5.2). E: E< b) If it is teamed from this survey that a pathway for dose to a MEMBER OF THE GENERAL PUBLIC no longer exists, an g additional pathway has been identified or site specific factors B affecting the dose calculations for a pathway have changed, then this information should be documented in the Land Use Survey3 Ban the Annual Radioactive Effluent Release Reiport. This information can be used to increase the accuracy of the dose models for the Annual Radioactive Effluent Release Report as well as dose g, estimates performed during the reporting period (i.e. quarterly dose a estimates). I m,< I Ig RB
1 FORT CALHOUN STATION . CH-ODCM-0001~ OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 47 OF 129 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 Comm.ission in the Annual Radiological Environmental 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 Rogulatory 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. 01/98 R8
I FORT CALHOUN STATION CH-ODCM.0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 48 OF 129 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 i-art 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 I 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 airbome effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1. C. An assessment of radiation doses from the radioactive liquid and airbome 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 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 I 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 3 during the reporting period. B F. An explanation of why instrumenta'. ion designated in the ODCM Part I, Sections 30 days. 2.1.1 and 2.2.1 was not restored to OPERABLE status within i g! 01/9B R8
'I .
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 49 OF 129 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 shallinclude:
- A. i 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 sha 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. t B. Interpretations and sta'istical 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 hours prior to the first sample in
~
which the limit was exceeded. 2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded 1 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 radiciodine conceuhations. ; i l l 01/98 i l R8 , l
FORT CALHOUN STATION Il CH-ODCM-0001 g OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 50 OF 129 E 5.2.2 E 3) Purification system flow history starting 48 hours 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 radiciodine limit.
5.2.3 Special Report if the limits or requirements of Sections 3.1.2.A, 3.1.3.A, 3.2.2.A, 3.2.3.A, issued to the Commission, pursu) ant to Technical report shallinclude: 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 specificationlimits. 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 iil liquid o gaseous effluents exceeding twice the limits of dose from Specifications 3.1.2.A, 32.2.A, or 32.3.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 5 25 mrem to the total body or any organ (except thyroid, which is limited to 5 75 mrem) over the calendar year. This special report shall include an analysis which demonstrates that radiation exposures to any member of the a public from uranium fuel cycle sources (including all effluent pathways and 3 direct radiation) are less than the 40 CFR Part 190 standard. Otherwise, , obtain a variance from the Commission to permit releases which exceed the a i 40 CFR Part 190 standard. The submittal of the report is to be considered a 3, timely request and a variance is granted pending the final action on the ' varianceTequest fium the Commission.' ~ ~ ~ - ' 01/98 R8 I I!
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 51 OF 129 5.3 Change Mechanism The ODCM is the controlling document for all radioactive emuent releases. It is defined as a procedure under the guidance of Technical Specification 5.8. It will 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 fonvarded to the Nuclear Regulatory Commission during the next reporting I 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 I parameters and methodologies in Part 11 to determine unrestricted area dose on a quarterly bases or as needed. It is based on an average of the highest calculated I sector X/O 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 I estimates performed quarterly or as needed for conservatism. When calculating X/O data for the Annual Radiological Effluent Release Report, if the highest calculated XIQ > for I the reporting period is observed to be greater than i10% of the Annual Average X Q previously calculated, contact the Supervisor-System Chemistry for further I instructions. This model conforms wPh the Nuclear Regulatory Commissions Regulatory Guide 1.111. l 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. l These are used in the calculation of doses to individuals in unrestricted areas as result of the operation of Fort Calhoun Station. The models used, GASPAR 2 and LADTAP 2, conform with the Nuclear Regulatory Commissions Reg. Guide 1.109 and l 1.21 for the reporting of doses due to routine radioactive effluent releases. I [ _. [- 01/98 R8
I FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 52 OF 129 l 5.5 References / Commitment Documents Regulatory Guide 1.109, Rev.1 - Calculation of Annual Dose to man from Routine Re! eases of Reactor Emuents for the purpose of evaluation compliance with 10 CFR Part 50, Appendix l - Regulatory Guide 1.111, Rev.1 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Emuents in Routine Releases from Light-Water-Cooled Reactors. Regulatory Guide 1.113, Rev.1 - Estimating Aquatic Dispersion of Emuents from Accidental and Routine Releases for the purpose of implementing Appendix 1. Nureg-0133 - Preparation of Radiological Emuent Technical Specifications for Nuclear Power Plants. , Nureg-0472, Rev. 3 - Draft Radiological Emuent Technical Specifications for PWRs. Regulatorv Guide 1.21, Rev.1 - Measuring, Evaluating, and Reporting Radioactivity in solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Emuents ' from Light-Water-Cooled Nuclear Power Plants. Code of Federal Regulations, Title 10, Part 20
- l
\
Code of Federal Regulations, Title 10, Part 50 Fort Calhouq Revised Environmental Report (Unit No.1)-1972 Fort Calhoun Technical Specifications (Unit No.1) Updated Safety Analysis Report Commitment Documents: IMPLEMENTING COMMITMENT STEP SOURCE NUMBER (CID) DOCUMENT Part I, Table 2.2.1 ACTION 4 920102/01 FC-0133-92 01/98 I R8 I I __-_ _ - - _ _ _ _ _ _ _ _ - . (
r. FORT CALHOUN STATION CH-ODCM-0001 {: OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 53 OF 129
- 6. BASIS 6.1 instrumentation 6.1.1 Radioactive Liquid Emuent Instrumentation The Radioactive liquid emuent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in liquid emuents during actual or potential releases ofliquid emuents. The Alarm / Trip setpoints for these instruments shall be esk:ulated in accordance with Part 11 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.
6.1.2 Radioactive Gaseous Effluent instrumentation The Radioactive gaseous emuent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous emuents during actual or potential releases of liquid effluents. The Alarm / Trip setpoints for these instruments shall be calculated in accordance with Part 11 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. 6.2. Radioactive Emuents 6.2.1 Radioactive Liquid Emuents A. Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste emuents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 11, 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 Seebon ll.A design objectives of Appendix 1,10 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-135 is the controlling isotope and its emuent concentration in air (submersion) was converted to an equivalent concentration in water. 01/98 R8
FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 54 OF 129 6.2.1 B. Dose
- This specification is provided to implement the requirements of Sections ll.A , Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid emuents 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 11 of the ODCM implement the requirements in l
Section Ill.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 l unlikely to be substantially underestimated. The equations specified in Part ll 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 Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Emuents from Accidental and Routine Reactor
, Releases for the Purpose of implementing Appendix I," 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 requisement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid emuents 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 goveming the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50 for liquid effluents are
* ~
not exceeded. 01/98 R8
FORT CALHOUN STATION CH-ODCM,-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE PAGEUSE 55 OF 129 6.2.1 D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained !n the spe 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 ll, ' Column 2, at the neare 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 ensure that the. dose at or beyond the Site Boundary from gaseous emuents will be within the annual dose limits of 10 CFR Part 2 MEMBERS OF THE PUBLIC. The release rate of radioact airborne effluents shall be controlled such that the instantaneou concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airborne emuonts 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 emuents 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 Pri 50 Appendixi cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous emuents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR Part 20.1301 I l
. _ _ _ , ~ . . _. _ ..
I 01/98
. U l
I' FORT CALHOUN STATION CH-ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 56 OF 129 6.2.2 B. Dose - Noble Gases This specification is provided to implement the requirements of Sections ll.8, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! 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 Ill.A of Appendix ! 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 11 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 1.111, Methods for Estimating Atmospheric Transoort and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.
g l 01/98 RB t
I { FORT CALHOUN STATION CH-ODCM-0001 . l OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 57 OF 129 ! 6.2.2 C. Dose - I-131, Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium l This specification is provided to implement the requirements of I Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition For Operation implements the guide's set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating I flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l assure that the releases of radioactive l material in gaseous effluents will be kept as low as is reasonably I achievable. The surveillance requirements implement the requirements in Section Ill.A of Appendix ! thatconform with the guides of Appendix I to be shown by calculational procedures based on models and data l - 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 ll of the l ODCM for calculating the doses due to actual release rates of I radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual l 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 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Efflue..ts -I in Routine Releases frcm Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for 1-131, radioactive materialin I 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:
I 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 I producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. I 01/98
I FORT CALHOUN STATION - OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM.0001 g PAGE 58 OF 129 6.2.2 D. Gaseous Waste Treatment g 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 appropr ate portions l of this system be used when spcified provides assurance that the releases of radioactive materia!.s 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 ! 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 systems were specified to ensure the design objectives set forth in Section 11.B and ll.C of Appendix 1,10 CFR Part 50 for gaseous effluents are not exceeded. 9 e I g m ee g RB
m FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 59 OF 129 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 I orgen, 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 I plant remains within twice the dose design objectives of Appendix 1,10 CFR Part 50, and if direct radiation doses ( including outside storage tanks, etc.) are kept small. The Special Report shall describe a course I - 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 l 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 l PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report, with a request for a variance (provided the release l 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 I 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 I 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 10 I CFR Part 190 or with .a design objectives of Appendix ! to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301. I I 01/98 R8
. I FORT CALHOUN STATION
- OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 60 OF 129 l'; 6.3 Radioactive Environmental Monitoring , 6.3.1 Monitoring Program l'! 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 j o' radioactive materials and levels of radiation are not higher than expected i on the basis of the emuent 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 j program are made if required by the results of this survey. The best survey l information from door to door, serial or consulting with local agricultural authorities, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix ! 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 i since a garden of this size is the minimum required to produce the quantity (26 kglyear) 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/m 2, ,lt i 1 I l 01/98 , R8
[- [ FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEEEERGELSE PAGE 61 OF 129 ( 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 materiali' n environmental sample ( matrices are performed as part of a quality assurance program for environmental monitoring in order to demons' rate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50. [ . [ . [ ( ( ( [. [ s 01/9B R8
I FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 62 OF 129 l ,
\
~
i PART11 CALCULATIONS
\
I 01/98 R8
R
\
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOCE CALCULATION MANUAL REFERENCE USE PAGE 63 OF 129
- 1. EFFLUENT MONITOR SETPOINTS I
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 circulating water discharge to upstream of the intake structure to help prevent ice from g forming en the circulating water pump intakes during winter months. The varying dilution flowrate and utilization of warm water recirculation is accounted for in dilution calculations for monitor tank and stream generation releases. 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 effluentsio unrestricted areas conforming to ten times 10 CFR l Part 20.1001-20.2401, Appendix B, Table 2, Column 2, For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCl/ml total activity. l 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 concentratims 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 I 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. g Cs-137 is used to calibrate the liquid effluent monitors. I I 01/98 RB
FORT CALHOUN STATION OFF-SITE DOSE CALCUI.ATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 64 OF 129 l NOTE: if the annual average X/Q value exceeds 1.4E-04 sec/m*, consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.0E-09 pCi/ml 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 automatichily 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 1.0E-06 pCl/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 as maximum allowable concentration in the blowdown line is calculated follows: C" = (1.0E-05 pcimo m f Where: 1.0E-05 pCi/mi
= 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 1.20,000 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 g each,270 gpm total. Other flow rates may be used, as g required.) C. l
= Maxim'um allowable blowdown concentration (pCi/ml).
01/98 I R8 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USEPAGE 65 OF 129 - NOTE: Setpoints may be recalculated based on adjusted dilution flow and adjusted blowdown flow. The High Alarm Setpoint (CPM) = 0.75 jS,)(CQ) + 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, Decket Number 050-0285 and Telecon FC-472-77.
10% tolerance to account for the difference in detector sensitivity for the range of !sotopes detected. I S,
= Detector sensitivity factor (CPM /pCl/ml). (Sensitivity based on Cs-137).
B = Background (CPM) C. = Maximum allowable blowdown line activity (pCl/ml).
' 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 1 activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective m
actions prior to exceeding the Alarm Setpoint. B. Overt >oard 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 1.0E-06 pCi/ml at site discharge for unidentified isotopes by the high { alarm setpoint which closes the overboard flow control valve. { 01/98 R8
1 Ii FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 66 OF 129 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. { 1 1 The maximum allowable concentration in the overboard discharge headeris: Curx ~- (1.0E-05 pCimo (8 y { l Where: 1.0E-05 pCi/mi
= 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.)
C. = Maximum allowable activity in discharge header (pCi/ml). I I g m e. R8 lI
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 67 OF 129 1.1.18 The High Alarm Setpoint (CPM) = 0.75 jS,) (Cy) + B; Where: l 0.75 l = An administrative correction factor which includes the following: 1 15% tolerance 'o ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. l 10% tolerance to account for the difference in detector sensitivity for the range of isotopes detected. l S,
= Detector sensitivity factor (CPM /pCi/ml). (Sensitivity based on Cs-137).
I Cm = Maximum allowable concentbation in discharge header (pCi/ml). l B
= Background (CPM)
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) l 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 l actions prior to exceeding the Alarm Setpoint. I I I l . I _ 01/98 R8
I FORT CALHOUN. STATION OFF-SITE DOSE CALCULATION MANUAL ftEFERENCE USE CH-ODCM-0001 PAGE 68 OF 129 l 1.2 Airbome Emuents There are three air affluent 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. Auxiliarv Buildino - The Auxiliary Building Exhaust Stack receives discharges from the waste gas decay tanks, containment purge, co.ntainment vent systems and the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and lodine 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 Processino Buildino (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 CFP Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration Table 2, Columnshall
- 1. be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, The airbome emuent monitc ing instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air emuents at site discharge will be isss than the concentrations specified in 10 CFR g
Part 20, Appendix B, Table 2, Column 1. g
.The airbome emuent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in air emuents at site discharge will be less than 5 times the concentrations l
specified in 10~CFR Part 20, Appendix B,'Tsbie 2, Column 1. ~ 01/98 I I R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE , PAGE 69 OF 129 1.2.1 Airbome 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 through a particulate filter, and charcoal cartridge. The monitor controls airbome releases so that five times the 10 CFR Part 20 limit at the unrestricte area boundary of 5.OE-07 pCl/ce, based upon Xe-133, is not exceeded. The Ventilation setpoint is reached. Isolation Actuation Signal is initiated when the high alarm The following calculations for maximum release rate and alarm setpoint
- are valid when Auxiliary Building Exhaust Stack is the only airbome release pathway. For simultaneous airbome releases from Auxiliary Building Exhaust Stack, Condenser Off-gas and the LRWPB Exhaust Stack, refer to Section 1.3.
I The maximum allowable release rate for. stack airbome activity is calculated as follows: R pCi/sec = 2.5E-06 pCice l X/Q sec/m8 x 1.0E+06 m
. Where:
2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the I unrestricted area boundary (based upon Xe-133). I X/O sec/m3 = Annual average dispersion factor at the unrestacted area boundary from ODCM Part 11 Table 4, Controlling Locatior,s, Pathways and Atmospheric Dispersion For Dose Calculations. { 1.0E+06 cc/m8 = Constant of unit conversion. E ~ 01/98 R8
FORT CALHOUN STATION CH-ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 70 OF 129 1.2.1 A The High Alarm Setpoint (CPM): Setpoint = 0.75 Y (RQ (S,) (50)' +B
,, (Fy ) (28317) , ,
Where: 0.75
= An administrative correction factor which includes the following:
15% inlerance to ensure radm' onitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. ; i 10% tolerance to allow for the contribution of noble gases ! other than Xe-133 towards the total ECL fraction sum. i S,
= Detector sensitivity factor (CPM /pCi/cc). (Sensitivity based ,
on Xe-133) { 60
= Conversion (seconds to minutes).
28317 1
= Conversion factor (ft* to cc).
F, = 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.) Rm = 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 VIAS actuation. 01/98 i l 4 RB ! l
1 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 71 OF 129 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 5.0E-07 pCi/ce, 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 teiease 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:
Rm pCi/sec = 2.5E-06 pCl/cc x 1.0E+06 cc/m3 X/Q sec/m3 Where: l 2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon I X/O sec/m8 = Xe-133). Annual average dispersion factor at the l unrestricted area boundary from ODCM Part 11, Table 4, Controlling Locations, Pathways and Atmospheric Dispersion For Dose Calculations. 1.0E+06 cc/m' = Constant of unit conversion. 1 I [ . - - . . . . . . . .. . . . . . - - - - . . . - - . . - - - - g . ~ 01/98 R8
R FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 72 OF 129 l The High Alarm Setpoint (CPM): Y (R,) (S,) (60)' l Setpoint = 0.75 +B
, (Fy ) (28317) ,
Where: 0.75 = l t An administrative correction factor which includes the following: 15% tolerance to ensure radmo'nitor VIAS response in accordance with License Event Report 77-17, Docket I 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 /pCl/cc). (Sensitivity based on Xe-133) 60 = Conversion (seconds to minutes). 28317 = Conversion factor (ft* to ec). F, = Vent stack flow rate (SCFM 4,755 scfm (3 vacuum pump). Default s in hogging maximum mode. Other flowflow rate is rates may be used, as required.) Rm = Maximum Allowable Release Rate in uCi/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. 1 i 01/98
, RB t 4
--------m i
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 73 OF 129 1.2.1 C. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and lodine and Particulate Sampler (RM-043) RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is tiased on five times the 10 CFR Part 20 limit for Xe-133 at the unrestricted area boundary. The following calculations for maximum release rate and s.larm 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:
R ,pCisec = .5-06 fi/cc , 3,954 gg,,s X/Q sec/m 3 Where: 2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the l unrestricted area boundary (based upon Xe-133). X/Q = l Annual average dispersion factor at the unrestricted area boundary from the ODCM Part 11, Table 4 Controlling Locations, Pathways and Atmospheric Dispersion for l Dosed Calculations. 1.0E+06 cc/m' = Constant of' unit conversion I - L [ . [ 01/98 R8
FORT CALHOUN STATION I{ . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 74 OF 129 CH-ODCM-0001 l NOTE: This monitor alarms in the Control Room. There are no . automatic control functions associated with the actuation of the alarm. The High Alarm Setpoint (CPM): { j Setpoint = 0.75 Y (RQ (S) (60)' +B
, (F,) (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. S,
= Detector sensitivity factor (CPM /pCl/cc). (Sensitivity based on Xe-133) 60
= Conversion (seconds to minutes).
2831'7
= Conversion factor (ft' to ec).
F,
= LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.)
R. = 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. l
~
I g 01/98 I
. i R8 g
FORT CALHOUN STATION - CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 75 OF 129 1.3 Simultaneous Release Pathways NOTE: If the annual average X/Q value exceeds 1.4E-04 sec/m8, consideration should be given to basing liquid radiation monitor setpoints on
. an 1-131 instantaneous limit of 2.0E-09 pCi/mi at the unrestricted area boundary with 10% vapor / liquid se Chemistry for further instructions. paration. Contact the Supervisor-System 1.3.1 Liquid Release Pathways The liquid radiation monitors (RM-054A/0548 and RM-055) control liquid releases so that ten times the 10 CFR Part 20 limit of 1.0E-06 pCi/mi for i 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 i 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: C, = KoC , + K, C m, Ko(1.0E-05 pCi/m/) (F) K, (1.0E-05 pCim/) (F) C' = + fo It l Where: i C, = Sum of individual maximum allowable concentrations for ' Steam Generator and Monitor Tank prior to dilution for simultaneous liquid releases (pCi/ml) C., = Maximum allowable concentration in Steam Generator blowdown Line (pCi/ml) C., = Maximum allowable concentration in Monitor Tank Discharge Line (pCi/ml) Ko = Allocation factor for Steam Generator (See Table 1) K, = Allocation foctor for Monitor Tank (See Table 1) F = Total dilution flow in Discharge Tunnel (GPM) - - fo = Steam Generator Blowdown flowrate (GPM) f, = Monitor Tank Discharge flowrate (GPM) 01/98 R8
FORT CALHOUN STATION
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 76 OF 129
.j The High Alarm Setpoint for Steam Generator Blowdown monitors, RM-054A/0548, will then be: l Alarm Setpoint (CPM) = 0.75 fqS Cg) + Bo The High Alarm Setpoint for Monitor Tank Discharge. Monitor, RM-055, will then be:
Alarm Setpoint (CPM) =' O.75 f, S,, Cy) + B,' Where: Se = Detector Sensitivity factor for RM-054A/054B, CPM /(pCi/ml), based on Cs-137. Sn = Detector Sensitivity factor for RM-055, CPM /(pCl/ml), based on Cs-137. C. = Maximum allowable concentration in S/G Blowdown line. (pCl/ml) Cw, = Maximum allowable concentration in MT Discharge line. (pCi/ml) Bo = RM 054A/0548 background countrate. (CPM) B, = RM-055 background countrate." (CPM) Ko , 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. 01/98
. I R8
+ . FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 77 OF 129 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 5.0E-07 pCi/cc for noble gases at the unrestricted area boundary is not 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 1.2.1 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 sim,ultaneous releases is:
Max. Re/eese Rate = f K,R 06 & 4=e1f IQ 41 X/Q sec/m3 Where: R. = RM-062/RM-052 release rate (pCi/sec) R ,, = RM-057 release rate (pCi/sec) Rm = RM-043 release rate (pCi/sec)
- X/Q =
Annual average dispersion factor at the unrestricted area boundary from the ODCM Part II, Table 4, Controlling Locations, Pathways and Atmospheric Dispersion for Dosed Calculations. K, - K, = Allocation factors. See Table 1. 2.5E-06 pCl/cc = 5 times the 10 CFR Part 20 Lirnit at the unrestricted area boundary (based upon Xe-133). 01/98 R8
e R I FORT CALHOUN STATION CH-ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 78 OF 129 The maximum release rate Rm then:
'(K,) Q.56-06 pCFce) (K,) 9.5E-06 pCice) l
+ +
(K)3 4.5E-06 pCice)' XO sedm' XC sedma 1.0E+06 ce =R* XC sedm 8 ,; mz The High Alarm Setpoints for the noble gas monitors will then be: l RM-062/052 = 0.75 K, +B F, @8317) j RM-057 = 0.75 K,
+B (F,) (28317) , ,
RM-043 = 0.75 K3 -
.S (F) (28317) , ,
Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor VIAS res accordance with License Event. Report 77-17,ponse Docket in Number 050-0285 and Telecon FC-472-77. 10% tolerance to allow for the contncution of noble gases other ; than Xe-133 towards the total ECL fmetion sum. t K, - K3 = Allocation factors. See Tebie 1. S, = Detector sensitivity fLetor. F, = Vent stack fic* rate. (Condenser off-gas flowrate for RM-057, LRWPB c:xhaust stack flow rate for RM-043, Auxiliary Building Exhaust Stack flow rate for RM-062/05.2). Rm = Maximum Allowable Release Rate in pCi/sec. B = Monitor background count rate. 60 = Constant of unit conversion (60 sec/ min). The Alert Set value of the h int will be chosen less than or equal to one fifth (1/5) the will be identifi alarm setpoint value so that significant increasesan activity prior to exceeding an Unrestricted Area fractional sum of 1.0. 11 will also p,rovide additional time for cotrective actions prior to exceeding the Alarm Setpoint. 01/98 RB
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL ENEfag.lifr.lBigg PAGE 79 OF 129 Table 1 " Allocation Factors for Simultaneous Releases" NOTE: The Fort Calhoun Station is capable of performing simultaneous airbome releases giveni sum of the Unrestricted Area Fraction Sum for all airtome releases remains less than or equal to 1.0. l A. Allocation Factors for Simultaneous Airtome Releases l
- 1. Auxiliary Building Exhaust Stack Total: 0.80 K, i Noble Gases (RM-062 or RM-052) 0.70 !
lodine / Particulate / Tritium 0.10 Contributing Pathways: a) Auxiliary Building ) 0.10 l b) Containment Building 0.65 c) Waste Gas Decay Tanks 0.05
- 2. Condenser /Off Gas Total: 0.10 K2 Noble Gases (RM-057) 0.05 Tritium 0.05 Contributing Pathways:
a) Condenser Off Gas 0.10
- 3. Laboratory and Radioactive Waste Building Exhaust Stack Total: 0.10 K3 Noble Gases (RM-043) 0.05 lodine / Particulate 0.05 Contributing Pathways:
a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airbome Release Total 1.00
- NOTE
The Fort Calhoun Station is capable of performing simultaneous liquid releases given that the sum of the Unrestricted Area Fraction Sum for allliquid releases remains less than or equal to 1.0.
