ML18005B023
| ML18005B023 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/29/1989 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18005B021 | List: |
| References | |
| PROC-890829, NUDOCS 8909050097 | |
| Download: ML18005B023 (540) | |
Text
OS2 SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)
Revision 3.0 DOCKET NO. STN 50-400 CAROLINA POWER 6 LIGHT COMPANY 8909P5Po 89p829 p~R ~~~~~ , p~PPPAPP
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OS2 TABLE OF CONTENTS Section Title ~Pa e CONTENTS' TABLE OF ... .................... ........-...........
~ ~
LIST OF TABLES..... .................... ~ ~ ~ . ~ ........o..... ... iii LIST OF FIGURES................ ~ .... .. ~ ~ . ~ .. ~ '... ~ ~ . ~ ..........
1.0 INTRODUCTION
............ ~ ............................... ...... ~ 1-1 2.0 LIQUID EFFLUENTS.................................o...o...... 2-1 2.1 Monitor Alarm Set Point Determinations... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ --.. 2-2 2.2 Compliance with 10CFR50. ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2-15 GASEOUS EFFLUENTS................. . . ..........-.............
~ ~ ~ 3-1 3.1 Monitor Alarm Set Point Determination...... ~ ~ ~ ~ ~ ~ ~ ~ .. .
~ ~ ~ 3-1 3.2 Postrelease Compliance with 10CFR20-Based Technical S pecxfzcatxon 3.11.2..................................... 3-13 3.3 Compliance with 10CFR50.................................. 3-21 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.................. 4-1 5.0 INTERLABORATORY COMPARISON STUDIES............................. 5-1 5 .1 Obgectxve. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-1 5~2 Program....oooo..00.........................0..0. 1....... 5-1 6.0 TOTAL DOSE (COMPLIANCE WITH 40CFR190).......................... 6-1 6.1 Dose to the Likely Most Exposed Member of the Public..... 6-.1 6.2 Dose to a Member of the Public due to Activities Within the Sxte Boundary.............. ~ .................. 6-2 DCM/ODC-TOC Rev. 3.0
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OS2 TABLE OF CONTENTS (continued)
Section t Title ~Pa e 7.0 LICENSEE INITIATED CHANGES TO THE ODCM......................... 7-1 APPENDIX A Meteorological Dispersion Factor Computations...................................... A-1 APPENDIX B Dose Parameters for Radioiodines, Part>.culates, and Tritium................................ B-1 B.l Calculation of P 3.
.............................. B-1 B .2 Calculation of R...............-.........-..... B-3 APPENDIX C Radioactive. Liquid and Gaseous Effluent Monitoring Instrumentation Numbers..... ~ ..... .......
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OS2 LIST OF TABLES No. Title ~Pa e 2.1-1 Liquid Effluent Release Tanks and Pumps.................... 2-23 2.1-2 Set Points for Cooling Tower Blowdown Dilution Flow Rate (B).............................................. 2-24 2.1-3 Signal Processor Time Constants (T) for GA-Technologies Effluent Monitors.......................................... 2-24 2.1-4 Liquid Effluent Monitor Gamma Sensitivities (Sens g)....... 2-25 2.2-1 A.
1T values for the Adult for the Shearon Harris Nuclear Power Plant................................................ 2-26 202-2 Decay Factors.............................................. 2-28 3.1-1 Gaseous Source Terms....................................... 3-11 3.1-2 Dose Factors and Constants................................. 3-12 3.2-1 Releases from Shearon Harris Nuclear Power Plant N ormal Operat1on........................................... 3-17 3 ~2 2 Distance to the Nearest Special Locations for Shearon Harris Nuclear Power Plant (Miles)......................... 3-18 3 ' 3 Dose Factors for Noble Gases............................... 3-19 3.2-4 '. I Values (Inhalation) for a Child for the Plant......................... 3-20 Shearon Harris Nuclear Power DCM/ODC-TOC Rev. 3.0
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OS2 LIST OF TABLES (continued)
No. Title ~Pa e 3.3-1 thru R Values for the Shearon Harris Nuclear Power Plant........ 3-32 3.3-19 4.1 Radiological Environmental Monitoring Program.............. 4-2 A-1 thru X/Q and D/Q values for long-term ground-level releases A-4 at special 1 locations.......................................
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A-4 A-5 thru Relative undepleted concentration, relative depleted A-12 concentration, and relative deposition flux estimates for ground-level releases for standard and segmented distance locations for long-term releases.................. A-5 A-13 Shearon Harris Nuclear Power Plant on-site joint wind frequency distributions for 1976-1987...................... A-13 A-14 Shearon Harris Nuclear Power Plant site information used for ground-level calculations with NRC 1l XOQDOQ II Program....................................... A-16 B-1 Parameters for Cow and Goat Milk Pathways.................. B-15 B-2 Parameters for the Meat Pathway............................ B-16 B-3 Parameters for the Vegetable Pathway....................... B-17 DCM/ODC-TOC 1v Rev. 3.0
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OS2 LIST OF FIGURES Noi Title ~Pa e 2.1-1 Liquid Waste Process Flow Diagram..........,............... 2-29 2.1-2 Liquid Effluent Flow Stream Diagram................ ~ ....... 2-30 2.1-3 Normal Service Water Flow Diagram.. ~ ....................... 2-31 2.1-4 Other Liquid Effluent Pathways............................. 2-32 3.1 Shearon Harris Nuclear Power Plant Gaseous Waste Streams... '3-51 3.2 Schematic of Plant Airborne Effluent Release Points ~ ~ ~ ~ ~ ... 3-52 Shearon Harris Nuclear Power Plant Condenser Off-Gas System............................................. 3-53 "
4.1-1 Shearon Harris Nuclear Power Plant Exclusion B oundary Plan.............................................. 4-16 4.1-2 thru Shearon Harris Nuclear Power Plant Environmental 4.1-5 Radiological Sampling Points............................... 4-17 DCM/ODC-TOC Rev. 3.0
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OS2 1 0 INTRODUCTION The Off-Site Dose Calculation Manual (ODCM) provides the informa-tion and methodologies to be used by Shearon Harris Nuclear Power Plant (SHNPP) to ensure compliance with Technical Specifications 3 3 3 ~ 10~ 3 ~3 ~3 11 ~ 3/4 1 1 1 3/4 1 1 2~ 3/4 1 1 4~ 4 12 1 ~ 4 12 2~
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4.12.3, and 6.9.1 of the SHNPP Operating License. These specifi-cations are those related to normal liquid and gaseous radio-logical effluents, environmental monitoring, and reporting. They are intended to show compliance with 10CFR20-based requirements and 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190 in terms of appropriate monitoring instrumentation and set points, dose rate, and cumulative dose limitations. Off-site dose estimates from nonroutine releases will also be included in the cumulative dose estimates for the plant to comply with Appendix I of 10CFR50.
The ODCM is based on "Westinghouse Standard Technical Specifica-tions" (NUREG 0452), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133),
and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are presented in the SHNPP Plant Operating Manual. These procedures are utilized by the operating staff of SHNPP to ensure compliance with technical specifications.
The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCM are expected in the future. Any such changes will be properly reviewed and approved as indicated in the Administration Control Section Specification 6.14.2 of the SHNPP Technical Specifications.
DCM/ODC-I Rev. 3.0
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1.0 INTRODUCTION
(continued)
The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant is estimated using the NRC codes LADTAP II and GASPAR using concurrent meteorology for the report period. These off-site dose estimates for each calendar year are reported in the Semiannual Radioactive Effluent Release Report submitted to the NRC by March 1 of the following year as required by Technical Specification 6.9.1.4.
DCM/ODC-I 1-2 Rev. 3.0
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OS2 Radioactive materials released in liquid effluents from SHNPP to unrestricted areas are required to implement 10CFR50 Appendix I (Technical Specification 3.11.1.2) and be limited to the concentrations specified in 10CFR Part 20, Appendix B, Table II, Column 2 (Technical Specification 3.11.1.1). For dissolved or en-trained noble gases the concentration shall be limited to 2E-4 pCi/ml total activity. The liquid effluent release point is at the point of discharge from the Cooling Tower Blowdown Line into Harris Lake (see Figure 2.1-3 and T/S Figure 5.1-3).
Radioactive liquids are routinely released as batches from the Waste Monitor Tank (WMT), Waste Evaporator Condensate Tank (WECT),
and Treated Laundry and Hot Shower Tank (TL&HST). Batch releases may also originate from the Secondary Waste Sample Tank (SWST).
These tanks are shown in Figures 2.1-1 and 2.1-2. Effluent monitor identification numbers are provided in Appendix C. Liquid effluent dilution prior to release to Harris Lake is provided by the Cooling Tower Blowdown Line. Concurrent batch releases should not normally occur at SHNPP.
Continuous releases are routinely permitted from the SWST and the Normal Service Water (NSW) system because a low potential for radioactive contamination exists. These releases are checked by effluent monitors on the SWST (Figure 2.1-2) and the NSW lines (Figure 2.1-3).
The turbine building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines for batch releases with low probability of radioactive contamination.
The radioactive liquid waste sampling and analysis required for batch and continuous releases are found in Table 4.11-1 of the
', Technical Specifications.
DCM/ODC-2 2-1 Rev. 3.0
i 1' OS2 2.1 Monitor Alarm Set Point Determination (Technical S ecifi-cation 3.3.3.10) 2.1.1 Batch Releases Liquid effluent monitor set points have two set points, the high alarm and the alert alarm. The high alarm set point (HSP) provides alarm and isolation if the tank radionuclide concentra-tions, when diluted, would approach the Technical Specification limits for concentrations in unrestricted areas. Alert alarm set points (ASP) are set at a fraction of the HSP to provide an early warning of the approach to Technical Specification limits. Based on analysis of the tank contents, the tank release rate is adjusted, based on the Cooling Tower Blowdown Line flow rate, to dilute the tank activities to 50 percent of the allowable concen-trations at the release point to Harris Lake.
- 1. Minimum Tank Mixing Time Footnote 2 to Technical Specification Table 4.11-1 requires that the method used to mix an isolated ef-fluent tank prior to sampling and analysis be described.
Equation 2.1-0 below provides an acceptable method for ensuring a well mixed tank so that a representative sample can be taken for radioactivity or other appro-priate analyses.
(V) (E) (n) (2.1-0) where:
R = Minimum allowable mixing time, hr DCM/ODC-2 2-2 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued)
V = Actual tank liquid volume, gal E = Eductor factor P = Pump design recirculation flow rate, gpm n ,
= Number of tank volumes for turnover; this will be typically two or more.
60 = 60 min/hr Table 2.1-1 lists the tank capacities, eductor factors, and pump design recirculation flow rates for individual liquid effluent release tanks.
- 2. Minimum Acceptable Dilution Factor Determine D , the minimum acceptable dilution factor required to meet the limits of ,Technical Specifica-tion 3.11.1.1, based on prerelease and composite sample analyses.
D ocomp ot (2.1-1) og C
where D ~
(2.1-.2) wee g
ocomp C
MPC.
+
MPC F -55 MPCFFe-55
) (2.1-3) s a C
ot (2.1-<)
DCM/ODC-2 2-3 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued)
Radioactivity concentration of radio-nuclides in the liquid effluent prior to dilution (pCi/ml) from analysis of the liquid effluent to be released or from composite sample analysis'MPC MPC gP, p MPC ary MPC sPy MPCt p and MPCFe 55 are the most restrictive values Eor the appropriate gamma (g)- and alpha (a)-
emitting, and strontium (s) radionu-clides, and Eor tritium (t), and Fe-55, from 10CFR20, Appendix B, Table II, Column 2.
The measured concentration of each gamma-emitting radionuclide observed by gamma spectroscopy including noble gases, yCi/ml. If no gamma activity is detect-able then assume an I-131 activity of 3E-07 pCi/ml and proceed to the Set Point Calculation Method: I-131.
C The measured concentration of alpha-emitting radionuclides as determined by gross alpha analysis of the previous monthly composite sample, pCi/ml.
C The measured concentration of Sr-89 and Sr-90 as determined by analysis of the previous quarterly composite sample, pCi/ml.
DCM/ODC-2 2-4 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued)
C The measured concentration of H-3 as determined 'by analysis of "the previous monthly composite sample, pCi/ml.
Fe-55 = The measured concentration of Fe-55 as determined by analysis of the previous quarterly composite sample, pCi/ml.
A safety factor used to assure that the radionuclide concentrations are approx-imately 50% of the limits specified in 10CFR20, Appendix B, at the point of discharge.
- 3. Maximum Batch Release Rate MRR = (Tm)
B D
0 where:
MRR = Maximum release rate of the tank batch, gpm B = Cooling tower blowdown dilution flow rate.
The minimum dilution flow rate for each setting is shown in Table 2.1-2.
4.7E+03 gpm nominal average flow rate based on measured release rate data during January 1989.
D 0
= Minimum acceptable dilution factor DCM/ODC-2 2-5 Rev. 3.0
OS2 2.1.1 Batch Releases (continued) m Fraction of the available dilution volume which may be assigned to a particular release to ensure discharge point limits are not exceeded by simultaneous radioactive liquid releases. The value of Tm is based on assumed operational considerations for simultaneous releases but normally will be 0.8 for a batch release and 0.2 for a continuous release.
- 4. Available Dilution Factor
'he Available " Dilution Factor, D 1, represents the cooling tower blowdown flow 'rate available during the time of a batch release to dilute the tank activities to or below the Technical Specification limits.
avl1 = Available dilution factor RR = Tank release rate, gpm The lower value between the calculated MRR and the pump discharge capacity in Table 2.1-1.
- 5. Prerelease Criteria For Permitting Batch Releases Compliance with 10CFR20 Based Technical Specifications Technical Specification 3.11.1.1 requires that the MPC values of 10CFR20 are not exceeded at the point of discharge for any radionuclide in a release. Therefore, DCM/ODC-2 2-6 Rev. 3.0
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OS2 2.1.1 , Batch Releases (continued) the available dilution factor (Davl1) for the release must equal or exceed the minimum acceptable dilution factor (Do) Thus D
If avl >1, the release can be made.
D 0
D If avl <1, the release cannot be permitted under the D
release0 conditions assumed for calculating D l. In this case, reduce the tank discharge release rate (RR) andlor increase the cooling tower blowdown flow rate (B) with an appropriate setting selected from Table 2.1-2.
- 6. Effluent Monitor Set Point Based on Sample Analysis (Set Point Calculation Method : REAL)
At SHNPP, tritium activity is a major controlling factor
'affecting the values of the dilution factors D and Davl. Howevers the, effluent monitors respond only to ganja emitters and the set points are direct functions of the tank gamma activity.
One of the purposes of the monitor is to detect unex-pected excursions of gamma activity during a release.
If for some reason this was to occur (e.g., settling of particulate matter or a non-representative prerelease sample), it is likely that the Fe-55'r-89, Sr-90, and alpha emitters in the release would behave similarly.
However, the H-3 concentration would not be expected to change during the release because it is homogeneously distributed.
DCM/ODC-2 2-7 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued)
The monitor set points, therefore, may be adjusted to r
reflect the proportion of the. total available dilution factor Davl remaining for the gamma and composite activ-ities (Dav 1 gc ) after the minimum acceptable dilution factor required by the H-3 activity (D t) is satisfied, avlgc avl ot'.
Liquid Channel set point based on the effluent sample gamma activity and the available dilution flow rate.
(1) Monitor High Alarm Set Point, HSPm (pCi/ml).
D
~avL c D [) C (Sens g)] + Bkg HSP m E m
where'.
Sens g Monitor gamma energy sensi-tivity, cpm/pCi/ml, as a func-tion of the effective energy for each gamma-emitter, Table 2.1-4.
ogc og ocomp Bkg Monitor background, cpm Bkg x E DCM/ODC-2 2-8 Rev. 3a0
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OS2 2.1.1 Batch Release (continued)
Em Monitor efficiency for the Cs-137 gamma energy, cpm/pCi/ml determined by primary calibra-tion.
Bk Bkg 'pC1/ml m
(2) Monitor alert alarm set point, ASPm (pCi/ml)
ASP = [(HSP - Bkg ) (F )] + Bkg (2+1-8) where:
An empirically determined value <1.0 designed to provide an operator with adequate warning that the high alarm set point is being approached.
(3) Check for Excessive Monitor Background In order to differentiate between the ASP and the statistical fluctuations associated with a high monitor background, a check for excessive monitor background is made. As a check, verify that the minimum detectable concentra-tion (MDC) for the monitor is less than 0 ' of the net ASP ; therefore, background is accept-able if:
~Bk 0.1 [(HSP Bkg ) F ] > 2 2T (2.1-9)
E DCM/ODC-2 2-9 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued) where.'DC
~Bk
= J E
m T = Time constant of the signal processor, minutes. Table 2.1-3 ~
If not, postpone the release and decontaminate or replace the sample chamber to reduce the background, then recalculate HSP and ASP using the new, lower background.
If analysis of the batch sample indicates all gamma-emitting nuclides are ( LLD, (as defined in Technical Specification Table 4.11-1), the tank gamma activity, Cg, may be assumed to consist only of I-131. This nuclide has the lowest MPC of any to be found in liquid effluents and provides a conservative basis for a monitor set point ~
(1) Monitor High Alarm Set Point, HSPm I 13]
(pCi/ml) .
DCM/ODC-2 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued)
D
~avl c D [) C (Sens g)] + Bkg HSP m-I-131 (2.1-10)
E m
where:
C 3E-07 pCi/ml in the calculation of Do (MPC for I-131).
Sens 1.55E+08 cpm/pCi/mlF the monitor sensitivity for I-131 gamma energy, Table 2.1-4.
(2) Monitor Alert Alarm Set Point, ASPm I 1312 (pCi/ml).
ASP '= [(HSP Bkg ) Fx] + Bkg (2al.ll)
I 131 I 1'31 (3) Check for Excessive Monitor Background Verify that:
~Bk 0.1 ((HBF BBB ) F
) > . (2.1-12)
- 8. Postrelease Compliance With 10CFR20 Based Technical Specification
- a. Postrelease Compliance Check To show final compliance with Technical Specifica-tion 3.11.1.1 the following relationship must hold:
DCM/ODC-2 2-11 Rev. 3.0
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OS2 2.1.1 Batch Releases (continued)
Conc.
ik ( (2.1-13) i MPC.
1 where:
Conc' Actual concentration of radionuclide "i" at the discharge point during release "k," pCi/ml C. V 1
(2.1-14) k and where:
C-1
= Concentration of radionuclide "i" in the batch release, pCi/ml Uk Actual volume of liquid effluent released during release "k," gal. Volume may be determined by flow integrator, difference in tank level, or estimated flow rate multiplied by the time of release.
Vd = Actual volume of dilution water during release "k," gal. Volume to be deter-mined by multiplying the lowest blowdown flow rate recorded by the time of release.
B'tk) where:
B' lowest recorded blowdown flow rate during release "K," gpm tk duration of release "k," min DCM/ODC-2 2-12 Rev. 3.0
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OS2 2.1.2 Continuous Releases The continuous releases from the SWST arid the NSW return lines are monitored as shown in Figures 2.1-2 and 2.1-. 3. The function of these monitors, in contrast to -the isolation function of batch release tank monitors, is to provide an indication of low levels of radioactivity in the effluent.
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- 1. Effluent Monitor Set Point 'based on an assumed FSAR nuclide mix for the SWST (Set Point Calculation Method CRP)
- a. Liquid channel set point Monitor high alarm set point, HSP (pCi/ml) ~
0.1 MPC ff (Sens ff) + Bkg HSP pCi/mi .(2.1-15) m where:
MPC ff = Weighted MPC for the SWST outlet nuclides listed in Table 11.2.1-14 of the FSAR.
Sens ff =
) (Sens g x % abundance) for the SWST nuclide mix, cpm/pCi/ml.
(2) Monitor Alert Alarm Set Point, ASP (uCi/ml)
[,(HSPm Bkgm) Fx) + Bkg (2.1-16)
When the monitor is operable and not in alarm, analysis of weekly composite samples is not required by Technical Specification Table 4.11-1.
DCM/ODC-2 2-13 Rev. 3.0
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OS2 2.1.2 Continuous Releases (continued)
If the monitor is in alarm or the presence of non-naturally occurring radioactivity >LLD is confirmed, the releases may continue provided the sampling and analysis required by Technical Specification Table 4.11-1 are performed. The results of the sample analysis will be evaluated for compliance with Technical Specification 3.11.1.1.
The monitor alarm set points may be, recalculated using Equations 2.1-7 and 2.1-8 with the results of the gamma analysis and analyses of the composite sample.
(3) Check for Excessive Monitor Background Monitor background is considered excessive when the minimum detectable concentration (MDC) for the monitor is >0.01 MPC ff. There-fore, background is acceptable if:
~Bk 0.01 MPC ff Sens 2 2T (2.1-17) m m 2.1.3 Nonroutine Li uid Releases Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rain water collected in the outdoor tank area to the storm drain system and from there directly to the lake. The line is monitored for radioactivity and is capable of automatic termination of effluent release. Because no radioactivity is normally expected in this line, the monitor high alarm and alert alarm set points are DCM/ODC-2 2-14 Rev. 3.0
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OS2 2.1.3 Nonroutine Li uid Release (continued) determined with Equations 2.1-15 and 2.1-16. If the set point is exceeded, the release to the storm drains is terminated. Effluent can then be diverted to the floor drain system for processing and eventual release via the waste monitor tanks (see Figures 2.1-1 and 2.1-2).
2 ~ Turbine Building Floor Drains Effluent Line Water collected in the turbine building floor drains is normally routed to the yard oil separator for release to the environment via the waste neutralization system and then to the cooling tower discharge line. Because no radioactivity is normally expected. in this, path, the set points for the radioactivity are determined with Equa-tion 2.1-15 and 2.1-16. Should the set point be exceeded, the release is automatically terminated.
Effluent can then be diverted to the secondary waste treatment system for processing and eventual release via the secondary waste treatment tank (see Figures 2.1-1 and 2.1-2).
2.2 Com liance with 10CFR50 A endix I 2.2.1 Cumulation of Doses The dose contribution from each release of liquid effluents will be calculated and a cumulative summation of the total body and any organ doses will be maintained for each 31 days (monthly), each calendar quarter, and the year. The dose contribution for batch releases and all defined periods of continuous release will be calculated using the following equation.
-X.t
() (Air tk Ci Fk ))
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P OS2 2.2.1 Cumulation of Doses (continued) where'.
D = The cumulative dose commitment to the total body or any 'organ v, from the liquid effluents releases, mrem; tk = The length of time of release "k" over which C.k and Fk are averaged for all liquid releases, hours',
C = The concentration of radionuclide "i" in the undi-luted liquid effluent during release "k," pCi/ml; A.
1T The site-related ingestion dose commitment factor to the total body or any organ v for each iden-tified principal gamma and beta emitter "i,"
mrem/hr per pCi/ml X.
1
= Radiological decay constant of radionuclide "i,"
hr 0.693/ (tl/2)i (tl/2) 12'. ~ = Radiological half-life of radionuclide "i," hr; tP = Average transport time to reach the point of expo-sure, hr',
12 hours. The more limiting decay time for the drinking water and fish exposure pathways (Reg.
Guide 1.109, Appendix A, Rev. 1).
DCM/ODC-2 2-16 Rev. 3.0
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OS2 2.2.1 Cumulation of Doses (continued)
The near-field average dilution factor for C.1 during any liquid effluent release "k." Defined as the ratio of the volume of undiluted liquid waste released to the product of the dilution volume from the si:te discharge structure to unrestricted re-ceiving waters times AF. AF is the site specific applicable factor for the mixing effect of the SHNPP discharge structure as defined in NUREG-0133 and has a value < 95.
According to Section 4.3 in NUREG-0133 for plants with cool-ing towers, the factor AF shall be a number such that the product of the nominal average blowdown flow (4,700 gpm) to the receiving water body, in cfs and applicable factor AF, is 1000 cfs or less, i.e.,
(Avg. Blowdown) (AF) ( 1000 cfs (2.2-1a)
Thus:
(2.2-2)
Vd x AF Where AF ( 95 and Vk and Vd are as defined in Equation 2.1-14.
In the case of a continuous secondary waste sample tank radioac-tive release, C 1 = the SWST composite sample activity. For the NSW, C = cooling tower basin concentration and Vk = discharge from the cooling tower ba'sin while Vd = the flow from the makeup water cross-tie.
DCM/ODC-2 2-17 Rev. 3.0
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, OS2 2.2.1 Cumulation of Doses (continued)
The dose factor A.1T (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:
A.
1T
= 1.14 E+05 730 +
(D w
21 BF.) DF.
1 1T (2.2-3) where:
1.14 E+05 10 6
pCi gCi x 10 3
ml 1
1 yr 8760 hr 21 = Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), kg/yr, The ingestion dose commitment factor to the whole body or any organ, T, for an adult for each isotope "i." Corresponding to dilution by the Cape Fear River for drinking water and fish consumption at Lillington, North Caro-lina.
Values for the adult total body and organs in mrem/hr per pCi/ml are given in Table 2.2-1.
730 = Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109 Rev. 1), liters/yr.
Dw Dilution factor from the near-field area within one-quarter mile of the release point to the potable water intake for the adult
~ater consumption.
DCM/ODC-2 2-18 Rev. 3.0
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OS2 2.2.1 Cumulation of Doses (continued) 13.95 for uptake at the municipal water facil-ity at Lillington, North Carolina. This is a conservative value based on minimum flow rates for the Cape Fear River. LADTAP II calculates a dilution,, factor of 67 based on average historical flow rates.
BF-1 Bioaccumulation factor for radionuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev. 1), pCi/kg per pCi/1 DF ~
1T Dose conversion factor for radionuclide "i" for adults for a particular organ x (from Table E-11 of Regulatory Guide 1 '09, Rev. 1),
mrem/pCi Table 2.2-1 presents the A values for an adult receptor. Values
~
of exp (-X.t 1 p
) are presented in Table 2.2-2 for each radionuclide "i." The sum of the cumulative dose from all batch and any con-tinuous releases for a quarter is compared to one-half the design objectives for total body and any organ. The sum of the cumula-tive doses from all releases for a calendar year is compared to the design objective doses. The following relationships should "hold'or the SHNPP to show compliance with Technical Specification 3.11.1.2.
For the calendar quarter'.
D < 1.5 mrem total body (2.2-4)
D < 5 mrem any organ (2.2-5)
DCM/ODC-2 2-19 Rev. 3.0
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OS2 2.2.1 Cumulation of Doses (continued)
For the calendar year:
D < 3 mrem total body (2.2-6)
D < 10 mrem any organ (2.2-7) where:
D T
= Cumulative total dose to any organ r or the total body from all releases, mrem'.
The quarterly limits given above represent one-half the annual design objective of 10CFR50, Appendix I, Section II.A. If any of the 'limits in Expressions 2.2-4 through 2.2-7 are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I, 10CFR50.
2.2.2 Pro'ection of Doses Dose projections for this section are required at least once per 31 days (monthly) in Technical Specification 4.11.1.3.1 whenever the liquid radwaste treatment systems are not being fully uti-lized.
DCM/ODC-2 2-20 Rev. 3.0
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OS2 2.2.2 Pro'ection of Doses (continued)
The doses will be projected using Equation 2.2-1. When the opera-tional conditions for the projected month are to be the same as for the current month, the source-term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, expected operational evolutions (i.e.,
- outages, increased power levels, major planned liquid releases,
'l etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar histor-.
ical operating experiences where practical. This may also be accomplished by using the projected Percent Power-Reactor Days for the unit as in the. following expression.
x.e.
Pl 1
=
P2 2
D 1 2 (2.2-8) where:
Dl = Past month's dose to total body or any organ, mrem D2 = Projected month's dose to total body or any organ, mrem Pl = For past month: (Average X power) x (Reactor days of operation)
P2 = For projected month: (Estimated average X power) x (Estimated reactor days of operation)
To show compliance with Technical Specification 3.11.1.3, the projected month's dose should be compared as in the following:
DCM/ODC-2 2-21 Rev. 3.0
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'OS2 2.2.2 Pro ection of Doses (continued)
D2 < 0.06 mrem for total body (2.2-9) and D2 < 0.2 mrem for any organ (2.2-10)
If the projections exceed either Expressions 2.2-9 or 2.2-10, then the appropriate portions of, the liquid radwaste treatment system shall be used to reduce releases of radioactivity.
DCM/ODC-2 2-22 Rev. 3.0
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OS2 TABLE 2.1-1 LIQUID EFFLUENT RELEASE TANKS AND PUMPS PUMP No. of DESIGN CAPACITY ( pm) Eductor Tank Capacity Radiation Tank Tanks D~lschar e Recirculation Facto ~(a I . > Effluent Monitor ID SMST 100 100 0.2 25,000 REM-3542 WECT 35 100 1.0 10,000 REM-3541 WMT 35 100 0.25 25,000 REM-3541 TLiIHS 100 100 0.25 25,000 REM-3540 1
Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 2
SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank
,WMT: Waste Monitor Tank TLKHS: Treated Laundry and Hot Shower Tank d
TLRHR discharge flow is Limited co 33 gpm by procedure when cross-connected to the floor drain system. )
DCM/ODC-2 2-23 Rev. 3.0
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OS2 TABLE 2.1-2 Set Points for Cooling Tower Blowdown Dilution Flow Rates (B)
~Set tin Tri Flow Rate ( m) Minimum Dilution Flow Rate ( m) 4,000 + 5% 3,800 7,000 + 5% 6,650 11,000 + 5% 10,450 15,000 + 5% 14,250 TABLE 2.1-3 Signal Processor Time Constants (T) for GA Technologies Effluent Monitors Detector Digital RM-80 T(min)
Back round (c m) Li uid Monitors 101 102 10 102 103 10 /cpm bkg 103 104 10 /cpm bkg 10 10 10 /cpm bkg 105 106 0.01 106. 107 0.01 DCM/ODC-2 2-24 Rev. 3.0
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OS2 TABLE 2.1-4 Liquid Effluent Monitor Gamma Sensitivities (Sens g)
SENSITIVITY& SENSITIVITY%'
NUCLIDE NUCLIDE m/gCi/cc t**'.22E+08 Ag-llOM Ni-65 '2.24E+07 Ar-41 9.28E+07 Np-239 1.13E+08 Ba-139 ~ 2.34E+07 Pr-143 1.08E+02 Ba-140 6.01E+07 Pr-144 1.68E+06 Ba-141 2.53E+08 Rb-86 8.39E+06 Ba-142 1.47E+08 Rb-88 1.45E+07 Br-83 1.95E+06 Rb-89 1.22E+08 Br-84 6.50E+07 Ru-103 1.38E+08 Br-85 6.76E+06 Ru-105 1.71E+08 Ce-141 6.11E+07 Ru-106 4.52E+07 Ce-143 9.60E+07 Sb-124 1.59E+08 Ce-144 1.30E+07 Sb-125 1.21E+08 Co-58 1.46E+08 Sn-113 ,3.08E+06 Co-60 1.'89E+08 Sr-89 1.46E+04 Cr-51 1.61E+07 Sr-91 8.16E+07 Cs-134 2.60E+08 Sr-92 1.01E+08 Cs-136 3.37E+08 Tc-101 1.66E+08 Cs-137 1.04E+08 Tc-99M 1.11E+08 Cs-138 1.15E+08 Te-125M 3.00E+05 Cu-64 5.16E+07 Te-127 1.97E+06 Fe-59 1.04E+09 . Te-127M 1.33E+04 Hf-181 2.08E+08 Te-129 1.58E+07 I-130 4.13E+08 Te-129M 5.17E+06 I-131 1.55E+08 Te-131 1.50E+08 I-132 3.31E+08 Te-131M 2.17E+08 I-133 1.39E+08 Te-132 1.39E+08 I-134 3.08E+08 W-187 1.04E+08 I-135 1.03E+08 Xe-131M 2.62E+06 "Kr-85 6.20E+05 Xe-133 9.90E+04 Kr-85M 1.20E+08 Xe-133M 1.59E+07 Kr-87 9.19E+07 Xe-135 1.47E+08 Kr-88 7.49E+07 Xe-135M 1.14E+08 Kr-89 1.39E+08 Xe-137 4.85E+07 Kr-90 1.59E+08 Xe-138 1.20E+08 La-140 1.53E+08 Y-91 2.83E+05 La-142. 9.59E+07 Y-91M 1.28E+08 Mn-54 1.03E+08 Y-92 2.76E+07 Mn-56 1.01E+08 Y-93 1.37E+07 Mo-99 3.47E+07 Zn-65 5.24E+07 Na-24 9.36E+07 Zn-69 2.22E+03 Nb-95 1.06E+08 Zr-95 1.07E+08 Nd-147 2.86K+07 Zr-97 2.68E+07
~SENSITIVITY = 80X of weighted response to 100 1400 keV gammas for Ga RD-53 offline sodium iodode (NaI) detector (reference GA Manual E-115-904, June 1980). Abundances for each gamma from "Radio-active Decay Tables" by David C. Kocher (Report DOE/TIC-11026, Washington, D.C., 1981)
DCM/ODC-2 2-25 Rev. 3.0
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OS2 Sheet 1 of 2 TABLE 2.2-1 A. VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT A-1T
= 1.14 x 10 ( + 21 BF-) DF-l.
D = 13.95 (mrem/hr per micro-Ci/ml)
Nuclide Bone Liver ~T.Bod ~Th roid ~Kidne ~hnn GI-LLI H-3 O.OOE+00 8.50E-01 8.50E-01 8.50E-01 8.50E-01 8.50E-01 8.50E-01 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 4.17E+02 4.17E+02 4.17E+02 4.17E+02 4.17E+02 4.17E+02 4.17E+02 P-32 4.62E+07 2.87E+06 1.79E+06 O.OOE+00 O.OOE+00 O.OOE+00 5.20E+06 Cr-51 O.OOE+00 O.OOE+00 1.29E+00 7.71E-01 2.84E-01 1.71E+00 3.23E+02 Mn-54 0.'OOE+00 4.40E+03 8.40E+02 O.OOE+00 1.31E+03 O.OOE+00 1.35E+04 Mn-56 O.OOE+00 1.11E+02 1.97E+Ol O.OOE+00 1.41E+02 O.OOE+00 3.54E+03 Fe-55 6.75E+02 4.66E+02 1.09E+02 O.OOE+00 O.OOE+00 2.60E+02 2.67E+02 Fe-59 1.06E+03 2.50E+03 9.59E+02 O.OOE+00 O.OOE+00 6.99E+02 8.34E+03 Co-58 O.OOE+00 9.36E+01 2.10E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.90E+03 Co-60 O.OOE+00 2.69E+02 5.93E+02 O.OOE+00 O.OOE+00 O.OOE+00 5.05E+03 Ni-63 3e19E+04 2.21E+03 1.07E+03 O.OOE+00 O.OOE+00 O.OOE+00 4.61E+02 Ni-65 '1.30E+02 1.68E+01 , 7.68E+00 O.OOE+00 O.OOE+00 O.OOE+00 4.27E+02 Cu-64 O.OOE+00 1.05E+01 4.91E+00 O.OOE+00 2.64E+01 O.OOE+00 8.92E+02 Zn-65 2.32E+04 7.38E+04 3.34E+04 O.OOE+00 4.94E+04 O.OOE+00 4.65E+04 Zn-69 4.94E+Ol 9.44E+01 6.57E+00 O.OOE+00 6.14E+01 O.OOE+00 1.42E+01 Br-83 O.OOE+00 O.OOE+00 4.07E+01 O.OOE+00 O.OOE+00 O.OOE+00 5.86E+Ol Br-84 O.OOE+00 O.OOE+00 5.27E+01 O.OOE+00 O.OOE+00 O.OOE+00 4.14E-04 Br-85 O.OOE+00 O.OOE+00 2.16E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.00E-15 Rb-86 O.OOE+00 1.01E+05 4.71E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.99E+04 Rb-88 0.00E+00 2.90E+02 1.54E+02 O.OOE+00 O.OOE+00 O.OOE+00 4.01E-09 Rb-89 O.OOE+00 1.92E+02 1.35E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.12E-11 Sr-89 2.40E+04 O.OOE+00 6.87E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.84E+03 Sr-90 5.89E+05 O.OOE+00 1.45E+05 O.OOE+00 O.OOE+00 O.OOE+00 1.70E+04 Sr-91 4.41E+02 O.OOE+00 1.78E+01 O.OOE+00 O.OOE+00 O.OOE+00 2.10E+03 Sr-92 1.67E+02 O.OOE+00 7.23E+00 O.OOE+00 O.OOE+00 O.OOE+00 3.31E+03 Y-90 6.33E-01 O.OOE+00 1.70E-02 O.OOE+00 O.OOE+00 O.OOE+00 6.71E+03 Y-91m 5.98E-03 O.OOE+00 2.32E-04 O.OOE+00 O.OOE+00 0.00E+00 1.76E-02 Y-91 9.28E+00 O.OOE+00 2.48E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.11E+03 Y-92 5.56E-02 O.OOE+00 1.63E-03 O.OOE+00 0 'OE+00 O.OOE+00 9.74E+02 Y-93 1.76E-Ol O.OOE+00 4.87E-03 O.OOE+00 O.OOE+00 O.OOE+00 5.59E+03 Zr-95 4.21E-01 1.35E-01 9.14E-02 O.OOE+00 2.12E-01 O.OOE+00 4.28E+02 Zr-97 2.33E-02 4.69E-03 2.15E-03 O.OOE+00 7.09E-03 O.OOE+00 1.45E+03 Nb-95 4.47E+02 2.49E+02 1.34E+02 O.OOE+00 2.46E+02 O.OOE+00 1.51E+06 Mo-99 O.OOE+00 1.29E+02 2.45E+01 O.OOE+00 2.92E+02 0.00E+00 2.99E+02 Tc-99m 1.03E-02 2.92E-02 3.72E-01 O.OOE+00 4.44E-01 1.43E-02 1.73E+01 Tc-101 1.06E-02 1.53E-02 1.50E-01 O.OOE+00 2.76E-01 7.83E-03 4.60E-14 Ru-103 5.53E+00 O.OOE+00 2.38E+00 O.OOE+00 2.11E+01 O.OOE+00 6.46E+02 Ru-105 4.60E-01 O.OOE+00 1.82E-01 O.OOE+00 5.95E+00 O.OOE+00 2.82E+02 DCM/ODC-2 2-26 Rev. 3.0
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OS2 Sheet 2 of 2 Table 2.2-1 (continued)
Nuclide Bone Liver.. ~T.Bod ~Th roid ~Kidne ~Lun GI-LLI Ru-106 8.22E+01 O.OOE+00 1.04E+01 O.OOE+00 1.59E+02 O.OOE+00 5.32E+03 Ag-110m 1.84E+00 1.70E+00 1.01E+00 O.OOE+00 3.34E+00 O.OOE+00 6.92E+02 Sn-113 2.01E+03 7.81E+Ol 1.90E+03 2.74E+01 5.71E+Ol O.OOE+00 3.53E+04 Sb-124 2.38E+01 4.42E-01 9.28E+00 5.68E-02 O.OOE+00 1.82E+01 6.65E+02 Te-125m 2.58E+03 9.36E+02 3.81E+02 7.77E+02 1.05E+04 O.OOE+00 1.03E+04 Te-127m 6.52E+03 2.33E+03 7.95E+02 1.67E+03 2.65E+04 O.OOE+00 2.19E+04 Te-127 1.06E+02 3.81E+Ol 2.29E+01 7.85E+01 4.32E+02 O.OOE+00 8.36E+03 Te-129m 1.11E+04 4.13E+03 1.75E+03 3.81E+03 4.63E+04 0.00E+00 5.58E+04 Te-129 3.03E+01 7.37E+00 1.14E+01 1.27E+02 2.32E+01 O.OOE+00 2.28E+Ol Te-131m 1.67E+03 8.15E+02 6.79E+02 1.29E+03 8.26E+03 O.OOE+00 8.09E+04 Te-131 1.90E+01 7.93E+00 5.99E+00 1.56E+01 8.32E+01 O.OOE+00 2.69E+00 Te-132 2.43E+03 1.57E+03 1.47E+03 1.73E+03 1.51E+04 O.OOE+00 7.43E+04 I-130 3.16E+Ol 9.33E+01 3.68E+01 7.91E+03 1.46E+02 O.OOE+00 8.04E+01 I-131 1.74E+02 2.49E+02 1.43E+02 8.16E+04 4.27E+02 O.OOE+00 6.57E+01 I-132 8.50E+00 2.27E+01 7.95E+00 7.95E+02 3.62E+01 O.OOE+00 4.27E+00 I-133 5.94E+01 1.03E+02 3.15E+01 1.52E+04 1.80E+02 O.OOE+00 9.29E+01 I-134 4.44E+00 1.21E+01 4.31E+00 2.09E+02 1.92E+01 O.OOE+00 1.05E-02 I-135 1.85E+01 4.86E+01 1.79E+01 3.20E+03 7.78E+01 O.OOE+00 5.48E+01 Cs-134 2.98E+05 7.10E+05 5.80E+05 O.OOE+00 2.30E+05 7.62E+04 1.24E+04 Cs-136 3.12E+04 1.24E+05 8.87E+04 O.OOE+00 6.86E+04 9.40E+03 1.40E+04 Cs-137 3.82E+05 5.23E+05 3.42E+05 O.OOE+00 1.77E+05 5.90E+04 1.01E+04 Cs-138 2.65E+02 5.23E+02 2.59E+02 O.OOE+00 3.84E+02 3.79E+01 2.23E-03 Ba-139 1.51E+00 1.07E-03 4.41E-02 O.OOE+00 1.00E-03 6.08E-04 2.67E+00 Ba-140 3.15E+02 3.96E-01 2.06E+01 0.00E+00 1.35E-01 2.27E-01 6.49E+02 Ba-141 7.31E-01 5.53E-04 2.47E-02 0.00E+00 "5.14E-04 3.14E-04 3.45E-10 Ba-142 3.31E-01 3.40E-04 2.08E-02 O.OOE+00 2.87E-04 1.92E-04 4.66E-19 La-140 1.64E-01 8.29E-02 2.19E-02 O.OOE+00 O.OOE+00 O.OOE+00 6.09E+03 La-142 8.42E-03 3.83E-03 9.54E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.80E+01 Ce-141 7.80E-02 5.28E-02 5.99E-03 O.OOE+00 2.45E-02 O.OOE+00 2.02E+02 Ce-143 1.38E-02 1.02E+01 1.13E-03 O.OOE+00 4.48E-03 O.OOE+00 3.80E+02 CG-144 4.07E+00 1.70E+00 2.18E-01 O.OOE+00 1.01E+00 O.OOE+00 1.38E+03 Pr-143 6.05E-01 2.43E-01 3.00E-02 0.00E+00 1.40E-01 O.OOE+00 2.65E+03 Pr-144 1.98E-03 8.22E-04 1.01E-04 O.OOE+00 4.64E-04 O.OOE+00 2.85E-10 Nd-147 4.14E-01 4.78E-01 2.86E-02 O.OOE+00 2.80E-01 O.OOE+00 2.30E+03 Hf-181 4.85E+00 2.73E-02 5.49E-01 1.73E-02 2.29E-02 O.OOE+00 3.60E+02 W-187 2.97E+02 2.48E+02 8.67E+01 O.OOE+00 O.OOE+00 O.OOE+00 8.12E+04 Np-239 3.56E-02 3.50E-03 1.93E-03 O.OOE+00 1.09E-02 O.OOE+00 7.17E+02 DCM/ODC-2 2-27 Rev. 3.0
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OS2 Table 2.2-2 DECAY FACTORS Radionuclide i(hr ) Radionuclide i(hr )
H-3 6.40E-6 1.00E+0 Zr-95 4.51E-4 9 '9E-01 C-14 1.38E-8 1.00E+0 Zr-97 4.10E-2 6.11E-01 F-18 3.79E-1 1.06E-02 Nb-95 8.21E-4 9.90E-01 Na-24 4.62E-2 5.74E-1 Mo-99 1.05E-2 8.92E-1 P-32 2.02E-3 9.76E-l Tc-99m 1.15E-l 2.52E-1 Cr-51 1.04E-3 9.88E-1 Tc-101 2.93E+0 5.37E-16 Mn-54 9.24E-5 9.99E-1 Ru-103 7.34E-4 9.91E-1 Mn-56 2.69E-1 3.96E-2 Ru-105 1.56E-1 1.54E-l Fe-55 2.93E-5 1.00E+0 RU-106 7.84E-5 9.99E-1 Fe-59 6.47E-4 9.92E-1 Sn-113 2.51E-4 9.97E-1 Co-58 4.08E-4 9.95E-1 Sb-124 4.80E-4 9.94E-1 Co-60 .1.50E-5 1.00E+0 Ag-110m 1.14E-4 9.99E-1 Ni-63 8.24E-7 1.00E+0 Te-125M 4.98E-4 9.94E-1 Ni-65 2.75E-1 3.69E-2 Te-127m 2.65E-4 9.97E-1 Cu-64 5.46E-2 5.19E-1 Te-127 7.42E-2 4.13E-1 Zn-65 1.18E-4 9.99E-1 Te-129m 8.59E-4 9.90E-1
'n-69 7.29E-1 1.59E-4 Te-129 5.97E"1 7.74E-1 Br-83 2.90E-1 3.08E-2 Te-131m 2.31E-2 7.58E-1 Br-84 1.31E+0 1.49E-7 Te-131 1.66E+0 2.23E-9 Br-85 1.45E+01 +33 0.00E+0- Te-132 8.86E-3 8.99E-1'.11E-1 Rb-86 1.55E-3 9.82E-1 I-130 5.60E-2 Rb-88 2.35E+0 5.66E-13 I-131 3.59E-3 9.58E-1 Rb-89 2.74E-O 5.25E-15 I-132 3.01E-1 2.70E-2 Sr-89 5.71E-4 9.93E-1 I-133 3.33E-2 6
'1E-1'.64E-5 Sr-90 2.78E-6 1.00E+0 I-134 7.90E-1 Sr-91 7.29E-2 4.17E-1 I-135 1.05E-1 2.84E-1 Sr-92 2.56E-1 4.63E-2 Cs-134 3.84E-5 1.00E+0 Y-90 1.08E-2 8.78E-l Cs-136 2.02E-3 9.74E-1 Y-91m 8.36E-1 4.40E-5 Cs-137 2.62E-6 1.00E+0 Y-91 4.94E-4 9.94E-1 Cs-138 1.29E+0 1.89E-7 Y-92 1.96E-1 9.52E-2 Ba-139 5.04E-1 2.36E-3 Y-93 6.88E-2 4.42E-1 6.02E-21
)B Ba-141
-140 2.26E-3 2.28E+0 9.73E-1 1.31E-12 Ba-142 3.88E+0 La-140 1.72E-2 8.13E-1 Pr-143 2.12E-3 9.75E-1 La-142 4.50E-1 4.52E-3 Pr-144 2.41E+0 2.76E-13 Ce-141 8.89E-4 9.89E-l Nd-147 2.61E-3 9.69E-1 Ce-143 2.09E-2 7.78E-1 HE-181 6.81E-4 9.92E"1 Ce-144 1.02E-4 9.99E-l W-187 2.90E-2 7.06E-1 Np-239 1.23E-2 8.63E-1
~Note: All values less than 1E-25 are'reported as 0.
DCM/ODC-2 2-28 Rev. 3.0
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C7 Figure 2.1-1 Liquid Waste Process Flow Diagram A
I Storage Treated Laundry Detergent Reverse Demineralizer Tanks Filtration and Hot Shower Drain Sump Osmosis Tanks
\
~
Filtration/ Reverse Osmosis Demineraliztion Storage Concentrate System Tanks Evaporator Floor Storage Reverse Waste Monitor Filtration Demineralizer Drain Sump Tanks Osmosis Tanks Evaporator Equipment Storage Reverse Demineralize r Tanks Filtration Condensate Drain Sump Osmosis Tank Bypass Condensate Secondary Low Conduclivity Demineralizer Polisher Regin Filtration Waste Storage Tanks Solution Sample Tank B ass High Conduclivity Evaporator Storage Tanks Note: Solid waste streams resulting from liquid watse processing are not shown
nK O Figure 2.1.2 LIQUID EFFLUENT FLOW STREAM DIAGRAM A
I TREATED LAUNDRY'OT TREATED LAUNDRY5 SHOWEA TANK HOT SHOWER TANK BEM REM I WL-3640 Z
SECONDARY WASTE 00 SAMPLE TANK 0
C 5
0 z
BEM 0
0 AEM.2IWSSSI2 WASTE NEUTRALIZATION WASTE MONITOA WASTE MONITOR BASIN TANK TANK SETTLING BASIN BEM AEM 21WL-3541 LEGEND: TANK OR BASIN HARRIS LAKE WASTE FVAPORATOB CONDENSATE TANK WASTE EVAPOAATOB CONDENSATE TANK 0 AADIATIONEFFLUENT MONITOR puMp
'Radioactive liquids are not permitted by procedure to be sent to the Waste Neutraliization Basin.
FIGURE 2.l-3 NORMAL SERVICE WATER FLOW DIAGRAM REACTOR AUXILIARYBUILDING
~ r O
O HEAT LOADS I EM 3500 A
WASTE PROCESSING HEAT LOADS BUILDING EM 3500 "e
MAINCONDENSER TURBINE BUILDING CIRCULATINGWATER PUMPS 0'
LEGEND 0 REM NSW RADIATION EFFLUENT MONITOR NORMALSERVICE WATER COOLING TOWER BASIN OO OO NSW PUMPS
<<Cello BYAees ICE HARRIS LAKE COOI.INQ TOWER BLOWDDWN NOTE: For deteiled liow drewiny ol Sereiee Weler Syrrem refer lo F SAR 2"31 Rev. 3.0 DCM/ODC-2
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O nI Figure 2.t-4 OTHER LIQUID EFFLUENT PATHWAYS TVRSINE BVILOINO FLOOR DRAINS EFF LUENT UNE WA5TE TURBINE SLDO YARD OIL NEUTRALIZATION F LOON DRAINS SFFARATOR SASIN REM SETTLINQ SASTN OUTSIDE TANK AREA DRAIN EF F LVENT LINE OUTSIDE TANK 5TOBM DRAIN AR'EA DRAIN SYSTFM IEM
~
CAN BE DIVERTED TO SECONDARY WASTE TREATMENT5Y5TEM CAN BE DIVERTED TO LIQUIDRADWASTE TREATMENTSYSTEM BARRIS LAK'E
OS2 3.0 GASEOUS EFFLUENTS At SHNPP there are four gaseous effluent release points: Plant Vent Stack 1, Turbine Building Vent Stack 3A, and the Waste Processing Building Vent Stacks 5 and 5A. These are shown in
'Figures 3.1, 3.2, and 3.3 along with their tributaries. All gaseous effluent releases at the plant are considered ground releases.
3.1 Monitor Alarm Set Point Determination (Technica1 Specifica-tion 3.3.3.11)
This section provides the methodology for stack effluent monitor set points to ensure that the dose rates from noble gases at the site boundary do not exceed the limits of 500 mrem/year to the whole body or 3000 mrems/year to the skin as specified in Tech-nical Specification 3.11.2.1 and LOCFR20.105. Thus, the stack monitor set points effectively provide pre-release compliance with LOCFR20-based technical specifications for noble gases.
The radioactivity effluent monitors for each stack and for specific effluent streams are shown in Figures 3.1 and 3.3 and are listed in Appendix C.
In Stacks 1 and 5, the potential exists for batch releases concur-rent with the normal continuous ventilation flow of effluents.
The sources of the batch releases for the respective stacks are containment preentry purge or pressure relief and WGDT releases.
In these cases, the monitor set point must reflect the contribu-tion of both the continuous and batch sources.
DCM/ODC-3 3.0
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OS2 3.1.1 Effluent Monitor Set Point Based On Known Or Assumed Stack Effluent Com osition (Set Point Calculation Method : GALE)
The following set point calculation is applicable to the 4 vent stack monitors for all conditions, e.g.
~ Continuous release via Plant Vent Stack 1.
~ Batch mode release of containment preentry purge, or pressure relief via Plant Vent Stack 1 concurrent with the continuous release.
~ ' Continuous release through Vent Stack 3A.
~ Continuous release via Vent Stack 5.
~ Batch release of a waste gas decay tank via Stack 5 concurrent with the continuous release.
~ Continuous release via Vent Stack 5A.
The general approach to gas monitor set point determination begins with the Technical Specification limits on noble gas. dose rates (mrem/year) to the whole body and skin at the site boundary.
These site limits are apportionated to each of the four stacks on the basis of respective design flow rate. Individual stack release rates (pCi/sec) are calculated which are functions of the known or assumed (GALE code) noble gas composition of the effluent. Based on stack flow rate (acfm) the release rate can be converted to an allowable noble gas concentration (pCi/cc). The monitor high alarm set point is then established to provide alarm when the concentration reaches 50 percent of the allowable level.
DCM/ODC-3 3-2 Rev. 3.0
yV OS2 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued)
- 1. Determine the noble gas radionuclide composition of the gaseous effluent.
a ~ Gamma spectroscopy analysis of the gas sample should provide the nuclide identification and activity. However, in the case where the noble gas activities are < LLD the relative nuclide composi-tion can be assumed from the Gale code activities for projected normal operating releases (Table 3.1-1).
A = Activity (pCi/cc) of noble gas nuclide "i" at the stack monitor weighted for dilution by other sources
-A.ib f +A- F (3.1-1)
( ) I.p ( F+f )
F+f where.'
ib = Activity of nuclide "i" in an undiluted batch sample, pCi/cc
- 3. p Activity of nuclide "i" in the ventila-tion flow sample, yCi/cc Use the measured effluent flow rate or the maximum effluent design flow rate at the point of release (acfm) as follows:
28,320 acfm (Turbine Buildings Vent Stack 3A)
DCM/ODC-3 3-3 Rev. 3.0
gP OS2 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued) 232,050 acfm (Waste Processing Building Vent Stack 5) 103,500 acfm (Waste Processing Building Vent Stack 5A) 390,000 acfm (Plant Vent Stack 1) f = Release flow rate for batch releases (acfm) 37,000 acfm for containment preentry purge 2.26 E+06 ( 14.7 ) (
273o T
c
)
for contain-ment pressure release 600 (
14.7 )
273o
( T )
for a waste gas t
decay tank release DCM/ODC-3 Rev. 3.0
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OS2 3.1.1 . Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued) where:
2.26E+06 and 600 are the volumes in ft of the containment and decay tank, respectively, and T , Tt, AP , and APt are the estimated, respective temperature and change in pressure (psig) following the release of the contain-ment and decay tank; and, 14.7 lb/in2 , i.e.,
~
1 atmosphere pressure Length of release, min 273'K = O'C TGJT' '273'K +
C'.
Determine S (the fraction of the total noble gas radioactivity in the gaseous effluent comprised by noble gas radionuclide "i") for each individual noble gas radionuclide in the gaseous effluent.
A.
1 S-1 E A.
(3.1-1a) 1
- 2. Determine the maximum allowable noble gas release rate from the stack, Q b (pCi/sec), based upon the whole body exposure limit of 500 mrem/year and the particular vent stack allocation for releases 500 Q wb= (T ), pCi/sec
(~XQ) Z. K. S.
DCH/ODC-3 3-5 Rev. 3.0
fv t>,
Ev L
OS2 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued) where:
(x/q) The highest calculated annual v
average relative concentration for any sector at or beyond the exclusion boundary (sec/m )
6.1E-06 sec/m from Table A-l, Appendix A K. 'The whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem/yr/pCi/m )
from Table 3.1-2 m
,Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded by simultaneous releases 0'.52 for Plant Vent Stack 1 0.03 for Turbine Building Vent Stack 3A 0.31 for Waste Processing Building Vent Stack 5 0.14 for Waste Processing Building Vent Stack 5A neM/ODC-3 3-6 Rev. 3.0
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OS2 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued)
Using the gaseous source terms for continuous venti-lation flow from Table 3.1-1 and the dose factors from Table 3.1-2, the Qm wb values for the vent stacks are'.
Stack 1 = 4.22E+04 pCi/sec Stack 3A = 2.68E+03 pCi/sec Stack 5 = 1.38E+06 pCi/sec Stack 5A = 1.14E+04 pCi/sec
- 3. Determine the maximum allowable noble gas release rate from the stacks Qm s ('pC1/sec), based upon the skin exposure limit of 3000 mrem/year by 3000 Q (T ), pCi/sec
(~X Q) E. [(L. + F 1 M.)S.]
where:
L1~ The skin dose factor due to beta emissions for each identified noble gas radionuclide (mrem/yr/pCi/m )
M.
1 The air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/pCi/m ). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose L-+1.1M = Skin dose factor (mrem/yr/pCi/m ) from Table 3.1-2 DCM/ODC-3 3-7 Rev. 3.0
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OS2 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued)
Using the gaseous source terms (Table 3.1-1) for con-tinuous flow and the dose factors (Table 3.1-2) the Q values are:
Stack 1 = 1.43E+05 pCi/sec Stack 3A = 9.30E+03 pCi/sec Stack 5 = 1.13E+05 pCi/sec
Stack 5A = 3.85E+04 pCi/sec
- 4. Determine the maximum allowable total noble gas concen-tration in the stack effluent (pCi/cc)
C m 472 (F + f) where.'
= The more restrictive release rate between Qm-wb and Qm-s 472 = Conversion factor for cfm to cc/sec
- 5. Determine the gas channel high alarm set point, HSP (pci/cc)
HSP = 0.5 (C ) + ~m DCM/ODC-3 3-8 Rev. 3.0
~ - ~
OS2 3.1.1 Effluent Monitor Set Point Based on Known or Assumed Stack Effluent Com osition (continued) where:
0.5 = Safety factor Bkg = Monitor background, cpm Em = Monitor efficiency, cpm/yCi/cc for Xe-133
- 6. Determine the effluent channel high alarm set point, HSP (pCi/sec)
HSP- = HSP (472)(F+f)
- a. ASP = [(HSP Bkgm) F ] + Bkgm where:
F = An empirically determined value < 1.0 designed to alert the operator that the high alarm set point is being approached b0 ASP = ASP (472) (F + f)
DCM/ODC-3 3"9 Rev. 3.0
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OS2 3.1.2 Alternative Set Point Method Based On Conservative Noble Gas Radionuclide Mixture And Monitor Efficienc (Set Point Calculation Method : CONG)
- 1. Substitute the Kr-89 dose factors for nuclide-specific K. and Li + 1.1M values in Eq. 3.1-2 and 3.1-3, respec-tively.
