ML20090A448
| ML20090A448 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/31/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML14174A256 | List: |
| References | |
| NUDOCS 9203020339 | |
| Download: ML20090A448 (56) | |
Text
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Enclosure 1 to Serial: RNPD/92-0409 Page 2 of 54 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 7/1/91 - 12/31/91 CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON SEG PLANT - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 l
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Enclosure 1 to Serial: RNPD/92-0409 Page 3 of.54 TABLE OF CONTENTS Enclosure 1 Description Eage I. EXECUTIVE-SUMM'.RY , . .... . . . . . . . . . . . . . . . . . . . 6 A '. Significant Variances . . . . . . . . . . . . . . , . . . . . 6 B. Regulatory compliance . . . . . . . . . . . . . . . . . . . . . . 8 II. SUPPLEMENTAL INFORMATION . ... . . . , . . . . . . . . .. . . 9 A. Regulatory Limits .. ., . . . . . . . . . . . . . . . . . . . 9 B. Measurements and Approximations of Total Radioactivity , . . . . 9
.C. Estimated Total Errors . . . . . . . . . . . . . . . . . . . . 11 III. CASEOUS EFFLUENTS . .. . . . . . . . . . . . , . . . . . . . 12 A. . Batch Releases . . .. , .. . . . . . . . . . . . . . , . . . . . 12 B. Abnormal Releases . . . . . . . . .. . . . . . . . . . . . . 12-C. Data Tables . . . ..... . . . . . . . . . . . . . . . . . . . . 12
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IV ,- LIQUID EFFLUENTS .. . , . ... . . . . . . . . . . . . . . . . . . 16-A. Batch Releases . . .... . . . . . . . . . . . . . . . . . . 16
.B. Abnormal Releases . . . . . . . . . . . . . . . . . . . . . 16 C. Data Tables . . . .. . . . . . . . . . . . . . . . . . . . . , , . 16 V. SOLID WASTE' AND IRRADIATED FUEL MlIPMENTS . . , , . . . . . . . . . -20 A .- Waste Class A . .. .. . , . .. . . . . . . . . . . . . . . . 20
-B. Vaste-Class B . . ... . . . . . . . . . . . . . . . . . . . . 22 C. Irradiated-Fuel Shipments . . . . . . . . . . . . . . . . . . . 23 iVI4 ANNUAL GASEOUS DOSE ASSESSMENTS- . . . . . . . . . . . . . . .- 24 A. ' Population Distribution: . . . . . . . . . . . . . . . . . . . . 24.
~B. Food Production Distribution.. . . . . ,. . . . . . . . . . . . 24' C. Food Production Total ... . . . . . . . . , , . . . . . . . i. 24-D. Source Terms and-Meteorologica1' Inputs-. . . . . . . . . . . . . ~. . .24-E. Maximum" Individual Doses . .. , ., . . . . , . , _. . . . . . . , . 24 F. Integrated-Population Doses: .. , . . . . . . . . . . . . . . 25
=G. Onsite;-Integrated.and Recreational Population Doses for-1991- . . . 25 H. Data Tables . .. . ... . . ., . . . . . . . . . . . . . . .:. 28 VII.- ANNUAL LIQUID DOSE AS'SESSMENTS . . .. . . , , .. . . - , . . . . . . . . 365 A. Environmental Inputs and Assumptions . . . . . . . . . . . . . . . . 36 B, Recreational-' Activities . . . . . . . . . . . . . . . . . . . .. 39
'C. Maximum. Individual Dose' ..... . . . . . . . . . . . . . . . 41-
.D. ,0nsite: Integrated Population: Doses . . . . . . . . . . . . . . . . 41 lE. Annual Integrated Population Doses , , . . . . . . . . . .41
.F. -Data-Tables' . . . .... . .. . . . . . . _ . - . , . . . . . . . 41
Enclosure 1 to Serial: RNPD/92-0409
- Page 4 of 54 TABLE OF CONTENTS Enclosure 1
! Description g ,
! -- VIII. 40CFR190 DOSE CONFORMANCE . . . . . . . . . . . . 46 -