- B. All
- cation Factors for Simultaneous Liquid Releases
- 1. Ko Steam Generator Releases (RM-054A/0548) 0.30
-2r K7 -- -~ -Waste Liquid Releases-(RM-OSS)- ~~ ' ~~ ~ - - - - " ~
0.70 Liquid Release Total 1.00 01/98 R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL , REFERENCE USE PAGE 80 OF 129 Figure 1
\ \ -
Tru. N \ y x sa.
'n N IOWA r l \
N y \ UNRESTRICTED AREA BOUNDARY
\ s l
i NEBRASKA
\\ .'N -RESTRICTED s
\ ^^ ^
s
\ \
[\ ~
'N \s /
MET (g \ s' ' OUN l TOWER , A /(n s / % UNIT #1 l ~ CONTROLLED TO 4 ADMIN. s w AREA BLDG. BLAIR -
)
p 5_ - TRAINING \ 'g CENTER si s
/ \
)i UNRESTRICTED AREA 75 \
i l t '
@ UQUID EFFLUENTS DISCHARGE N, AIRBORNE EFFLUENTS DISCHARGE N TO OMAHA . . O. - .. '
1[2 } SCALE IN MILES EXCLUSION AND SITE BOUNDARY MAP 01/98 ll RB
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE B1 OF 129 Figure 2 i 1 HOTEL S/G S/G RAW TANKS A B , BLOWDOWN WATER BLOWDOWN V N i MONITOR A TANKS (1) (2) J i
)
O)
\
i if if OUTFALL
/ f( -
CIRCULATING (T1 l
/- WATER
/ \ T !
(/ l WARM WATER RECIRCULATION f un RIVER 1r
. RIVER if
- kMR-F.&n n
~' ~ '
Sc~5MCb"dm hSWR&&cR?MM E%... .-PAMW - Q RM-054A
@ RM-0548
@ RM-055 LIOUlD RADIOACTIVE DISCHARGE PATHWAYS 01/98 R8
I FORT CALHOUN STATION . OFF-SITE DOSE CALCULATION MANUAL REEEEENCEMEE CH-ODCM4001 PAGE B2 OF 129 li , Figure 3 AUXILIARY SYSTEMS PROCESS WASTE HOTEL WASTE CrCS slee u r Floor Drew [ gap,,ng g,3n, t,jg, w,,a Sumpflows RC Loop &ams Sho.er Droms F V V s,,n, mom mm
)
'ts "'
ssa cei.
> at ti ,
( ) . ggc,1- u se1.
. cm Worte Falters 58fterons l Dominerehrer vessels
~
38 Cu. Ft. ' Charcoal ' Filter 69 Co. ft. (opueneD I em Monstar Tanks 6770 Col. C. Y Overboard Heeder (To Faver)
"'8 LIOUID RADI0 ACTIVE WASTE DISPOSAL SYSTEM RB
FORT CALHOUN STATION CH-ODCM@01 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 83 OF 129 Ogure -; N RM-043 Noble Gas Monitor, and lodine & Particulate Sampler , LRWPB Laboratory 1ABORATORY AND RADIOACTIVE WASTE PROCESSING BUILDING h RM-062,052 Noble Gas Monitor Iodine & Particulate Sampler h RM-057 Noble Gas' Monitor CONDENSER OFFGAS AUXILIARY BUILDING EXHAUST STACK Condenser Auxiliary Building Containment Ventilation Building Ventilation
. AIRBORNE EFFLUENT DISCHARGE PATHWAYS J1/98 RB
FORT CALHOUN STATION . OFF-SITE DOSE CALCULATION MANUAL REFERENCE U,gg CH-ODCM-OD01 PAGE 84 OF 129 l Figure 5 l Turbine k A Ventilation "7, (~
* "d'"**# Stack
~ To Atmosphere 122.500 S. C.
g w ( To Roof Condenser Vacuum l Pumps
+
Charcoal
+ Absorber ash Gas Holdup Tanks (4) >
( 400 CuFt (each) ) 3 HEPA Filt'er WASTE GAS AND CONDENSER OFF-GAS SYSTEMS Inlet Roll Fans O Filters Containment e 3 Purge Containment I"I'l HEPA Filter Coo nd m
}n l D j $50,000 SCFM ^
Recirculation System-HIPA Purge Charcoal Filters Outlet CONTAINMENT BUILDING VENTILATION CONTROL Charcoal Tilters Fuel Handling "* Mg
-~
4 ^Y*** +~ Tilter i C Fans Safety -
~ ri$tk h NeNs .- _ .
h, Other 172.500 SCFM Ground AIRBORNE RADIOACTIVE WASTE DISPOSAL SYSTEM ouss a i RB
FORT CALHOUN STATION CH-ODCMM1 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 85 OF 129
- 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 concentratioris 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 (Steem Gene 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 site discharge: at
- A; = i F+f n
A' and [ s1 l m wec, Where: I A = 3 concentration at site discharge for radionuclide (i), in pCi/ml. l a, = concentration of radionuclide (i) in the undiluted effluent, in pCl/ml. f = undiluted effluent flowrate, in gpm. F = total diluted effluent flowrate in gpm. I weci = water effluont concentration limit for radionuclide (i) per 10 CFR Part 20, Appendix B, Table 2, Column 2. I l I ' L O u 01/98 R8
FORT CALHOUN STATION CH-ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 86 OF 129 l , I NOTE: In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable. l 2.2 Airbome Emuent Concentrations The concentration at the unrestricted area boundary, due to airbome 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. l In the event an airbome 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: l-To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used: l A, = Ko Q, (X/Q) . l and f 1., EC4 s1 Where: I A, = Concentration of radionuclide (i) at the unres;ricted area boundary Ko = Constant of unit conversion. (1.0E-6 m'/cc) l ECL,'= Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, ' Column 1 value for radionuclide(i)) Q, = The release rate of radionuclide (i) in airbome effluents from all vent releases (in pCi/sec.) (X/ Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Controliing Locations, Pathways and Atmospheric Dispersion For Dose Calculations (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 time period not to exceed 15 minutes )
- when determining noble gas release rate based on correlation of the inonitoFreading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airbome emuent dose rate.
l 01/98 l I R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 87 OF 129 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 setooint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20.
- 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) drinkirig water, and 3) Shoreline deposition. Fish are considered to be taken from the vicinity of the plant discharge. The drinking water for Omaha is
! located 19 miles downstream from FCS. The dilution factors for these pathways are g derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and p 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be 514% 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 I 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 individualin unrestricted areas. 10 CFR Part 50, Appendix ! restricts the dose to' individuals in the unrestricted areas from radioactive materials in liquid effluents from the F. ort Calhoun Station to the following limits: e during any calendar quarter 51.5 mrem to total body l 55.0 mrem to any organ and I e during any calendar year 5 3.0 mrem to total body l 510.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents. 4 01/98 RB
I FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 88 OF 129 3.1.1 Doses from Liquid Effiuent Pathways A. Potable Water Rg = 1100 u,p* f E Q,D,exp(-A/)
la1 Where: Rg = is the total annual dose to organ 0) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem /yr. U,, = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in t/yr. (Table 6) M, = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless. (Table 4) F = is the flow rate of the liquid effluent, in ft'/ sec.
, Q, = is the annual release rate of radionuclide (i), in Ci/yr.
D, = 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 mrem /pCl. (Tables 13-16) 4 = is the radiological decay constant of radionuclide (i), in br'. I t, = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, t is the total l time elapsed between release of the radionuclide,s and l ingestion of water, in hours. (Table 17) { 1100 = Constant (pCi
- yr
- ft'/Ci
- sec
- L) l 01/98 ,
I R8 3 1
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 89 OF 129 3.1.1 B. Aquatic Foods R4 # 1100 U,M* f O,B,,D,g exp(-A,t,) f i=1 Where: Rg = is the total annual dose to organ 0) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem /yr. U,, = is a usage factor that specifies the intake rate for an
- individual of age group (a) associated with pathway (p), in kglyr. (Table 6) l M, =
is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. (Table 4) l F = is the flow rate of the liquid effluent, in ft'/sec. Q, = is the annual release rate of radionuclide (i), in Ci/yr. B, = is the equilibrium bioaccumulation factor for radionucilde (i) in pathway (p) expressed as the ratio of the concentration in I ' biota (in pCilkg) to the radionuclide concentration in water (in pCl/ liter), in (pCi/kg)/(pCi/ liter). (Table 3) I D. = is the dose factor specific to a given age group (a), radionuclide (i), pathway (p), and organ G), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem /pCl. (Tables 13-16) Ai
= is the radiological decay constant of radionuclide (i), in hr'.
t, = is the average transit time required for radionuclides to reach the point of exposure. For intemal dose, t is the total time elapsed between release of the radionuclide,s and ingestion of food in hours (Table 17) 1100 = Constant (pCi
- yr
- ft'/Ci
- sec
- L)
[
- 01/98 L
R8
l FORT CALHOUN STATION CH-ODCM-0001 ~ OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 90 OF 129 3.1.1 C. Shoreline Deposits ! R,g = 110,000 U,,FM,W [" Q,7 p D,g[exp(-A,t,)][1-exp(-A f ty] M Where: Rg = is the total annual do:s to organ (i) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrom/yr. U,, = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p), in br/yr. (Table 6)
~
{ M, = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 4) W '
= is the shore-width factor, dimensionless. gTable 17)
F = is the flow rate of the liquid effluent, in ft*/sec. O, = is the annual release rate of radionuclide (I), in Ci/yr. T, * = is the radioactive half life of radionuclide (i), in days.
.D , = 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 (in2 mrern/hr) and the real radionuclide concentration (in pCl/m ). (Table 8)
A = is the radiological decay constant of radionuclide (i), in hrd. t, = is the average transit time required for radionuclides to g reach the point of exposure, in hours. (Table 17) E t, = 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
- ft*)/(Ci
- sec
- L)]
g 01/98 I I R8 l
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 91 OF 129 3.2 Airborne Effluent Dose Calculations - 3.2.1 Noble Gas 10 CFR Part 50, Appendix 1, restricts the dose to individuals in the unrestricted areas from noble gases in airbome effluents from the Fort Calhoun Station to the following limits: During any calendar quarter 55 mrad-gamma air dose 510 mrad-beta air dose and *
- During any calendar year
~ .
$10 mrad-gamma air dose 520 mrac-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:
A. Doses from Noble Gases
- l 1)
Annual Gamma / Beta Air Dose from All Other Noble Gas Releases o,[x/qor,e)(DFj or o$ ov(r.e) or D Nr,e) = 3.17 x to' Where: ' DFi,DFf = are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide (i), in g mrad-m*/pCl-yr. (Table 2) D"(r,0) or D8(r,0) = are the annual gamma and beta air doses at I distance r, in the sector at angle e, from the discharge point, in mradlyr. Qi I = is the annual release rate of radionuclide (i), in Ci/yr. [X/Q] (r,0) = is the annual average gaseous dispersion factor at distance r, in the sector at angle e, in
'~~ "
sec/m*. (Table 4) 3.17x10' = is the number of pCi per Ci divided by the number of seconds per year. 01/98 u R8
I FORT CALHOUN STATION CH-ODCM-0001 gi . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 92 OF 129 5 3.2.1 A. 2) Annual Total Body Dose from All Other Noble Gas Releases D,7(r,0) = S r f Xi(r,0)DFB, g Where: DFB, = is the total body dose factor for a semi-infinite cloud of the radionuclide (i), which includes the attenuation of 2 5 g/cm cf tissue, in mrem-m'/pCl-yr. (Table 2) D!(r,0)
= is the annual total body dose due to immersion in a {
semi-infinite cloud at distance r, in the sector at I angle 0, in mrem /yr. yu(r,0) = is the annual average ground-level concentration of radionuclide (i) at distance r, in the sector at angle 0, l in pCl/m*. (Table 4) S, = Shielding Factor (Table 17) i
- 3) Annual Skin Dose from All Other Noble Gas Releases T
D (r,0) = 1.11 rS f Xfr,0)DFf + f X(/;0)DFS, i l ist i= 1 Where: D!(r,0) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle 6, in mrem /yr. DFS, = is the beta skin dose factor for a semiinfinite cloud of radionuclide (i), in mrem-m'/pCI-yr. (Table 2) 1.11 = is the average ratio of tissue to air energy absorption coefficients. 01 /98
. R8 ll 1
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 93 OF 129 3.2.2 Radiciodine, Tritium, and Particulates 10 CFR Part 50, Appendix 1, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to:
- During any calendar quarter 57.5 mrem to any organ and
- During any calendar year 515 mrem to any organ The dose to an individual from radiciodines, radioactive materials in .
particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airbome effluents released to unrestricted areas should be determined by the following expressions: I I I I I w . [ 01/98 b ' R8
1 FORT CALHOUN STATION I' CH-ODCM-0001 . OFF-SITE DOSE CALCUl.ATION MANUAL REFERENCE USE PAGE 94 OF 129 3.2.2 Radiciodine, Tritium, and Particulates (Continued) NOTE In all cases, for releases of tritium, use the dispersion parameter ) forinhalation (X/Q). 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 0, with respect to the release point, may be determined { by: j j C (r,0) = # I [1-exp( A/)] Where: Ci = is the ground plane enneentration of the radionuclide (i) at distance r, in the sector at angle 0, from the release point, in pCl/m2. Q, = is the annual release rate of radicquelide (i) to the atmosphere, in Cl/yr.
- t. = is the time period over which the ac' umulation is evaluated, which is assumed to be 15 years (n.id-point of plant operating life). (Table 17) 5,(r,0) = is the anriual average relative deposition of radionuclide (i) st distance r, in the sector at angle 6, considering depletion lu of the plume by deposition during transport, in m.2. Table 4 Ai
= is the radiological decay constant for radionuclide (i), in yrd.
1.0x1052 = is the number of pCl/Ci I. I 01/98 R8 l
l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 95 OF 129 4 3.2.2 A. The annual organ dose is then calculated using the following equation: O D$(r,8) 1
= 8760 S f C (r,0)DFG, f
11 I Where: l C}r,0) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle 8, in pCi/m2, l DFG y = is the open field ground plane dose conversion factor for organ 0) from radionuclide (i), in mrem-m /pCI-hr. (Table 8) l - D}r,0) = is the annual dose to the organ 0) at distance r, in the sector at angle 8, in mrem /yr. l
~
S, = is the shielding factor that accounts for the dose reduction due to shielding provided by residential structuras during ' occupancy, dimensionless. (Table 17) I 8760 = is the number of hours in a year B. Annual Dose from Inhalation of Radionuclides in Air
, The annual average airbome concentration of radionuclide (i) at distance r, in the sector at angle 0, with respect to the release point, may be determined as:
X(r,0) i = 3.17 x 104Q,[X/Q) (r,0) Where: Q,
= is the annual releasts rate of radionuclide (i) to the atmosphere, in C1/y.
yq(r,0) = is the annual avers.ge ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle 0, in pCi/m'. [X/Q](r,0) = is the annual 3 average atmosphere dispersion factor, in
.. . _ _ _ . . . . . . . - . . . . - sec/m (see Reg Guide 1.111). This includes depletion (for radiciodines' arid'particulatesTand rsdiological decay of the plume. (Table 4)
{ 3.17x10' = is the number of pCi/Ci divided by the number of sec/yr. 01/9B u RB ,
I i FORT CALHOUN STATION CH-ODCM-0001 g.
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 96 OF 129 I 3.2.2 B.
The annual dose associated with inhalation of all radionuclides to organ (j) of an individual in age group (a), is then: g DJB(r,0) = R, f Xi(r,0) DFA,
- 1. s l
Where: E-D^3(r,0) = is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle 6, due to l e inhalation, in mram/yr. R,
= is the annual air intake for individuals in the age group (a), in m'/yr. (Table 6) I DFA, = is the inhalation dose factor for radionuclide (I), organ (j),
and age group (a), in mrerNpCl. (Tables 9-12) 1 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases l A. Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium l' c[(r,0) dy,e) -
~
* *N + ~"
. exp(-NQ YJe Ph ,
Where: CXr,0)
= is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle 8, in pCl/kg.
d,(r,0) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle 0, in pCl/m2 hr. f ,g, ,,m game e o ap aase . ee- . 01/98
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 97 OF 129 3.2.3 A. The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev.1, Page 1.109-26, Equa. C-6): d,(r,0) = 1.1 x 10 85,(r,0)Qf Where: d,(r,0) = is the deposition rate of radionuclide (i). 5,(r,0)
= is the relative deposition of radionuclide (i), considering depletion and decay, in m 2 (see Reg Guide 1.111).
l (Table 4) 1.1x10' = is the number of pCi/Ci (10 12) divided by the number of l , hours per year (8760). , Q, I = is the annual release rate of radionuclide (i) to the atmosphere, in Cl/yr. I I I I I I - [ [ ... . [ L 01/98 R8 E
FORT CALHOUN STATION CH-ODCM-0001 g
. OFF-SITE DOSE CALCULATION MANUAL SEFERENCE USE PAGE 98 OF 129 3.2.3 B. For radiolodines, the model considers only the elemental fraction of the effluent: la d,(r,0) = 5.5 x 10' 5,(r,0) Q, Where:
I. di (r, 0) = The deposition rate of radiciodine (i). 5.5 x 107 = The number of pCl/Ci (1052) divided by the number of hours per year (8760), then multiplied by the amount of radiciodine l emissions considered to be nonelemental (0.5). 5, (r, 0) = The relative deposition of radiciodine (i), considering depletion and decay, in m-2. (Table 4) ; Q, = The totalrate. (elemental and nonelemental) radiciodine (i) u emission r = is the fraction of deposited activity retained on crops, j dimensionless. (Table 17) Ao = is thecrops, from effective in hr'.removal rate constant for radionuclide (i) l{ As= h + A. - A, = 0.0021/hr. (Tr.Jole 17)
- t, = l 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) By = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pul/ kg (wet weight) per pC1/kg dry soll. (Table 5) Ai = is the radiological decay constant of radionuclide (l), in br' I
- t. =
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 soi.l, in kg (dry soil)/m2, t, =
is the holdup time that represents the time interval between harvest and consumption of the food, in hours. (Table 17) l 01/98l R8
FOFF-SITE DOSE CA FORT CALHOUN STATION CH-ODCM-0001 PAGE 99 OF 129 Different values for the parameters t , Y, and to, 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. 3.2.2 C. Parameters for Calculating the Concentration of Radionuclide (i) in the ' Animal's Feed (Milk Cow, Beef Cow, and Goat) c{(r,e) = f/[r,e) + 0-f,)cf(r,e) f,0-f,)cjt.e) Where: -
~
CY(r,0) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. CRr,8) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3C with t3=0), in pCi/kg. CI(r,0)
= is the concentration of radionuclide (i) in stored feeds I (calculated using Equation 3.2.3C with tn=90 days), in pCI/kg.
f, I = 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 I animal grazes on pasture. (Table 17) I I [ . 01/98 RB
FORT CALHOUN STATION CH-ODCM-0001 g OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 100 OF 129 5 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk C (r,0) = E Cf(r,0)Qg exM-y) C7(r,0) = is the concentration of radionuclide (i) in milk, in pCl/ liter. l CY (r,0) = is the concentration of radionuclide (i) in the animal's feed, in a PCi/kg. l F,,, = 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)
Q, = is the amount of feed consumed by the animal per day, in kg/ day. (Table 7) l t, = 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) 4 = is the radiological decay constant of radionuclide (i), in days". 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium ((r,0) = F,Cf(r,0)Og exp(-4t) Where: C5(r,8) = is the concentration of radionuclide (i) in meat, in pCl/ liter. F, = 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) 1 m,.g, I R8 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL . REFERENCE USE PAGE 101 OF 129 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. 7 Chr,e) = 3.17 x 10 q Wol (r.0) (0.75) (0.5) = 1.2 7x 10 q Wo] (r.0) 2 H H _ c." Where Cl(r,0) = is the concentration of Tritium in vegetation grown at distance r, in the sector at angle 8, in pCl/kg. H = is the absolute humidity of the atmosphere at distance r, in the sector at angle 8, in g/m3 . H=8 gm/kg. Or = is the annual release rate of Tritium, in Ci/yr. g [X/Q](r,0) = is the atmospheric dispersion factor, in sec/m8 . (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. I 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ G) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by:
- D$t,0) j = f DF/,, U f,Cf(r,0) + C (r,0) + U,FC (r,0) + Uff,Cj(r,0) i D%(r,0) = is the annual dose to organ 0) of an indivmual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem /yr.
F DFi g = is the dose conversion factor for the ingestion of L radionuclide (i), organ 0), and age group -(a)'~ in mrem /pCI. , Tables 13-16. b F 01/98 ~ RB
I FORT CALHOUN STATION CH ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USEPAGE 102 OF 129 g U!,U"
= are the ingestion rates of prdduce (non-leafy vegetables, 3 fruits, and grains); milk, meat, and leafy U U E respectively for individuals in age group (al),.
(Table 6) I vege Values of F, and f, are 0.76 and 1.0, respectively. 3.2.7 B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce) Vegetation for Radionuclide (i) to Each Organ 0) and Age Group (a) L f(r,@ = oft, t};rp,gzgy , y y,cfg,,gy Where:
- D$(r,0) = is the annual dose from the ingestion of radionuclide (i) to organ 0) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem /yr.
DFI, = is the dose conversion factor for the ingestion of radionuclide (i), organ G), and age group (a), in mrem /pci. Tables 13-16 U!,U!
= are the ingestion rates ofleafy vegetabics and produce (non-leafy vegetables, fruits, and grains), for individuals in age group (a), in kglyr. (Tabis 6)
'Ci = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
C7 = is the concentration of radionuclide (i) in and on produce, in pCilkg.
- e. ee emer
- _ g I
RB
1 [ FORT CALHOUN STATION CH-ODCM-0001 OFC-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 103 OF 129 [ 3.2.7 C, Calcu!ation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ 0), and Age Group (a) Of(r,@=OFI,, Cf(r@ , ( Where: ( "' D$(r,0) = 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 cow milk, in ( mrem /yr. DFI, = is the dose conversion factor for the ingestion of (
- radionuclide (i), organ 0), and age group (a), in mrem /pcl.
(Tables 13-16) [ UT = is the ingestion rate of cow milk for individuals in age group (a), in t/yr. (Table 6) [ C7 = is the radionuclide concentration in cow milk, in pCi/kg. Equation 3.2.4 3.2.7 D. Calculation Determining the ingested Dose from Meat for Radionuclide
, (i) to Organ 0) and Age Group (a)
D (r,0) = DFly, (r,0) Where: r l Df,(r,0) = 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 mrom/yr. DFI, = is the dose conversion factor for the ingestion of ( radionuclide (i), organ 0), and age group (a), in mrem /pCi. (Tables 13-16) Ul = is the ingestion rate of meat for individ:' in age group (a), [ . . _ _ - . _ . _ . . . . . . . .
. _ .in kgtyr--(Tablev -- ' " --- '"- -- ~
CI = is the radionuclide (i) concentration in meat, in pCi/kg. { 01/98 M
' FORT CALHOUN STATION CH-ODCM-0001 E , OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 104 OF 129 5 4.
LOWER LIMIT OF DETECTION O I r)) 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 g smallest concentration of radioactive material in a sample that will yield a net count, above l 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: uo. 4.66 . s. E=V D = Y = exp(-4t) Where: 49 (~~ M 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 l Sb= the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute h 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
-tm ) = the radioactive decay constant for the particular radionuclide 1
at = the elapsed time between the midpoint of sample collection and time of coualing 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 perforTned on a periodic basis. This determination is to ensur0 that
~ the counting system is able to detect levels of radiation at the LLD values for the specific.
~
type of anla9sifrequir'ed. They willbb' performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample. 01/98 RB l
I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 105 OF 129 Table 2 " Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases
- Nuclide S-Air' (Dff) 2 S-Skin (DFS)- y-Air' (DfT) y-Body (DFB,)
Kr-83m l 2.88E-04 - 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 l 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 1.47E-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-131m 1.11 E-03 4.67E-04 1.56E-04 9.15E-05
, Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51 E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 l 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51 E-03 1.42E-03 l Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 mrad - m3 8 9C1 - yr miem - m*
- 2.88EN= 2.88 x 10d l
1 l l l l .