3.1.3 Effluent Monitorin Durin Ho in 0 erations If the reactor has been shut down for greater than 30 days, the condenser vacuum pump discharge during initial hogging operations at plant start-up and prior to turbine operation may be routed as dual exhaust to (1) the Turbine Vent Stack 3A and (2) the atmo-sphere directly. In this instance, the blind flange on the latter exhaust route will be removed (see Figure 3.3).
A conservative effluent channel set point (2.68E+03 pCi/sec; see 3;1.1.2) has been established for Vent Stack 3A. The monitor set point should be reduced proportionately to the estimated fraction of the main condenser effluent flowing directly to the atmosphere.
DCM/ODC-3 3-10 Rev. 3.0
lg C
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Table 3.1-1 GASEOUS SOURCE TERHS O
aO Containment I
WPB Plant Vent Condenser Vacuum Pump Purge or WPB WGDT Ventilation Flow Ventilation Flow Ventilation Flow Pressure Relief Ventilation Flow Release ( )
via vl a Via via via via Stack 5A Stack 1 Stack 3A Stack 1 Stack 5 Stack 5 Nuclide Ai()Ci/cc Si Ai()Ci/cc) Si Ai()Ci/cc) Si Ai()Ci/cc) Si Ai()Ci/cc) Si Ai()Ci/cc) Si Kr-83m 1.82E-9 3.78E-4 Kr-85m 1.95E-9 2. 16E-2 5. 17E-10 2. 16E-2 4. 74E-9 2.43E-2 2. 18E-8 4. 53E-4 Kr-85 7.26E-9 1.51E-3 6.08E-8 9.81E-1 7.05E-5 9.81E-1 Kr-87 6.49E-10 7.19E-3 1.72E-10 7.19E-3 3.63E-9 7.56E"4 Kr-88 3.25E-9 3.60E-2 8.61E-10 3.60E-2 7.12E-9 3.66E-2 2.91E-8 6.05E-3 Kr-89 Xe-131m 1.82E-B 3.78E-3 8.69E-10 1.40E-2 1.01E-6 1.40E-2 Xe-133m 1.30E-9 1.44E-2 3.45E-10 1.44E-2 2.37E-9 1.22E-2 7.81E-8 1.62E-2 Xe-133 7.79E-8 8.63E-1 2.07E-8 8.63E-1 1 ~ 71E-7 8.78E-1 4.54E-6 9.44E-1 2.90E-10 4.67E-3 3.36E-7 4.67E-3 Xe-135m 0 Xe-135 4.54E-9 5.06E-2 1.21E-9 5.04E-2 9.49E-9 4.87E-2 1.07E-7 2.23E-2 Xe-137 Xe-138 6.49E-10 7.19E-3 1,72E-10 7.19E-3 (a) Source terms are based upon GALE code (SHNPP FSAR Table 11.3.3-1) and not actual releases. Values apply only to routine releases and not emergency situations.
(b) Source term for this effluent stream not presented with FSAR. RAB mix assumed.
(c) Ai()Ci/cc) = Ci/ r ( r/min) ()Ci/Ci) (ft3/cc)
For f (d) Based on an assumed f = 200 CFH for WGDT.
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OS2 TABLE 3.1-2
.DOSE FACTORS AND CONSTANTS Whole Body Dose Skin Dose Factor Factor (K ) (ri + 1.1 Mi)
Radionuclide (mrem/yr/pci/m ) (mrem/yr/pCi/m
)'r-83m 7.56E-02 2.12E+01
,Kr-85m 1.17E+03 2.81E+03 Kr-85 1.61E+01 1.36E+03 Kr-87 5.92E+03 1.65E+04 Kr-88 1.47E+04 1.91E+04 Kr-89 1.66E+04 - 2.91E+04 Kr-90 1.56E+04 2.52E+04 Xe-131m 9.15E+Ol 6.48E+02 Xe-133m 2.51E+02 1.35E+03
,Xe-133 .2.94E+02 6.94E+02 Xe-135m 3.12E+03 4.41E+03 Xe-135 1.81E+03 3.97E+03 Xe-137 1.42E+03 1.39E+04 Xe-138 8.83E+03 1.43E+04 Ar-41 8.84E+03 1.29E+04 Regulatory Guide 1.109, Rev. 1, Table B-l, multiplied by,(1.0+E6 pCi/pCi).
DCM/ODC-3 3-12 Rev. 3.0
OS2 3.2 Postrelease Com liance with 10CFR20-Based Technical S ecifi-cation 3.11.2 3.2.1 Noble Gases The gaseous effluent monitors set points are utilized to show pre-release compliance with Technical Specification 3.11'.2.1. How-ever, because they may be based upon a conservative (GALE code) mix of radionuclides, when using Table 3.1-1, the possibility exists that the set points could be exceeded and yet 10CFR20-based limits may actually be met. Therefore, the following methodology has been provided in the 'event that if the high alarm set points are exceeded, a determination may be made as to whether the actual
'releases 'have "exceeded the dose rate limits of Technical Specifi-cation 3.11.2.1.
The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to 'he 'skin. Based upon NUREG-0133, the following equations are used to show compliance'.
(3.2-1)
K. (~XQ) 500 mrem/yr (L. + 1.1 M.) < 3000 mrem/yr (3. 2-2)
(~X Q) Q.
1 where:
(~X Q) v = The highest calculated annual average relative'concentration for Long-term vent stack releases for areas at or beyond the exclusion boundary sec/m .
6.1E-06 sec/m from Table A"1, Appendix A, for ground-level releases in the S sector at the exclusion boundary.
DCM/ODC-3 3-13 Rev. 3.0
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OS2 3.2.1 Noble Gases (continued)
K.
1
= The total body dose factor due to gamma emissions for noble gas radionuclide "i,"
mrem/year per pCi/m . Table 3.2-3.
L ~ The skin dose factor due to beta emissions for noble gas radionuclide "i," mrem/year per pCi/m . Table 3.2-3.
M. The air dose factor due to gamma emissions for noble gas radionuclide "i," mrad/year per yCi/m . Table 3.2-3.
1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photon of. interest. Converts mrad to mrem (Reference NUREG-0133). The factors (L- + 1.1
'. M- ) are 'tabulated in Table 3.1-2.
Q.
1v
= The release rate of radionuclide ".i" in, gaseous effluents from all plant vent stacks (pci/sec).
The determination of the controlling location for implementation of dose rate limits for noble gas exposure is a function of the historical annual average meteorology.
The noble gas radionuclide mix was based upon source terms cal-culated using the NRC GALE Code and presented in the SHNPP FSAR Table 11.3.3-1. They are reproduced in Table 3.2-1 as a function of release point.
DCM/ODC-3 3-14 Rev. 3.0
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OS2 3.2.1 Noble Gases (continued)
The X/Q value utilized in the equations is the highest long-term annual average relative concentration (~X Q) v in the unrestricted area for the period 1976 1987. Long-term annual average (~X Q) v values at other locations shown in Table 3.2-2 are presented in Appendix A. A description of their derivation is also provided in this appendix.
To select the limiting location for ground-level releases, long-term annual average (~X Q) v values were calculated assuming no decay, undepleted transport to the exclusion boundary. These values are given in Table A-l, Appendix A . The maximum exclusion boundary (~X Q) v for ground-level releases occurs in the S sector.
Therefore, the limiting location for implementation of the dose rate limits for noble gases is considered to be the exclusion boundary (1.36 miles) in the S sector.
Values for K , L., and Mi which are to be used by SHNPP in Equa-tions 3.2-1 and 3.2-2 to show compliance with Technical Specifica-tion 3.11.2 are presented in Table 3.2-3. These values were taken A
from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert mrad/pCi to mrad/pCi for use in Equations 3.2-1 and 3.2-2.
3.2.2 Radioiodines and Particulates The bases for Technical Specification 3/4.11.2.1 states that the dose rate to the thyroid of a child in an unrestricted area resulting from the inhalation of radioiodines, tritium, and par-ticulates with half-lives > 8 days is limited to 1500 mrem/yr to any organ. Based upon NUREG-0133, the following is used to show compliance:
DCM/ODC-3 3-15 Rev. 3.0
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OS2 3.2.2 Radioiodines and Particulates (continued)
P. [ (~XQ) Q. ] < 1500 mrem/yr (3.2-3) i I where:
P The dose parameter for radionuclides other than 1I noble gases for the inhalation pathway, mrem/yr per pCi/m In the calculation to show compliance with Technical Specification 3.11.2.l.b, only the inhalation pathway is considered.
The radionuclide mix is again based upon the normal operational source terms calculated using the GALE Code and presented in Table 3.2-1 as a function of release point.
The determination of the controlling exclusion boundary location upon the highest exclusion boundary was based (~X Q) v value.
Values for P. in Eq. 3.2-3 were calculated for a child for,
"'various'adionuclidesI for the inhalation pathway using the metho-dology of NUREG-0133. The P.
1 values are presented in Table 3.2-4. A description of the methodology used in calculating the P. values is presented in Appendix B. The values of P. reflect, for each radionuclide, the maximum P value for any organ.
The (~X Q) v value utilized in Equation 3.2-3 is obtained from the tables presented in Appendix A. A description of the derivation of the X/Q values is provided in Appendix A.
DCM/ODC"3 3-16 Rev. 3.0
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TAB .2-1 RELEASES FROM SHEARON HARRIS NUCLEAR POWER PLANT(
NORMAL OPERATION (Curies/year)
Waste Processing Building Waste Processing Building Exhaust and/or Exhaust via Vent Stack 5A or CONDENSER VACUUM PUMP Waste Gas Decay Tanks RAB/FHB and Containment Exhaust AND TURBINE BUILDING VIA VENT STACK 5 VIA VENT STACK 1 EXHAUST OBL VIA VENT 3ases SHUTDOWN NORMAL OPERTRATION CONTAINMENT RAB/FHB .-- TURBINE STACK 3A TOTAL KR-83M l. UK++6 KR-85M 0. 0. 1.2E+Ol 3.0E+00 0. 2.0E+00 1.7E+01 KR-85 3.0E+00 2. 1E+02 4.0E+00 0. 0. 0. 2.2E+02 KR-87 0. 0. 2.0E+00 1.0E+00 0. 0. 3.0E+00 KR-88 0. 0. 1.6E+01 5.0E+00 0. 3.0E+00 2.4E+01 KR-89 0. 0. 0. 0. 0. 0. 0.
XE-131M 0. 3.0E+00 1. OE+01 0. 0. 0. 1.3E+01 XE-133M 0. 0. 4.3E+01 2.0E+00 0. 1.0E+00 4.6E+01 XE-133 0. 1.0E+00 2.5E+03 1. 2E+02 0. 7.2E+01 2.7E+03 XE-135M 0. 0. 0. 0. 0. 0. 0.
XE-135 0. 0. 5.9E+01 7.0E+00 0. 4.0E+00 7.0E+01 XE-137 0. 0. 0. 0. 0. 0. 0.
XE-138 0. 0. 0. 1.0E+00 0. 0. 1.0E+00(3)
AR-41 2.5E+01 Particulates I-131 0. 0. 1.3E-02 4.5E-03 3.0E-04 2.8E-02 4.6E-02 I-133 0. 0. 1.1E-02 6. 7E-03 4.2E-04 4.2E-02 6.0E-02(3)
H-3 5.8E+02(3)
C-14 8.0E+00 MN-54 0. 4.5E-03 2.2E-04 1.8E-04 0. 0. 4.9E-03 FE-59 0. 1.5E-03 7.3E-05 6.0E-05 0. 0. 1.6E-03 CO-58 0. 1.5E-02 7.3E-04 6. OE-04 0. 0. 1.6E-02 CO-60 0. 7.0E-03 3.3E-04 2. 7E-04 0. 0. 7.6E-03 SR-89 0. 3.3E-04 1.7E-05 1.3E-05 0. 0. 3.6E-04 SR-90 0. 6.0E-05 2.9E-06 2.4E-06 0 ~ 0. 6.5E-05 CS-134 0. 4.5E-03 2.2E-04 1.8E-04 0. 0. 4.9E-03 CS-137 0. 7.5E-03 3.7E-04 3.0E-04 0. 0. 8.2E-03 Adapted from SHNPP FSAR Table 11.3.3-1. Calculations based upon GALE Code and do not reflect actual release data. These values are only for routine releases and not for a complete inventory of gases in an emergency.
Waste gas decay tank releases assumed after a 90-day decay period.
,Calculated using guidance of NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWRs."
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OS2 TABLE 3.2-2 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (MILES)*
EXCLUSION MILK MEAT SECTOR BOUNDARY RESIDENCE ANIMAL GARDEN ANIMAL N 1.32 2.2 2 ' 2.2 2.2 1.33 1.8 4.6 1.7 1.8 NE 1.33 2.3 2.3 2.3 ENE 1.33 3.6 1.33 1.9 1.9 1.9 ESE 1.33 2 ' 2.7 4.3 USE 1.33 4.3 4.3 SSE 1.33 4' 1.36 SSW 1.33 3.9 3.9 SW 1.33 2.8 2.8 2.8 w'sw 1.33 4.3 4.3 4.3 W 1.33 2-7 3.0 3.1 1.33 2.1. 2.1 2.5 1.26 1.8 1.8 1.8 NNW 1.26 1.5 1.7 1.7 As of May, 1988.
Distance estimates are + 0.1 mile except at the exclusion boundary.
DCM/ODC-3 3-18 Rev. 3.0
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OS2 TABLE 3 2-3 DOSE FACTORS FOR NOBLE GASES Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor K ~ L. M. N ~
(mrem/yr (mrem/yr (mra'd/yr (mrad/yr Radionuclide per pCi/m ) per pci/m ) per 'pCi/m ) per pCi/m )
Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 "Kr'-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 "Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 The listed dose factors are for radionuclides that may be detected in gaseous effluents.
DCM/ODC-3 3-19 Rev. 3.0
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OS2 TABLE 3.2-4 P. VALUES (INHALATION) FOR A CHILD FOR THE 1I SHEARON HARRIS NUCLEAR POWER PLANT
~Isoto e -iI (mrem/ r er uCi/m )
H-3 1.12E+03 P-32 2.60E+06 Cr-51 1.70E+04 Mn-54 1.57E+06 Fe-59 1.27E+06 Co-58 1.10E+06 Co-60 7.06E+06 Zn-65 9.94E+05 Rb-86 1.98E+05 Sr-89 2.15E+06 Sr-90 1.01E+08 Y-91 2.62E+06 Zr-95 2.23E+06 Nb-95 6.13E+05 Ru-103 6.61E+05 RG-106 1.43E+07 Ag-110m 5.47E+06 Sn-113 3.40E+05 Sb-124 3.24E+06 Te-127m 1.48E+06 Te-129m ,1.76E+06 I-131 1.62E+07 I-132 1.93E+05
~
I-133 3.84E+06 I-135 7.91E+05 Cs-134 1.01E+06 Cs-136 1.71E+05 Cs-137 9.05E+05 Ba-140 1.74E+06 Ce-141 5.43E+05 Ce-144 1.19E+07 Hf-181 7.95E+05 DCM/ODC-3 3-20
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OS2 4.05 ' ,
COMPLIANCE WITH 10CFR50 5.0.1 Noble Gases
- 1. Cumulation of Doses Based upon NUREG-0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following equations'.
D = 3.17 E-08 $ M. [
1 (TX Q) V Q.1 + (TX q) V q.1 ] (3.3-1)
Y ~
V V 1
D = 3.17 E-08 $ N. [ (~XQ) Q. + (XTq) q- ] (3.3-2)
V where:
D The air dose from gamma radiation, mrad.
D8 The air dose from beta radiation, mrad.
N- The air dose factor due to beta emissions for each identified noble gas radio-nuclide "i," mrad/year per pCi/m .. Table 3.2-3.
(~X q) V = The relative concentration for areas at or beyond the exclusion boundary for short-term ground-level vent stack 3
releases (< 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year), sec/m . See Section 3.0 earlier or use 6.1E-06 sec/m from Table A-l, Appendix A.
Qi The average release of noble gas v
radionuclide "i" in gaseous effluents for long term releases (>500 hrs/yr) from all vent stacks (pCi).
DCM/ODC-3 3-21 Rev. 3.0
OS2 3.3.1
~ ~ Noble Gases (continued) qiv The release of radionuclide "i" in gaseous releases for short-term releases from all vent stacks (<500 hours/year), pCi.
3.17 E-08 The inverse of the number of seconds in a year (sec/year)
To show compliance with 10CFR50, Expressions 3.3-1 and 3.3-2 are evaluated at the controlling location where the air doses are at a maximum.
At SHNPP the limiting location is the exclusion boundary at 1.36 miles in the S sector based upon the tables presented in Appendix A (see Section 3.2.1 earlier).
For this document, long-term annual average ~X Q values can be used in lieu of short-term values (see Section 3.0 earlier).
The determination of the limiting location for implemen-tation of 10CFR50 is a function of parameters such as radionuclide mix, isotopic release, and meteorology.
The radionuclide mix was based upon source terms cal-culated using the NRC GALE Code and is presented in Table 3 2 1 as a function of release point. The only source of short-term releases from the plant vent are containment purges, containment pressure relief, and waste gas decay tank release. To select the limiting location, the highest annual average ~g v value for ground-level releases is controlling.
DCH/ODC-3 3-22 Rev. 3.0
~y I tt'g V
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5l
OS2 3.3.1 Noble Gases (continued)
Values for M'- and N , which are utilized in the calcula-tion of the gamma air and beta air doses in Equation 3.3-1 to show compliance with 10CFR50, are presented in Table 3.2-3. These values originate from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert from mrad/pCi to mrad/yCi.
The following relationships should hold for SHNPP to show compliance with Technical Specification 3.11.2.2.
For the calendar quarter:
D < 5 mrad (3.3-3)
Y D
8 < 10 mrad (3.3-4)
For the calendar year'.
D < 10 mrad (3.3-5)
Y D
S < 20 mrad (3.3-6)
The quarterly limits given above represent one-half of the annual design objectives of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of Equa-tions 3.3-3 through 3.3-6 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.
DCM/ODC-3 3-23 Rev. 3.0
J~
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OS2 3.3.1 Noble Gases (continued)
- 2. Projection of Doses Doses resulting from the release of gaseous effluents will be projected once every 31 'ays (monthly). The doses will be projected utilizing Equations 3.3-1 and 3.3-2. When the operational conditions are expected to be the same as for the current month, the source-term inputs into the equation for the'projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e.,
outages, increased power levels, major planned batch gas releases, etc.) should be integrated into the dose projections by using source-term data from historical operating experiences. This may also be accomplished by using the projected Percent Power-Reactor Days for the unit as in the following expression.'
D- D P 1 2 1 2 1 ~e ~ p D (3.3-7)
P P 2 P To show compliance with Technical Specification 3.11.2.4, the projected month's dose should be compared as in the following:
D < 0.2 mrad to air for gamma radiation (3.3-8) and D
8
< 0.4 mrad to air for beta radiation (3.3-9)
If the projections exceed either Expressions 3.3-8 or 3.3-9, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce
'eleases of" radioactivity.
DCM/ODC-3 3-24 Rev. 3.0
1$
OS2 5.0.2 Radioiodine and Particulates
- 1. Cumulation of Doses Section II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from a reactor such that the estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG-0133, the dose to an organ of an individual from radioiodines and particulates with half-lives greater than 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:
D = 3.17E-08 (R [(X/Q) Q + (X/q) q ] +
T 1 1 V 1 V 1 I V V (R + R + R ' R ") [(D/Q) '
+ (D/q) q ]) +
1 1 1 1 V 1 V 1 M
G B V V
(RT M I V B V T U T where.'
Dose to any organ v from tritium, radioiodines, and particulates, mrem.
DCM/ODC-3 3-25 Rev. 3.0
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OS2 3.3.2 Radioiodine and Particulates (continued)
(Toq) The highest long-term (> 500 hr/yr) annual average relative deposition:
8.8 E-09 m for the food and ground plane pathways at the controlling location which is the exclusion boundary in the S sector (from Table A-4, Appendix A, for ground-level vent stack releases).
(TDq) The relative deposition factor for short-term, ground-level vent releases (< 500 hrs/yr), m . See Section 3.0 earlier if using "real" meteorology or use 8.8 E-09 m from IO~
Table A-4, Appendix A, for the food and ground plane pathways at the controlling location.
R. Dose factor for an organ for radio-nuclide "i" for either the cow milk M
or goat milk pathway, mrem/yr per pCi/sec per m R Dose factor for an organ for radio-nuclide "i" for the ground plane G
exposure pathway, mrem/yr per pCi/sec per m R~ Dose factor for an organ for radio-I nuclide "i" for the inhalation pathway, mrem/yr per pCi/m 3
~
DCM/ODC-3 3-26 Rev. 3.0
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OS2 3.3.2 Radioiodine and Particulates (continued)
R~
1p Dose factor for an organ for radionuclide "i" for the vegetable pathway, mrem/yr per pci/sec per m R. Dose factor, for an organ for radionuclide B
"i" for the meat pathway, mrem/yr per pci/sec per m RT = Dose factor for an organ for tritium for M
the milk pathway mrem/yr per pci/m .
RT = 'ose factor for an organ for tritium for V
the vegetable pathway, mrem/yr per pci/m3.
RT Dose factor for an organ for tritium for I
the 'nhalation pathway, mrem/yr per pCi/m3.
RT Dose factor for an organ for tritium for B
the meat pathway, mrem/yr per pci/m 3 QT Release of tritium in gaseous effluents for long-term vent stack releases '(> 500 hrs/yr), pCi.
qTv Release of tritium in gaseous effluents for short-term vent stack releases (< 500 hrs/yr), pCi.
DCM/ODC-3 3-27 Rev. 3.0
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OS2 3.3.2 Radioiodine and Particulates (continued)
To show compliance with 10CFR50, Equation 3.3-10 is evaluated for a hypothetical individual at the limiting location. At SHNPP this location is the exclusion boundary in the S sector which has the highest annual average (~X Q) v and (~D Q) v values. This assures that the actual exposure of a member of the public will not be substantially underestimated. The critical receptor is a child. Appropriate (TX Q) v and (7D Q) v values from tables in Appendix A are used. For this document, long-term annual average (TX Q) v and (TD Q) v values may be used in lieu of short-term values (see Section 3.0 earlier).
The determination of a limiting location for implementa-tion of 10CFR50 for radioiodines and particulates is a function of:
- 1. Radionuclide mix and isotopic release
- 2. Meteorology
- 3. Exposure pathway
- 4. Receptor's age In the determination of the limiting location, the radionuclide mix of radioiodines and particulates may be based upon the source terms calculated using the GALE Code. This mix is presented in Table 3.2-1 as a func-tion of release point.
DCM/ODC-3 3-28 Rev. 3.0
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OS2 3.3.2 ,Radioiodine and Particulates (continued)
In the determination of the limiting sector, all age groups and all of the exposure pathways are initially evaluated using the GASPAR code. These include cow milk, beef and vegetable ingestion, inhalation, and ground plane exposure. Goat milk is not currently an exposure pathway at SHNPP.
SHNPP Technical Specification 3.12.2 requires that a land-use census survey be conducted on an annual basis. The age groupings at the various receptor loca-'ions are also determined during this survey. Thus, depending on'he results of the survey, a new limiting location and receptor age group could result.
To avoid possible annual revisions to the ODCM software which evaluates effluent releases for, compliance with 10CFR50, the limiting., sector location has been fixed at the exclusion boundary in the S sector where the highest historical annual average (TX Q) v and (WD Q) v values occur (Appendix A). With all of the exposure pathways identified in the land use census (Table 3.2-2) available to a hypothetical receptor, the critical organ is a child's bone. This approach avoids a substantial underestimate of the dose to a real member of the public.
v values for Long-term (TX Q) v and (TD Q) ground-level releases are provided in tables in Appendix A. They may be utilized if an additional special location arises different from those presented in the special locations of Table 3.2-2. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.
DCM/ODC-3 3-29 Rev. 3.0
OS2 3.3.2 Radioiodine and Particulates (continued)
, Tables 3.3-1 through 3.3-19 present R. values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways. These values were cal-culated using the methodology described in NUREG-0133 assuming a grazing period of eight months. A descrip-tion of the methodology is presented in Appendix B.
The following relationship should hold for SHNPP to show compliance with SHNPP Technical Specification 3.11.2.3.
For the calendar quarter.'
D T
< 7.5 mrem (3.3-11)
For the calendar year:
D
'T
< 15 mrem (3.3-12)
The quarterly limits given above represent one-half the annual design objectives of Section II.C of Appendix I of 10CFR50. If any of the limits of Equations 3.3-11 or 3.3-12 are exceeded, a Special Report pursuant to Tech-nical Specification 6.9.2 must be filed with the NRC.
This report complies with Section IV.A of Appendix I of 10CFR50.
DCM/ODC-3 3-30 Rev. 3.0
g("
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OS2 3.3.2 Radioiodine and Particulates (continued)
- 2. Projection of Doses Dqses resulting from release of radioiodines and parti-culates will be projected once every 31 days (monthly) utilizing Equation 3.3-10. 'When the operational condi-tions for the projected month are expected to be the same as for the current month, the source-term inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e.,
outages, increased power levels, major batch gas releases, etc.)'hould be integrated into the dose projections by using source term data from historical operating experiences. This may also be accomplished by the using projected Percent Power-Reactor Days for the unit as in the following expression'.
Dl D2 Dl P Pl P2 i.e., D 2 Pl (3.3-13)
To show compliance with Technical Specification 3.11.2.4, the projected month's dose should be compared as in the following:
D < 0.3 mrem to any organ (3.3-14)
If the projections exceed Expression 3.3-14, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivi'ty.
DCM/ODC-3 3-31 Rev. 3.0
I II 4 l,(l" I ~ l
OS2 TABLE 3.3-1 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Ground Nuclide Trod Bl-Truer Bone Liver ~Kl dna ~Th roid ~Lan Skin Cr-51 4.66E+06 4.66E+06 4.66E+06 4.66Et06 4.66Et06 4.66Et06 4.66E+06 5.51E+06 Mn-54 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34Et09 1.34Et09 1.34Et09 1.57E+09 Fe"59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75Et08 2.75E+OS 2.75E+08 3.23E+08 Co>>58 3.79E+08 3.79E+08 3.79E+08 3.79Et08 3.79Et08 3.79Et08 3.79E+08 4.44E+09 Co-60 2. 15E+10 2.15E+10 2. 15E+IO 2, 15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 Zn-65 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49Et08 7.49E+08 8.61E+08 Rb-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99Et06 1.03E+07 Sr-89 2.23E+04 2.23E+04 2.23E+04 2.23Et04 2.23E+04 2.23E+04 2.23Et04 2.58E+04 Y-91 I.OSE+06 1.08Et06 1.08Et06 1.08Et06 1.08Et06 I.OSEt06 1.08E+06 1.22E+06 Zr-95 2.49E+08 2.49E+08 2.49E+OS 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.89E+08 Nb-95 1.36E+08 1.36Et08 1.36Et08 1.36Et08 1.36Et08 1,36Et08 1,36Et08 1.60E+08 Ru-103 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09Et08 1.09Et08 1.09E+08 1.27E+08 Ru-106 4.19Et08 4,19E+08 4,19E+08 4,19E+08 4.19Et08 4.19E+08 4.19E+08 5.03Et08 Ag-110M 3.48E+09 3.48E+09 3.48E+09 3.48Et09 3.48E+09 3.48E+09 3.48E+09 4.06E+09 Sn-113 1.44E+07 6.28E+06 1.22E+07 6.21Et06 I.OOE+07 1.33E+07 8.14Et06 4.09Et07 Sb-124 8.76Et08 7.53E+08 8.99E+08 7.76Et08 8.17E+08 1.01E+09 8.23E+08 1.24E+09 Te-127M 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 1.08E+05 Te-129M 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2 '4E+07 1-131 1.72E+07 1.72E+07 1.72E+07 1.72Et07 1.72Et07 1.72E+07 1.72Et07 2.09E+07 I -132 1.24E+06 1.24Et06 1.24Et06 1.24Et06 1.24E+06 1.24Et06 1.24E+06 1.46E+06 I-133 2.47Et06 2.47E+06 2.47E+06 2.47Et06 2.47E+06 2.47E+06 2.47Et06 3.00E+06 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56Et06 2.99E+06 Cs-134 6.82Et09 6.82E+09 6.82Et09 6.82Et09 6.82E+09 6.82Et09 6.82E+09 7.96E+09 Cs-136 1.49Et08 1.49E+08 1.49E+08 1.49Et08 1.49E+08 1.49E+08 1.49Et08 1.69E+08 Cs-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 Ba"140 2.05E+07 2.05E+07 2.05E+07 2.05Et07 2.05Et07 2.05E+07 2.05E+07 2.34E+07 Ce-141 1.36E+07 1.36E+07 1.36E+07 1.36Et07 I ~ 36E+07 1.36Et07 1.36E+07 1.53E+07 Ce-144 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95Et07 8.03E+07 Hf-181 1.97E+08 1.63E+08 2.30E+08 1.70E+08 1.77E+08 2.33E+08 1.82E+08 2.82E+08 "R Values in units of mrem/yr per 11CI/m for inhalatlon and tritium and in units of mrem/yr per 11CI/sec per m for all others.
DCM/ODC-3 3-32 Rev. 3c0
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OS2 TABLE 3.3-2 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT+
PATHWAY = Veget AGE GROUP = Adult llccltda ~T. Bod Gl-Tract Bone Liver K~ldc c T~hro i d ~Lun Skin H-3 2.28E+03 2.28E+03 0.00ft01 2.28ft03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 P-32 5.91E+07 1.72E+08 1.53E+09 9.51E+07 0.00fiOI O.OOE+01 O.OOEIOI 0.00ft01 Cr-51 4.60E+04 1.16E+07 0.00ft01 O.OOE+01 I.OIfi04 2.75E+04 6.10ft04 O.OOE+Ol Mn-54 5.83E+07 9.36E+08 O.OOE+01 3.05E+08 9.09E+07 O.OOE+01 Q.OOft01 O.OOEIOI Fe-59 1.12E+08 9.75E+08 1.24ft08 2.93E+08 O.OOE+01 O.OOE+Ol 8.17E%07 O.OOE+01 Co-58 6.71E+07 6.07E+08 O.OOE+01 2.99E+07 O.OOE+01 O.OOE+01 O.OOE<OI O.OOE+01 Co-60 3.67E+08 3.12E+09 O.OOE+01 1.66f+08 0.00f+01 O.OOE+01 O.OOEIOI O.OOE+01 Zn-65 5.77E+08 8.04E+08 4.01E+08 1.28E+09 8.54E+08 O,OOE+01 O.OOE401 O.OOE+01 Rb-86 1.03E+08 4.36E+07 O.OOE+01 2.21E%08 O.OOE+01 O.OOE+01 O.OOE401 O.OOE401 Sr-89 ,2.87E+08 .,1.60E+09 I.OOE+10 O.OOE>01 O.OOE+01 O.OOE+01 0.00ftOI 0.00f+01 Sr-90 . 1.64E+ll 1.93E+10 6.70E+ll O.OOE+01 O.OOE>01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91" 1.34E+05 2.76E+09 5.01E+06 O.OOE+01 O.OOE>01 O.OOE+01 O.OOE+01 O.OOE+Ol Zr-95 2.51E+05 1.'I7E+09 1.16E+06 3.71E+05 5.82fi05 O.OOE+01 O.OOE>01 O.oofioi Nb-95 4.19E+04 4.73E+08 1.40E+05 7.79E+04 7.70E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.04E+06 5.53E+08 4.74E+06 O.OOE+Ol 1.81E+07 O.OOE+01 O.OOE+01 0.00ftOI Ru-106 2.46E+07 1.26E+10 1.94ft08 O.OOE+01 3.75E+08 O.OOE+01 O.OOE+01 O.OOE+01 Ag-IIOM 6.23E+06 4.28E+09 I ~ 13E+07 1.05E+07 2.06E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn"113 1.36E+07 2.52E+08 1.44E+07 5.66E+05 4.09E+05 1.96E+05 O.OOE+01 O.OOE+01 Sb-124 4.02E+07 2.88E+09 1.01E+08 1.92E+06 O.OOE+00 2.46E+05 7.90ft07 O.OOE+Ol Te-127M 6.12E+07 1.68E+09 5.02E+08 1.80E+08 2.04E+09 1.28E+08 O.OOE+01 O.OOE+Ol Te-129M 4.71E+07 1.50E+09 2.98E+08 1. 11E+08 1.24E+09 1.02E+08 O.OOE<01 O.OOE+01 1-131 6.61E+07 3.04E+07 8.07E+07 1.15E+08 1.98E+08 3.78E+10 O.OOE+01 0.00ft01 1-132 5.21E+01 2.80E+Ol 5.57E+01 1.49E+02 2.37E+02 5.21E+03 O.OOE+01 O.OOE+Ol 1-133 1.12E+06 3.30E+06 2.11ft06 3.67E+06 6.40E+06 5 '9E+08 O.OOE+01 O.OOE+Ol 1-135 3.91E+04 1.20E+05 4.05E+04 1.06E+05 1.70E+05 7.00f+06 O.OOE+01 O.OOE+01 Cs-134 8.83E+09 1.89E+08 4.54E+09 1.08E+10 3.49E+09 O.OOE+01 1.16E+09 O.OOE+01 Cs-136 1.19E+08 1.88E+07 4.19fi07 1.66E+08 9.21E+07 O.OOE+01 1.26E+07 O.OOE+01 Cs-137 5.94E+09 1.76E+08 6.63E+09 9.07E+09 3.08E+09 O.OOE+Ol 1.02E+09 O.OOE+01 Ba-140 8.40E+06 2.64E+08 1.28E+08 1.61E+05 5.47E+04 O.OOE+01 9.22E+04 O.OOE+01 Ce-141 1.48E+04 4.99E+08 1.93E+05 1.31E+05 6.07E+04 O.OOE+01 O.OOE+01 O.OOE+Ol Ce-144 1.69E+06 1.06E+10 3.15E+07 1.32E+07 7.80ft06 O.OOE+Ol O.OOE+01 O.OOE+01 Hf-181 1.07E+06 7.06E+08 9.51E+06 5.36E+04 4.48E+04 3.41E+04 0.00ft01 O.OOE+01 "R Values ln units of mrem/yr per llCI/m for Inhalation and tritium and in units of mrem/yr per pCI/sec per m for all others.
DCM/ODC-3 3-33 Rev. 3.0
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OS2 TABLE 3.3-3 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Veget AGE GROUP = Teen Nvcltde T~Bod Gl-Tract Bona Liver K~idno ~Th rotd ~Lun Skin H-3 2.61E+03 2.61Et03 O.OOEt01 2.61Et03 2.61E+03 2.61E+03 2.61Et03 2.61Et03 P-32 6.80E+07 1.47Et08 1.75E+09 1.09Et08 O.OOE+01 O.OOE+Ol O.OOEt01 O.OOEt01 Cr-51 6.11E+04 1.03Et07 O.OOEt01 O.OOEt01 1.34E+04 3.39E+04 8.72Et04 O.OOE+01 Mn-54 8.79E+07 9.09E+08 O.OOE+01 4.43E+08 1.32E+08 O.OOE+Ol O.OOEt01 O.OOEt01" Fe-59 1.60Et08 9.78E+08 1.77Et08 4.14Et08 O.OOE+01 O.OOEt01 1.30E+08 O.OOE+01 Co-58 9.79E+07 5.85E+08 O.OOEt01 4.25E+07 O.OOE+01 O.OOE+01 O.OOEt01 O.OOEt01 Co-60 5.57E+08 3.22E+09 O.OOEt01 2.47Et08 O.OOE+01 O.OOEt01 O.OOEt01 O.OOE+01 Zn-65 8.68E+08 7.88E+08 5.36E+08 1.86Et09 1.19E+09 O.OOE+01 O.OOEt01 O.OOE+01 Rb-86 1.30E+08 4.09Et07 O.OOE+01 2.76Et08 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOEt01
= "'Sr-89 > 4.36E+08 d .1.81E+09 1.52E+10 a" O.OOEt01 O.OOEt01 O.OOE+Ol O.OOE+01 O.OOEt01 Sr-90 2.05E+ll 2.33E+10 8.32E+ll O.OOEt01 0 ~ OOE+01 O.OOE+01 O.OOE+01 .
O.OOEt01 Y-91 2.06E+05 3.I5Et09 7.68Et06 O.OOEtol O.OOEt01 O.OOEt01 O.OOEt01 O.OOEt01 Zr-95 3.68Et05 1.23Et09 1.69Et06 5.35Et05 7.86E+05 O.OOEt01 O.OOEt01 O.OOEt01 Nb-95 5.77Et04 4.48E+08 1.89Et05 1.05Et05 1.02E+05 O.OOEt01 O.OOEt01 O.OOEt01 Ru-103 2.90Et06 5.66Et08 6.78Et06 O.OOEt01 '2.39E+07 O.OOEt01 O.OOE+01 O.OOEt01 Ru-106 3.93E+07 1.50E+10 3.12Et08 O.OOEt01 6.02E+08 O.OOEtol O.OOEt01 O.OOEt01
'g-IIOM 9.39Et06 4.34Et09 1.63Et07 1.54Et07 2.95E+07 O.OOE+01 O.OOEt01 O.OOE+01 Sn-113 Sb-124 Te-127M 2.02E+07 5.89E+07 9.44E+07 2.29Et08 3.04E+09 1.98E+09 1.91E+07 1.51Et08 7.93E+08 8.03E+05 2.78Et06 2.81E+08 5.65E+05 O.OOE+01 3.22E+09 2.63E+05 3.43E+05 1.89Et08 O.OOEt01 1.32Et08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 I
Te-129M 6.79Et07 1.61Et09 4.29E+08 1.59Et08 1.79E+08 1.38Et08 O.OOE+01 O.OOE+Ol 1-131 5.77E+07 2.13Et07 7.68Et07 1.07Et08 1.85E+08 3.14E+10 O.OOEt01 O.OOEt01 I -132 4.72Et01 5.72Et01 5.02E+01 1.31E+02 2.07E+02 4.43E+03 O.OOEt01 O.OOE+01 I-133 1.01E+06 '.51Et06 1.96Et06 3.32Et06 5.83E+06 4.64Et08 O.OOEt01 O.OOEt01
'-135 3.49E+04 1.04Et05 3.66E+04 9.42Et04 1.49E+05 6.06E+06 O.OOEt01 O.OOE+01 Cs-134 7.54E+09 2.02Et08 6.90E+09 1.62E+10 5.16E+09 O.OOEt01 1.97Et09 O.OOE+Ol Cs-136 1.13E+08 1.35E+07 4.28Et07 1.68Et08 9.16E+07 O.OOE+01 1.44Et07 O.OOEt01 Cs-137 4.90Et09 2.00Et08 1.06E+10 I . 41E+10 4.78E+09 O.OOE+01 1.86E+09 O.OOEt01 BQ-140 8.88Et06 2.12Et08 1.38Et08 1.69Et05 5.72E+04 O.OOE+01 1.14E+05 O.OOE+Ol Ce-141 2. 12E+04 5.29Et08 2.77E+05 1.85Et05 8.70E+04 O.OOE+01 O.OOEt01 O.OOEt01 Ce-144 2.71E+06 1.27E+10 5.04E+07 2.09Et07 1.25E+07 O.OOE+01 O.OOEt01 O.OOEt01 Hf"181 1.54Et06 6.90Et08 1.38E+07 7.58Et04 6.32E+04 4.63E+04 O.OOEt01 O.OOE+Ol "R Values ln units of mrem/yr per yCI/m for inhalatlon and tritium and in units of mrem/yr per IICI/sec per m for all others.
DCM/ODC-3 3-34 Rev. 3.0
C~
IJ
OS2 TABLE 3.3-4 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Veget AGE GROUP = Child Ncclldc ~T. Bod Gl-Tract L I ver ~KI dne T~hrc i d ~Lun Skin H-3 4.04ft03 4.04E+03 O.OOE+01 4.04E+03 4.04Et03 4.04Et03 '.04E+03 4.04E+03'.OOE+01 P-32 1.42E+08 1.01E+08 3.67E+09 1.72E+08 O.OOEt01 O.OOEt01 O.OOE+Ol Cr-51 '.16ft05 6.15E+06 O.OOE+01 O.OOEtol 1.76Et04 6.44Et04 1.18Et05 O.OOEt01 Mn-54 1.73Et08 5.44E+08 O.OOE+Ol 6.49Et08 1.82Et08 O.OOEt01 O.OOE+01 O.OOE+Ol Fe-59 3.17Et08 6.62E+08 3.93E+08 6.36E+08 O.OOEt01 O.OOEt01 1.84E+08 O.OOE+Ol Co-58 1.92E+08 3.66E+08 0.00f+Ol 6.27E+07 O.OOEtol O.OOEt01 O.OOE+01 O.OOE+01 Co-60 1. IIE+09 2.08E+09 O.OOE+01 3.76Et08 O.OOEt01 O.OOEt01 O.OOE+01 0 OOE+Ol
~
Zn-65 1.70E+09 4.81E+08 1.03E+09 2.74E+09 1.73Et09 0.00f+01 O.OOEt01 O.OOE+01 Rb-86 2.81E+08 2.94E+07 O.OOE+01, 4.56E+08 O.OOEt01 O.OOEt01 O.OOE+01 O.OOE+01
'Sr -89 c a1.03ft09 4 1.40E+09 3.62E+10 O.OOE+01 r ~ O.OOEt01 O.OOEt01" O.OOEt01 0 'OE+01
'r-90
/ 3.49Etll 1.86E+10 1.38E+12 O.OOEt01 O.OOEt01 O.OOEt01 0.00ft01 O.OOE+Ol Y-91 4.89Et05 2.44E+09 1.83E+07 O.OOEt01 O.OOEt01 O.OOEt01 O.OOEt01 O.OOE+01 Zr-95 7.44Et05 8.71E+08 3.80E+06 8.35E+05 1.20Et06 O.OOEt01 O.OOE+01 O.OOE+Ol Nb-95 . 1.12Et05 2.91Et08 4.04E+05 1.57E+05 1.48Et05 O.OOEt01 O.OOE+01 O.OOE+01 Ru-103 5.86Et06 3.94E+08 1.52E+07 O.OOE+Ol 3.84Et07 O.OOEt01 O,OOEt01 O.OOE+01 Ru-106 9.38Et07 1. 17E+10 7.52E+08 O.OOE+Ol 1.02Et09 O.OOEt01 O.OOEt01 O.OOE+Ol Ag-110M 1.87Et07 2.78E+09 3.46E+07 2.34E+07 4.35Et07 O.OOE+01 O.OOEt01 O.OOE+01 Sn-113 3.97Et07 1.45E+08 3.64E+07 1.18E+06 8.09Et05 4.82E+05 O.OOE+01, O.OOE+01 Sb-124 1.21Et08 2.16E+09 3.44E+08 4.47E+06 O.OOE+01 7.61Et05 1.91E+08 O.OOE+01 Te-127M 2.26Et08 1.54E+09 1.90E+09 5.12E+08 5.42Et09 4.55E+08 O.OOEt01 O.OOE+Ol Te-129M 1.55Et08 1.22Et09 9.98E+08 2.79Et08 2.93Et09 3.22Et08 O.OOE+01 O.OOEt01 1-131 8.16Et07 1.23E+07 1.43f+08 1.44Et08 .2.36Et08 4.75Etlo O.OOE+01 O.OOE+01 1-132 7.53Et01 1.93ft02 8.91E+01 1.64E+02 2.51Et02 7.60Et03 O.OOE+Ol O.OOE+01 1-133 '.67ft06 1.78Et06 3.57E+06 4.42E+06 7.36Et06 8.21Et08 O.OOEt01 O.OOE+Ol 1-135 5.54Et04 8.92Et04 6.50E+04 1.17E+05 1.79Et05 1.04Et07 O.OOE+Ol O.OOE+01 Cs-134 5.40E+09 1.38Et08 1.56E+10 2.56E+10 7.93Et09 0.00ft01 2.84E+09 O.OOE+01 Cs-136 1.43Et08 7.77E+06 8.04E+07 2.21E+08 1. 18Et08 O.OOEt01 1.76Et07 O.OOE+Ol Cs-137 3.52Et09 1.50E+08 2.49E+10 2.39E+10 7.78Et09 O.OOEt01 2.80E+09 O.OOE+01'.OOE+01 Ba-140 1.61Et07 1.40E+08 2.76E+08 2.42E+05 7.87Et04 O.OOEtol 1.44E+05 Ce-141 4.75Et04 3.99E+08 6.42E+05 3.20E+05 1.40Et05 O.OOEt01 O.OOEt01 O.OOE+01 Ce-144 6.49Et06 9.94E+09 1.22Et08 3.81Et07 2.11Et07 O.OOEt01 0.00f tOI O.OOE+01 Hf-181 3.15Et06 5.17Et08 3.13E+07 1.22E+05 9.78E+04 1.03Et05 O.OOEt01 O.OOE+01 d
"R Values in units of mrem/yr per IICI/m for inhalation and tritium and In units of mrem/yr per MCI/sec per m for all others.
DCM/ODC-3 3-35 Rev. 3.0
0 'I t
OS2 TABLE 3.3-5 R VALUES FOR THEtSHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Meat AGE GROUP = Adult Nuclide 'rod Gl-Trect Liver ~Kiddo ~TN roid ~Lun Skin H-3 3.27E+02 3.27Et02 O.OOE+Ol 3.27Et02 3.27Et02 3.27Et02 3.27E+02 3.27E+02 P-32 1.18E+08 3.43E+08 3.05E+09 1.89E+08 O.OOE+01 O.OOEtol O.OOE+01 O.OOE+Ol Cr-51 4.27E+03'.08Et06 O.OOEt01 O.OOEt01 9.42Et02 2,56Et03 5.67E+03 O.OOE+01 Mn-54 1.06E+06 1.71Et07 O.OOE+01 5.57E+06 1.66Et06 O.OOEt01 O.OOEtol O.OOE+01 Fe-59 1.43E+08 1.25E+09 1.59Et08 3.74Et08 O.OOEt01 O.OOEt01 1.04Et08 O.OOE+01 Co-58 2.43E+07 2.20Et08 O.OOEt01 1.08Et07 O.OOEt01 O.OOE+01 O.OOE+01 O.OOEt01 Co-60 1.03E+08 8.76Et08 O.OOE+01 4.66E+07 O.OOEt01 O.OOEt01 O.OOE+01 O.OOE+01 Zn-65 3.58E+08 4.98E+08 2.49E+08 7.91E+08 5.29Et08 O.OOEt01 O.OOE+01 O.OOEt01 Rb-86 1.42E+08 6.00Et07 O.OOEt01 3.04Et08 O.OOEt01 O.OOEt01 O.OOE+01 O.OOE+01
- << GSr-89 ""!-"5.23Et06 B <<K2.92E+07 , 1.82Et08 O.OOEt01 0 OOEt01 O.OOEt01 O.OOEt01 O.OOE+01 Sr-90 2.02E+09 2.38E+08 8.22E+09 O.OOEt01 0 'OEt01 O.OOEt01 O.OOE+01 O.OOE+01 Y-91 1.80E+04 3.71Et08 6.75Et05 O.OOE+01 O.OOEto'I O.OOEt01 O.OOE+Ol O.OOEt01 Zr-95 2.43Et05 1.14E+09 1.12Et06 3.59E+05 5.64Et05 . O.OOEt01 O.OOE+Ol O.OOEt01 Nb-95 4.12E+05 4.65E+09 1.38E+06 7.66E+05 7.58Et05 O.OOEt01 O.OOE+Ol O.OOE+01 Ru-103 2.72E+07 7.38E+09 6.32E+07 O.OOEt01 2.41Et08 O.OOE+01 O.OOEt01 O.OOE+01 Ru-106 2.19E+08 1.12E+11 1.73E+09 O.OOE+01 3,35Et09 O.OOEt01 O.OOEt01 O.OOE+01 Ag-110M 2.34Et06 1.61Et09 4.27E+06 3.95E+06 7.76Et06 O.OOEt01 O.OOEt01 O.OOE+01 Sn-113 Sb-124 Te-127M 2.80E+07 4.72Et06 1.00E+08 5.19Et08 3.38E+08 2.76E+09 2.97E+07 1.19E+07 8.22E+08 1.15E+06 2.25E+05 2.94E+08 8.40Et05 O.OOEt01 3.34Et09 4.03E+05 2.88Et04
- 2. IOEt08 O.OOEt01 9.27E+06 O.OOEt01 O.OOE+Ol O.OOE+01 O.OOE+01 I
Te-129M 1.17E+08 3.73Et09 7.40E+08 2.76Et08 3.09Et09 2.54E+08 O.OOEt01 O.OOE+01 1-131 5.77E+06 2.66E+06 7.04E+06 1.01E+07 1.73Et07 3.30Et09 O.OOEt01 O.OOE+01 1-133 1.51E-OI 4.46E-OI 2.85E-01 4.96E-01 8.66E-OI 7.29E+01 O.OOEt01 O.OOE+01 I-135 6.07E-17 1.86E"16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE+01 O.OOE+Ol Cs-134 7.81E+08 1.67Et07 4.01Et08 9.55Et08 3.09E+08 O.OOEt01 1.03E+08 O.OOE+Ol Cs-136 2.14Et07 3.33E+06 7.53E+06 2.97E+07 1.65Et07 O.OOEt01 2.27Et06 O.OOE+Ol Cs-137 4.99E+08 1.47Et07 5.57E+08 7.61Et08 2.58Et08 O.OOE+01 8.59E+07 O,OOE+01 Ba-140 1.20E+06 3.77E+07 1.83Et07 2.30Et04 7.82Et03 O.OOEt01 1.32E+04 O.OOE+01 Ce-141 6.46E+02 2.18Et07 8.42E+03 5.69Et03 2.65Et03 O.OOEt01 O.OOE+01 O.OOE+01 Ce-144 4.70E+04 2.96Et08 8.75Et05 3.66Et05 2.17Et05 O.OOE+01 O.OOEt01 O.OOE+01 Hf <<181 1.52E+06 9.97Et08 1.34Et07 7.57E+04 6.33Et04 4.81E+04 O.OOE+01 O.OOE+01 "R Values in units of mrem/yr per pCI/m for inhaiatlon and tritium and in units of mrem/yr per pCI/sec per m for all others.
DCM/ODC-3 3-36 Rev. 3.0
tl N
4 wl I
,f iV
OS2 TABLE 3.3-6 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Meat AGE GROUP = Teen Noel tdh, T~Bod Gl-Tract Bone Liver K~idac ~Th roid ~Lun Skin H-3 1.95E+02 1.95E+02 O.OOE+01 1.95E402 1.95E+02 1.95E+02 1.95E+02 1.95E+02 P-32 9.98E+07 2.16E+08 2.58E+09 1.60E+08 O.OOE+01 O.OOE+01 O.OOEt01 O.OOE401 Cr-51 3.42E+03 5.75E+05 O.OOE+01 O.OOE+01 7.49E+02 1.90E+03 4.88E403 O.OOE+01 Mn-54 8.43E+05 8.72E+06 O.OOE+01 4.25Ei06 1.27E+06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 1.15E+08 7.02E+08 1.27E+08 2.97E+08 O.OOE+01 O.OOE+01 9.36E+07 O.OOE+01 Co-58 1.93E+07 1.15E+08 O.OOE+01 8.36E406 O.OOE+01 O.OOE+01 O.OOE401 O.OOE401 Co-60 8.15E+07 4.71Et08 O.OOEt01 3.62E+07 O.OOEt01 O.OOE+01 O.OOEt01 O.OOEt01 Zn-65 2.83E+08 2.57E+08 1.75E+08 6.07Et08 3.89E+08 O.OOE+01 O.OOEt01 O.OOE>OI Rb-86 1.19E+08 3.76E+07 O.OOE+01 2.54E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOEtOI
'r-89 d 4.40E+06 , -1.83E+07 1.54E+08,, O.OOE+01 O.OOE+01 O.OOE+01 O.OOE401 O.OOEt01 Sr-90 1.31E+09 1.49Ei08 '.32E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOEi01 Y-91 1.52E+04 2.33E+08 5.68E+05 O.OOE>01 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 1.95E+05 6.53E+08 8.97E+05 2.83E+05 4.16E+05 O.OOE+01 O.OOE+01 O.OOEt01 Nb-95 3.29E+05 2.55E+09 I.OSE+06 5.97Ef05 5.79E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.20E+07 4.30Ei09 5.15E+07 O.OOEIOI 1.82E+08 O.OOE+01 O.OOE401 O.OOE+01 Ru-106 1.84E+08 7.00E+10 1.46E+09 O.OOE<01 2.81E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-IIOM 1.86E+06 8.59E+OS "3.23E+06 3.06E>06 5.83E+06 O.OOE+01 O.OOE+Ol O.OOE+01 Sn-113 2.22E+07 2.51E+08 2.09E+07 8.80E+05 6.19E+05 2.88E+05 O.OOE+01 O.OOE+01 Sh-124 3.80E+06 1.96E+08 9.73E+06 1.79Ei05 O.OOE+01 2.21Et04 8.50E+06 O.OOE+01 Te-127M 8.25E+07 1.73Ei09 6.94Et08 2.46E+08 2.81E+09 1.65E+08 O.OOE+01 O.OOE+01 Te-129M 9.81E+07 2.33E+09 6.20E%08 2.30Et08 2.59E+09 2,00E+08 O.OOE+01 O.OOE+01 1-131 4.40E+06 1.62E+06 5.85E+06 8.20E+06 1.41E+07 2.39E+09 O.OOE+01 O.OOE+01 1-133 1.23E-OI 3.06E-01 2.39E-OI 4.05E-OI 7.10E-OI 5.65E+01 O.OOE+01 O.OOE+01 1-135 4.88E-17 1.46E-16 5. 11E-17 1.32E-16 2.08E-16 8.46E-15 O.OOE+01 O.OOE+01 Cs-134 3.48E+08 9.34E+06 3.19Et08 7.51E408 2.39E408 O.OOE+01 9.11E+07 O.OOE&01 Cs-136 1.55E+07 1.86E+06 5.87Et06 2.31Ei07 1.26E+07 O.OOE+01 1.98E406 O.OOEWOI Cs-137 2.14E+08 8.75E+06 4.62E+08 6.15%408 2.09E+08 O.OOE+01 8.13E+07 O.OOE+01 Ba-140 9.76E+05 2.34E+07 1.51E+07 1.86E>04 6.29E+03 O.OOE+01 1.25E+04 O.OOEtOI Ce-141 5.42E+02 1.35E+07 7.07E+03 4.72Ei03 2.22E+03 O.OOE+01 O.OOE+01 O.OOE>01 Ce-144 3.96E+04 1.85E+08 7.37E+05 3.05E+05 1.82E+05 O.OOE+01 O.OOE+01 0.00f>OI Hf-181 1.22E+06 5.50E+08 1.10E+07 6.05Ei04 5.04E+04 3.69E+04 O.OOE401 O.OOE+01 "R Values In units of mrem/yr per IICI/m for inhalation and tritium and in units of mrem/yr per NCI/sec per m" for all others.
DCH/ODC-3 3-37 Rev. 3.0
I P
Cd
>b'4' I
t
OS2 TABLE 3.3-7 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Meat AGE GROUP = Child Hcclide T~Bcd Gl-Tract Liver ~KI dna T~are Id ~Lun Skin H-3 2.36E+02 2.36E+02 O.OOE+01 2.36E+02 2.36E+02 '.36E+02 2.36E+02 2.36E+02 P-32 1.87E+08 1.34E+08 4.86ft09 2,27ft08 O.ooftol O.ooftol O.OOE+01 O.OOE+01 Cr-51 5. 33EI03 2.83E+05 O.OOE+01 O.OOE+01 8.09E+02 2.96E>03 5.40E+03 O.OOE+01 Mn-54 1.30E+06 4.08E+06 O.OOE+01 4.86E+06 1.36E+06 O.OOE+01 O.OOE+01 O.OOE+Ol Fe-59 1.82E+08 3.80ft08 2.25ft08 3.65E+08 O.OOE+01 O.OOE+01 1.06E+08 O.OOE+01 Co-58 2.99E>07 5.70E+07 O.ooftol 9.76E+06 O.OOE+01 O.OOE+01 O.ooftol O.ooftol Co-60 1.27E+08 2.38E+08 O.ooftol 4.30E+07 O.OOE+01 O.OOE+01 O.oofioi O.OOE+01 Zn-65 4.35E+08 1.23E+08 2.62E+08 6.99E+08 4.40E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rh-86 2.21E>08 2.32ft07 O.OOE+01 3.60E+08 O.OOE+Ol O.ooftol O.OOE+01 O.OOE+01
""SI -89 < 8.31ft06 . 1.13E+07 2.91E+08 O.OOE+Ol O.ooftol O.OOE+Oi O.OOE+Ol O.OOE+01 Sr-90 1.74fi09 9.26fi07 6.87E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE%01 Y-91 2.87E+04 1.43E<08 1.07E+06 O.OOE+OI O.OOE+Ol O.OOE+01 O.OOE+01 O.oofiol Zr-95 3.12ft05 3.65fioe 1.59E+06 3.50E+05 5.01fi05 O.OOE>01 O.oof>01 O.oofiol Nh-95 5.17E+05 l.34E i09 1.86E+06 7.23E+05 6.80ft05 O.oofiol O.ooftol O.OOE+01 Ru-103 3.58E+07 2.41fi09 9.31f F07 O.OOE+Ol 2. 34EI08 O.oofiol O.OOE+01 O.ooftol Ru-106 3.43E+08 4.27E+10 2.75E+09 O.oof+01 3.71fi09 O.OOE+01 O.OOE+01 O.OOEI01 Ag-IIOM 2.89E<06 4.30E+08 5.36E+06 3.62E+06 '.74E+06 O.OOE>01 O.OOE+01 O.OOE+01 Sn-113 3.42ft07 1.25E+08 3. 14f+07 1.01f+06 6.97E+05 4.15E+05 O.OOE+Ol O.OOE+01 S0-124 6.17E+06 I ~ I of408 1.76E+07 2.28E+05 O.OOE+01 3.88E>04 9.77E+06 O.OOE+01 Te-127M 1.55E+08 I'06ft09 1.31E+09 3.52E+08 3.73fi09 3.13E+08 O.OOE+01 O.OOE+Ol Te-129M 1.81E+08 1.42E+09 1. 17E+09 3.26ft08 3.43E+09 3.77E+08 O.oof>OI O.OOE+01 1-131 6.20E+06 9.72E+05 1.09E+07 1.09E+07 1.79E+07 3.61E+09 O.oof<01 O.oof+01 1-133 2 07E 01 2.21E-OI 4.43E-01 5.48E"01 9.13E-OI 1.02E+02 O.ooftol O.OOE+01 1-135 7.87E-17 1.27E-16 9.25E-17 1.66E"16 2.55E-16 1.47E-14 O.OOE+01 O.OOE+Ol Cs-134 1.95EI08 4.93EI06 5.63E+08 9.23E+08 2.86E+08 O.OOE+01 1.03ft08 O.OOE+01 Cs-136 1.80E<07 9.78E+05 1.01E+07 2.78E+07 1.48E+07 O.OOE+01 2.21E+06 O.OOE+01 Cs-137 1.20E<08 5.10Ef06 8.51E+08 8.15E+08 2.65ft08 O.OOE>OI 9.55E+07 O.oof+01 Ba-140 1.63E+06 1.42fi07 2.80E+07 2.45E+04 7.97E+03 O.OOE+01 1.46E+04 O.OOE+01 Ce-141 9.86ft02 8.28E+06 1.33E+04 6.64E+03 2.91E+03 O.OOE+01 O.OOE+01 0.00E+01 Ce-144 7.42E+04 1.14E+08 1.39E+06 4.36E+05 2.4IE405 O.OOE+01 O.OOE+Ol . O.OOE+01 Hf-181 2.02E+06 3.31E+08 2.00E+07 7.79E+04 6.26E>04 6.56E+04 O.OOE+01 O.OOE+01 I 3 "R Values in units of mrem/yr per pCI/m for inhalation and tritium 'and in units of mrem/yr per NCI/sec per m for all others.