IX. METEOROLOGICAL DATA . . . . . . . . . . . . . . . . . . . . . . . . . 46 A. Continuous Release Diffusion Analysis . . . . . . . . . . . . . . 46 B. Mixed Mode Batch Release Diffusion Analysis .. . . . . . . . . . 49 '
I C. Ground Level Batch Release Diffusion Analysis , , . . . . . . 52 ,
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Enclosure.1 to Seriali RNPD/92-0409 Page 5 of 54 LIST OF TABLES Enclosure 1 '
TABLE- DESC3]PTION Pace- ,
Table III-A Gaseous Effluents Summation of All Releases . . . . 13
. Table III B- Gaseous Effluents Ground -Level and Mixed Mode Releases ~
. . . 14 Table III C Typical Lower Limits of Detection for Gaseous Effluents . . 15 Table IV-A Liquid Effluents - Summation of All Releases . , . . . . . . 17 Table IV-B Liquid Effluents - Continuous Mode and Batch Mode Releases . . 18 Table IV-C- Typical Lower Limits of Detection for Liquid Effluents . . . . 19 Table VI-A Caseous Pathway Hypothetical Site Boundary Maximum Individual Doses for 1991 , . . . . . . . . . . . . . . . . . . 29 Table VI-B Gaseous Pathway - True Offsite Maximum Individual Doces for 1991 31 Table VI-C Gaseous Pathway - Onsite Hypothetical Maximum Indi idual Doses for 1991 . . . . . . . . . . . . , , . . , , . . 33 Table VI-D Gaseous Pathway - Offsite Annual Integrated Population Dose Summary for 1991. . . . . . . . . . . . . . . . . . 34 Table VI-E Gaseous Pathway - Onsite Annual Integrated and Recreational Population Doses for 1991 . , , , , , . . . . . . , , . 35
. Table VII-A Liquid Pathway . Hypothetical Maximum Individual Doses.for 1991 . . . . . . . . . . . . , , . , , . . . . . 42-Table VII-B Liquid Pathway - Lake Robinson (onsite) Annual Integrated and Recreational Population Doses for 1991 . . . . . . . . , 44 Table VII-C Liquid Pathway - Annual Integrated Population Dose Summary for 1991 . . . . . . . . . , , , . . 45
-Table IX-A. -Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD -
Continuous Releases , , , . . . . . . , , , . . . . . . . . m 46 Table'IX-B Joint Occurrence Frequencies for LOWNDDEG and LOWNDSPD - Mixed Mode Batch. Releases . . . . , . . . . . . , . . . 49 TableflX-C Joint Occurrence Frequencies for LOWNDDEC and LOWNDSPD - Ground Level Batch Releases , , , . . . . . , , , 52 l
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Enclosure 1 to Serial: RNPD/92-0409 Page 6 of $4 I. EXECUTIVE
SUMMARY
Sirnificant Variances A. The following are explanations of significant variances in this Semiannual Report:
- 1. The 10CFR50 Appendix I, Percent of Limits, were calculated from the last posted release for the period indicated using the Nuclear Data LRW/CRW (ODCM meteorology) Release Permit Generating System. The following is a summary of the comparison of the annual dose commitment of the ODCM and 1ADTAP/GASPAR dose programs.
CASEOUS UNITS LRW/GRW 1ADTAP/GASPAR Annual Beta Air Dose mrad 1.37E-02 3.33E-03 Camma Air Dose mrad 1.75E-02 4.32E-03 1-131, 1-133, Tritium & Part.
>8 Day Half-Lives Dose mrem 7.44E-04 6.21E-02 L10UID Total Body Dose mrem 2,31E 02 8.87E-03 Critical Organ Dose mrem 4.52E-02 1.61E-02 The annual gaseous dose commitment was calculated with CASPAR using batch mixed mode, continuous mixed mode, batch ground level mode, and continuous ground level concurrent meteorology. The ODCM (GRW ;
Software) provides day-by-day dose estimates that are higher because
-all releases ~are assigned to the limiting receptor, using the continuous ground level dispersion factors calculated from 1978 meteorology.