. I FORT CALHOUN STATION CH-ODCM-0001 g' . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 106 OF 129 5 Table 3 ' Bioaccumulation Factors" g (pCilkg per pCilliter) l FRESHWATER Element Fish invertebrate I
H 9.0E-01 9.0E-01 . C 4.6E+03 9.1E+03 Na 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 Cr 2.0E+02 2.0E+03 i Mn 4.0E+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.0E+01 2.0E+02 Ni 1.0E+02 ' 1.0E+02 Cu 5.0E+01 4.0E+02 Zn 2.0E+03 1.0E+04 Br 4.2E+02 3.3E+02 l Rb 2.0E+03 1.0E+03 Sr 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+0J Zr 3.3E+00 6.7E+00 l Nb 3.0E+04 ' 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.5E+01 5.0E+00 Ru 1.0E+01 3.0E+02 : Rh 1 OE+01 Te 4.0E+02 3.0E+02 6.1E+03 l1 1 1.5E+01 5.0E+00 Cs 2.0E+03 1.0E+03 Ba 4.0E+00 . 2.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+00 1.0E+03 l Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 . . . . . . . _ . - - - _,_...W_...._.. ..
. .... -t2E+03- - - - - - - - - -
1.0E+01" Np 1.0E+01 4.0E+02 , R8
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 107 OF 129 Table 4 " Controlling Locations, Pathways And Atmospheric Dispersion for Dose Calculations
- Atmospheric bispersion*
- X/Q D/Q Controlling {X/Q (r,0)}
Location Pathway (s) Age Group {5(r8)} (sec/m ) (m ) Unrestricted Noble Gases Area Boundary Direct Exposure N/A 9.53E-06 N/A Unrestricted Infant / Area Boundary inhalation Child 9.53E-06 N/A Unrestricted Gamma-Air Area Boundary ' Beta-Air N/A
, 9.53E-06 N/A
' Milk, Ground Plane, E. Ellis Farm', Meat, inhalation, & Infant /
0.74 miles S Vegetation Child 9.53E-06 1.70E-08 Site Discharge Liquid N/A Mixing Ratio, M, 7.14 M.U.D. Intake Liquid N/A Mixing Ratio, M, 30.8 I area dose during the reporting period.3 year average of 9.53E-06,10% sh i a Location is subject to change depending on the results of the Land Use Survey performed l cnnually in accordance with Part 11, Section 5.4. Values listed are used for calculating dose during the annual reporting period (i.e. qu l dose estimates). The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating dose.
~
I 9 { 01/98 R8
q
~
I FORT CALHOUN STATION CH-ODCM-0001 g
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 108 OF 129 E Table 5 " Stable Element Transfer Data' B, F,,, (cow)
Element F, Veo/ Soil Milk (d/M Meat (d/ko) 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 4.0E-02 3.0E-02 P 1.1E+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni - 1.9E-02 6.7E-03' 5.3E-02 Cu 1.2E-01 1.4 E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 Sr 1.7E-02 8.0E-04 3.1 E-02 6.0E-04 l Y l 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 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E+1 1.0E-02 1.5E-03 - Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E+00 1.0E-03 7.7E-02 1 2.0E-02 6.0E-03 2.9E-03 Cs 1.0E-02 1.2E 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 i 5.0E-06 2.0E-04 l Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 Nd W- '- ~ 2.4E-03
~
5.0E-06 5.0E-06 4.7E-03 3.3E-03 l : 1'.8E 02'
'3.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04 01/98 l
RB
FORT CALHOUN STATION 1 CH-ODCM-O'V" OFF-SITE DOSE CALCULATICN MANUAL REFERENCE USE: PAGE 109 OF 1.. / ; Table 6 " Recommended Values for U to Be Used for the Maximum Exposed Individualin ! Lieu oISite Specific Data' Pathway _ in.fant Chi!d Teen A_qlyJLt Fruits, vegetables, & grain (kglyr) - 520 630 520 Leafy vegetables (kglyr) - 26 42 64 Milk (flyr) 330 330 400 310 Meat & poultry (kg/yr) --
, 41 65 110 Fish (fresh or salt)
(kg/yr) - 6.9 16 21 O therSeafood(kg/yr) - 1.7 3.8 1 Drinking water (flyr) 5 330 510 510 730 l (Shoreline hr/yr) recreation - ' 14 67 *i2 l Inhalation (m'/yr) 1400 3700 8000 8000 Table 7 " Animal Consumption Rates" I Q, Om Animal Feed or Forage Water TKa/ day (wet weich)1 (t/dav) Milk Cow 50 60 Beef Cattle 50 50 [ Goats 6 8 { _. 01/98 - R8
FORT CALHOUN STATION CH-ODCM-0D01 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 110 OF 129 Table 8 *Extemal Dose Factors for Standing on Contaminated Ground" (mrem /hr per pCl/ma) 3 a Page 1 of 2 ELEMEN7 TOTAL BODY SKIN
~
C-14
~
Na-24 2.b-08 2.90E-08 P-n _
~
Cr-51 i 220E-10 2.60E-10 Mn-54 5.80E.09 6.80E-09 Mn-58 1.10E-08 . 1.30E-08 Fe-55 Fe-59 . 8.00E-09 9.40E-09 Co-58 7.00E-09 820E-09 Co40 1.70E-08 2.00E-06 NMi3 Nr.65 3.70E-09 4.30E-09 Cu44 1.50E-09 1.70E-09 Zn45 4.00E-09 4.60E-09 Zn-89 Br-83 6.40E-11 930E-11 Br-84 120E-08 1.40E-08 Br-85 - Rt>86 6.30E-10 720E-10 Rt>88 3.50E-09 4.00E-09 Rt> 89 1.50E 08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 j 7.10E-09 , 8.30E 09 Sr-92 9.00E 09 1.00E-08 Y-90 220E-12 2.60E-12 Y-91M 3.80E-09 4.40E-03 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E 09 Zr-97 5.50E-09
, 6.40E-09,,
Ns95 5.10E-09 6.00E-09 Mo-99 1.90E-09 220E-09 Tc-99M 9.60E-10 1.10E-09 ' 01/98 I RB
{ FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 111 OF 129 { Table 8 (Continued) ' Page 2 Of 2 [ ELEMENT TOTAL BODY 1 SKIN Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E 09 420E-09 Ru-105 { 4.50E 09 5.10E-09 Ru-106 1.50E 09 1.80E-09 A9-110M 1.80E-08 2.10E-08 To-125M 3.50E-11 4.80E-11 To 127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 f Te-129M 7.70E-10 9.00E-10 Te-129 , 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 To-131 220E-09 2.60E-08 To-132 1.70E-09 2.00E-09 l-130 1.40E-08 1.70E-08 L131 2.80E-09 3.40E-09 l-132
- 1.70E-06 2.00E-08 1133 3.70E-09 4.50E-09 l-134 1.60E-08 1.90E-08 l-135 1.20E-08 1.40E-08 Cs-134 120E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 420E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E49 2.70E-09 Ba-140 2.10E49 2.40E-09 Be-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Co-141 5.50E-10 620E-10 Ce-143 220E-09 2.50E-09 Co-144 320E-10 3.70E-10 Pr-143 -
.. .. .P,,[-1,,4, 4,, , , ._ , . , , , , , ,, , _ ,
2.00E-10__ __ . . _ _ _ .. . . . _ _ . . 2.30E-10 Nd-147 1.00E-09 120E-09 W-187 3.10E-09 3.60E-09 NP-239 9.50E-10 1.10E-09 01/98 R8 {
FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 112 OF 129 g
Table 9 " Inhalation Dose Factors for Adult" 3 (mrom perpCiinhaled) Page 1 of 2 E Nuclide Bone Uver T. Body Thyroid Kidney Luna 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 4.2GE-07 4.26E-07 426E-07 4.26E-97 Na-24 P-32 Cr-51 1.28E-06 1.65E-04 1.28E-06 9.64E-06 1.28E-06 6.26E-06 1.25E-08 1.28E-06 7.44E-09 1.28E-06 2.85E-09 1.2BE46 1.28E-06 1.08E-05 l 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 Fe-59 9.01E-06 7.54E-07 1.47E-06 3.47E-06 1.32E-06 - - 1.27E-04 2.35E-05 Co-58 - 1.9BE-07 2.59E-07 - - 1.16E-04 1.33E-05 Co-60 - 1.44E-06 1.85E-06 Ni-63 7.46E-04 3.56E ' ' 5.40E-05 3.93E-06 1.81E-06 2.23E-05 Ni-65 1.67E-E 3 1.92E-10 2.62E-11 1.14E-11 7.00E-07 1.54E-06 Cu-64 - 1.83E-10 m 7.69E-11 - 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 ' 5.82E-06 8.62E-06 Zn-69 1.08E 04 6.68E-06 g 4.23E-12 8.14E-12 5.65E-13 Br-83 -- - 3.01E-08 5.27E-12 1.15E-07 2.04E-09 g Br-84 2.90E-08 3.91 E-08 - - - 2.05E-13 Br-85 - - 1.60E-09 - - - - Rb-86 - 1.69E-05 7.37E-06 - Rb-88 2.08E-Ob 4.84E-08 2.41 E-08 - - - 4.18E-19 . P,b-89 2.12E-08 l
~3.20E-08 - - -
i.16E-21 ' Sr-89 3.80E-05 - 1.09E-06 Sr-90 1.75E-04 4.37E-05 3.59E-03 - 7.21E-05 - 1.20E-03 Sr-91 9.02E-05 7.74E-09 - 3.13E-10 4.56E-06 Sr-92 2.39E-05 8.43E-10 - 3.64E-11 2.06E-06 Y-90 5.38E-06 2.61EO7 - 7.01E-09 - 2.12E.05 Y-91M 6.32E-05 3.26E-11 - 1.27E-12 Y-91 5.78E-05 - 1.55E-06 2.40E-07 1.66E-10 g Y-92 1.29E-09 2.13E-04 4.81E-05 g 3.77E-11 - - 1.96E-06 9.19E-06 ' Y-93 1.18E-08 - 3.26E-10 Zr-95 6.06E-06 5.27E-05 g 1.34E-05 4.30E-06 2.91E-06 Zr-97 1.21E-08 2.45E-09 1.13E-09 6.77E-06 2.21E 04 1.88E-05 g Nb - 3.71 E-09 9.84E46 6.54E-05 1.76E-06 9.77E-07 5.26E-07 9.67E-07 6.31E-05 1.30E-05 Mo-99 Tc-99M Tc-101 1.29E-13 5.22E-15 1.51E-08 3.64E-13 7.52E-15 2.87E-09 4.63E-12 7.38E-14 3.64E-08 5.52E-12 1.14E-05 9.55E-08 3.10E-05 5.20E-07 l 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91 E-07 - 8.23E-08 7.29E-07 6.31 E-05 1.38E-05 01/98 1 R8
FORT CALHOUN STATION . CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 113 OF 129 Table 9 (Continued) Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI Ru-105 9.88E-11 - 3.89E-11 Ru-106 8.64E-06 1.27E-10 1.37E-06 6.02E-06 1.09E-06 - 1.67E-05 1.17E.03 1.14E-04 Ag-110M 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 1.31E-07 1.55E-06 Te-127M 1.5BE-06 3.92E-05 8.83E-06 7.21 E-07 1.96E-07 4.11E-07 5.72E-06 Te-127 1.75E-10 1.20E-04 1.87E-05 8.03E-11 i Te-129M 1.22E-06 Te-129 6.22E-12 5.84E-07 2.99E-12 3.87E-11 1.98E-07 1.55E-12 1.32E-10 4.30E-07 4.87E-12 6.37E-10 4.57E-06 2.34E-11 8.14E-07 1.45E-04 2.42E-07 7.17E-06 4.79E-05 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 I Te-131 Te-132 1.39E-12 3.25E-0B 7.44E-13 2.69E-08 4.49E-13 2.02E-08 1.17E-12 2.37E-08 5.46E-12 1.82E. V 1.74E-07 3.60E-05 2.30E-09 6.37E-05 l-130 5.72E-07 1.60E-06 6.60E-07 1.42E-04 2.61E. :.: i - 9.61 E-07 l-131 3.15E-06 I l-132 1.45E-07 4.47E-06 4.07E-07 2.56E-06 1.45E-07 1.49E-03 1.43E-05 7.66E-06 6.48E-07 7.85E-07 5.08E-08 l-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 l-134 3.23E-06 - 1.11E-06 8.05E-08 2.16E-07 7.69E-08 I 1-135 Cs-134 3.35E-07 8.73E-07 3.21E-07 3.73E-06 5.60E-05 3.44E-07 1.39E-06 1.26E-10 6.56E-07 4.66E-05 1.06E-04 9.10E-05 - 3.59E-05 Cs-136 4.88E-06 1.22E 05 1.30E-06 1.83E-05 1.38E-05 - 1.07E-05 1.50E-06 Cs-137 5.98E-05 1.46E-06 7.76E-05 5.35E-05 - 2.78E-05 Cs-138 4.14E-08 9.40E-06 1.05E-06 7.76E-08 4.05E-08 - 6.00E-08 Ba-139 1.17E-10 6.07E-09 2.33E-13 8.32E-14 3.42E-12 - 7.78E-14 4.70E-07 1.12E-07 I Ba-140 Ba-141 4.88E-06 1.25E-11
'6.13E-09 9.41E-15 3.21E-07 4.20E-13 2.09E-09 8.75E-15 1.59E-04 2.73E-05 82-142 3.29E-12 2.42E-07 1.45E-17 3.38E-15 2.07E-13 -
2.86E-15 1.49E-07 1.96E-26 i Lo-140 Lo-142 CC-141 4.30E-08 8.54E-11 2.17E-08 3.88E-11 5.73E.09 9.65E-12 1.70E 05 7.91E-07 5.73E-05 2.64E-07 2.49E-06 1.69E-06 1.91E-07 Co-143 7.83E-07 4.52E 05 1.50E-05 2.33E-08 i CO-144 Pr-143 4.29E-04 1.17E-06 1.72E-08 1.79E-04 1.91 E-09 2.30E-05 7.60E-09 1.06E-04 9.97E-06 9.72E-04 2.83E-05 1.02E-04 4.69E-07 5.80E-08 - 2.70E-07 3.51 E-05 Pr-144 3.76E-12 2.50E-05 1.56E-12 1.91 E-13 i Nd-147 W-187 6.59E-07 1.06E-09 7.62E-07 8.85E-10 4.56E-08 8.81E-13 4.45E-07 1.27E-07 2.76E-05 2.69E-18 2.16E-05 3.10E-10 - - 3.C3E-06 1.94E-05 Np-239 2.87E-08 2.54E-08 1.55E-09 8.75E-09 4.70E-06 1.49E-05 1 h 01/98 R8
FORT CALHOUN STATION I CH-ODCM-0001
- OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 114 OF 129 Table 10 " Inhalation Dose Factors for Teenager" (mrom per pCIinhaled) Page 1 of 2 !
Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI H-3 - 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 C-14 3.2SE-06 6.09E-07 6.09E-07 6.09E-07 6.019E-07 6.09E-07 6.03E-07 Na-24 1.72E.06 1.72E-06 l 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 g' P-32 2.36E-04 1.37E-05 8.95E-06 - Cr-51 - 1.16E-05 E 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 -- 6.39E-06 1.05E 06 - 1.59E-06 2.48E-04 8.35E-06 Mn-56 - 2.12E-10 3.15E-11 Fe-55 2.24E-10 1.90E-06 7.18E 06 4.18E-06 2.98E-06 6.93E-07 Fe-59 1.55E-05 7.99E-07 1.99E-06 4.62E-06 1.79E-06 l 1.91E-04 2.23E-05 Co-58 Co-60 Ni-63 7.25E-05 2.59E-07 1.89E-06 5.43E-06 3.47E-07 2.48E-06 2.47E-06 - 1.68E 1.09E-03 3.84E-05 1.19E-05 3.24E-05 1.77E-06 l' Ni-65 2.73E-10 3.66E-11 1.59E-11 Cu-64 1.17E-06 4.59E-06 2.54E-10 1.06E-10 - 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 - 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 1 Br-83 - 7.53E-12 1.98E-07 3.56E-08 ! 4.30E-08 - - - - Ee94 - - 5.41 E-08 - - - - Br-05 - - 2.29E-09 - - - - Rb-86 - 2.38E-05 1.05E-05 - i Rb-88 2.21E-Ou i 6.62E-08 3.40E-08 - - - 3.65E-15 Rb-89 - 4.40E-08 2.91 E-08 - { Sr-89 5.43E-05 4.22E-17 1.56E-06 -
~
3.02E-04 4.64E-05 Sr-90 4.14E-03 - 8.33E-05 Sr-91 1.10E-08 2.06E-03 9.56E-05 4.39E-10 - - 7.59E-06 3.24E-05 Sr-92 Y-90 Y-91M 1.19E-09 3.73E-07 4.63E-11 5.08E-11 1.00E-08 1.77E.12 3.43E-06 3.66E-05 4.00E-07 1.49E-05 6.99E-05 l Y-91 8.26E-05 3.77E-09 2.21 E.06 - - 3.67E-04 5.11E-05 Y-92 1.84E-09 - 5.36E-11 Y-93 1.69E-08 3.35E-06 2.06E-05 4.65E-10 - - 1.04E-05 7.24E-05 Zr-95 1.82E 05 5.73E-06 3.94E-06 Zr-97 8.42E-06 3.36E-04 1.o6E-05 1.72E-08 3.40E-09 1.57E-09 5.15E-09 Nb-95 1.62E-05 7.3:5E-05 2.32E-06 1.29E-06 7.08E-07 Mo-99 1.25E-06 9.39E-05 1.21 E-05 2.11E-08 4.03E-09 - 5.14E-08 1.92E-05 3.36E-05 g' Tc-99M 1.73E-13 4.83E-13 6.24E-12 Tc-101 7.20E-12 1.44E-07 7.66E-07 EI 7.40E-15 1.05E-14 1.03E-13 1.90E-13 Ru-103 8.34E-08 1.09E l 2.63E-07 - 1.12E-07 - 9.29E-07 . . . _ . ~ - - - - . . . . . - . - - - . . - . - . . - - - - - . - - - - - - - - - - 9.79E. -05
~
1.36E-05 i
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 115 OF 129 Table 10 (Continued) Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI Ru-105 1.40E-10 - 5.42E-11 P Rv-106 1.76E-10 2.27E-06 1.13E 05 1.23E-05 -- 1.55E-06 Ag-110M 1.73E-06 2.38E-05 2.01E-03 1.20E44 1.64E-06 9.99E-07 - 3.13E-06 8.44E-04 3.41 E-05 I Te-125M 6.10E-07 Te-127M 2.25E-06 Te-127 2.80E-07 1.02E-06 8.34E-08 2.73E 07 1.75E47 5.48E 07 8.17E-06 6.70E-05 2.07E-04 9.38E-06 1.99E-05 2.51E-10 1.1(E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 I Te-129 8.87E-12 Te-131M 1.23E-08 8.23E-07 4.22E-12 2.81 E-07 2.20E-12 5.72E-07 6.48E-12 6.49E-06 3.32E-11 2.47E-04 4.12E-07 5.06E-05 2.02E-07 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 Te-131 1.97E-12 2.97E-05 7.76E-05 1.04E-12 6.30E-13 I Te-132 4.50E-08' l-130 7.80E-07 3.63E-08 2.24E-06 2.74E-08 1.55E-12 3.07E-08 7.72E-12 2.44E-07 2.92E-07 5.61E-05 1.89E-09 5.79E-05 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 l l-132 l-133 1.99E-07 1.52E-06 5.47E-07 2.56E-06 1.97E-07 7.78E 07 1.89E-05 3.65E-04 1.05E-05 8.65E-07 8.11E-07 1.59E-07 l-134 4.49E-06 - 1.29E-05 1.11E-07 2.90E.07 1.05E-07 4.94E-06 4.58E-07 2.55E-09 I l-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 - 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 Cs-136 6.44E-06 4.69E-05 1.83E-05 1.22E-06 2.42E 05 1.71E-05 - 1.38E-05 2.22E-06 1.36E-06 I Cs-137 Cs-138 Ba-139 8.38E-05 5.82E-08 1.06E-04 1.07E-07 3.89E-05 5.58E-08 - 3.80E-05 8.28E-08 1.51 E-05 9.84E-09 1.06E-06 3.38E-11 1.67E-10 1.18E-13 4.87E-12 Ba-140 6.84E-06 1.11E-13 8.08E-07 8.06E-07 I Ba-141 1.78E-11 Ba-142 4.62E-12
'8.38E-09 1.32E-14 4.63E-15 4.40E-07 5.93E-13 -