DCH/ODC-3 3-38 Rev. 3.0
I
'J TW'J
+1 A
OS2 TABLf 3.3-8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Cow Mi lk AGE GROUP = Adult hccltdc T~Bcd Gl-Tract Bone Liver ~Kl dec T~hrctd ~Lun Skin H-3 7.69Et02 7.69Et02 O.OOE+01 7.69Et02 7.69ft02 7.69Et02 7.69E+02 7.69E+02 P"32 4.32Et08 1.26Et09 1.12E+10 6.95Et08 O.OOE+01 O.OOEt01 O.OOEt01 O.OOE+01 Cr-51 1.73Et04 4.36Et06 O.OOEt01 O.OOEt01 3.82E+03 1.04Et04 2.30Et04 O.OOE+01 Mn-54 9.76Et05 I ~ 57Et07 O.OOE+01 5.11Et06 1.52E+06 O.OOEt01 O.OOE-OI O.OOE+Ol Fe-59 1.60Et07 1,39Et08 1.77Et07 4. 17Et07 O.OOE+01 O.OOEt01 1.17Et07 O.OOE+01 Co-58 6.28Et06 5.68Et07 O.OOE+01 2.80E+06 O.OOE+01 O.OOEt01 O.OOE+01 O.OOE+01 Co-60 2.24Et07 1.91Et08 O.OOE+01 1.02E+07 O.OOE+Ol O.OOEt01 O.OOE+01 O.OOE+01 Zn-65 1.38Et09 1.92E+09 9.59E+08 3.05E+09 2.04ft09 O.OOE+01 O.OOE+Ol O.OOE+01 Rb-86 7.54Et08 3 '9Et08 O.OOEt01 1.62E+09 O.OOEt01 O.OOEtol O.OOE+01 O.OOE+01
'Sr-89 't2.50Et07 <<.1.40E+08 8.70E+08 O.OOE+01 O.OOE+01 O.OOEt01 O.OOE+01 O.OOE+01 Sr-90 7.59Et09 8.94Et08 3.09E+10 O.OOE+01 O.OOEt01 O.OOEt01 O.OOE+01 O.OOE+01 Y"91 1.37Et02 2.81Et06 5.11Et03 O.OOE+01 O.OOE+01 O.OOEt01 O.OOE+Ol O.OOEt01 Zr-95 1.22Et02 5.71Et05 5.62E+02 I ~ 80Et02 2.83Et02 O.OOEt01 O.OOEt01 O.OOE+01 Nb-95 '.48Et04 1.67Et08 4.95Et04 2.75E+04 2.72Et04 O.OOEt01 O.OOEt01 O.OOE+01 Ru-103 2.63Et02 7.14Et04 6.11E+02 O.OOE+01 2.33Et03 O.OOEt01 O.OOEt01 O.OOE+01 Ru-106 1.60Et03 8 '7Et05 1.26Et04 O.OOE+01 2.44E+04 O.OOEt01 O.OOEt01 0.00f+01 Ag-I IOM 2.04Et07 1.40E+10 3.71E+07 3.44E+07 6.76E+07 O,OOEt01 O.OOEt01 O.OOE+01 Sn-113 1.32Et06 2.44E+07 1.40Et06 5.41Et04 3.95Et04 1.90E+04 O.OOE+01 O.OOE+01 Sb-124 6.14Et06 4.39E+08 1.55Et07 2.92E+05 O.OOEt01 3.75Et04 1.20Et07 0.00f+01 Te-127M 4.11Et06 1. 13E+08 3.37Et07 1.21E+07 1.37Et08 8.62Et06 O.OOE+01 O.OOE+01 Te-129M 6.19Et06 1.97Et08 3.91E+07 1.46E+07 1.63Et08 1.34Et07 O,OOEt01 O.OOE+01 1-131 1.59E+08 7.32E+07 1.94E+08 2.77E+08 4.76E+08 9.09Et10 O.OOEt01 O.OOE+01 1-132 1.03Et01 5.51E-02 1.10Et01 2.93E+01 4.67Et01 1.03Et01 O.OOEt01 O.OOE+01 1-133 1.40Et06 4.13E+06 2.64E+06 4.59E+06 8.01E+06 6.75Et08 O.OOEt01 O.OOE+01 1-135 9.03Et03 2.76E+04 9.34Et03 2.45E+04 3.92Et04 1.61E+06 O.OOEt01 O.OOE+01 Cs-134 6.71E+09 1.44Et08 3.45Et09 3.21E+09 2.66Et09 O.OOEt01 8.82Et08 O.OOE+01 Cs-136 4.73Et08 7.46Et07 1.66Et08 6.57E+08 3.65Et08 O,OOEt01 5.01Et07 O.OOE+01 Cs-137 4.22Et09 1.25Et08 4. 71E+09 6.44E+09 2.19Et09 O.OOE+01 7.27Et08 O.OOE+01 Ba-140 1.12Et06 3.53Et07 1.71Et07 2.15E+04 7.32E+03 O.OOEt01 1.23Et04 0.00f+01 Ce-141 2.23E+02 7.52Et06 2.91E+03 1.97E+03 9.14Et02 O.OOEt01 O.OOEt01 O.OOE+01 Ce-144 1.15Et04 7.26Et07 2.15E+05 8.97E+04 5.32ft04 O.OOE+01 O.OOEt01 O.OOE+01 Hf-181 6.68Et02 4.38Et05 5.91Et03 3.33E+01 2.79Et01 2.12Et01 O.OOE+01 O.OOE+01 "R Values in units of mrem/yr per pCI/m for inhalation and tritium and in units of mrem/yr per IICI/sec per m for all others.
DCM/ODC-3 3-39 Rev. 3.0
~ 'g4 ly f V fg
OS2 TABLE 3.3-9 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT+
PATHWAY "- Cow Ml lk AGE GROUP = Teen llccltde T~Bod Gl-Tract Liver ~KI dne ~Th roid ~Lun Skin H-3 I.OOE+03 1.00Et03 O.OOE+01 1.00E+03 I.OOE+03 I.OOEt03 1.00Et03 1.00Et03 P-32 S.OOE+08 1.73Et09 2.06E+10 1.28E+09 O.OOEt01 O.OOE+01 O.OOE+01 O.OOEt01 Cr-51 3.02E+04 5.08Et06 O.OOE+01 O.OOE+01 6.63E+03 1.68E+04 4.32E+04 O.OOE+Ol Hn-54 1.69E+06 1.75E+07 O.OOE+Ol 8.52Et06 2.54E+06 O.OOEt01 O.OOE+01 O.OOEtol Fe-59 2.79E+07 1.71Et08 3.10E+07 7.23E+07 O.OOEt01 O.OOEt01 2.28E+07 O.OOE+01 Co-58 1.09E+07 6.50E+07 O.OOEt01 4.72E+06 O.OOEt01 O.OOE+Ol O.OOE+01 O.OOE+01 Co-60 3.88E+07 2.25Et08 O.OOE+01 1.72E+07 O.OOE+Ol O.OOEt01 O.OOEt01 O.OOE+01 Zn-65 2.3SE+09 2.16Et09 1.47Et09 5.11E+09 3.27E+09 O.OOE+01 O.OOE+01 O.OOEt01 Rb-86 1.39E+09 4.37Et08 O.OOEt01 2.95E+09 O.OOEtol O.OOEt01 O.OOEt01 O.OOE+01
'dSr-89 , 4.59E+07 <<,1.91E+08 . 1.60Et09 O.OOE+01 O.OOE+01 O.OOEt01 O.OOE+Ol O.OOEt01 Sr-90 I.OSE+10 1.23E+09 4.37E+10 O.OOE+01 O.OOEt01 O.OOEt01 O.OOEt01 O.OOE+01 Y-91 2.52E+02 3.85E+06 9.40Et03 O.OOE+01 O.OOE+01 O.OOEt01 O.OOEt01 O.OOEtol Zr-95 2.13E+02 7.16E+05 9.83Et02 3.10E+02 4.56Et02 O.OOEtOI O.OOEt01 O.OOEt01 Nb-95 2.58E+04 2.00E+08 8.45E+04 4.68Et04 4.54E+04 O.OOEt01 O.OOEt01 O.OOE+01 Ru-103 4.65E+02 9 'SEt04 1.09Et03 O.OOE+01 3.S3E+03 O.OOEt01 O.OOEt01 O.OOEt01 Ru-106 2.93E+03 1.11E+06 2.32E+04 O.OOE+01 4.48E+04 O.OOEt01 O.OOEt01 O.OOE+01.
Ag-IIOH 3.53E+07 1.63E+10 6.14E+07 "'5.81Et07 1.11Et08 O.OOEt01 O.OOEt01 O.OOEt01 Sn-113 2.28E+06 2.58E+07 2.15E+06 9.06E+04 6.37Et04 2.97E+04 O.OOE+Ol O.OOE+01 Sb-124 1.08E+07 5.56E+08 2.76Et07 5.08E+05 O.OOEt01 6.26E+04 2.41E+07 O.OOE+01 Te-127M 7.39Et06 1.55Et08 6.22E+07 2.21E+07 2.52Et08 1.48E+07 O.OOE+Ol O.OOEt01 Te-129H 1.13E+07 2.69E+08 7.15E+07 2.65E+07 2.99E+08 2.31Et07 O.OOEt01 O.OOEtOI 1-131 2.65E+08 9.75E+07 3.52Et08 4.93Et08 8.48E+08 1.44E+11 O.OOEt01 O.OOE+01 1-132 1.83E+01 2.22Et0) 1.94Et01 5.09E+01 8.02E+01 1.71Et01 O.OOEt01 O,OOEt01 1-133 2.49E+06 6.19E+06 4.82Et06 8.18E+06 1.43Et07 1.14Et09 O.OOEt01 O.OOE+01 1-135 1.58Et04 4.74E+04 1.66Et04 4.27E+04 6.75E+04 2,75Et06 O.OOE+01 O.OOEt01 Cs-134 6.54Et09 1.75E+08 5.99Et09 1.41E+10 4.48E+09 O.OOEt01 I .71E+09 O.OOEt01 Cs-136 7.48Et08 8.97E+07 2.83E+08 1.11Et09 6.07Et08 O.OOEt01 9.56Et07 O.OOE+01 Cs-137 3.96E+09 1.62E+08 8.54Et09 1.14E+10 3.87Et09 O.OOEt01 1.50Et09 O.OOEt01 Ba-140 1.99Et06 4.77E+07 3.09E+07 3.79E+04 1.28Et04 O.OOE+01 2.55Et04 O.OOE+01 Ce-141 Ce-144 4.09E+02 2.12Et04 1.02E+07 9.93E+07 5.33Et03 3.95Et05 3.56E+03 1.63Et05 1.68E+03 9.76Et04 O.OOEt01 O.OOE+01 O.OOEt01 O,OOEt01 O.OOEtol O.OOEtol i
Hf-181 1.18E+03 5.28Et05 1.06Et04 5.82E+01 4.84E+01 3.55Et01 O.OOEt01 0. OOE+01 igp "R Values" in units of mrem/yr per HCI/m for inhalation and tritium and in units of mrem/yr per pCI/sec per m for all others.
DCM/ODC-3 3-40 Rev. 3.0
't ~ t Cj I
Jk pA
OS2 TABLE 3.3-10 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Cow Miik AGE GROUP = Child Ncclfda T~Bod Gl-Tract Liver ~KI dne ~Th ro1d ~Lun Skin H-3 1.58E+03 1.58E+03 O.OOE+Ol 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 P-32 1.96E+09 1.41f+09 5.09E+ 10 2.38E+09 O.OOE+01 O.OOE+Ol 0.00ft01 0.00fiOI Cr-51 6.17E+04 3.27E+06 O.OOE+01 O.OOE+01 9.36E+03 3.42E+04 6.25E+04 O.OOE+Ol Mn-54 3.39E+06 1.07E+07 O.OOE+01 1.27E+07 3.57E+06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 5.79E+07 1.21E+08 7.18E+07 1.16E+08 O.OOE+01 O.OOE+Ol 3.37E>07 O.OOE>OI Co-58 2.21E+07 4.20E+07 O.OOE+Ol 7,21E+06 O.OOE+01 O.OOE+01 0.00ft01 O.OOE401 Co-60 7.90E+07 1.48E+08 O.OOE+Ol 2.68ft07 0.00ftOI O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 4.79E+09 1.35E+09 2.89E+09 7.70fi09 4.85E+09 O.OOE+01 O.OOE+Ol O.OOE+01 Rb-86 3.36E+09 3.52E+08 0.00ft01 5.47fi09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01
'r-89 h
-, >,'1.13E+08 .,1.54E+08 ,, 3.97fi09 0,00ft01 O.OOE+01 O.OOE+01 0.00ft01 O.OOE+01 Sr-90 '.87E+10 9.95E+08 7 '8E+10 0.00fi01 O.OOE+01 O.OOE+01 O.OOE+01 0.00fiOI Y-91 6.21E+02 3.09E+06 2 '2E+04 0.00fiOI O.OOE+01 'O.OOE+01 O.OOE+01 O.OOE>01 Zr-95 4.47E+02 5.23E+05 2.28E+03 5.02E~02 7.18E+02 O.OOE+01 O.OOE+01 O.OOE401 Nb-95 5.31E+04 1.37E+08 1.91E+05 7.42E004 6.98E+04 O.OOE+01 O.OOE+Ol O.OOE>01 Ru-103 9.88E+02 6.65E+04 2.57E+03 O.OOE~OI 6,47E+03 O.OOE+01 O.OOE+Ol O.OOE+01 Ru-106 7.14fi03 8.90E+05 5.72E+04 O.OOE+01 7.72E+04 O.OOE+01 O.OOE>01 O.OOE+01 Ag-I IOM 7.19E+07 1.07E+10 1.33E+08 9.00E007 I;68E+08 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 4.61E%05 1.69E+06 4.22E+05 1.36ft04 9.37fi03 5.58E+03 O.OOE+01 O.OOE+01 Sb-124 2.29E+07 4.09E+08 6.53E+07 8.47ft05 O.OOE+Ol I.44E~05 3.62E+07 O.OOEWOI Te-127M 1.82E+07 I.24E408 1.53E+08 4.13fi07 4.37E+08 3.66E+07 O.OOE+01 O.OOE+Ol Te-129M 2.74E+07 2.15E+08 1,76E+08 4.92E>07 5.18E+08 5.68E+07 0.00f+01 0.00f+01 1-131 4.88ft08 7.64E+07 8.54E+08 8.59fi08 1.41E+09 2.84E+11 O.OOE+01 O.OOE>01 1-132 3.89E+01 9.95E+Ol 4.60E+01 8,45ft01 1.29E+00 3.92fi01 O.OOE+01 0.00ftOI 1-133 5.48E+06 5.84E+06 1.17E+07 I 45fi07
~ 2.4IE+07 2.69E+09 O.OOE+01 O.OOE+Ol 1-135 3.35E+04 5.39E+04 3.93E+04 7.07E+04 1.08E+05 6.26E+06 O.OOE+01 O.OOEfol Cs-134 4.78E+09 1.22E+08 1.38E+10 2.27E+10 7.03E+09 O.OOE+01 2.52E+09 O.OOE+01 Cs-136 1.14E+09 6.17E407 6.39E408 1.76E+09 9.36E+08 O.OOE+01 1.40E>08 O.OOE+01 Cs-137 2.91E+09 1.23E+08 2.06E~IO 1.97E+10 6.42E+09 0.00ft01 2.31E+09 O.OOE+01 Ba-140 4.36E+06 3.78E+07 7.47E+07 6.54E+04 2. 13Et 04 O.OOE+OI 3.90E+04 O.OOE+01 Ce-141 9.73E+02 8.17E+06 1.31E+04 6.55E+03 2.87E%03 O.OOE+Ol O.OOE+01 O.OOE+01 Ce-144 5.20E+04 7.96ft07 9 '4E+05 3.05fi05 1.69E+05 O.OOE+Ol O.OOE+01 O.OOE+01 Hf-.181 2.53E+03 4.16E+05 2,51ft04 9.79fiOI 7.86E+Ol 8.24fiOI O.OOE+01 O.OOE>01 "R Values in units of mrem/yr per pCI/m for inhalation and tritium and in units of mrem/yr per IICI/sec per m for all others.
DCM/ODC-3 3-41 Rev. 3.0
tt I.
d'I t'a i t
OS2 TABLE 3.3-11 R VALUES FOR THE SHEARON'ARRIS NUCLEAR POWER PLANT" PATHWAY = Cow Milk AGE GROUP = Infant iicclidc Trod Gl-Tract Liver ~KI dne ~Th roid ~Lun Skin H-3 2.40E+03 2.40E+03 O.OOE+01 2.40Et03 2.40E+03 2.40E+03 2.40Et03 2.40Et03 P"32 4.06Et09 1.42Et09 1.05Etll 6.17Et09 O.OOE+Ol O.OOE+01 O.OOEtol O.OOEtol Cr-51 9.77E+04 2.85Et06 O.OOE+01 O.OOE+01 1.39E+04 6.38Et04 1.24Et05 O.OOEtol Mn-54 5.37E+06 8.71Et06 O.OOEtol 2.37E+07 5.25E+06 O.OOEtoi O.OOEtol O.OOEtol Fe-59 9.23E+07 1.12E+08 1.34Et08 2.34E+08 O.OOEtol O.OOE+01 6.92E+07 O.OOEtol Co-58 3.60E+07 3.59Et07 O.OOEtol 1.44Et07 O.OOEtoi O.OOEtol O.OOEtol O.OOEtol Co-60 1.29E+08 1.30Et08 O.OOE+01 5.47E+07 O.OOEtoi O.OOE+01 O.OOE+01 O.OOEtol Zn-65 6.14E+09 1.12E+10 3.88Et09 1.33E+10 6.45E+09 O.OOE+01 O.OOE+01 O.OOEtol
.Rh-86 6.86E+09 3.55Et08 O.OOEtOI 1.39E+10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOEtol
<<Sr-89 <<,2.,1 7E+08 %,1.55Et08, 7.55Et09 O.OOEtol O.OOEtol O.OOEtol O.OOEtol O.OOEtol Sr-90 2.05E+10 1.00Et09 8.04E+10 O.OOEtol O.OOE+01 O.OOEtol O.OOEtol O.OOEtol Y-91 1.16E+08 3.12Et06 4.36Et04 O.OOE+01 ,O,OOEtol O.OOE+Ol O.OOEtol , O.OOEto I Zr-95 7.01E+02 4.92Et05 4.05Et03 9.88E+02 1.06E+03 O.OOE+01 O.OOEtol O.OOEto I Nb-95 8.48E+04 1.24Et08 3.56Et05 1.47E+05 1.05Et05 O.OOEtol O.OOEtoi O,OOEtol Ru-103 1.74E+03 6.33E+04 5.21E+03 O.OOEtol 1.08Et04 O.OOE+Ol O,OOEtoi O.OOEtol Ru-106 1.47E+04 8.95E+05 1.18Et05 O,OOE+01 1.39E+05 O.OOE+Ol O.OOE+01 O.OOEtol Ag-110M 1.19E+08 '.32E+09 "
2.46E+08 1.80Et08 2.57E+08 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 6.65E+06 1.37E+07 6.45Et06 2.45E+05 I 31E+05
~ 9.34E+04 O.OOE+01 O.OOEtol Sb-124 3.90E+07 3.88E+08 1.26Et08 1.85Et06 O.OOE+01 3.34E+05 7.88Et07 O.OOEtol Te-127M 3.75E+07 1.25E+08 3.10E+08 1.03Et08 7.64Et08 8.96E+07 O.OOE+01 O.OOE+01 Te-129M 5.57Et07 2.16E+08 3.62E+08 1.24E+08 9.05Et08 1.39E+08 O.OOE+01 O.OOE+01 1-131 9.23E+08 7.49E+07 1.78Et09 2.10E+09 2.45E+09 6.90E+ll O.OOE+01 O.OOEtol 1-132 6.90E+01 1.57E-OO 9.55Etol 1.94E+00 2.16Etoo 9.09E+01 O.OOE+Ol O.OOEtoi 1-133 1.05E+07 6.09Et06 2.47Et07 3.60E+07 4.23Et07 6.55E+09 O.OOEtol O.OOEtol 1-135 5.93E+04 5.88Et04 8.17Et04 1.63Et05 1.81E+05 1.46E+07 O.OOE+01 O.OOEtol Cs-'134 4.19E+09 1.13Et08 2.23E+10 4.15E+Io 1.07E+10 O.OOE+01 4.38E+09 O.OOE+Ol Cs-136 1.37E+09 5.58Et07 1.25Et09 3.67Et09 1.46Et09 O.OOE+01 2.99E+08 O.OOE+01 Cs-137 2.72Et09 1.20E+08 3.28Et 10 3.84E+10 1.03E+10 O.OOE+01 4.18E+09 O.OOE+Ol Ba-140 7.91E+06 3 '7E+07 1.54E+08 1.54E+05 3.65Et04 O.OOE+01 9.43E+04 O.OOEtol Ce-141 1.87E+03 8.21E+06 2.60E+04 1.59E+04 4.90E+03 O.OOE+01 O.OOEtol O.OOE+01 Ce-144 7.82Et04 8.01Et07 1.40Et06 5.71E+05 2.31E+05 O.OOE+01 O.OOE+01 O.OOEtol Hf-181 4.23Et03 3.93Et05 4.78Et04 2.26E+02 1.32E+02 1.91E+02 O.OOE+01 O.OOE+01 "R Values in units of mrem/yr per 1ICI/m for Inhalation and tritium and in units of mrem/yr per IfCI/sec per m for all others.
DCM/ODC-3 3-42 Rev. 3.0
4
~ aw j.r
,'P
'Ql P
a
'g I
, I
OS2 TABLE 3.3-12 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY -"Goat Milk AGE GROUP = Adult Meal /de 7~Bod Gl-Tract Bone Liver ~dydee T~hro id ~Lun Skin H-3 1.57E+03 1.57fi03 O.OOE+Ol 1.57EE 03 1.57fi03 1.57E+03 1.57E+03 1.57E+03 P-32 5.19E+08 1.51ft09 1.34E+10 8.34E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 2.08E+03 5.23E+05 0.00f+Ol O.OOE+Ol 4.58E+02 1.24fi03 2.76fi03 O.OOE+01 Mn-54 1.17E+05 1.88E+06 O.OOE+Ol 6.14E+05 1.83E+05 O.OOE401 0.00fi01 O.OOE+01 Fe-59 2.08E+05 1.81E+06 2.31E+05 5.42E+05 O.OOE+01 O.OOE+01 1.5 If405 O.OOE+01 Co-58 7.54E+05 6.82E+06 O.OOEIO I 3.36E+05 O.OOE+01 O.OOE+01 O.OOE+01 0.00ft01 Co-60 2.69E+06 2.29E<07 O.OOE+01 1.22E+06 0.00ft01 O.OOE+01 O.OOE+01 0.00ft01 Zn-65 1.65E+08 2.31 f+08 1.15E+08 3.66E+08 2.45E+08 O.OOE+01 0.00ft01 O.OOE+01 Rb-86 9.05E+07 3.83ft07 O.OOE+01 1.94E+08 O.OOE+01 O.OOE>OI O.OOE401 O.OOE>01
<<.Sr-,89 ,4 5.24E+07, 2.93E+08 1.83E+09 O.OOE+01 O.OOE+Ol O.OOE 401 O.OOE+01 O.OOE+01 Sr-90 1.59E+10 1.88ft09 6.49E+10 O.OOE+01 O.OOE+01 0.00ft01 O.OOE+01 0.00ft01 Y"91 1.64E+01 3.37fi05 6.13E+02 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 1.46E+Ol 6.85E<04 6.74E+01 2.16E+01 3.39E+01 0.00ft01 '.OOE+01 O.OOE+01 Nb-95 1.78E+03 2.01E+07 5.94E+03 3.31E+03 3.27f i03 0.00ft01 O.OOE+01 0.00ft01 Ru-103 3.16E+01 8.56E+03 7.33E+01 O.OOE+01 2.80E+02 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 1.92E+02 9.81fi04 1.52E+03 O.OOE+01 2.93E+03 O.OOE>01 O.OOE<01 O.OOE+01 Ag-110M 2.45E+06 1.68E+09 4.46E+06 4.12E+06 8.11E+06 0.00fi01 O.OOE>01 O.OOE+01 Sn-113 Sb-124 1.32E+05 7.36E+05 2.44E+06 5.27E+07 1.40E+05 1.86ft06 5.41E+03 3.51E+04 3.96fi03 O.OOE+01 1.90f i03 4.50E+03 O.OOE+01 1.44E+06 O.OOE+01 0 OOE>01
~
I Te-127M 4.93E+05 1.36E+07 4.05E+06 1,45E+06 1.64E+07 1.03fi06 O.OOE+01 0.00ft01 Te-129M 7.43E+05 2.36E+07 4.69ft06 1,75E+06 1.96E+07 I.6IE406 O.OOE+01 O.OOE+01 1-131 1.91E+08 8.78fi07 2.33E+08 3.33E+08 5.71E+08 1.09E+11 0.00f+01 O.OOE+01 1-132 1.23E+01 6.61E-02 1.32E>01 3.52E+01 5.61E+01 1.23E+01 O.OOE+01 O.OOE+01 1-133 1.68E+06 4.95E+06 3.17fi06 5.51E+06 9.61E+06 8.10E+08 O.OOE+01 O.OOE+01 1-135 1.08E+04 3.32E>04 I.I2ft04 2.94E+04 4.71E+04 1.94E>06 O.OOE>01 0.00ft01 Cs-134 2.01E+10 4.31E+08 1.03E+10 2.46E+10 7.97E+09 O.OOE+01 2.65E+09 O.OOE+01 Cs-136 1.42E+09 2.24E+08 4.99E+08 1.97E+09 1.10E+09 O.OOE+01 1.50ft08 0.00fiOI Cs-137 1.27f+10 3.74E>08 1. 4 I E+10 1.93E+10 6.56E+09 O.OOE>01 2.I8E>09 O.OOE+01 Ba-140 1.35E+05 4.23E+06 2.06E+06 2 '8E+03 8.78E+02 0.00fiOI 1.48f+03 O.OOE+01 Ce-141 2.68E+01 9.03E+05 3.49E+02 2.36E+02 1. IOE+02 O.OOE+01 O.OOE+01 0 'OE+01 Ce-144 1.38E+03 8.71E>06 2.58E+04 1.08E+04 6.39E+03 O.OOE+01 O.OOE+01 0 'OE+01 HF-181 8.02E+01 5.26E404 7.09E+02 3.99E+00 3.34E+00 2.54E+00 O.OOE+01 0 'OE+01 "R Values in units of mrem/yr per lICI/m for Inhalation and tritium and in units of mrem/yr per IICI/sec per m for all others.
DCM/ODC"3 3-43 Rev. 3.0
gk
,t7 d
t
OS2 TABLE 3.3-13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Goat Milk AGE GROUP = Teen Ncclidc 7~Bad Gi-Tract Bone Liver ~KI dne T~hrcid ~Lun Skin H-3 2.04E+03 2.04E+03 O.OOE+01 2.04Et03 2.04E+03 2.04Et03 2.04E+03 2.04Et03 P-32 9.60Et08 2.08f+09 2 '8E+10 1.53Et09 O.OOEt01 O.OOEt01 0.00f+01 O.OOEt01 Cr-51 3.63E+03 6.10E+05 O.OOE+Ol O.OOEt01 7.95E+02 2.02Et03 5.18E+03 0.00ft01 Mn-54 2,03Et05 2. IOE+06 O.OOE+Ol 1.02Et06 3.05Et05 O.OOEt01 O.OOE+01 O.OOEt01 Fe-59 3.63E+05 2.22Et06 4.03E+05 9.40Et05 O.OOEt01 O.OOEt01 2.96E+05 O.OOEt01 Co-58 1.30Et06 7.80E+06 O.OOE+01 5.66Et05 O.OOEt01 O.OOEt01 O.OOE+01 O.OOEt01 Co-60 4.66E+06 2.69E+07 O.OOE+01 2.07E+06 O.OOEt01 0.00f+01 O.OOE+01 O.OOEt01 Zn-65 2.86E+08 2.60E+08 1.77E+08 6.13Et08 3.93Et08 O.OOE+01 O.OOE+01 O.OOEt01 Rb-86 1.66Et08 5.24E+07 O.OOE+Ol 3.54Et08 O.OOEt01 O.OOEt01 O.OOE+01 O.OOEtol SI -89 49.65ft07 ', 4.01E+08 '.37Et09 0.00ft01 O.OOEt01 O.OOE+01 0.00f+01 O.OOEt01 SI -90 2.27E+10 2.58E+09 9.18E+10 O.OOEt01 O.OOEt01 O,OOE+01 O.OOE+01 O,OOEt01 Y-91 3.02E+01 4.62E+05 1.13E+03 O.OOEt01 0.00ft01 O.OOEt01 O.OOE+Ol O.OOEt01 Zr-95 2.56E+01 8.59E+04 1.18E+02 3.72Et01 5.47Et01 O.OOEt01 O.OOE+Ol O.OOEt01 Nb-95 3.09E+03 2.40E+07 1.01E+04 5.62Et03 5.45Et03 O.OOEt01 O.OOE+01 O.OOEt01 Ru-103 5.58E+01 1.09E+04 1.30E+02 O.OOEt01 4.60Et02 O.OOE+Ol O.OOE+01 0.00f+01 Ru-106 3.51E+02 1.34Et05 2.79E+03 0.00ft01 5.38Et03 O.OOE+01 O.OOE+01 O.OOEt01 Ag-IIOM 4.24E+06 1.96E+09 '7 37E+06 6.97Et06 1.33Et07 O.OOEt01 O.OOEt01 O.OOE+01 Sn-113 2.28E+05 2.58E+06 2. 15f+05 9.06Et03 6.37Et03 2.97Et03 0.00ft01 O.OOE+01 Sb-124 1.29E+06 6.67E+07 3.31E+06 6.,10Et04 O,OOEt01 7.51Et03 2.89Et06 O.OOEt01 Te-127M 8.87f+05 1.86E+07 7.46Et06 2.65Et06 3.02E+07 1.77Et06 O.OOE+01 0.00ft01 Te-129M 1.36E+06 3.22E+07 8.58E+06 3,19E+06 3.59Et07 2.77Et06 O.OOE+01 O.OOE+01 1-131 3.18E+08 1.17ft08 4.22E+08 5.91Et08 1.02Et09 1.73E+11 O.OOE+Ol O.OOE+01 1-132 2.19Et01 2.66E+01 2.33E+01 6.11Et01 9.62ft01 2.06E+01 O.OOEt01 O.OOEt01 1-133 2.99E+06 7.43E+06 5.79E+06 9.81Et06 1.72Et07 1.37Et09 O.OOEt01 O.OOEt01 1-135 1.90E+04 5.63E+04 1.99Et04 5.13ft04 8.10Et04 3.30Et06 O.OOEt01 O.OOE+01 Cs-134 1.96E+10 5.26E+08 1.80E+10 4.23E+10 1.34E+10 O.OOEt01 5.13f+09 O.OOEt01 Cs-136 2.25E+09 2.69E+07 8.50E+08 3.34Et09 1,82Et09 O.OOE+Ol 2.87E+08 O.OOE+01 Cs-137 1.19E+10 4.85E+08 2.56E+10 3.41E+10 I ~ 16E+10 O.OOEt01 4.51Et09 O.OOEt01 Ba-140 2.39E+05 5.72E+06 3.71E+06 4.55Et03 1.54Et03 O.OOEt01 3.06E+03 O.OOE+01 Ce-141 4.91Etol 1.22Et06 6.40E+02 4.27Et02 2.01E+02 O.OOE+01 O.OOE+01 O.OOE+Ol Ce-144 2.55Et03 1.19E+07 4.74Et04 1.96Et04 1.17ft04 O.OOEt01 O.OOEt01 O.OOEt01 Hf-181 1.41Et02 6.34E+04 1.27E+03 6.97Et00 5.80Et00 4.26Et00 0.00f+01 0.00ft01 "R Values in units of mrem/yr per 1ICI/m for inhalation and tritium and in units of mrem/yr per llCI/sec per m for all others.
DCM/ODC-3 3-44 Rev. 3c0
V l c
'd J
OS2 TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY -"Goat Milk AGE GROUP = Child hcclide T~Bcd Gl-Tract Liver ~Kidce T~hrctd ~Lun Sk in H-3 3.23E+03 3.23E+03 O.OOE+01 3.23fi03 3.23E+03 3.23E+03 3.23E+03 3.23E+03 P-32 2.35E+09 1.69ft09 6.11E+10 2.86ft09 O.OOE+Ol O,ooftoi O.OOE+Ol O.OOE+01 Cr-51 7.40E+03 3.93fi05 O.OOE+01 O.ooftol 1.12E403 4.11E+03 7.50E+03 O.OOE+01 Mn-54 4 '7E+05 1.28E+06 O.OOE+01 I . 53EI06 4.29E+05 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 7.52E+05 1.57E+06 9.34E+05 1.51E+06 O.OOE>01 O.OOE+Ol 4.38E+05 O.OOE+01 Co-58 2.65ft06 5.05E+06 O.OOE+01 8,65E+05 O.ooftol O.OOE+01 0 ~ OOE+01 O.OOE+Ol Co-60 9.48E+06 1.78E+07 O.OOE+01 3.21E+06 O.OOE+01 O.OOE+01 0 ~ OOE+01 O.OOE+01 Zn-65 5.74E+08 1.62E+08 3.47E+08 9.24E+08 5.82ft08 O.OOE+01 O.OOE+Ol O.ooftol Rb-86 4.04E+08 4.22E+07 O.OOE+Ol 6.57E+08 O.OOE+Ol O.OOE+01 O.OOE+01 O.oof to I
- Sr-89 '2.38E+08 . 3.23E+08 8.34E+09 ~ O.OOE+01 O.OOE>OI O.oof IOI O.OOE+01 O.ooftol Sr-90 3.93E+10 2.09E+09 1.55E+ll O.OOE+Ol O,OOE+OI O.OOE+01 O.OOE+01 O.OOEfol Y-91 7.45E+01 3.71fi05 O.ooftol O.OOE+01 O.OOE+Ol O.OOE+Ol O.ooftol 2.79E+03'.74E+02 Zr-95 5.36E+01 6.28E+04 6.02E+Ol 8.62E+01 O.OOE+01 O.oof+01 O,ooftol Nb-95 6.37E+03 1.65E+07 2.29E+04 8.91E+03 8.37E+03 O.OOE+Ol O.OOE+01 O.OOE>OI Ru-103 1.19E+02 7.98E+03 3.09E+02 O.OOE+01 7.77E+02 O.OOE+01 O.OOE+01 O.OOE>OI Ru-106 8.56E+02 1.07E+05 6.86E+03 O.OOE+01 9.27E+03 O.OOE+Ol O.OOE+Ol O.oofiol Ag-110M 8.63E+06 1,28E+09 I.60E407 1.08E+07 2.0IE407 O.OOE+01 O.OOE+01 O.ooftol Sn-113 4.61E+05 1.69E+06 4.22E+05 1.36ft04 9.38E+03 5.59E+03 O.OOE+01 O.ooftol Sb-124 2.75E+06 4.91E+07 7.84E+06 1.02E+05 O.oofiol 1.73E+04 4.35E+06 O.OOE+01 Te-127M 2.18E+06 1.49E+07 1.84E+07 4.95E+06 5.24E+07 4.40E+06 O.OOE+01 O.ooftol Te-129M 3.28E+06 2.58E+07 2.12E+07 5.91E+06 6.21E+07 6.82E+06 O.OOE+01 O.OOE>01 1-131 5.85ft08 9. I 7E i07 1.02f+09 1.03fi09 1.69E409 3.41filI O.OOE+01 O.OOE+01 1-132 4.67fiol 1. 19E+00 5.52E+01 I.OIE400 1.55fioo 4.71E+01 O.OOE+Ol O.ooftol 1-133 6.58E+06 7.00E+06 1.41E+07 1.74E+07 2.90E+07 3.23E+09 O.OOE+01 O.OOE+01 1-135 4.01E+04 6.47E+04 4.72E+04 8.49fi04 I.30E<05 7.52E+06 O.OOE+01 O.OOE>01 Cs-134 1.43E+10 3.67E+08 4.14E+10 6.80E+10 2.11E+10 O.OOE+Ol 7 '6E+09 O.OOE+01 Cs-136 3.41E+09 1.85E+08 1.92E+09 5.27E+09 2.81E+09 O.OOE+01 4.19E+08 O.OOE>01 Cs-137 8.72E+09 3.70E+08 6.17E+10 5.91E+10 1.93E+10 O.OOE+01 6.93E+09 O.OOE>01 Ba-140 5.23E+05 4.54E+05 8.96E+06 7.85E+03 2.56ft03 O.OOE+01 4.68E+03 O.OOE+01 Ce-141 1.17E+02 9.81E+05 1.53E+03 7.36E+02 3.45E+02 O.OOE+Ol O,OOE+Ol O.OOE+01 Ce-144 6.24E+03 9.55E+06 1.17E+05 3.66ft04 2.03E+04 O.OOE+01 O.OOE+Ol O.OOE+01 Hf-181 3.04E+02 4.99fi04 3.02E403 1.17E>01 9.43E+00 9.88E+00 O.OOE+Ol O.OOE+01 "R Values In units of mrem/yr per pCi/m for inhalation and tritium and in units of mrem/yr per pCI/sec per m for all others.
DCM/ODC-3 3-45 Rev. 3.0
t 1
C r,
P,
OS2 TABLE 3.3-15 R VALUES FOR THE SHEARON HARRIS NUCLfAR POWfR PLANT+
PATHWAY "-Goat Milk AGE GROUP = Infant Nuclide ~T. Bod Gl -Tract I!one Liver K~idne ~Th roid ~Lun Skin H-3 4.90fi03 4.90fi03 0.00ftOI 4.90E+03 4.90E+03 4.90E+03 4.90E+03 4.90fi03 P-32 4.88E+09 1.70E+09 1.26E( II 7.40E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Cr<<51 1.17E+04 3.42E+05 O.OOE401 O.OOE+Ol 1.67E+03 7.65E+03 I.49fi04 O.OOE+01 Mn-54 6.45E+05 1.04E>06 O.OOE+01 2.84f+06 6.30E+05 O.OOE+Ol O.OOEIOI 0.00fi01 Fe-59 1.20E+06 1.45E+06 1.74E+06 3.04E+06 O.OOE+01 O.OOE+01 9.00ft05 O.OOE+01 Co-58 4.31E+06 4.3IE+06 O.OOE+01 1.73E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Co-60 1.55E+07 1.56E+07 0.00ft01 6.56E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Zn-65 7.36E+08 1.35E+09 4.66ft08 1.60E+09 7.74E+08 O.OOE+01 O.OOE+01 O.OOE+01
" ." Rb-86 (8*.23E+08 i . 4;26E+07 0.00ftOI 1.67E+09 O.OOE+01 O.OOE+01 O.OOEWOI O.OOE+Ol Sr-89 4.55E+08 3.26E+08 1.59E+10 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Sr-90 4.30E+10 2.11E+09 1.69E+11" O.OOE+01 O.OOE+01 O.OOE+01 0.00ftOI O.OOE+01 Y"91 1.39E+02 3.75E+05 5.23E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE>OI 0.00ft01 Zr-95 8.41E+01 5.90E+04 4.85E+02 1.19E+02 1.28E+02 O.OOE+01 O.OOE>01 O.OOE+01 Nb-95 1.02E+04 1.48E+07 4.27ft04 1.76E+04 1.26E+04 O.OOE+01 O.OOE>01 0.00f+01 RU-103 2.09E+02 7.60E+03 6 '5ft02 O.OOE+01 1.30E+03 O.OOE+Ol 0.00fiOI O.OOE+Ol Ru-106" 1.77E+03 1.07E+05 1.41E+04 ',O.OOE+01 I.67fi04 O.OOE+01 0 ~ OOE+01 O.OOE+01 Ag-IIOM 1.43E+07 1.12E+09 2.95fi07 2.16E+07 3.08E+07 O.OOE401 O.OOE(OI O.OOE+01 Sn-113 6.66E+05 1.37E+06 6.46E+05 2.45E+04 1.32E+04 9.34E+03 0.00ft01 O.OOE+01 Sb-124 4.68E+06 4.66E+07 1.51EI07 2.22E+05 O.OOE+01 4.01E+04 9. 46EI06 O.OOE+01 Te-127M 4.51E+06 I.50fi07 3.72EI07 1.23E+07 9.16E+07 1.08E+07 O.OOE<01 O.OOE+01 Te-129M 6.69E+06 2.59E+07 4.34E+07 1.49E+07 1.09E408 I.67E407 O.OOE~OI O.OOE+01 1-131 1.11E+09 8.99E>07 2.14E+09 2.52E+09 2.94E+09 8.28E+11 O.OOE+Ol O.OOE+01 1-132 8.28E+01 1.88ft00 1.15E+00 2.33E+00 2.59E+00 1.09fi02 O.OOE(01 O.OOE+01 1-133 1.27E+07 7.31E+06 2.97E+07 4.32E+07 5.08E+07 7.86E+09 O.OOE>01 O.OOE+01 1-135 7.11E+04 7.06E<04 9.81f+04 1.95E+05 2.17E+05 1.75E+07 O.OOE+01 O.OOE>01 Cs-134 1.26E+10 3.38ft08 6.68E+10 1.25E+ll 3.21E+10 O.OOE+01 1.31E+10 O.OOE+01 Cs-136 4.1IE+09 1.67ft08 3.75E+09 1.10E+10 4.39E+09 O.OOE+01 8.98E+08 O.OOE+Ol" Cs-137 8.17E+09 3.6IE>08 9.85E+10 1.15E+11 3.10E+10 O.OOE+01 1.25E+10 O.OOE+Ol Ba-140 9.50E+05 4.53EI06 1.84E+07 1.84E+04 4.38E+03 O.OOE+01 1.13E+04 O.OOE+01 Ce-141 2.24f+02 9.85E>05 3.13E+03 1.91E+03 5.88E+02 O.OOE+01 0.00ft01 O.OOE>01 Ce-144 9.39E+03 9.61E>06 1.67E+05 6.86E+04 2.77E+04 O.OOE+01 O.OOE~OI O.OOE+Ol Hf-181 5.08E+02 4.72E+04 5.74fi03 2.71E+01 1.58E+01 2.30E+01 O.OOE401 O.OOE+01 "R Values in units of mrem/yr per IICI/m for Inhalation and tritium and in units of mrem/yr per
.NCI/sec per m for all others.
DCM/ODC-3 3-46 Rev. 3.0
I 8
+Wl "<</4A">
~r'F d
Y'C ll g
V
>I , lpga
' }+
f +l Yp "i.'
I'P, 4g l
lf 4M lf J $
Al
OS2 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Inhal AGE GROUP = Adult Nuclide Trod Bl-Trent Bone Liver ~Kidna ~Th roid ~Lee Skin H-3 1.26E+03 1.26Et03 O.OOEt01 1.26E+03 1.26E+03 1.26E+03 1.26Et03 1.26E+03 P-32 5.00E+04 8.63E+04 1.32Et06 7.70E+04 O.OOEt01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 9.99E+01 3.32Et03 O.OOEt01 O.OOEt01 2.28E+01 5.94E+01 1.44Et04 O.OOE+01 Mn-54 6.29E+03 7.72E+04 O.OOE+01 3.95E+04 9.83E+03 O.OOE+01 1.40E+06 O.OOEt01 Fe-59 1.05E+04 '1.88E+05 1.17E+04 2.77Et04 O.OOEt01 O.OOE+01 1.01E+06 O.OOE+01 Co-58 2.07Et03 1.06Et05 O.OOE+01 1.58E+03 O.OOE+01 O.OOE+01 9.27E+05 O.OOEt01 Co-60 1.48E+04 2.84Et05 O.OOE+01 1.15Et04 O.OOE+01 O.OOEt01 5.96Et06 ~ O.OOEt01 Zn-65 4.65E+04 5.34E+04 3.24Et04 1.03E+05 6.89E+04 O.OOEt01 8.63E+05 O.OOE+01 Rb-86 5.89E+04 1.66ft04 O.OOE+01 1.35Et05 O.OOE+01 O.OOEt01 O.OOEt01 O.OOEtol
~
Sr-89 L8;7 I ft03 3.49Et05 3.04E+05 n O.OOEt01 O.OOE+Ol O.OOE+Ol 1.40E+06 O.OOE+01 Sr-90 . 6.09E+06 7.21E+05 9.9IE+07 O.OOEt01 O.OOE+Ol O.OOE+Ol 9.59E+06 O.OOE+01 Y-91 1.24E+04 3.84E+05 4.62E+05 O.OOE+01 O.OOE+01 O.OOE+01 1.70Et06 O.OOEt01 Zr-95 2.32Et04 1.50E+05 1.07Et05 3,44E+04 5.41E+04 O.OOEt01 1.77Et06 O.OOEt01 Nb-95 4.2OEt03 1.04E+05 1.41E+04 7.80E+03 7.72E+03 0.00f+01 5.04E+05 O.OOE+01 Ru-103 6.57E+02 1.10E+05 1.53E+03 O.OOE+Ol 5.82E+03 O.OOE+01 5.04E+05 O.OOEtol Ru-106 8.71Et03 9. IIE+05 6.90Et04 O.OOEt01 1.33Et05 O.OOE+01 9.35E+06 O.OOE+01 Ag-110M 5.94E+03 3.02E+05 1.08E+04 9.99Et03 1.97E+04 O.OOE+Ol 4.63Et06 O.OOE+01 Sn-113 6.48E+03 2.48Et04 6.86E+03 2.69Et02 1.97E+02 9,33E+01 2.99E+05 O.OOEt01 Sb-124 1.24E+04 4.06E+05 3.12Et04 5.88Et02 O.OOE+01 7.55E+01 2.48Et06 0.00ft01 Te-127M 1.57E+03 1.49E+05 1.26Et04 5.76Et03 4.57E+04 3.28E+03 9.59Et05 O.OOEt01 Te-129M 1.58E+03 3.83Et05 9.75E+03 4.67Et03 3.65ft04 3.44E+03 1.16E+06 0.00ft01 I -'1 31 2.05Et04 6.27E+03 2.52Et04 3.57Et04 6.12E+04 1.19f+07 O.OOE+01 O.OOEt01 1-132 1.16E+03 4.06Et02 1.16Et03 3.25Et03 5.18E+03 1.14Et05 O.OOEt01 O.OOEt01 1-133 4.51Et03 8.87ft03 8.63Et03 1.48Et04 2.58E+04 2.15E+06 O.OOE+01 O.OOEt01 I -135 2 '6E+03 5.24E+03 2.68E+03 6.97ft03 1.11Et04 4.47E+05 O.OOE+01 O.OOEt01 Cs-134 7.27E+05 1.04E+04 3.72E+05 8.47E+05 2.87E+05 O.OOE+01 9.75E+04 O.OOEt01 Cs-136 1.10Et05 1.17E+04 3.90E+04 1.46E+05 8.55E+04 O.OOEt01 1.20E+04 O.OOE+01 Cs-137 4.27E+05 8.39E+03 4.78E+05 6.2OEt05 2.22E+05 O.OOE+01 7.51Et04 O.OOEt01 Ba-140 2.56Et03 2.18E+05 3.90Et04 4.90Et01 1.67Et01 O.OOE+01 1.27Et06 O.OOEt01 Ce-141 1.53Et03 1.20E+05 1.99Et04 1.35Et04 6.25E+03 O.OOE+01 3.61E+05 O.OOEt01 Ce-144 1.84E+05 8.15E+05 3.43E+06 1.43Et06 8.47E+05 O.OOE+01 7.76E+06 O.OOEt01 Hf-181 5.16Et03 1.29E+05 4.56Et04 2.57E+02 2.15E+02 1.63E+02 5.99E+05 O.OOEt01 "R Values in units of mrem/yr per IICI/m for inhalation and tritium and in units of mrem/yr per pCI/sec per m for all others.
DCM/ODC-3 3-47 Rev. 3.0
4I
~A 1
C) 4 J
4
OS2 TABLE 3.3-17 R VALUfS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY = Inhal AGE GROUP = Teen Necllde ~T. Bcd Gl-Tract Liver ~Kldne ~Th roid ~Lun Skin H-3 I .27E i03 1.27E+03 O.OOE+01 1.27ft03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P>>32 7.15E404 9.27E+04 1.89E+06 1.09fi05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr -51 1.35E+02 3.00E+03 O.OOE+01 O.oof>01 3.07fioI 7.49E+Ol 2.09E+04 O.OOE+01 Nn-54 8.39E+03 6.67E+04 O.OOE+01 5 ~ Iof>04 1.27ft04 O.OOE+01 1.98f+06 O.OOE+Ol Fe-59 1.43E+04 1.78E+05 1.59fi04 3.69E+04 O.oof>OI O.OOE+01 1.53E+06 O.OOE+01 Co-58 2.77E+03 9.51E+04 O.OOE+Ol 2.07E>03 O.oof>01 O.OOE+01 1.34E+06 O.OOE+01 Co-60 1.98E+04 2.59E+05 O.OOE+01 1.51E+04 O.ooftol O.OOE+01 8.71E+06 O.OOE+01 Zn-65 6.23E+04 4.66E+04 3.85E+04 1.33E+05 8.63E+04 O.OOE+01 1.24E+06 O.OOE+01 Rb-86 8.39E+04 1.77E+04 O.OOE+Ol 1.90E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01
~ -d Sr-89 hlI.25E+04 te. 3.7.1E+05 - 4.34E+05 . O.OOE+01 O.OOE+01 O.OOE+01 2.41E+06 O.OOE+01 Sr-90 6.67E+06 7.64E+05 1.08E+08 O.OOE+01 O.ooftol O.OOE+Ol 1.65E+07 O.oofiol Y-91 1.77E+04 4.08E+05 6.60E+05 O.OOE+01 O.OOE+01 O.OOE+01 2.93E+06 O.OOE+01 Zr-95 3.15E+04 1.49E+05 1.45E+05 4.58E>>04 6.73ft04 O.oof+Ol 2 '8ft06 O.OOE+01 Nb-95 5.66E>03 9.67E+04 1.85E+04 1.03E+04 9.99E+03 O.OOE+01 7 '0E+05 O.OOE+Ol Ru-103 8.95E+02 1.09E+05 2.10E+03 O.oof<OI 7.42E+03 O.OOE+Ol 7.82E+05 O.OOE+01 Ru-106 1.24E+04 9.59E+05 9.83E+04 O.OOE>OI 1.90ft05 O.OOE+01 1.6IE+07 O.OOE+Ol Ag-IIOH '.98E+03 2.72E+05 1.38E+04 1.31fi04 2.50E>04 O.OOE+01 6.74E+06 O.OOE+01 Sn-113 8.68E+03 2.03E+04 '.19E+03 3.44E<02 2.45E+02 1.13E+02 4.27E+05 O.OOE+01 iQ>>
Sb-124 1.68E+04 3.98E+05 4.30E+04 7.94fi02 O.OOE>01 9.76E+01 3.85E+06 O.oof+01 Te-12714 2.18E403 1.59E+05 1.80E+04 8.15E+03 6.53E>>04 4,38E+03 1.65E+06 O.OOE+Ol Te-12914 2.24E+03 4.04E+05 1.39E+04 6.57f>>03 5.18fi04 4.57E+03 I ~ 97f+06 O,OOE+01 1-131 2.64E+04 6.48E+03 3.54E+04 4.90fi04 8.39fi04 1.46E+07 O.OOE+01 O.OOE+01 1-132 1.57E+03 1.27E+03 1.59E+03 4.37fi03 6.91E+03 1.51E+05 O.OOE+01 O.OOE+01 1-133 "
'6.'21E+03 1.03E+04 1.21E+04 2.05ft04 3.59E+04 2.92f+06 O.OOE+01 O.OOE+Ol 1-135 3 '8E+03 6.94E+03 3.69E+03 9.43ft03 1.49fi04 6.20E+05 O.OOE+01 O.OOE+Ol Cs-134 5.48E+05 9.75E+03 5.02E+05 1.13ft06 3.75E+05 O.OOE+Ol 1.46E+05 O.OOE+01 Cs-136 1.37E+05 1.09E+04 5.14E>04 1.93fi05 1.10E+05 0.00fi01 1.77E+04 O.OOE+01 Cs-137 3.11E+05 8.48E+03 6.69E+05 8.47E>>05 3.04E+05 O.OOE+01 1.21E+05 O.OOE+01 Ba-140 3.51E+03 2.28E+05 5.46E+04 6.69E+01 2.28E+01 O.OOE+01 2.03E+06 O.OOE+01 Ce-141 2.16E+03 1.26E+05 2.84E+04 I ~ 89E+04 8.87E+03 O.OOE+01 6.13E+05 O.OOE+01 Ce-144 2.62E+05 8.63E+05 4.88E+06 2.02E>06 1.21E>06 O.OOE~OI 1.33E+07 O.OOE+01 Hf-181 7.04E+03 1.20E+05 6.32E+04 3.48E+02 2.90E+02 2.12E+02 9.39E+05 O.OOE+01 "R Values in units of mrem/yr per liCI/m for inhalation and tritium and in units of mrem/yr per liCI/sec per m for all others.
DCM/ODC-3 3-48 Rev. 3.0
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OS2 TABLE 3.3-18 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT+
PATHWAY = Inhal AGE GROUP = Child Nuclide Trod Gl-Tract Bone Liver ~KI dna Teraid ~Lac Skin H-3 1.12E+03 1.12Et03 O.OOEt01 1. 12E+03 1.12E+03 1.12E+03 1.12Et03 I ~ 12E+03 P-32 9.86Et04 4.21Et04 2.60E+06 1.14Et05 O.OOEt01 O.OOE+01 O.OOEtOI O.OOE+01 Cr -51 1.54E+02 1.08E+03 O.OOE+Ol O.OOEt01 2.43Et01 8.53E+01 1.70Et04 O.OOEt01 Mn-54 9.50E+03 2.29Et04 O.OOE+01 4.29E+04 I.OOE+04 O.OOE+01 1.57Et06 O.OOEt01 Fe-59 1.67E+04 7.06Et04 2.07E+04 3.34Et04 O.OOEt Ol O.OOEt01 1.27E+06 O.OOEtOlu Co-58 3.16Et03 3.43Et04 O.OOEt01 1.77Et03 O.OOE+Ol O.OOE+Ol 1.10Et06 O.OOEt01 Co-60 2.26E+04 9.61Et04 O.OOE+Ol 1.31E+04 O.OOEt01 O.OOE+Ol 7.06Et06 O.OOEt01 Zn-65 7.02E+04 1.63E+04 4.25Et04 1.13E+05 7.13E+04 O.OOEt01 '9.94Et05 O.OOEt01 Rb-86 1.14E+05 7.98E+03 O.OOE+01 1.98E+05 O.OOEt01 O.OOE+01 O.OOEt01 O.OOE+Ol
<<, ~ ", <<.Sr-89 ~I.72Et04 '.d1.67E+05 5.99Et05 O.OOEt01 O.OOE+01 O.OOEt01 2.15Et06 O.OOE+Ol Sr-90
- 76.43Et06 3.43E+05 1.01E+08 O.OOEt01 O.OOEt01 O.OOEt01 1.47E+07 O.OOEt01 Y-91 2.43E+04 1.84Et05 9.13E+05 O.OOE+01 O.OOEt01 O.OOEt01 2.62Et06 O.OOE+Ol Zr-95 3.69E+04 6.10E+04 1.90E+05 4.17Et04 5.95Et04 O.OOEtol, 2.23E+06 O.OOE+01 Nb-95 6.54E+03 3.69Et04 2.35E+04 9.16E+03 8.61Et03 O.OOEtol 6.13E+05 O.OOEt01 Ru-103 " 1.07E+03 4.47E+04 2.79E+03 O.OOE+01 7.02E+03 O.OOE+01 6.61E+05 O.OOE+01 Ru-106 1.69E+04 4.29Et05 1.36E+05 O.OOEt01 1.84Et05 O.OOE+01 1.43E+07 O.OOE+01 Ag-IIOM 9.13Et03 1.00Et05 . 1.68E+04 '.14Et04 2.12E+04'.02E+02 O.OOE+01 5.47E+06 O.OOE+01 Sn-113 9.83E+03 7.45E+03 9.00E+03 2.91E+02 1.19E+02 3.40E+05 O.OOE+01 Sb-124 2.00E+04 '.64E+05 5.73E+04 .