The annual liquid dose commitment is lower with LADTAP.because total annual' dilution flow is used. Day-by day dose estimates provided by-the ODCM-(LRW software). utilizes dilution flow during actual release periods from Unit 2 only, reyesv+ *rna ---wn ewee er- **- -t- qge-m -=M-r,a -gm+>--gt*- ,+- 4 - y --- Y- e Hpw-'+ ew.* -n-----
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Enclosure 1 to Serial: 'RNPD/92 0409 Page-7 of 54
- 2. On March 11, 1991, the Unit was returned to service following the completion of refueling outage 13. From this date through the end of 1991, the Unit, with few exceptions, ran at steady-state power
- operations. Consequently, variances in most effluent parameters are relatively small when comparing the two quarters in this reporting period. Gaseous affluents showed a decrease in fission and activation 4
gas curies as well as tritium curies in the fourth quarter as compared to the third quarter. This is mainly due to Containment Vessel purging for personnel heat stress management during July and August Containment
-entries. Gaseous effluents in the third and fourth quarters showed no detectable iodine. This continues a trend which began in the third quarter of 1990 and is attributable to continued good Reactor Coolant System and fuel integrity. Some of the gaseous release parameters for this reporting period are summarized below:
GASEOUS EFFLUENTS UNITS 3rd ,QUARTED. 4th OUARTER Fission 6 Act. Gas Ci 6.08E-01 7.03E 02 I-131 Ci 0. 00E4 00 0.00E+00 Part. >8 Day Half-Lives Ci 6.78E-05 5.09E-05 Tritium C1 1.59E400 8.22E-01
- 3. Little difference can be seen when comparing liquid release parameters for the third and fourth quarters of 1991. This is consistent with steady-state plant operations during the period. Some of the liquid release parameters for this reporting period are shown below:
LIOUID EFFLUENTS UNITS 3rd OUARTER 4th OUARTER Fission & Act. Products Ci 6.08E-02 5,11E-02 Dis, & Entrained Gas Ci 9.56E-03 1.14E 02 Tritium Ci 5.86E+01 1.09E+02 Dilution Volume Liters 2.69E+11 2.61E+11 Waste Volume Liters 8.12E+05 6.43E+05 4
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-Enclosure 1 to Serial: RNPD/92 0409 Page 8 of 54 B. Renulatory Compliance
- 1. When proj ected on a day by-day basis utilizing conservative meteorological conditions, the dose commitment from gaseous and liquid effluents is a small fraction of the 10CFR50, Appendix 11 limits. The direct radiation assessment to the likely most exposed member of the public is -reported in the Annual Radiological Environmental Operating Report. During 1991, the results of the-direct radiation assessment demonstrated no measurable affect above background for plant operations. The Independent Spent Fuel Storage Installation onsite is now operational and is evaluated in Addendum I to this report.
- 2. There were no changes to the waste solidification process ' control program (PCP) during this reporting period.
- 3. There were no changes - to the Radioactive Waste Systems (liquid, -
gaseous, or solid) during this reporting period.
- 4. There was a reportable instrumentation inoperability event during this reporting period. See Enclosure 2 for details,
- 5. There were no outside liquid holdup' tanks that exceeded the ten curie limit during this reporting period.
- 6. There were no Waste Gas Decay Tanks that exceeded the 1.9E404 curie limit during this reporting _ period.
- 7. There was a revision to the ODCM during this reporting period. See Enclosure 2 for details-.
Enclosure 1 to'Scrial: RNPD/92 0409 z
Page 9 of 54
+ 1 TII. SUPPLEMENTAL INFORMATION A. Reculatory Limits
- 1. Fission and Activation Gases: 4 10CFR20 Limits (Instantaneous Release Rate) '
total Body Dose $500 mrom/yr Skin Dose $3000 mrem /yr 10CFR50, Appendix I For Calendar Quarter Gamma Dose % mrad Beta Dose sto mrad For Calendar Year Gamma Dose $10 mrad Beta Dose $20 mrad
-2. Iodine + 131 and 133, Tritium, and Particulates >8 day half-lives:-
10CFR20 Limits (Instantaneous Release Rate)
Dose -from Inhalation (only) to a child to any organ $1500 mrem /yr 10CFR50, Appendix I (Organ Doses)
For Calendar Quarter 57.5 mrem For Calendar Year $15 mrem
- 3. Liquids:
Concentrations are_specified in 10CPR20, Appendix B,;
Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2,00E-04 pCi/ml total activity, 10CFR50, Appendix 1 For Calendar Quarter Total Body Dose $1.5 mrem Any Organ Dose $5 mrem For Calendar Year Total Body Doso $3 mrem
-Any Organ Dose'510 mrem JB, Measurements and Annroximations of Total Radioactivity'
-1; Continuous Gaseous Releases
- n. Fission : andJ Activation Gases -
Die total l activity _ released is determined from the net-count rate of1the gaseous monitor, its calibration factor, and the - total exhaust flow. 'The activity of radioactive gas is-~ determined by_the: fraction of that radioactive-gas in the-isotopic analysis.for'that period.:
Enclosure 1 to Serial: RNPD/92-0409 Page 10 of 54
- b. Iodines -
The activity released as iodine-131, 133, and 135 is based on isotopic analysis of the charcoal cartridge and particulate filter and the total vent flow.