2.85E-09 1.23E-14 2.54E-04 4.11 E-07 2.86E-05 9.33E-14 2.84E-13 - 3.92E-15 2.39E-07 5.99E-20 LO-140 5.99E-08 2.95E-08 7.82E-09 I LO-142. 1.20E-10 2.68E-05 6.09E-05 5.31 E-11 1.32E-11 - Co-141 3.55E-06 1.27E-06 1.50E-06 2.37E-06 2.71E-07 - 1.11 E-06 Ce-143 3.32E-OS 7.67E-05 1.58E-05 2.42E-08 2.70E-09 - 1.08E-OB 1.63E-05 3.19E-05 I C@-144 Pr-143 6.11 E-04 1.67E-06 2.53E-04 6.64E-07 3.28E-05 8.28E-08 1.51E-04 1.67E-03 1.08E-04 Pr-144 3.86E-07 6.04E-05 ~ 2.67E-05 5.37E-12 2.20E-12 2.72E-13 Nd-147 1.26E-12 2.19E-07 2.94E-14 9.83E 07 I W-187 1.50E-09 1.07E-06 1.22E-09 6.41E-08 4.29E-10 6.28E-07 4.65E-05 2.28E-05 i Np-239 4.23E-08 5.92E-06 2.21E-05 i 3.60E-08 2.21E-09 - 1.25E-08 8.11E-06 1.65E-05 I b [ 01/98 s R8
l FORT CALHOUN STATION CH-ODCM-0001 l , OFF-SITE DOSE CALCUl.ATION MANUAL REFERENCE USE PAGE 116 OF 129 i Table 11 ' Inhalation Dose Factors for Child" Nuclide Bone Liver (mrom perpCiinhaled) T. Body Thyroid _ Kidney Luno Page 1 of 2 GI-LLI l 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-03 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-L 7.04E-04 3.09E-05 2.67E-05 - E CFM - 4.17E-08 1.14E-05 E 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 -- 1.16E-05 2.57E-06 Mn-56 2.71E-06 4.26E-04 6.19E-06 g 4.48E-10 8.43E-11 Fe-55 1.28E-05 6.80F.-06 2.10E-06 4.52E-10 3.55E-06 3.33E-05 g Fe-59 5.59E-06 3.00E-05 7.75E-07 9.04$-06 4.51E-06 - - 3.43E-04 1.91E-05 Co-58 - 4.79E-07 8.55E-07 Co-60 - 2.99E-04 9.29E-06 3.55E-06 6.12E-06 - - 1.91E 03 2.60E-05 Ni-63 2.22E-04 1.25E 05 7.56E-06 l Ni-65 8.08E-10 7.43E-05 1.71E-06 7.99E-11 4.44E-11 - - 2.21 E-06 2.27E-05 Cu-64 Zn-65 1.15E 05 5.39E-10 3.06E-05 2.90E-10 1.90E-05 1.63E-09 2.59E-06 9.92E-06 lll' Zn-69 1.93E-05 2.69E-04 4.41E-06 1.81E-11 2.61E-11 2.41E-12 1.58E-11 Br-83 - 3.84E-07 2.75E-06 1.2BE-07 - - - - Br-84 - - 1.48E-07 - - - - Br-85 - - 6.84E-09 - - - Rb 86 - 5.36E-05 3.09E-05 - E Rb-88 - 1.52E-07 9.90E-G8 - - 2.16E-Ob 5 Rb-89 - 4.66E-00
~9.33E-08 7.85E-08 - - -
5.11E-10 Sr-89 1.62E-04 - 4.66E-06 E Sr-90 5.83E-04 4.52E-05 E 1.04E-02 - 2.07E-04 Sr-91 3.99E-03 9.28E-05 3.28E-08 - 1.24E-09 - - 1.44E-05 4.70E-05 Sr-92 Y-90 Y-91M 3.54E-09 1.11 E-06 1.37E-10 1.42E-10 2.99E-08 4.98E-12 6.49E-06 7.07E-05 7.60E-07 6.55E-05 7.24E-05 l Y-91 2.47E-04 4.64E-07 6.59E-06 - - 7.10E-04 4.97E-05 Y-92 5.50E-09 - 1.57E-10 Y-93 5.04E-08 6.46E-06 6.46E-05 1.38E-09 - - 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 - 1.61 E-05 6.03E-04 1.65E 05 Zr-97 5.07E-08 7.34E-09 4.32E-09 - 1.05E-08 3.06E-05 9.49E-05 g Nb-95 6.35E-06 2.48E-06 1.77E-06 Mo-99 2.33E-06 1.66E-0W 1.00E-05 4.66E-08 1.15E-08 ' - 1.06E-07 3.66E-06 3.42E-05 Tc-99M 4.81E-13 9.41 E-13 1.56E-11 Tc-101 1.37E-11 2.57E-07 1.30E-06 2.19E-14 2.30E-14 2.91 E-13 Ru-103 3.92E-13 1.58E-07 4.41E-09 7.55E-07 - 2.90E-07 1.90E-06 .-- 1.79E 04 1.21E-05 m ,. 3 I R8
FORT CALHOUN STATION CH-ODCM 0001 OFF-SITE DOSE CALCULATION MANUAL ' REFERENCE USE PAGE 117 OF 129 TABLE 11 (Continued) Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI [ 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 Ag-110M 4.56E-06 4.97E-05 3.87E-03 1.16E-04 [ 3.08E-06 2.47E-06 - 5.74E-06 1.48E-03 2.71E-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 Te-127 1.93E 05 { 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71 E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 t Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 [L 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 'E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21 E-06 E-06 2.28E-06 4.99E-04 6.61E-06 - 1.38E-06 [ 1-131 1.30E-05 ' ' 05 7.37E-06 4.39E-03 2.13E-05 l-132 7.68E-07 5.72E-07 . h. 06 5.07E-07 5.23E-05 1.69E-06 l-133 4.48E-06 8.65E-07 5.4 06 2.08E-06 1.04E-03 9.13E-06 - 1.48E-06 ( l-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 - 2.58E-07 l-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 2.81E-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 fL B2-139 4.98E-10 2.66E-13 1.45E-11 - 2.33E-13 1.56E-06 1.56E-05 Br-140 2.00E-05 1.75E-08 1.17E-06 - 5.71 E-09 4.71E-04 2.75E-05 Bs-141 5.29E-11 2.95E-14 1.72E-12 - 2.56E-14 7.89E-07 7.44E-08 Bs-142 1.35E-11 9.73E-15 7.54E-13 ( - 7.87E-15 4.44E-07 7.41E-10 Lo-140 1.74E.07 6.08E-08 2.04E-08 Lc-142 4.94E-05 6.10E-05 3.50E-10 1.11E-10 3.49E-11 - 2.35E-06 Ce-141 - 1.06E-05 2.05E-05 5.28E-06 7.83E-07 - 2.31E-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 Co-144 1.83E-03 5.72E-04 9.77E-05 Pr-143 3.17E-04 3.23E-03 1.05E-04 4.99E-06 1.50E-06 2.47E-07 8.11E-07 Pr-144 1.17E-04 2.63E-05 1.61 E-11 4.99E-12 8.10E-13 Nd-147 2.92E-06 2.64E-12 4.23E-07 5.32E-08 2.36E-06 1.84E-07 - 1.30E-06 8.87E-05 2.22E-05 ! W-187 4.41E-09 2.61 E-09 1.17E-09 Np-239 1.11 E-05 2.46E-05 [ 1.26E-07 8.14E-08 6.35E-09 2.63E-08 1.57E-05 1.73E-05 [ . _ . ... { 01/98 R8 e w r
FORT CALHOUN STATION CH-ODCM-0001 I OFF-SITE DOSE CALCULATION MA!!UAL REFERENCE USE PAGE 118 OF 129 Table 12 " Inhalation Dose Factors for infant" l (mrom per pCiinhaled) Page 1 of 2 Nuclide Bone g Liver _T. Body Thyroid Kidney Luno GI-LLI H-3 - 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 C-14 1.89E-05 3.79E-06 2.63E-07 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54tE-OS 7.54E-06 3.79E-06 P-32 7.54E-06 7.54E-06 7.54E-06 7.54E-06 1.45E-03 8.03E-05 5.53E-05 - - Cr-51 - 1.15E-05 6.39E-08 4.11E-08 9.45E-09 9.17E-06 Mn-54 - 1.81E-05 2.55E-07 3.56E-06 - 3.56E-06 7.14E-04 Ma-56 5.04E-06 1.10E-09 l 1.58E-10 - 7.86E-10 8.95E 06 Fe-55 1.41 E-05 8.39E-06 5.12E-05 2.38E-06 - - 6.21E-05 Fe-59 9.69E-06 1.68E-05 7.82E-07 6.77E-06 - - 7.25E 04 Co-58 - 8.71 E-07 1.77E-05 1.30E-06 - - 5.55E 04 Co 60 - - 5.73E-06 7.95E-06 I 8.41E-06 - - 3.22E-03 Ni-63 2.42E-04 1.46E-05 2.28E-05 8.29E-06 - - 1.49E-04 Ni-65 1.71E-09 2.03E-10 1.73E-06 i 8.79E-11 - - 5.80E-06 Cu 64 - 1.34E-09 3.58E-05 5.53E-10 - 2.84E-09 6.64E-06 Zn-65 1.38E-05 4.47E-05 1.07E-05 2.22E-05 - 2.32E-05 4.62E-04 Zn-69 3.85E-11 6.91E-11 3.67E-05 5.13E-12 - 2.87E-11 1.05E-06 Br-83 - 9.44E-06 E 2.72E-07 - - Br-84 - - 2.86E-07 - . - E Br-85 - 1.46E-08 - Rb-86 - 1.36E-04 6.30E-05 - Rb-88 - 3.98E-07 2.17E-06 2.05E-07 -- - Rb-89 - 2.42E-07
'2.29E-07 1.47E-07 - -
Sr-89 - 4.87E-08 Sr-90 Sr-91 2.84E-04 1.11E-02 6.83E-08 - 8.15E-06 2.23E-04 2.47E-09 1.45E-03 8.03E-03 4.57E-05 9.36E-05 l Sr-92 /.50E-09 3.7d-05 5.24E-05 2.79E-10 - - 1.70E-05 Y-90 2.35E-06 1.00E-04 6.30E-08 - - 1.92E-04 Y-91M 2.91E-10 7.43E-05 9.90E-12 - - 1.99E-06 Y-91 4.20E-04 1.68E-06 1.12E 05 - - 1.75E-03 Y-92 1.17E-08 5.02E-05 3.29E-10 - 1.75E 05 Y-93 1.07E-07 9.04E-05 2.91 E-09 - 5.46E-05 1 Zr-95 8.24E 05 1.99E-05 1.19E-04 ' 1.45E-05 - 2.22E-05 1.25E-03 Zr-97 1.07E-07 1.83E-08 1.55E-05 E 8.36E-09 - 1.85E-08 7.88E 05 Nb-95 1.12E-05 4.59E-06 1.00E-04 m 2.70E-06 - 3.37E-06 3.42E-04 9.05E 06 Mo-99 - 1.18E-07 2.31 E-08 Tc-99M 1.89E-07 9.63E-05 3.48E-05 gl 9.98E-13 2.06E-12 2.66E-11 Tc-101 4.65E-14 2.22E-11 5.79E-07 1.45E-06 gi 5.88E-14 5.80E-13 - 6.99E-13 Ru-103 1.44E-06 4.17E-07 6.03E 1 4.85E-07 - 3.03E-06 1.15E-05 _ 3.94.E-04 01/98 R8
_ _----~~~ FORT CALHOUN STATION CH-ODCM.0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCEjlgf, PAGE 119 OF 129 Table 12 (Continusd) Page 2 of2 Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI Ru-105 8.74E-10 - Ru-106 6.20E-05 2.93E-10 - 6.42E-10 7,77E-06 1.12E-05 3.46E-05 Ag-110M 7.13E-06 5.16E-06 7.61E-05 8.26E-03 1.17E-04 3.57E-06 - 7.80E-06 Te-125M 3.40E-06 1.42E-06 4.70E-07 2.62E-03 2.36E-05 Te-127M 1.19E-05 1.16E-06 - 3.19E-04 4.93E-06 1.48E-06 3.48E-06 9.22E 06 Te-127 1.59E-09 6.81 E-10 2.68E-05 9.37E-04 1.95E-05 3.40E-10 1.32E-09 3.47E-09 Te-129M 1.01E-05 4.35E-06 1.59E-06 7.39E-06 1.745-05 Te-129 5.63E-11 3.91 E-06 2.27E-05 1.20E-03 2.48E-11 1.34E-11 4.93E-05 Te-131M 7.62E-08 4.82E-11 1.25E-10 2.14E-06 3.93E-08 2.59E-08 6.38E-08 1.88E-05 Te-131 1.24E-11 1.89E-07 1.42E-04 8.51E-05 5.87E-12 3.57E-12 1.13E-11 Te-132 2.66E 07 1.69E-07 2.85E-11 1.47E!-06 5.87E-06 l-130 1.26E-07 1.99E-07 7.39E-07 4.54E-06 9.91 E-06 3.98E-06 2.432-04 3.15E-05 l-131 2.71E-05 1.14E-03 1.09E-05 3.17E-05 1.40E-05 1.06E-02 1.42E-06 l-132 1.21E-06 2.53E-06 3.70E-05 - 7.56E 07 l-133 8.99E-07 1.21E-04 2.82E-06 9.46E-06 1.37E-05 4.00E-06 1.36E-06 I-134 6.58E-07 2.54E-03 1.60E-05 - 1.34E-06 4.75E-07 3.18E-05 1.54E-06 l-135 2.76E-06 1.49E-06 - 5.43E-06 1.98E-06 4.97E-04 9.21E-07 Cs-134 2.83E-04 5.02E-04 6.05E-06 - 1.31E-06 Cs-136 3.45E-05 5.32E-05 - 1.36E-04 9.61E-05 3.78E-05 - 5.69E-05 9.53E-07 CP-137 3.92E-04 4.37E-04 4.03E-05 8.40E-06 3.25E-05 1.32E-06 Cs-138 3.61 E-07 5.58E-07 1.23E-04 0.09E-05 2.84E-07 9.53E-07 B:-139 1.06E-09 7.03E-13 2.93E-07 4.67E-08 6.26E-07 B:-140 4.00E-05 3.07E-11 -
'4.00E-08 4.23E-13 4.25E-06 3.64E-05 BS-141 2.07E-06 -
9.59E-09 1.12E-10 7.70E-14 3.55E-12 1.14E-03 2.74E-05 Bn-142 2.64E-11 2.36E-14 4.64E-14 2.12E-06 3.39E-06 Lc-140 1.40E-12 - 1.36E-14 3.61E-07 1.43E-07 3.68E-08 1.11E-06 4.95E-07 La-142 7.36E-10 2.69E-10 1.20E-04 6.06E-05 C2-141 6.46E-11 - 1.98E-05 1.19E-05 1.42E-06 --- 5.87E-06 4.25E-05 C2-143 2.09E-07 1.38E-07 3.75E-06 3.69E-04 1.54E-05 CO-144 2.28E-03 1.58E-08 - 8.65E-04 4.03E-08 8.30E-05 3.55E-05 Pr-143 1.26E-04 1.00E-05 3.74E-06
, 3.84E-04 7.03E-03 1.06E-04 Pr-144 4.99E-07 --
1.41E-06 3.42E-11 1.32E-11 1.72E-12 3.09E-04 2.66E-05 Nd-147 5.67E-06 - 4.80E-12 1.15E-06 5.81E-06 3.57E-07 3.06E-06 W-187 9.26E-09 6.44E-09 2.25E-06 2.30E-04 Np-239 2.65E-07 2.23E-09 - 2.23E-05 l 2.13E-07 1.34E-08 - 2.83E-05 2.54E-05 4.73E-08 4.25E-05 1.78E-05 I L . . . . . . _ . . . . . . . -. . . - . - 01/a8 R8
FORT CALHOUN STATION CH-ODCM-0001
. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 120 OF 129 Table 13 " Ingestion Dose Factors fcir Adult" (mrem per pCiingested) Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidnev Luna 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 P-32 1.93E-04 1.20E-05 1.70E-06 1.70E-06 1.70E-06 g 7.46E-06 - - - 2.17E-05 5
.Cr-51 - -
2.66E-09 1.59E-09 5.86E-10 Mn-54 3.53E-09 6.69E-07 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 Fe-59 1.06E-06 1.09E-06 4.34E-06 1.02E-05 3.91 E-06 - 2.85E-06 Co-58 3.40E-05 7.45E-07 1.67E-06 - - - 1.51E 05 Co-60 - 2.14E-06 4.72E-06 - Ni-63 4.02E-05 1.30E-04 9.01E-06 4.36E-06 - Ni-65 1.88E-06 5.28E-07 6.86E-08 3.13E-08 - Cu-64 1.74E-06 8.33E-08 3.91E-08 - 2.10E-07 - 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 - 1.03E-05 - 9.70E-06 Zn49 1.03E-08 1.97E-08 1.37E-09 1.28E-08 Br-83 2.96E-09 4.02E-08 - - - 5.79E-08 Br-84 - - 5.21 E-08 Br-85 4.09E-13 2.14E-09 - - - - Rb-86 - 2.11 E-05 9.83E-06 Rb-88 4.16E-06 6.05E-08 3.21E-08 - - - 8.36E-19 Rb-89 - 4.01 E-08 2.82E-08 - Sr-89 2.33E-21 3.08E-04 - 8.84E-06 - Sr-90 4.94E-05 8.71 E-03 - 1.75E-04 Sr-91 5.67E-06 2.19E-04 2.29E-07 - - - 2.70E-05 Sr-92 2.15E-0G - 9.30E-08 ! Y-90 9.62E-09 4.26E-05 2.58E-10 - - - 1.02E-04 Y-91M 9.09E-11 - 3.52E-12 - Y-91 1.41E-07 2.67E-10 3.77E-09 - - - 7.76E 05 Y-92 8.45E-10 - 2.47E-17 - Y-93 2.68E-09 1.48E-05 7.40E-11 - - - 8.50E-05 Zr-95 ' 3.04E-08 9.75E-09 6.60E-09 - 1.53E-08 - 3.09E-05 Zr-97 1.6BE-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 - 2.10E-05 l Mo-99 - 4.31E-06 8.20E-07 - 9.76E-06 - 9.99E-06 3i Tc-99M 2.47E-10 6.98E-10 8.89E-09 1.06E-08 Tc-101 3.42E-10 4.13E 07 E 2.54E-10 3.66E-10 3.59E-09 - 6.59E-09 1.87E-10 P 5103 1.10E-21 ' 1.85E-07 - 7.06E-07 7.97E .08 2.16E-05 su g! 1 01 /9 8 I R8 I
- - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - ~ - - - ~
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 121 OF 129 Table 13 (Continued) Page 2 of 2 : Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI Ru-105 1.54E-08 - 6.08E-09 Ru-106 2.75E-06 1.99E-07 - 9.42E 06 3.48E-07 - 5.31E-06 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 Te-125M 2.68E-06 2.91E-07 - 6.04E-05 9.71E-07 3.59E-07 8.06E-07 1.09E-05 Te-127M 6.77E-06 2.42E-06 1.07E-05 8.25E-07 1.73E-06 2.75E-05 2.27E-05 Te-127 1 10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 - 8.68E-06 Te-129M 1.15E-05 4.29E.06 1.82E-06 3.95E-06 Te-129 3.14E-08 4.80E-05 - 5.79E-05 1.18E-08 7.65E-09 2.41E-08 1.32E-07 Te-131M 1.73E-06 8.46E-07 2.37E-08 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 1.63E-06 1.53E-06 1.80E-06 1.57E-05 7.71E-05 l-130 7.56E-07 2.23E-06 8.80E-07 l-131 1.89E-04 3.48E-06 - 1.92E-06 4.16E-06 5.95E-06 3.41E-06 1.95E-03 l-132 1.02E-05 - 1.57E-06 2.035-07 5.43E-07 1.90E-07 1.90E-05 l-133 1.4M-06 8.65E-07 - 1.02E-07 2.47E-0G 7.53E-07 3.63E-04 4.31E-06 l-134 1.06E-07 2.88E-07 2.22E-06 1.03E-07 4.99E-06 4.58E-07 - 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21 E-04 Cs-136 6.51 E-06 4.79E-05 1.59E-05 2.59E-06 2.57E-05 1.85E-05 1.43E-05 I Cs-137 7.97E-05 1.96E-06 2.92E-06 1.09E-04 7.14E-05 - 3.70E-05 Cs-138 5.52E-08 1.09E-07 1.23E-05 2.11 E-06 5.40E-08 - G.01 E-08 7.91E 09 Ba-139 9.70E-08 6.91E-11 4.65E-13 2.84E-09 - 6.46E-11 3.92E-11 1.72E-07 I Ba-140 2.03E-05 Ba-141 Ba-142 2.13E-08 4.71E-08
~2.55E-08 3.56E-11 2.19E-11 1.33E-06 1.59E-09 1.34E-09 8.67E-09 3.31E-11 1.46E-08 2.02E-11 4.18E-05 2.22E-17 LC-140 2.50E-09 1.85E-11 1.24E-11 3.00E-26 l LC-142 Ce-141 1.28E-10 9.36E-09 1.26E-09 5.82E-11 6.33E-09 3.33E-10 1.45E-11 7.18E-10 -
2.94E-09 9.25E-05 4.25E-07 Ce-143 1.65E-09 1.22E-06 2.42E-05 1.35E-10 I 5.37E-10 Ce-144 4.88E-07 2.04E-07 4.56E-05 2.62E-08 - 1.21 E-07 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 Pr-144 3.01E-11 2.13E-09 - 4.03E-05 1.25E-11 1.53E-12 - 7.05E-12 4.33E-18 I Nd-147 6.29E-09 - 7.27E-09 4.35E-10 - 4.25E-09 W-187 1.03E-07 8.61 E-08 3.49E-05 3.01E-08 - - 2.82E 05 Np-239 1.19E-09 1.17E-10 6.45E-11 - 3.65E-10 - 2.40E-05 I ^
. - . ~ .
k 01 /98 R8 L e
-u. _ _ _ _ _ _ _ _ _ _
i l FORT CALHOUN STATION I CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL . REFERENCE USE PAGE 122 OF 129 Table 14 " Ingestion Dose Factors for Teenager" (mrom per pCi Ingested) Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI H-3 - 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E 05 1.07E-05 - - - 2.32E 05 Cr-51 - - 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 - 5.90E-06 1.17E-06 1.76E-06 Mn-56 1.21E-05 g Fe-55 1.58E-07 2.81E-08 - 2.00E-07 - 1.04E-05 g 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 L - 4.32E-06 3.24E-05 Co-58 g 9.72E-07 2.24E-06 - - - 1.34E-05 g Co-60 - 2.81 E-06 6.33E-06 - - - 3.66E-05 Ni-63 1.77E-04 1.25E.05 6.00E-06 - - - 1.99E-06 Ni-65 7.49E-07 9.57E.08 4.36E-08 - - - 5.19E-06 Cu-64 - 1.15E-07 5.41E-08 - 2.91E-07 - 8.92E-06 Zn-65 5.76E-06 2.00E-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 - - - - Sr-84 - - 7.22E-08 - - - - Sr-85 - - 3.05E-09 -- Rb-86 E 2.98E-05 1.40E-05 - - - 4.41E-06 5 Rb-88 - 8.52E-08 4.54E-08 - - - 7.30E-15 Rb-89 3.89E 08 Sr-89 4.40E-04
'5.50E-08 - - .