7.40E+02 O.OOEt01 I 26Et02
~ 3.24Et06 O.OOEt01 Te-127M 3.01Et03 7.13Et04 2.48E+04 8.53E+03 6 '5E+04 6.06E+03 1.48E+06 O.OOE+01 Te-129M 3.04E+03 1.81Et05 1.92E+04 6.84E+03 5.02Et04 6.32E+03 1.76Et06 O.OOEt01 1-.1 31 2.72E+04 2.84Et03 4.80E+04 4.80E+04 7.87Et04 1.62E+07 O.OOEt01 O.OOEt01 1-132 1.87E+03 3.20E+03 2,IIEt03 d 4.06Et03 6.24E+03 1.93E+05 O.OOE+Ol O.OOEt01 1-133 '" 7;68E+03 5.47Et03 1.66E+04 2.03Et04 3,37Et04 3 '4E+06 O.OOEt01 O.OOEt01 1-135 4.14E+03 4.43Et03 4.91E+03 8.72Et03 1.34E+04 7.91E+05 O.OOEt01 O.OOEt01 Cs-134 2.24E+05 3.84E+03 6.50E+05 1.01E+06 3.30E+05 O.OOE+Ol 1.21Et05 O.OOEt01 Cs-136 1.16E+05 4.17E+03 6.50E+04 1.71E+05 9.53Et04 O.OOE+01 1.45E+04 O.OOEt01 Cs-137 1.28E+05 3.61Et03 9.05E+05 8.24Et05 2.82E+05 O.OOE+01 1.04Et05 O.OOEt01'.OOEt01 Ba-140 4.32Et03 1.02E+05 7.39E+04 6.47E+01 2.11E+01 , O.OOE+01 1.74Et06 Ce-141 2.89Et03 5 .65E+04 3.92E+04 1.95E+04 8.53E+03 O.OOE+Ol 5.43E+05 O.OOE+01 Ce-144 3.61E+05 3.88E+05 6.76Et06 2.11E+06 1.17E+06 O.OOE+01 1.19Et07 O.OOEt01 Hf-181 8.50Et03 5.31E+04 8.44E+04 3.28Et02 2.64E+02 2.76E+02 7.95E+05 O.OOE+01 "R Values in units of mrem/yr per pCI/m for inhalation and tritium and in units of mrem/yr per NCI/sec per m for all others.
DCM/ODC-3 3-49 Rev. 3c0
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OS2 TABLE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLfAR POWER PLANT" PATHWAY = Inhal AGE GROUP = Infant Nuclide T~i. Bod GI-Tract Liver ~KI dne T~hroid ~Lun Skin 6.46Et02 6.46Et02 O.OOEt01 6.46Et02 6.46E+02 6.46ft02 6.46Et02 6.46Et02 P-32 7.73E+04 1.61Et04 2.03Et06 1.12Et05 O.OOE+01 O.OOEtol O.OOEt01 O.OOE+01 Cr-51 8.93Et01 3.56E+02 O.OOEt01 O.OOEt01 1.32E+Ol 5.75Et01 1.28Et04 O.OOE+01 Mn-54 4.98E+03 7.05Et03 O.OOEt01 2.53E+04 4.98E+03 O.OOE+Ol 9.98Et05 O.OOEt01 Fe-59 9.46E+03 2.47Et04 1.35Et04 2,35Et04 O.OOE+Ol O.OOEt01 1.01Et06 O.OOEt01.
Co-58 1.82E+03 1.11Et04 O.OOE+01 1.22E+03 O.OOE+01 O.OOEt01 7.76Et05 O.OOE+01 Co-60 1.18E+04 3.19Et04 O.OOE+01 8.01Et03 O.OOE+01 O.OOEt01 4.50Et06 O.OOEt01 Zn-65 3.10E+04 5 '3Et04 1.93E+04 6,25Et04 3.24E+04 O.OOE+01 6.46Et05 O.OOEt01 Rb-86 8.81E+04 3.03Et03 O.OOEt01 1.90Et05 0.00f+Ol O.OOEt01 O.OOEt01 O.OOE+01 Sr-89 -. -'1.14E+04d 6:39Et04 r . 3.97Et05 O.OOEt01 ,O.OOE+01 O.OOEt01 2.03Et06 O.OOEt01 Sr-90 2.59E+06 I ~ 31Et05 4.08Et07 O.OOEt01 O.OOE+Ol O.OOEt01 1.12Et07 O.OOE+01 Y-91 1.57E+04 7.02Et04 5.87E+05 O.OOE+01 O.OOE+Ol O.OOE+01 2.45Et06 O.OOEt01 Zr-95 2.03E+04 2.17ft04 1.15Et05 2.78Et04 3.10E+04 O.OOEt01 1.75Et06 O.OOEt01 Nb-95 3.77E+03 1.27E+04 1.57Et04 6.42E+03 4.71E+03 O.OOE+01 4.78Et05 0.00f+Ol Ru-103 6.78E+02 1.61Et04 2.01Et03 O.OOEt01 4.24E+03 0.00f+01 5.51f t05 0.00ft01 Ru-106 1.09E+04 1.64Et05 8.67Et04 O.OOEt01 1.06E+05 O.OOE+01 1.15Et07 O.OOE+01 Ag-IIOM 4.99E+03 3,30Et04 9.97Et03 7 '1Et03 '.09f+04 O.OOE+01 3.66Et06 O.OOEt01 Sn-113 4.89E+03 2.29Et03 4.67Et03 1.74Et02 9.94E+01 6.73E+01 2.30Et05 O.OOE+01 Sb"I24 1.20E+04 5.91Et04 3.79E+04 5.56Et02 O.OOE+Ol I.OOEt02 2.64Et06 O.OOE+01 Te-127M 2.07E+03 2.73E+04 1.66Et04 6 '9Et03 3.75E+04 4.86E+03 1.31Et06 O.OOE+01 Te-129M 2.22f+03 6.89E+04 1.41Et04 6.08Et03 3.17E+04 5.47E+03 1.68Et06 0.00f t01 I-131 1.96E+04 1.06Et03 3.79Et04 4.43E+04 5.17Et04 1.48E+07 O.OOEt01 O.OOE+01 I-132 1.26E+03 1.90Et03 1.69Et03 3.54Et03 3.94Et03 1.69E+05 O.OOEt01 O.OOEt01 I-133 5.59E+03 2.15Et03 1.32Et04 1.92Et04 2.24E+04 3.55Et06 O.OOEt01 O.OOEt01 I-135 2.77E+03 1.83Et03 3.86Et03 7.59Et03 8.46Et03 6.95E+05 O.OOEt01 O.OOEt01 Cs-134 7.44E+04 1.33E+03 3.96Et05 7.02Et05 1.90Et05 O.OOE+01 7.95Et04 O.OOE+01 Cs-136 5.28E+04 1.43Et03 4.82Et04 1.34Et05 5.63E+04 O.OOEt01 1. 17Et04 O.OOEt01 Cs-137 4.54f+04 1.33Et03 5.48Et05 6.11Et05 1.72E+05 O.OOEt01 7.12Et04 O.OOEt 01 Ba-140 2.89E+03 3.83Et04 5.59Et04 5.59E+01 1.34E+Ol O.OOE+01 1.59Et06 O.OOEt01 Ce-141 1.99E+03 2.15E+04 2.77E+04 1.66E+04 5.24E+03 O.OOE+01 5.16Et05 O.OOE+01 Ce-144 1.76E+05 1.48E+05 3.19Et06 1.21E+06 5.37E+05 O.OOE+01 9.83Et06 O.OOE+01 Hf-181 5.05Et03 1.90Et04 5.65ft04 2.66Et02 1.59E+02 2.25Et02 6.73Et05 O.OOE+01 "R Values in units of modem/yr per MCI/m for Inhalation and tritium and In units of mrem/yr per MCI/sec per m for al I others.
DCM/ODC-3 3-50 Rev. 3.0
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C1 REM-RADIAllOH EFFLUEHT IIOHITOR nK Figure 3,1 SHNPP GASEOUS WASTE STREAMS UNIT 1 WPB-WASTE PROCESSIHC BlDC RAB-REACTOR AVXIUARY BlDC FHB-FIIEL HAHDUHC BLDC O WRCM-WIDE RAHCE CAS MOHITOR nI TURBiNE BLDG VENT STACK 3A RM RM-ITV-3536-1 (WRCM)
REM llV-3534 REM CONDENSER POL AREA CONDENSER VACUUM PUMP WASTE PROCESSiNG BLDG VENT STACK 5 RM REM REM-1WV-3546 RMI-WV-3546-1 (WRCM)
WPB HOT Cc COLD LAUNDRY WPB OFflCE AREA EXHAUST WPB COLD LAUNDRY DRYERS WPB CONTROI. ROOM SMOKE EXHAUST WPB OFflCE AREA WPB GENERAL AREA EXHAUST WPB CHILLER ROOM EXHAUST WASTE GAS DECAY TANKS WASTE PROCESSING AREAS FlLTERED EXHAUST WASTE PROCESSiNG BLDG VENT STACK 5A RM-IWV-3547-1 (WRCM) RM REM REM-IWV-3547 WPB S'NTCHGEAR ROOM EXHAUST WPB HVAC EQUIP. ROOM EXHAUST WPB PERSONNEL HANDLING FACIUTY EXHAUST VPB HOT 84 LOW ACTIVITY EXHAUST WPB LAB AREA EXHAUST PLANT VENT STACK 1 RM-21 AV-3509-1SA (WRCM)
REM-1LT-35028 REM REM-IAV-3509A REM CONTAINMENT PRE ENTRY PURGE REM-ILT-3531 REM FHB NORMAL EXHAUST NORTH RAB NORMAL EXHAUST FHB NORMAL EXHAUST SOUTH REM-IAV-3532A REM REM REM-IFL-3506 RAB EMERGENCY EXHAUST REM-IAV-35328 FHB NORMAL EXHAUST (OPER. FL) SOUTH REM REM 1FL 3507 REM RAB VENTILATION SYSTEM FHB NORMAL EXHAUST (OPER. FL) SOUTH C) REM REM-IFL-3508 A-SA HYDROGEN PURGE RAB SMOKE PURGE REM-IFL-35088-SB REM FHB EMERGENCY EXHAUST RAB PURGE
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PLANT NORTH MAGNETIC NORTH 0
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5A COOLING TOWER BWST RhlWS T WATEfl SE flVICE ECV I EATME BLDG PA f1 KING AREA 0 OO WARE HOUSE I5 SWITCHYARQ PARKING AREA Q
SHEABON HARRIS NUCLEAR POWER PLANT CAROLINA POWER 5 LIGHT COMPANY SCHAIIATICOF PLANT AIRBORNE EFFLUENT RELEASE POINTS FIGURE 3.3 lA CD
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Figure 3.3 SHNPP CONDENSEA OFF.GAS SYSTEM TV((BINE BLDG RM.I TYPES 06 I PIRGhl) VENT STACK SA GLAND STEAM COND.
MAI N CONDEt(SE(l HOGGING VALVE WAGM WIDE RANGE GAS MONI'TO(l BLIND FLANGE I(EM IIAOIATIONEFFLUENT h(Ot(ITOR
'CONDENSEll VACUUhl PUMP EFFLUENT TAEAThIENT ATMOS('NERE SYSTEM ADAPTED f IIOM F IGUAE 0.4.02 SHNPP FSAII AhIEt(OMENT NO, 'IS
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OS2 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.1 contains the sample point description, sampling and collection frequency, analysis type, and frequency for various exposure pathways in the vicinity of the SHNPP for the radiological monitoring program. Figure 4.1-1 shows the exclusion boundary surrounding SHNPP. Figures 4.1-2, 4.1-3, and 4.1-4 show the locations of the various sampling points and TLD locations.
Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4.
DCM/ODC-4 4-1 Rev. 3.0
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TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description I
~
Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~F55 5555 ~5551 515
- 1. Airborne 0.1 mi. S on SR 1134 Continuous operating Weekly Gross Beta Particulates from SR 1011 intersection. sampler with sample I-131 and Radioiodine N. sector, 2.5 mi. from collection as required (charcoal.<<.
site. by dust loading but at canisters) least once per 7 days. Quarterly Gamma Isotopic by 'omposite Location 1.4 mi. S on SR 1134 from SR 1011 inter-section. NNE sector, 1.5 mi. from site.
0.5 mi. S on SR 1127 from intersection with SR 1011 NNE sector, 3.2 mi . from site.
Pittsboro.
12 mi. NW sector from site (Control Station) m (A
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point-, Description I Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Frn cnnc A~nal nln
- 1. Airborne 26 Harris Lake Spill<<ay. Continuous operating Weekly Gross Beta Particulates S sector, 4.6 mi. from sampler with sample Meekly 1-131 n and Radioiodine site. collection as required (charcoal (continued) by dust loading but at canisters) least once per 7 days. Quarterly Gamma Isotopic by 'omposite Location 47 1.3 miles N on SR 1912 from intersection of NC 42 and SR 1912.
SSW sector, 3.4 miles from site.
- 2. Direct 0.1 mi. S on SR 1134 Continuous measurement Quarterly Gamma Dose Radiation from SR-1011 inter- with an integrated (TLD) section. N sector, 2.5 readout at least ml. from site. once per quarter.
2 1.4 mi. S on SR 1134 from SR 1011 inter-section. NNE sector, 1.5 mi. from site.
0.9 mi. S on SR 1127 from US I intersection.
HENDEC. ENE sector, 2.6 mi. from site.
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TABLE 4.1
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I Sample Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Frequenc ~Frn cnnc A~nnl nln
- 2. Direct 0.5 mi, S on SR 1127 Continuous measurement Puarterly Gamma Dose Radiation from intersection with with an integrated (continued) SR 1011 NNE sector, readout at least 3.2 mi. from site. once per quarter.
Pittsboro, NW sector,
> 12 mi. from site (control station)
Intersection of SR 1134 6 SR 1135, ENE sector, On9 mi.
from site.
Extension of SR 1134. E sector, On8 mi. from site.
Dead end of road.
Extension of SR 1134. ESE sector, 0.7 mi. from site.
I mi. S on SR 1130 from intersection of SR 1127, 1115, and m 1130. SE sector, 2.3 mi. from site o
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description I
~ ~
Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~yrc uency A~nnl nln
- 2. Direct 10 SR 1130 S of intersection Continuous measurement Quarterly Gamma Dose Radiation of SR 1127, 1115, and 1130. with an integrated (continued) SSE sector, 2.2 mi. from site. readout at least once per quarter.
SHNPP site. S sector, 0.7 mi. from site.
12 SHNPP site. SSW sector, 0.8 mi. from site.
13 SHNPP site. SW sector, 0.7 mi. from site.
14 SHNPP site. Access road to aux. reservoir. W sector, 1.4 mi. from site.
15 SR 1911. W sector, 1.8 mi. from site.
16 1.2 mi. E of inter-section of US I and SR 1011. WNW sector.
1.7 mi. from site.
17 Intersection of US I and Aux. Res. NW sector, 1.4 mi. from site.
I Y
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t-Sample I
Exposure Pathway Point Sample Point, Description Sampl ing .arid Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Fee cene ~Ann I ete
- 2. Direct IS 0.2 mi. N on US I from Continuous measurement Quarterly Gamma Dose Radiation Station 17. NNW sector, with an integrated (continued) 1.3 mi. from site. readout at least once per quarter.
19 0.6 mi. E on SR 1142 from intersection of SR 1141. NNE sector 4.9 mi from site.
20 US I at intersection SR 1149. NE sector 4.7 mi. from site.
21 1.2 mi. W on SR 1152 from intersection SR 1153. ENE sector, 4.8 mi.
from site.
22 Formerly Ragan's Dairy on SR 1115. E sector, 4.6 mi. from site.
23 Intersection of SR 1127 and SR 1116. ESE sector, 5.0 mi. from site.
24 Sweet Springs Church on SR 1116. SE sector, 4.7 mi. from site.
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description I
~
Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~rrn cene ~Anni nln
- 2. Direct 25 0,2 mi. W on SR 1402 Continuous measurement Quarterly Gamma Dose Radiation from intersection of SR with an integrated (continued) 1400. SSE sector, 4.8 readout at least mi. from site. once per quarter.
26 Harris Lake Spillway.
S sector, 4.6 mi. from site.
27 NC 42 Il Buckhorn United Methodist Church SSW sector, 4.8 mi. from site.
28 0.6 mi. on SR 1924 from intersection of SR 1916.
SW sector, 4.8 mi. from site.
29 Parking lot of Chembond Corporation on SR 1916.
WSW sector, 5.6 mi. from site.
30 Exit intersection of SR 1972 and US 1. W sector, 5.1 mi. from site.
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample
~ - I Analysis Exposure Pathway Point Sample Point, Description Sampling and and/or Sample ID No. Distance and Direction Collection Fre uenc ~Fcn nnnc A~nnl nln
- 2. Direct 31 At intersection of SR Continuous measurement Quarterly Gamma Dose Radiation SR 1908, 1909, 1910. WNW with an integrated (continued) sector, 4n5 mi. from site. readout at least once per quarter 32 SR 1008. NW sector, 6.4 mi. from site.
33 SR 1142. 1.7 mi. from intersection of SR 1141.
NNW sector, 4.4 mi. from site.
34 Apex (Population Center).
NE sector, 8.6 mi. from site.
Holly Springs (Population Center). E sector, 6.9 mi. from site.
36 SR 1393 at intersection of SR 1421. E sector, 11.2 mi from site 37 US 401 at old CPIIL office, Fuquay-Varina (Population Center). ESE sector, 9.7 mi. from site.
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description ~ 1 Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uency ~Fre uenc A~nal sis
- 2. Direct SR 1142. 1.5 mi. from Continuous measurement Quarterly Gamma Dose Radiation intersection of SR 1141. with an integrated (continued) N sector, 4.5 mi. from readout at least site. once per quarter.
49 SR 1127. 0.3 mi. S from intersection with US 1.
NE sector, 2.6 mi. from site.
50 SR 1127 W from inter-section SR 1115 and 1130.
ESE sector, 2.8 mi. from site.
53 SR 1972 N from inter-section of SR 1910 and SR 1972. NW sector, 5.5 mi. from site.
56 SR 1912 at intersection of SR-1912 and SR 1924 WSW sector, 2.8 mi. from site.
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample I
Exposure Pathway Point Sample Point, Description Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Frn nnnn ~Anni nln
- 3. Waterborne a.'urface 26 Harris Lake Spillway Composite sample Monthly Gross Beta Water S sector, 4.6 mi. from collected over a Gamma Isotopic site. period of < 31 days. Quarterly Tritium .
38 Cape Fear Steam Electric=-
Plant Intake Structure (Control Station)
WSW sector, 6.1 mi. from s iie.
40 U.S. Geological Survey gauging station. Lilling-ton, at intersection of NC 210 and the Cape Fear River. SSE sector " 17 mi.
from site.
- b. Groundwater 39 On-site deep well in the Grab sample quarterly Each Sample Gamma Isotopic proximity of the diabase dikes. Tritium SSW sector, 0.7 mi. from site.
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Pathway Point Sample Point, Description I Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Fnn nnnc ~Anni nln
- c. Drinking 38 Cape Fear Steam Composite sample 1-131 On 1-131 water Electric Plant Intake over two-week period each compo-Structure (Control if I-131 analysis is site when Station) 3 . WSW sector, performed; monthly ihe dose 6.1 mi. from site. composite otherwise. calculated for the consumption of the water is greater than I mrem per yr.
Monthly Gross Beta Gamma Isotopic Quarterly Tritium 40 U.S. Geological Survey gauging station. Lillington, at intersection of NC 210 and the Cape fear River.
SSE sector, 17 mi. from site.
51 SHNPP Water Treatment Building on site
- d. Sediment 26 Harris Lake Spillway. Surface sediment sample Each sample Gamma Isotopic from S sector, 4.6 mi. from semiannually Shoreline site.
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TABLE 4.1 (continued)
RAD I OLOG I CAL ENV I RONMENTAL MON I TOR I NG PROGRAM O
aA Sample I
Exposure Pathway Point Sample Point, Description I Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Fre uenc ~Anal sis
- d. Sediment 41 Shoreline of mixing zone from of cooling tower blowdown Shoreline line. S sector, 3.8 mi.
(continued) from site.
- e. Bottom 52 Harris Lake in the vicinity Bottom sediment sample Each sample Gamma Isotopic Sediment of the mixing zone of the semiannually cooling tower. S sector, 3.8 mi. from site.
- 4. Ingestion 42 Maple Knoll on SR 1403. Grab samples semi- Each sample 1-131 II
- a. Milk SSE sector, 7.5 mi. from monthly when animals Gamma Isotopic site. are on pasture;
- monthly g other times.
Olive's Dairy on SR 1178.
NNE sector, 4.6 mi. from site.
43 Goodwin's Dairy on SR 1134.
N sector, 2.2 mi. from site.
Strowd's Dairy, Pittsboro (Control Station) > 12 mi.
NW sector from site.
m
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TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample I
Exposure Pathway Point Sample Point, Description
~
Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Fre ccnc A~nal nln
- b. Fish 44 Site varies within One sample of each Each sample Gamma Isotopic the Harris Lake. of the following semi- on edible por-annually: tion for each
- 1. Catfish (bottom feeders)
- 2. Sunfish & Largemouth Bass (free swimmers) 45 Site varies above One sample of each of Each sample Gamma Isotopic Buckhorn Dam on the following semi- on edible Cape Fear River rnid annually: portion for each (Control Station)
- 1. Catfish (bottom feeders)
- 2. Sunfish &, Largemouth Bass (free swimmers)
- c. Food 54 SR 1189. Gunter-Morris Rd. Samples of .3 different Each sample Gamma Isotopic Products NNE sector, 1.7 from kinds of broadleaf and 1-131 analysis site vegetation monthly dur-ing the growing season 55 SR 1167. Bonsai. NNW sector, 1.7 mi. from site.
PQ 41 1
TABLE 4.1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM e
Sample Exposure Pathway Point Sample Point, Description I Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc ~Are cene ~Anal ale
- c. Food Pittsboro. (Control Products Station) 3 . WNW, NW, or (continued) NNW sector, greater than 12 mi. from site
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OS2 NOTES TO TABLE 4 '
SHNPP Radiolo ical Environmental Monitorin Pro ram
- 1. Sample locations are shown on Figures 4.1-2, 4.1-3, and 4.1-4. Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4.
- 2. Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.
- 3. Control sample stations (or background stations) are located in areas that are unaffected by plant operations. All other sample stations that have the potential to be affected by radioactive 'emissions from plant opera-tions are considered indicator stations.
4.
~ Gamma isotopic analysis means "the identification,
~ ~
and quantitation of
.gamma-emitting radionuclides that may be attributable to effluents from plant operations.
- 5. Composite samples will be collected 'with equipment which is capable of collecting an aliquot at time intervals which are very short (e.g., every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) relative to the compositing period (e.g., monthly).
- 6. The dose will be calculated for the maximum organ and age group,, using the methodology contained in ODCM Equation 2.2-1.
- 7. Based on historical meteorology (1976-1987), food product Locations 54 and
, 55 were added in the summer of 1988 as the off-site locations with the highest predicted D/Q values. Food product locations 43 and 46 were deleted after the 1988 growing season.
DCM/ODC-4 4-15 Rev. 3.0
Oj DIXIE PIPELINE SHEARON HARRIS NUCLEAR POWER PLANT yP'< CAROLINAPOWER & LIGHT COMPANY q<
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Figure 4.1-5 Legend REFER TO STATION REFER TO STATION FIGURE NUMBER SAMPLE TYPE FIGURE NUMBER SAMPLE TYPE 4.1-4 I AP, AC, TL 4.1-3p 4.1-4 26 APp ACp SWp SS TL
- 4. 1-4 3 TL 4.1-2, 4.1-4 28 TL 4.1-4 4 AP, AC, TL 4.1-2 29 TL 4.1-2% 5 AP, AC, MK, FC, TL 4.1-2 30 TL 4.1-4 6 TL 4.1-2 31 TL 4.1-4 7 TL 4.1-2 32 TL 4.1-4 8 TL 4.1-3 .33 TL 4.1-4 9 TL 4.1-3 34 TL
- 4. 1-4 IO TL 4.1-3 35 TL 4.1-4 ll TL 4.1-3 36 TL 4.1-4 12 TL 4.1-3 37 TL 4.1-4 13 TL 4.1-2 38 SW, DW 4.1-4 14 TL 4.1-4 39 GW 4.1-4 15 TL 4.1.3 40 SW, DW
- 4. 1-4 16 TL 4.1-4 41 SS 4.1-4 17 TL 4.1-3 42 MK 4.1-4 18 TL 4.1-4 43 MK
- 4. 1-3 22 TL 4. 1-3 48 TL 4.1-3 23 TL 4. 1-4 49 TL 4.1-3 24 TL 4. I "4 50 TL 4.1-3, 4.1-4 25 TL 4. 1-4 51 DW
- 4. 1-4 52 SD
- 4. 1-2 53 TL AC Air Cartridge 4. 1-4 54 FC Air Particulate 4. 1-4 55 FC SD Bottom Sediment 4,1-4 . 56 TL FC Food Crop FH fish GW Groundwater MK Milk SW Surface Water DW Drinking Water TL TLD SS Shoreline Sediment "Approximate location
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OS2 5 ' INTERLABORATORY COMPARISON STUDIES 5.1 O~b'ective The objective of this program is to evaluate the total laboratory analysis process by comparing results for an equivalent sample with those obtained by an independent laboratory or laboratories.
5.2 ~Prc ram 5.2.1 Environmental Sam le Anal ses Com arison Pro ram Environmental samples from the SHNPP environs are to be analyzed by the Harris Energy &.Environmental Center (HE&EC) or by a qualified contracting laboratory. These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the laboratories'erformances in the study will be provided to SHNPP Environmental &
Radiation Control (E&RC) ~ The results will be included in the Annual Radiological Environmental Operating Report (see 'SHNPP Technical Specification 4.12.3) ~
5.2.2 Effluent Release Anal ses Pro ram SHNPP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases. The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study. Radiochemical analyses of composite samples required by Technical Specifications Tables 4.11-1 and 4.11-2 will be performed by the HE&EC.
DCM/ODC-5 5-1 Rev. 3.0
I' c ~
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OS2 5.2.3 Abnormal Results If the CP&L laboratory or vendor laboratory results lie at greater than three standard deviations from the "recognized value," an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete documentation on the evaluation will be available to SHNPP and will be provided to the NRC upon request.
DCM/ODC-5 5-2 Rev. 3.0
4 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190)
Technical Specification 3.11.4 requires that the annual dose or dose commitment to a member of the public from uranium fuel cycle sources be limited to 25 mr'em for the whole body and any organ except the thyroid which is limited to 75 mrem. In addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct radiation, and any other nearby uranium fuel cycle sources are required by Tech-nical Specifications 6.9.1 to show conformance with 40 CFR 190 limits. The results of the dose assessments are to be submitted with the Semiannual Radioactive Effluent Release Report after January 1 of each year.
6.1 Dose to the Likel Most Ex osed Member of the Public 6.1.1 Effluent Pathwa s The ODCM dose equations for noble gases, iodines, particulates, and tritium provide conservative estimates because the X/Q and D/Q are historical values for the exclusion boundary distances.
Because these distances are fixed and represents the closest points in the unrestricted areas to the plant, it assures that 10 CFR 50 Appendix I doses to a member of the public are unlikely to be substantially underestimated.
More realistic estimates of the actual doses from the gas and liquid effluent pathways to the likely most exposed member of the
'public can be obtained by using the Regulatory Guide 1.109- and WASH 1258-based NRC codes LADTAP II and GASPAR. These permit use of current annual average meteorology X/Q and D/Q values derived from the NRC XOQDOQ (NUREG/CR-2919) Code appropriate for the specific location of the receptor and the applicable exposure pathways.
DCM/ODC-6 6-1 Rev. 3.0
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6.1.2 'irect Radiation Radiation exposures of members of the public from direct radiation sources (the 'eactor unit and other primary system components, radwaste, radioactivity in auxiliary systems such as storage tanks, transportation of radioactive material, etc.) will be determined from TLD measurements. Quarterly TLD measurements at locations within three miles of the plant center (inner ring) will be compared with the four-year, pre-operational TLD measurements using methods contained in NBS Handbook 91, "Experimental Statistics," to determine any significant contribution from direct radiation associated with plant operation.
If there is a significant direct radiation component at the TLD location in the sector containing the likely most exposed member of the public then this dose will be added to the doses from effluent pathways derived from LADTAP II and GASPAR.
6.2 Dose to a Member of the Public Due to Activities Within the Site Boundar The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include assess-ments of the radiation doses to members of the public due to activities within the site boundary. The Harris Lake is generally available for public recreational purposes year-round, and certain areas are within the site boundary (Figure 4.1-4).
LADTAP II and GASPAR allow the calculation of doses for special cases. The assumptions used in the calculations, e.g., exposure time, location, and activity, will be included in the Semiannual Radioactive Effluent Release Report.
DCM/ODC-6 6-2 Rev. 3.0
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OS2 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM Pursuant>> to Technical Specification 6.14.2, licensee-initiated changes to the Off-Site Dose Calculation Manual:
- 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made effective. This submittal shall contain'.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental infor-mation. Information submitted should consist of a package of those pages of the ODCM changed with each page numbered, dated, and containing the revision number together with appropriate analyses of evaluations justifying the change(s).
- b. A determination that the change will not reduce the accuracy or reliability of dose calculations or set point determinations.
- c. Documentation of the fact that the change has been reviewed and found acceptable by the PNSC.
- 2. Shall become effective upon review and acceptance by the.
PNSC.
DCM/ODC-7 7-1 Rev. 3.0
5)
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4
OS2 Sheet 1 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CPGL) has performed the assessment of the transport and dispersion of the effluent in the atmosphere as outlined in Pre aration of Radiolo ical Effluent Technical S ecifications for Nuclear Power Plants, NUREG 0133 (USNRC, 1978). The methodology for this assessment. ~ .
was based on guidelines presented in Regulatory Guide 1.111, Revision 1977). The results of the assessment were to provide the relative 1'USNRC, depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.
Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory),
(2) puff-advection model (a variable trajectory model based on the statistical 4
approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight-line method described in X~O ~DO Com uter Pro ram for the Meteorolo ical Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG/CRC-2919 (USNRC, September 1982) would be used for generating the required analyses of Appendix I. To provide a more realistic accounting of the variability of wind around the plant',."site; standard terrain/recirculation correction factors (TCF) were used.
DCM/ODC-AA A-1 Rev. 3.0
4 j
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OS2 Sheet 2 of 3 APPENDIX A (continued)
A twelve-year record of meteorological data was used from the on-site meteorological program at the Shearon Harris Plant. These data consisted of all collected parameters from the normal 10.0 meter tower level for the years 1976-1987. The description of the model used and the computations are presented in NUREG/CRC-2919. The following tables provide the meteorological dilution factors (i.e., the X/Q and D/Q values) utilized to show compliance..
with Technical Specifications 3/4.11.2 for noble gases and radioiodines and particulates.
Tables A-1 through 'A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for special locations for long-term releases'ables A-5 through A-12 "'elative ~undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for standard and segmented distance locations for long-term releases.
Table A-13 SHNPP on-site joint wind frequency distri-butions for 1976-1987.
The X/Q and D/Q values which are utilized in the appendices are all assumed to be ground Level releases.
DCM/ODC-AA A-2 Rev. 3.0
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OS2 Sheet 3 of 3 APPENDIX A (continued)
The NRC "XOQDOQ" Program (Version 2.0) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appro-priate meteorological information for the standard distances, and special locations of interest with a terrain/recirculation factor. The input. to "XOQDOQ" for ground level releases are presented in Table A-14. The resulting computations will have the TCFs applied to produce a final atmospheric diffu-sion estimate for the site.
DCN/ODC-AA A-3 Rev. 3.0
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TABLE A-l THROUGH A-4 I/Q and D/Q Values for Long-Term Ground Level Releases At Special Locations (Sec/H )
USNk~ COMPUTER CODE - XOQOOQ, VERSION 2.0 RUN DaTE: IO/ 13/88 XOQOOQ -- SHNPP GROUND-LEVEL HI STOR ICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA. 1976-1987 CORRECTEO USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST TABLE A-1 TABLE A-2 Table A-3 Table A-4 RELEASE TYPE OF DIRECTION OISTaNCE rla R75 0/ Q Io LOCATION FROM SITE (MILES) (METERS) (SEC/CUB.METER) (SEC/CUB.METER) (SEC/CUB.METER) (PER SQ.METER)
NO 2.300 OAY DECAY 8.000 OAY DECAY DEPLETED DEPLETED DEPLETED A SITE BOUNDARY 5 1.36 2189. 6. IE-06 5.9E-06 5.2E-06 8.8E-09 A SITE BOUNDARY SSW 1.33 2140. 6.0E-OB 5.8E-06 5. 1E-06 8.7E-09 A SITE BOUNDARY SW I . 33 2140. 5.5E-06 5.4E-06 4.7E-06 '7.08-09 A SITE BOUNDARY WSW 1. 33 2140. 4.88-06 4.7E-06 4. IE 06 5.4E-09 A SITE BOUNDARY W 1.33 2140. 3.6E-06 3.6E-06 3. 1E-06 4. 16-09 A SITE BOUNDARY WNW 1.33 2140. 2.8E-06 2.7E-OB 2.4E-06 3.3E-09 A SITE BOUNDARY NW I . 26 2028. 2.9E-06 2.8E-06 2.5E-06 3.9E-09 A SITE BOUNDARY NNW 1. 26 2028. 3.3E-06 3.26-06 2.8E-06 S.IE-OS A SITE BOUNDARY N 1. 32 2124. 3.8E-06 3.8E-06 3.3E-OB 6.6E-09 A SITE BOUNDARY NNE 1. 33 2140. 4.1E-06 4.0E-06 3.5E-06 7.9E-OS A SITE BOUNDARY NE 1. 33 2140. 3.2E-06 3. 2E-06 2.7E-06 7.3E-09 A SITE BOUNDARY ENE 1.33 2140. 2.4E-06 2.4E"06 2. 1E-06 6.3E-09 A SITE BOUNDARY E 1.33 2 'I 40. 2.0E-06 1.9E-06 1.7E-06 3.8E-09 A SITE BOUNDARY ESE 1.33 2140. 1.8E-06 1.7E-06 1.5E-06 4.0E-09 A SITE BOUNDARY SE 1.33 2140. 2. 16-06 2. 1E-06 'I.BE-06 5.1E-09 A SITE BOUNDARY SSE 1. 33 2140. 3.5E-06 3.4E-06 2.9E-06 6.2E"09 A NEAREST RESIDENT SSW 3.90 6275. 7.8E-07 7.3E-07 5.9E-07 6.8E- 10 A NEAREST RESIDENT SW 2.80 )506. 1.3E-06 1.2E-06 1.0E-06 1.2E-09 A NEAREST RESIDENT WSW 4.30 5.4E-07 5.0E-07 4.0E-07 3. 4E-10 NEAREST RESIDENT W 2.70 4345. 9.2E-07 B.BE-07 7.3E-07 7. 3E-10 NEAREST RESIDENT WNW 2. 10 3380. 1. 1E-06 I . 1E-06 9.1E-07 1. 1E-09 NEAREST RESIDENT NW 1.80 2897. I. 4E-06 I. 3E-06 1. IE 06 '1.6E-09 NEAREST RESIDENT NNW 1. 50 2414. 2.2E-06 2.2E-06 1.9E-06 3.3E-09 A NEAREST RESIDENT N 2.20 3540. 1.4E-06 1.3E-06 1. IE-06 1.9E-09 '7Z A NEAREST RESIDENT NNE 1.80 ~ 2897. 2.2E-06 2. 1E-OB 1. BE-06 3.86-09 A NEAREST RESIDENT NE 2.30 3701. 1.0E-06 1. OE-06 8.5E-07 1.9E-09 A NEAREST RESIDENT ENE 3.60 5794. 3.4E-07 3.3E"07 2.66-07 5. 9E-10 A NEAREST RESIDENT E 1.SO 30SZ'. 9.3E-07 9. IE-07 7.7E-07 1.6E-09 A NEAREST RESIDENT ESE 2. 70 4345. 4.3E-07 4. IE-07 3.4E-07 7.3E-10 A NEAREST RESIDENT SE 4. 30 6920. 2.2E-07 2. 1E-07 1.7E-07 3.2E-IO A NEAREST RESIDENT SSE 4.40 7081. 3.6E-07 3.4E-07 2.7E-07 3.7E-10 A GARDEN SSW 3.90 6$ ,76. 7.8E-07 7.3E-07 5.9E-07 6.8E-IO A GARDEN SW 2.80 asbs. 1. 3E 06 1.28-06 I.OE 06 1.2E-09 A GaRDEN WSW 4.30 6920. 5.4E-07 S.OE"07 4.0E"07 3.4E-IO A GARDEN W 3.00 4828. 7.6E-07 7.2E"07 6.0E-07 5.7E-IO A GARDEN WNW 2. 10 3380. 1. IE-06 1.1E-06 9.1E-07 1.1E-09 A GARDEN NW 1. 80 2897. '1.48-06 I. 3E-06 1.1E-06 1.6E-OS A GARDEN NNW 1. 70 2736. 1.7E-06 1.7E"06 I.aE-06 2.4E-09 A GARDEN N 2.20 3540. 1.4E706 1.3E-06 1.'E-06 1.9E"09 A ~ GAROEN NNE 1.70 2736. 2.4E-06 2.4E-06 2.0E-06 4.36-09 A GARDEN NE 2.30 3701. I.OE-06 I.OE-06 8.5E-07 1.9E-09 A GARDEN E I. 90 3058. 9.3E-07 9.1E-07 7.7E-07 1.6E-09 A ~ GARDEN ESE 2.70 4345. 4.3E-07 4.16-07 3.4E-07 7.3E-10 A GARDEN SE 4.30 6920. 2.2E-07 2. IE-07 1.7E-07 3.2F-10 A COW MILK N 2.20 3540. I.aE-06 1.3E-06 I . 16-06 1.9E-09 A COW MILK NNE 4.60 7401. 3.8E-07 3.6E-07 2.8E-07 4. 3E-10 A MEAT & POULTRY SW 2.80 4506. 1.36-06 1.2E-06 I.OE-06 1.2E-09 A MEAT 8. POULTRY WSW 4.30 6920. 5.4E-07 5.0E-07 4.0E-07 3.4E-'10 A MEat & PoULTRY W 3. 10 4989. 7.2E-07 B.BE-07 5.6E-07 5.3E-10 A MEAT 8, POULTRY WNW 2.50 4023. 8. IE-07 7.7E-07 6.4E-07 7.2E-10 a MEAt 8 POULTRV NW 1.80 2897. I . 4E-06 1.36-06 1. 1E-06 1.66-09 A MEAT & POULTRV NNW I. 70 2736. 1. 7E-06 1.7E"06 1. 4E-06 2.4E 09 A MEAT 8, POULTRY N 2.20 3540. 1.4E-06 1.3E-06 I . 1E-OB 1. 91'.-09 A MEAI & POULtRV NNE 1.80 2897. 2.2E-06 2. IE-06 I . BE-OB 3.8L"09 A MEAT & POULTRY NE 2.30 3701. 1.0E-UB I.OE-06 8.5E-07 1.9E-09 MEAT & POULTRY E 1 . 90 3058. 9.3E-07 9.1E-07 7.7E-07 1.66-09 MEAT & POULTRY ESE 4.30 6920. I.SE-07 1.8E-07 1.4E-07 2. SE-10 VE BUILDING PARAMETERS:
LEASE HEIGHT (METERS) 0.00 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 55.0 EXIT vELOCITY (METERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.
A-4
TABLE k.-5 O Undepleted, Mo Decay, X/Q Values Por Long Term Ground Level Releases kt Standard Distances (Sec/m )
~USNRC COMPUTER CODE - XOQDOQ ~ VERSION 2.0 RUN DATE: 10/ 13/88 CI OQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 NO DECAY, UHDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IH MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1. 000 1.500 2.000 2.500 3.000, 3.500 4.000 4.500 S 1.720E-04 5.121E-05 2.53)6-05 1.246E-05 4.943E-06 2.814E-06 1.85IE"06 1.330E-06 1.015E-06 8.0776-07 6.637E-07 SSW 1.571E-04 4.715E-05 2.346E-05 1. 158E-05 4.596E-06 2.6076-06 1.7) IE-06 '1.227E-06 9.34)E-07 7.4246"07 6.093E"07 SW I . 48 I E-04 4.412E-05 2.182E-05 I . 074 E-05 4.263E-06 2,428E-OS 1.597E-06 I. 148E-06 8.757E-al 6.97 16-07 5.7286-07 WSW 1.295E-04 3.842E-05 1.893E-OS 9.308E-06 3.693E-06 2.108E-06 1.389E-06 9,995E-07 7.632E-07 6.080E-07 4.999E-07 W 9.839E-05 2.921E-OS 1.4406-05 7.0876-06 2.814E-06 ).605E-06 ).057E-06 7.608E-07 5.808E-07 4.626E-07 3.803E-07 WNW 7.430E"05 2.2)BE-as I.aSBE-as 5.420E-06 2. 154E-06 1.225E-OS 8.053E-07 5.784E-07 4.409E-07 3.5086-07 2.88 IE-07 NW 6.636E-05 1.996E-05 9.994E-06 4.967E-06 1.982E-06 1.12IE-06 7.339E-07 5.254E-07 3.995E-07 3.1716-07 2.599E-07 HNW 7. 179E-05 2. ISSE-05 1. 1116-05 5.570E-06 2.234E-06 1.254E-OS 8.)66E-07 5.820E-07 4.409E-07 3.489E-07 2.853E-07 N 9.224E-05 2.824E-05 1.448E-OS 7.277E-06 2.9)9E-06 1.633E-06 1.060E-06 7.539E-07 5.70IE-07 4.505E-07 3.678E-07 HNE 9.847E-OS 3.034E-OS 1.560E-OS 7.846E-06 3.'145E-06 1.754E-06 1.137E-06 8.070E-07 6.094E-07 4.810E-07 3.923E-07 NE 7.892E-05 2.430E-05 ).240E-05 6. 194E-06 2.467E-06 1.3766-06 8.9)SE-07 6.333E-07 4.784E-Ol 3.'777E-07 3.081E-07 ENE 5.998E-OS 1.8456-05 9.388E-06 4.679E-06 1.860E-06 1.036E-OS 6.7)IE-07 4.764E-07 3.597E-07 2.839E-07 2.3')6E-07 E 4.903E-05 1.498E-05 7.585E-06 3.779E-06 I.SOBE-06 8.439E-07 5.488E-07 3.908E-07 2.959E-07 2.341E-07 1.913E-07 ESE 4.458E-05 1.36 IE-05 6.872E-06 3. 417E-06 1.359E-06 7.616E-07 4.952E-07 3.527E-07 2.670E-07 2.112E-07 1.726E-07 SE 5.351E-05 ).632E-05 8.2556-06 4.)02E"06 1.629E-06 9.1236-07 5.929E-07 4.2216.-az 3.195E-07 2.526E-07 2.064E-07 SSE 9. IOIE-05 2.734E-05 1.361E-OS 6. 7186-06 2.666E-06 1.509E-06 9.885E-07 7.08)E-07 5.387E-07 4.278E-07 3.509E-07 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 5.589E-07 3.0646-07 2.075E-07 1.263E-07 8.904E-OS 6.799E-OS 5.459E-OS 4.537E-OS 3.8676-08 3.360E"08 2.964E-OB SSw 5. 126E-07 2.798E-07 1.890E-07 1. ) 47E-07 8.066E-OB 6. 149E-08 4.930E-OS 4.093E-OS 3.485E-OB 3.026E-OB 2 '67F-08 Sw 4.824E-07 2.645E-07 1.79)E-07 ).090E-07 7.686E-OS 5.869E-OS 4.7126-08 3.916E-OB 3.338E-OB 2.9aaE-aB 2.558E-OB WSW 4.2)3E-07 2. 3 I SE-07 1.570E-07 9.574E-OS 6.758E-DS 5. 165E-08 4. 150E-08 3.45 IE-08 2.9436-08 2.558E-OB 2.257E-OB W 3. 205E-07 1.760E-07 1. 193E-07 7.275E-OS 5. 133E-08 3.922E-DB 3. ISIE-08 2.620E-OS 2.234E-OS 1.941E-OS I. 713E-08 WNW 2.426E-07 1.328E-07 8.985E-OS 5.463E"08 3.849E-OB 2. 93l6-08 2.3576-08 1.95SE-OS 1.668E-OS '1.449E-OS 1.278E-OS NW 2.)85E-07 1. IBBE-07 8.005E-OS 4.839E-OS 3.396E-OB 2.5846"08 2.069E-OB 1.716E-OB 1.460E-OS 1.266E-OS 1.'IISE"08 HNW 2.392E-07 1.290E-07 8.639E-OS 5. 181E-08 3.6)7E-OS 2.74 IE"08 2. 187E-08 1.809E"08 I.535E-OB ).3296-08 1. 168E-08 N 3. 08 IE-07 1.654E-07 1. IOSE-07 6.6D3E-OB 4.597E-OB 3.478E-OB 2. 771E-08 2.289E-OB 1.940E-OB ).678E-08 1.474E-OB NNE 3.283E-07 ).758E-07 ).)7 IE-07 6.980E-OB 4.8526'-08 3.'ssss.-as 2.9 I BE-08 2.408E-OB 2.040E-OB 1.763E-OS 1.548E-OB NE 2.579E-07 1.383E-07 9.230E-OB 5.512E-OB 3.839E-OS 2.904E-OB 2. 315E-08 1.9)2E-OB 1.622E-OB 1.403E-OB 1.232E-OB EHE ).938E-07 1.039E-07 6.93SE-OB 4. 142E-08 2.886E-OB 2.184E-OS 1. 741E-08 I:439E-08 1.2206-08 ).056E-OB 9.278E-09 6 1.6046 07 8.645E-OB 5.789E-OS 3.473E-OS 2.426E-OB 1.840E-OB 1.469E-OS 'I . 215E" 08 1.032E-OB 8.935E-09 7.858E-09 ESE I . 447E-07 7.804E-OB 5.228E-OB 3.139E-OB 2. 193E-08 1.664E-OS 1.3296-08 1. IOOE-08 9. 341E-09 8. 091E" 09 7. 117E-09 SE 1.730E-07 9.328E-OS 6.248E-OB 3.750E-OS 2.620E-OB ).988E-OB I.SSSE-OB I . 314E-08 ). I'I6E-08 9.6656-09 8.50)E-09 SSE 2.9506-07 1.608E"07 1.085E-07 6.575E-OB 4.622E-OB 3.522E-OB 2.823E-OS 2.343E-OS 1.995E-OB ).732E-OB 1.526E-OB MENT AHD BUILDING PARAMETERS:
RELEASE HEIGHT (METERS) 0.00 REP. WIND HEIGHT (METERS) 10. 0 DIAMETER (METERS) 0.00 BUILDING HEIGHT 'METERS) 55.0 EXIT VEI.DC)TV (MEIERS) a.aa BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EMISSION RATE (CAL/SEC) 0.0 O
ALL GROUND LEVEL RELEASES.
TABLE h-6 O
aO Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases ht Standard Distances (Sec/m3)
I 0 USNRC COMPUTER CODE - XOQDOQ. VERSION 2.0 RUN DATE: 09/O'I/88 XOQDDQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976- 1987 EXIT ONE -" GROUND-LEVEL HISTORICAL DATA, 1976-1987 NO DECAYS UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 2.535E-OS 5.667E-06 1.900E-06 1.0265-06 6.676E-07 3. 185E-07 1.278E-07 6.824E-OB 4.545E-OB 3.363E-OB SSW 2.344E-05 5.264E-OS 1.756E-06 9.447E-07 6. 129E-07 2.9125-07 I. 161E-07 6. 172E-08 4. IOIE-08 3.029E-OB Sw 2. 185E-05 4.887E-06 1.639E-06 8.855E-07 5.761E-07 2.749E-07 1. 103E-07 5.891E-OS 3.923E-OS 2.903E-OB wSw 1.899E-05 4.2365-06 1.425E-06 7.715E-07 5.028E-07 2.405E-07 9.683E 08 5. 184E-08 3.457E-OB 2.560E-OB w 1.444E-05 3.226E-06 1.085E-06 5.872E"07 3.826E-07 1.829E-07 7.358E-OS 3.937E-OS 2.624E-OS 1.943E-OB WNW 1.099E-05 2.467E-06 8.265E-07 4.459E-07 2.898E-07 I . 381E" 07 5.528E-OB 2.948E-OS 1.962E-OS 'I.451E-OB NW 9.975E-06 2.263E-06 7.538E-07 4.04 IE-07 2.615E-07 1.237E-07 4.902E-OB 2.595E-OB 1. 719E-08 1.267E"08 NNW 1. 103E-05 2.540E-06 8.395E-07 4.462E-07 2.87 IE-07 1.345E-07 5.254E-OB 2.753E-OS 1. 813E-08 1.330E-OB N 1.434E-05 3.316E-06 1.090E-06 5. 77 IE-07 3.702E-07 1.727E"07 6.700E-OB 3.494E-OS 2.294E-OS 1.680E"08 NNE 1.543E-05 3.572E-06 1. 169E-06 6. 169E-07 3.949E-07 1.836E-07 7.086E-OB 3.682E-OB 2. 413 E-OS 1.765E-OB o IIE 1.229E-05 2.8'IIE-06 9. 176E-07 4.843E-07 3. 102E-07 1.445E-07 5.595E-OB 2.9IBE-OB 1.917E-OB 1.404E-OB ENE 9.309E-06 2. 120E-06 6.906E-D7 3.642E-07 2.331E-07 1.085E-07 4.204E-OB 2. 194E-08 1.4426-08 '1.057E-OS E 7.536E-06 1.717E-OS 5.643E-07 2.995E-07 1.925E-07 9.019E-OB 3.523E-OB 1.848E-OB 1. 218E-08 8.946E-09 ESE 6.833E-06 I . 551E-06 5.092E-07 2.702E-07 1.737E-07 8. 141E-08 3. 183E-08 1.671E-DB 1.'I02E-08 8. I DIE-09 SE 8.202E-06 1.860E-06 6.097E-07 3.233E-07 2.078E-07 9.732E-OB 3.803E-OS 1.996E-OB 1.317E-OB 9.676E-09 SSE 1.360E-05 3.052E-06 I . 015E-06 5.449E-07 3.530E-07 1.674E-07 6.657E-OB 3.536E-OB 2.348E-OS 1.733E-OB
C) n Table h-7 O
Undepleted, 2.26 Day Decay, X/Q Values for Long-Tera Ground Level Releases at Standard Distances (Sec/a )
CUSNRC COMPUTER CODE - XOQDOQ VERSION 2.0 RUN DATE: 10/13/88 nI ~
XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, )976- 1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 2.30O OAY DECAY, UNOEPLETED CORRECTEO USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROIA THE SITE SECTOR 0.250 0.500 0.750'.000 1.500 2.000 2.500 3.000 3. 500 4. 000 4. 500 S 1.7)26-04 5.078E"05 2.500E-OS '1.226E-OS 4.824E-06 2.723E-06 1.776E-06 1.266E-06 9.57 IE-07 7.553E-07 6. 153E-07 SSW 1.5646-04 4.675E-OS 2.318E-05 1.'139E-05 4.489E-06 2.525E-OB 1.643E-06 1.168E-06 8.820E-07 6. 95)E-07 5.657E-07 SW 1.4746-04 4.374E-OS 2. 154E-05 1.056E-05 4. 158E-06 2.347E-OB 1.531E 06 1.091E-06 8.2476-07 6.508E-07 5.301E-07 WSW 1.2896-04 3.BOSE-05 1. 869E-05 9. 149E" 06 3.600E-06 2.036E-06 1.330E-06 9.484E-07 7. 1776-07 5.667E-07 4. 619 E-07 W 9.7946-05 2.895E-05 1.422E-OS 6.966E-06 2.7436-06 ) .551E-06 1.013E-06 7.221E-07 5.464E-07 4. 314E-07 3. 515E-07 WNW 7.398E-05 2. 197E-05 1.085E-OS 5.331E-06 2.102E-06 I . 185E-OS 7.723E-07 5.499E-07 4. 1566-07 3.278E-07 2. 669 E-0 I NW 6.6096-05 1.980E-05 9.879E-06 4.892E-06 ).938E-06 1.087E-06 7.060E-07 5.014E-07 3.782E-07 2.978E-07 2.42IE-07 NNW 7. 152E-05 2. 170E-05 1.099E-OS 5.495E-06 2. 189E-06 1.220E-06 7.887E-07 5.58'IE-0'7 4. 1976-07 3.297E-07 2.676E-07 N 9. 1916-05 2.805E-OS 1.434E-OS 7. 184E-06 2.864E-06 1.591E-06 1.026E-06 7.247E-07 5.442E-07 4.270E-07 3.463E-07 NNE 9. 8 14F.-05 3. 014E-05 1.546E-OS 7.7516-06 3.0886-06 I . 712E-06 I.'102E 06 7.770E-07 5.829E-07 4.570E"07 3.703E-07 NE 7.8656-05 2. 414E-05 1.228E-OS 6. 117E-06 2.422E-06 1.342F-06 8.635E-07 6.091E-07 4.5696-07 3.582E-07 2.902E-07 ENE 5.978E-05 I . 833E-05 9.300E-06 4.62IE-.06 ).825E-06 1.0)IE-06 6.499E-07 4.582E-07 3.436E-07 2.693E-07 2. 182E" 07 I E 4.885E-05 I . 487E-05 7.507E-06 3.729E-06 1.476E-06 8.2126-07 5.301E-07 3.748E-07 2.8176-07 2. 212E "07 1.794E-07 ESE 4. 44 16-05 1.35)E-OS 6. 80 I E-06 3.372E-06 1.332E-06 7.411E"07 4.783E-07 3.382E-07 2. 5416-07 1.996E-07 1.6)9E-07 SE 5.331E-05 I . 621E-05 8. 172E-06 4.047E-OB 1.5976-06 8.8796-07 5.728E 07 4.048E-07 3.042E-07 2.388E-07 1.937E-07 SSE 9.063E-05 2.7 12E-05 1.345E-05 6.616E"06 2.6066"06 1.463E-06 9.505E-07 6 '53E-07 5.0956-07 4.014E-07 3.265E-07 ANNUAL AVFRAGE CHI/O (SEC/METER CUBED) 0 I STANCE I N MILES FROM THE S I TE SECTOR 5.000 7.500 10.000 '15. 000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 5. 138E-07 2.700E-07 1.755E"07 9.871E 08 6.459E-OB 4.597E-OS 3.454E-OB 2.697E-OB 2. 167E-08 I . 78)E-08 1.490E-OS SSW 4.719E-07 2.472E"07 1.603E-07 8.9906-08 5.87'IE-08 4.')726-08 3. 131E-08 2.442E-OB 1.960E-OB 1.609E-OB ).345E-08 Sw 4.426E-07 2.324E-07 1.509E-07 B.a726.-08 5.532E-OB 3.9296-08 2.946E"08 2.296E-OB 'I .841E-08 1.5'IOE-08 I . 261E-08 WSW 3.858E-07 2.029E-07 1.3)BE-07 7.405E"08 4.835E-OS 3.4336-08 2.574E-OS 2.005E-OB 1.607E-OS 1. 317E" 08 I . 'I OOE-08 W 2.936E"07 1.544E-07 ).0036-07 5.633E-OB 3.678E-OS 2.612E-OS 1.958E-OB ).525E-08 1.223E-OB 1.003E-OB 8.3706-09 WNW 2.228E-07 I. 169E-07 7.589E-OB 4.259E 08 2.782E-OS 1.976E-OB 1.482E-OS 1. 155E-08 9.267E-09 7.602E"09 6.350E-09 NW 2.0 19E-07 1.055E-07 6.837E-OB 3.834E-OS 2.505E-OS 1.7826-08 1.339E-OB ).045E-08 8.394E-09 6.896E-09 5.768E-OB NNW 2.228E-07 1.159E-07 7.490E-OB 4. 194E-08 2.7a2E-OB 1.9536-08 '1.470E 08 1. 150E-08 9.252E-09 7. 614E-09 6.3"IBE-09 N 2.880E-07 1.495E-07 9.650E-OB 5. 40 IE-08 3.534E-OS 2.520E-OS 1.898E-OB I . 486 E-08 I . 198E-08 9.868E-09 8.276E-09 NNE 3.078E-07 1.594E-07 1.028E-07 5.753E-OB 3.766E-OB 2.6876-08 2.026E-OB 1.5886-08 1.281E-OB 1.057E-OB 8.8726-09 NE 2.4 13E-07 1.250E-07 8.065E-OB 4.512E"08 2.953E-OS 2. 106E-08 1.588E-OB 1.2446-08 1.003E-OS 8.276E-09 6.949E-09 ENE 1.814E;07 9.395E-OS 6.060E-OS 3.39 IE-08 2.220E-OB 1.585E-OS 1. 195E-08 9.369E-09 7.561E-09 6.239E-09 S. 24 I E-09 E 1.493E-07 7.761E-OB 5. 014E-08 2.807E-OB 1.836E-OS 1.3086-08 9.847E-OB 7.705E-OB 6.205E-09 5. 110E-09 4.284E-09 ESE 1.347E-07 7.005E-OB 4.527E-OB 2.535E-OB ).659E-08 ) . 183E-08 8.908E-09 6.974E-09 5.619E-09 4.630E-09 3.884E-09 SE 1.612E-07 8.378E-OB 5. 414E-08 3.033E-OS 1.985E-OS 1.4)66-08 1.067E-OB 8.353E-09 6.732E-09 5.549E-09 4.657E-09 SSE 2.723E-07 1.425E-07 9.243E-OB 5.189E-OB 3.394E-OB 2. 416E-08 I . 816E-08 1.4'ISE-08 I ..)40E-08 9.378E-09 7.851E-09 VENT AND BUILDING PARAMETERS:
~ RELEASE HEIGHT (METERS) 0.00 REP. WIND HEIGHT (METERS) '10.0 DIAMETER (METERS) 0.00 8UILDING HEIGHT (METERS) 55.0 EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2')61.0 ED HEAT EMISSION RATE ~ (CAL/SEC) 0.0 ALL GROUND. LEVEL RELEASES.