8.43E-17 g Sr-90 1.26E-05 - - - 5.24E-05 g 1.02E-02 - 2.04E-04 - - - 2.33E-04 Sr-91 8.07E-06 - 3.21E-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-91M 1.29E-10 - 4.93E-12 - - - 6.09E-09 Y-91 Y-92 Y-93 2.01 E-07 1.21 E-09 3.83E-09 5.39E-09 3.50E-11 1.05E-10 8.24E-05 3.32E-05 1.17E-04 l Zr-95 4.12E-08 1.30E-08 8.94E-09 - 1.91 E-08 - 3.00E-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 2.51E-09 - 4.42E-09 - 1.95E-05 Mo-99 6.03E-06 1.15E-06 gI 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 To-101 Ru-103 3.GOE-10 2.55E-07 5.12E-10 5.03E-09 1.09E-07 9.26E-09 8.99E-07 3.12E-10 8.75E 2.13E-05 5{! 01/9s I I i R8 I i I >
b FORT CALHOUN STATION CH-ODCM-0001' - OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 123 OF 129 [ Table 14 (Continued) Page 2 of 2 [ Nuchde Bone Liver T. Body Thyroid Kidney Luna GI-LLI Ru-105 2.18E-08 - 8.46E-09 - 2.75E-07 - 1.76E-05 ( Ru-106 Ag-110M 2.05E-07 3.92E-06 - 4.94E-07 - 7.56E-06 - 1.88E-04 1.94E-07 1.18E-07 - 3.70E 07 Te-125M 3.83E-06 5.45E-05 1.38E 06 5.12E-07 1.07E-06 - Te-127M 9.67E-06 1.13E-05 [ 3.43E-06 1.15E-06 2.30E-06 3.92E-05 To-127 1.58E-07 2.41E 05 5.60E-08 3.40E-08 1.09E-07 6.40E-07 To-129M 1.63E-05 6.05E-06 1.22E-05 2.58E-06 ' 5.26E-06 6.82E-05 - 6.12E-05 [ To-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 l 1.88E-07 - 2.45E-07 Te-131M 2.44E 06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 Te-131 2.79E-08 9.39E-05 1.15E-08 8.72E-09 2.15E-08 1.22E-07 Te-132 3.49E 06 2.21E-06 2.29E-09 2.08E-06 2.33E-06 2.12E-05 - 7.00E 05 l-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 - 2.29E-06 l-131 5.85E-06 8.19E-06 4.40E-06 2.39E 03 1.41E-05 - 1.62E-06 l-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 l-133 1.15E-06 - 3.18E-07 2.01 E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 l-134 1.46E-07 3.87E-07 2.58E-06 1.39E-07 6.45E 06 6.10E-07 - 5.10E-09 l-135 6.10E-07 1.57E-06 ' 5.82E-07 1.01E-04 C -134 8.37E 05 2.48E-06 - 1.74E-06 ( Cs-136 8.59E-06 1.97E-04 9.14E-05 - 6.26E-05 2.39E 05 2.45E-06 3.38E-05 2.27E 05 - 1.84E-05 2.90E-06 Cs-137 1.12E-04 2.72E-06 1.49E-04 5.19E-05 5.07E-05 Cs-138 7.76E-08 1.97E-05 2.12E-06 1.49E-07 ( Ba-139 1.39E-07 9.78E-11 7.45E-08 4.05E-09 1.10E-07 1.28E-08 4.76E-11 Bs-140 2.84E-05 9.22E-11 6.74E-11 1.24E 06
'3.48E-08 1.83E-06 -
1.18E-08 2.34E-08 B0-141 6.71E-08 4.38E-05 5.01 E-11 2.24E-09 - 4.65E-11 B2-142 2.99E-08 3.43E-11 1.43E-13 2.99E-11 1.84E-09 - 2.53E-11 Lc-140 3.48E-09 1.99E-11 9.18E-20 1.71E-09 4.55E-10 - - La-142 1.79E-10 7.95E-11 9.28E-05 1.98E-11 - - - 2.42E-06 Ce-141 1.33E 08 8.88E-09 1.02E-09 Cc-143 2.35E-09 4.18E-09 - 2.54E-05 1.71E 06 1.91E-10 - 7.67E-10 C2-144 6.96E 07 2.88E-07 5.14E 05 3.74E-08 - 1.72E-07 - 1.75E 04 Pr-143 1.31E-08 5.23E-09 6.52E-10 Pr-144 3.04E-09 - 4.31E-05 4.30E-11 1.76E-11 2.18E-12 - 1.01 E-11 Nd-147 9.38E 09 1.02E-08 4.74E-14 6.11E-10 - 5.99E-09 - 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 { Np-239 1.76E-09 3.22E-05 1.66E-10 9.22E-11 - 5.21 E-10 - 2.67E-05 Y 01/98
r j FORT CALHOUN STATION l OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 )
' PAGE 124 OF 129 I Table 15 ' Ingestion Dose Factors for Child" (mrom per pCiingested) Page 1 of 2 Nuclide Bone Liver T. Body h Kidney Luno GI-LLI I H-3 -
1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 C-14 1.21E-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 Cr-51 2.28E-05 { 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 -- 1.07E-05 2.85E-06 3.00E-06 Mn-56 8.98E-06 3.34E-07 7.54E-08 - 4.04E-07 - 4.84E-05 Fe-55 1.15E-05 6.10E-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 Co-60 Ni-63 5.38E-04 1.80E-06 5.29E-06 2.88E-05 5.51E-06 1.56E-05 1.83E-05 1.05E-05 2.93E-05 1.94E-06 l NM5 2.22E-06 2.09E-07 1.22E-07 Cu-64 2.56E-05 2.45E-07 1.48E-07 - S.92E-07 - 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 2.30E-05 Zn-69 6.41E-06 4.38E-08 6.33E-08 5.85E-09 - 3.84E-08 3.99E-06 Br-83 - - 1.71 E-07 E Br-84 E 1.98E-07 - - - - Br-85 - - 9.12E-09 - - - - RL-86 - 6.70E-05 4.12E-05 Rb-88 4.31 E-06 1.90E-07 1.32E-07 - - - 9.32E-09 Rb-89 -
~1.17E-07 1.04E-07 Sr-89 1.02E-09 1.32E-03 ~
3.77E-05 - - - 5.11 E-05 Sr-90 2.56E-02 - 5.15E-04 Sr-91 2.29E-04 2.40E-05 - 9.06E-07 - - 5.30E-05 Sr-92 9.03E-06 - 3.62E-07 - - - 1.71E-04 Y-90 4.11E-08 - 1.10E-09 Y-91M 1.17E-04 3.82E-10 - 1.39E-11 Y-91 7.48E-07 6.02E-07 - 1.61E-08 - - 8.02E-05 g Y-92 3.60E-09 - 1.03E-10 Y-93 1.04E-04 1.14E-08 - 3.13E-10 - - - - 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 Zr-97 3.65E-08 - 2.66E-05 3 6.99E-09 1.01 E-09 5.96E-10 1.45E-09 Nb-95 2.25E-08 1.53E-04 B 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 3.00E-08 - 2.63E-08 9.19E-10 1.03E-06 To-101 1.07E-09 1.12E-09 1.42E-08 , 1.91 E-08 5.92E-10 3.56E-09 I Ru-103 7.31E-07 - 2.81E-07 1.84E-06 .. 1.89E-05 ) l o1/98 g a8 I lu
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 125 OF 129 TABLE 15 (Continued) Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI Ru-105 6.45E-08 - 2.34E-08 - 5.6 7 E -0' 7 Ru-106 1.17E-05 - 4.21E-05 Ag-110M 5.39E-07 1.46E-06 - 1.58E-05 3.64E-07 2.91E-07 1.82E-04 Te-125M 1.14E-05 6.78E-07 - 4.33E-05 3.09E-06 1.52E-06 3.20E-06 - Te-127M 2.89E.05 7.78E-06 3.43E-06 1.10E-05 Te-127 4.71E-07 6.91E-06 8.24E-05 - 2.34E-05 1.27E-07 1.01E-07 3.26E-07 Te-129M 4.87E 05 1.34E-06 - 1.84E-05 1.36E.05 7.56E-06 1.57E-05 Te-129 1.34E-07 1.43E-04 - 5.94E-05 3.74E-08 3.18E-08 9.56E-08 Te-131M 7.20E-06 3.92E-07 - 8.34E-06 2.49E-06 2.65E-06 5.12E-06 Te-131 8.30E-08 2.41E-05 - 1.01E-04 2.53E-08 2.47E-08 6.35E48 Te-132 1.01E 2.51E-07 - 4.36E-07 4.47E-06 5.40E-06 6.51E-06 l-130 2.92E-06 4.15E-05 - 4.50E-05 5.90E-06 3.04E-06 6.50E-04 1-131 1.72E-05 1.73E-05 8.82E-06 - 2.76E-06 1-132 9.83E-06 5.72E-03 2.84E-05 8.00E-07 1.47E-06 6.76E-07 1.54E 06 1-133 6.82E-05 2.25E-06 1.73E-06 5.92E-06 7.32E-06 2.77E-06 l-134 1.36E-03 1.22E-05 - 2.95E-06 4.19E-07 7.78E-07 l l-135 1.75E 06 3.15E-06 3.58E-07 1.49E-06 1.79E-05 2.79E-04 1.19E-06 4.83E-06 5.16E-07 B Cs-134 2.34E-04 3.84E-04 2.40E-06 Cs-136 8.10E-05 - 1.19E-04 4.27E-05 2.35E-05 6.46E-05 4.18E-05 2.07E-06 Cs-137 3.27E-04 3.44E-05 5.13E-06 2.27E-06 3.13E-04 4.62E-05 I Cs-138 2.28E-07 3.17E-07 2.01 E-07 1.02E-04 3.67E-05 1.96E-06 Ba-139 4.14E-07 2.23E-07 2.40E-08 1.46E-07 2.21E-10 1.20E-08 BI-140 8.31E-05 1.93E-10 1.30E-10 2.39E-05 7.28E-08 4.85E-06 i BO-141 B -142 2.00E-07 1.12E-10 6.51E-09 2.37E-08 9.69E-11 4.34E-08 6.5BE-10 4.21E-05 8.74E-08 6.29E-11 4.88E-09 1.14E-07 La-140 1.01E-08 5.09E-11 3.70E-11 1.14E-09 3.53E-09 1.19E-09 - l La-142 5.24E-10 1.67E-10 9.84E-05 5.23E-11 - C -141 3.97E-08 1.98E-08 3.31 E-05 Ce-143 2.94E-09 - 8.68E-09 6.99E-09 3.79E-06 5.49E-10 2.47E-05 Ce-144 2.08E-06 1.59E-09 - 5.55E-05 I 6.52E-07 1.11E-07 - Pr-143 3.93E-08 3.61 E-07 - 1.70E-04 1.18E-08 1.95E-09
. Pr-144 1.29E-10 6.39E-09 -
4.24E-05 3.99E-11 6.49E-12 - Nd-147 2.79E-08 2.11 E-11 - 8.59E-08 2.26E-08 I W-187 4.29E-07 2.54E-07 1.75E-09 - 1.24E-08 - 3.58E-05 Np-239 1.14E-G7 - - 5.25E-09 3.77E-10 2.65E-10 3.57E-05 1.09E-09 - 2.79E-05 I i . L 01/98 R8 e r
FORT CALHOUN STATION CH-ODCM-0001 . OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 126 OF 129 E Table 16 " Ingestion Dose Factors for Infant" 3 (mram per pCIIngested) Page 1 of 2 Nuclide Bone _ Liver T. Body Thyroid Kidney Luna GI-LLI H-3 C-14 No-24 2.37E-05 1.01E-05 1.76E-07 5.06E-06 1.01 E-05 1.76E-07 5.06E-06 1.01 E-05 1.76E-07 5.06E-06 1.76E-07 5.06E-06 1.76E-07 5.06E-06 1.76E-07 5.06E-06 l 1.01E-05 1.01E-05 1.01E-05 1.01 E-05 P-32 Cr-51 Mn-54 1.70E-03 1.00E-04 1.99E-05 6.59E-05 1.41E-08 4.51E-06 9.20E-09 2.01E-09 1.79E-08 2.30E-05 4.11 E-07 l Mn-56 4.41E-06 - 7.31E-06 8.16 07 1.41E-07 - 7.03E-07 - 7.43E 05 Fe-55 1.39E-05 8.98E-06 2.40E-06 4.36E-06 l)l Fe-59 3.08E-05 1.14E-06 5.38E-05 2.12E-05 - 1.59E-05 Co-58 2.57E-05 3.60E-06 8.98E-06 - Co 60 - 8.97E-06 1.08E-05 2.55E 05 - Ni-63 6.34E-04 2.57E-05 3.92E-05 2.20E-05 - Ni-65 4.70E-06 1.95E-06 5.32E-07 2.42E-07 Cu-64 - 6.09E-07 2.82E-07 4.05E-05 ~ g Zn-65 1.03E-06 - 1.25E-05 m 1.84E-05 6.31 E-05 2.91 E-05 Zn-69 3.06E-05 - 5.33E-05 9.33E-08 1.68E-07 1.25E-08 - 6.98E-08 Br-83 - 1.37E-05 E 3.63E-07 - Br-84 - - 3.82E-07 - - 5 Br-85 - - 1.94E-08 - - - - Rb-85 - 1.70E-04 8.40E-05 - j Rb-88 4.35E-Ob 4.98E-07 2.73E-07 - Rb-89 - 4.85E-07
'2.86E-07 1.97E-07 - - -
9.74E-08 Sr-89 2.51 E-03 7.20E-05 l Sr-90 2.83E-02 5.16E-05 5.74E-04 - - - 2.31E-04 Sr-91 5.00E-05 - 1.81 E-06 - Sr-92 1.92E-05 5.92E-05 7.13E-07 - - - 2.07E-04 Y-90 8.69E-08 - 2.33E-09 - - - 1.20E-04 g Y-91M 8.10E-10 - 2.76E-11 - Y-91 1.13E-06 2.70E-06 3.01 E-08 - - - 8.10E-05 g Y-92 7.65E-09 - 2.15E-10 - Y-93 2.43E-08 - 6.62E-10 - 1.46E-04 5 Zr-95 2.06E-07 1.92E-04 ; 5.02E-08 3.56E-08 - 5.41E-08 Zr-97 1.48E-08 2.50E-05 g! 2.54E-09 1.16E-09 - 2.56E-09 Nb-95 4.20E-08 1.62E 04 3l 1.73E-08 1.00E-08 - 1.24E-08 Mo-99 1.46E-05 3.40E-05 6.63E-06 - 5.08E-05 To-99M 1.92E-09 1.12E-05 3.96E-09 5.10E-08 - 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 Ru-103 3.40E-08 1.56E-09 4.86E-07 1.48E-06 - 4.95E-07 - 3.08E-06 _ , , -- ,,, 1.80E-05 l w ,. Re I
4 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 127 OF 129 l Tabl.e_16 (Continued) l Nuclide Bone Liver T. Body Page 2 of 2 Thyroid Kidney Luno GI-LLI I Ru-105 1.36E-07 Ru-106 2.41 E-05 4.58E-08 3.01E-06 1.00E-06 - 5.41E-05 Ag-110M 9.96E-07 2.85E-05 - 1.83E-04 7.27E-07 4.81E-07 - 1.04E-06 Te-125M 2.33E-05 7.79E-06 3.77E 05 1 Te-127M 5.85E-05 1.94E-05 3.15E-06 7.84E-06 - - 1.11E 05 7.08E-06 1.69E 05 1.44E-04 - 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 2.102-05 i Te-129M 1.00E-04 3.435-05 1.54E-05 3.84E-05 Te-129 2.84E-07 2.50E-04 - 5.97E-05 9.79E-08 6.63E-08 2.3BE-07 7.07E-07 Te-131M 1.52E-05 6.12E-06 2.27E-05 5.05E-06 1.24E-05 4.21E-05 - 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 I Te-132 2.08E 1.03E-05 9.61E-06 1.52E-05 4.50E-07 G.44E-05 - 7.11E-06 3.81E-05 l-130 6.00E-06 1.32E-05 5.30E-06 l-131 1.48E-03 1.45E-05 - 2.83E-06 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 I l-132 l-133 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 1.51 E-06 2.73E-06 1.25E-05 ' 1.82E-05 5.33E-06 3.31E-03 2.14E-05 l-134 8.69E-07 1.78E-06 3.08E-06 6.33E-07 4.15E-05 1.99E-06 1.84E-06 l-135 - I Cs-134 3.64E-06 3.77E-04 7.24E-06 7.03E-04 2.64E-06 6.49E-04 8.07E-06 - 2.62E-06 7.10E-05 - 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 Cs-137 5.38E-05 1.10E-05 2.05E-06 I Cs-138 5.22E-04 4.81E-07 6.11 E-04 7.82E-07 4.33E-05 3.79E-07 1.64E-04 3.90E-07 6.64E-05 1.91E-06 B:-139 8.81E-07 6.09E-08 1.25E-06
~5.84E-10 2.55E-08 -
3.51 E-10 3.54E-10 5.58E-05 i Ba-140 B:-141 B -142 1.71 E-04 4.25E-07 1.84E-07 1.71 E-07 2.91 E-10 8.81E-06 1.34E-08 4.06E-08 1.75E-10 1.05E-07 1.77E-10 4.20E-05 5.19E-06 1.53E-10 9.06E-09 - 8.81 E-11 Lc-140 2.11E-08 9.26E-11 7.59E-07 8.32E-09 2.14E-09 I LC-142 Ce-141 1.10E-09 7.87E-08 4.04E-10 9.67E-11 9.77E-05 6.86E-05 4.80E-08 5.65E-09 - 1.43E-08 Ce-143 1.48E-08 9.82E-06 2.48E-05 1.12E-09 - 2.86E-09 l 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 Pr-143 8.13E-08 4.93E-07 - i.71E-04 3.04E-08 4.03E-09 - 1.13E-08 Pr-144 2.74E-10 1.06E-10 4.29E-05 1.3BE-11 - 3.84E-11 Nd-147 5.53E-08 4.93E-06 I W-187 9.03E-07 5.68E-08 6.28E-07 3.48E-09 - 2.19E-08 - 3.60E-05 2.17E-07 - - 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61 E-10 - 1.98E-09 - 2.87E-05 I ~. .. _ . . . . . . . - - . . - [ [
- 01/98 R8 L
W
FORT CALHOUN STATION I CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BEFERENCFM Table 17
- Recommended Values for Other Parameters" PAGE 128 OF 129 l
Parameter Symbol Definition Values f, f, Fraction of produce ingested grown in garden ofinterest.
'O.76 l
Fraction of leafy vegetables grown in garden of interest. ~ 1.0 g g P Effective surface density of soil (assumes a 240 kg/m2 15 cm plow layer, expressed in dry vMght) r g Fraction of deposited activity retained on crops, 0.25 leafy vegetables, or pasture grass 1.0 (iodines) S, " Attenuation factor accounting for shielding 0.2 (other particulates) 0.7 (maximum individual) l provided by residential structures 0.5 (general population) t, Period of long-term buildup for activity in 1.31 x 105 hr sediment or soil (nominally 15 years) t, Period of crop, leafy vegetable, or pasture 30 days (grass-cow-milk-rnan I grass exposure during growing season pathway) 60 days (crop / vegetation-mar-patnway) l,1 t, Transport time from animal feed-milk-man 2 days (maximum individual provided by residential structures
, 4 days (general population))
t,, Time delay between harvest of vegetation or crops and ingestion: For ingestion of forage by animals Zero (pasture grass) 90 days (stored feed) l Fr.r ingestion of crops by man - 1 day (leafy vegetables arxf max. Individualfeed) 60 days (produce and max. individual) 14 days (general population) l I g 01/98 4 RB I
FORT CALHOUN STATION CH-ODCM-0001 g OFF-SITE DOSE CALCULATION MANU/L REFERENCE USE PAGE 129 OF 129 Tabie 17 (Continued) I Parameter _ Symbol Page 2 of 2 Definition Values l t, Environmental transit time, release to receptor (add time from release to exposura individual 12 hrs. (maximum) l 1 day (naximum individual) point to minimums shown for distribution) 1 day (ger.sral population) l 7 days (population-sport fish doses) I 10 days (population-commericalfish doses)
- t. Average time from slaughter of meat animal to 20 days
,consumption Y, ,
l Agricultural productivity by unit area (measured 2 0.7 kg/m in wet weight) (grass-cow-milk-man pathway) 2 2.0 kg/m (produce or leafy vegetable ingested by man) W Shore-width factor for river shoreline 0.2 A, Rate constant for removal of eetivity on plant or 0.0021 hr4 leaf structures by weathering , corresponds to a l 14-day half-life) I I I . 'I 01/98 R8
I I I I I SECTION VI I RADIOACTIVE EFFLUENT RELEASES - SOLID RADIOACTIVE WASTE l Technical Specifications 5.9.4a,5.17d and 5.18d i January 1,1998 - December 31 1998 I I [ [ [ u VI-1 r
- ~~ - Em .E . ,a. nD-WASIE EFFLUENT AND WASTE DISPOSAL REPGtT j January 1,1993 through Doomsber 31,1998
. SOUD WASTE AND DutADIA'IED FUE SEPMDU3
'A. SOUD WASTE SHIPPED OFFETIE POR BURIAL ORDISPOSAL (NOTIRRADIA7ED)
- 1. Type of Wassis Moesh Nussbarof Vohmes Curis Est. Total Sidpped nap ==== ca. Megar Coasset 5 Error
- a. Spent resins, flher sindges, January 1 3.4 9 5.617 N/A
" Pobruary 0 0 N/A 0
March 0 0 0 N/A AprH 0 0 0 N/A W . 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A j e 1 3.4 2590 20 October 1 3.4 2520 20 Novaunbar 0 0 0 N/A I D* 1 3.4 1430 20 i Total (Type A) 4 13.6 7235.617 N/A
- b. Dry casupressable, January 0 0.00 0.000 N/A I
" 0.68 0.003 20 February 2 March 1 0.09 0.001 20 AprH 2 0.04 0.000 20 May 0 0.00 0.000 N/A Jens 4 2.99 0.010 20 July 2 0.03 0.001 20 August 3 2.26 0.048 20 W 3 0.57 0.006 20 October 1 0.20 0.001 20 Novesuber 0 0.00 0.000 N/A December 6 2.03 0.003 20 Total (Type B) 29 s.s9 0.0725 20 VI-2
r III. RADI0 ACTIVE EFFLUDfT RELEASES - SOLID RADI0 ACTIVE IdASTE EFFLUENT Afe idASTE DISPOSAL REPORT [. (Continued)
- 1. Type of Waste Monk Number of Volume Orie Est. Total
{ shippui up Co. Meter Coment 5 Error ( - Irradiated P and 0 N/A
'c. January 0 0 Palmaary 0 -
0 0 N/A Mard 0 0 0 N/A AprH 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August O O O N/A W 0 0 0 N/A Ocaober 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type C) 0 0 0 N/A
- d. Other January 0 0 0 N/A February 0 0 0 N/A 0 0 N/A
( March 0 AprH 0 0 0 N/A [ W 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A l August 0 0 0 N/A-September 0 0 0 N/A October 0 0 0 N/A Ocsober 0 0 0 N/A 0 0 N/A ( Novaunhar 0 Decesabar 0 0 0 N/A f i Total (Typed) 0 0 0 N/A VI-3 f
B. ES11 MATE OF MAJOR NUCLIDE COMPOSmON (By Type of Waste)
- 1. Percentage of Curies from Represensed Isotopes I
Isotope Percast Curies
- a. Cs-137 43.9 % 3.10E+03 All other nuclides nnania** less than Cs-134 39.8 % 2.8(E+03 1%
Be-137m 11.3 % 7.93E+02 Co 58 2.3% 1.61E+02 i Co40 1.4% 9.79E+01
- b. Cs-137 32.7 % 2.37E-02 All other nuclides anmelan* ! ass than Ni43 29.2 % 2.12E42 1%
Fe-55 22.8 % 1.65E42 Co40 4.25 3.04E43 H-3 2.7% 1.99E43 C-14 2.6% 1.91E-03 . Cs-134 1.4% 9.88E-04 St90 1.4% 9.79E 04 Co-58 1.1% 7.37E44 Sb-125 1.0% 6.81E-04
- c. N/A N/A N/A 1
- d. N/A N/A N/A C. SOLID WASTE (DISPOSmON)
Number of Shipments ' Transportation Mode Ddamina 33 Closed Sole Use Vehicle Barnwell, S.C. D. IRRADIATED FUEL SHIPMENTS (DISPOSmON) N.mbe, - N/A T-N/A
-a-N/A I
VI-4 l I
I I SECTION Vil ATTACHMENT 1 l ODCM and PCP revisions for the period January 1,1998 through December 31,1998 in accordance with Technical Specification 5.17d and 5.18d, the radioactive effluent release report shallinclude any revisions to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP). 2 revisions were made to the Offsite Dose Calculation Manual (ODCM). O revisions were made to the Process Control Program (PCP). January 1,1998 - December 31,1998 I I I I-Vil-1
I "T l l I Fort Calhoun Station : Unit No.1 l 1 i CH-ODCM-0001 l I OFF-SITE DOSE CALCULATION MANUAL i I 1
Title:
OFF-SITE DOSE CALCULATION MANUAL (ODCM) l FC-68 Number: 53173 I ! Reason for Change: To incorporate elemental lodine fraction determined in EA-FC-94-048. l Contact Person: J. Shipman I I ISSUED: 06-12-98 4:00 pm R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 1 OF 129 TABLE OF CONTENTS PARTI Page
- 1. D E F I N ITI O N S . . . . . . . . . . . . . . . . . . . . . . . .' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 g 2. I N STR U M E NTATI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 1 2.1 Radioactive Liquid Effluent Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2.1.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2.1.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 I 2.2 Radioactive Gaseous Effluent Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 2.2.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 2.2.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
- 3. R ADIOACTIVE E FFLU ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 l 3.1 Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 3.1.1 Concentration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 3.1.2 Dose from Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . 24 l 3.1.3 3.1.4 Liq uid Waste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Liq uid Holdup Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 3.2 Radioactive Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 3.2.1 Concentration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 3.2.2 Dose - Noble Gas . . . . . . . . . . . . . . . . . . . . . . . . ..................31 3.2.3 Dose - l-131, Particulates, Tritium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 1 3.2.4 Gaseous Radwaste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 3.3 Uranium Fuel Cycle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5 3.3.1 Total Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............ 35
- 4. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . . . . . . . . . . . . . . 36 4.1 Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 1 4.1.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 4.1.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 4.2 Land Use Su rvey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 l 4.2.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 4.2.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 4.3 Interlaboratory Comparison Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 4.3.1 Limiting Condition for Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
[ 4.3.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
- 5. ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 5.1 Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
{ 5.1.1 FCS Chemistry Department . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 5.1.2 FCS Operations Department . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 L R9 P
FORT CALHOUN STATION CH-ODCM-0001 Il i OFF-SITE DOSE CALCULATION MANUAL REFERENGE_USE PAGE 2 OF 129 TABLE OF CONTENTS (Continued) l PARTI ' Page 5.2 Radioactive Effluent Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 5.2.1 Annual Radioactive Effluent Release Report . . . . . . . . . . . . . . . . . . . . . . 48 5.2.2 Annual Radiological Environmental Operating Report . . . . . . . . . . . . . . . 49 5.2.3 Special Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 5.2.4 EPA 40 CFR Part 190 Reporting Requirements . . . . . . . . . . . . . . . . . . . 50 5.3 C ha nge Mecha nism . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 { 5.4 Meteorological Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 1 5.5 References / Commitment Documents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 I
- 6. B A S I S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3 I
6.1 I nstrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 6.1.1 6.1.2 Radioactive Liquid Effluent Instrumentation . . . . . . . . . . . . . . . . . . . . . . . 53 Radioactive Gaseous Effluent instrumentation . . . . . . . . . . . . . . . . . . . . 53 l 6.2 Radioactive Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 6.2.1 Radioactive Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 6.2.2 Radioactive Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 6.3 Radioactive Environmental Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 6.3.1 Monitoring Prog ram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 3 m 6.3.2 Land Use Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 6.3.3 Interlaboratory Comparison Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 I R9 I
FORT CALHOUN STATION CH-ODCM-0001 [' OFF-SITE DOSE CALCULATION MANUAL REFERENCE.USE PAGE 3 OF 129 LIST OF TABLES {. PARTI I 1.2 Freq uency N otation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 ( 1.3 Radiological Effluent Controls Program Technical Specification Implementation . . . 9 2.1.1 Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . 11 2.1.2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 13 f 2.2.1 Radioactive Gaseous Effluent Monitoring instrumentation . . . . . . . . . . . . . . . . . . . 15 7 2.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance L Req u ireme nts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3.1 Radioactive Liquid Effluent Sampling And Analysis . . . . . . . . . . . . . . . . . . . . . . . . 22 { 3.2 Radioactive Airbome Effluent Sampling and Analysis Program . . . . . . . . . . . . . . . 28 [ 3.3 Sampler Deposition / Transportation Correction Factors . . . . . . . . . . . . . . . . . . . . . 30 4.1 Radiological Environmental Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . . . . 38 [ 4.2 Radiological Environmental Sampling Locations and Media . . . . . . . . . . . . . . . . . 40 4.3 Detection Capabilities for Environmerital Sample Analysis (LLD) . . . . . . . . . . . . . . 44 4.4 Reporting Levels for Radioactivity Concentrations in Environmental Samples . . . . 45 LIST OF FIGURES PARTI (- 1 Environmental Radiological Sampling Points . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 r l R9
FORT CALHOUN STATION CH-ODCM-0001 I OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 4 OF 129 TABLE OF CONTENTS 3 PARTll l Page
- 1. EFFLUENT MONITOR SETPOINTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 1.1 Liq uid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3 1.1.1 Liquid Effluent Radiation Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 g 1.2 Airbome E ffluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 68 1.2.1 Airbome Effluent Radiation Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69 1.3 Simultaneous Release Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 1.3.1 Liquid Release Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 1.3.2 Airbome Release Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77
- 2. EFFLUENT CONCENTRATIONS . . . . . . . . . ................................85 2.1 Liquid Effluent Concentrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 2.2 Airborne Effluent Concentrations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86
- 3. RADIOACTIVE EFFLUENT DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . 87 g 3.1 Liquid Effluent Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87 3 3.1.1 Doses from Liquid Effluent Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . 88 3.2 Airbome Effluent Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 i 3.2.1 N oble G a s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91
! 3.2.2 Radioiodines, Particulates, Tritium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 l 3.2.3 Concentrations of Radionuclides in Food and Vegetation from Atmospheric Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96 3.2.4 Parameters for Calculating Radionuclide Concentrations in Milk . . . . . . 100 3.2.5 Parameters for Calculating Radionuclide Concentrations in Cow Meat, Excluding Tritium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation . . . . . 101 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Food . . 101 l
- 4. LOWE R LI M IT O F D ETECTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104 R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 5 OF 129 LIST OF TABLES PARTil Page 1 Allocation Factors for Simultaneous Releaces. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79 2 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases . . . . . . . . . . . . . . . 105 3 Bioaccumulation Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 4 Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations . . 107 5 Stable Element Transfer Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108 6 Recommended Values for U, to be Used for the Maximum Exposed Individual I in Lieu of Site Specific Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 7 Animal Consumption Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109 8 Extemal Dose Factors for Standing on Contaminated Ground . . . . . . . . . . . . . . . . . . . 110 1 9 inhalation Dose Factor for Adult . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112 l 10 inhalation Dose Factor for Teenager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 114 11 inhalation Dose Factor for Child . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 116 1 12 inhalation Dose Factor for infant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 118 13 Ingestion Dose Factor for Adult . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 120 14 Ingestion Dose Factor for Teenager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 122 15 Ingestion Dose Factor for Child . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 124 16 Ingestion Dose Factor for infant . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126 l 17 Recommended Values for other Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 128 l l R9 u F h a _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 6 OF 129 LIST OF FIGURES PART11 Page 1 Exclusion and Site Boundary Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80 2 . Liquid Radioactive Discharge Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 81 l 3 Liquid Radioactive Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 82 4 Airbome Effluent Dis [harge Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 5 Airbome Radioactive Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 I I I l R9 l I,
l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEEBfMCfdlSE PAGE 7 OF 129
- 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 i 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 opersble, including any alarm and/or trip initiating action. Member (s) of the Public I Member (s) of the Public means any individual except when that individual is receiving occupational dose. I Operable - Ooerability l 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, I 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). Purae-Puraino A means for the removal and replacement of gases within the containment building. Source Check Verification of channel response when the channel sensor is exposed to a radioactive source. e L R9
i l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BEEEEE!KERSE PAGE 8 OF 129 l
- 1. DEFINITIONS (Continued)
Ventina 1 A means for the reduction of pressure greater than atmospheric within the containment structure. l 1 Unrestricted Area Means an area, 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. ll TABLE 1.2 ; FREQUENCY NOTATION The surveillance intervals are defined as follows: NOTATION TITLE FREQUENCY I l S Shift At least once per shift D Daily At least once per 24 hours W Weekly At least once per 7 days I BW Biweekly At least once per 14 days l M Monthly At least once per 31 days Q Quarterly At least once per 92 days I SA Semiannual At least once per 184 days A Annually At least once per 366 days R Refueling At least once per 18 months I P Prior to Pnor to each release R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 9 OF 129 Table 1.3 ' Radiological Effluent Controls Program Technical Specification implementation" Technical Soecific.at10D ODCM imolementina Steo 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 1 5.16.1.d 3.1.2 l 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 5.16.1.h 3.2.2 5.16.1.i 3.2.3 5.16.1.] 3.3.1 5.16.2.a 4.1.1 5.16.2.b 4.2.1 l 5.16.2.c 4.3.1 1 5.17 5.3, 5.2.1.d l 5.18 5.2.1.d E ~ R9 u
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 10 OF 129
- 2. INSTRUMENTATION 2.1 Radioactive Liquid Effluent Instrumentation 2.1.1 Limiting Condition for Operation A. The radioactive liquid effluent monitoring instrumentation channe!s 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 11 of the Off-site Dose Calculation Manual. APPLICABILITY: At all times Ii ACTION:
- 1) With a radioactive liquid effluent monitoring instrumentation .
channel alarm / trip setpoint less conservative than required by the above specification, immed!ately suspend the releases of radioactive liquid effluents monitored by the affected channel or { declare the channelinoperable.
- 2) With less than the minimum number of radioactive liquid effluent Ijl' 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 l 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 i instrumentation that monitors effluent streams: RM-055, RM-054A, I and RM-054B. )
I 2.1.2 Surveillance Requirements I 1 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. l R9 I I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 11 OF 129 Table 2.1.1 " Radioactive Liquid Effluent Monitoring Instrumentation" MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. Radioactivity Monitors Providing Alarm and Automatic I Termination of Release.
l a. Liquid Radwaste Effluent Line (RM-055) 1 1, 5
- b. Steam Generator Blowdown Effluent Line I (RM-054 A and B) 1' 2, 5
- 2. Flow Rate Measurement Devices
- a. Liquid Radwaste Effluent Line 1 3
- b. Steam Generator Blowdown Effluent Line 1 3
~
1
- 3. Radioactivity Recorders
- a. Liquid Radwaste Effluent Line 1 4 l b. Steam Generator Blowdown Effluent Line 1 4 i S If one of the two radiation monitors is inoperable, the activity of both blowdown lines shall be g monitored by the operable monitor within 2 hours of the declaration of inoperability by the l Shift Supervisor, or the action steps of ACTION 2, Table 2.1.1 should be performed on the Steam Generator that is not being monitored.
I I
~
/
l R9
i FORT CALHOUN STATION CH-ODCM-0001 Il OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 12 OF 129 Table 2.1.1 (Continued) Table Notation I ACTION 1 With the number of channels OPERABLE less than required by the Minimum l Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release: l
- 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 OPEPABLE less than required by the Minimum Channels OPEPABLE requirement, effluent releases may continue provided that grab samples are analyzed for principal gamma emitters at a sensitivity of 5.0E-07 pCi/ gram:
- 1. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 pCi/ gram dose equivalent I-131.
- 2. At least daily when the specific activity of the secondary coolant is less than or equal to 0.01 pCi/ gram equivalent 1-131. Otherwise, suspend g 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 l the flow rate is determined at least once per four hours during the actual release. l 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 l 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. l R9 l
I I)l{l lIl ll ll4 i'll 1 9 9 02 R 01 0 F MO E C3 S D1 A OE E M - HG L E C PA 2 "s K R t n CO e ET m e HR - P - i r CO I u q ER M e CP R R U e O c a n ST l S l i E e v T r u N M S O I n T i o L C t a EN t n NU M e NF Q Q - m A E u r H S t s CN M U i n O I E g T A C n e s N i r R a E o B M R t i I e n L le E o A r F M C o E t t r R n o M e u R R R i r p m s E r d h M i u q 4 2 - L i L i n h A v e L it U i t EK w N c NC ' d A a M o NE D - D t e i d AH e M N a H C C lp O R m I T o c NA 2 e OLU I 1 c r ly b T ALC 2 it B o ia t s e ga s t a D u TA l b inm 4 5 r o r e m SC a T d o 0 t n k c k M NE T N i t v u / A i n en e c US E tyoAr 4 o Gwo h e i 5 c h OO M vP d 5 5 M md w C c sr na i HD L U H t ao o n 0-M 0-M t e a aw eo l o e c AE T 1 i otimi t R R r t l SB F i r u CI S dnr aoaolas w o n u 3 TS - N I RMAi l a
. . l a
s S RF b F i V A M OF FO 1 2 ' 2 1 l
i FORT CALHOUN STATION CH-ODCM-0001 l OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 14 OF 129 l I 2.2 Radioactive Gaseous Effluent instrumentation l 2.2.1 Limiting Condition for Operation l A. The radioactive gaseous effluent monitoring instrumentation channels g 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. El l The alarm / trip setpoints of these channels shall be determined in accordance with Section 11 of the Off-site Dose Calculation Manual. APPLICABILITY: At als times g ACTION: q
- 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 j instrumentation that monitors effluent streams: RM-057, RM-043, j RM-062, RM-063, and RM-052. j 1 2.2.2 Surveillance Requirements ll l A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL l)' FUNCTIONAL TEST at the frequencies shown in Table 2.2.2. I R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BEEEEENCfdSE PAGE 15 OF 129 [ 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. lodine and Particulate 1 2,9,11
- 2. Laboratory and Radwaste Processing Building Stack (RM-043)
{
- a. Noble Gas 1 3, 9 I
- b. lodine and Particulate 1 4, 9
- 3. Condenser Off Gas (RM-057) f a. Noble Gas 1 5, 9
- 4. Containment Purge Line (RM-050/51)
- a. Noble Gas 1 1,6,9,11,12
- b. lodine and Particulate 1 2,9,11,12
- 5. Containment Pressure Relief Line (RM-050/51)
I
- a. Noble Gas 1 1,9,11
- b. lodine and Particulate 1 2,9,11
- 6. Containment Penetrations M72 and
( M74 (Integrated Leak Rate Test Depressurization Vent Path) N/A 10 R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 16 OF 129 Table 2.2.1 (Continued) MINIMUM CHANNELS l INSTRUMENT OPERABLE ACTION
- 7. Flow Rate Measurement Devices
- a. Waste Gas Discharge Header 1 7
- b. Auxiliary Building Stack 1 7
- c. Laboratory and Radwaste Processing Building Stack 1 7
- d. Containment Purge Line 1 7
- e. Containment Pressure Relief Line Annubar D/P 1 7 l
- 8. Radioactivity Chart Recorders
- a. Auxiliary Building Exhaust Stack 1 8 I
I I l I i I R9 Il I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEEBEliCE_UM PAGE 17 OF 129 Table 2.2.1 (Continued) TABLE NOTATION ACTION 1 If the Auxiliary Building Exhaust Stack Noble Gas Moni:or 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 I the auxiliary ouilding via the Auxiliary Building Exhaust Stack may continue provided grab samples are taken once per 8 hours (+25% maximum extension) and analyzed for principal gamma emitters. (See Table 3.2) ACTION 2 If the Auxiliary Building Exhaust Stack lodine and Particulate Sampler is inoperable, ventilation of the Auxiliary Building and releases from the I 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 i auxiliary sample collection equipment is initiated within 2 hours of the declaration of inoperability by the Shift Supervisor. 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 hours (+ 25% maximum extension) and analyzed for principal gamma I emitters. (See Table 3.2)
ACTION 4 If the lodine and Particulate Sampler is inoperable, ventilation of the LRWPB I may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours of the declaration of inoperability, by the Shift Supervisor, in accordance with l Table 3.2. ACTION 5 During power operation, when the condenser air ejector is in service, the l condenser off gas discharge shall be monitored for gross radioactivity. If this monitor is inoperable, grab samples shall be taken once per 24 hours (+25% maximum extension) and analyzed for principal gamma emitters. (See
]- Table 3.2)
ACTION 6 The release of airbome 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. R9
r FORT CALHOUN STATION CH-ODCM-0001 l OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 18 OF 129 Table 2.2.1 (Continued) TABLE NOTATION ACTION 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 considerad 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 tetminate the effluent release. ACTION 10 Automatic release termination capability is not required provided manual isolation can be accomplished in accordance with the requirements of SS-ST-lLRT-0001. ACTION 11 During the ventilation of airbome 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 l during the calender quarter, a special report shall be submitted to the NRC as defined in Section 3.2.4 l I I I i l i l R9 j i
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 19 OF 129 Table 2.2.2 " Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements" CHANNEL SOURCE CHECK 2 CHANNEL FUNCTION PRIOR TO u
. INSTRUMENT CHECK CAllBRATION TEST RELEASE
- 1. Radioactivity Monitors I Providing Alarm and Automatic isolation I a. RM-043 D R Q -
l b. RM-057 D R Q -
- c. RM-062 D R Q P
- d. RM-052 ' D R Q P
- 2. Flowrate Monitors
- a. RM-043 Sampler D R - -
- b. RM-062 Sampler D R - -
- c. RM-052 Sampler D R - -
- d. Auxiliary Bldg I Exhaust Stack D R - -
- c. Laboratory and l Radwaste Process Bldg Exhaust Stack D R - -
Ooerations Check Air Flow Calibration
- 3. Environmental Monitors
- a. RM-035-40 M A Required when RM-052 is sampling the Auxiliary Building Exhaust Stack.
2 A Source Check must be completed within 24 hrs prior to release. E R9
W FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 20 OF 129
- 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 g not exceed the values specified in 10 CFR Part 20 for liquid 3 efiluents at site discharge. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limit g specified in Technical Specifications 5.16.1.b. For dissolved or 3 entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/ml, total activity.
- 2) Technical Specification 5.16.1.b establishes the administrative controllimit on concentration of radioactive n iterial, other than dissolved or entrained noble gases, release' liquid effluents to unrestricted areas conforming to ten times . .FR Part 20.1001-20.2401, Appendix B, Table r ~;olumn 2. For dissolved or entrained noble gases, the conuntration shall be limited to 2.0E-04 pCi/ml total activity.
APPLICABILITY: At all times i ACTION: g 5i a) When the concentration of radioactive material released at site ! discharge exceeds the above limits, appropriate corrective g) actions shall be taken immediately to restore concentrations 3l within the above limits. B. Surveillance Requirements
- 1) Radioactive liquid waste shall be sampled and analyzed according g to the sampling and analysis program in Table 3.1. E
- 2) The results of the radioactivity analysis shall be used with the g calculational methods in Part ll of the ODCM to assure that the E concentration at the point of release is maintained within the limits of Technical Specification 5.16.1.b.
R9
FORT CALHOUN STATION { OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 21 OF 129 3.1.18 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. b [ [ [- [ [ [ [ [ [ [ { { [ R9
F - i FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 22 OF 129 Table 3.1 " Radioactive Liquid Effluent Sampling And Analysis" A. Monitor & Hotel Waste Tanks Releases Lower Limit of Type of Detection (LLD) Sampling Frequency Activity Analysis (pCi/ml) ' Each Batch Principal Gamma Emitters 2 5.0E-07 Each Batch I-131 1.0E-06 Monthly from One Dissolved Noble Gases Batch (Gamma Emitters) 1.0E-05 Monthly Composite
- H-3 1.0E-05 _
Monthly Composite
- Gross Alpha 1.0E-07 Quarterly Composite
- S;-89, Sr-90 5.0E-08 Quarterly Composite
- Fe-55 1.0E-06 B. Steam Generator Blowdown Type of Lower Limit of Detection (LLD) l Sampling Frequency Activity Analysis (pCi/ml)'
Weekly Composite
- Principal Gamma Emitters : 5.0E-07 Weekly Composite
- l-131 8 1.0E-06 Monthly Dissolved Noble Gases (Gamma Emitters) 1.0E-05 Monthly Composite
- H-3 1.0E-05 Monthly Composite
- Gross Alpha 1.0E-07 Quarterly Composite
- Sr-89, Sr-90 5.0E-08 Quarterly Composite
- Fe-55 1.0E-06 R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 23 OF 129 Table 3.1 (Continued) l NOTES:
' LLD is defined in Part 11 of the ODCM.
3 The principal gamma emitters for which the LLD specification applies exclusively are the I 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 5.0E-06. I
- 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 l composite analysis indicates the 1-131 concentration is greater than 1.0E-06 pCi/ml.
d To be representative of the average quantities and concentrations of radioactive materials in I 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. I I I I I [ [ R9 {
FORT CALHOUN STATION CH-ODCM-0001 I OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 24 OF 129 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 during any calendar year shall not exceed a millirems to the total body and 1Q millirems to any organ.
- 2) The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents during any calendar quarter shall not exceed 15 millirems to the total body and 5 millirems to any oroan.
~
APPLICABILITY: At all times ACTION: a) The radiation dose contributions from radioactive materials in liquid effluents released at site discharge shall be determined, in accordance with the methodology and parameters in Part ll of the ODCM, on a quarterly basis. If the dose contribution, due to the cumulative release of liquid effluents averaged over a calendar quarter, exceeds one-half of the annual design objectives, the following course of actions shall be taken: (1) Make an investigation to identify the causes for such releases. l (2) Define and initiate a program of action to reduce such releases to the design levels. (3) Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, identifying the causes and describing the proposed program of action to reduce such releases to the design levels. 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 11 of the ODCM at least once per quarter.
l R9 I
l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 25 OF 129 3.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation h 1) The Liquid Radwaste Treatment System shall be OPERABLE, and p appropriate portions of these systems shall be used to reduce the radioactive materialin liquid wastes so that one half of the annual l dose objective listed in ODCM Specification 3.1.2.A will not be exceeded in a calender quarter. l APPLICABILl1Y: At all times ACTION: a) Every effort will be made to process all liquid waste, except from the hotel waste tanks, through the Filtration /lon Exchange I (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 I 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 I days of the end of the quarter during which the equipment or subsystem (s) were inoperable. This report shall include the following information: l (1) Identification of equipment or subsystem (s) not l operable and reasons for inoperability. (2) Action (s) taken to restore the inoperable equipment to l operable status. (3) Summary description of action (s) taken to prevent a 1 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 11 of the ODCM , when Liquid Radwaste
( Treatment Systems are not fully OPERABLE. [ R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL RE.FERENCf].EE PAGE 26 OF 129 3.1.3B 2) OPERABLE is defined as follows: A filtration / ion exchange (FIX) system will be utilized for processing liquid radwaste. The system consists 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
)
I decontamination factors (iodines, Cs, Rb, others) was taken for i these filters during the 10 CFR Part 50 Appendix l dose design l 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 hours reduce the tank contents to within the limit. R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 27 OF 129 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 h a
- 1) The release rate of radioactive materialin airbome effluents shall
' be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR Part 20 for airbome 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 I controllimit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR I 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 I 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 accoting 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. b y R9 W
1 F 1 FORT CALHOUN STATION CH-ODCM-0001 PAGE 28 OF 129 l l l OFF-SITE DOSE CALCULATION MANUAL REEERENCE_USE Table 3.2 " Radioactive Airbome Effluent Sampling And Analysis" I A. Gas Decay Tank Releases Lower Limit of g Type of Detection (LLD) , Sampling Frequency Activity Analysis (pCi/ml) ' 2 Prior to each release Principal Gamma Emitters 1.0E-04 5 G. Containment Purge Releases or Containment Pressure Relief Line Releases
. , , , g Lower Limit of 5 Type of Detection (LLD)
Sampling Frequency Activity Analysis (pCi/ml) ' g
. Prior to each release Principal Gamma Emitters 2 1.0E-04 Prior to each release H-3 1.0E-06 l
5 C. Condenser Off Gas Releases Type of Lower Limit of Detection (LLD) l Sampling Frequency Activity Analysis (pCi/mi) ' Monthly
- Tritium (H-3) l.0E-06
! Monthly Principal Gamma Emitters 2 1.0E-04 I Il i
. R9
l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFEREPfGE.1!SE PAGE 29 OF 129 Table 3.2 (Continued) D. Auxiliary Building Exhaust Stack and Laboratory and Radwaste Building Exhaust Stack s I Lower Limit of Type of Detection (LLD) l Sampling Frequency ActivityAnalysis (pCi/ml) ' Weekly (Charcoal Sample) 1-131 l 1.0E-12 Weekly (Particulates) Principal Gamma Emitters 2, l-131, and Particulates with I half-lives > eight (8) days. 1.0E-11 Weekly (Noble Gases) 2 Principal Gamma Emitters 1.0E-4 Monthly Composite d Gross Alpha 1.0E-11 Quarterly Composite (Particulates) Sr-89, Sr-90 1.0E-11 1 NOTES:
' LLD is defined in Part 11 of the ODCM 3
The principal gamma emitters for which the LLD specification applies exclusively are the i following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 for particulate emissions. Required only when steam generator blowdown radioactivity for tritium (Table 3.1, item B) exceeds 3.0E-03 pCi/ milliliter. l Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media. l b 5 Particulate and lodine 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). R9 m e
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 30 OF 129 Table 3.3 " Sampler Deposition / transportation Correction Factors" I PARTICULATE LODINE SAMPLER SAMPLE DF ACTMULT ' DF ACTMULT , 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 : CONT 0.52b 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 l ACRONYM DEFINITIONS: AB - Auxiliary Building Exhaust Stack CONT - Containment Building l LRWPB - Laboratory and Rad Waste Processing Building g DF - Deposition Factor E ACTMULT - Activity multiplication factor to correct for sample loss.
' ACTMULT factors are automatically determined using the appropriate analysis sequence file far the sample type.
2 Sampler can be used to monitor either the Containment or Auxiliary Building. I R9 i,. - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 31 OF 129 1 3.2.2 Dose - Noble Gases A. Limiting Condition for Operation
- 1) During any calender year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
- 2) During any calender quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation.
APPLICABILITY: At all times ACTION: a) If the dose contribution, due to the cumulative release of noble gases in airbome effluents averaged over a calendar quarter I exceeds one-half of the annual design objectives, the following course of actions shall be taken. ; (1) Make an investigation to identify the cause for such release rates. l (2) Define and initiate a program of action to reduce such releases to design levels. (3) Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, identifying the causes and describing the proposed program of action to reduce dose contributions. B. Surveillance Requirements
- 1) The radiation dose contributions from radioactive noble gases in airbome effluents shall be determined, in accordance with the methodologies and parameters of Part 11 of the ODCM, on a quarterly basis. j R9
1 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL MN_C.E_USE PAGE 32 OF 129 l 3.2.3 Dose - lodine-131, Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases) and Tritium A. Limiting Condition for Operation j
- 1) The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater 3 than eight days (excluding noble gases) in airbome effluents shall E not exceed 7.5 millirems in any calender quarter and 15 millirems from all exposure pathways during any calendar year.
APPLICABILITY: At all times ACTION: a) If the dose contribution, due to the cumulative release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents averaged over a calendar quarter exceeds one-half of the annual design objectives, the following course of actions shall be taken: (1) Make an investigation to identify the cause for such release rates. (2) Define and initiate a program of action to reduce such releases to design levels. (3) Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, l identifying the causes and describing the proposed program of action to reduce dose contributions. B. Surveillance Requirements
- 1) The radiation dose contributions from I-131, Tritium, and I
radioactive materials in particulate form with half-lives greater than gfI eight days (excluding noble gases) in airborne effluents shall be E determined, in accordance with the methodologias and parameters
)
of Part ll of the ODCM, on a quarterly basis. R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BEEggEM_Q.E_l)_%g PAGE 33 OF 129 3.2.4 Gaseous Radwaste Treatment A. Limiting Condition far 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 materialin gaseous wastes so that one half of the annual dose 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 l 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 l 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 I following information: (1) Identification of equipment or subsystem (s) not I operable and reasons for inoperability. (2) Action (s) taken to restore the inoperable equipment to I operable status. (3) Summary description of action (s) taken to prevent a recurrence. l B. Surveillance Requirements
- 1) Dose due to gaseous releases shall be projected frequently and at l least once per quarter, in accordance with the methodology and parameters in Part 11 of the ODCM, when Waste Gas Systems and Ventilation Exhaust Systems are not fully OPERABLE.
r R9 m W
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL . REFERENCE.USE PAGE 34 OF 129 3.2.4 B 2) OPERABLE is defined as follows: I 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 i one of the four gas decay tanks. The waste airbome ( 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 eanier release allowed to support i plant operation only, and thus achieve decay of short half-life i radioactive materials, e.g.,1-131, Xe-133. If the radioactive airbome 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 l Section 3.2.4.A. b) Ventilation Exhaust Systems The radioactive effluents from the controlled access area of the I auxiliary building are filtered by the HEPA filters in the auxiliary l building ventilation system. If the radioactive effluents are discharged without the HEPA filters, a speciz' oport shall be i submitted to the NRC as defined in Action a) above. l The discharge from the gas decay tanks is routed through l,' 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 3 confirmed that one half of the annual dose objective will be 3 exceeded during the calender quarter, a special report shall be submitted to the NRC as defined in Action a) above. R9
t
- FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 35 OF 129 3.3 Uranium Fuel Cycle 3.3.1 Total Dose-Uranium Fuel Cycle b
A. Limiting Condition for Operation ( 1) The dose to any real individual from uranium fuel cycle sources shall be limited to 5 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 5 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 mources, 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 40 CFR Part 190 has not airoady been corrected, the Special p Report shall include a request for a variance in accordance L 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. [ r R9 u r-
1 1 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 36 OF 129 1 3.3.1 B. Surveillance Requirements Cumulative dose contributions from liquid and gaseous effluents shall
]
be determined in accordance with Surveillance requirements 3.1.2.B, j 3.2.2.B and 3.2.3.B and in accordance with the methodology and j parameters in Part ll of the ODCM.