Cj Table h-8 Undepleted, 2.26 Day Decay, X/Q Values for Long-Term Ground Level Releases at Standard Distances (Sec/m )
cjUSNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 10/13/88 I
XOQDOO -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1876-1987 2.300 DAY DECAY, UNDEPLETED CHI/O (SEC/METER CUBED) FOR EACH SEGMENT SEGMEHT BOUNDARIES IH MILES FROM THE SITE DIRECTION . 5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE S 2.506E-05 5.542E"06 '1.825E-06 9.683E-07 6. 192E-07 2.822E-07 1.006E-07 4.636E-OS 2. 711E-08 1.787E"08 SSW 2. 318E-05 5. 151E-06 1.688E-OS 8.926E-07 5.693E"07 2.585E-07 9. 168E-08 4.209E-OS 2.455E-OB 1.615E-OB SW 2. 159E-05 4.776E-06 1.572E-06 8.345E-07 5.334E-07 2.429E-07 8. 636E-08 3.964E-OB 2.309E"08 I . 516E-08 WSW 1.876E-05 4.138E-06 1.366E-OB 7.261E-07 4.647E-07 2. 119E-07 7.547E-OB 3.463E-OB 2.016E-OB 1.323E-OB W 1.427E-OS 3. 152E 06 1.040E-OS 5.528E-07 3.537E-07 I . 613E-07 5.74'IE-08 2.635E-OB 1.534E-OS 1.006E-OB WNW I . 061E-05 2. 412E-06 7.934E-07 4.205E-07 2.686E-07 I . 222E-07 4.343E-OB 1.994E-OB 1.162E-OB 7.632E"09 NW 9.867E"06 2.216E-06 7.259E-07 3.827E-07 2.437E-07 1. 104E 07 3.911E-OB 1.798E-OS I . 051E-08 6.922E-09 NHW '1.093E-05 2 .493E-06 8. 116E-07 4.250E-07 2.694E-07 1. 214E-07 4. 281E-08 1.970E-OB I . 156E-08 7. 64 IE-09 N 1.421E-05 3.258E-06 1.056E-06 5. 51 IE-07 3.486E"07 1.567E-07 5. 515E-08 2.54 IE-08 1.494E-OB 9.903E-09 NHE 1.530E"05 3. 513E-06 1. 134E-06 5.904E-07 3.728E-07. 1.672E-07 5.877E-OB 2.7'IOE-08 1.596E-OS 1.060E-OB NE I . 218E-05 2.763E-06 8.893E-07 4.628E-07 2.923E-07 1.3'IIE-07 4.608E-OS 2. 125E-08 1. 25 IE-08 8.305E-09 ENE 9.227E-06 2.084E-06 6.694E-07 3.480E-07 2. 197E-07 9.855E-OB 3.464E-OB 1.598E-OS 9. 418 E-09 6.261E-09 E 7.464E-06 1.685E-06 5.456E-07 2. 852E-01 '1.806E-07 8. 134E-08 2.866E-OB 1. 319E-08 7.746E-09 5. 129E 09 ESE 6.768E-06 1.523E-06 4.923E-07 2.574E-07 1.630E-07 7. 34 I E-08 2.588E-OB I . 193E-08 7.010E-09 4.647E"09 SE 8.124E-06 1.826E-06 5.897E-07 3.080E-D7 1.950E-07 8. 781E-08 3.096E-OS 1.428E-OB 8.396E-09 5.569E-09 SSE 1.345E-OQ 2.989E-06 9.77 IE-07 5. 157E-07 3.286E-07 1. 491E-07 5.292E-OS 2.437E-OB 1.426E-OB 9.413E-09
0 O
O Table h-9 K
o Depleted, 8.0 Day Decay, I/Q Values for Long-Teri Ground Level Releases at Standard Distances (Sec/m~)
QSNRC COMPUTER CUUh - XUUUUU, VERSION 2.0 RUH DATE: IO/ )3/BII XOQOOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 8.000 OAY DECAYS DEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IH MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 1.625E-04 4.665E-OS 2.247E-05 1.085E-05 4. 169E"06 2.308E-06 1.482E-06 1.042E-06 7.784E-OZ 6.080E 07 4.908E-OZ SSW '1.485E-04 4.295E-OS 2.083E-05 1.009E-OS 3.877E-06 2. 139E-06 1.369E-06 9.606E-07 7. 168E-07 5.590E-OZ 4.507E-07 SW 1.400E-04 4.019E-05 1.937E-OS 9.357E-06 3.594E-OB I . 991E-06 1.278E-06 8.984E-07 6.715E-OZ 5.244E 07 4.233E-07 W S'W 1.224F-04 3.499E-05 1.681E-05 8. 107E-06 3. 113E-06 1.728E"06 1.111E-06 7.8IBE-07 5.849E-07 4.572E-07 3.693E-07 W 9.3006-05 2.660E-05 1.279E-05 6. 173E-06 2.372E-OB 1. 316E-06 8.458E-OZ 5.952E-07 4.452E-07 3.479E-OZ 2.810E-OZ WNW 7.023E-OS 2.018E-05 9.753E-OB 4.72IE-06 I . 816E-06 1.005E"06 6.444E-07 4.527E-07 3.382E-07 2.640E-07 2. 130E" 07 NW 6. 273E-05 1.819E-OS 8.876E-OB 4.329E-06 1.672E-06 9.202E-07 5.878E-OZ 4. 117E-07 3.068E-OZ 2.aeOE-OZ ).925E-OZ NHW 6.787E-05 1.991E-OS 9.8718-06 4.857E-06 1.886E-06 1.030E-06 6.548E-07 4.567E-07 3.391E-07 2.635E-07 2.'117E-07 H 8.72IE-OS 2.574E"05 1.287E-OS 6.346E-06 2.465E-06 1.342E-06 8.505E-OZ 5.920E-OZ 4.389E-OZ 3.404E-OZ 2.732E-07 NNE 9.311E-05 2.765E-05 1.387E-05 6.844E-06 2.657E-06 1.442E-06 9. 123E-07 6.339E"07 4.694E-07 3.637E-07 2.916E-07 HE 7.462E"05 2.215E-05 I . 102E-05 5.403E-OB 2.084E-06 1. 13'IE"06 7. 156E-07 4.974E-OZ 3.683E-07 2.855E-07 2.289E-07 ENE 5.67'IE-05 1.682E-05 8.343E-06 4. 08 I E-06 I . 571E" 06 8.5 I9E-07 5.385E-07 3.741E-07 2.770E-07 2. 146E-07 1.72IE-07 I E 4.6asE-os l.'aesE-os 6.739E-06 3.295E-06 I . 27 IE-06 6.933E-OZ 4.40)E-OZ 3.067E-OZ 2.276E-07 1.767E"07 I . 419E-07 ESE 4.2'I4E-05 1.240E-OS 6. 105E-06 2.980E-06 I . ')47E-06 6.256E-OZ 3.97 IE-07 2.767E-OZ 2.054E-OZ 1.595E 07 I . 281E-07 SE 5.058E-05 1.4876-05 7.335E-06 3.576E-06 '1.376E-06 7.495E-07 4.755E-07 3.312E-07 2.457E-OZ 1.908E"07 1.532E-07 SSE 8.603E-05 2.49 IE-05 ).209E-05 5.855E-06 2.249E-06 '1.238E-06 7.917E-07 5.547E-07 4.136E-07 3.223E-07 2.597E-OZ ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) 'ISTANCE IH MILES FROM THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 4.064E-OZ 2.080E-07 1.325E-07 7.280E-OB 4.700E"08 3.317E-OB 2.477E-OB 1.924E-OB 1.538E-OB 1.257E-OB 1.045E-OB SSW 3.729E-OZ 1.901E-OZ 1.208E-OZ 6.616E-OB 4.263E-OB 3.004E-OB 2.240E-OB 1.738E-OB 1.388E-OB 1. 134F-08 9.424E-09 SW 3.506E-OZ 1.794E-07 1. 143E-07 6.274E-OB 4.049E-OB 2.856E"08 2. 13 IE"08 1. 654E-08 1.322E-OB 1.079E-OB 8.973E-09 WSW 3.060E-07 1.569E-OZ 1. 00 I E-07 5.502E-OB 3.554E-OB 2.508E-OB 1.872E-OB 1.453E-OB 1. 161E-08 9.487E-09 7.887E-09 W 2.328E-OZ I. 193E-07 7.809E-OB 4. 182E-08 2.701E-OB 1.906E-OB 1.422E-OB 1. 104E-08 8.823E-09 7.207E-09 5.99 IE-09 WNW 1.764E-OZ 9.0')4E-08 5.738E-OB 3. 147E-08 2.030E-OB 1.431E-OB 1.068E-OB 8.289E-09 6.622E-09 5.409E-09 4.4966-09 NW 1.591E-07 8.086E-OB 5. 129E-OB 2.801E-OB ).803E-OB 1.269E-OB 9.462E-09 7.339E-09 5.861E-09 4.787E-09 3.979E-09 NNW = I . /46E-07 B.BOBE-OB 5.560E-OB 3. 019E-08 1.936E-OB 1.360E-OB 1.013E-OB 7.848E-09 6.264E-09 5. 1)SE-09 4.2SIE-09 H 2. 25 IE-07 I . 132E-07 7. 127E-08 3.859E-OB 2.47 IE-08 1.735E-OB 'I.291E-OB I.OOOE-OB 7. 981E-09 6.516E-09 5.417E-09 NNE 2.401E-OZ 1.204E-07 7.567E-OB 4.089E-OB 2. 616E-08 1.835E-OB 1.365E-OB 1.057E-OB 8.437E-09 6.888E-09 5.726E-09 NE 1.885E-OZ 9.461E-OB 5.954E-OB 3.222E-OB 2.063E-OB 1.449E-OB 1.078E-OB 8.353E-09 6.668E-09 5.445E-09 4.527E-09 EHE ).4)ZE-OZ 7.'109E-08 4.473E-OB 2.421E-OB I . 551E-08 1.089E-OB 8. 109E-09 6.285E-09 5. 0 I BE-09 4.099E-09 3.409E-09 E I. 171E-07 5.902E 08 3.724E-OB 2.023E-OB 'I.298E-OB 9. 120E-09 6.79 IE-09 5.264E-09 4.203E-09 3.432E-09 2.853E-09 ESE 1.056E-07 5.327E-OB 3.363E-OB 1.827E-OB I.'173E-08 8.246E-09 6. 143E-09 4.763E 09 3.803E-09 3. 107E-09 2.583E-09 SE 1. 263E-07 6. 369E-08 4.020E-OB 2. 184 E-08 1.402E"08 9.856E"09 7.343E-09 5.694E-09 4.547E-09 3. 714E-09 3.089E-09 SSE 2. )48E-07 1.094E"07 6.946E-OB 3.801E-OB 2.449E-OB 1.726E-OB 1.288E-OB 9.994E-09 7.985E-09 6.524E-09 5.425E-09 CLIENT AHD BUILD)NG PARAMETERS:
RELEASE HEIGHT (METERS) 0.00 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 55.0 EXIT VELOCITY (METERS) 0.00 BLDG.MIH.CRS.SEC.AREA (SQ.METERS) 2')61.0 HEAT EMISSION RATE 'CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.
0 CI Table k-10 Depleted, 8.0 Day Decay, Y/Q Values for Long-Term Cround Level Releases at Standard Distances (Sec/m )
O CIUSNRC COMPUTER CODE - XOOOOQ. VERSION 2.0 RUN DATE: 10/13/88 I
XOOOOO -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL H1STORICAL DATA, 1976-1987 8.000 DAY DECAY, DEPLETED CHI/O (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE S1TE D1RECT10N .5-'I 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40 50 FROM SITE S 2.268E-OS 4.827E-06 I . 526E-06 7.887E-07 4.943E-07 2. 186E-07 7.461E-OB 3.350E-OB 1.935E-OB 1.262E-OB SSW 2.097E-05 4.485E-OS 1. 4115-06 7.263E-07 4.540E-07 I . 999E-07 6.785E 08 3.034E-OS 1.748E-OB 1.'138E-08 SW 1.955E-05 4. 162E-OB 1. 316E-06 6.803E-07 4.264E"07 1.885E-07 6.430E-OS 2.884E-OB 1.664E-OS 1.084E"08 WSW 1.69BE-05 3.607E-06 I . 144E-06 5.925E-07 3. 7 19E-07 1.648E-07 5.637E-OS 2.532E-OB 1.462E-OB 9.524E-OB W 1.292E-05 2.747E-06 8.710E-07 4. 510E-07 2.830E-07 1.253E-07 4.285E"08 1.924E-OB 1.111E-OB 7.236E-09 WNW 9.835E-06 2. IOIE-06 6.638E-07 3.426E-07 2. 145E-07 9.474E-OB 3.226E-OS 1.446E-OB 8.338E-09 5.430E-09 NW 8.924E-06 1.928E"06 6.060E-07 3. 109E"07 1.939E-07 8. 510E-08 2.875E-OS 1.2826-08 7.383E-09 4.806E-09 NNW 9.874E-06 2. 166E-06 6.757E-07 3.439E-07 2. 133E-07 9.287E-OB 3.'102E 08 1.375E-OB 7.896E-09 5. 136E-09 N 1.283E-OS 2.828E-06 8.782E-07 4.451E-07 2.753E-07 1. 194E-07 3.969E-OB 1.754E-OB 1.006E-OB 6.543E-09 NNE 1.38'IE-05 3.048E-06 9.423E-07 4.761E"07 2.939E-07 I . 271E-07 4.207E-OS 1.855E-OB 1.064E-OB 6. 9 17 E-09 NE 1.100E-05 2.398E"06 7.3925-07 3.736E-07 2.307E-07 9.990E-OS 3.314E-OB 1.464E-OB 8.404E-09 5.467E-09 ENE 8.332E-06 1.809E-06 5.563E-07 2. 8 IOE-07 1.734E-07 7.506E-OB 2. 491E-08 1. I 0 IE-08 6.323E-09 4. 115E-09 I
E 6.744E-06 1.464E-06 4.542E-07 2.308E-07 1.430E-07 6.224E-OB 2.079E 08 9. 217E-09 5.296E-09 3.446E-09 ESE 6. IISE-06 1.323E-06 4.099E-07 2.083E-07 1.291E-07 5.618E-OB 1.878E-OB 8.333E-09 4. 79 I E-09 3. 119E-09 O SE 7.340E-06 1.586E-06 4.908E-07 2.492E-07 1.544E-07 6.717E-OB 2.244E-OS 9.960E-09 5.728E-09 3.730E-09 SSE 1.217E-05 2.601E"06 8. 160E-07 4. 191E-07 2.616E-07 1. 15 IE-07 3.899E-OB 1.743E-OB 1.005E-.OB 6.550E-09
TABLE A-11 n
x O
C$ Deposition Values (D/Q) For Long Term Releases At Standard Distances (m )
USNRC COMPUTER CODE XOQOOQ, VERS)ON 2.0 RUN DATE: )0/ 13/88 XOQOOQ - SNNPP GROUND-LEVEL H)STORICAL DATA, 1976- 1987 FX)T'NE -- GROUND-LEVEL H)STOR)CAL DATA, )976- 1987 CORRECTED US)NG STANDARD. OPEN TERRA)N FACTORS
~ oe ~ ~ ~ o ~ ~ e ~ ~ 4to ~ ~ ~ ~ ~ 0 RFI.ATIVE DEPOSITION PER UN)T AREA (M~'-2) AT FIXED Po)NTS BY OOWNW)ND SECTORS ~ IO ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~0 ~ ~ ~
0)RECT)ON D)STANCES IN M)LES FROM S)TE 0.25 0.50 0.75 I 00
~ 1.50 2.00 2.50 3.00 3.50 4.00 4.50 5 2.324E-07 7.85?E-OB 4.034E-OB 1.918E-OB 6.889E-09 3.417E-O9 2.012E-09 1.3)7E-09 9.269E-IO 6.869E-IO 5.294E-IO SSW 2. 17 )E-07 7.343E-OB $ .7?OE-OB 1.792E-OB 6.438E-OB 3. 193E-09 1.880E-09 1.23IE-09 8.662E-)0 6.420E-IO 4.947E-IO SW 1.740E-O? 5.885E-OB 3.022E-OB 1.437E-OB 5. 160E-09 2.559E-09 ).507E-09 9.866E-IO 6.942E-IO 5. 145E-10 3.965E-IO WSW 1.355E-O? 4.582E-OB 2.353E-OB ). I'19E-OB 4.0IBE-09 1.993E-09 1.173E-09 7.682E-IO 5.406E-IO 4.006E-)0 3.08?E-IO W 1.013E-O? 3.427E-OB 1.759E-OB 8.365E-09 3.005E-09 1.490E-09 8.774E- Io 5.745E-IO 4.042E-)0 2.996E- 10 2.3095-10 WN'W 8.296E-OB 2.805E-OB 1.440E-OB 6.848E-09 2.460E-09 1.220E-09 7. 183E-IO 4.703E- Io 3.309E- 10 2.453E-)0 1.890E- 10 NW 8.468E-OB 2.864E-OB 1.4?OE-OB 6.990E"09 2.511E-09 1.245E-09 7.332E-IO 4.80IE-IO 3.378E- Io 2.503E-IO 1.9296-10 NNW 1.)OSE-O? 3.736E-OB 1.918E-OB 9.120E-09 3.276E-09 ).625E-09 9.566E-IO 6.264E-)0 4.408E-IO 3.266E-)0 2.5)?E-IO N 1.626E-07 5.499E-OB 2.823E-OB 1 342E-08 4.821E-09 2.39IE-09 1.408E-09 9.2IBE-IO 6.487E-'Io 4.807E- 10 3.705E- 10 NNE ).985E-07 6.713E-OB 3.44?E-OB 1.639E-OB 5.886E"09 2.919E-09 I . 719E-09 I. ) 256-09 7.919E-IO 5.869E- 10 4.522E-IO NE I.BISE-07 6.137E-OB 3.15'IE-08 1.498E-OB 5.38'IE-09 2.669E-09 1.57 IE-09 1.029E-09 7.240E- 10 5.366E-IO 4.)35E-IO EHE 1.568E-O? 5.302E-OB 2.723E-OB '1.294E-OB 4.649E-09 2.306E-09 1.358E-09 8.890E-IO 6.255E- 10 4.636E- 10 3.572E" 10 ESE f 9.5956-08 3.245E-OB 1.666E-OB 7.920E-09 2.845E-OB 1.411E-OB 8.307E-IO 1.003E-07 3.393E-OB 1.742E-OB 8.281E-09 2.975E"09 1.475E-09 8.686E-IO 5.439E-IO 5.688E-IO 3.827E- 10 4.002E-IO 2.83?E-IO 2.966E"'Io 2.186f-lo 2.286E-IO SE 1.270E-O? 4.294E-OB 2.205E-OB '1.048E-OB 3.765E-09 ).867E-09 1.099E-09 7.199E-IO 5.066E- Io 3.754E-)0 2.893E-)0 SSE 1.5486-07 5.236E-OB 2.6BBE-OB 1.278E-OB 4.591E-09 2.277E-09 1.34)E-09 8.778E- Io 6. 177E-10 4.578E-IO 3.528E- 10 O)RECT)ON DISTANCES )N M)LES FROM S)TE s.oo ?.50 10.00 ls. 00 20.00 25. 00 30.00 35.00 40. 00 4s.oo so.oo S 4.205E-IO I . 868E- I 0 1. 132E- \0 5.720E-II 3.462E-)I 2. 32)E- I I 1.663E-I) 1.249E-I) 9.71)E-)2 7. 757E- 12 6.332E- 12 SSW 3.930E-IO 1. 746E-10 1.058E-)0 5.346E-II 3.235E-I) 2. 169E-11 1.554E-) I ) . 167E" I I 9.075E-)2 7. 249E-12 5.91?E-12 SW 3. 150E- Io 1. 399E- )0 8.476E-II 4.284E-I) 2.593E-II '1.739E-'ll 1.246E-)1 9.354E-)2 7.273E-')2 5.810E-12 4.742E-)2 WSW 2.453E- IO 1.090E- 10 6.600E-II 3.336E-II 2. 019E-I ) 1.354E-I) 9.700E-)2 7.284E-12 5. 663E-12 4.524E-12 3.692E-12 W 1. 834 E- I 0 8. 148E- I I 4.935E-II 2.495E-II 1.510E-'I 'I 1.012E-I I 7.254E-12 5.447E-)2 4.235E-)2 3.383E-)2 2.761E-12 WNW I . 501E-10 6.6?OE-) I 4 . 040E- 11 2.042E-'I) 1. 236E-11 8. 2$ ?E-12 5.938E-)2 4.459E- 12 3.467E-)2 2.769E-I2 2.26IE-I2 NW I . 533E-10 6.808E-2.000E-)0 8.884E- 11 ll 4. 124E-11 2.085E- 11 1. 262E-11 8.459E-12 5.381E-I I 2.720E-II 1. 646E-11 1. 104E-11 6.062E-12 4.552E- 12 3.539E- 12 7.909E-12 5.939E-)2 4. 6 I BE-12 2.8276-12 2.307E-12 3.689E-)2 3.01)E-IR NNW N 2.943E- IO 1.307E-)0 7.920E- I 'I 4.003F.-)l 2. 423E-11 I . 624E- I ) 'I . 164E-)1 8.740E-)2 6.796E-)2 5.428E-12 4.43)E-12 NNE 3. 593E- Io 1.596E- 10 9.668E-) I 4.887E-II 2. 958E- I 'I 1.983E-11 1.42)E-)1 1.06?E-II 8.296E-)2 6.627E-12 5.409E-12 NE 3.285E-)0 I . 459E- 10 8.839E-)) 4.468E-II 2.704E-II 1. 813E-11 1.299E-II 9.755E-12 7.585E-I2 6.059E-12 4.946E- 12 ENE 2.838E-IO I . 26)E-10 ?.637E-11 3.860E-I) 2.336E-)l 1. 566E-11 I . 122E-11 8.428E- 12 6.553E-)2 5.235E-I2 4.273E- 12 E 1.737E-IO 7. 714E- I I 4.6?3E-I 'I 2.362E-)1 1.430E-II 9.585E-)2 6.868E-12 5.)57E-I2 4.0 IOE-12 3. 203E-)2 2. 614E-12 ESE 1.816E-IO 8.066E- II 4.886E-II 2.4?of-ll 1.495E-)1 1.002E 'I I 7. 18)E" 12 5.393E-12 4. 193E-12 3. 349E-12 2. 734E-12 SE 2. 298E- I 0 'I . 02 IE-10 6. 185E-11 3. 126E 11 1. 892E- I I 1. 269E-11 9.090E-)2 6.826E-12 5.30?E- 12 4 . 240E- 12 3.460E- )2 SSE 2. 802E- I 0 I. 245E- I 0 7.541E-I I 3.812E 11 2. 307 E- I I 1.54?E 11 ) . IOBE-) I 8.323E-12 6. 47)E-12 5. 169E- 12 4. 219E-12 EA CI
TABLE A~12 0CI Deposition Values (D/Q) For Long Tenn Releases ht Standard Distances (m )
~USNRC COMPUTER CODE - XOQOOQ, VERSION 2.0 RUN DATE: 10/13/88 XOQDOQ -- SHNPP GROUND-LEVFL HISTORICAL DATA, 1976-1987 FXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 4~~~0 004 ~~0~ ~~ ~~~0~ ~ ~ ~ ~ ~ RELATIVE DEPOSITION PER UNIT AREA (M' ~-2) BY DOWNWIND SECTORS 0~0~~~~~~ 04J4 ~~ 44 ~~ ~ ~ ~ 11 SEGMENT BOUNDARIES 1N MILES DIRECTION . 5-) 1-2 2 3 3 4 4"5 5 10 10 20 20-30 30-40 40-50 FROM SITE S 3.943E-OB 8.07?E"09 2. 109E-09 9.470E-IO 5.35?E- IO 2. 060 E-10 5.960E-I I 2.362E-)1 'I .26)E-)1 7.808E-I2 SSw 3.685E-OB 7.548E-09 I . 97 I E-09 8.850E-)0 5.007E-)0 I . 925E-10 5.570E-)1 2.20BE-I'I 1. '179E-11 7.297E-)2
~
Sw 2.953E-OB 6.050E-09 1.579E-09 7.093E-IO 4. 013E-10 I . 543E-10 4.464E-II I. 769E-11 9. 448E-12 5.848E-12 WSW 2.300E-OB 4. 7)OE-09 1.2306-09 5.523E-IO 3. 124E-10 1.201E-IO 3.476E-II I. 378 E- I I ?.357E-12 4.554E-12 w 1.720E-OB 3.523E-OB 9. 196E-IO 4. ')30E-10 2. 33?E-)0 8.985E-II 2.599E-II 1. 030E- I I 5.502E- 12 3.405E- I 2 wNW 1.408E-OB 2.884E-09 7.52BE-IO 3.381E" 10 'I
. 9 13E- I 0 7.356E-I) 2. 128E-11 8.4346-12 4.504E- 12 2. 788E-12 Nw 1.43?E-OB 2.944E-09 7.685E-IO 3. 451E- I 0 1.952E-IO 7.508E-I'I 2. 172E-11 8.609E-12 4.59?E-12 2.846E-12 NNW 1.875E-OB 3. 841E-09 1.003E-OB 4.503E-)0 2.548E-)0 9.797E-II 2.834E- II 1. 123E- I I 5.998E-12 3. 713E-12 N 2.760E-OB 5.652E-09 1.476E-09 6.62?E-IO 3.749E-.)0 1.442E-IO 4. '17)E-) I 1.653E-)1 8. 828 E" 12 5.464E-12 NNE -3.369E-OB 6.901E"09 1.80)E"09 8. 09 1E" 'I 0 4.577E-IO 1.760E- IO 5.092E-I ) 2. 018E-11 I . 078 E" I I 6. 67 IE-12 NE 3.080E-OB 6.309E-09 1.64?E-OB 7. 39?E-10 4. 185E-10 I . 609E-10 4.655E-) I 1.845E-I'I 9.853E-12 6.099E"12
~I ENE 2.66)E-OB 5.45IE-09 1.423E-09 6.391E- 10 3. 615E-10 I . 39QE- I 0 4.022E-II 1.594E )I 8. 513E-12 5.269E-12 E 1.628E-OB 3.335E"09 8.707E"10 3.91 IE- 10 2. 212E-10 8.507E-II 2.46) f-I I 9.754E-\2 5. 209E-)2 3.224E-12
& ESE 1.703E-OB 3.487E-09 9. 104E- 'IO 4.089E-IO 2. 313E-10 8.895E-)l 2.573E-II 1.020E-II 5. 447E-12 3.3? IE-12 SE 2. 155E-08 4.414E-09 1. 1526-09 5. 176E-10 2. 928E-10 1. 126E-10 3.257E-II 1. 291E-11 6.894E-I2 4. 26?E-12 SSE 2.628E-OB 5.383E-09 I . 405E-09 6.311E" 10 3.5?OE-IO 1.373E- IO 3.972E-II 1.574E-) I 8.406E-12 5.203E-I2 VENT AND BUILDING PARAMETERS:
RELEASE HEIGHT (METERS) 0.00 REP. WIND HEIGHT (METERS) 10. 0 DIAMETER (METERS) 0.00 BUILDTNG HEIGHT (METERS) 55. 0 EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EMISSION RATE (CAL/SEC) o.o ALL GROUND LEVEL RELEASES.
aO TABLE h 13 O
aO Distribution Pasquill Stability Classes At Joint Wind Frequency By SHMPP LJSNRC COMPUTER CODE - XOQOOQ ~ VERSION 2.0 RUN DATE: 10/ )3/88 XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976- 1987 JOINT FREQuENcY olsTRIBuTIDH 0F WIND spEED AND DIREGTIDH ATMOSPHERIC STABILITY CLASS A UMAx (M/S) N NNE NE ENE E ESE SE SSE 5 SSW SW WSW WNW NW NNW TOTaL 0.34 0.000 Q.ooa o.aao 0.000 0.000 0. 000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0. 001 1.56 O. 014 0.009 0.016 0.012 0.012 0.009 0.021 0.008 0.020 0.016 0.020 0. 018 0.015 0. 010 0.011 0.009 0. 219 3.3S 0.425 0.354 0.307 0.2)9 0. 162 0.)23 O. 116 0. 177 0.357 0.329 0.338 0.416 0. 163 0. 165 0.317 0.334 4.303 5.59 0.307 0.296 0. )73 0.060 0.017 0.029 0.020 0.02) 0.083 0.257 0.361 0.450 0. 145 0.234 0. 367 0.356 3. 176 8.27 0.008 0.000 0.002 0.000 0.000 0.001 0.000 0.001 0.005 0.011 0.057 0.084 0.033 0.07) 0.059 0.044 0.374 I).18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00) 0.000 0.004 0.004 O.QOB o.oaa a.aol 0.018
) 1.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.75 0.66 0.50 0. 29 0. 19 0. 16 0. 16 0. 21 0.47 0. 6'I o.78 a.97 O.36 0.49 0.75 0.74 8.09 JOIHT FREQUEHCY DISTRIBUTION OF WINO SPEED ANO OIRECTIOH ATMOSPHERIC STABILITY CLASS 8 1))Max (M/s) N NNE NE EHE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL m 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000
~ 1.56 0.014 0.015 0.023 0.022 0.017 0.02) 0. 017 0. 018 0.022 0.020 0.032 0.021 0.025 0.0)3 0. 018 0. 017 0. 314 3.35 0.308 0.269 0.204 0. 181 0. 151 0.)21 0.087 0. 133 0.234 0.282 0.323 0. 314 0.111 0.)42 0.221 0. 217 3.298 5.59 0. 109 0.087 0.061 0.022 0.021 0.008 0.020 0.022 0.047 0.099 0. 160 0. 196 0. ')02 0. 151 0. 216 a. Ise 1.478 8.27 0.006 0.000 0.001 0.000 0.000 0.000 0.000 0.001 0.004 0.005 0.03'I 0.026 0.032 0.053 0.028 0. 019 0.205 I I. 18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Q.002 0.002 O.ao) 0.003 0.00'I 0. 001 0.010 II. 62 0.000 0.000 0.000 0.000 a.ooo 0.000 0.000 0.000 0.000 0.000 0.000 0.00) 0.000 0.000 0.000 0.000 0.001 TOTAL 0.44 0.37 0.29 0.23 0. 19 0. 15 0. 12 a.lz 0.31 0.41 0.55 0.56 0.2/ 0.36 0.48 0. 41 5.31 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS C UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW WNW NW NNW TOTAL 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 '.000 0.000 0.000 0.000
).56 0. 031 0.031 0.035 0.028 0.023 0. 031 0. 041 0.037 0.050 0.057 0.069 0.045 0.035 0.029 0.033 0.038 0. 610 3.35 0.347 0.287 0.245 0.220 0. 152 0. )31 0. 121 0. 158 0.261 0.332 0. 375" ~
0.369 0. '175 0. 192 0.246 0.261 3.874 5.59 0. 139 0. 081 0.039 0.036 0.008 0.009 0.014 0.027 0.029 0. I)2 0. 160 0. 192 0. 117 0. 115 0. 199 0. 145 1.423 8.27 0.007 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.00) 0.008 0. 019 0.023 0.012 0.055 0. 024 0. 015 0. )64 I 1. 18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 a.aao 0.002 0.003 0.002 0.002 0. 000 0.000 0.009
- 11. 62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0. 000 0.000 0.000 0.000 0.000 0.000 0.000 D.OOO 0.000 0.000 TOTAL 0.52 0.40 0.32 a.28 o. 18 a.)7 o. )e 0.22 0.34 0.51 0.63 0.63 0.34 0.39 0.50 0.46 6.08 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED ANO OIRF CT ION ATMOSPHERIC STABILITY CLASS 0 lD
< UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.002 0.002 0.002 0.002 0.001 0.001 0.001 0.001 0.002 0.002 0.002 0. 001 0. 001 0. 00) 0. 001 0. 001 0.025 1.56 0.434 0.506 0.444 0.370 0.329 0.266 0.278 0.300 0.362 0.48'I 0.465 0.346 0.287 0.258 0.269 0.346 5.739
~ 3.35 1.759 2.054 1.350 0.964 0.624 0.523 0.556 0.742 'I . 058 1.346 1.316 I . 177 0.647 0.583 0.746 1.025 16.471 5.59 0.556 0.491 0.330 0. 114 0.066 0.076 0. 100 0. 190 0.220 0.376 0.550 0. 462 0.260 0.402 0.523 0.558 5.271 8.27 0.055 0.023 0.004 0.011 0.004 0.006 0.005 0. 023 0.032 0.047 0. 069 0.075 0.042 0.092 0.062 0.063 0. 610
- 11. 18 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 o.oal a.ool 0.008 0.017 a.ooo 0.004 0.000 0.000 0.032
- 11. 62 0.000 0.000 0.000 0.000 0.00) 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 o.oao 0.000 0.000 0.001 TOTaL Z.el 3.08 2. 13 I . 46 1.02 0.87 0.94 1. 26 1.68 2.25 2.41 2.08 '1.24 1.34 ).60 1.99 28. 15
TABLE A-13 (continued)
CI K
CI Joint Mind Prequency Distribution By Pasquill Stability Classes At SHMPP Cl r I
USNRC COMPUTER CODE XOQDOQ. VERSION 2.0 RUN DATE: 09/OI/88 g
XOQDOQ SHNPP GROUND"LEVEL HISTORICAL DATA, 1976 1987 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED ANO DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S) N NHE NE ENE E ESE SE -SSE 5 .SSW SW WSW W WNW NW NNW TOTAL 0.34 o.aos 0.007 0.006 0.005 0.004 0.003 0.004 0.006 0.009 0.009 0.005 0.004 0.003 0.002 0.003 0.003 0.079 I. 56 0.747 0.962 0.824 0.692 0.518 0.480 0.536 0.8'l8 1.244 I . 183 0.723 0 492 0.4 IS 0.3)2 0.405 0.466 10.816 3.35 1.028 0.855 0;549 0.329 0.309 0.266 0.3S6 0.577 1.058 1.547 1. 029 0.744 0.488 0.459 0.660 0.667 10,920 5.59 0. 124 0.032 0.046 0.029 0.019 0.028 0.032 0.080 o.)3e a. 148 0. 216 0. 145 0.067 0. Ia'I 0.085 0. 131 'I. 421 8.27 0.007 0.003 0.000 0.002 0.002 0.004 0.006 0.006 0.016 0. 010 0.015 o.a26'.004 0.0)0 0. 003 0.003 0.008 0. ')20
- 11. 18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0. 000 0.000 0.003 0.000 O.QO I o.ooa 0.000 a.ooa
>> .62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 '0. 000 0.000 0.000 a.aoa TOTAL '1.91 1.86 I . 42 1.06 0.85 0.78 0.93 1.49 2.47 2.90 1.99 1.41 0.98 0.88 I. IG I . 28 23.36 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECT ION ATMOSPHERIC STABILITY CLASS F UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW WNW Nw TOTAL I 0.34 0. 018 0. 018 0.017 0.014 0. 01 'I 0.009 0.011 0. 015 0.018 0.019 0.012 0.009 0.008 0.007 0.007 a.o II 0.203 1.56 0. /77 a.?aa 0.735 0.62) 0. 500 0. 414 0.489 0.667 0.803 0.857 0.553 0.395 0.341 0. 291 0.321 0.467 9.0)7
~ 3.35 0.349 0. 159 0.072 0.071 0.056 0.033 0.043 0.046 0. 128 0. 192 0. )76 0. 144 0.098 0. 106 0.098 0. )54 1.925 5.59 0.003 0.00'I o.aoa a.ool 0.000 0.000 0.000 0.000 0.000 0.001 0.006 0.001 0.000 0.000 o.ooa 0.002 0,015 8.27 0.000 ,o ooo
~ 0.000 0.000 0.000 0.000 a.aao 0.000 0.000 a.ooa o.ool 0.000 0.000 0.000 0.000 0.000 0.001 I 'I. 18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 a.aao o.aoo 0.000 a.ooo a.oao 0.000 O.ODO 0.000
)1.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 a.aoo 0.000 0.000 0.000 0.000 TOTAL ).15 0.97 0.82 0,71 0.57 0.46 0.54 0.73 0.95 ).07 0.75 0.55 0.45 0.40 O.43 0.63 )1. 16 JOINT FREQUENCY OISTRteUTION OF WINO SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS G UMAX (M/S) N NHE HC EHE E ESE SE SSE 5 SSW SW WSW W WHW HW NNW TOTAL 0.34 0.360 0. 317 0. 316 0.284 0. 214 0. )54 0. 121 0. 108 0. 128 0. 128 0. 112 a.oes 0,077 0.071 0.085 0. 1/6 2.737 1.56 1.932 I. 699 I . 692 1.522 I . 146 0. 823 0.649 0.580 0.684 0.688 0.600 0.457 0. 414 o.381 a.455 0.945 '14.668 3.35 0. 162 0.032 0.024 0.021 0.009 0.012 0.012 0.007 0.007 0.008 0.026 0.023 0.014 0. 0 IS 0.021 o.a47 0.439 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0; 001 0.000 0.000 0.000 0.001 0.001 0.003 8.27 a.ooo 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 I I . 18 0.000 0.000 a.aao a.aao o.aao 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 o.ooa 0.000 0.000 o.aoo a.ooo 0.000 0.000 0.000 0.000 0 000 TOTAL 2.45 2.05 2.03 1.83 1.37 0.99 0.78 0.70 0.82 0.82 0.?4 0.57 0. 51 0.47 0.56 1. 17 17.85 TOTAL HOURS CONS)DERED ARE
+IND MEASURED AT 12.0 METERS.
TABLE h-13 (continued)
O a Joint Wind Frequency Distribution By Paaquill Stability Claaaea ht SHMPP I
QVERALI WIND DIRECTION FREQUENCY WIND DIRECTION: N NNE NE ENE E ESE SE SSE S SSw TOTAL FREQUENCY: 10.0 9.4 7.5 5.9 4.4 3.6 3.7 4.8 7.0 8.6 7.8 6.8 4.1 4.3 5.5 6.7 100. 0 OVERALL WIND SPEED FREQUENCY MAX WIND SPEED (M/S): 0.335 1.565 3.353 5.588 8.270 11. 176 11.623 AVE WINO SPEED (M/S): 0. 168 0.950 2.459 4.470 6.929 9.723 11.400
. WIND SPEED FREQUENCY: 3.05 41.38 41.23 12.79 1.48 0.08 0.00 THE CONVERSION FACTOR APPLIED TO THE WTND SPEED CLASSES IS 0.447
- 1. I. I. I. I. 1. I. I I, I, l. I I. I 1. I.
11 1.000 2189.
0.
1.000 2140.
0.
1.000 2140.
0.
1.000 2140.
0.
1.000 2140.
0.
1.000 2140.
0.
1.000 2028.
0.
1.000 2028.
0.
1.000 2124.
0.
1.000 2140.
0.
- 1. 000 2140.
- 0. 0.'.
1.000 2140.
1.000 2140.
1.000 2140.
0.
1.000 2140.
0.
1.000 2140.
0.
DISTANCES AND TERRAIN HEIGHTS IN METERS AS FUNCTIONS OF DIRECTION FROM THE SITE:
DIRECTION = 5 SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE DISTANCE 2189. 2140. 2140. 2140. 2140. 2140. 2028. 2028. 2124. 2140. 2140. 2140. 2140. 2140. 2140. 2140.
~ EI.EYAIION 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
12 16 15 13 2 0 I I
aA TABLE A'-14 X
O Shearon Harris Plant Site Input Information for Continuous Groundlevel Release an Calculations With the NRC XOODOQ ProItram I
Card Type 1 ls an array (XOpT) of options; such tLat 1 ~ do, 0 bypass. These options rennin ln effect for all release points run. Thus, all release points est have the saat assueptions.
Card Variable Value Used In X 1 ropl(1) tlon to dlstrlbute calns as the first mind-speed c ass (lf calss are already dlstrlbuted by dlrectlon ln Card Type 5, XOPT(l) ~ 0, and Card Type 5 ls blank). lf XOPT(1) ~ ), the cain values of Card Type 5 are dlstrfbuted by dlrectlon ln the s~ pro-portion as the dlrectlon frequency of wind-speed class tuo ropT(2) ll Option to input joint frequency dlstrlbutlon data 0 as percent frequency.
ropT(3) ll Option to coepute a sector spread for conparlson ulth centerline value ln purge calculation (Nornally ~ 1).
ropT(i) Option to plot short-tera X/Q values versus prob-ablllty of occurrence (IIoraally ~ 0).
ropT(5) Option to use cubic spline ln lieu of least square function for flttlng Internlttent release dlstrlbut lan (lhraal ly 1).
ropT(6) Option to pwch radial segnent X/Q and 0/Q values (Ilorwa 1 ly ~ 1).
ropT(T) Option to punch output of X/Q and 0/Q values of the points of Interest (Noraally ~ 1).
ropT(a) Option to correct X/Q and 0/Q values for open terrain roc lrcul at lon.
ropl(9) ll Option to correct X/Q and 0/Q values using site
-speci flc terrain reclrculatlon data.
Cl TABLE A-14 (continued) n
à O Card cartable naI ~aud s ~re Value Used In X IO ilpl (IO) Il Option to use desert signa curves (Noroally a 0). 0 1 ll IOPT (ll) Option to calculate aanwl 2/9 averages ulth 30 degree SectorS for north. east, south and uest
~ nd 20 degree sectors for all others (Normally ~ 0, and ihe code ull) use 22-1/2 degree sectors).
2 I-$0 Tl Till 20AI The aaln title printed at the beginning of the output. N/A 3 1-5 NTEL l5 The nueber of ve(netty categories (oaxt~ of 14).
3 S- IO NSTA 15 Tha auaber of stability categories (oaxl~ of 7)
(I ~ Iwys eqwla pat~ill stability class O, 2 ~ g,
..., 2 - O).
3 I I- IS NP!5 'Ihe nuebar of distaacas uith terrain data for each sector. The nueber of distances oust be the sane for each sector (Card Type 10)(aaxiam of 10).
3 16-20 INC IS The fncreoent in percent for uhich plotted results 15 are printed out (Noraally ~ 15).
3 21-25 NPTIPE The nuaber of titles of receptor types (cou, garden,
~ tc.) (Card Type 13)(aaxioua of eight) 3 26-30 NEIIT The nuaber of release exit points (naxi~ of five).
3 31-35 NCOg The nuebar of distances of site specific correction factors for recirculation (naxf-oi 10).
1-5 PtEV FS.O The height (in aeters, above ground level) of tbe 12:0
~ natured ulnd presented in the Joint fluency
~ ata (Card Type )). (For elevated/ground-level
~
oined release, use the IO-outer level ulads).
Card Ter fable Tyr~ Dose I tlon Value Used In X i 0-20 DECAYS(l) 3F5.0 For each I: The half-life (days) used In the X/Q I.I, 3 calculations s If DECAYS i 100, no decay <<Ill 101.00 occur; lf DECAYS d 0, depletion factor <<III be used In the X/Q calculations; If DECAYS ~ 0, X/Q 2e30
<<III not be calcul ~ ted. (Nor<<ally e DECAYS(l) ~ IOI ~ -8.00 (2) - 2.2d. (3) - -O.DO.)
2l-2$ PLQAO FS.O Plant grade elevation (feet above sea level). If ftCNAO 0.0, DIST and HT data Card Type IO and ll oust he In'actors. If ptGAAO < 0.0. DIST In 0.00 Ilies and Hl data ln feet. above plant grade. If bourse'r ptQOO i 0.0 above DIST ln alias and IIT dale ln feet above sea level.
I-3$ CAIN,(l) TF$ .0 of Inl ~
The nunber percents of cela for NSTA ~ ach stability categoryl If KOpf(I) ~ 0, BLANK 2 I'..
Insert blank card. (Note: I' Is stablllty class A, ~ Te6).
I-00 FAEQ(X,I.J) The joint fredI41 ncy dlstrlbutlon In hours (or N I, IC ~ ercent). Ihe values for TC (N) seclors are I ~ I, NTEt (If KOPT(I) read on each card for each coddblnatlon of <<lnd-
- 0) speed class (I) and stablllty class (J). The I.2. NYEt (lf rOPT(l) loop to read these value cycles first on dlrec-
~ I) tlon contlnulng In a a)oct<<lse fashion) e lhen on Joie NSTA <<Ind class and finally on stablllty class.
FS.O A correction factor applied to <<lnd-speed classes. If UCOR c 0: no corrections <<III be 200.
~ Ba*. If UCOA B 100I the <<lnd-speed classes
<<III be converted froa alias/hour to neters/second.
O Cl TABLE A-14 (continued) n X
O nI Card
~o~s Variable Nanc fLoraat Oescrl tlon Value Used In X 7 6-75 - I8IAT(I) TIFS.O The wx1~ wind speed ln each wind-speed class, ln either alias/hour or acters/ 0.75,3.50,7.50,12.50, second. (If 9lvcn In atlas/hour, sct UCOR i 100.) 18.50,25.00,26.00 Card Types 8 and 9 are read ln for each corrcctlon factor and distance 8lvca, 1 ~ I,NCOR 1-80 VRDIST(N,I) 16F5.4 Thc distance In actors at which corrcctloa All Distances = 1.0 K 1,16 factors are 8lvca. These values are read la be8lnnla8 with south and proceeding ln a clockwise direction (naxi~ of 10).
1-80 VRCR(8.1) k~1, l6 16F5.0 Correction factor to be applied to X/4 and D/I) values corresponds to distances specified All Factors =1.000 In VRDIST.
Card Types 8 and 9 arc repeated for the renatatn9 distances and correction factors.
Card Types 10 and ll arc read ln for each terrain distance and hat8ht 8ivcn, 1 ~ T,NDIS.
'10 1-80 DIST(N.I) '16F5.0 The distance ia eaters at >>hlch terrain Distances =Site Boundar 8 1,16 heights arc Riven. These values arc read In bc8innln9 >>1th south and procccdin9 la Distances a clock>>isa dlrcctlon (naxiaua of tcn distances).
terrain hel9hts (la acters, above pleat 1-80 IIT (K, 1 8-1,16
) 16F5.0 Thc 8radc level) correspondin8 to thc distances All Heights = 0.0 specified ln the 0151 array (Card Type 1D).
These values are read la the sane order as the D1$ 1 array. For a 9lvcn direction and distance, thc terrain hcl9ht should bc thc hI8hcst elevation between thc source and that distance anywhere wlihia thc direction sector.
Card Types 10 and ll are repeated for thc rcnatnln8 distances and hcl9hts.
t E
TABLE A 14 (conts.nued)
Card JXRR ~s 1-25 Variable Vniuo Used in X 12 HPOIHT( I ) 515 ~
The nunbcr (<<axiom of 30) of receptor loca-I I ~ HPIYPE tions for particularmceptor type (such as the nueber a
of caa, gardens, or site 16,15,13,2,0,11 boundaries).
Card Types 13 and I& are read in For each receptor type. thus I I, HPTTPE 13 I-'16 7 ITLPT(I,J) 4Ai The title (cacs, gardens, etc.) of the Site Boundary 16 receptor type for the receptor locations (Card Type 14) (a <<axinu<<of I& spaces). Nearest Resident 15 Garden 13 1-80 KDIR(I H) receptor direction and distance. KDIR PTOIST(I,H) 8(IS) The ls the direction of interest, such that Cow Milk 2 H 1,HPOIHT(l ) I South, 2 SSQ,... ~ 16 SSE, PTDIST ls Goat Milk = 0 the distance, In <<eters, to the receptor Meat & Poultry = 11 location. See Table A-l.
Card Types 13 and II are repeated for the rc<<alning receptor typos.
Card Iypes 15, 16, and II read In for each plant release point, thus I ~ I~ HEXIT 15 1-80 TITlE(I.J) 20AL The title for the release point Mesc characteristics aro described on Card Types 16 and 17.
16 1-5 EXIT(I) F5.0 The vent average velocity (stars/second).
(Hote: lf a lOOK greed-level releaso ls 0 asswed, sct EX!T > 0, DIAHIR 0, and SLEV ~ 10 <<eters).
16 6-10 D IJHTR f5.0 The vent inside dla<<ater (<<etcrs).
16 11-15 HSTACK(l ) FS.O The height of the vent release point (<<eters ~
plant grade level). If release ls IOOK ele- 0.0 vated. input negative of height.
16-20 HBLDG(I ) f5.0 height of thc vent's building The (stars, above plant grade level). 55.0
J TABLE A-14 (continued)
Card Variable Col~s llano Desc Value Used ln X 16 21-25 CRSEC(I) f5.0 The ainlaa cross-sectional area for the vent's building (squar~ters). 2161.0 16 26-30 StEV(I) f5.0 The <<Ind height used for iho vent elevated release (neters . above plant grade level). 10. 0 16 31-35 HEATR( I ) F5.0 The vent heat eaission rate (cal/sec)
(lorna) ly 0). 0.0 17 RLSID(I) Al 'A one letter Identification for the release point.
17 2-5 IPURGE( I) IPURGE ~ I. 2 or 3 If the vent has inter-
<<Ittant releases. The l. 2 or 3 corres-ponds to DECAYS(l), DECATS(2), or DECAYS(3)
(Card Type d), respectively, <<hlchaver Is used as the base for Intermittent release calculations (normally no decay/no deplete x/q, s~h that IPURGE(l) - I); lf a vent has no Interalttent releases, IPURGE ~ 0.
17 6-10 NPURGE( I) l5 . The nueber of Interalttent releases per year for this release point. 0 ~
17 11-15 llPRGIN(l ) 15 The average nueber of hours per Interalttent release.
Card Types 15 '6 and 17 are repeated for the renatnine release Card Types 1-17 nay be repeated for the next case.
points.
(1) Appropriate data to be supplied.
OS2 Sheet 1 of 14 APPENDIX B DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with Technical Specification 3.11.2.l.b and Appendix I of 10CFR50 for gaseous effluents. These dose parameters, PE and R , were calculated using'he meth-
~
odology outlined in NUREG 0133 along with Regulatory Guide 1.109, Revision 1. The following sections provide the specific methodology which was utilized in calculating the PE1 and R.1 values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively).
B.l Calculation of P The dose parameter, P ~
, contained in the radioiodine and particulates portion of Section 3.2 includes only the inhalation pathway transport parameter of the "i" radionuclide, the receptor's usage of the pathway media, and the dosimetry of the exposure. Inhalation rates and the internal dosimetry are functions of the receptor's age; however, under the exposure conditions for Technical Specification 3.11.2.1b the child is considered to receive the highest dose.
The values for PE represents the highest dose to any organ including the l~
whole body resulting from inhalation of radionuclide "i" by a child. The following sections provide in detail the methodology which was used in calcu-lating the P. values for inclusion into this ODCM.
B.l.l Inhalation Pathwa The evaluation of this pathway consists of estimating the maximum dose to the most critical organ received by a child through inhalation by.'
= K'(BR) DFA. (B.1-1)
I DCM/ODC-AB B-1 Rev. 3.0
f.I lf I g,'
OS2 Sheet 2 of 14 APPENDIX B (continued)
B.l.l Inhalation Pathwa (continued where.'E 1I
= Dose parameter for radionuclide "i" for the inhalation. pathway, mrem/yr per pCi/m K' A constant of unit conversion; 10 'pCi/pCi; BR = The breathing rate of the children's age group, m /yr, DFA.
1 The maximum organ inhalation dose factor for the children's age group for radionuclide "i," mrem/pCi.
The age group considered is the child because the bases for the Technical Specification 3.11.2.l.b is to restrict the dose to the child's thyroid via inhalation to 5 1500 mrem/yr. The child's breathing rate is taken as 3700 m /yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the child, DFA., are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem/pCi. The total body is considered as an organ in the selection of DFA..
The incorporation of breathing rate of a child (3700 m /yr) and the unit conversion factor results in the following equation:
3~7 x 10 DFA.
I DCM/ODC-AB B-2 Rev. 3.0
1$
4'c
OS2 Sheet 3 of 14 APPENDIX B (continued)
B.2 Calculation of R.
The bases for Technical Specification 3.11.2.3 state that conformance with the guidance in Appendix I should be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.
Underestimation of the dose can be avoided by assigning a theoretical individual to the exclusion boundary in the sector with the highest X/Q and
.D/Q-".values and employing all of the likely exposure pathways, e.g., inhala-tion, cow milk, meat, vegetation, and ground plane. R values have been cal-culated for the adult, teen, child, and infant age groups for the inhalation, ground plane, cow milk, goat milk, vegetable, and beef ingestion pathways.
The methodology which was utilized to calculate these values is presented below.
B.2.1 Inhalation Pathwa The dose factor from the inhalation pathway is calculated by:
R = K'BR) (DFA )
I where:
R. Dose factor for each identified 'radionuclide "i" of the I
organ of interest, mrem/yr per pCi/m ;
K' A constant of unit conversion',
10 pCi/pCi; (BR) = Breathing rate of the receptor of age group "a," m /yr',
DCM/ODC-AB B-3 Rev. 3.0
>'c'It tg 4
f q1 1
fi'I I
'@l
OS2 Sheet 4 of 14 APPENDIX B (continued)
B.2.2 Inhalation Pathwa (continued)
(DFA. ) Organ inhalation dose factor for radionuclide "i" for the receptor of age group "a", mrem/pCi.
The breathing rates (BR) a for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109, Revision 1.
Age Group (a) Breathing Rate (m /yr)
Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA.) i a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.
B.2.2 Ground Plane Pathwa The ground plane pathway dose factor is calculated by:
-X.t R.
1G
= I. K'K"(SF)DFG.
1 (1-e )/) . (B.2-2) where:
R. Dose factor for the ground plane pathway for each identified radionuclide "i" for the organ of interest, mrem/yr per pCi/sec G
per m DCM/ODC-AB B-4 Rev. 3.0
f 4l l
A
'c g~
y, '~C
OS2 Sheet 5 of 14 APPENDIX B (continued)
B.2.2 Ground Plane Pathwa (continued)
K' A constant of unit conversion, 10 pCi/pCi; K" = A constant of unit conversion; 8760 hr/year; X. = 'he radiological decay constant for radionuclide "i," sec t = The exposure time, sec; 4.73 x 10 sec (15 years);
DFG = The ground plane dose conversion factor for radionuclide "i,"
mrem/hr per pCi/m ',
A tabulation of DFG values is presented in Table E-6 of Regulatory Guide 1 '09, Revision 1.
SF = The shielding factor (dimensionless);
A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.
Ii = Factor to account for fractional deposition of radionuclide II u For radionuclides other than iodine, the factor I's equal to one. For radioiodines, the value of I may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2. (Reference NUREG 0133)
DCM/ODC-AB B-5 Rev. 3.0
OS2 Sheet 6 of 14 APPENDIX B (continued)
B.2.3 Grass Cow or Goat Milk Pathwa The dose factor for the cow milk or goat milk pathway for each radionuclide for each organ is calculated by:
-X. tf t (1-e i b)
R. = I.K'Q,U (DFL.) (fp fs ( r(1-e i E. e
)
B.
1v i F'.ap F m i a e
Y XE p E.
PX.
1 t it b )
~
t (1-e -X ih) where.'X E. e B.
fp fs )( r(1-e Y
~
z ) 1v (1
PX. ) (B.2-3) s 1 1
R. Dose factor for the cow milk or goat milk pathway, for each identified radionuclide "i" for the organ of interest, mrem/yr M
per yCi/sec per m K' A constant of unit conversion',
10 pCi/pCi; QF
= The cow's or goat's feed consumption rate, kg/day (wet weight);
ap The receptor's milk consumption rate for age group "a,"
liters/yr',
DCM/ODC-AB B-6 Rev. 3.0
A I
~
lt I
J A 'll tl p J
/$
'~pl
OS2 Sheet 7 of 14 APPENDIX B (continued)
B.2.3 Grass Cow or Goat Milk Pathwa (continued)
Y P
= The agricultural productivity by unit area of pasture feed grass, kg/m ',
Y s
= The agricultural productivity by unit area of stored feed, kg/m F ' 'he stable element transfer coefficients, pCi/liter per pCi/day; r = Fraction of deposited activity retained on cow's feed grass)
(DFL-) = The organ ingestion dose for radionuclide "i" for the receptor in age group "a," mrem/pCi; E.
X.
i +X w'.
1
= The radiological decay constant for radionuclide "i,"
sec The decay constant for removal of activity on leaf and plant surfaces by weathering, sec 5.73 x 10 sec (corresponding to a 14 day half-life);
tf = The transport time from feed to cow, or goat to milk, to receptor, sec; DCM/ODC-AB , 8-7 Rev. 3.0
t ll~>>
OS2 Sheet 8 of 14 APPENDIX B (continued) th = The transport time from pasture, to cow or goat, to milk to receptor, sec',
tb = Period of time that sediment is exposed to gaseous effluents, sec',
xv Concentration factor for uptake of radionuclide "i" from the soil by the edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil);
P = Effective surface density for soil, Kg (dry soil)/m ;
fP = Fraction of the year that the cow or goat is on pasture>
s Fraction of the cow feed that is pasture grass while the cow is on pasture', (dimensionless).
te = Period of pasture grass and crop exposure during the growing season, sec',
I'1 Factor to account for fractional deposition of radio-nuclide "i."
For radionuclides other than iodine, the factor I's equal to one.
radioiodines, the value of I 1 may vary. However, a value of 1.0 was used in For calculating the R values in Tables 3.3-8 through 3.3-15. (Reference NVREG 0133)
'DCM/ODC-AB B-8 Rev. 3.0
i 1~
'7 k
h I
1 n
I t
i 4
F~
OS2 Sheet 9 of 14 APPENDIX B (continued)
B.2.3 Grass Cow or Goat Milk Pathwa (continued)
Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following. the development in Regulatory Guide 1.109, Revision 1, the value of fs was considered unity in lieu of site-'.667 specific information. The value of f was based upon an 8-month period. grazing'able B-1 contains the appropriate parameter values and their source in Regu-latory Guide 1.109, Revision 1.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R 1 is based on X/Q:
R = K'KF QFU (DFL.) 0.75(0.5/H). (B.2-4)
M where'.
RT Dose factor for the cow or goat milk pathway for tritium for M
the organ of interest, mrem/yr per pCi/m ',
K A constant of unit conversion; 10 gm/kg',
H = Absolute humidity of the atmosphere, gm/m ;
.0.75 = The fraction of total feed that is water',
DCM/ODC-.AB B-9 Rev. 3.0
OS2 Sheet 10 of 14 APPENDIX B (continued)
B.2.3 Grass Cow or Goat Milk Pathwa (continued) 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water.
and other parameters and values are given above. A value of H = 8 grams/
meter , was used in lieu of site-specific information.
B.2'4 Grass-Cow-Meat Pathwa The integrated concentration in meat follows in a similar manner to the devel-opment for the milk pathway; therefore:
-X.t t -X.tb i (fp fs r(1-e E. e i ) iv (1-e )
R.
i = I.K'QFUFapfFf (DFL.) ia e ( Y p
XE E ~
PX.
1
)
i where.'X.t t b -X.t (1 fp fs ) (
r(l-e X
E. e i )
B.
1v (1-e PX ~
)
) ih) (B.2-5) s XE E. 1 1
R. = Dose factor for the meat ingestion pathway for radionuclide "i" B
for any organ .of interest, mrem/yr per pCi/sec per m Ff = The stable element transfer coefficients, pCi/Kg per pCi/day',
ap The receptor's meat consumption rate for age group "a," kg/yr,
. DCM/ODC-AB Rev. 3.0
tp i
OS2 Sheet 11 of 14 APPENDIX B (continued)
B.2.4 Grass-Cow-Meat Pathwa (continued) ts = The transport time from slaughter to consumption, sec, th = 'he transport time from harvest to animal consumption, sec',
te = Period of pasture grass and crop exposure during the growing season, sec; I'1 Factor to account for fractional deposition of radionuclide fI II For radionuclides other than iodine, 1 I's equal to one. For radioiodines, the value of I may vary. Ho~ever, a value of 1.0 was used in calculating the R values in Tables 3.3-5 through 3.3-7.
'All other teims remain the same as defined in Equation B.2-3. Table B-2 contains the values which were used in calculating R. for the meat pathway.
The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R. is based on X/Q.
R = K'KFfQ U (DFL.) 0.75(0.5/H) (B.2-6)
B where.'T Dose factor for the meat ingestion pathway for tritium for any B
organ of interest, mrem/yr per pCx/m 3 .
All other terms are defined in Equations B.2-4 and B.2-5.
DCM/ODC-AB .B-11 Rev. 3.0
à r
va, 1
OS2 Sheet 12 of 14 APPENDIX B (continued)
B.2'5 Ve etation Pathwa The integrated concentration in vegetation consumed by man follows the expres-sion developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:
-X t E. e
-X. t
~
tLL r(1 e i ) iv (1-e )
Ri1 I.K'DFL.i ) a ( U a fL L e ( Y PX.
)
v E.
1 1
E. e t '
X. tb US fg e ~ith (
r(1 e i ) + iv (1-e ) ) (BE 2-7) a Y PX v XE
~
1 1
where'.
R~ Dose factor for vegetable pathway for radionuclide "i" for the iV organ of interest, mrem/yr per pCi/sec per m K' A constant of unit conversion; 10 pCi/pCi; U
a
= The consumption rate of fresh leafy vegetation by the receptor in age group "a," kg/yr',
U a
= The consumption rate of stored vegetation by the receptor in age group "a," kg/yr; fL = The fraction of the annual intake of fresh leafy vegetation grown locally',
1.0 "DCM/ODC-AB B-,12 Rev. 3.0
I 1'J P.
C't 1
~ e t
OS2 Sheet 13 of 14 APPENDIX B (continued)
B.2.5 Ve etation Pathwa (continued) g The fraction of the annual intake of stored vegetation grown locally; 0.76 tL = The average time between harvest of leafy vegetation and its consumption, sec/
th =
e The average time between harvest of stored vegetation and its consumption, sec; Y = The vegetation a real density, kg/m ;
te = Period of leafy vegetable exposure during growing season, sec; Ii = Factor II' to account for fractional deposition of radionuclide All other factors as defined before.
For radionuclides other than iodine, the factor I is equal to one. For radioiodines, the value of I-1 may vary. However, a value of 1.0 was used in Tables 3.3-2 through 3.3-4.
Table B-3 presents the appropriate parameter values and their source in Regu-latory Guide 1.109, Revision 1.
In lieu of site-specific data default values for fl and f , 1.0 and 0.76, respectively, were used in the calculations on R . These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.
=DCM/ODC-AB B-13 Rev. 3.0
h w
l1 lr.
OS2 Sheet 14 of 14 APPENDIX B (continued)
B.2.5 Ve etation Pathwa (continued)
The concentration of tritium in vegetation is based on the airborne concentra-tion rather than the deposition. Therefore, the R. is based on X/Q:
= K'K fL + fg (DFL.) 0.75(0.5/H) (B.2-8)
R TV a U
a ia whdre
.'T Dose factor for the vegetable pathway for tritium for any organ V
of interest, mrem/yr per pCi/m All other terms remain the same as those in Equations B.2-4 and B.2-7.
-DCM/ODC-AB .: B-l4 Rev. 3.0
~1 J
t k
l,1
OS2 TABLE B-1 Parameters For Cow and Goat Milk Pathways Reference Parameter Value (Re . Guide 1.109 Rev. 1)
QF (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 Yp ( kg/m ) 0.7 Table E-15 tf (seconds) 1.73 x 10 ,(2 days) Table E-15 1.0 (radioiodines) Table E-1S 0.2 (particulates) Table E-15 (DFLi)a (mrem/pCi) Each radionuclide Tables E-11 to E-14 F" (pCi/liter per pCi/day) .Each stable element Table E-1 (cow)
Table E-2 (goat) 0 Tb (seconds) 4 '3 x 10 (15 yr) Table E-15 Y (kg/m ) 2.0 Table E-1S th (seconds) 7.78 x 10 (90 days) Table,E-15 Uap ( 1 i ters /yr ) 330 infant Table E-5
,330 child Table E-5 400 teen Table E-5 310 adult Table E-5 te (seconds) 2.59 x 10 (pasture) Table E-15 5.18 x 10 (stored feed)
Biv (pCi/kg [wet weight] Each stable element Table E-1 per pCi/kg [dry soil])
P (kg dry soil/m ) 240 Table E-15 DCM/ODC-AB B"15 Rev. 3.0
gJ ly
~P.
J '
(I 4
<<P
OS2
'TABLE B-2 Parameters For The Meat Pathway Reference Parameter Value (Re . Guide 1.109 Rev. 1) 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/kg per pCi/day) Each stable element Table E-1 (kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFLi)a (mrem/pCi) Each radionuclide Tables E-ll to E-14
,Y (kg/m ) 0.7 Table E-15 Y (kg/m ) 2.0 Table E-15 Tb (seconds) 4.73 x 10 (15 yr) Table E-15 Ts (seconds) 1.73 x 10 (20 days) Table E-15 th (seconds) 7.78 x 10 (90 days) Table E-15 t (seconds) 2.59 x 10 (pasture) Table E-15 5.18 x 10 (stored feed) qF (tg/day) 50 Table E-3 B .(pCi/kg [wet weight] Each stable element Table E-1 per pCi/kg [dry soil])
P (kg dry soil/m ) 240 Table E-15
'DCM/ODC-AB B-16 Rev. 3.0
I OS2 TABLE B-3 Parameters for The Vegetable Pathway Reference Parameter Value (Re . Guide 1.109 Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFLi)a (mrem/pCi) Each radionuclide Tables E-11 to E-14 IQri QF (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 L Infant Ua (kg/yr) 0 Table E-5 Child 26 Table E-5 Teen 42 Table E-5 Adult 64 Table E-5 S Infant Ua (kg/yr) 0 Table E-5 Child 520 Table E-5 Teen 630 Table E-5 Adult 520 Table E-5 TL (seconds) 8.6 x 10 (1 day) Table E-15 th (seconds) 5.18 x 10 (60 days) Table E-15 Y (kg/m2) 2.0 Table E-15 te (seconds) 5.18 x 10 (60 days) Table E-15 Tb (seconds) 4.73 x 10 (15 yr) Table E-15 P (kg dry soil/m ) 240 Table E-15 BE (pCi/kg [wet weight] Each stable .element Table E-1 per pCi/kg [dry soil])
- DCM/ODC-AB - B-.17 Rev. 3.0
I 1
I
OS2 Sheet 1 of 2 APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Monitor I. Li uid Effluent Monitorin Instruments Identification A. Treated Laundry and Hot Shower Tank................ REM-3540 B. Waste Monitor Tank................................. REM-3541 C. Waste Evaporator Condensate Tank................... REM-3541 D. Secondary Waste Sample Tank........................ REM-3542 E. Normal Service Water Returns to Circulating Water System From Waste Processing Building... REM-1SW-3500A Water System From Reactor Auxiliary B ld'lldlngo ~ o ~ ~ ~ ~ o ~ o ~ oo ~ o ~ oo ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ oooo ~ ~ ~ REM-1SW-3500B F. Outdbor Tank Area Drain Transfer Pump Monltol ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ REM-3530 G. Turbine Building Floor Drains Effluent............. REM-3528 II. Gaseous Effluent Monitorin Instruments A. Plant Vent Stack 1
- 1. Plant Vent Stack l............................ REM-1AV-3509-SA RM-1AV-3509-1SA"<
- 2. Reactor Auxiliary Building Normal Exhaust....................................... REM-1AV-3531
- 3. Reactor Auxiliary Building Emergency E xhaust.....o................................. REM-1AV-3532A
- 4. Reactor Auxiliary Building Emergency E xhaust....................................... REM-1AV-3532B
- 5. Fuel Handling Building Normal Exhaust (South)....................................... REM-1FL-3506
- 6. Fuel Handling Building Normal Exhaust (South)....................................... REM-1FL-3507
- 7. Fuel Handling Building Emergency E xhaust....................................... REM-1FL-3508A-SA
- 8. Fuel Handling Building Emergency Exhaust.....o...................oo.o.....o.oo. REM-1FL-3508B-SB
- 9. Containment Preentry Purge.................... REM-1LT-3502B 0 B. I Turbine Building Vent Stack
- 1. Condenser Vacuum Pump 3A.....................
Effluent Line...........
RM-1TV-3536-1""
REM-1TV-3534 DCM/ODC-AC C-1 Rev. 3.0
pI
~ "'gt'I
OS2 Sheet 2 of 2 APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Monitor II. Li uid Effluent Monitorin Instruments Identification C. Waste Processing Building Vent Stack 5......... REM-1WV-3546 RM-1WV-3546-1>'c D. Waste Processing Building Vent Stack 5A........ REM-1WV-3547 RM-1WV-3547-1~'c Wide-Range Gas Monitor (WRGM)
DCM/ODC-AC C-2
0 Carolina Power & Light Shearon Harris Nuclear Power Plant License No. NPP-063 SEMIANNUAL RADIOACTIVE EPFLUENT RELEASE REPORT July 1, 1989 to December 31, 1989 Prepared by:
Sr. Specialist V
Environmental & Chemistry Reviewed by:
Project Specia ist - Radiation Control Reviewed by:
Manager nvironmental & Rad a ion Control Approved by:
lant General Manager
Table of Contents Page No.
Introduction Discussion Appendix 1. Supplemental Information Appendix 2. Effluent and Waste Disposal Report 1 ~ Lover Limits of Detection (LLD's) 2/1
- 2. Effluents Released 2/3 3 ~ Solid Waste Disposal 2/11 Appendix 3. Changes to Process Control Program (PLP) 3/1 Appendix 4. Changes to Offsite Dose Calculation 4/1 Manual (ODCM)
Appendix 5. Changes to the Environmental Monitoring Program
- 1. Environmental Monitoring Program 5/1
- 2. Land Use Census 5/2 Appendix 6. Additional Technical Specification Responsibilities
- 1. Inoperability of Liquid Effluent Monitors 6/1
- 2. Inoperability of Gaseous Effluent Monitors 6/2 3 ~ Unprotected Outdoor Tanks Exceeding Limits 6/4 4, Gas Storage Tanks Exceeding Limits 6/5 Appendix 7. Major Modifications to Radwaste System 7/1 Appendix 8. Meteorological Data 8/1 Appendix 9. Assessment of Radiation Doses for Calendar Year 1989
- 1. Population Doses outside Site Boundary due to Effluent Releases 9/1
- 2. Doses to the General Public Due to Activities Inside the Site Boundary 9/2 3 ~ Doses to the Likely Most Exposed Member of the Public 9/4
- 4. Major Assumptions used to Calculate Radiation Doses 9/8 Appendix 10. Addendum to Appendix 2, Enclosure 3, Table 3 of the January 1, 1989 to June 30, 1989 Report Period 10/1 Appendix 11. Addendum to Appendix 2, Enclosure 3, Table 3 of the July 1, 1988 to December 31, 1988 Report Period 11/1
g f I
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1,4 to the Shearon Harris Nuclear Power Project (SHNPP) Operating License No. NPF-63. It provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS).
The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3, 1987. This report covers the period from July 1, 1989 to December
'31, 1989. During this period, the plant was in Cycle 2 operation until October 10, a refueling outage until December 27, and in Cycle 3 operation through December 31. This report also covers the period from January 1, 1989 to December 31, 1989 for meteorology and dose accountability.
Discussion Appendices 1 and 2:
The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev. 1) Appendix B format. As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container and solidification agent or absorbent.
Except for continuous noble gas releases, liquid and gaseous average concentrations (uCi/cc) and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD) tables show a typical sensitivity level for detection of the nuclide.
Continuous noble gas effluent activities were based on hourly average stack monitor readings (in uCi/cc) and stack flow rate estimates based on design fan flow rates. No specific noble gas nuclides were identified in any of the stack gas grab samples taken for characterizing continuous gaseous releases. Therefore, the total noble gas activities are based on stack monitor readings and apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM. Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.
No activity above background was detected in any continuous liquid release pathway. Therefore, the reported activities are the summation of nuclides in batch releases only.
A total of 101.11 m of solid waste, containing 20.86 Ci of radioa~tivity, was shipped for burial during this Report period, compared with 59.3 m and 4.57 Ci shipped during the previous Report period.
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Discussion (continued)
Appendix 3:
No changes to the Process- Control Program (PCP) were made during this Report period.
Appendix 4:
Revision 3/1 to the ODCM was approved by the PNSC in November 1989. The changes reflected in Revision 3/1 are intended to provide guidance for containment normal purge batch releases.
Appendix 5:
No Changes were made to the Environmental Monitoring Program or the Land Use Census during this Report period.
Appendix 6:
All effluent monitor inoperabilities greater than 30 days are given along with a brief explanation. During these periods, compensatory sampling and flow rate estimations consistent with Technical Specification requirements have provided accountability and control of effluents.
No unprotected outdoor tank or gas storage tank exceeded Tech Spec limits during this Report period.
Appendix 7:
No major modifications were made to the Radwaste System during this Report period.
Appendix 8:
The 1989 annual summary of meteorological data is available to the NRC upon request. This summary is also used in the NRC approved program XOQDOQ, which is used in the Appendix 9 dose calculations.
Appendix 9:
The effluent quantities reported for both semiannual periods in 1989 were combined for determining the annual dose impact from plant operations. The doses were calculated by the programs LADTAP II (for liquid effluents) and GASPAR (for gaseous effluents). GASPAR and LADTAP II are NRC approved programs for implementing Reg. Guide 1.109 methodology, which is also the basis of the ODCM calculations. When appropriate, the doses are also broken down by age group (adult, teen, etc.) and organ (bone, thyroid, etc.).
Enclosure 1 shows the integrated population doses within the 50-mile ingestion zone (in man-rem) due to liquid and gaseous, releases for the various e applicable pathways Also, the tritium contribution to the hydrosphere is shown.
ll
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Discussion (continued)
Appendix 9 (Continued)
Enclosure 2 shows the doses (in mrem/yr) to a hypothetical individual member of the general public due to activities inside the site boundary. Since portions of Harris lake are within the site boundary, these doses result from the recreational usage of the lake. The highest dose received by that individual corresponds to 0.29% of their applicable dose limit. The corresponding values for CY 1988 was 0.41%,
Enclosure 3 shows the hypothetical doses (in mrem/yr) for the "Likely Most Exposed Individual". For the liquid pathways, this calculation assumes that Lillington, the closest downstream public water supply, is the source of drinking water and Harris Lake is the source of all other liquid exposure. For liquid effluents, the highest whole body dose corresponds to 0.90% of the applicable dose limit, and the highest organ dose corresponds to 0.29% of the applicable dose limit. Corresponding values for CY 1988 were 0.16% and 0.05%,
respectively.
For the airborne pathways, the gaseous dose considers two types of individuals: (1) the "Maximum Hypothetical Individual", who resides at the site boundary in the sector of highest plume exposure, and (2), the "Maximum Real Individual" who, based on the Land Use Census, had the highest combined dose from his actual exposure pathways, e.g, plume, ground, etc. In 1989, the
~
"Maximum Real Individual" is located at 2897 meters ("1.8 miles) in the NNE
~ ~ ~
~
sector. In 1988, this individual was located at 2414 meters (1.5 miles) in the
~ ~ ~
~
NNW sector. ~
For the "Maximum Hypothetical Individual", the highest whole body dose corresponds to 0.02% of the applicable dose limit, and the highest organ dose corresponds to 0.01% of the applicable dose limit. Beta and gamma annual air doses were 1.41% and 1.95% of their respective limits. Corresponding values for CY 1988 were 0.05%, 0.02%, 2.67%, and 3.67%, respectively.
For the "Maximum Real Individual", the highest whole body dose corresponds to 0.02% of the applicable dose limit, and the highest organ dose corresponds to 0.01% of the applicable dose limit. Beta and gamma annual air doses were 0.43% and 0.59% of their respective limits. Corresponding values for CY 1988 were 0.02%, 0.01%, 1.06%, and 1.48%, respectively.
Enclosure 4 lists the major assumptions associated with the liquid and gaseous effluent doses. Where available, site specific information is used to derive these values. In other cases, parameter values or derivations are as given in Reg. Guide 1.109.
I~
4
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Discussion (continued)
Appendices 10 and 11: Addendum to Previous Semiannual Reports In May 1989, SHNPP was informed by the vendor (SAIC) who performs the 10CFR61 sample analysis, that an error was made in the Dry Compressible Waste sample analysis. SHNPP received the amended analysis and corrected the curie totals for waste shipped to Scientific Ecology Group (SEG) for processing.
SHNPP has received the corrected totals for all SHNPP waste that has been shipped by SEG for burial. Dry Compressible Waste totals from the two previous Report periods were affected. The corrected Appendix 2, Enclosure 3, Table 3 pages from these reports are included in Appendix 10 (January 1 June 30, 1989) and Appendix 11 (July 1 December 31, 1988)
For the period January 1, 1989 to June 30, 1989, the Dry Contaminated Waste Total Activity was originally reported as 3.72 E-Ol Ci. The Corrected Total Activity for this period is 1.24 E+00 Ci.
For the period July 1, 1988 to December 31, 1988, the Dry Contaminated Waste Total Activity was originally reported as 3.87 E-01 Ci. The Corrected Total Activity for this period is 1.27 E+00 Ci.
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 1: Supplemental Information
- 1. Regulatory Limits A. Fission and activation gases (1) Calendar Quarter
- a. 5 mrad gamma
- b. 10 mrad beta (2) Calendar Year
- a. 10 mrad gamma
- b. 20 mrad beta B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1) Calendar Quarter
- a. 7.5 mrem to any organ (2) Calendar Year
- a. 15 mrem to any organ C. Liquid effluents (1) Calendar Quarter
- a. 1.5 mrem to total body
- b. 5 mrem to any organ (2) Calendar Year
- a. 3 mrem to total body
- b. 10 mrem to any organ
l Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 1 (Continued): Supplemental Information
- 2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and activation gases (1) 500 mrem/year to total body (2) 3000 mrem/year to the skin B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.
1500 mrem/year to any organ C. Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the MPC shall be equal to 2.0E-4 uCi/ml.
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Measurements by continuous monitors of activity concentrations times total stack flow, and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides in representative grab samples.
B. Iodines Continuous charcoal cartridge sampling and analysis by gamma spectroscopy for specific radionuclides times total stack flow.
C. Particulates Continuous particulate sampling and analysis by gamma spectroscopy, alpha counting and radiochemical analysis for specific radionuclides times total stack flow.
D. Liquid Effluents Pre-release representative sampling and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides times total release volume.
1/2
Semiannual Radioactive Effluent Release Report July', 1989 to December 31, 1989 Appendix 1 (Continued): Supplemental Information
- 4. Batch Releases A. Liquid (1) Number of batch releases: 1,10 E+02 (2) Total time period for batch releases: 6.98 E+04 min.
(3) Maximum time for a batch release: 8.34 E+02 min.
(4) Average time for a batch release: 6.34 E+02 min.
(5) Minimum time for a batch release: 2.23 E+02 min.
(6) Average stream flow during periods of release: 7.24 E+03 gpm B. Gaseous (1) Number of batch releases: 3.70 E+01 (2) Total time period for batch releases: 2,08 E+04 min.
(3) Maximum time for a batch release: 3,01 E+03 min.
(4) Average time for a batch release: 5.62 E+02 min.
(5) Minimum time for a batch release: 2.00 E+00 min.
- 5. Abnormal Releases A. Liquid No abnormal liquid releases were made in the period.
B. Gaseous No abnormal gaseous releases were made in the period.
'I I
r Semiannual Radioac'tive Effluent Release Report July 1, 1989 to December. 31, 1989 Appendix 2: Effluent and Waste Disposal Report Enclosure 1 : LOWER LIMITS OF DETECTION (LLD)
H - 3 1.01 E-08 Ar-41 4.42 E-08 Cr-51 1.08 E-13 Mn-54 1.56 E-14 Co-58 1.54 E-14 Fe-59 3 '2 E-14 Co-60 3.62 E-14 Zn-65 5.94 E-14 Kr-85 8.56 E-06 Kr-85m 2.17 E-08 Kr-87 3.82 E-08 Kr-88 2.63 E-08 Sr-89 7.91 E-16 Sr-90 4.99 E-16 Nb-95 1.43 E-14 Mo-99 1.09 E-13 I -131 1.19 E-14 Xe-131m 7.78 E-07 I -132 3.84 E-14 I -133 1.82 E-13 Xe-133 4.48 E-08 Xe-133m 1.60 E-07 Cs-134 1.12 E-14 I -135 9,64 E-10 Xe-135 1.93 E-08 Xe-135m 4,88 E-07 Cs-137 1.42 E-14 Xe-138 9.68 E-07 Ba-140 3.81 E-14 La-140 4.27 E-14 Ce-141 1.70 E-14 Ce-144 7.48 E-14 Gross Alpha 4.28 E-15
4 T r
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1 : LOWER LIMITS OF DETECTION (LLD)
H 3 3.22 E-06 Na- 24 4.63 E-08 Ar- 41 6.61 E-08 Cr- 51 2.99 E-07 Mn- 54 2.86 E-08 Fe- 55 1.37 E-07 Co- 57 1.69 E-08 Co- 58 2.80 E-08 Fe- 59 6.47 E-08 Co- 60 4.31 E-08 Zn- 65 7.28 E-08 Kr- 85m 3.78 E-08 Sr- 89 1.57 E-09 Sr- 90 1.43 E-09 Zr- 95 4.72 E-08 Nb- 95 5.29 E-08 Nb- 97 4.19 E-08 Mo- 99 2.02 E-07 Tc- 99m 1.65 E-08 Ag-110m 2.43 E-08 Sn-113 3.63 E-08
'b-122 3.98 E-08 Sb-124 1.62 E-08 Sb-125 7.17 E-08 I -131 3.49 E-08 I -132 3.20 E-08 I -133 2.41 E-08 Xe-131m 1.51 E-06 Xe-133 9.45 E-08 Xe-133m 2.28 E-07 Xe-135 4.03 E-08 Cs-134 2.35 E-08 Cs-137 2.93 E-08 Cs-138 2.24 E-07 Ba-140 7.51 E-08 La-140 5.77 E-08 Ce-141 3,54 E-08 Ce-144 1.97 E-07 Pr-144 2.31 E-06 Hf-181 2.87 E-08 W -187 9.12 E-08 Gross Alpha 6.18 E-08 2/2
~ ~ J Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents'Released Table 1A : GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total 3 4 Error Fission & Activation Gases A. Total Release Ci 1.77 E+02 1.82 E+02 4.50 E+01 B. Average Release Rate for Period uCi/sec 2.23 E+01 2.29 E+01 C. Percent of Technical Specification Limit 6.01 E-01 6.18 E-01
A. Total Iodines Ci 0.00 E+00 9.49 E-07 2.00 E+01 B. Average Release Rate for Period uCi/sec 0.00 E+00 1.19 E-07 C. Percent of Technical Specification Limit 0.00 E+00 7.65 E-03
- 3. Particulates A. Particulates with T1/2> 8 days Ci 3. 12 E-07 3. 44 E-07 2. 00 E+01 B. Average Release Rate for Period uCi/sec 3.93 E-08 4.33 E-08 C. Percent of Technical Specification Limit 2.18 E-03 2.40 E-03 D. Gross Alpha Radioactivity Ci 0.00 E+00 0.00 E+00
- 4. Tritium A. Total Release Ci 0.00 E+00 0.00 E+00 3.00 E+01 B. Average Release Rate for Period uCi/sec 0.00 E+00 0.00 E+00 C. Percent of Technical Specification Limit 0 00 E+00 0 00 E+00 F
2/3
~ t Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1B : GASEOUS EFFLUENTS ELEVATED RELEASES All releases at Shearon Harris are made 'as ground releases.
2/4
I ~
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989
, Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1C : GASEOUS EFFLUENTS GROUND LEVEL RELEASES
- 1. Fission and Activation Gases Continuous Mode
- Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 3 4 3 4 H-3 Ci < LLD < LLD < LLD < LLD Ar-41 Ci < LLD < LLD < LLD 2.07 E-02 Kr-85 Ci < LLD < LLD < LLD 3.12 E-03 Kr-85m Ci 3.82E+00 3.92E+00 < LLD < LLD Kr-87 Ci 1.27E+00 1.31E+00 < LLD < LLD Kr-88 Ci 6.37E+00 6,53E+00 < LLD < LLD Xe-131m Ci < LLD < LLD < LLD 3.53 E-04 Xe-133 Ci 1.53E+02 1.57E+02 < LLD 1.81 E-01 Xe-133m Ci 2.55E+00 2.61E+00 < LLD 2.01 E-05 Xe-135 Ci 8.91E+00 9.14E+00 < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD Xe-138 Ci 1.27E+00 1.31E+00 < LLD < LLD Total Ci 1.77E+02 1.82E+02 < LLD 2.05 E-01
- Noble Gas quantities apportioned as per GALE code.
- 2. Iodines Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 3 4 3 4 I-131 Ci < LLD < LLD < LLD 9.49 E-07 I-132 Ci < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD LLD Total Ci < LLD < LLD < LLD 9.49 E-07 2/5
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released Table 1C (Continued): GASEOUS EFFLUENTS
'- GROUND LEVEL RELEASES
- 3. Particulates Continuous Mode Batch Mode Nuclides Uni ts Quarter ,Quarter Quarter Quarter Released 3 4 3 4 Cr-51 Ci < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci 3.12 E-07 3,44 E-07 < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Ba/La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Gross Alpha Ci < LLD < LLD < LLD < LLD Total Ci 3. 12 E-07 3. 44 E-07 < LLD < LLD 2/6
r Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A : LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Uni ts Quarter Quarter Est. Total 3 4 Error
- 1. Fission & Activation Products A. Total Release (not including tritium, Ci 4.27 E-02 1.17 E-01 3.50 E+01 gases, or alpha)
B. Average Diluted Concentration during Period uCi/ml 9.47 E-09 4.22 E-08 C. Percent of Technical Specification Limit '4.89 E-03 5.45 E-02
- 2. Tri tium A. Total Release Ci 1.34 E+02 1.02 E+02 3.50 E+01 B. Average Diluted Concentration during Period uCi/ml 2.98 E-05 3.68 E-05 C. Percent of Technical Specification Limit 9.92 E-Ol 1.23 E+00
- 3. Dissolved and Entrained Gases A. Total Release Ci 2.88 E-04 6,51 E-04 3.50 E+01 B. Average Diluted Concentration during Period uCi/ml 6.39 E-11 2.34 E-10 C. Percent of Technical Specification Limit 3.19 E-05 1.17 E-04
Semiannual Radioactive EXfluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A : LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Uni ts Quarter Quarter Est. Total 3 4 Error
- 5. Volume of. water released prior to dilution A. Batch Release liters 4.36 E+06 3.18 E+06 1.00 E+01 B. Continuous Release liters 1.93 E+07 7,04 E+06 1.00 E+01
- 6. Volume of dilution water liters 4.51 E+09 2.77 E+09 1.00 E+01 used during period 2/8
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released Table 2B : LIQUID EFFLUENTS Fission and Activation Products Continuous Mode Batch Mode Nuclides Uni ts Quarter Quarter Quarter Quarter Released 3 4 3 4 H-3 Ci < LLD < LLD 1.34 E+02 1.02 E+02 Na-24 Ci < LLD < LLD < LLD 2.14 E-05 Cr-51 Ci < LLD < LLD < LLD 1.41 E-02 Mn-54 Ci < LLD < LLD 4.35 E-04 7.70 E-04 Fe-55 Ci < LLD < LLD 3.71 E-02 7.23 E-03 Co-57 Ci < LLD < LLD 8.63 E-06 8.62 E-05 Co-58 Ci < LLD < LLD 7.60 E-04 6.82 E-02 Fe-59 Ci < LLD < LLD < LLD 2.08 E-03 Co-60 Ci < LLD < LLD 1.99 E-03 4.03 E-03 Zn-65 Ci < LLD < LLD < LLD 2.97 E-05 Sr-89 Ci < LLD < LLD 1.07 E-06 < LLD Sr-90 Ci < LLD < LLD 4.32 E-07 1.15 E-05 Zr/Nb-95 Ci < LLD < LLD < LLD 4.92 E-04
'b-97 Ci < LLD < LLD < LLD 7.05 E-06 Mo-99 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD Ag-110m Ci < LLD < LLD < LLD 1.36 E-04 Sn-113 Ci < LLD < LLD < LLD 3.88 E-05 Sb-122 Ci < LLD < LLD < LLD 2.95 E-04 Sb-124 Ci < LLD < LLD < LLD 1.19 E-03 Sb-125 Ci < LLD < LLD 2.10 E-03 1.83 E-02 I -131 Ci < LLD < LLD 1.55 E-05 4.83 E-05 Te-132 Ci < LLD < LLD < LLD 1,05 E-05 I -132 CI < LLD < LLD < LLD 1.94 E-05 I -133 Ci < LLD < LLD < LLD < LLD
<" LLD Cs-134 Ci < LLD < LLD 8.19 E-05 Cs-137 Ci < LLD < LLD 2.24 E-04 3.21 E-06 Cs-138 Ci < LLD < LLD < LLD 1.47 E-05 Ba/La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Pr-144 CI < LLD < LLD < LLD 2.61 E-04 Hf-181 Ci < LLD < LLD < LLD 2.85 E-05 Gross Alpha Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD 1.34 E+02 1.02 E+02 2/9
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released Table 2B (Continued) : LIQUID EFFLUENTS
- 2. Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 3 4 3 4 Ar-41 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD 1.03 E-04 6.51 E-04 Xe-133m Ci < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD 1.85 E-04 < LLD Total Ci < LLD < LLD 2.88 E-04 6.51 E-04 2/10
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
6 month Est. Total Solid. Cont. No.
A. Type of waste Uni ts Period Error (%) Agent Type Form Ship a ~ Spent Resin, filter 6.12 E+01 1.00 E+01 Cement STP S/D 10 sludge, evaporator bottoms, etc. Ci 1,42 E+01
- b. Dry Compressible m3 3.99 E+01 1.00 E+01 NA STP D 18 Waste, contaminated equipment, etc. Ci 6.65 E+00
- c. Irradiated Components, m3 No waste of this type shipped.
Control rods, etc. Ci
- d. Other (Describe) m3 No waste of this type shipped.
Ci
- STP Strong Tight Package
- S Solidified D Dewatered
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
B. Estimate of Major Nuclide Composition (by type of waste)
Type of Percent Total Activity Waste Nuclide Composition Ci a~ H -3 3.90 E+00 5.54 E-01 C -14 9.00 E-02 1.21 E-02 Mn-54 5.29 E+00 7.51 E-01 Fe-55 5.89 E+01 8.37 E+00 Co-58 2.01 E+01 2.85 E+00 Co-60 8.66 E+00 1.23 E+00 Ni-63 3.09 E+00 4.39 E+00 Sb-125 1.00 E-02 1.60 E-03
- b. H -3 1.35 E+00 8.97 E-02 C -14 5.00 E-02 3,14 E-03 Cr-51 1.70 E-01 1.14 E-02 Mn-54 1.74 E+00 1.16 E-01 Fe-55 8.53 E+01 5.67 E+00 Fe-59 1.00 E-02 7.46 E-04 Co-58 2.15 E+00 1.43 E-01 Co-60 6.23 E+00 4.14 E-01 Ni-63 2.00 E+00, 1.33 E-01 Nb-95 5.50 E-01 3.68 E-02 Zr-95 4.60 E-01 2.96 E-02 Cs-137 1.00 E-02 7.01 E-04 Am-241 5.87 E-05 3,90 E-06 Cm-244 8.72 E-05 5.80 E-06
- c. No waste of this type shipped.
- d. No waste of this type shipped.
'/12
C Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
C. Solid Waste Disposal Number of Shipments
- 2.80 E+01 Mode of Transportation Truck Destination Barnwell, S.C.
- 18 of these shipments (all type 1.A.b) were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee. The other 10 shipments (all type 1.A.a) were made from the Harris site.
- 2. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B )
No waste of this type was shipped during this Report period.
3.
~ Solid Waste Shipped for Burial or Disposal-(
~
WASTE CLASS C )
No waste of this type was shipped during this Report period.
- 4. Irradiated Fuel Shipments (Disposition)
No irradiated fuel was shipped during this Report period.
2/13
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 3 : Changes to Process Control Program (PCP)
Technical Specification 6.13 No changes were made to the PCP during this Report period.
C I
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 4 : Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specification 6.14 ODCM Revision 3/1 was approved during the Report period, resulting in four changes to the ODCM. The first change added a place for the Plant Nuclear Safety Committee (PNSC) to approve the changes to the ODCM. Change 2, 3, and 4 were editorial changes that incorporate guidance for containment normal purge batch releases. The changed pages are included in this appendix.
Item 1: ODCM Cover Page Add the following:
PNSC Chairman Approval Effective Date Item 2 : Page 3-1, Section 3.1, third paragraph.
Replace the following sentence:
"The sources of the batch releases for the respective stacks are containment preentry purge of pressure reliefs and VGDT releases."
with "The sources of the batch releases for the Plant Vent Stack 1 include containment normal and preentry purge and pressure reliefs. Batch release sources for Vent Stack 5 include releases from the waste gas decay tanks (WGDT)."
Item 3: Page 3-2, Section 3.1.1 Replace the following phrase:
"Batch mode release of containment preentry purge or pressure relief via plant wi th "Batch mode release of containment normal purge, preentry purge, or pressure relief via Plant Item 4: Page 3-4, Section 3.1.1 Add the following:'
= 1,500 acfm for containment normal purge
OS2 SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCH)
Revision 3.0 Advance Change 3/1 DOCKET NO. STN 50-400 CAROLINA POWER & LIGHT COMPANY PNSC CHAIR%M APPROVAL EFFECTIVE DATE
OS2 3.0 GASEOUS.EFFLUENTS At SHNPP there are four gaseous effluent release points: Plant Vent Stack 1, Turbine Building Vent Stack 3A, and the Waste Processing Building Vent Stacks 5 and 5A. These are shown in Figures 3.1, 3.2, and 3.3 along vith their tributaries. All gaseous effluent releases at the plant aze considered ground releases.
3.1 Monitor Alarm Set Point Determination (Technical Specifica-tion 3.3.3.11)
This section provides the methodology for stack effluent, monitor set points to ensure that the dose rates from noble gases at the site boundary do not exceed the limits of 500 mrem/year to the whole body or 3000 mrems/year to the skin as specified in Tech-nical Specification 3.11.2.1 and 10CFR20.105. Thus, the stack monitor set points effectively provide pre-release compliance with 10CFR20-based technical specifications for noble gases.
The radioactivity ezzluent monitors for each stack and zor specizic effluent streams are shown in Figures 3.1 and 3.3 and are listed in Appendix C.
In Stacks 1 and 5, the potential exists for batch releases concur-rent with tne normal cont'uous ventilation flov of effluents.
The sources of batcn releases zo" the Plant Vent Stack 1 include containment normal and preentry purge and pressure re ief. Batch AC fi release sources zoz Vent Stack 5 include releases f om the vaste gas decay I
tanks (WGDT). In these cases, the monitor set point must reflect the contribution of both the continuous and batch sources.
DCM/ODC-3 Rev. 3.0 4/3
OS2
'3.1.1 Effluent Monitor Set Point Based On Known Or Assumed Stack Effluent Com osition (Set Point Calculation Method : GALE)
The following set point calculation is applicable to the 4 vent stack monitors for all conditions, e.g.
~ Continuous release via Plant Vent Stack l.
~ Batch mode release of containment normal purge, preentry purge, or pressure relief 'via Plant Vent Stack 1 concurrent with the continuous release.
~ Continuous release through Vent Stack 3A.
~ Continuous release via Vent Stack 5 ~
~ Batch release of a waste gas decay tank via Stack 5 concurrent with the continuous release.
~ Continuous release via Vent Stack 5A.
The general approach to gas monitor set point determination begins with the Technical Specification limits on noble gas dose rates (mrem/year) to the whole body and skin at the site boundary.
These site limits are apportionated to each of the four stacks on the basis of respective design flow rate. Individual. s" ack release "ates {yCi/sec) are calculated which are functions of the known or assumed (GALE code) noble gas composition of he effluent. Based on stack flow rate (acfm) the release rate can be converted to an allowable noble gas concentration (yCi/cc). The monitor high alarm set point is 'then establisned to provide alarm wnen the concentration reaches 50 percent of the allowable level.
DCM/ODC-3 3 2 Rev. 3.0 4/4
3.1.1 Effluent Honitor Set Point Based on Known or Assumed Stack Effluent Composition (continued) 232,050 acfm (Waste Processing Building Vent Stack 5) 103,500 acfm (Haste Processing Building Vent Stack 5A) 390,000 acfm (Plant Vent Stack 1) f = Release flow rate for batch releases (acfm) 1,500 acfm for containment normal purge 37,000 acfm ror containment preentry purge 2.2e E+oe ( 14.7 ') 2730
( T )
c for contain-
-t ment pressure release coo ( t 14.7 )
273o
( T )
for a vaste gas t
decay tank release DCH/ODC-3 3-4 Rev. 3.0 4/5
I Semiannual Radioac(ive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 1 : Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.1.c No changes were made to the Environmental Monitoring Program during the Report period.
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications 3.12.2.a 3.12.2.b No changes were made to the Land Vse Census during the Report period.
5/2
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1 : Inoperability of Liquid Effluent Monitors Technical Specification 3.3;3;10~- Action b "
Monitors Out-of-Service > 30 Days During the Report Period Effluent Days Monitor Inop. Reason REM-01MD-3528 166 Electronic noise problems during pump Turbine Building Drains starts. Modification has been made which corrected the problem.
REM-01MD-3530 96 Due to a design deficiency, the high alarm Tank Area Drains signal tripped the process flow pump but did not isolate the release. Modification has been made which corrected the problem.
FT-1968 A&B 184 Flow monitors A & B are not within the Cooling Tower Make-up required tolerances, resulting in Bypass Line inaccurate flow measurements.
Flow Rate Monitors FT-6119 122 Modification to increase the accuracy and Waste Monitor Tank/ reliability of the readings has been Waste Evaporator Condensate Tank initiated.
Flow Rate Monitors FT-6193 110 Modification to increase the accuracy and Treated Laundry & reliability of the readings has been Hot Shower Tanks initiated.
Flow Rate Monitor
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service ) 30 Days During the Report Period Effluent Days Monitor Inop ~ Reason PNL-21AV-3509-SA 184 Problems with calibration of flov PNL-21AV-3509-1SA measurement system resulting in Plant Vent Stack discrepancies between actual and expected Flov Rate Monitor flow rates. Modification initiated to correct.
RM-01TV-3536-1 184 Moisture interferences vith the flow TB Vent Stack 3A measurement system resulting in Flov Rate Monitor discrepancies between actual and expected flov rates. Modification initiated to correct.
PNL-1WV-3546 & 184 Problems with calibration of flov PNL-1WV-3546-1 measurement system results in WPB Vent Stack 5 discrepancies betveen actual and expected Flow Rate Monitor flow rates. Modification initiated to correct.
PNL-1WV-3547 & 184 Problems with calibration of flow PNL-1WV-3547-1 measurement system resulting in WPB Vent Stack 5A discrepancies between actual and expected Flow Rate Monitor flov rates. Modification initiated to correct, 6/2
Semiannual Radioactive Bffluent Release Report July 1, 1989 to December 31, 1989 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service > 30 Days During the Report Period Effluent Days Monitor Inop. Reason OAI-21WG-1101 159 Monitor does not agree with analyzed Waste Gas samples. Modification has been Compressor Discharge initiated to improve the reliability of Oxygen Monitor the monitor.
116 Modification to improve
'AIC-21WG-1118B reliability of Waste Gas Recombiner monitor initiated.
"B" Outlet Gas Hydrogen Monitor OARC-21WG-1119B 181 Defective detector cell replaced.
Waste Gas Recombiner Recalibration delayed due to installation "B" Outlet Gas of a modification to increase the Oxygen Monitor reliability of the monitor.
6/3
Semiannual Radioactive Effluent Release Report
~
July 1, 1989 to December 31, 1989 Appendix
~
6 (Continued): Additional Technical Specification Responsibilities Enclosure 3 : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.
6/4
Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.
6/5
>~ I 1
Semiannual Radioactive E'ffluent Release Report July 1, 1989 to December 31, 1989 Appendix 7 : Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste system during this Report period.
Semiannual Radioactive Pffluent Release Report July 1, 1989 to December 31, 1989 Appendix 8 : Meteorological Data Technical Specification 6.9.1.4 As allowed by the Footnote to Technical Specification 6.9.1.4, the annual summary of meteorological data will be retained in a file. These data will be provided -to the NRC upon request.
I P
~
~
1
Semiannual Radioact ffluent Release Report July 1, 1989 ecember 31, 1989 Appendix 9 : Assessaent of Radiation Doses Enclosure 1: Population Doses Outside Site Boundary Due to Effluent Releases
- 1. Integrated Population Dose Due to Liguid Effluents (nan-rea)
A. 50 nile Ingestion Zone Bone Liver W. Body Thyroid Kidney Lung GZ-LLI Skin Sport Pish .22 E-03 7.27 E-03 4. 74 E-03 1.66 E-03 3.34 E-03 2.47 E-03 5. 17 E-03 0.00 E+00 Conn Fish 0 .00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Sport Invert 0 .00 K+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 K+00 0 F 00 E+00 0.00 E+00 Conn Invert 0 .00 K+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 F 00 E+00 0.00 E+00 Drinking Water 1 .38 E-03 1.67 E-01 1.67 E-01 1.66 E-01 1.66 E-01 1.67 E 01 1.70 E-01 0.00 E+00 Shoreline .05 E-03 4.05 E-03 4.05 E-03 4.05 E-03 4.05 E-03 4.05 E-03 4.05 E-03 4.74 E-03 Swimming 2 .77 E-05 2.77 E-OS 2.77 E-05 2.77 E 05 2.77 E-05 2.77 E-05 2.77 E-05 0.00 K+00 Boating 1 .39 E-05 1.39 E-05 1. 39 E-05 1.39 E-05 1.39 E-05 1.39 E-05 1.39 E-05 0.00 E+00 Zrri Veg 0 .00 E+00 0.00 E+00 0.00 K+00 0.00 E+00 0.00 E+00 0.00 K+00 0.00 E+00 0.00 E+00 Zrri Leafy Veg 0 .00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 K+00 0.00 E+00 Zrri Milk 0 .00 K+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 8+00 0.00 E+00 Zrri Meat 0 .00 E+00 0.00 E+00 0.00 K+00 0.00 E+00 0.00 E+00 0 00 E+00 0.00 E+00 0.00 E+00 ALL PATHWAYS 9.68 E-03 1.79 E-01 1.76 E-01 1.72 E-01 1.74 E-01 1.73 E-01 1. 79 E-01 4.74 E-03 B. Tritium (Hydrosphere)
Bone Liver W. Body Thyroid Kidney Lung GZ-I I I Skin Total 0. 00 E+00 6. 14 E-03 6.14 E-03 6. 14 E-03 6. 14 E-03 6.14 E-03 6. 14 E-03 0.00 E+00 Zntegrated Population Dose Due to Gaseous Effluents (aan-rea) 50 mile Ingestion Zone W. Body GZ-LI I Bone Liver Kidney Thyroid Lung Skin Plune 2.47 E-01 2.47 E-01 2.45 E-0 2.47 E-01 2.47 E-01 2. 47 E-0 1 2.63 E-01 8.15 E 01 Ground 5.38 E-09 5.38 E-09 5.38 E-0 5.38 E-09 5.38 E-09 5.38 E-09 5.38 E-09 6.53 E-09 Inhalation'egetation 4.83 E-06 5.15 E-07 7.77 E-0 4.38 E-08 7.43 E-08 1.44 E-05 8.72 E-06 0.00 E+00 2.09 E-05 2.00 E-06 8.41 E-0 2.00 E-08 3.37 E 08 6.48 E-06 0.00 E+00 0.00 E+00 Cow Milk 1.65 E-06 1.53 E-07 6.57 E-0 3.02 E-08 5.08 E-08 9.76 E-06 0.00 E+00 0.00 E+00 Meat a Poultry 8.02 E-07 8.56 E-08 3.25 E-0 1.93 E-09 3.29 E-09 6.29 E-07 0.00 E+00 0.00 E+00 Total 2. 47 E-0 1 2.47 E-01 2. 45 E-01 2.47 E-01 2.47 E-01 2. 47 E-01 2 ~ 63 E-01 8.15 E-01
Seniannual Radioact ffluent Release Report July 1, 1989 ecenber 31, 1989 Appendix 9 : Assessaent of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Inside Site Boundary Individual Dose Due to Liquid Effluents (mren/yr.)
Bone Liver W. Body Thyroid Kidney Lung GI LLI Skin ADULT Fish 4.62 E-03 8.73 E-03 6.41 E-03 2.13 E-03 4.11 E-03 3.04 E-03 7.24 E-03 Shoreline 4.24 E-04 4.24 E-04 4.24 E-04 4 24 E-04 4.24 E-04 4.24 E-04 4-24 E-04 4.97 E-04 Swinning 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 Boating 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 TOTAL 5. 11 E-03 4.22 E-03 6.90 E-03 2.62 E-03 4.60 E-03 3.53 E-03 7.73 E-03 4.97 E-04 TEEN Fish 4.87 E-03 8.47 E-03 4.24 E-03 1 '4 E-03 3.68 E-03 2.74 E-03 5.20 E-03 Shoreline Swinning 2 '7 4.52 E-03 E-05 2.37 4.52 E-03 E-05 2.37 4.52 E-03 E-05 2.37 E-03 4.52 E-05 2.37 4.52 E-03 E-05 2.37 4.52 E-07 E-05 2.37 4.52 E-03 E-05 2.77 E-03 Boating 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 TOTAL 7.33 E-03 1.09 E-02 6.71 E-03 4.10 E-03 6.15 E-03 5.21 E-03 7.66 E-03 2.77 E-03 CHILD Fish 6. 10 E-03 7. 45 E-03 2.69 E-03 1.35 E-03 3.09 E-03 2.26 E-03 2.59 E-03 Shoreline 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 5.08 E-04 Swinning 1.51 E-05 1.51 E-05 1.51 E-05 1.51 E-05 1.51 E-05 1. 51 E-05 1.51 E-05 Boating 1.88 E-05 1.88 E-05 1.88 E-05 1.88 E-05 1.88 E-05 1.88 E-05 1.88 E-05 TOTAL 6.63 E-03 7.98 E-03 3.22 E-03 1.88 E-03 3.62 E-03 2.79 E-03 3. 12 E-03 5.08 E-04 9/2
Semiannual Radioact ffluent Release Report July 1, 1989 December 31, 1989 Appendix 9 : Assessment of Radiation Doses Enclosure 2 (Continued): Doses to General Public Due to Activities Znside Site Boundary Zndividual Dose Due to Gaseous Effluents (mrem/yr.)
W. Body GZ-LLZ Bone Liver Kidney Thyroid tung Skin ADULT P lume 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1. 51 E-02 1. 51 E-02 1.55 E-02 3. 16 E-02 Ground 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Inhalation 1.03 E-07 1.22 E-08 1.66 E+06 0.00 E+00 1.23 E-09 2.39 E-07 l. 61 E-07 0.00 E+00 TOTAL 1.51 E-02 1. 51 E-02 1.51 E-02 1. 51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3. 16 E-02 TEEN Plume 1. 51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3- 16 E-02 Ground 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Inhalation 1.12 E-07 1.29 E-08 1. 81 E+06 0.00 E+00 1.69 E-09 2.94 E-07 2.76 E-07 0-00 E+00 TOTAL 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3.16 E-02 CHILD Plume 1. 51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3-16 E-02 Ground 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 00 E+00 Inhalation 1.08 E-07 5. 81 E-09 1.69 E+06 0.00 E+00 1.58 E-09 3.26 E-07 2.47 E-07 0.00 E+00 TOTAL 1.51 E-02 1. 51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3.16 E-02 INFANT Plume 1. 51 E-02 1. 51 E-02 1 ~ 51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3 16 E-02 Ground 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0"00 E+00 Inhalation 4.38 E-08 2.22 E-09 6.85 E+07 0.00 E+00 1.04 E-09 2.98 E-07 1.88 E-07 0.00 E+00 TOTAL 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.51 E-02 1.55 E-02 3.16 E-02 9/3
Semiannual Radioact ffluent Release Report July 1, 1989 ecember 31, 1989 Appendix 9 : Assessment of Radiation Doses Enclosure 3: Doses to Likely Most Exposed Member of the Public Zndividual Dose Due to Liquid Ef fluents (nrem/yr. )
Bone Liver W. Body Thyroid Kidney Lung GZ-LLZ Skin ADULT Fish 4.62 E-O 3 8.73 E-03 6.41 E-03 2.13 E-03 4.11 E-03 3.04 E-03 7.24 E-03 Drinking 1.36 E-04 2.02 E-02 2-02 E-02 2.01 E-02 2. 01 E-02 2.02 E-02 2.07 E-02 Shoreline 4.24 E-04 4.24 E-04 4.24 E-04 4.24 E-04 4.24 E-04 4.24 E-04 4.24 E-04 4.97 E-04 Swimming 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 3.02 E-05 Boating 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 3.46 E-05 TOTAL 5.24 E-03 2.94 E-02 2.71 E-02 2.28 E-02 2.47 E-02 2.37 E-02 2.84 E-02 4.97 E-04 TEEN Fish Drinking 4.87 0.00 E-03 E+00 8.47 0.00 E-03 E+00 4.24 0.00 E-03 E+00 1.64 0.00 E-03 E+00 3.68 0.00 E-03 E+00 2 '4 0.00 E-03 E+00 5.20 0.00 E-03 E+00 Shoreline 2.37 E-03 2.37 E-03 2.37 E-03 2.37 E-03 2.37 E-03 2.37 E-07 2.37 E-03 2.77 E-03 Swimming 4.52 E-05 4.52 E-05 4.52 E-05 4.52 E-05 4.52 E-05 4.52 E-05 4.52 E-05 Boating 5 '3 E-05 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 5.03 E-05 TOTAL 7.33 E-03 1.09 E-02 6.71 E-03 4.10 E-03 6. 15 E-03 5. 21 E-03 7.66 E-03 2.77 E-03 CHZLD Fish 6.10 E-03 7.45 E-03 2.69 E-03 1.35 E-03 3.09 E-03 2.26 E-0 3 2.59 E-03 Drinking 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Shoreline 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 4.95 E-04 5.08 E-04 Swimming l. 51 1.88 E-05 1.51 1.88 E-05 1.51 1.88 E-05 1. 51
- 1. 88 E-05 E-05 1.51 1.88 E-05 1.51 1.88 E-OS E-05
- 1. 51
- 1. 88 E-05 E-05 Boating E-05 E-05 E-05 E 05 TOTAL 6.63 E-03 7.98 E-03 3.22 E-03 1.88 E-03 3.62 E-03 2.79 E-03 3.12 E-03 5.08 E-04
~ ~
1
Semiannual Radioact ~ ffluent Release Report July 1, 1989 December 31, 1989 9 : Assessment of Radiation Doses 'ppendix Enclosure 3 (Continued): Doses to Likely Host Exposed Member of the Public
- 2. Zndividual Dose Due to Gaseous Effluents (nrem/yr.)
A. Maximum Hypothetical Zndividual Exposure from Noble Gases, Particulates, Zodines, and Tritium W. Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume 1.24 E-01 1. 24 E-01 1.24 E-01 1.24 E-01 1.24 E-01 1. 24 E-01 1.27 E-01 2.65 E-01 Ground 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 8.20 E-09 Znhalation 9.42 E-07 1. 13 E-07 1.52 E-OS 1.72 E-08 2.95 E-08 5.74 E-06 1.47 E-06 0.00 E+00 Vegetation Milk 4.27 1.44 E-05 E-06 5.03 E-06 1.85 E-07
- 1. 74 5.75 E-04 E-06 2 '0 7.55 E-08 E-08 4.62 1.29 E-08 E-07 8.84 2.47 E-06 E-05 0.00 E+00 0.00 E+00 0.00 0.00 E+00 E+00 Meat a Poultry 3.73 E-07 4.49 E-08 1.52 E-06 2.74 E-09 4.70 E-09 8.99 E-07 0.00 E+00 0.00 E+00 TOTAL 1.25 E-01 1.24 E-01 1.25 E-01 1.24 E-01 1.24 E-01 1. 25 E-01 1. 27 E-01 2.65 E-01 TEEN Plume Ground
- l. 24 6.75 E-01 E-09
- l. 24 6.75 E-01 E-09 1.24 6.75 E-01 E-09
- 1. 24 E-01 6.75 E-09 1.24 6.75 E-01 E-09 1.24 6.75 E-01 E-09 1.27 6.75 E-01 E-09 2.65 8.20 E-01 E-09 Znhalation 1.03 E-06 1.20 E-07 1.65 E-05 2.37 E-08 4.05 E-08 7.05 E-06 2.52 E-06 0.00 E+00 Vegetation 5.47 E-05 6.23 E-06 2.22 E-04 2.56 E-08 4.41 E 08 7.48 E 06 0.00 E+00 0.00 E+00 Milk 2.06 E-06 2.53 E-07 8.15 E 06 1.34 E-07 2. 31 E-07 3.91 E-OS 0.00 E+00 0.00 E+00 Meat 8 Poultry 2.43 E-07 2.80 E-08 9.81 E-07 2.23 E-09 3 . 84 E-09 6.51 E-07 0.00 E+00 0.00 E+00 TOTAL 1. 25 E-01 1.24 E-01 1. 25 E-01 l. 24 E-01 1. 24 E-01 1. 25 E-01 1.27 E-01 2.65 E-01 CHZLD Plume 1. 24 E-01 1.24 E-01 1.24 E-01 1.24 E-01 1. 24 E-01 1. 24 E-01 1.27 E-01 2.65 E-01 Ground 6.75 E 09 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E 09 6.75 E 09 6.75 E-09 8.20 E-09 Znhalation 9.98 E-07 5.39 E-08 1.55 E-05 2.32 E-08 3. 80 E 08 7.82 E-06 2.26 E-06 0.00 E+00 Vegetation 9.38 E-OS 4.99 E-06 3.70 E-04 3.47 E-08 5.70 E-08 1. 15 E-05 0.00 E+00 0.00 E+00 Hilk 3.51 E-06 2.04 E-07 1.38 E-05 2.34 E-07 3. 84 E-07 7.73 E-OS 0.00 E+00 0.00 E+00 Meat a Poultry 3.23 E-07 1.73 E-08 1.27 E-06 2.97 E-09 4. 88 E-09 9.83 E-07 0.00 E+00 0.00 E+00 TOTAL 1. 25 E-01 1. 24 E-01 1.25 E-Ol 1. 24 E-Ol 1. 24 E-01 1.25 E-01 1. 27 E-01 2. 65 E-01 ZNFANT Plume 1.24 E-01 l. 24 E-01 1.24 E-01 1. 24 E-01 1.24 E-01 1.24 E-01 1. 27 6.75 E-01 E-09
- 2. 65 8.20 E-01 E-09 Ground 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 6.75 E-09 Znhalation 4.06 E-07 2.06 E-08 6.27 E-06 2. 14 E-08 2.49 E-08 7. 15 E-06 1.72 E-06 0.00 E+00 Milk 4.02 E-06 2.05 E-07 1.53 E-05 5.71 E-07 6.67 E-07 1.88 E-04 0.00 E+00 0.00 E+00 TOTAL 1.24 E-01 1.24 E-01 1.25 E-01 1.24 E-Ol 1. 24 E-01 1. 25 E-01 1.27 E-01 2.65 E-01 9/5
Semiannual Radioact ffluent Release Report July 1, 1989 ecember 31, 1989 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Likely Most Exposed Member of the Public
- 2. Individual Dose Due to Gaseous Effluents (mrem/yr.)