- 4. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) l I
4.1 Monitoring Program I 4.1.1 Limiting Condition for Operation , 1 A. The Radiological Environmental Monitoring Program shall be conducted l as specified in Table 4.1. APPLICABILITY: At alltimes 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 3 (Section 5.2). 5
- 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.
- 3) If the level of radioactivity in an environmental sampling medium exceeds the reporting level specined in Table 4.4, and the activity II {
is attributable to plant operation, a Special Report shall be l prepared and submitted to the Nuclear Regulatory Commission within 30 days from the end of the quarter (Sc-ction 5.2.3). The i detection capabilities of the equipment used for the analysis of l environmental samples must meet the requirements of Table 4.3 for Lower Level of Detection (LLD). ,
- 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 the Radiological Emergency Response Plan. I R9 L
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 37 OF 129 4.1.1 A 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 i person discontinues participation in the program, etc. If the equipment malfunctions, corrective actions will be complete as soon as practicable. If a person no longer supplies samples, a replacement will be made if possible. All deviations from the I sampling schedule will be described in the Annual Radiological Enviro 1 mental Operating Report, pursuant to Section 5.2. 4.1.2 Surveillance Requirements A. The Radiological Environmental Monitoring Program (REMP) shall be I collected and analyzed in accordance with Tables 4.1,4.2, and 4.3. I I I I I I I I [ [ c R9
FORT CALHOUN STATION CH-ODCM-0001 I OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 38 OF 129 Table 4.1 " Radiological Environmental Monitoring Program" Exposure Pathway and/or Sarnple Cofiection SRe ' Type of Analysis 8 Frequency
- 1. Direct Radiation A. Ten TLD indcator stations, two control Gamma dose Quarterty stations, total of 12. -
B. An inner-ring of 16 stations, one in each Gamma dose during SRe Area and Replaced Annually cardinal sector in the general area of the General Emergencies only. unrestricted area boundary and within 2.5 miles. C. An outer-ring of 16 stations,1 in each Gamma dose dunng Site Area and Rr,splaced Annually cardinal sector located outside of the General Emergencies only. inner-nng, but no more distant than approximately 5 miles. *
- 2. Air Monitonng A. Indicator Stations Finer for Gross Bets
- Weekly
- 1. 3 stations in the general area of Charcoal for 1-131 Weekly the unrestricted area boundary Finer for Gamma Isotopic Quarterly composne
- 2. City of Blair of weekly finers B. Two background stations
- 3. Water A. Missourt River at nearesNownstream Gamma Isotopic, H-3 Monthly composite for drinking water intake. Gamma isotopic Anatysis ,
B. Missouri River downstream near the mixing zone. Quarterty composite C. Missouri River upstream of Plant intake (background).
- 4. Milk
- A. Nearest family cow when available or Gamma Isotopic and 1-131 Semimonthly grazing one dairy farm within 5 miles. season (May to October) ,
B. One dairy farm between 5 miles and l 18.75 miles (background).
- 5. Fish A. Four fish sarnples within vicinity of Plant Gamma Isotopic Once per season discharge. (May to October) 1 B. One background sample upstream of Plant discharge.
- 6. Sediment A. One sample from downstream area on Gamma Isotopic Semiannually the station side of the Missouri River. l S. One sample from upstream of Plant intake (background).
~ l
- 7. Vegetables or Food A. One sample in the highest exposure Gamma isotopic Once per season i Products
- pathway. (May to October)
B. One sarnple outside of 5 miles (background). R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 39 OF 129 Table 4.1 (Continued) NOTES: 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. 8 When a gross beta count indicates radioactivity greater than 1E-12 pCi/mi or 1 pCi/m8, a gamma spectral analysis will be performed. I 0 When milk samples are not available, a broad leaf vegetation or pasture grass sample shall be collected, when available. m 8 Details of the Emergency TLD Stations are contained in the Radiological Emergency Response Plan 8 2 Samples should be collected from garden plots of 500 ft or more. Reference Reg. Guide 4.8 " Environmental Technical Specifications for Nuclear Power Plants," Dec.1975. I I I I I M m E R9 M
1 9 02 01 0F s led bo t a cu e F d g e n ot s d or 9 R m m_ MO VaP C0 D4 OE HG h CA P is F t n e im d S e m lk i M a id r e e X M t a d n W A n o - it a c D X X X X X X X X X X o L X L T g E h n S p m U a e e S mn X X E la g oi b do X X X C t e n in r A nl N n t o E o r n o n R iv r M e E n i r =ta F E A -. uc
-,l v X X X X X E l a
c ti k rt R ig o AaP loi d - a e
)
R t ansh
- mieooet r * ' * * * * '
2 4 it xcr n oeg r em 3 9 2 8 0 2 5 4 1 3 0 3 7' 5 1 9 4 1 1 0 1 0 8 1 0 1 3 0 5 2 0 3 1 6 5 1 M_ e r pD( p i d o lb r a A f L T A U emt n M_ N taro mf m )s e 0 A ie ne xci i l 5 6 8 0 5 7 8 0 2 6 0 0 7 0 0 7 M onam 4 1 0 0 0 3 1 1 r pt atn( N pso AiC D O I T o t n ,.t NA o R M r a e, t a is n t e t H t e5 f l a O UL I t e n r t n e cd 5 7
.da n o R y
a ge eu g c7 n a r y. f o W o P f o DlP st TC te 0 aa yo hi t t r a C kf a Re t n w W S E ieneE AL a no 1 dj o r wr e ot E t n e, H N, W S, lt i m N, mis 1 a, ss Hss it TA ide x ei nr ne nf oe c ic f f N, S ge r N, ie df R nm n n, n Ut a a SC ol po S r l t o ew it oc t c o it nc D o nw n o u nd ul oo ir t f a o it a o it b o it a n reh aTa NE ao aa taoi a i t id lip o A pC t t Sr t St n Stcm P P u a h oW r a o t et Si t S S t S i epcO e m US teh e itea e rera O B h la C et eS te t e R e n ur teh w OO t sf co it t it t s lp s n it r Fa t ns s n ins a fs r sa s ed i la Om r ee n la n na eoo HD ne o f f nd MFN l l f t n OP l Ow Olo OIn a B EO F FD OP OP O L AE T CI ener TS l pob 0 1 2 i 2 3 4 5 6 7 8 9 1 1 RF mtam at u 1 1 OF SSN FO M_
j l lllll_ lljllll l1 l l 1 9 9 02 s 01 t c u 8 R 0 F d X X X X X o MO P r C1 D4 OE HG h CP A is F X t n e im X X d e S k l 8 i M X X X X X ia d e r M t e a X X X X X d n W A. X- D 9 L t_ T g E. u n S p m U a e ne r n S E l a g oi b d C a, ino A lo ir N e. r E it M n R o E n n Mr et e mlua i F E A E l a o bi c c R rt r M ig lo o i AaP d a e ) R t an;t h
- mio 2 it ;o ;r * * . ' * * * * * *
- M 4 le xc ;n pi4om oe r r 6
0 1 4 3 5 3 3 1 4 5 1 3 5 6 0 2 0 3 1 7 8 1 9' 2 1 2 7 0 8 6 1 8 3 1 6 9 2 b pD( r L a A f T A M U emt n N t aro e 0 0 A mf m )s 5 4 2 9 8 5 4 6 6 iailne x 1 1 4 8 3 6 6 7 7 7 0 M enai n atn (r 0 0 0 1 O 3 0 3 9 6 0 2 2 2 N t so M. M.. M O I fD wi C R R T f NA r e OLU I ivt Rn a eve r
'eg * *
- T ALC te a no i l r P u
ki taf r ' .f ge u a a, e m m m R om n ko 8 e ldR e r r a r a TA r r mis s o I A A a F F ide x s mn w Be F SC o r nS aN if M m r o ba z ite si f l elrd gr ne gr n r e n e ' t r e 1i e NE po pC k a f t 'm s t r i m y r y y liv pR i uh pR s h lc h c US A n areg e ms a e r a O n aW u o r a ia r ia r ia mir mi u a m r a e le btsa r ew. F F D D D au a ru h F W Wy M OO t nh s ewc t r sg h it D P qt do as t e n n h r p So h ss So h s n e z n HD L Wdd ois pld UB S m P O ee HD n i M ly F M o J p a isi FM isis FM L g e lt S e h J o J n e AE T CI en O T S- 3 mt i 3 4 5 6 7 8 9 0 2 3 4 5 6 7 RF OF po% at SS a 1 1 1 1 1 1 1 2 1 2 2 2 2 2 2 2 l FO U lll N
1 9 s 9 02 01 led b ot s c
- R a o u 0 F t e F d X X X X X gdnr o MO e VaP C2 D4 OE HG h is CA P F t
n e m i d e S k l i M
- e ia t u
d r it e e t s M t a b d u n W s A a n s o a h n a io c D o L t a L T c g lo E i n t a S lp m ht U a e. r e t a M S i n E !a g vi X yd lnt e C d L'ulo d i bor A oc . N m nl le y E . i it n ic oo ln p. o i o t a e a R ar v M mb em c E i ir et e a r oR ne E ml f i eh F A ou inwe r t E la c X fe n c bi lal np eo R g i ir AaP r t r d lo i o om.l it dssiar r i a ae ct d a e dn eot st s R t ansh
) ao rt i oisu dhi R
- noet r oa ieo * * * *
- f t d r e 2 utcr n 4 0 7 5 9' 7 d e gt efo b 4
le veg
. r pi pD (d for em 6
1 8 1 0 2 0 2 1 2 0 2 aeaet wvl l
. ub n o M b ofal c an L a A Jle cec at a T
A vddt hn o s an U emt n n oait ni o ibyd r c a N tar o e t c a, vt ee r n lo A mf ne ie m )s 9 7 7 5 7 e xci i 1 9 nnuec 2 M ona r at pt l n (m O 0 O 1 1 0 ooSma c, aeuti x N pso gcs cE AiC D noUo dt O nl I d eadsnian T t oa adp l NAL me nao yb l Lnf C U I 2 0 9 aa wHd et odh r . h aeuo TC AL te. ar o
'mr
- n o
t vsnn aaai pt b n s t a TA onodesm ole mtis ice F 'e m it a r ci x r SC o r uS po eit k ii m g a F a t S n r r f dicdr st i N E pC i n r a e r c n o b u a F e r lele yv e et i US A n i F A s S n iup qm snR OO F n is u s e n a y e e s eastiu1 r sere 0 r k n n HD i t t lv E. x a a a ok sc2 L A E A H V B nH gmoii nss AE T Hn inn ataoo CI e ner pnt it it me gcc e aa T S- lpobi mtam 8 9 0 1 2 3 : ah eoo SWVLl RF et u 2 2 3 3 3 3 s e OF SS N t o)234 )))) FO , N((1 ((( 5 m
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 43 OF 129 Agure 1 23 (RM 666.0) 4 7 i 75 M
/LE
%g%,
CALIFORNIA JUNCTION BLAIR l
\ .,, 7 . - .,
~
'J6
! s
- q. 22 4 i, L 10* wng ,,p o g,,,
CALHOUN STATION 24 . 28 h eli ' i 30 31* l *15 ,/ 18 s
- 75 +26 , , , , ,
STATE P N,*%25* l
)
7 F T. CALHOUN %
/ ,,,
s f 2. f )s 22
.__5 ,
R9
1 1 0 0 0 1 9 4 + + 9 02 01 1 a
- E 5
- E 5
- - - R 0- F B 1 1 e h
MO f t C4 7 1 0 2 0 1 0 2 2 0 1 0 o2. D4 3 1 + + + 0- + + e s5 OE 3 s
- 2 E E E E E on 6 5 8 0 8 0 HG 2 C 1 1 1 1 1 8 h t
h c ito h e C PA s
) it e t D 4 1 2 1 2 2 1 wS h it 3 0 0 0 0- 0 0 r ,
L 1 + + + + + et I w L - E E E E E E h r e ( s 5 3 5 0 5 0 t a c n C 1 1 1 1 1 6 eP g n o oo a t t dr it ,t c 0 0 2 1 sn o ' e 0 0 0 t n a c 1 0-e c u usru t 3 + + + a e 1 E - E E - E n D 1
- 0 0 0 0 l f
f ep i f 1 1 7 6 e o t t r b it 1 no lap l la n 5 0 Pe h 9- + L b E 5
- - - - - sR ag s
s e,. N ein t n 1 lb a t e o w 1 iare f it p m e r M L 5 0 u 9- + nO e s is r E - - - - - d l a s Z 5 i ta e y en l a 1 ar e m la m M n t a n t n E A 5 1 0 0 2 h or e e 6- + + t i m S l p n E E - - - - sv k n n U Z 0 6 aE o r E m 3 2 el pa i v a n C S 2 r ic eg e N l 8,0 1 0 0 h r o E a 56- -
+ + t lo Oio f R
t n oo E E - - - - d E e CC 5 3 .d e 1 1 deRa s F m r l u E n ea s r R o r 9 1 0 2 0 d u e
+ + isn t e
i v 5-E E - - - - nn n e 0 6 oA c e m E F is r 3 2 bt eh o d o oin t F 1 2 t n s 4 0 0 e d e 5- + + r e c e n E E - - - - at r s e L s o i t 5 3 n A i l i M 1 1 epe U b d i r im.u3 N a lcd p 3 un lo 1 M. A a 3-0
+
na m4 C M C E - - - - - ed r e G H se ed N n 0 ezy hi t u O O it o 2 hynla t rG o f y h e M I T c e l na sr t f NA t s s ta 2 0- o e ieto o OLU e oe - - - E - - t a b it la l l l I D r GB 0 h o i u b g t r M_ TC " 1 t s nla ae p P a AL - a aR in TA l 3 el a cf SC 4 s g
- g g mh n o d io sn e NE US l
b e it U n L
/
i C p k )t
/
ie Cw p( L
/
i C p i/m k) Cp
/
i y Crp( d k )t
/
ie Cw p( t s o ns, s de t co et i a in f e m OO a ei t ed d HD T ol c d n is d u d e L r d a s t n em D AE o o rt oc is e ir L CIT e s u m L l r e B
/
s u s v qo e lp n ol ed io TS - m ela t t n e r o ib t r o hb Ta e c Rr e h T RF a r mu c s m s aaP t t OF S t e h lk oie br rt s i d sf eed aaggo FO a is i iaa e r eeeo ' 2 3 W F M APG S GLVVF
lj!l l il) l l ll!i i ll I!lIiI4 0 2 2 19 4 0 c 0
+ 9 1
02 - E - E - - l R 01 a 0 0 g t a 0 F B 2 3 n n f e MO i lp o C5 7 1 3 1 1 3 es m D4 3 1 0
+
0
+
0
+
0
+
0
+ m a bet v no n OE s
- E 0
E 0 E 0 E 0 E 0 s l l atiai v l r HG C 5 2 7 2 2 h e hecPn sjfE C PA t t r ot bo 3 n o l peuc a 4 1 1 1 3 l 3 0 0 0 0 0 i
' + + + + + d 1
- E E E E E e e ssig
; s 0 0 0 0 0 roe
; C 3 1 6 1 1 t
c e he i sdro eio l 4 r t e ththd i 0 0 0 0 1 2 d ,t t a a 3 1
+ + 0- 0
+ e t s noR S 1 E - E E E r nanl a l
a l
- 0 0 0 0 a eh s u t
n 2 3 9 1 e v utra n mewn e 2 o 0 eta yA m 5 0 b 1 t t n 9-E
+
a t nreie a gi v h o b 0 d l t i v r N 4 t e , 3 Prct oan n s 3 f oi E i l n e l ooidtde 2 s o v l t l a i n 5 9-0
+ e i t
a L e uarb r i s r E - - - - d i t r g suf eqo c n Z 0 l c n r o 4 u e i t n e s e el se i n c r t a o n o hivd r 2 4 o p t cledn C e i E t n 5 0
+
0
+ d R el i S e 6-n E E - - - a r rbda a ue U n c Z 0 0 e
d pu rd e 3 2 nl st E o h t 2 2 aar ar C C f n l e de ep o N 2 4 o v E i t y v 0 4 0
+
0
+ e i t
o e a L tenme ce r R o E E - - - n r egehe E i t c C 0 0 o t n e n g t F a 3 1 n c i t r e etb dthfl E o a n o il R i d 8 3 4 h t C o p e efd roe hsa a 5-0
+
0
+ e R ari r R
r C o E 0 E 0
- - - r o , e vb eun qo o eit f
s 1 3 n m 1 1 l e omrd bet i l e v 9 2 0 4 0 h e i n o e v d amon noc 5- + + t a L ea L e e E E - - - w r g t oie s L F 0 0 d t n n s tth A g 4 1 e e tr i i l eo rt U n t t c n o e s pt , N A i t r o 4 3 0 4 0 i m o p C e s o oe dr n e p 5- + + b R h s v M n E E - - - u tl aie e 0 0 s n uh N R M 1 3 e a nTna O I
- b hn t .
T 4 l r a 2.h c 4 l a NA 4 3-0
+ h el hia3u s OLU e I H E 0
- - - - s on nn ttd T
ALC ba l 2 t r o ste a i r TA T p dp eo1 et r SC e s L g L m g r h ce 3vep o NE i t n / i k l ie
)t /
i
/
i k
/
ie
)t e: uhnwe nt o oR US U Cp Cw p( C p C p Cw p(
i nd oifi t t n ch OO oua i dde;n g HD L d r ae rtSti s r a s t nta AE T o o r oc t nc ni , CI l e s e B r / n sedu oi Ned emt hbr I er ue TS p t elbro u am p _ RF a m r ela mu s r o s t aaP Am WsPeO OF oiec t t S e h sf eed FO t a is k l i b rt s r aa aa9go r eeeo ' W F M iAPG GLvVF il l ll
l FORT CALHOUN STATION CH-ODCM-0001 1 OFF-SITE DOSE CALCULATION MANUAL REEERENCEESE PAGE 46 OF 129 4.2 Land Use Survey 4.2.1 Limiting Condition for Operation l A. A Land Use Survey shallidentify 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 I 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 alltimes ACTION: l I a) If it is leamed from this survey that milk animals are present at a location which yields a calculated dose greater than from previously sampled location (s), the new location (s) shall be added to the monitoring program. The 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 E monitoring program. Also, any location (s) from which milk can no 3 longer be obtained may be dropped and replaced if practicable from the monitoring program and the Nuclear Regulatory Commission shall be notified 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 l 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. Tais information l 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). 1 l R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 47 OF 129 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 Environmental 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. I R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCUl.ATION MANUAL REFERENCE USE PAGE 48 OF 129 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 g contained in 10 CFR Part 50.36a; Reg. Guide 1.21, Rev.1; Reg. Guide 4.8, Table 1; g 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. l The Radioactive Effluent Release Report shall include: g A. A summary of the quantities of radioactive liquid and airbome effluents and solid waste released from the plant as outlined in Regulatory g Guide 1.21, Revision 1. B. A summary of the meteorological conditions concurrent with the release of airbome 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 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 l 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. g I i i R9 i
-_-_-__________________________a
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 49 OF 129 [' 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 Spacifications 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 y report contains the data gathered from the Radiological Environmental t Monitoring Program. The content of the report shall include: r A. Summarized and tabulated results of the radiological environmental L sampling / analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event that some results are not available, the r report shall be submitted noting and explaining the reasons for the t 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 hours prior to the first sample in which the limit was exceeded.
[ 2) Results of the last isotopic analysis for radioiodine performed prior to exceeding 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 radiolodine concentrations. k I R9 ,
l l FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEEEENCEMSE PAGE 50 OF 129 j 5.2.2 E 3) Purification system flow history starting 48 hours prior to the first sample in which the limit was exceeded.
- 4) Graph of the 1-131 concentration and one other radiciodine isotope I
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.
5.2.3 Special Report if the limits or requirements of Sections 3.1.2.A,3.1.3.A,3.2.2.A,3.2.3.A, ( 3.2.4.A,3.3.1.A and/or 4.1.1.A(3) are exceeded, a Special Report shall be j issued to the Commission, pursuant to Technical Specification 5.16. This report shallinclude: A. The results of an investigation to identify the causes for exceeding the ! specification. l B. Define and initiate a program of action to reduce levels to within the g specification limits. 3 1 C. The report shall also include an evaluation of any release conditions, j environmental factors, or other aspects necessary to explain the { condition. l 5.2.4 EPA 40 CFR Part 190 Reporting Requirements l With the calculcted 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 rt to 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 ) 5 25 mrem to the total body or any organ (except thyroid, which is limited to l 5 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 1 40 CFR Part 190 standard. The submittal of the report is to be considered a j timely request and a variance is granted pending the final action on the l variance request from the Commission. J i l R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL Rgff,Eg,N_GE_ME PAGE 51 OF 129 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. It will 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/O 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 ll 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 XOODOQ 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 X/O 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/O 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, conform with the Nuclear Regulatory Commissions Reg. Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases. l R9
I FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 52 OF 129 5.5 References / Commitment Documents 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 1 Regulatory Guide 1.111, Rev.1 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors. l Regulatory Guide 1.113, Rev.1 - Estimating Aquatic Dispersion of Effluents from j Accidental and Routine Releases for the purpose of implementing Appendix 1. j Nureg-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear
?
Power Plants. Nureg-0472, Rev. 3 - Draft Radiological Effluent Technical Specifications for PWRs. Regulatory Guide 1.21, Rev.1 - 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 10, Part 20 Code of Federal Regulations, Title 10, Part 50 Fort Calhoun Revised Environmental Report (Unit No.1)-1972 Fort Calhoun Technical Specifications (Unit No.1) Updated Safety Analysis Report CID 920102/01 Implement Recommendations of Memo FC-0133-92, Part 1, Table 2.2.1 Action 4 I I I l l l R9 Il
{ FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 53 OF 120
- 6. BASIS 6.1 Instrumentation 6.1.1 Radioactive Liquid Effluent Instrumentation The Radioactive liquid emuent instrumentation is provided to monitor and
[ 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 11 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. 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 gaseoi's effluents during actual or potential releases of liquid effluents. The Alarm / Trip setpoints for these instruments shall be calculated in accordance with Part ll 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 60,03 and 64 of Appendix A to 10 CFR Part 50, 6.2 Radioactive Effluents [ 6.2.1 Radioactive Liquid Effluents { A. Concentration This specification is providad 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 11, 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 ll.A design objectives of Appendix 1,10 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-135 is the controlling isotope and its effluent concentration in air (submersion) was converted to an ( equivalent concentration in water. R9 ?
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 54 OF 129 g 6.2.1 B. Dose This specification is provided to implement the requirements of Sections ll.A , Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operatina flexibility and at the same time implement the guides set forth in Sect.oa 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 ll of the ODCM implement the requirements in Section Ill.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 ll 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 1," Revision 1, October 1977, and Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1,"
April 1977. 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 I 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 1 to 10 CFR Part 50 and design objective and in Section ll.D of Appendix A to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the liquid radwaste l treatment system were specified to ensure the design objectives set l forth in Section ll.A of Appendix 1,10 CFR Part 50 for liquid effluents are not exceeded. l R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 55 OF 129
,I 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 l limits of 10 CFR Part 20, Appendix B, Table 11, 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 I 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 3 in airborne effluents shall be controlled such that the instantaneous 5 concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airbome effluents at the unrestricted area boundary. To support plant operations, Supervisor-System
;I 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 l 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 j 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 j 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 Part 20.1301(a). I l w . t-- L . R9 M
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEgftENCE USE PAGE 56 OF 129 6.2.2 B. Dose - Noble Gases This specification is provided to implement the requirements of Sections ll.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix i 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 Ill.A of Appendix l that conform with the guides of Appendix 1 to be shown by calculational procedures based on models and data i 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 ll of the ODCM for calculating the doses due to actual release rates of , radioactive noble gases in gaseous effluents are consistent with the 1 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 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111. I I Il R9 3
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEEBfEGEMSE PAGE 57 OF 129 6.2.2 C. Dose - l-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 ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I 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 Ill.A of Appendix i that conform with the guides of Appendix l 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 ll 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 1.111, 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.