B. Maximum Real Individual - Exposure from Noble Gases, Particulates, Zodines, and Tritium W Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 Ground 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.70 E-09 Inhalation 2.84 E-07 3. 41 E-08 4.59 E-06 4.62 E-09 7.91 E-09 1.54 E-06 4.43 E-07 0.00 E+00 TOTAL 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 TEEN Plume 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 Ground 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.70 E-09 Znhalation 3. 12 E-07 3.62 E-08 4.99 E-06 6.34 E-09 '1.08 E-08 1.89 E-06 7. 61 E-07 0.00 E+00 TOTAL 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 CHILD Plume 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-Q2 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 G round 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.70 E-09 Inhalation 3.01 E-07 1.62 E-08 4.67 E-06 6.21 E-09 1.02 E-08 2.10 E-06 6.82 E-07 0.00 E+00 TOTAL 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 INFANT Plume 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 Ground 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.22 E-09 2.70 E-09 Inhalation 1.22 E-07 . 6. 19 E-09 1.89 E-06 5.73 E-09 6.69 E-09 1.92 E-06 5. 19 E-07 0.00 E+00 TOTAL 3.79 E-02 3.79 E-02 3 '9 E-02 3.79 E-02 3.79 E-02 3.79 E-02 3.87 E-02 8.10 E-02 9/6
Semiannual Radioact ffluent Release Report July 1, 1989 t ecember 31, 1989 Appendix 9 : Assessment of Radiation Doses Annual Air Dose (mrad)
A. Maximum Hypothetical Zndividual: Beta 2.81 E-01 Gamma ~ 1. 95 E-01 B. Maximum Real Individual: Beta 8.66 E-02 Gamma ~ 5.93 E-02
- 4. Doses Due to Direct Radiation from the Harris Plant
,On-going environmental TID dose measurements show that the offsite Direct Radiation Dose is negligible.
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Semiannual Radioact ffluent Release Report July 1, 1989 ecember 31, 1989 Appendix 9 : Assessment of Radiation Doses Enclosure 4 : Major Assumptions Used to Calculate Radiation Doses
- 1. Doses Due to Liquid Effluents A. Dilution Factors Location Value Ex osure Pathwa s Harris Lake 1. 00 E+01 Shoreline, Swimming, Boating, Fish Consumption Cape Fear River 6. 67 E+02 Shoreline, Drinking Water (for Lillington, Dunn, and Fayetteville)
Cape Fear River/
Raven Rock Park 1.62 E+03 Boating B. Populations Af f ected Location Value Ex osure Pathwa s Harris Lake 1.10 E+05 person-hours Shoreline, Swimming Lillington 1.95 E+03 persons Drinking Water Dunn 9.00 E+03 persons Drinking Water Fayetteville 1.15 E+05 persons Drinking Water Harris Lake/
Cape Fear River 7.84 E+03 person-hours Fishing Cape Fear River/
Raven Rock Park 5.00 E+04 person-hours Boating Raven Rock Park 4.40 E+05 person-hours Shoreline Doses for "Activities Inside the Site Boundary" and the "Likely Most Exposed Member of the Public" use the Cape Fear River as the Drinking Water supply and Harris Lake as the source of all other liquid pathway doses.
Doses Due to Gaseous Effluents A. The 50 mile Inge sation Zone population is 1.47 E+06 persons.
B. The Maximum Real Individual is located at 2897 meters ( 1.8 miles) in the NNE sector.
C. The Maximum Hypo thetical Individual is located on the site boundary at 2140 meters in the SSW sector".
D. For the Inside S ite Boundary Individual, access time is assumed to be 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />s/yr at 1207 meters (3/4 mile) in th e NE sector f rom the plant, which is the closest accessible lake location.
E. Concurrent meteo rology is applied separately to batch vs. continuous release source terms.
The dose commitm ent from each mode was summed to obtain annual dose.
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Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 10: Addendum to Appendix 2, Enclosure 3, Table 3 of the January 1, 1989 to June 30, 1989 Report Period The following pages are an addendum to the January 1, 1989 to June 30, 1989 Semiannual Radioactive Effluent Release Report and show the corrected curie totals for Dry Compressible Waste.
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Semiannual Radioactive Effluent Release Report January 1, 1989 to June 30, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
6 month Est. Total Solid. Cont. No.
A. Type of waste Units Period Error (X) Agent Type Form Ship a ~ Spent Resin, filter m3 4.14 E+Ol 1.00 E+01 Cement STP S/D 7 sludge, evaporator bottoms, etc. Ci 3.33 E+00
- b. Dry Compressible 1.79 E+01 1.00 E+01 NA STP D 8 Waste, contaminated equipment, etc. Ci ],24 Ey00 ***
- c. Irradiated Components, m3 No waste of this type shipped.
Control rods, etc. Ci
- d. Other (Describe) m3 No waste of this type shipped.
Ci
- STP Strong Tight Package
- S Solidified D - Dewatered
+** This is an amended page showing the corrected Ci amounts for Dry Compressible Waste. All other values are correct.
2/11 10/2
Semiannual Radioactive Effluent Release Report January 1, 1989 to June 30, 1989 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
B. Estimate of Major Nuclide Composition (by type of waste)
Type of Percent Total Activity Waste Nuclide Composition **
a~ H -3 1.36 E+01 4.54 E-01 C -14 2.60 E+00 8.81 E-02 Mn-54 1.37 E+01 4.55 E-01 Fe-55 3.09 E+01 1.03 E+00 Co-58 1.59 E+01 5.29 E-01 Co-60 1.25 E+01 4.17 E-01 Ni-63 1.07 E+01 3.55 E-01 Sb-125 1.00 E-01 4.29 E-03
- b. H-3
- 1.48 E+00 1.83 E-02 C -14 5.66 E-01 6.99 E-03 Cr-51 1.10 E+00 1.36 E-02 Mn-54
- 3.51 E+00 4.33 E-02 Fe-55 7.46 E+01 9.21 E-01 Fe-59 2.21 E-01 2.73 E-03 Co-58
- 9.80 E+00 1.21 E-01 Co-60 1.81 E+00 2.23 E-02 Ni-63 5.77 E+00 7.12 E-02 Nb-95 7.68 E-01 9.48 E-03 Zr-95 4.07 8-01 5.02 E-03 Cs-137
- 7.34 E-03 9.07 E-05 Am-241 1.05 E-03 1.30 E-05 CIA-244 1.53 E-03 1.90 E-05
- Isotopes that were NOT affected.
- c. No waste of this type shipped.
- d. No waste of this type shipped.
- This is an amended page showing the corrected Ci amounts for Dry Compressible Waste. All other values are correct.
2/12 10/3
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Semiannual Radioactive Effluent Release Report July 1, 1989 to December 31, 1989 Appendix 11: Addendum to Appendix 2, Enclosure 3, Table 3 of the July 1, 1988 to December 31, 1988 Report Period The folloving pages are an addendum to the July 1, 1988 to December 31, 1988 Semiannual Radioactive Effluent Release Report and shov the corrected curie totals for Dry Compressible Vaste.
Semiannual Radioactive Effluent Release Report July 1, 1988 to December 31, 1988 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
6 month Est. Total Solid. Cont. No.
A. Type of waste Units Period Error (%) Agent Type Form Ship
- a. Spent Resin, filter m3 6.75 E+Ol 1.00 E+01 Cement STP S/D 6 sludge, evaporator bottoms, etc. Ci 7.81 E+00
- b. Dry Compressible m3 2.75 E+01 1.00 E+01 NA STP D 13 Waste, contaminated equipment, etc. Ci 1.27 E+00 ***
- c. Irradiated Components, m3 No waste of this type shipped.
Control rods, etc. Ci
- d. Other (Describe) m3 No waste of this type shipped.
Ci
- STP Strong Tight Package
- S Solidified D Dewatered
- This is an amended page showing the corrected Ci amounts for Dry Compressible Waste. All other values are correct.
2/10 11/2
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Semiannual Radioactive Effluent Release Report July 1, 1988 to December 31, 1988 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
B. Estimate of Major Nuclide Composition (by type of waste)
Type of Percent Total Activity Waste Nuclide Composition Ci a ~ H-3 7.19 E+00 5.62 E-01 C -14, 1.87 E+00 1.46 E-01 Cr-51 9.80 E-01 7.64 E-02 Mn-54 6.07 E+00 4.74 E-01 Fe-55 1.77 E+01 1.38 E+00 Co-58 5.18 E+01 4.05 E-01 Co-60 7.66 E+00 5.99 E-01 Ni-63 5.44 E+00 4.25 E-01 Sb-125 1.26 E+00 9.84 E-02
(
(
I b. H-3
- 9.23 E-01 1.17 E-02 C -14 5.79 E-01 7.34 E-03 4
(
( Cr-51 5.76 E-01 7.30 E-03 Mn-54
- 2.55 E+00 3.23 E-02 Fe-55 7.49 E+01 9.50 E-01 Fe-59 1.12 E-01 1.42 E-03 Co-58
- 1.10 E+01 1.39 E-01 Co-60
- 2.04 E+00 2.58 E-02 Ni-63 5.78 E+00 7.33 E-02 Nb-95 1.26 E+00 1.59 E-02 Zr-95 1.77 E-01 2.24 E-03 Cs-137
- 9.38 E-02 1.19 E-03 Sr-89 3.87 E-02 4.91 E-04 Am-241 1.49 E-04 1.89 E-06 C01-244 2.18 E-04 2.76 E-06
- Isotopes that were NOT affected.
- c. No waste of this type shipped.
- d. No waste of this type shipped.
- This is an amended page showing the corrected Ci amounts for Dry Compressible Waste. All other values are correct.
2/10a 11/3
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9)09040034 Carolina Power & Light Shearon Harris Nuclear Power Plant License No, NPF-063 SEMIANNUAL RADIOACTIVE EFFIUENT RELEASE REPORT January 1, 1991 to June 30, 1991 Prepared by:
Jr. pecialist Environmental & Chemistry Reviewed by:
Manager Envir, &, Radiation Control Support Reviewed by:
Manager - Envi . & Radiation Control Approved by:
General Manager Harris Plant
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Table of Contents Page No.
Introduction Discussion Appendix 1. Supplemental Information Appendix 2. Effluent and waste Disposal Report
- 1. Lower Limits of Detection (LLD's) 2/1
- 2. Effluents Released 2/3
- 3. Solid Waste Disposal 2/11 Appendix 3. Changes to the Process Control Program (PLP) 3/1 Appendix 4. Changes to the Offsite Dose Calculation Manual (ODCM) 4/1 Appendix 5. Changes to the Environmental Monitoring Program
- l. Environmental Monitoring Program 5/1
- 2. Iand Use Census 5/2 Appendix 6. Additional Technical Specification Responsibilities
- 1. Inoperability of Liquid Effluent Monitors 6/1 2 ~ Inoperability of Gaseous Effluent Monitors 6/3 3~ Unprotected Outdoor Tanks Exceeding Limits 6/5 4, Gas Storage Tanks Exceeding Limits 6/6 Appendix 7. Major Modifications to the Radwaste System Appendix 8. Amendment to the January 1, 1990 to June 30, 1990 Effluent Release Report Semiannual'adioactive 8/1
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~ 1 Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Plant (SHNPP) Operating License No. NPF-63. It provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS).
The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3, 1987. This report covers the period from January 1, 1991 to June 30, 1991. During this period, the plant ended Cycle 3 operation, had a refueling and maintenance outage, and began Cycle 4 operations.
Discussion Appendices 1 and 2:
The information on gaseous and 'liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev. 1) Appendix B format. As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container and solidification agent or absorbent.
Except for continuous noble gas releases, liquid and gaseous average concentrations (pCi/cc) and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (I LD) tables show a typical sensitivity level for detection of the nuclide.
Continuous noble gas effluent activities were based on hourly average stack monitor readings (in pCi/cc) and stack flow rate estimates based on design fan flow rates. No specific noble gas nuclides were identified in any of the stack gas grab samples taken for characterizing continuous gaseous releases. Therefore, the total noble gas activities are based on stack monitor readings and apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM. Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.
The "Percent of Technical Specification Limit" is calculated using ODCM default methodology and parameters.
A total of 44.95 m of solid 3
waste, containing 135.54 Ci of radioactivity, was shipped for burial during this Report period, compared with 49.8 m and 57.57 Ci shipped during the previous Report period.
No unplanned gaseous releases occurred during this Report period.
One unplanned liquid release occurred on April 8, when approximately 350 gallons of water containing 0.45 pCi of Co-58 was pumped from an area surrounding the Refueling Water Storage Tank to the storm drain system.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 3:
No changes to the Process Control Program (PCP) were made during this Report period.
Appendix 4:
No changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period.
Appendix 5:
The annual Land Use Census was performed during this Report period. As a result of the census, Table 3.2-2 of the ODCM, which provides the distances to the nearest special locations, i.e., residences, milk animals, gardens, and meat animals, will be revised in the next Report period.
To determine whether any of the new special locations yielded calculated doses greater than the locations previously used, the 1991 land use data was coupled with SHNPP 1990 meteorology, and dose calculations were performed by the GASPAR program using the GALE source terms provided in Table 3.2-1 of the ODCM.
No significant differences in estimated doses occurred as a result of the 1991 changes in the locations of the nearest resident, garden, or meat animal.
Appendix 6:
All effluent monitor inoperabilities greater than 30 days are given along with a brief explanation. During these periods, compensatory sampling and flow rate estimations consistent with Technical Specification requirements have provided accountability and control of effluents. Modifications performed to the Radiation Monitoring System have improved system reliability.
SHNPP has no unprotected outdoor tanks, and no gas storage tank exceeded Tech Spec limits during this Repor't period, Appendix 7:
No major modifications were made to the Radwaste System during this Report period.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 8:
An error was discovered in the amount of solid waste reported as shipped for burial or disposal (Appendix 2, Enclosure 3, Table 3, Item 1.A. a) in the Semiannual Radioactive Effluent Report for January 1, 1990 to June 30, 1990.
The corrected table is provided in this appendix, along with a change to the Discussion section of the same Report in which the information is also referenced.
Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 1: Supplemental Information 1~ Regulatory Limits A. Fission and activation gases (1) Calendar Quarter
- a. 5 mrad gamma
- b. 10 mrad beta (2) Calendar Year
- a. 10 mrad gamma
- b. 20 mrad beta B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1) Calendar Quarter 7.5 mrem to any organ (2) Calendar Year 15 mrem to any organ C. Liquid effluents (1) Calendar Quarter
- a. 1.5 mrem to total body
- b. 5 mrem to any organ (2) Calendar Year
- a. 3 mrem to total body
- b. 10 mrem to any organ 2 ~ Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and activation gases (1) 500 mrem/year to total body (2) 3000 mrem/year to the skin B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.
1500 mrem/year to any organ
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L Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 1 (Continued): Supplemental Information 2 ~ Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates (continued).
C, Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides'ther than dissolved or entrained noble gases. For dissolved and entrained noble gases, the MPC shall be equal to 2.0E-4 pCi/ml.
- 3. Average Energy (E)
N/A at SHNPP. SHNPP determines doses and dose rates based on actual release, not on an average energy value.
4, Measurements and Approximations of Total Radioactivity A. Fission and activation gases Measurements by continuous monitors of activity concentrations times total stack flow, and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides in representative grab samples.
B. Iodines Continuous charcoal cartridge sampling and analysis by gamma spectroscopy for specific radionuclides times total stack flow.
C. Particulates Continuous particulate sampling and analysis by gamma spectroscopy, alpha counting and radiochemical analysis for specific radionuclides times total stack flow.
D. Liquid Effluents Pre-release representative sampling and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides times total release volume.
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~ I Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 1 (Continued): Supplemental Information
- 5. Routine Batch Releases A. Liquid 1 ~ Number of batch releases: 121 2~ Total time period for batch releases: 7.87 E+04 min.
3~ Maximum time for a batch release: 9.54 E+02 min.
4, Average time for a batch release: 6.51 E+02 min.
- 5. Minimum time for a batch release: 1.99 E+02 min.
- 6. Average stream flow during periods of release: 1.17 E+04 gpm B. Gaseous 1 ~ Number of batch releases: 15 2 ~ Total time period for batch releases: 1.03 E+04 min, 3~ Maximum time for a batch release: 3.02 E+03 min.
Average time for a batch release: 6.88 E+02 min.
- 5. Minimum time for a batch release: 1.22 E+02 min.
- 6. Abnormal Releases A. Liquid One unplanned liquid releases was made on April 8, when approximately 350 gallons of water containing 3.37 E-07 pCi/ml Co-58 was inadvertently pumped from an area surrounding the Refueling Water Storage Tank to the storm drain system. This resulted in a release of 0.45 pCi (4.5 E-07 Ci) ~
The release was monitored, and the activity is included in Table 1 of Appendix 2. The doses attributed to this release were calculated and were negligible.
B. Gaseous No abnormal gaseous releases were made in the period.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2: Effluent and Waste Disposal Report Enclosure 1 LOWER LIMIT OF DETECTION (LLD)
- 1. Typical LID's for Gaseous Effluents NUCLIDE LLD (pCi/cc)
H - 3 1.01 E-08 Ar-41 4.42 E-08 Mn-54 1.56 E-14 Co-58 1.54 E-14 Fe-59 3.72 E-14 Co-60 3.62 E-14 Zn-65 5.94 E-14 Kr-83m 8. 37 E-08 Kr-85 8.56 E-06 Kr-85m 2.17 E-08 Kr-87 3.82 E-08 Kr-88 2.63 E-08 Sr-89 7.91 E-16 Sr-90 4 '9 E-16 Mo-99 1.09 E-13 I -131 1,19 E-14 Xe-131m 7. 78 E-07 I -133 1. 82 E-13 Xe-133 4.48 E-08 Xe-133m 1.60 E-07 Cs-134 1.12 E-14 I -135 9.64 E-10 Xe-135 1.93 E-08 Xe-135m 4.88 E-07 Cs-137 1.42 E-14 Xe-138 9.68 E-07 Ba-140 3. 81 E-14 La-140 4,27 E-14 Ce-141 1.70 E-14 Ce-144 7.48 E-14 Gross Alpha 4.28 E-15
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I Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1 : LOWER Lll4IT OF DETECTION (LLD)
Typical LLD's for Liquid Effluents NUCLIDE LLD(DCi/ml)
H - 3 3.22 E-06 Na- 24 4.63 E-08 Cr- 51 2,99 E-07 Nn- 54 2.86 E-08 Fe- 55 1.37 E-07 Co- 57 1.69 E-08 Co- 58 2.80 E-08 Fe- 59 6.47 E-08 Co- 60 4,31 E-08 Zn- 65 7.28 E-08 Kr- 85m 3.78 E-08 Kr-87 2.35 E-08 Sr- 89 1.57 E-09 Sr- 90 1.43 E-09 Zr- 95 4 '2 E-08 Nb- 95 5 '9 E-08 Nb- 97 4.19 E-08 No- 99 2.02 E-07 Tc- 99m 1.65 E-08 Ag-110m 2.43 E-08 Sn-113 3.63 E-08 Sb-122 3.98 E-08 Sb-124 1.62 E-08 Sb-125 7.17 E-08 Te-132 2.14 E-08 I -131 3. 49 E-08 I -132 3. 20 E-08 I -133 2.41 E-08 I -134 3.49 E-08 Xe-131m 1.51 E-06 Xe-133 9.45 E-08 Xe-133m 2.28 E-07 Xe-135 4.03 E-08 Cs-134 2.35 E-08 Cs-137 2.93 E-08 Cs-138 2.24 E-07 Ba-140 6.18 E-08 La-140 5,77 E-08 Ce-141 3.54 E-08 Ce-143 2.06 E-08 Ce-144 1.97 E-07 Pr-144 2.31 E-06 Hf-181 2,87 E-08 Gross Alpha 6.18 E-08 2/2
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~ I Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A : GASEOUS EFFLUENTS SUN4ATION OF AI,L RELEASES Units Quarter Quarter Est. Total 1 2 Error X 1 ~ Fission & Activation Gases A. Total Release Ci 8.91 E401 2.79 E%02 4.50E401 B. Average Release Rate for Period pCi/sec 1.15 E401 3.55 E401 C. Percent of Technical Specification Limit 2.27 E-01 1.66 E-01 2~ Iodines (I-131, I-133, I-135)
A. Total Iodines Ci 0.00 E+00 0.00 E400 2.00 E+01 B. Average Release Rate for Period pCi/sec 0.00 E400 0.00 E400 C. Percent of Technical Specification I imit x See Footnote Below
- s. Particulates A. Particulates with T$ > 8 days Ci 2.72 E-05 4.14 E-06 2.00 E%01 B. Average Release Rate for Period pCi/sec 3. 51 E-06 5. 25 E-07 C. Percent of Technical Specification Limit 8.00 E-03 5.13 E-05 D. Gross Alpha Ci 0.00 E+00 0.00 E400 4, Tritium A. Total Release Ci 8.08 E-01 5.69 E-04 3.00 E401 B. Average Release Rate for Period pCi/sec 1.04 E-01 7.24 E-05 C. Percent of Technical Specification Limit See Footnote Below The "Percent of Technical Specification Limit" applies to Iodines, Tritium, and Particulates combined. The value for Iodines and Tritium is included in the Particulate summation.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1B : GASEOUS EFFLUENTS ELEVATED RELEASES All releases at Shearon Harris are made as ground releases.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1C : GASEOUS EFFI,UENTS GROUND LEVEL REIEASES
- 1. Fission and Activation Gases Continuous Mode ~ Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 Ar-41 Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD 1.88 E-01 1.01 E-01 Kr-85m Ci 1.90 E+00 6.02 E+00 5.04 E-04 < LLD Kr-87 Ci 6.34 E-01 2.01 E+00 < LLD < LLD Kr-88 Ci 3.17 E+00 1.00 E+01 2.61 E-04 < LLD Xe-131m Ci < LLD < LLD 4.52 E-03 5.70 E-04 Xe-133 Ci 7.61 E+01 2.41 E+02 7.09 E-01 1.62 E-01 Xe-133m Ci 1.27 E+00 4.01 E+00 7.28 E-03 2.16 E-03 Xe-135 Ci 4.44 E+00 1.40 E+01 1.71 E-02 6.25 E-04 Xe-135m Ci < LLD < LLD < LLD 2.41 E-05 Xe-138 Ci 6,34 E-01 2,01 E+00 < LLD < LLD Ci 8.82 E+01 2.79 E+02 9.27 E-01 2.66 E-01 Noble Gas quantities apportioned as per GALE code.
- 2. Iodines Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 I-131 Ci < LLD < LID < LLD < LLD I-133 Ci < LLD < LLD < ILD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < ILD 2/5
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1C (Continued): GASEOUS EFFLUENTS GROUND LEVEL RELEASES
- 3. Particulates Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 Cr-51 Ci < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD Fe-59 Ci < LID < LLD < LLD < LLD Co-58 Ci < LLD 4,14 E-06 < LLD < LLD Co-60 Ci 2.72 E-05 < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LID < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Total Ci 2.72 E-05 4.14 E-06 < LLD < LLD Gross Alpha Ci < LLD < LLD < LLD < LLD
- 4. Tritium Continuous Mode Batch Mode Nuclide Units Quarter Quarter Quarter Quarter Released 1 2 1 2 H-3 Ci 8.08 E-01 5.69 E-04 < LLD LLD 2/6
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A: LIQUID EFFLUENTS - SUh91ATION OF ALL RELEASES Units Quarter Quarter Est, Total 1 2 Error X Fission k Activation Products A. Total Release (not including tritium, gases, or alpha) Ci 4.00 E-01 1.66 E-01 3.50 E+01 Average Diluted Concentration during Period pCi/ml 6,61 E-08 2.98 E-08 C. Percent of Technical Specification Limit 1.06 E-01 1.39 E-01 2 ~ Tritium A. Total Release Ci 1.39 E+02 8.85 E+01 3.50 E+01 B. Average Diluted Concentration during Period pCi/ml 2.30 E-05 1.59 E-05 C. Percent of Technical Specification Limit 7.68 E-01 5.30 E-01 Dissolved and Entrained Gases A. Total Release Ci 3.02 E-03 1.47 E-03 3.50 E+01 B, Average Diluted Concentration during Period pCi/ml 4.99 E-10 2.64 E-10 C. Percent of Technical Specification Limit 2.50 E-04 1.32 E-04
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A : IIQUID EFFLUENTS SUhMATION OF ALL RELEASES Quarter Quarter Est.Total
- 5. Volume of effluent released Units 1 2 Error X prior to dilution A. Batch Releases liters 3.10 E+06 4.50 E+06 1.00 E+01 B. Continuous Releases liters 2.53 E+07 3.45 E+07 1.00 E+01
- 6. Volume of Dilution water used during period liters 6.02 E+09 5.53 E+09 1.00 E+01
- 7. Total Volume Released (Releases + Dilution) liters 6.05 E+09 5.57 E+09 1.00 E+01 2/8
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B : LIQUID EFFLUENTS
- 1. Fission and Activation Products Continuous Mode Batch Mode Nuclides Quarter Quarter Quarter Quarter Released Units 1 2 1 2 Na-24 Ci < LLD < LLD < LLD 3.52 E-05 Cr-51 Ci < LLD < LLD < LLD 4.86 E-03 Mn-54 Ci < LLD < LLD 9.87 E-04 9.03 E-04 Fe-55 Ci < LLD < LLD 4.14 E-03 2.77 E-03 Co-57 Ci < LLD < LLD 1.02 E-03 2.68 E-04 Co-58 Ci < LLD < LLD 3.53 E-01 1.07 E-01 Fe-59 Ci < LLD < LLD 2.38 E-05 2.76 E-03 Co-60 Ci < LLD < LLD 2.72 E-02 1.37 E-02 Zn-65 Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LID < LLD < LLD Zr-95 Ci < LLD < LLD < LLD 1.85 E-04 Nb-95 Ci < LLD < LLD < LLD 3.28 E-04 Nb-97 Ci < LLD < LLD < ILD 1.10 E-05 Mo-99 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD Ag-llOm Ci < LLD < LLD < LLD 3.12 E-04 Sn-113 Ci < LLD < LLD < LLD 1.19 E-04 Sb-122 Ci < LLD < LLD 1.89 E-04 < LLD Sb-124 Ci < LLD < ILD 2.71 E-04 1.50 E-03 Sb-125 Ci < LLD < LLD 1.25 E-02 2.48 E-02 I -131 Ci < LLD < LLD 4,15 E-04 1.24 E-03 Te-132 Ci < LLD < LLD 2.32 E-05 < LLD I -132 Ci < LLD < ILD 5.00 E-05 < LLD I -133 Ci < LLD < LLD E-05 '.87 4.54 E-05 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD 6.01 E-06 < LLD Cs-138 Ci < LLD < LLD < LLD 8,50 E-05 Ba-140 Ci < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-143 Ci < LLD < LLD 2.86 E-05 < LLD Ce-144 Ci < LLD < LLD < LLD 3.26 E-05 Pr-144 Ci < LLD < LLD < LLD 4.33 E-03 Hf-181 Ci LLD < LLD < LLD 3.34 E-05 Total Ci 6.40 E-02 1.69 E-01 4.00 E-01 1.66 E-01 2/9
1 Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table. 2B (Continued) : LIQUID EFFLUENTS
- 2. Tritium Continuous Mode Batch Mode Nuclides Quarter Quarter Quarter Quarter Released Units 1 2 1 2 H-3 Ci 6.40 E-02 1.69 E-01 1.39 E+02 8,83 E+01
- 3. Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1. 2 1 2 Kr-85m Ci < LLD LLD 2.14 E-05 < LLD Kr-87 Ci < LLD < LLD 1.31 E-05 < LLD Xe-133 Ci < LLD < LLD 2.95 E-03 1.43 E-03 Xe-133m Ci < LLD < LLD < LLD 1.84 E-05 Xe-135 Ci < LLD < LLD 3,46 E-05 2.53 E-05 Total Ci < LLD < LLD 3.02 E-03 1.47 E-03
- 4. Gross Alpha Continuous Mode Batch Mode Nuclide Quarter Quarter Quarter Quarter Released Units 1 2 1 2 Gross Alpha Ci < ILD < LLD < LLD < LLD 2/10
I 1
Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
A. Type of Waste Spent Resin, filter sludge, evaporator bottoms, etc.
Number of Shipments 3 Activity Shipped 2.44 E+01 Ci Estimated Total Error 1.00 E+01 X Quantity Shipped 1.61 E+01 m Solidification Agent N/A Container Type Strong Tight Package Shipment Form Dewatered
- b. Dry Compressible Waste, Contaminated Equipment, etc, (DAW)
Number of Shipments 8 Activity Shipped 3.14 E+00 Ci Estimated Total Error 1.00 E+01 X Quantity Shipped 2.50 E+01 m Solidification Agent N/A Container Type Strong Tight Package Shipment Form Dewatered
- c. Irradiated Components, Control rods, etc.
No waste of this type shipped
- d. Other (Describe)
No waste of this type shipped
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h Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
B. Estimate of Major Nuclide Composition (by type of waste)
- a. Spent Resin, filter sludge, evaporator bottoms, etc.
Percent Total Activity Nuclide Composition Ci H-3 5.27 E-01 1.29 E-01 C -14 5.60 E-02 1.37 E-02 Mn-54 2.90 E+00 7.08 E-01 Fe-55 6.58 E+01 1.61 E+01 Co-58 9.45 E+00 2.31 E+00 Co-60 1.08 E+01 2.63 E+00 Ni-63 1.02 E+01 2.49 E+00 Cs-137 2.94 E-01 7.18 E-02
- b. Dry Compressible Waste, Contaminated Equipment, etc. (DAW)
Percent Total Activity Nuclide Composition Ci H - 3 3.88 E-01 1.22 E-02 C -14 2.07 E-02 6.50 E-04 Fe-55 8.38 E+01 2.63,E+00 Co-58 1.55 E+00 4,87 E-02 Co-60 1.09 E+01 3.42 E-01 Ni-59 8.11 E-01 2.54 E-02 Ni-63 1.06 E+00 3.33 E-02 Zr-95 1.45 E+00 4.54 E-02 ce Irradiated Components, Control rods, etc.
No waste of this type shipped dO Other (Describe)
No waste of this type shipped 2/12
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
C. Solid Waste Disposal Number of Shipments ~ 11 Mode of Transportation Truck Destination Barnwell, S.C.
All three of the type 1.A.a shipments were made from the Harris site. All eight of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
- 2. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B )
A. Type of Waste
- a. Spent Resin, filter sludge, evaporator bottoms, etc.
Number of Shipments 1 Activity Shipped 1.10 E+02 Ci Estimated Total Error 1.00 E+01 X Quantity Shipped 3.85 E+00 m Solidification Agent N/A Container Type NRC Approved Package Shipment Form Dewatered
- b. Dry Compressible Waste, Contaminated Equipment, etc. (DAW)
No waste of this type shipped.
ce Irradiated Components, Control rods, etc.
No waste of this type shipped Other (Describe)
No waste of this type shipped 2/14
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
- 2. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B )
B. Estimate of Major Nuclide Composition (by type of waste)
- a. Spent Resin, filter sludge, evaporator bottoms, etc.
Percent ~ Total Activity Nuclide Composition Ci C -14 1.30 E-01 1.43 E-01 Nn-54 1.07 E+01 1.18 E+01 Fe-55 1.24 E+01 1.36 E+01 Co-58 4.34 E+01 4.77 E+01 Co-60 1.68 E+01 1.85 E+01 Ni-63 1.52 E+01 1.67 E+Ol Sb-125 3.65 E-01 4.02 E-01 Zn-65 1.98 E-01 2.18 E-01 Cs-134 3.45 E-01 3.80 E-01 Cs-137 4.00 E-01 4.40 E-01 Ce-144 1,18 E-01 1.30 E-01
- b. Dry Compressible Waste, Contaminated Equipment, etc. (DAW)
No waste of this type shipped co Irradiated Components, Control rods, etc.
No waste of this type shipped dt Other (Describe)
No waste of this type shipped C. Solid Waste Disposal Number of Shipments 1 Node of Transportation Truck Destination Barnwell, S.C.
3~ Solid Waste Shipped for Burial or Disposal ( WASTE CLASS C )
No waste of this type was shipped during this Report period.
4, Irradiated Fuel Shipments (Disposition)
No irradiated fuel was shipped during this Report period.
~ Only nuclides with > 0.1X composition are listed.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 3 : Changes to Process Control Program (PCP)
Technical Specification 6.13 No changes were made to the PCP during this Report period.
I Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 4 : Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specification 6.14 No changes were made to the Offsite Dose Calculation Manual (ODCM) during the Report period.
As a result of the 1991 Land Use Census, Table 3.2-2, "Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant", will be changed. These changes are shown in Appendix 5, and will be included in the next Report, after approval and incorporation into the ODCM.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix. 5 : Changes to the Environmental Monitoring Program Enclosure 1 : Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.1.c No changes were made to the radiological Environmental Monitoring Program during the Report period.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications 3.12.2.a 3.12.2.b A Land Use Census was performed in June of 1991. Several changes have occurred in the locations of the nearest resident, garden, and meat animal. None of the changes would necessitate a change in the SHNPP Environmental Monitoring program.
These changes will be included as Changes to the ODCM in the next Report, Table 1 summarizes these locations and the changes. Table 2 lists the kinds of meat animal at each meat animal location.
Table 1 Distance to the Nearest Special Locations for the Harris Nuclear Plant (Miles)~
(Comparison of 1990/1991 Data)
Residence Milk Animal Garden Meat Animal Exclusion Sector Boundary 1990 1991 1990 1991 1990 1991 1990 1991 1.32 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 NNE l. 33 1.8 1.8 4.6 1.7 1.7 3.5 3.5 NE 1 ~ 33 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1. 33 2.0 3.6 3.6 3.8 1 ~ 33 1.9 1.9 4.7 4.7 2.2 2.2 ESE l. 33 2.7 2.7 2.7 4,4 4,4 4,4 SE 1.33 4.3 4.3 4~3 4,4 4.3 4.3 SSE 1. 33 4,4 4,4 4.6 1.36 SSW 1. 33 3.9 3.9 3.9 3.9 SW 1. 33 2.8 2.8 2.8 2.8 WSW 1 '3 4.3 4.3 4.3 4.3 4.3 1.33 2.8 2.8 2.9 2.9 2.9 2.9 WNW 1.33 2.1 2.1 2.1 2.9 3.6 NW 1. 26 2.1 2 ' 3.8 3.8 3.8 3,8 NNW 1.26 1.5 1.5 1.7 1.7 1.7 1.7 4 Distance estimates are + 0.1 miles except at the exclusion boundary.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications 3.12.2.a 3.12.2.b Table 2 Meat Animal Type at Nearest Location to SHNPP
( by Sector )
Sector Distance Owner (miles) Meat Type(s) 2.2 Beef/Hogs/Chickens Goodwin, W.
NNE 3.5 Chickens Hudson, H.
NE 2.3 Beef/Chickens James Rest Home ENE 2.2 Chickens/Hogs Harris, H.
ESE 4,4 Chickens McLean, E.
SE 4.3 Chickens Taylor, M.
SSE SSW WSW 2.9 Chickens Hill) A.
WNW NW 3.8 Hogs Stone, D.
NNW 1.7 Beef Godwin> W.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1 : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service > 30 Days During the Report Period Days Effluent Monitor , Inop Reason for Inoperability REN-01SW-3500B 32 The Service Water system was drained to Normal Service Water perform a modification to the system.
Return from RAB During this time, the service water header was drained, so there was no process flow from which the monitor could obtain a sample.
REN-01TD-3528 40 Monitor was inoperable due to a bus Turbine Building Floor outage and subsequently, a bad flow Drain Effluent Line switch, 69 Process loop seal was intermittently draining, causing repeated loss of sample flow alarms. Check valves for T.B. sumps were disassembled and cleaned. There was no problem with the monitor itself.
REM-01WL-3540 144 High sample chamber background. The Treated Laundry 5, Hot chamber was not deconned because no Shower Tank Monitor releases were being made via this pathway.
REM-21WL-3541 32 Sample lines had to be removed to Waste Monitor Tank/Waste install a modification to the Service Evap. Condensate Tank Water system.
Discharge Monitor REN-21WS-3542 85 The flow switch was sticking, so a Secondary Waste Sample modification was implemented to replace Tank Monitor the flow switch with one less prone to sticking.
38 Nonitor had a bad solenoid valve. The valve was replaced, but the monitor could not be made operable because there was no service water for the monitor's heat exchanger due to the service water outage,
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i' Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 1 : Inoperability of Liquid Effluent Monitors Technical Specification 3.3,3.10, Action b Monitors Out-of-Service > 30 Days During the Report Period Days Effluent Monitor Inop Reason for Inoperability FT-01MP-1968A 41 Flow transmitter was operable, however, Cooling Tower Make-up a modification to the trip logic was Bypass being installed (PCR-4446). Plant procedures require the instrument to be inoperable until the modification is completed.
FT-01MP-1968B 37 Monitor was considered inoperable Cooling Tower Make-up because of indication drifts. Monitor Bypass Flow Monitor was tested and found to be satisfactory.
41 Flow transmitter was operable, however, a modification to the trip logic was being installed (PCR-4446). Plant procedures require the instrument to be inoperable until the modification is completed.
FT-21WL-6119 181 Monitor has an improper range for the Waste Monitor Tank/waste releases that occur through this Evaporator Condensate pathway. A modification is being Tank Discharge Flow Rate performed to correct the Monitor orifice/transmitter sizing.
FT-41WL-6193 181 Monitor has an improper range for the Treated Laundry and Hot releases that occur through this Shower Tanks Discharge pathway. A modification is being Flow rate Monitor performed to correct the orifice/transmitter sizing.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3,3.3.11, Action a Monitors Out-of-Service > 30 Days During the Report Period I
Days Effluent Monitor Inop Reason for Inoperability PNL-1AV-3509 and 181 Problems with calibration of flow PNL-1AV-3509-1 measurement system resulting in RAB Vent Stack 1 Flow discrepancies between actual and Rate Monitor expected flow rates. Modification initiated to correct.
RM-01TV-3536-1 181 Moisture interferences with the flow Turbine Building Vent measurement system resulting in Stack 3A Flow Rate discrepancies between actual and Monitor expected flow rates. Modification initiated to correct.
PNL-1WV-3536 and 181 Problems with calibration of flow PNL-1WV-3546-1 measurement system resulting in Waste Processing discrepancies between actual and Building Vent Stack 5 expected flow rates. Modification Flow Rate Monitor initiated to correct.
PNL-1WV-3547 & and 181 Problems with calibration of flow PNL-1WV-3547-1 measurement system resulting in Waste Processing discrepancies between actual and Building Vent Stack 5A expected flow rates. Modification Flow Rate Monitor initiated to correct.
RM-41WG-3546-1 36 During a 18 month channel calibration, WPB Vent Stack 5 WRGM parts were found to be bad. One part (1) Noble Gas Monitor was obsolete, so an engineering (2) Iodine Sampler evaluation had to be performed to (3) Particulate Sampler specify a replacement. Also, a part was not in stock and had to be ordered.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service > 30 Days During the Report Period Days Effluent Monitor Inop Reason for Inoperability OAI-21WG-1101 181 Monitor does not agree with analyzed Waste Gas Compressor samples. Modification has been Discharge Oxygen Monitor initiated to improve the reliability of the monitor.
HAIC-21WG-1118A 181 Modification to improve the reliability Waste Gas Recombiner "A" of the monitor has been initiated.
Outlet Gas Hydrogen During this period, the "B" channel Monitor monitor was operable.
OARC-21WG-1119A 181 Modification to improve the reliability Waste Gas Recombiner "A" of the monitor has been initiated.
Outlet Gas Oxygen Monitor OARC-21WG-1119B 75 Numerous failure (analyzer cell, logic Waste Gas Recombiner "B" card, amplifier) encountered during Outlet Gas Oxygen maintenance and testing.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 3 : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a There were no unprotected outdoor tanks at SHNPP during this Report period.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.
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Semiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 7 : Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste system during this Report period.
Semiannual Radioactive Effluent Release Report, January 1, 1991 to June 30, 1991 Appendix 8 Amendment to the January 1, 1990 to June 30, 1990 Semiannual Radioactive Effl'uent Release Report Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Vesta Disposal Report Enclosure 3 : Solid 'Vaste Disposal Table 3 : SOLID VASTE AND IRRADIATED FUEL SHIPHENTS
- 1. Solid Vaste Shipped for Burial or Disposal ( VASTE CLASS A )
6 month Est. Total Solid. Cont. No.
A. Type of waste Units Period Error (X) Agent Type Form Ship a~ Spent Resin, filter m3 '.53 E+00 1.00 8+01 N/A STP D 1 sludge, evaporator bottoms, etc, Ci 3.35 8+00
- b. Dry Compressible m3 2.21 E+01 1.00 E+01 N/A STP D 14
'Vesta, contaminated equipment, etc. Ci 1.58 8+00
- c. Irradiated Components, m3 No waste of this type shipped.
Control rods, etc. Ci
- d. Other (Describe) m3 No waste of this type shipped.
Ci,
- STP - Strong Tight Package
- S - Solidified D - Dewatered
C I
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'emiannual Radioactive Effluent Release Report January 1, 1991 to June 30, 1991 Appendix 8 Amendment to the January 1, 1990 to June 30, 1990 Semiannual Radioactive Effluent Release Report Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Pro)ect (SHNPP) Operating License No. NPF-63. It provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS).
The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3, 1987. This report covers the period from January 1, 1990 to June 30, 1990. During this period, the plant was in Cycle 3 operation.
Discussion Appendices 1 and 2:
The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev. 1) Appendix B formats As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CPR61 class, type of container and solidification agent or absorbent.
Except for continuous noble gas releases, liquid and gaseous average concentrations (uCi/cc) and total-curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD) tables show a typical sensitivity level for detection of the nuclide.
Continuous noble gas effluent activities were based on hourly average stack monitor readings (in uci/cc) and stack flow rate estimates based on design fan flow rates. No specific noble gas nuclides were identified in any of the stack gas grab samples taken for characterixing continuous gaseous releases. Therefore, the total noble gas activities are based on stack monitor readings and apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCH. Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.
No activity above background was detected in any continuous liquid release pathway. Therefore, the reported activities are the summation of nuclides in batch releases only.
A total of 27.61 m 3 of solid waste, containing 4 '43 Ci of radioact)vity, was shipped for burial during this Report period, compared with 101.11 m and 20.86 Ci shipped during the previous Report period.
Two unplanned gaseous releases occurred during this Report period. The first release occurred because of an improper valve line-up in the waste gas system. Approximately 2.38 Ci of noble gases were released. Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CFR50 (total dose) 8/2
j/9103050237 Carolina Power & Light Shearon Harris Nuclear Power Plant License No. NPF-063 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT July 1, 1990 to December 31, 1990 Prepared by:
Jr. Specialist E&C Reviewed by: )
Manager E&RC Supp rt Reviewed by:
Manager Environmental & adiation Control Approved by:
General Manager Harris Plant
Y l
I'
Table of Contents Page No.
Introduction Discussion Appendix 1. Supplemental Information Appendix 2. Effluent and Waste Disposal Report 1.. Lover Limits of Detection (LLD's) 2/1
- 2. Effluents Released 2/3
- 3. Solid Paste Disposal 2/11 Appendix 3. Changes to Process Control Program (PLP) .3/1 Appendix 4. Changes to Offsite Dose Calculation Manual (ODCM)
- 1. Revision 3.0, Change 2 4/1
- 2. Revision 3.0, Change 3 4/2
- 3. Changed ODCM pages for Revision 3.0, Change 2 4/6 4, Changed ODCM pages'or Revision 3.0, Change 3 4/9 Appendix 5. Changes to the Environmental Monitoring Program
- 1. Environmental Monitoring Program 5/1 2.'and Use Census 5/2 Appendix 6. Additional Technical Specification Responsibilities
- 1. Inoperability of Liquid Effluent Monitors 6/1
- 2. Inoperability of Gaseous Effluent Monitors 6/2
- 3. Unprotected Outdoor Tanks Exceeding Limits 6/4 4, Gas Storage Tanks Exceeding Limits 6/5 Appendix 7. Major Modifications to Radwaste System 7/1 Appendix 8. Meteorological Data 8/1 Appendix 9. Assessment of Radiation Doses for Calendar Year 1990
- 1. Population Doses outside Site B'oundary due to Effluent Releases 9/1
- 2. Doses to the General Public Due to Activities Inside the Site Boundary 9/2 3 ~ Doses to the Likely Most Exposed Member of the Public 9/4 4, Major Assumptions used to Calculate Radiation Doses 9/8
E I
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with (SHNPP) Operating License No. NPF-63 't Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Plant provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS).
The Shearon Harris Nuclear Power Plant achieved initial,criticality on January 3, 1987. This report covers the period from July 1, 1990 to December 31, 1990. During this period, 'the plant was in Cycle 3 operation. This report also covers the period from January 1, 1990 to December 31, 1990 for meteorology and dose accountability.
Discussion Appendices 1 and 2:
The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev. 1) Appendix B format. As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container and solidification agent or absorbent.
Except for continuous noble gas releases, liquid and gaseous average concentrations'(uCi/cc) and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD) tables show a typical sensitivity level for detection of the nuclide.
Continuous noble gas effluent activities were based on hourly average stack monitor readings (in uCi'/cc) and stack flow rate estimates based on design fan flow rates. No specific noble gas nuclides were identified in any of the stack gas grab samples taken for characterizing continuous gaseous releases. Therefore, the total noble gas activities are based on stack monitor readings and apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM. Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.
On October 14, 1990, the plant experienced a minor ( 50 gpd max) primary-to-secondary tube leak, which continued until the plant shut down in mid-November to repair the leak. This resulted in H-3 activity in a continuous liquid release pathway.
. A total of 49.8 m of solid waste, containing 57.57 Ci of radioac)ivity, was shipped for burial during this Report period, compared with 59.3 m and 4.57 Ci shipped during the previous Report period.
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Discussion (continued)
Appendix 3:
No changes to the Process Control Program (PCP) were made during this Report period.
Appendix 4:
ODCM Revision 3.0, Change 2 and Revision 3.0, Change 3 were approved by the PNSC during the Report period. Revision 3.0, Change 2 includes the results of the 1990 Land Use Census, which was performed in June, 1990.
Revision 3.0, Change 3 was made to allow for continuous releases of liquid effluents containing tritium only.
Appendix 5:
One change was made to the Environmental Monitoring Program during the Report period, the loss of a dairy monitoring station. No Changes were made to the Land Use Census during this Report period.
Appendix 6:
All effluent monitor inoperabilities great'er than 30 days are given along with a brief explanation. During these periods, compensatory sampling and flow rate estimations consistent with Technical Specification requirements have provided accountability and control of effluents.
No unprotected outdoor tank or gas storage tank exceeded Tech Spec limits during this Report period.
Appendix 7:
No major modifications were made to the Radwaste System during this Report period.
Appendix 8:
The 1990 annual summary of meteorological data is available to the NRC upon request. This summary is also used in the NRC approved program ZOQDOQ, which is used in the Appendix 9 dose calculations.
Appendix 9:
The effluent quantities reported for both semiannual periods in 1990 were combined for determining the annual dose impact from plant operations. The doses were calculated by the programs LADTAP II (for liquid effluents) and GASPAR (for gaseous effluents). GASPAR and LADTAP II are NRC approved programs for implementing Reg. Guide 1.109 methodology, which is also the basis of the ODCM calculations. Vhen appropriate, the doses are also broken down by age group (adult, teen, etc.) and organ (bone, thyroid, etc.).
Semiannual Radioactive Effluent Release Report July 1, 1990-to December 31, 1990 Discussion (continued)
Appendix 9 (Continued)
Enclosure 1 shows the integrated population doses within the 50-mile ingestion zone (in man-rem) due to liquid and gaseous releases for the various
'applicable pathways. Also, the tritium contribution to the hydrosphere is shown.
Enclosure 2 shows the doses (in mrem/yr) to a hypothetical individual member of the general public due to activities inside the site boundary. Since portions of Harris lake are within the site boundary, these doses result from the recreational usage of the lake. The highest dose received by that individual corresponds to 0.12X of the applicable dose limit. The corresponding value for CY 1989 was 0.29X.
Enclosure 3 shows the hypothetical doses (in mrem/yr) for the "Likely Most Exposed= Individual". For the liquid pathways, this calculation assumes that Lillington, the closest downstream public water supply, is the source of drinking water and Harris Lake is the source of all other liquid exposure. For liquid effluents, the highest whole body dose corresponds to 3.20X of the applicable dose limit, and the highest organ dose corresponds to 1.18X of the applicable dose limit. Corresponding values for CY 1989 were 0.90/ and 0.29%%u, respectively.
For the airborne pathways, the gaseous dose considers two types of individuals: (1) the "Maximum Hypothetical Individual", who resides at the site boundary in the sector of highest plume exposure, and (2), the "Maximum Real Individual" who, based on the Land Use Census, had the highest combined dose from his actual exposure pathways, e.g. plume, ground, etc. In 1990, the "Maximum Real Individu'al" is located at 2897 meters ( 1.8 miles) in the NNE sector, the same as in 1989.
For the "Maximum Hypothetical Individual", the highest whole body dose corresponds to 0.53X of the applicable dose limit, and the highest organ dose corresponds to 0.11/ of the applicable dose limit. Beta and gamma annual air doses were 0.88X and 1.20X of their respective limits. Corresponding values for CY 1989 were 0.02X, 0.01X, 1.41X, and 1.95X, respectively.
For the "Maximum Real Individual", the highest whole body dose corresponds to 0.14X of the applicable dose limit, and the highest organ dose corresponds to 0.29X of the applicable dose limit. Beta and gamma annual air doses were 0.23X and 0.31X of their respective limits. Corresponding values for CY 1989 were 0.02X, 0.01%%u, 0.43/, and 0.59X, respectively.
Enclosure 4 lists the major assumptions associated w'ith the liquid and gaseous effluent doses. Where available, site specific information is used to derive these values. In other cases, parameter values or derj.vations are as given in Reg. Guide 1.109,
1 Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 1: Supplemental Information
- 1. Regulatory Limits A. Fission and activation gases (1) Calendar Quarter
- a. 5 mrad gamma
- b. 10 mead beta (2) Calendar Year
- a. 10 mrad gamma
- b. 20 mrad beta B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1) Calendar Quarter
- a. 7.5 mrem to any organ (2) Calendar Year
- a. 15 mrem to any organ C. Liquid effluents (1) Calendar Quarter
- a. 1.5 mrem to total body
- b. 5 mrem to any organ (2) Calendar Year
- a. 3 mrem to total body
- b. 10 mrem to any organ
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 1'(Continued): Supplemental Information
- 2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and activation gases (1) 500 mrem/year to total body (2) 3000 mrem/year to the skin B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.
1500 mrem/year to any organ C. Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the MPC shall be equal to 2.0E-4 uCi/ml.
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Measurements by continuous monitors 'of activity concentrations times total stack flow, and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides in representative grab samples.
B. Iodines Continuous charcoal cartridge sampling and analysis by gamma spectroscopy for specific radionuclides times total stack flow.
C. Particulates Continuous particulate sampling and analysis by gamma spectroscopy, alpha counting and radiochemical analysis for specific radionuclides times total stack flow.
D. Liquid Effluents Pre-release representative sampling and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides times total release volume.
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 1 (Continued): Supplemental Information
- 4. Batch Releases A. Liquid (1) Number of batch releases: 1.74 E+02 (2) Total time period for batch releases: 9.67 E+04 min.
(3) Maximum time for a batch release: 1.11 E+03 min.
(4) Average time for a batch release: 5.56 E+02 min.
(5) Minimum time for a batch release: . 4.00 E+00 min.
(6) Average stream flow during periods of release: 9.93 E+03 gpm B. Gaseous (1) Number of batch releases: 4.00 E+00 (2) Total time period for batch releases: 7.49 E+03 min.
(3) Maximum time for a batch release: 3.77 E+03 min.
(4) Average time for a batch release: 1.87 E+02 min, (5) Minimum time for a batch release: 2.24 E+02 min.
- 5. Abnormal Releases A. Liquid No abnormal liquid releases were made in the period.
B. Gaseous No abnormal gaseous releases were made in the period.
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2: Effluent and Waste Disposal Report Enclosure 1 : LOWER LIMITS OF DETECTION (LLD)
H-3 1.01 E-08 Ar-41 4.42 E-08 Cr-51 1.08 E-13 Mn-54 1.56 E-14 Co-58 1.54 E-14 Fe-59 3.72 E-14 Co-60 3.62 E-14 Zn-65 5.94 E-14 Kr-85 8.56 E-06 Kr-85m 2.17 E-08 Kr-87 3.82 E-08 Kr-88 2.63 E-08 Sr-89 7.91 E-16 Sr-90 4.99 E-16 Nb-95 1.43 E-14 Mo-99 1.09 E-13 I -131 1.19 E-14 Xe-131m 7.78 E-07 I -132 3.84 E-14 I -133 1.82 E-13 Xe-133 4.48 E-08 Xe-133m 1.60 E-07 Cs-134 1.12 E-14 I -135 9.64 E-10 Xe-135 1.93 E-08 Xe-135m 4.88 E-07 Cs-137 1.42 E-14 Xe-138 9.68 E-07 Ba-140 3.81 E-14 La-140 4.27 E-14 Ce-141 1.70 E-14 Ce-144 7.48 E-14 Gross Alpha 4.28 E-15
0 Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, '1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1 : LOWER LIMITS OF DETECTION (LLD)
H 3 3.22 E-06 Be- 7 9.82 E-14 Na- 24 4.63 E-08 Ar- 41 6.61 E-08 Cr- 51 2.99 E-07 Mn- 54 2.86 E-08 Fe- 55 1.37 E-07 Co- 57 1.69 E-08 Co- 58 2.80 E-08 Fe- 59 6.47 E-08 Co- 60 4.31 E-08 Zn- 65 7.28 E-08 Kr- 85m 3.78 E-08 Sr- 89 1.57 E-09 Sr- 90 1.43 E-09 Zr- 95 4.72 E-08 Nb- 95 5.29 E-08 Nb- 97 4.19 E-08 Mo- 99 2.02 E-07 Tc- 99m 1.65 E-08 Ru-103 2.25 E-14 Ag-110m 2.43 E-08 Sn-113 3.63 E-08 Sb-122 3.98 E-08 Sb-125 7.17 E-08 I -131 3.49 E-08 I -133 2.41 E-08 Xe-131m 1.51 E-06 Xe-133 9.45 E-08 Xe-133m 2.28 E-07 Xe-135 4.03 E-08 Cs-134 2.35 E-08 Cs-137 2.93 E-08 Cs-139 2.74 E-13 Ba-139 3.99 E-14 Ba-140 7.51 E-08 La-140 5.77 E-08 Ce-141 3.54 E-08 Ce-143 2.05 E-14 Ce-144 1.97 E-07 Pr-144 2.31 E-06 Hf-181 2.87 E-08 Gross Alpha 6.18 E-08 2/2
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A : GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Uni ts Quarter Quarter Est. Total 3 4 Error Fission & Activation Gases A. Total Release Ci 1.71 E+02 1.42 E+02 4.50 8+01 B. Average Release Rate for Period uCi/sec 2.15 8+01 1.79 E+01 C. Percent of Technical Specification Limit 4.99 E-01 5.35 8-01
A. Total Iodines Ci 0.00 8+00 0.00 E+00 2.00 E+01 B. Average Release Rate for Period uCi/sec 0.00 8+00 0.00 E+00 C. Percent of Technical Specification Limit See Footnote Below
- 3. Particulates A. Particulates with T1/2> 8 days Ci 1.49 8-05 3.65 8-05 2.00 E+01 B. Average Release Rate for Period uCi/sec 2.11 E-06 4.59 E-06 C. Percent of Technical Specification Limit 7.33 8-04 1.60 E-02 D. Gross Alpha Radioactivity Ci 0.00 E+00 1.04, E-07
- 4. Tritium ,
A. Total Release Ci 0.00 Ew00 1.56 8+00 3.00 E+01 B. Average Release-Rate for Period uCi/sec 0.00 8+00 1.96 E-01 C. Percent of Technical Specification Limit See Footnote Below The Percent of Technical Specification limit applies to Iodines, Tritium, and Particulates combined, and is calculated using ODCM default methodology and parameters. The value for Iodines and Tritium is included in the Particulates summation.
2/3
\
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste ~Disposal Report
- Enclosure 2 : Effluents Released Table 1B : GASEOUS EFFLUENTS ELEVATED RELEASES All releases at Shearon Harris are made as ground releases.
2/4
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31; 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1C : GASEOUS EFFLUENTS GROUND LEVEL RELEASES
- 1. Fission and Activation Gases Continuous Mode
- Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 3 4 3 4 H-3 Ci < LLD 1.56 E+00 < LLD < LLD Ar-41 Ci < LLD < LLD < LLD < LLD KI-85 Ci < LLD < LLD < LLD 4.19 E-02 Kr-85m Ci 3.69 E+00 2.87 Ew00 < LLD < L'LD Kr-87 Ci 1.23 E+00 9.58 E-01 < LLD < LLD Kr-88 Ci 6.15 E+00 4'.79 E+00 < LLD < LLD Xe-131m Ci < LLD < LLD < LLD 9.50 E-02 Xe-133 Ci 1.48 E+02 1.15 E+02 < LLD 8.54 E+00 Xe-133m Ci 2.46 8+00 1.92 E+00 < LLD 9.50 E-02 Xe-135 Ci 8.62 8+00 6.70 E+00 < LLD 2.26 E-03 Xe-135m Ci < LLD < LLD < LLD < LLD Xe-138 Ci 1.23 E+00 9.58 E-01 < LLD < LLD Total Ci 1.71 E+02 1.35 E+02 < LLD 8.77 E+00
- Noble Gas quantities apportioned as per GALE code.