{ l R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 58 OF 129 6.2.2 D. Gasecus 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 providos assurance that the releases of radioactive materials in gaseous efduents 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 l of Appendix A to 10 CFR Part 50. The specified limits goveming ihe use of appropriate portions of the systems were specified to ensure the design objectives set forth in Section ll.B and ll.C of Appendix 1, 10 CFR Part 50 for gaseous effluents are not exceeded. I I l Il I I I R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BEEEEENGE11EE PAGE 59 OF 129 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 1,10 CFR Part 50, and if direct radiation doses ( including outside storage tanks, etc.) are kept small. The Special Report shal! 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 5t dose contributions from other nuclear fuel cycle facilities at the e .e site or within a radius of 8 km must be considered. If the dose t' ,y MEMBER OF THE PUBLIC is estimateo to exceed the rr .coirements 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 10 CFR Part 190 or with the design objectives of Appendix l to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit cc 10 CFR Part 20.1301. R9 y
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 60 OF 129 6.3 Radioactive Environmental Monitoring 6.3.1 Monitoring Program l 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 l 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 E operational experience. E 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 g program are made if required by the results of this survey. The best survey E information from door to door, aerial or consulting with local agricultural authorities, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix 1 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 kglyear) 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 l vegetation yield of 2 kg/m2. I
.I R9 4
l
p [- FORT CALHOUN STATION CH-ODCM-0001 S OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 61 OF 129 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 materialin 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 l to 10 CFR Part 50. ( [ [ [ [ [ [ { { { t i R9 L -
FORT CALHOUN STATION CH-ODCM-0001 I OFF-SITE DOSE CALCULATION MANUAL BEEEEENCEllEE PAGE 62 OF 129 I I I I I Il PART11 f CALCULATIONS l I I I I I I I R9 I
[, FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 63 OF 129 [ 1. EFFLUENT MONITOR SETPOINTS 1.1 Liquid Emuents 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 empy 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 emuent 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.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid emuents 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 2.0 E-04 pCi/ml total activity. { The liquid effiuent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid emuents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. [ The liquid emuent monitoring instrumentation HIGH ALARM setpoints shall be f es+ablished low enough to ensure that the concentration of radioactive material l released in liquid emuents at site discharge will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B Table 2, Column 2. Cs-137 is used to calibrate the liquid effluent monitors. L L i [ R9 L -
CH-ODCM-0001 I FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUA1. REFEREMCE USE PAGE 64 OF 129 g NOTE: If the annual average X/Q value exceeds 1.4E-04 sec/m 8, consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.0E-09 pCi/ml 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 E generator blowdown lines and automatically close the blowdown g 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 ilmit at the unrestricted area boundary of 1.0E-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 mcximum allowable concentration in the blowdown line is calculated as follows: g uax , (1.0E-05 pCl/ml) (F) y Where: 1.0E-05 pCi/mi = 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 l required.) 3 C. = Maximum allowable blowdown concentration (pCi/ml). R9
'[ FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCF,ygg PAGE 65 OF 129 { NOTE: Setpoints may be recalculated based on adjusted dilution flow and adjusted blowdown flow. The High Alarm Setpoint (CPM) = { 0.75 [((s,)(C,)) + 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 /pCi/ml). (Sensitivity based on Cs-137). [ B = Background (CPM) { Cm = Maximum allowable blowdown line activity (pCi/ml). 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. { 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 controiled below ten times the 10 CFR Part 20 limit of 1.0E-06 pCi/mi at site discharge for unidentified isotopes by the high alarm setpoint which closes the overt >oard flow control valve. L L F R9 L
r ] FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 66 OF 129 1.1.1 B The following calculations for maximum concentration and alarm setpoints are valid when Monitor Tank discharge is the only liquid Ei release pathway. For simultaneous radioactive liquid releases of monitor tank discharge and steam generator blowdown, refer to El-Section 1.3. The maximum afiowable concentration in the overboard discharge header is: C urx = 0.0E07, d#m0 W I I Where: 1.0E-05 pCi/mi = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Pait 20, i 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.) Cm = Maximum allowable activity in discharge header (pCi/ml). I l l R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 67 OF 129
, 1.1.1 B The High Alarm Setpoint (CPM) =
0.75 [((S,) (Cuy)) + 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 I Number 050-0285 and Telecon FC-472-77. 10% tolerance to account for the difference in detector I sensitivity for the range of isotopes detected. S, = Detector sensitivity factor (CPM /pCi/ml). (Sensitivity based I on Cs-137). C. = Maximum allowable concentration in discharge header I (pCi/ml). B - Background (CPM) l 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 I fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint. I [ [ [ c R9 L F e- .
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 68 OF 129 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 airbome 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 Processina Building (LRWPB)- Noble gas monitoring and particulate and iodine sampling is provided by RM-043. This E radiation monitor / sampler does not serve a control function. 5
- 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 i 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 l ' 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. l The airbome 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. I R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 69 OF 129 1.2.1 A%orne Efiluent 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 through 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 5.0E-07 pCi/cc, based upon Xe-133, 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 Auxiliaiy Building Exhaust Stack, Condenser Off-gas and the LRWPB Exhaust Stack, refer to Section 1.3. The maximum allowable release rate for stack airbome activity is calculated as follows:
-06 pC//cc R, pC//sec = .
x 1.0E+06 cc/m 8 I X/Q sec/m
- Where:
2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon l 8 Xe-133). X/Q sec/m = Annual average dispersion factor at the I unrestricted area boundary from ODCM Part il Table 4, Controlling Locations, Pathways and Atmospheric Dispersion For Dose Calculations. 1.0E+06 cc/m2 = Constant of unit conversion. E { R9 F
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BEEERENGE USE PAGE 70 OF 129 1.2.1 A The High Alarm Setpoint(CPM): I1
* +B Setpoint = 0.75 (F,) (28317) ,
Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor VIAS response in 3 accordance with License Event Report 77-17, Docket 5 i 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-133) 60 = Conversion (seconds to minutes). 8 28317 = Conversion factor (ft to cc). Ij F, = Auxiliary Building Exhaust stack flow rate (SCFM). (Default j maximum flow rate is 122,500 cfm for 3 Auxiliary Building I exhaust fans and 2 containment purge fans in operation. Other flow rates may be used, as required.) lI Rm = 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 l actions prior to exceeding the Alarm Setpoint and VIAS actuation. l l
'l R9
)
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 71 OF 129 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 5.0E-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 airbome release pathway. For simultaneous airbome releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.3. l b The maximum allowable release rato for condenser air ejector monitor is 3 as follows:
-06 pC#ce R, pC//sec =
1.0E+06 cc/m ' I X/O sec/m
- Where:
2 5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the l unrestricted area boundary (based upon Xe-133). X/O sec/m' Annual average dispersion factor at the I = unrestricted area boundary from ODCM Part 11, ' Table 4, Controlling Locations, Pathways and Atmospheric Dispersion For Dose Calculations. 1.0E+06 cc/m$ = Constant of unit conversion. I I I \ l l l R9 k
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 72 OF 129 The High Alarm Setpoint(CPM): y 3
" +B Selpoint c 0.75
, (F,) (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 I other than Xe-133 towards the total ECL fraction sum. S, = Detector sensitivity factor (CPM /pCi/cc). (Sensitivity based on Xe-133) 60 = Conversion (seconds to minutes). 28317 = Conversion factor (ft* to cc). F, = 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.) l Rm = Maximum Allowable Release Rate in pCi/sec. B = Background (CPM) I 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. I R9 I
FORT CALHOUN STATION CH-ODCM-0001 i OFF-SITE DOSE CALCULATION MANUAL BEffBEN9fLLI.SE PAGE 73 OF 129 1.2.1 C. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and lodine and Particulate Sampler (RM-043) RM-043 is located in the Radwaste Building and samples the LRWPB I Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-133 at the unrestricted area boundary. l The following calculations for maximum release rate and alarm setpoint are valid when the LRWPB Exhaust Stack is the only airbome release pathway. For simultaneous airbome releases from condensor off-gas, I Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.3. l The maximum allowable release rate for RM-043 is as follows: l Rm pC//sec = 2.5E-06 pCi/cc x 1.0E+06 cc/m 8 X/Q sec/m 8 Where: 2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon I X/Q = Xe-133). Annual average dispersion factor at the unrestricted area boundary from the ODCM I Part II, Table 4, Controlling Locations, Pathways and Atmospheric Dispersion for Dosed Calculations. 1.0E+06 cc/m = Constant of unit conversion E [ L R9 r l-- .
~ ___ _ _ _ . _ _ _
7 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REEEEg_NCfdlEE PAGE 74 OF 129 NOTE: This monitor alarms in the Control Room. There are no I automatic control functions associated with the actuation of the alarm. 1 The High Alarm Setpoint(CPM): Setpoint = 0.75 +B
, (F,) (28317) ,
Where: 0.75 = An administrative correction factor which includes the g following: E 15% tolerance to ensure radmonitor VIAS response in ) accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. l 10% tolerance to allow for the contribution of noble gases I other than Xe-133 towards the total ECL fraction sum. S, = Detector sensitivity factor (CPM /pCi/cc). (Sensitivity Isased on Xe-133) i 60 = Conversion (seconds to minutes). 8 28317 = Conversion factor (ft to cc). F, = LRWPB Exhaust stack flow rate (SCFM). (Default flow rate I is 28,700 cfm. Other flow rates may be used if required.) Rm = 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) l the value of the high alarm setpoint value so that significant increases in gI activity will be identified, prior to exceeding an Unrestricted Area m' fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint. 1 R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 75 OF 129 1.3 Simultaneous Release Pathways NOTE: if the annual average X/O value exceeds 1.4E-04 sec/m8, consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.0E-09 pCi/ml at the unrestricted area boundary with 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) controlliquid releases so that ten times the 10 CFR Part 20 ilmit of 1.0E-06 pCi/mi 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 radioact.ve relenses, 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 fodows: C, = K oC yg, + K,C yg, I C' = Ko (1.0E-05 pC#ml) (F) fo
+
K, (1.0E-05 pC#m/) (F) fi Where: I C, = Sum of individual maximum allowable concentrations for Steam Generator and Monitor Tank prior to dilution for simultaneous liquid releases (pCi/ml) l Cwo = Maximum allowable concentration in Steam Generator blowdown Line (pCi/ml) Cui = Maximum allowable concentration in Monitor Tank Discharge Line (pCi/ml) L = Ko Allocation facter for Steam Generator (See Table 1) K3 = Allocation factor for Monitor Tank (See Table 1) F = Total dilution flow in Discharge Tunnel (GPM)
=
fo Steam Generator Blowdown flowrate (GPM) f, = Monitor Tank Discharge flowrate (GPM) p R9 u F -
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL SEFERENCE USE PAGE 76 OF 129 The High Alarm Setpoint for Steam Generator Blowdown monitors, RM-054A/054B, will then be: Alarm Setpoint (CPM) = 0.75 fa S,, Cyg,) + B, The High Alarm Setpoint for Monitor Tank Discharge Monitor, RM-055, will then be: Alarm Setpoint (CPM) = 0.75 (K, S,, Cug,) + B, , Where: So = Detector Sensitivity factor for RM-054A/054B, CPM /(pCi/ml), based on Cs-137. Sn = Detector Sensitivity factor for RM-055, CPM /(pCi/ml), based on Cs-137. Cao = Maximum allowable concentration in S/G Blowdown line. (pCi/ml) Cui = Maximum allowable concentration in MT Discharge line. , (pCi/ml) Bo
= RM-054A/054B background countrate. (CPM)
B, = RM-055 background countrate. (CPM) l Ko , 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 J will be identified, prior to exceeding an Unrestricted Area fractional sum of l 1.0. It will also provioe additional time for corrective actions prior to exceeding the Alarm Setpoint. I < R9
I [ FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 77 OF 129 1.3.2 [ Airbome Release Pathway The noble gas radiation monitors (RM-043, RM-057, and RM-062/RM-052) { control airbome releases so that five times the 10 CFR Part 20 limits of 5.0E-07 pCi/cc for noble gases at the unrestricted area boundary is not 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 1.2.1 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 re! eases is: Max. Release Rate = K,R w' = K, 06 @ cc i1 X/o sec/m
- Where:
R. = RM-062/RM-052 release rate (pCi/sec) [ R, = RM-057 release rate (pCi/sec) { Rm = RM-043 release rate (pCi/sec) X/Q = Annual average dispersion factor at the unrestricted area boundary from the ODCM Part II, Table 4, Controlling [- Locations, Pathways and Atmospheric Dispersion for Dosed Calculations. b K, - K 3 = Allocation factors. See Table 1. 2.5E-06 pCi/w = 5 times the 10 CFR Part 20 Limit at the unrestricted area [ boundary (based upon Xe-133). [ [ R9 ( _ ---- -
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 78 OF 129 The maximum release rate Rm then: (K,) (2.5E-06 pCl/cc) (K,) (2.5E-06 pCi/ce) (K,) (2.5E-06 pCl/cc) g, XIQ sec/m
- X/Q sec/m
- X/Q sec/m
- m*
The High Alarm Setpoints for the noble gas monitors will then be:
" +B RM-062/052 = 0.75 K,
, F, (28317) ,
" +B RM-057 = 0.75 K
\ , (F,) (28317) ,
I RM-043 = 0.75 K, +B
, , (F,) (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, - K 3 = Allocation factors. See Table 1. S, = Detector sensitivity factor. F, = Vent stack flowrate. (Condenser off-gas flowrate for RM-057, LRWPB Exhaust stack flow rate for RM-043, Auxiliaty Building Exhaust Stack flow rate for RM-062/052). Rm = Maximum Allowable Release Rate in pCi/sec. B 60
=
=
Monitor background count rate. Constant of unit conversion (60 sec/ min). l The Alert Se oint will be chosen less than or equal to one fifth (1/5) the value of the h h alarm setpoint value so that significant increases in activity will be identifi , prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to E exceeding the Alarm Setpoint. 5 R9 f l'
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL BgBLRENCE USE PAGE 79 OF 129 Table 1 " Allocation Factors for Simultaneous Releases" NOTE: The Fort Calhoun Station is capable of performing simultaneous airborne releases given that the sum of the Unrestricted Area Fraction Sum for all airbome releases remains less than or equal to 1.0. l A. Allocation Factors for Simultaneous Airborne Releases l l
- 1. Auxiliary Building Exhaust Stack Total: 0.80 l l
K, Noble Gases (RM-062 or RM-052) 0.70 lodine / Particulate / Tritium 0.10 l Contributing Pathways- l a) Auxiliary BuildMg 0.10 b) Containment Building 0.65 c) Waste Gas Decay Tanks 0.05
- 2. Condenser /Off Gas Total: 0.10 K2 Noble Gases (RM-057) 0.05 Tritium 0.05 Contributing Pathways:
a) Condenser Off Gas 0.10 l
- 3. Laboratory and Radioactive Waste Building Exhaust Stack Total: 0.10 l K3 Noble Gases (RM-043) 0.05 l lodine / Particulate 0.05 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 given that the sum of the Unrestricted Area Fraction Sum for all liquid releases remains less than or equa! to 1.0. B. Allocation Factors for Simultaneous Liquid Releases
- 1. Ko Steam Generator Releases (RM-054A/0543) 0.30
- 2. K, Waste Liquid Releases (RM-055) 0.70 Liquid Release Total 1.00 R9
FORT CALHOUN STATION CH-ODCM-0001 I .. OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 80 OF 129 Figure 1
\ \ Tru.
\ sie.
\ IO WA s, l
s UNRESTRICTED \ s, AREA BOUNDARY l
, NEBRASKA .-RESTRICTED N s j AREA
^
\
N
\ c FORT -
MET \ g l TOWER 2 b '/ ' CALHOUN UNIT #1 3
/ s s
, ,- ,/ W ' ' ~~~_ lisg 8
j { SUBSBTION ) N gug, 4/Jeg.,% CONTROLLED
's V -
ADMIN. NQ s x TO AREA BLDG. BLAIR ( ) m-- , TRAINING ' CENTER sk J I
/ \ 3
)
,e UNRESTRICTED AREA j
\ E LIQUID EFFLUENTS DISCHARGE 'N
' I AIRBORNE EFFLUENTS DISCHARGE 's TO I
o 1/2 1 SCALE IN MILES EXCLUSION AND SITE BOUNDARY MAP l R9 I
y FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 81 OF 129 Figure 2 J I I HOTEL TANKS S/G A BLOWDOWN S/G B BLOWDOWN ; RAW WATER I MONITOR V A N TANKS (1) (2) t
=
'I = I cc I l i I OUTFALL ( CIRCULATING U If (} ( () WARM WATER RECIRCULATION fus RIVER 1r RIVER If
, ~_
Q RM-054A g @ RM-054B j Q) RM-055 I I l LIQUID RADIOACTIVE DISCHARGE PATHWAYS I R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 82 OF 129 Figure 3 REACTOR COOLANT AUXILIcRY SYSTEMS g73 PROCESS WASTE cvts sie.dorr NN Floor Dreins foutpment Dreins laun*v Weste Sump Flows RC Loop Drains Sho er Dreins y F F s,e,, mem oc
'h', , )
- y d ,
5530 Ce!. ( )
,5 gj'g- 1200 Gal.
000 00 I y v Weste Filters V l 50 Microns Deminereli2er Vessels 30 Cu. Ft. w [bercoal Filter 69 Ca. f t. (optionell OQ Monitor IeYs 6770 Gol, oe 4 h Overboard Hebder l (Io b1ver) LIOUID RADI0 ACTIVE WASTE DISPOSAL SYSTEM R9
7: FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 83 OF 129 reymu ,
)(
RM-043 Noble Gas Monitor, and lodine & Particulate Sampler C LRWPB Laboratory LABORATORY AND RADIOACTIVE WASTE PROCESSING BUILDING l ll RM-062,052 Noble Gas Monitor lodine & Particulate Sampler
]\
RM-057 Noble Gas Monitor CONDENSER OFFGAS AUXILIARY BUILDING EXHAUST STACK Condenser Auxiliary Building Containment i Ventilation Building Ventilation i AIRBORNE EFFLUENT DISCHARGE PATHWAYS I R9 1
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE B4 OF 129 l Figure 5 I A" l Turbine h Bu ding ) Ventilation W
, , Condenser Stack To Atmosphere 122.500 'I S C. M
-s -s g To Roof Condenser Vacuum Pumps
+
,, Charcoal l Absorber
+ :
'$ ash w Cas Holdup Tanks (4)
( 400 Curt (each) ) > - HEPA Filter , l WASTE GAS AND CONDENSER OFF-GAS SYSTEMS i Inlet m Roll 5'a ns > D Filters , Containment / ) fe*,*hY l h,0 Purge f
~
I"I"
, Containmen
HEPA 1 Filter l 1
Cooling and Internas
.' > 5 50.000 SCFM " i Recirculation Purge !
System- HEPA Outlet Charcoal Filters CONTAlb;ENT BUILDING VENTILATION CONTROL Charcoal Filters p Fuel Handling HEPA Areas - Filter C3 Fans Safety 1 D Fi t s reas .d j j Other 172.500 SCFM Areas Ground AIRBORNE RADIOACTIVE WASTE DISPOSAL SYSTEM R9 I I i
i FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 85 OF 129
- 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 l 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 ana'yses 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: 1 Radionuclide concentration at site discharge:
a, f A,= F+f l A wec, i Where: A, = concentration at site discharge for radionuclide (i), in pCi/ml. a, = concentration of radionuclide (i) in the undiluted effluent, in pCi/ml. f = undiluted effluent flowrate, in gpm. F = total diluted effluent flowrate in gpm. wec, = water effluent concentration limit for radionuclide (i) per 10 CFR Part 20, Appendix B, Table 2, Column 2. I l R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 86 OF 129 NOTE: In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable. 2.2 Airbome Effluent Concentrations The concentration at the unrestrlcted area boundary, due to airbome 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 airbome 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 I summation at the unrestricted area boundary, the following equations will be used: A, = K, Q, (X/Q) A' and [ 1., ECL, s1 Where: A, = Concentrativii of radionuclide (i) at the unrestricted area boundary 8
= Constant of unit conversion. (1.0E-6 m /cc)
Ko ECL,= Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, , Column 1 value for radionuclide(i)) Q, = The release rate of radionuclide (i) in airbome effluents from all vent releases (in pCi/sec.) (x/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Controlling Locations, Pathways and Atmospheric Dispersion For Dose Calculations (Table 4) l As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack, g 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 time 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 airbome s? fluent dose rate. R9
[. FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 87 OF 129 [ For administrative purposes, more conservative alarm setpoints than those as t 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. [ 3. RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Emuent Dose Calculations Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish,2) drinking water, anu 3) Shoreline deposition. Fish are considered to be taken from the vicinity of the plant 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 ststes that during Low-Low river conditions, the concentration at Omaha's water intake will be 514% 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 individualin 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: [ e during any calendar quarter 51.5 mrem to total body { 55.0 mrom to any organ and e during any calendar year s 3.0 mrem to total body 510.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid emuents. f R9
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL MN_GFJ1EE PAGE 88 OF 129 3.1.1 Doses from Liquid Effluent Pathways A. Potable Water R,g = 1100 Q,D,,gexp(-A,t,) F Where: Rg = is the total annual dose to organ (j) ofindividuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem /yr. U, = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in t/yr. (Table 6) M, = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless. (Table 4) F = is the flow rate of the liquid effluent, in ft*/ sec. O, : is the annual release rate of radionuclide (i), in Ci/yr. Dm = 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 /pCl. (Tables 13-16) l A = is the radiological decay constant of radionuclide (i), in hr'. t, = is the average transit time required for radionuclides to reach the point of exposure. For intemal dose, t, is the total time elapsed between release of the radionuclides and ingestion of water, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft 8/Ci
- sec
- L)
I I R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 89 OF 129 3.1.1 B. Aquatic Foods R,,j = 1100 U"M' f Q,8,D,,,jexp(-A,t,) f i=1 Where: R. = is the total annual dose to organ (j) ofindividuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem /yr. U,, = 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) M, = is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. (Table 4) F = is the flow rate of the liquid effluent, in ft 8/sec. Q, = is the annual release rate of radionuclide (i), in Ci/yr. B, = is the equilibrium bioaccumulation factor for radionuclide (i) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/ liter), in (pCi/kg)/(pCi/ liter). (Table 3) D. = 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 /pCl. (Tables 13-16) A = is the radiological decay constant of radionuclide (i), in br'. t, = is the average transit time required for radionuclides to reach the point of exposure. For intemal dose, t is the total time elapsed between release of the radionuclide,s and ingestion of food, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft*/Ci
- sec
- L)
R9 o . . . .
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 90 OF 129 3.1.1 C. Shoreline Deposits R,,j = 110,000 U,, M,W F Q,T,,D,,,j[exp(-A,t,)][1 -exp(-A,t3)] l Where: l > Rg = is the total annual dose to organ (j) of individuals of age { group (a) from all of the radionuclides (i) in pathway (p), in l I mrem /yr. U,, = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p), in hr/yr. (Table 6) l M, = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 4) W = is the shore-width factor, dimensionless. (Table 17) F = is the flow rate of the liquid effluent, in ft'/sec. Q, = is the annual release rate of radionuclide (i), in Ci/yr. T, = is the radioactive halflife of radionuclide (i), in days. D, = 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 pCi/m2 ). (Table 8)
.\ = is the radiological decay constant of radionuclide (i), in hr'.
t, = is the average transit time required for radionuclides to reach the point of exposure, in hours. (Table 17) li to = 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
- ft )/(Ci
- sec
- L)]
R9 I
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 91 OF 129 3.2 Airbome Efficent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix 1, restricts the dose to individuals in the unrestricted areas from noble gases in airbome effluents from the Fort Calhoun Station to the following limits: ~ e During any calendar quarter 55 mrad-gamma air dose 510 mrad-beta air dose and e During any calendar year 510 mrad-gamma air dose 520 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 I}}