- 2. Iodines Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 3 4 3 4 I-131 Ci < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD 2/5
Semiannual Radioactive Effluent Release Report July 1, 1990,to December 31, 1990 Appendix 2 (Continued): Effluent and Paste Disposal Report Enclosure 2 : Effluents Released Table 1C (Continued): GASEOUS EFFLUENTS GROUND LEVEL RELEASES
- 3. Particulates Continuous Mode Batch Mode Nuclides Uni ts Quarter Quarter Quarter Quarter Released 3 4 3 4 Cr-51 Ci < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD Fe-59 Cj < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD Co-60 Ci 1.49 E-05 3.65 E-05 < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD, Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Ba/La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Gross Alpha Ci < LLD 1.04 E-07 < LLD < LLD Total Ci 1.49 E-05 3.66 E-07 < LLD < LLD 2/6
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A : LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Uni ts Quarter Quarter Est. Total 3 4 Error
- 1. Fission & Activation Products A. Total Release (not including tritium, Ci 5.61 E-02 4.66 E-01 3.50 E+01 gases, or alpha)
B. Average Diluted Concentration during Period uCi/ml 1.49 E-08 7.40 E-08 C. Percent of Technical Specification Limit 3.46 E-02 3.28 E+00
- 2. Tritium A. Total Release Ci 9.39 E+01 4.28 E+02 3.50 E+01 B. Average Diluted
, Concentration during Period uCi/ml 2.49 E-05, 6.78 E-05 C. Percent of Technical Specification Limit 8.30 E-01 2.26 E+00
- 3. Dissolved and Entrained Gases A. Total Release Ci 3.01 E-04 4.26 E-03 3.50 E+01 B. Average Diluted Concentration during Period uCi/ml 7.99 E-11 6.77 E-10 C. Percent of Technical Specification Limit 3.99 E-05 3.38 E-04
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A : LIQUID EFPLUENTS SUMMATION OP ALL RELEASES Uni ts Quarter Quarter Est. Total 3 4 Error
- 5. Volume of water released prior to dilution A. Batch Release liters 2.72 E+06 8.54 E+06 1.00 E+01 B. Continuous Release liters 1.66 E+07 2.64 E+07 1.00 E+01
- 6. Volume of dilution water liters 3.75 E+09 6.26 E+09 1.00 E+01 used during period
- 7. Total Volume Released (Releases + Dilution) liters 3.77 E+09 6.29 E+09 2/8
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released Table 2B : LIQUID EFFLUENTS Fission and Activation Products Continuous Mode Batch Mode Nuclides Uni ts Quarter Quarter Quarter Quarter Released 3 4 3 4 H-3 Ci < LLD 9.84 E-01 9.39 E+01 4.27 E+02 Be- 7 Ci < LLD < LLD 4.16 E-05 < LLD Na-24 Ci < LLD < LLD < LLD 7.23 E-05 Cr-51 Ci < LLD < LLD < LLD 1.35 E-03 Mn-54 Ci < LLD < LLD 3.55 E-04 1.33 E-03 Fe-55 Ci < LLD < LLD 3.80 E-03 1.53 E-02 Co-57 Ci < LLD < LLD 9.09 E-05 6.81 E-04 Co-58 Ci < LLD < LLD 4.33 E-02 3.02 E-01 Fe-59 Ci < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD 6.76 E-03 1.11 E-01 Zn-65 Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Zr/Nb-95 Ci < LLD < LLD < LLD < LLD Nb-97 Ci < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD 5.19 E-05 Tc-99m Ci < LLD < LLD 1.39 E-05 1.84 E-04 Ru-103 Ci < LLD < LLD < LLD 4.75 E-05 Ag-110m Ci < LLD < LLD 3.05 E-05 < LLD Sn-113 Ci < LLD < LLD < LLD 4.88 E-05 Sb-122 Ci < LLD < LLD < LLD 1.29 E-04 Sb-125 Ci < LLD < LLD 1.59 E-03 2.57 E-02 I -131 Ci < LLD < LLD 1.72 E-04 1.72 E-03 Te-132 Ci < LLD < LLD < LLD 1.20 E-05 I -133 Ci < LLD < LLD < LLD 4.69 E-05 Cs-134 Ci < LLD < LLD < LLD 1.92 E-03 Cs-137 Ci < LLD < LLD 5.03 E-06 4.02 E-03 Cs-139 Ci < LLD < LLD < LLD 4.38 E-04 Ba 139 Ci < LLD < LLD < LLD 3.04 E-05 Ba/La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-143 Ci < LLD '
LLD 2.77 E-05 < LLD Ce-144 Ci. < LLD < LLD < LLD < LLD Pr-144 CI < LLD < LLD < LLD < LLD H f-'181 Ci < LLD < LLD < LLD < LLD Gross Alpha Ci < LLD < LLD < LLD < LLD Total Ci < LLD 9.84 E-01 9.40 E+01 4.27 E+02 2/9
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B (Continued) : L1:QUID EFFLUENTS
- 2. Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 3 4 3 4 Ar-41 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD '< LLD 8.13 E-06 Xe-131m Ci < LLD < LLD < LLD 3.60 E-05 Xe-133 Ci < LLD < LLD 2.41 E-04 4.18 E-03 Xe-133m Ci < LLD < LLD < LLD 2.41 E-05 Xe-135 Ci < LLD < LLD 6.07 E-05 1.23 E-05 Total Ci < LLD < LLD 3.01 E-04 4.26 E-03 2/10
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report, Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPHENTS
- 1. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )
6 month Est. Total Solid. Cont.'o.
A. Type of waste Units Period Error (%) Agent Type Form Ship
- a. Spent Resin, filter m3 8.00 E+00 1.00 E+01 Cement STP S/D 2 sludge, evaporator bottoms, etc. Ci 1.92 E+01
- b. Dry Compressible m3 3.80 E+01 1.00 E+01 NA STP D 31 Waste, contaminated equipment, etc. Ci 7.27 E+00
- c. Irradiated Components, m3 No waste of this type shipped.
Control rods, etc. Ci
- d. Other (Describe) m3 No waste of this type shipped.
Ci
- STP Strong Tight Package NRC NRC Approved Package
- S Solidified D Dewatered One of the type 1.A.a shipments consisted of solidified filter sludge. The other shipment consisted of dewatered resin.
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Vaste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
Estimate of Major Nuclide Composition (by type of waste)
Type of Percent Total Activity Waste Nuclide Composition Ci a H -3 7.86 E-02 1.51 E-02
'3
~
C -14 1 E-02 2.75 E-03 Mn-54 2.61 E+00 5.01 E-01 Co-58 1.23 E+00 2.36 E-01 Co-60 1.14 E+01 2.19 E+00 Fe-55 7.79 E+01 1.49 E+01 Ni-63 6.72 E+00 1.29 E+00
- b. H -3 3.43 E-01 2.50 E-02 C -14 2.90 E-02 2.11 E-03 Cr-51 4.83 E-02 3.51 E-03 Mn-54 1.09 E-01 7.90 E-03 Fe-55 9.02 E+01 6.56 E+00 Ni-59 9.13 E-02 6.64 E-03 Co-58 1.45 E+00 1.06 E-01 Co-60 6.53 E+00 4.75 E-01 Ni-63 1.03 E+00 7.51 E-02 Nb-95 6.80 E-03 4.95 E-04 Zr-95 1.66 E-01 1.21 E-02 Cs-137 4.45 E-03 3.24 E-04 Th-234 3.84 E-03 2.79 E-04 C~ No waste of this type shipped.
- d. No waste of this type shipped.
Solid Waste Disposal Number of Shipments
- 3.30 E+01 Mode of Transportation Truck Destination Barnwell, S;-C.
- 31 of these shipments (all type 1.A.b) were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee. The other 2 shipments (all type 1.A.a) were made from the Harris site.
2/12
I I~
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 2. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B )
6 month Est. Total Solid. Cont. No.
A. Type of waste Units Period Error (%) Agent Type Form Ship a ~ Spent Resin, filter m3 3.85 E+00 1.00 E+01 None NRC D 1 sludge, evaporator bottoms, etc. Ci 3.11 E+01
- b. Dry Compressible m3 No waste of this type shipped.
Waste, contaminated equipment, etc. Ci
- c. Irradiated Components, m3 No waste of this type shipped.
Control rods, etc. Ci
- d. Other (Describe) m3 No waste of this type shipped.
Ci
- STP Strong Tight Package NRC NRC Approved Package
- S Solidified D Dewatered 2/13
t 0
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FVEL SHIPMENTS (Continued)
B. Estimate of Major Nuclide Composition (by type of waste)
Type of Percent Total Activity Waste Nuclide Composition Ci at H -3 3.1.74-03 5.41 E-04 C -14 1.50 E-01 4.67 E-02 Mn-54 1.99 E+01 6.18 E+00 Fe-55 2.03 E+01 6.32 E+00 Co-58 4.79 E+00 1.49 E+00 Co-60 2.44 E+01 7.59 E+00 Ni-63 3.00 E+01 9.30 E+00.
Sr-90 3.44 E-02 1.07 E-02 Sb-125 3.76 E-01 1.17 E-01 Cs-137 8.49 E-02 2,64 E-.02 Pu-238 2.26 E-05 7.06 E-06 Pu-239/240 5.72 E-05 1.78 E-05 Am-241 1.22 E-05 3.81 E-06 Cm-243/244 8.45 E-06 2.63 E-06
- b. No waste of this type shipped.
- c. No waste of this type shipped.
- d. No waste of this type shipped.
C. Solid Waste Disposal Number of Shipments 1.00 E+00 Mode of Transportation Truck Destination Barnwell, S.C.
2/14
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
- 3. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS C )
No waste of this type was shipped during this Report period.
- 4. Irradiated Fuel Shipments (Disposition)
No irradiated fuel was shipped during this Report period.
2/15
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 3 : Changes to Process Control Program (PCP)
Technical Specification 6.13 No changes were made to the PCP during this Report period.'
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 4 : Changes to the Offsite Dose Calculation Manual (ODCM)
' Two changes Technical Specification 6.14 were made to the ODCM during the Report period, The first change, Revision 3.0, Change 2, was approved by the PNSC in September. The second change, Revision 3.0, Change 3 was approved by the PNSC in November: A description of the changes follows, and the changed pages are included in this appendix.
Revision 3, Change 2 incorporates the results of the 1990 Land Use Census, which was performed in June of 1990 and deletes a sample location from the environmental monitoring program.
Page 3-18, Table 3.2-2; DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POVER PLANT (MILES)
Revised as a result of the 1990 land use census.
2~ Page 4-12, Table 4.1; RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Page 4-20, Figure 4.1-5 These two item were revised because one of the dairies in the HNP Radiological Monitoring Program has gone out of business (See Appendix 5). No other dairy is available as a substitute for milk sampling. This sample location (Sample Number 19) will remain available as a TLD monitoring station.
Li Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 4 (Continued) : Changes to the Offsite Dose Calculation Manual (ODCH)
Technical Specification 6.14 Revision 3.0, Change 3 was made after the primary-to-secondary leak occurred, and was made to support the release of tritium contaminated water through the Secondary Waste pathway in the continuous. mode, along with providing clarifications in several sections.
Page 2-1, Section 2.0 4th Paragraph Change the sentence from:
"The turbine building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines for batch releases with low probability of radioactive contamination."
to:
"The turbine building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines with low probability of radioactive contamination."
This change was made to reflect the fact that the turbine building floor drains and the outside tank area drains are not processed in a batch mode.
- 2. Page 2-1a, Section 2.0 5th Paragraph New paragraph This paragraph was added to clarify monitor response and limitations of response to radioactivity.
Page 2-3, Section 2.1.1 Page 2-3a, Section 2.1.1 Added the definition of D 0 g, D
0 comp, and D0 t Changed the formula by adding C to the numerator. Adding this factor will reduce the dilution available for H-3 in a batch release to compensate for possible releases from the waste neutralization system. This change will reduce the maximum release rate slightly.
4/2
Semiannual Radioactive Effluent Release Report 1
1 July 1, 1990 to December 31, 1990 Appendix 4 (Continued) : Changes to the Offsite Dose Calculation Manual (ODCM)
- 4. Page 2-15, Section 2.1.3, Item 2 Add these two sentences: "Tritium is expected to be detected in this pathway from sources such as background from the lake or secondary activity. Tritium activity will be administratively controlled to limit the activity at the release point."
These sentences were added to clarify that detecting tritium is a normal occurrence. It also acknowledges that tritium is not seen by the release monitor, so the levels will be administratively controlled to prevent any release limits from being exceeded.
Change the next sentence from:
"Because no radioactivity is normally expected in this path, the set points for the radioactivity are determined with Equation 2.1-15 and 2.1-16."
to:
"Because no other radioactivity is normally expected in this path, the set points for the turbine building drain monitor are determined with Equation 2.1-15 and 2.1-16."
"Other" was added to clarify that tritium is an expected item in this release pathway. "Radioactivity" was changed for clarity.
- 5. Page 2-17, Section 2.2.1 Fk Definition Change the sentence "...to the product of the dilution volume..." to
"...to the product of the diluted volume...".
This was changed to clarify that the volume being discussed is the combined volume of the effluent and the dilution volume.
- 6. Page 2-17, Section 2.2.1 Fk Formula Added the Vk term to the bottom part of the equation This was changed to support the definition in 5 above.
7 ~ Page 2-17, Section 2.2.1 Last Paragraph Sentences were added to the paragraph to clarify accountability and cumulation of dose as it release to the Turbine Building Floor Drains release pathway.
4/3
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 4 (Continued) : Changes to the Offsite Dose Calculation Manual (ODCM)
- 8. Page 2-18, Section 2.2.1 Definition of D w
Change the definition of D w
Dilution factor for the near field area within one-quarter mile of the release point to the closest potable water inlet for the adult water consumption pathway. The factor is calculated for uptake at the municipal water facility at Lillington, North Carolina.
Cape Fear River Flow (gpm)
Maximum Effluent Release Rate (gpm)
- The Cape Fear River flow is assumed to be 2790 gpm. This is a conservative value based on minimum flow rates for the Cape Fear River.
- The Maximum Effluent Release Rate is the sum of the release rate pathways. It assumes simultaneous releases of the following:
For All Isotopes except Tritium :
100 gpm Treated Laundry & Hot Shower Tank Batch 100 gpm Secondary Waste Sample Tank Continuous 200 gpm Maximum Effluent Release Rate For Tritium ONLY:
100 gpm Treated Laundry & Hot Shower Tank Batch 100 gpm Secondary Waste Sample Tank Continuous 800 gpm - Settling Basin Discharge 1000 gpm Maximum Effluent Release Rate Tritium is treated differently to allow for releases of water containing tritium only from the Turbine Building Drain system to the Waste Neutralization System.
13.95 for all isotopes except tritium 2.79 for Tritium LADTAP II calculates a dilution factor of 67 based on average historical flow rates.
NOTE: Although Dw and Fk are both referred to as near-field dilution factors, they are not the same.
4/4
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 4 (Continued) : Changes to the Offsite Dose Calculation Manual (ODCM),
- 9. Page 2-23, Table 2.1-1 Added the two sentences dealing with the settling basin pumps:
- 10. Page 2-26; Table 2.2-1 Changed the value of A, for H-3 from 8.50E-01 to 3.36E+00.
This was changed because the value of D changed for H-3 due to the need to include the settling basin pumps in the Maximum Effluent Release Rate calculation (see change on page 2-18)
J Eliminated the D term from this page, as it is explained in detail on page 2-18. Eliminating it from this page should reduce some confusion on which term to use (tritium or non-tritium).
4/5.
'OS2
~. ~
TABLE 3:2-2 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (MILES)*
s EXCLUSION MILK MEAT SECTOR BOUNDARX RESIDENCE AN ZEAL GARDEN AN ZEAL N 1.32 2.2 2 ' 2.2 2.8 NNE 1.33 1.8 ~ 1.7 3.5 NE 1.33 2.3 2.3 2.3 ENE 1.33 2.0 .3.6 1.33 1.9 4.7 2.2 ESE 1.33 2.7 2.7 4' SE 1.33 4.3 4'3 4.3 SSE 1.33 4' 1.36 SSW 1.33 3.9 3.9 SW 1.33 2.8 2.8 WRW 1.33 4.3 4.3 4.3 W 1.33 2.8 2.9 2.9 1.33 2.1 2.1 3.6 NW 1.26 2.1 3.8 3.8 NNW 1.26 1.7 1.7 1.7 As of June, 1990.
Distance estimates are + 0.1 mi1e except at the exc1usion boundary.
DCM/ODC-3 3-18 Rev. 3.0 4/6
aA TABLE 4.1 (continued)
O aO RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Exposure Path~ay Point Sample Point, Description I Sampling and Analysis and/or Sample ID No. Distance and Direction Collection Fre uenc F~re uenc A~na1 sos
- d. Sediment 41 Shoreline of mixing zone from of cooling tower blowdown Shoreline line. S sector, 3.8 site.
ml.'rom (continued)
- e. Bottom 52 -Harris Lake in the v>cinlty Bottom sediment sample Each sample Gamma Isotopic 4 Sediment of the mixing zone of the semiannually cooling tower. S sector, 3.8 ml. trom site.
- 4. Ingestion 42 Maple Knoll on SR 1403. Grab samples semi- Each sample 1-131 8, I
tV a. Ml Ik SSE sector, 7.5 mi. from monthly when animals Gamma Isotopic site. are on pasture; monthly II other times.
43 Goodwin's Dairy on SR 1134.
N sector, 2.2 mi. from site.
,Strowd's Dairy, Pittsboro (Control Station) > 12 mi.
NW sector from site.
a, Figure 4.1-5 A Legend O
a AI REFER TO STATION REFER TO STATION FIGURE NUMBER SAMPLE TYPE FIGURE NUMBER SAMPLE TYPE 4.1-4 I AP, AC, TL 4 ~ I -3) 4 '-4 26 AP, AC) SW) SS TL 4.1-4 2 AP, AC, TL 4.1 -2 ~ 4 ~ 1-4 27 TL 4.1-4 TL 4.1 -2 ~ 4 1-4 28 TL 4.1-4 4 AP, AC, TL 4. 1-2 29 TL 4.1-2>> 5 AP, AC, MK, FC, TL 4. 1-2 30 TL 4.1-4 6 TL 4. 1-2 31 TL 4.1-4 7 TL 4. 1-2 32 TL 4.1-4 8 TL 4. 1-3 33 TL 4.1-4 9 TL 4. 1-3 34 TL 4.1-4 10 TL 4. 1-3 35 TL 4.1-4 ll TL 4. 1-3 36 TL 4.1-4 12 TL 4. 1-3 37 TL
- 4. 1-4 16 TL 4. 1-4 41 SS I 4.1-4 17 TL 4. 1-3 42 MK M 4. 1-4 O 18 TL 4. 1-4 43 CO 4. 1-3 19 TL 4. 1-4 44 FH .) AC, g/2.
- 4. 1-3, 4. 1-4 20 TL 4. 1-2 45 FH
- 4. 1-3 22 TL 4. 1-3 48 TL
- 4. 1-3 23 TL 4. 1-4 49 TL
- 4. 1-2 53 TL AC Air Cartridge 4. 1-4 54 FC AP Air Particulate 4. 1-4 55 FC SD Bottom Sediment 4. 1-4 56 TL FC Food Crop FH Fish GW Groundwater MK Milk SW Surface Water DW Drinking Water TL TLD SS Shoreline Sediment
'Approximate location C)
OS2 Radioactive materials released in liquid effluents from SHNPP to unrestricted areas are required to implement 10CFR50 Appendix (Technical Specification 3.11.1.2) and be limited to the concentrations specified in 10CFR Part 20, Appendix B, Table II>
Column 2 (Technical Specification 3.11.1.1). For dissolved or en-trained noble gases the concentration shall be limited to 2E-4 pCi/ml. total activity. The liquid effluent release point is at the point of discharge from the Cooling Tower Blowdown Line
'I into Harris LakeI (see Figure 2.1-3 and T/S Figure 5.1-3).
Radioactive liquids are routinely released as batches from the Waste Monitor Tank (WMT), Waste Evaporator Condensate Tank (WECT)>
and Treated Laundry and Hot Shower Tank (TL&HST)., Batch releases may also originate from the Secondary Waste Sample, Tank (SWST).
These tanks are shown in Figures 2.1-1 and 2.1-2. Effluent monitor identification numbers are provided in Appendix C. Liquid effluent dilution prior to release to Harris Lake is provided by the Cooling Tower Blowdown Line. Concurrent batch releases should not normally occur at SHNPP.
Continuous rele'ases are routinely permitted from the SWST and the Normal Service Water (NSW) system because a low potential for radioactive contamination exists. These releases are checked by effluent monitors on the SWST (Figure 2.1-2) and the NSW lines (Figure 2.1-3).
The turbine building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines with low probability of radioactive contamination.
The radioactive liquid waste sampling and anaLysis required for batch and continuous releases are found in Table 4.11-1 of the Technical Specifications.
DCM/ODC-2 2-1 Rev. 3.0 4/9
OS2 The effluent monitors used to monitor liquid effluent releases are gamma sensitive only, and will not detect non-gamma emitting isotopes (e.g. Fe-55, H-3). Therefore, administrative controls are used to limit the concentrations of these non-gamma emitt'ing isotopes in release pathways so that release limits are not exceeded.
DCM/ODC-2 2-la Rev. 3.0 4/10
OS2 2.1.1 Hatch Releases (continued)
V = Actual tank liquid volume, gal E = Eductor factor P = Pump design recirculation flow rate, gpm n = Number of tank volumes for turnover; this will be typically two or more.
60 = 60 min/hr Table 2.1-1 lists the tank capacities, eductor factors, and pump design recirculation flow rates for individual liquid effluent release. tanks.
- 2. Minimum Acceptable Dilution Factor Determine D , the minimum acceptable dilution factor required to meet the limits of Technical Specifica-tion 3.11.1.1, based on prerelease and composite sample analyses.
rD og
+Docomp +Dot ] (2.1-1)
Qhere D the minimum acceptable dilution factor apportioned to the gamma emitting isotopes.
wee ~
(2.1-2) g DCM/ODC-2 2-3 Rev. 3.0 0/11
OS2 2.1.1 Batch Releases (continued) ocomp the minimum acceptable dilution factor apportioned to the non-gamma emitting composite pc.
isotopes (Sr-89, Sr-90, Fe-55, gross alpha), R/R excluding tritium.
C F -55 s a Fe-55 Dot the miniriium acceptable dilution 'factor h
apportioned to tritium. This value takes
,into account that tritium is potentially being released via the settling basin discharge to the cooling touer discharge line.
MPC + C MPC (2.1-4) t DCM/ODC-2 2 3a Rev. 3.0 4/12
OS2 2.1.3 Nonroutine Li uid Release (continued) determined with Equations 2.1-15 and 2.1-16. If the set point is exceeded, the release to the storm drains is terminated. Effluent can then be diverted to the floor drain system for processing and eventual release via the waste monitor tanks (see Figures 2.1-1 and 2.1-2).
- 2. Turbine Building Floor Drains Effluent Line
. Water collected in the turbine building floor drains is normally routed to the yard oil separator for release to the environment via the waste neutralization system and then to the cooling tower discharge line. Tritium is
~
expected to be detected in this pathway from sources such as background from the lake or secondary activity. Tritium activity will be administratively controlled to limit the activity at the release point.
Because no other radioactivity is normally'xpected in this path, the set points for the turbine building drain monitor are determined with Equation 2.1-15 and 2.1-
- 16. Should the set point be exceeded, the release is automatically terminated. Effluent can then be diverted to the secondary waste treatment system for processing and eventual release via the secondary ~aste treatment tank (see Figures 2.1-1 and 2.1-2) ~
2.2 Com liance with 10CFR50 A endix I 2.2.1 Cumulat'ion of Doses The dose contribution from each release of liquid 'effluents will be calculated and a cumulative summation of the 'total body and any organ doses will be maintained for each 31 days (monthly), each calendar quarter, and the year. The dose contribution for batch
, releases and all defined periods of continuous release will be calculated using the following equation:
-A. t
) ($ (Ai~ tk Ci (2.2-1) k i k DCM/ODC-2 2-15 Rev. 3.0 4/13
OS2 2.2.1 Cumulation of Doses (continued)
The near-field average dilution factor for C-during any liquid effluent release "k." Defined as the ratio of the volume of undiluted liquid waste released to the product of the diluted volume from I A C 9J9 the site discharge structure to unrestricted re-ceiving waters times AF. AF is the site-specific applicable factor for the mixing, effect of the SHNPP discharge structure as defined in NUREG-0133 and has a value < 95.
According to Section 4.3 in NUREG-0133 for plants with cool-ing towers, the factor AF shall be a number such that the product of the nominal average blowdown flow (4,700 gpm) to [O~0 the receiving water body, in cfs and applicable factor AF, is 1000 cfs or less, i.e.,
(Avg. Blowdown) (AF) < 1000 cfs '2.2-1a)
Thuse (2.2-2)
Qk d) P Where AF < 95 and V and V are as k d defined in Equation 2.1-14.
In the case of a continuous secondary waste sample "tank radioac-tive release C. = the SWST composite sample i activity. For the NSW C i = cooling tower basin concentration and Vk = discharge from the cooling tower basin while Vd = the flow from the makeup water cross-tie. For a release through the Turbine Building Floor Drain Line to the waste neutralization system, Ci = the Turbine Building floor drain sample activity (normally H-3 only), Vk discharge from the Turbine Building floor drain Line, and Vd = the average flow during the period of the total Cooling Tower discharge. The total Cooling Tower discharge is the sum of the Cooling Tower Blowdown flow and the Cooling Tower By-pass Line flow.
DCM/ODC-2 2-17 Rev. 3.0 4/14
~ 'S2 2.2.1 Cumulation of Doses (continued)
The dose factor A-1T (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation.'.
1T
= 1.14 E+05 +'1 730 (D
w BF.)
1 DF.
1T (2.2-3) where.
1.14 E+05 = 10 6
pCi pCi x 10 3
ml 1
x 1 yr 8760 hr 21 = Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), kg/yr',
The ingestion dose commitment factor to the whole body or any organ, T, for an adult for each isotope "i." Corresponding. to dilution by the Cape Fear River for drinking ~ater and fish consumption at Lillington, North Caro-lina.
Values for the adult total body and organs in mrem/hr per pCi/ml are given in Table 2.2-1.
730 Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109 Rev. 1), liters/yr.
Dw Dilution factor from the near-field area within one-quarter mile of the release point to the closest potable water inlet For the adult water consumption pathway. The factor is calculated for uptake at the municipal water facility at Lillington, North Carolina.
Ca e Fear River Flow ( m)
Maximum Effluent Release Rate (gpm DCM/ODC-2 2-18 Rev; 3.0 4/15
-I OS2'.2.1 Cumulation of Doses (continued)
The Cape Fear River flow is assumed to be 2790 gpm. This is a conservative value based on minimum flow rates for the Cape Fear River.
,The Maximum Effluent Release Rate is the sum of the release rate pathways. It assumes simultaneous releases C
of the following:
For All Isotopes except Tritium.'
100 gpm Treated Laundry & Hot Shower Tank Batch 100 gpm Secondary Waste Sample Tank Continuous I
200 gpm - Maximum Effluent Release Rate For Tritium ONLY:
100 gpm Treated Laundry 6 Hot Shower Tank Batch 100 gpm Secondary Waste Sample Tank Continuous 800 gpm Settling Basin, Discharge 1000 gpm Maximum Effluent Release Rate Tritium is treated differently to allow for releases of water containing tritium only from the Turbine Building Drain system to the Waste Neutralization System.
13.95 for all isotopes except tritium 2.79 for Tritium LADTAP II calculates a dilution facto'r of 67 based on average historical flow rates.
NOTE: Although D w and Fk are both referred to as near-field dilution factors, they are not the same.
DCM/ODC-2 2-18a Rev. 3.0
1<
0
QS2 TABLE 2.1-1 LIQUID EFFLUENT RELEASE TANKS AND PUMPS PUMP No. of DESIGN CAPACITY ( pm) Eductor Tank Capacity Radiation k(2) Tanks ~hlachar a Racfrcolatloc Factor ~<ai;> Effluent Monitor 10 SlhIST 100 0.2 25,000 REM-3542 WECT 2 35 1.0 10,000 REM-354I 2 35 0.25 25,000 REM-3541 TLKHS 2 100 100 0.25 25,000 REM-3540 The settling basin has two pumps. When one pump is running,'he design flow rate is 500 .gpm. When both pumps are running, the design flow rate is 800 gpm.
Reference SHNPP FSAR Tables 1).5.1-1 and 11.2.1-7 a
SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TL&HS: Treated Laundry and Hot Shower Tank TLSHS discharge flow is limited to 35 gpm by procedure when, cross-connected to the floor drain system.
DCM/ODC-2, 2-23 Rev. 3.0
OS2 Sheee 1 oE TABLE 2.2-1 A. PLANT 1T VALUES FOR THE ADULT FOR THE SHEARON HARRlS NUCLEAR POMER A-I.T
= 1.14 x 10 5 ( 730 + 21 BF-) DF-DW 1 I.'C (mrem/hr per micro-Ci/ml)
Nuclide'one Liver ~T.Bod ~Th roid ~Kidue . ~huo Gl-LLI H-3 0 ~ OOE+00 3.36E+00 3.36E+00 3.36E+00 3.36E+00 3.36E+00 3.36E+00 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 4.17E+02 4.17E+02 4-17E+02 4.17E+02 4.17E+02 '4.17E+02 4. 17E+02 )
P-32 4 '2E+07 2.87E+06 1.79E+06 O.OOE+00 O.OOE+00 O.OOE+00 5.20E+06 Cr-51 0.'OOE+00 O.OOE+00 1.29E+00 7.71E-01 2.84E-01 1.71E+00 3.23E+02 Mn-54 O.OOE+00 4.40E+03 8.40E+02 0 OOE+00 1.31E+03 O.OOE+00 1.35E+04 Mn-56 O.OOE+00 1.11E+02 1.97E+01 O.OOE+00 1.41E+02 O.OOE+00 3.54E+03 Fe-55 6 75E+02 4.66E+02 1.09E+02 O.OOE+00 O.OOE+00 2.60E+02 '.67E+02 Fe-59 1 ~ 06E+03 2.50E+03 9.59E+02 O.OOE+00 O.OOE+00 6.99E+02 8.34E+03 Co-58 O.OOE+00 9.36E+01 2.10E+02 O.OOE+00 O.OOE+00 0.00E+00 1.90E+03 Co-60 O.OOE+00 2.69E+02 5.93K+02 O.OOE+00 O.OOE+00 O.OOE+00 5.05E+03 Ni-63 3.19E+04 2.21E+03 1.07E+03 O.OOE+00 O.OOE+00 O.OOE+00 4.61E+02 Ni-65 1 ~ 30E+02 1.68E+01 7.68E+00 O.OOE+00 O.OOE+00 O.OOE+00 4.27E+02 Cu-64 O.OOE+00 1.05E+01 4.91E+00 O.OOE+00 2.64E+01 0;OOE+00 8.92E+02 Zn-65 2.32E+04 7.38E+04 3.34E+04 0.00E+00 4.94E+04 O.OOE+00 4.65E+04 Zn-69 4.94E+01 9.44E+01 6.57E+00 O.OOE+00 6.14E+Ol O.OOE+00 1.42E+01 Br-83 O.OOE+00 O.OOE+00 4.07E+01 O.OOE+00 O.OOE+00 O.OOE+00 5.86E+01 Br-84 O.OOE+00 0.()OE+00 5.27E+01 O.OOE+00 0.00E+00 O.OOE+00 4.14E"04 Br-85 O.OOE+00 O.OOE+00 2.16E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.00E-15 Rb-86 O.OOE+00 1.01E+05 4.71E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.99E+04 Rb-88 O.OOE+00 2.90E+02 1.54E+02 O.OOE+00 O.OOE+00 O.OOE+00 4.0)E-09 Rb-89 O.OOE+00 1.92E+02 1.35E+02 0.00E+00 0.00E+00 O.OOE+00 1.12E-ll Sr-89 2.40E+04 O.OOE+00 6.87K+02 0.00E+00 O.OOE+00 O.OOE+00 3.84E+03 Sr-90 5.89E+05 O.OOE+00 1.45E+05 0.00E+00 O.OOE+00 O.OOE+00 1.70E+04 Sr-91 4.41E+02 O.OOE+00 1.78E+01 O.OOE+00 O.OOE+00 O.OOE+00 2.10E+03 Sr-92 1.67E+02 O.OOE+00 7.23E+00 O.OOE+00 O.OOE+00 O.OOE+00 3.31E+03 Y-90 6.33E"01 O.OOE+00 1.70E-02 O.OOE+00 O.OOE+00 O.OOE+00 6.71E+03 Y-91m 5.98E-03 O.OOE+00 2.32E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.76E-02 Y-91 9.28E+00 O.OOE+00 2.48E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.11E+03 Y-92 5.56E-02 0 ~ OOE+00 1.63E-03 ,O.OOE+00 0 OOE+00 O.OOE+00 9.74E+02 Y-93 1.76E-01 O.OOE+00 4.87E-03 O.OOE+OQ O.OOE+00 O.OOE+00 5.59E+03 103 Zr-95 4.21E"01 1.35E-01 9.14E-02 O.OOE+00 2.12E-01 O.OOE+00 4.28E+02 Zr-97 2.33E-02 4.69E-03 2.15E-03 O.OOE+00 7.09E-03 O.OOE+00 1.45E+03 Nb"95 4.47E+02 2.49E+02 1.34E+02 O.OOE+00 2.46E+02 O.OOE+00 1.51E+06 Mo-99 O.OOE+00 1.29E+02 2.45E+01 O.OOE+00 2.92E+02 O.OOE+00 2.99E+02 Tc-99m 1.03E-02 2.92E-02 3.72E-01 O.OOE+00 4.44E-01 1.43E-02 1.73E+01 Tc-101 1.06E-02 1.53E-02 1.50K-Ol O.OOE+00 ,2.76E-01 7.83E-03 4.60E-14 RU-103 5.53E+00 O.OOE+00 2.38E+00 O.OOE+00 2.11E+Ol O.OOE+00 6.46E+02 Ru-105 4 '0E-01 O.OOE+00 1.82E-01 O.OOE+00 5.95E+00 O.OOE+00 2.82E+02 DCM/ODC-2 2-26 Rev. 3 '
4/18
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 1 : Environmental Monitoring Program
>> Technical Specifications 3.11.2.3 3.12.1 3.12.1.c In July, Olive's Dairy (MK-19), 4.6 miles NNE of the plant, ceased milk production. This leaves the environmental monitoring program with three active milk producers, including a control location. These are the only available locations for this media type within the EPZ.
The necessary revisions to the environmental monitoring program were provided to SHNPP in July and incorporated into ODCM Revision 3, Change 2.
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications 3.12.2.a 3.12.2.b No changes were made to the Land Use Census during the Report period. The changes reported in Appendix 4 were made and reported in the previous monitoring period.
5/2
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1 : Inoperability of Liquid Effluent Monitors Technical Specification 3.3,3.10, Action b Monitors Out-of-Service ) 30 Days During the Report Period Effluent Days Monitor Inop. Reason REM-*1WL-3540 34 Electronic noise problems during pump Treated Laundry 6 starts. Modification has been made which Hot Shower Tank Monitor corrected the problem.
REM-21WS-3542 85 Resin carry-over caused the flow switch to Secondary Waste Sample fail, causing monitor to indicate flow when Tank Monitor there was none. Delay occurred due to de-sludging the applicable tanks to prevent a reoccurrence.
PT-01MP-1968A 87 Intermittant spiking of the flow reading.
Cooling Tower Make-up Monitor kept inoperable for troubleshooting Bypass Line and testing'.
Flow Rate Monitor FT-6119 Modification to increase the accuracy and Waste Monitor Tank/ reliability of the readings has been Waste Evaporator Condensate Tank initiated.
Flow Rate Monitor FT-6193 184 Modification to increase the accuracy and Treated Laundry & reliability of the readings has been Hot Shower Tanks initiated.
Flow Rate Monitor
Semiannual. Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 I
Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service ) 30 Days During the Report Period Effluent Days Monitor Inopo Reason PNL-21AV-3509-SA 184 Problems vith calibration. of flov PNL-21AV-3509-1SA measurement system resulting in Plant Vent Stack discrepancies between actual and expected Flow Rate Monitor flov rates. Modification initiated to correct.
RM-01TV-3536-1 184 Moisture interferences with the flov TB Vent Stack 3A measurement system resulting in Flov Rate Monitor discrepancies between actual and expected flov rates. Modification initiated to correct.
PNL-1WV-3546 & 184 Problems vith calibration of flov PNL-1WV-3546-1 measurement system results in WPB Vent Stack 5 discrepancies betveen actual and expected Flow Rate Monitor flov rates. Modification initiated to correct.
PNL-1WV-3547 6 184 Problems with calibration of flov PNL-1WV-3547-1 measurement system resulting in WPB Vent Stack 5A discrepancies between actual and expected Flow Rate Monitor flov rates. Modification initiated to correct.
6/2
I Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : -Inoperability of Gaseous Effluent Monitors Technical. Specification 3.3.3.11; Action a Monitors Out-of-Service > 30 Days During the Report Period Effluent Days Monitor Inop. Reason OAI-21WG-1101 88 Monitor does not agree with analyzed Waste Gas samples. 'odification has been Compressor Discharge initiated to improve the reliability of Oxygen Monitor the monitor.
HAIC-21WG-1118A 184 Modification to improve reliability of Waste Gas Recombiner monitor initiated, "A" Outlet Gas Hydrogen Monitor r
HAIC-21WG-1118B 39 Differences in the calibration gas and Waste Gas Recombiner the dilution gas pressure caused the monitor "B" Outlet Gas to fail its calibration. Once the problem Hydrogen Monitor determined, adjustments were made and the monitor was calibrated and returned to service.
OARC-21WG-1119A 184 Modification to improve reliability of Waste Gas Recombiner monitor initiated.
"A" Outlet Gas Oxygen Monitor 6/3
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 3 : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.
6/4
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.
6/5
Semiannual Radioactive Effluent Release Report July 1, 1990 to December 31, 1990 Appendix 7 : Major Modifications to Radwaste System Technical Specification 6;15.1 No major modifications were made to the Radwaste system during this Report period.
Semiannual Radioactive, Effluent Release Report July', 1990 to December 31, 1990 Appendix 8 : Meteorological Data Technical Specification 6.9.1.4 As allowed by the Footnote to Technical Specification 6.9.1.4, the annual
'summary of meteorological data will be retained in a file. These data will be provided to the NRC upon request.
Semiannual Radioact ffluent Release Report July 1, 1990 to December 31, 1990 Appendix 9 : Assessment of Radiation Doses Enclosure 1: Population Doses Outside .Site Boundary Due to Effluent Releases Integrated Population Dose Due to Liquid Effluents (man-rem)
A. 50 mile Zngestion Zone Bone Liver W. Body Thyroid Kidney Lung GZ-LLZ Skin Sport Fish 4.57 E-02 6.96 E-02 4.25 E-02 2.64 E-03 2.46 E-02 1. 03 E-02 l.'42 E-02 0.00 E+00 Comm Pish 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0. 00 E+00 0.00 K+00 0.00 E+00 Sport Znvert 0.00 E+00 0.00 K+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 K+00 0.00 E+00 Comm Invert 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Drinking Water 3.45 E-03 2. 67 E-01 2.68 E-01 2. 63 E-01 2.64 E-01 2.64 E-01 2. 81 E-01 0.00 E+00 Shoreline 3.04 E-02 3.04 E-02 3.04 E-02 3.04 E-02 3.04 E-02 3.04 E-02 3.04 E-02 3.57 E-02 Swimming 1.77 E-04 1.77 E-04 1.77 E-04 1.77 E-04 1.77 E-04 1.77 E-04 1.77 E-04 0.00 K+00 Boating 8.92 E 05 8.92 E-05 8.92 E-05 8.92 E-05 8.92 E-05 8.92 E-05 8.92 E-05 0.00 E+00 Zrri Veg 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 . 0.0 E+00 0.00 E+00 0.00 E+00 Zrri Leafy Veg 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 . 0 0 E+00 0.00 E+00 0.00 E+00 Zrri Milk 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 . 00 E+00 0.00 E+00 0.00 E+00 Zrri Meat 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0 . 00 E+00 0.00 E+00 0.00 E+00 ALL PATHWAYS 7.98 E-02 3. 68 E-01 3.41 E-01 2. 96 E-01 3.19 E-01 3.04 E-01 3. 26 E-01 3.57 E-02 Tritium (Bydrosp'here)
Bone Liver W. Body Thyroid Kidney Lung GZ-LLZ Skin Total 0.00 E+00 9.70 E-03 9.70 E-03 9.70 E-03 9.70 E-03 9.70 E-03 9.70 E-03 0.00 E+00
- 2. Integrated Population Dose Due to Gaseous Effluents (man-rem) 50 mile Ingestion Zone W. Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin Plume 1. 36 E-01 1. 36 E-01 1.36 E-01 1. 36 E-01 1.36 E-01 1.36 E-01 1.45 E-01 4.49 E-01 Ground 1.24 E-03 1. 24 E-03 1.24 E-03 l. 24 E-03 1.24 E-03 1.24 E-03 l.
3.66 24 E-03 E-03 1.46 E-03 3.19 E'-0 3 Znhalat ion 3.19 E-03 3. 21 E-03 0.00 E+00 3. 19 E-03 3.19 E-03 3.19 E-03 Vegetat ion 8.60 E-04 8. 81 E-04 0.00 E+00 8. 58 E-04 8.56 E-04 8.56 E-04 8.56 E-04 8.56 E-04 Cow Milk 4.33 E-04 4. 35 E-04 0.00 E+00 4. 32 E-04 4.32 E-04 4.32 E-04 4.32 E-04 4.32 E'-0 4 Meat s, P oui t ry 5. 02 E-04 5. 26 E-04 0.00 E+00 4. 99 E-04 4.98 E-04 4.98 E-04 4.98 E-04 4.98 E.-O 4 Total 1. 42 E-01 1. 43 E-01 1.37 E-01 1. 42 E-01 1.42 E-01 1.42 E-01 1.51 E-01 4.55 E'-01
Semiannual Radioacti fluent Release Report July 1, 1990 to ecember 31, 1990 Appendix 9 : Assessment of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Inside Site Boundary
- 1. Zndivi dual Dose Due to Liquid Effluents (nrem/yr.)
Bone Liver W. Body Thyroid Kidney Lung GZ-LLZ Skin ADULT Fish 5. 01 E-02 8.23 E-02 5.99 E E-03 2.94 E-02 1. 21 E-02 1 ~ 96 E-02 Shoreline 3. 18 E-03 3- 18 E-03 3.18 E-03 3. 18 E-03 3.18 E-03 3. 18 E-03 3. 18 E-03 3-74 E-03 Swimming 1.93 -E-04 1.93 E-04 E-04'.38 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 Boating 2.22 E-04 2 '2 E-04 2.22 2.22 E-04 2 '2 E-04 2.22 E-04 2;22 E-04 TOTAL 5.37 E-02 8.58 E-02 6.35 E-02 6.98 E-03 3.30 E-02 1.57 E-02 2.32 E-02 3.74 E-03 TEEN Fish 5.31 E-02 8. 41 E-02 3.52 E-02 2.61 E-03 2.94 E-02 1. 31 E-02 1.39 E-02 Shoreline 1.78 E-02 1.78 E-02 1.78 E-02 1.78 E-02 1.78 E-02 . 1.78 E-02 1.78 E-02 2.09 E-02 Swimming 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 Boating 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 TOTAL 7. 15 'E-02 1. 02 E-01 5.36 E-02 2.10 E-02 "4.78 E-02 3.15 E-02 3.23 E-02 2.09 E-02 CHZLD Fish 6.62 E-02 7.43 E-02 1.59 E-02 2. 16 E-03 2.51 E-02 1.05 E-02 6.09 E-03 Shoreline 3. 71 E-03 3.71 E-03 3.71 E-03 3. 71 E-03 3.71 E-03 3. 71,E-03 3.71 E-03 4.36 E-03 Swimming 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E 05 9.67 E-05 Boating 1.21 E-04 1. 21 E-04 1. 21 E-04 1.21 E-04 1.21 E-04 1. 21 E-04 1. 21 E-04 TOTAL 7. 01 E-02 7 '2 E-02 1..98 E-02 6.09 E-03 2.90 E-02 1.44 E-02 1.00 E-,02 4.36 E-03 9/2
C .1
,r
Semiannual Radioacti fluent Release Report July 1, 1990 to ecemb'er 31, 1990 Appendix 9 : Assessment of Radiation Doses Enclosure 2 (Continued): Doses to General Public Due to Activities Inside Site Boundary
- 2. Individual Dose Due to Gaseous EfFluents (mrem/yr.)
W. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7. 61 E-03 1.55 E-02 Ground 8.44 E-05 8.44 E-05 8.44 E 05 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-OS 9.92 E-05 Inhalation 4.04 E-05 4.o8 E-OS 0.00 E+00 4.04 E-OS 4.04 E-05 4.04 E-05 4.88 E-05 4.04 E-05 TOTAL 7.58 E-03 7.58 E-03 7.54 E-03 7.58 E-03 7.58 E-03 7.58 E-03 7.74 E-03 1.56 E-02 TEEN Plume 7.4.5 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E.-03 7. 61 E-03 1.55 E-02 Ground 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-OS 8.44 E-05 8.44 E-05 8.44 E-05 9.92 E-05 Inhalation 4.07 E-05 4.10 E-05 0.00 E+00 4.07 4.06 E 05 4.06 E-OS 5.30 E-05 4.06 E-05 E-05'.58 TOTAL 7.58 E-03 7.58 E-03 7.54 E-03 E-03 7.58 E-03 7.58 E-03 7.74 E-03 1.56 E-02 CHILD Plume 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 7.61 E-03 1.55 E-02 Ground 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 9.92 E-05 Inhalation 3.60 E-05 3.61 E-05 0.00 E+00 3.59 E-05 3.59 E-05 3.59 E-05 4.59 E-05 3.59 E-05 TOTAL 7.57 E-03 7'.57 E-03 7.54 E-03 7.57 E-03 7.57 E-03 7.57 E-03 7.74 E-03 1.56 E-02 INFANT Plume 7.45 E-03 7.45 E-03 7.45 E-03 7.45 E-03 .7.45 E-03" 7.45 E-03 7.61 E-03 1.55 E-02 Ground 8.44 E-05 8.44 E-OS 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 9.92 E-05 Inhalation 2.07 E-05 2 07 E-05 0.00 E+00 2.07 E-05 2.07 E 05 2.07 E-05 2.70 E-05 2.07 E-05 TOTAL 7.56 E-03 7.56 E-03 7.54 E-03 7.56 E-03 7.56 E-03 7.56 E-03 7.72 E-03 1.56 E-02 9/3
Semiannual Radioacti fluent Release Report July 1, 1990 to December 31, 1990 Appendix 9 : Assessment of Radiation Doses Enclosure 3: Doses to Likely Most Exposed Member of the Public Individual Dose Due to Liquid Effluents (nrem/yr.)
Bone Liver W. Body Thyroid Ki dney Lung GZ-LLI Skin ADULT Fish 5. 01 E-02 8.23 E-02 5.99 E-02 3.38 E-03 2.94 E-02 1.21 E-02 1.96 E-02 Drinking 3.43 E-04 3.23 E-02 3.24 E-02 3.19 E-02 3.20 E-02 3.19 E-02 3.45 E-02 Shoreline 3.18 E-03 3.18 E-03 3.18 E-03 3.18 E-03 3.18 E-03 3.18 E-03 3.18 E-03 3.74 E-03 S~imming 1.93 E-04 1.93 E-04 1.93 E 04 1.93 E-04 1.93 E-04 1.93 E-04 1-93 E-04 Boating 2.22 E-04 2.22 E-04 2.22 E-04 2.22 E-04 2.22 E-04 2.22 E-04 2.22 E-04 TOTAL 5.40 E-02 1. 18 E-01 9.59 E-02 3.89 E-02 6.50 E-02 4.76 E-02 5.77 E-02 3.74 E-03 TEEN Fish 5.31 E-02 8. 41 E-02 3.52 E-02 2.61 E-03 2.94 E-02 1.31 E-02 1.39 E-02 Drinking 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 shoreline 1.78 E-02 1.78 E-02 1.78 E-02 1.78 E-02 1.78 E-02 1.78 E-02 1.78 E-02 2.09 E-02 Swimming 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 2.90 E-04 Boating 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 TOTAL 7.1,5 E-02 1. 02 E-01 5.36 E-02 2-10 E-02 4.78 E-02 3.15 E-02 3.23 E-02 2.09 E-02 CHILD Fish 6.62 E-02 7.43 E-02 1.59 E-02 2. 16 E-03 2.51 E-02 1.05 E-02 6.09 E-03 Drinking 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Shoreline 3.71 E-03 3.71 E-03 3.71 E-03 3.71 E-03 3.71 E-03 3. 71 E-03 3.71 E-03 4.36 E-03 Swimming 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E-05 9.67 E-05 Boating 1 ~ 21 E-04 1.21 E-04 1.21 E-04 1.21 E-04 1.21 E-04 1. 21 E-04 1.21 E-04 TOTAL 7.02 E-02 7.82 E-02 1 ~ 98 E-02 6.09 E-03 2.90 E-02 1.44 E-02 1.00 E-02 4.36 E-03
~. ~
1
Semiannual Radioacti ffluent Release Report July 1, 1990 to December 31, 1990 Appendix 9: Assessaent of Radiation Doses Enclosure 3 {Continued): Doses to Likely Most Exposed Meaber of the Public
- 2. Individual Dose Due to Gaseous Effluents (area/yr.)
A. Maximum Hypothetical Zndividual Exposure from Noble Gases, Particulates, Zodines, and Tritium Tif Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume 7.62 E-02 7.62 E-02 7.62 E-02 7.62 E-02 7.62 E-02 7.62 E-02 7.80 E-02 1.64 E-01 Ground 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.88 E-04 Inhalation 4.93 E-04 4.98 E-04 0.00 E+00 4.93 E-04 4.93 E-04 4.93 E-04 5.92 E-04 4.93 E-04 Vegetation 8.45 E-04 9.02 E-04 0.00 E+00 8.41 E-04 8.38 E-04 8.38 E-04 8.38 E 04 8.38 E-04 Milk 1. 99 E-04 2. 01 E-04 0.00 E+00 1.98 E-04 1.98 E-04 1.98 E-04 1.98 E-04 1.98 E 04 Meat a Poultry 8.59 E-05 9.73 E-OS 0.00 E+00 8.51 E-05 8.44 E-05 8.44 E-05 8.44 E-05 8.44 E-05 TOTAL 7.&3 E-02 7.84 E-02 7.67 E-02 7.83 E-02 7.83 E-02 7.83 E-02 8.02 E-02 1.66 E-ol TEEN Plume 7.62 E-02 7.62 E-02 7.62 E-02 7. 62 E-02 7.62 E-02 7.62 E-02 7.80 E-02 1.64 E-o 1 Ground 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.88 E-04 Znhalation 4.97 E-04 5.01 E-04 0.00 E+00 4.96 E-04 4.96 E-04 4.96 E-04 6 - 41 E-04 4.96 E-04 Vegetation 9.96 E-04 1.05 E-03 0.00 E+00 9.90 E-04 9.85 E-04 9.85 E-04 9.85 E 04 9.85 E-04 Milk 2.59 E-04 2.62 E-04 0.00 E+00 2.59 E-04 2.58 E 04 2.58 E-04 2.58 E-04 2.58 E-04 Meat I Poultry 5.16 E-OS 5.73 E-05 0.00 E+00 5.09 E-05 5.04 E-05 5.04 E-05 5.04 E-05 S.o4 E 05 TOTAL 7.&5 E-02 7.86 E-02 7.67 E-02 7.85 E-02 7.85 E-02 7.85 E-02 8.04 E-02 1.67 E-01 CHILD Plume 7.62 E-02 7.62 E-02 7.62 E-02 7.62 E-02 7.62 E-02 7.62 E-02 7.80 E-02 1. 64'.88 E-0 1.
Ground 5.00 E-O4 5.00 E-04 5.00 E-04 5.00 E 04 5.00 E-04 5.00 E-04 5.00 E-04 E 04 Inhalation 4.39 E-04 4.4o E-04 0.00 E+00 4.39 E-04 4.39 E>>04 4.39 E-04 5.56 E-04 4.39 E-0 4 Vegetation Milk 1.56 4.09 E-03 E-04
- l. 58
- 4. 10 E-03 E-04 0.00 0.00 E+00 E+00 1.55 4.08 E-03 E-04 1.54 4.08 E-03 E-04 1.54 4.08 E-03 E-04 1.54 4.08 E-03 E-04 1.54 4.08 E-03 E-O4 Meat a Poultry 6.27 E-05 6.43 E-05 0.00 E+00 6. 15 E-05 6.08 E-05 6.08 E-05 6.08 E-05 6.08 E-OS TOTAL 7.92 E-02 7.92 E-02 7.55 E-02 7.92 E-02 7.92 E-02 7.92 E-02 7.92 E-02 1. 67 E-o 1 INFANT
?
Plume 7.62 E-02 7.62 E-02 7.62 E-02 .7.62 E-02 7.62 E-02 7.62 E-02 7.80 E-02 1.64 E-01 Ground 5.00 E-04 . 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.00 E-04 5.88 E-04 Znhalation 2.53 E-04 2.53 E-04 0.00 E+00 2.52 E-04 2.52 E-04 2.52 E-04 3.27 E-04 2.52 E-04 Milk 6.21 E-04 6. 21 E-'04 0.00 E+00 6.20 E-04 6.19 E-04 6.19 E-04 6. 19 E-04 6.19 E-04 TOTAL 7.76 E-02 7.76 E-02 7.48 E-02 7.76 E-02 7.76 E-02 7.76 E-02 7.94 E-'02 1.65 E-01 9/5
Semiannual Radioact ffluent Release Report July 1, 1990 to December 31, 1990 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Likely Host Exposed Hember of the Public
- 2. Individual Dose Due to Gaseous Effluents (nrem/yr.)
B. Haximum Real Zndivi dual Exposure f rom Noble Gases, particulates, Zodines, and Triti:um W. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin, ADULT Plume 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 2.03 E-02 4.25'-02 Ground 2-02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.38; E-04 Inhalation 1.25 E-04 1.26 E-04 0.00 E+00 1.25 E-04 1.25 E-04 1.25 E-04 1.49 E-04 1.25: E-04 Vegetation 2.1S E-04 2.38 E-04 0.00 K+00 2.13 E-04 2.12 E-04 2. 12 E-04 2.12 E-04 2. 12'-04 I
TOTAL 2.04 E-02 2.04 E-02 2.01 E-02 2.04 E-02 2.04 E-02 2.04 E-02 2.09 E-02 4.30. E-02 TEEN Plume 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 2.03 E-02 4.25: E-02 Ground 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.38 E-04 Inhalation 1.25 E-04 1.26 E-04 0.00 E+00 1.25 E-04 1.25 E-04 1.25 E-04 1.61 E-04 1.25'-04 Vegetation 2.53 E-04 2.76 E-04 =
0.00 E+00 2.51 E-04 2.49 E-04 2-49 E-04 2.49 E-04 2.49 E-04 TOTAL 2-04 E-02 2.05 E-02 2 ~ 01 E-02 2. 04 E-02 2.04 E-02 2.04 E-02 2.09 E-02 4 . 31. E-02 CHILD Plume 1.99 E-02 1.99 E>>02 1.99 E-02 1.99 E-02 1.99 E;02 1.99 E-02 2.03 E-02 4.25 E-0 2 Ground 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2. 38'.
E-0 4 Inhalation 1. 11 E-04 1. 11 E-04 0.00 E+00 1.11 E-04 1.11 E-04 1. 11 E-04 1.40 E-04 11, E-0 4 Vegetation 3.98 E-04 4.06 E-04 0.00 E+00 3.92 E-04 3.88 E-04 3.88 E-04 3.88 E-04 3.88. E 04 TOTAL 2.06 E-02 2.06 E-02 2.01 E-02 2.06 E-02 2.06 E-02 2.06 E-02 2. 10 E-02 4 .'2. E-02 INFANT I
Plume 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 1.99 E-02 2.03 E-02 4.25! E-'0 2 Ground 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2.02 E-04 2. 38! E-'0 4 Znhalation 6.38 E-05 6.39 E-05 0.00 E+00 6.38 E-OS 6.38 E-05 6.38 E-05 8. 21 E-05 6.36m E-05 TOTAL 2. 01 E-02 2.01 E-02 2.01 E-02 2.01 E-02 2.01 E-02 2. 01. E-02 2.06 -E-02 4i. 28! E-02 9/6 i'
i
ce hi
Seaiannual Radioactx f fluent Release Report July 1, 1990 to Deceaber 31, 1990 Appendix 9 : Assessaent of Radiation Doses Enclosure 3 (Continued): Doses to Likely Most Exposed Meaber of the Public Annual Ai r Dose { arad)
A. Maxiaua Hypothetical Individual: Beta = 1.76 E-01 Gaaaa = 1. 20 E-01 B. Maxiaua Real Individual: Beta ~ 4.51 E-02 Qaaaa ~ 3. 11 E-02
- 4. Doses Due to Direct Radiation froa the Harris Plant On-going environaental TLD dose aeasureaents shoM that the offsite Direct Radiation Dose is negligible.
9/7
p4 Semiannual Radioacti fluent Release Report July 1, 1990 to December 31, 1990 Appendix 9 : Assessment of Radiation Doses Enclosure 4 : Major Assumptions Used to Calculate Radiation Doses
- 1. Doses Due to Liquid Ef f luents A.
L'ocation Harris Lake
'alue Dilution Factors 1.00 E+01 Ex osure Pathwa s Shoreline, Swimming, Boating, Fish Consumption Cape Fear River 6.67 E+02 Shoreline, Drinking Water (for Lillington, Dunn, and Fayetteville)
Cape Fear River/
Raven Rock Park 1.62 E+03 Boating Populations Af f ected Location Value Ex osure Pathwa s Harr is Lake 1. 10 E+05 person-hours Shoreline, Swimming Lill ington 1.95 8+03 persons Drinking Water Drinking Water Dunn 9.00 E+03 persons Faye tteville 1. 15 E+05 persons Drinking Water Harr is I.ake/
Ca pe Fear River 7.84 E+03 person-hours Fishing Cape Fear River/
Ra ven Rock Park 5.00 E+04 person-hours Boating Rave n Rock Park 4.40 E+05 person-hours Shoreline Doses for "Activities Inside the Site Boundary" and the "Likely Host Exposed Hember of the Public" use the Cape Fear River as the Drinking Water supply and Harris Lake as the source of all other liquid pathway doses.
- 2. Doses Due to Gaseous Effluents A. The 50 mile Ingestion Zone population is 1.47 E+06 persons B. The Haximum Real Individual is located at 2897 meters ( 1.8 miles) in the NHE sector.
C. The Haximum Hypothetical Individual is located on the site boundary at 2140 meters in the SSW sector D. For the Inside Site Boundary Individual, access time is. assumed to be 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />s/yr at 1207 meters- (3/4 mil the NNE sector f rom the plant, which is the closest: accessible lake location.
E. Concurrent meteorology is applied separately to batch and continuous release source terms The dose commitment from each mode was summed to obtain annual dose.
9/8
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