- c. Particulates - The activity released via particulates with half-lives greater than eight days is determined by isotopic analysis of particulate filters and the total vent flow,
- d. Tritium - The activity released as tritium is based on weekly grab sample analysis and total vent flow.
- 2. Batch Gaseous Releases
- a. Fission and Activation Gases - The activity released is based on the volume released and the activity of the individual nuclides obtained from an isotopic analysis of the grab sample taken prior to the release,
- b. Iodines - The iodines from mixed mode batch releases are included in the iodine determination from the mixed mode continuous Auxiliary Building release.
- c. Particulates - The particulates from mixed mode batch releases are included in the particulate determination from the mixed mode continuous Auxiliary Building release. Ground level batch particulates are reported in the batch mode accountability.
- d. Tritium - The activity released as tritium is based on the grab sample analysis of each batch and the batch volume,
- 3. Liquid Release's
- a. Fission and Activation Products - The total release values (not including tritium, strontium, iron-55. and alpha) are comprised of the sum of the individual radionuclide activities in each release to the discharge canal for the respective quarter. These values represent the activity known to be present in the liquid radwaste effluent,
- b. Tritium & Alpha - The measured tritium and alpha concentrations in a monthly composite sample are used to calculate the total release and average diluted concentration during each period.
- c. Strontium-89, 90, and Iron The total release values are measured quarterly from composite samples.
Enclosure 1 to. Serial: RNPD/92iO409 Page 11 of 54
- - C. Estimated Total Errors
- 1. Estimated totel errors for gaseous effluents are based on uncertainties in counting egtipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
- 2. - Estimated total errors for liquid effluents are based on uncertainties in counting equipment calibration, counting statistics, non-steady release flow rate, sampling and mixing losses, and volume determinations.
- 3. Estimated total errors for solid waste are based on uncertainties in equipment _ calibration, dose rate measurements, geonstry, and volume determinations.
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Enclosure 1.to Seriali 'RNPD/92-0409 Page 12 of 54
- - .III; ' GASEOUS EFFLUENTS A. Batch Releases 1, Number of Batch Releases 8.70E+01 2, Total Time Period for Batch Releases 6.21E+04 Min 3, Maximum Time Period for a Batch Release 3.96E+03 Min Average Time Period for Batch Releases
, 4. 7.14E+02 Min
- 5. Minimum Time Period for a Batch Release 1.00E400 Min B. Abnormal Releases
- 1. Number of Releases 0.00E+00
- 2. Total Activity Released 0.00E400 Ci C. Data Tables The following tables provide the details of gaseous releases:
Table III-A Summation of all Releases Table III-B -Ground Level and Mixed Mode Releases Table III-C Lower Limits of Detection I
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Enclosure 1.to Serial: RNPD/9220409 Page 13 of 54 TABLE III-A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1991 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNITS 3RD OUARTER 4TH OUARTER
. A. Fission and Activation Gases:
- 1. Total Release ~ Ci 6.08E-01 7.03E-02
- 2. Estimated Total-Error % 6.00E+01 '6.00E+01
- 3. Average Relaase Rate for Period pCi/sec 7.65E-02 8.84E-03
- 4. Percent of 10CFR50, Appendix 1 Ouarterly Limit Gamma Air % 2.83E-01 2 . 9 7 E - 0_1 Beta Air % 5.03E-02 5.44E-03 Annual Limit Gamma Air % 1.60E-01* 1.75E-01*
Beta Air % 6.56E-02* 6.84E-02*
B-. Iodines, Particulates, and Tritium:
- 1. Total Iodine - 131 Ci <LLD <LLD
- 2. Estimated Total Error % 4.00E+01 -4.00E401 3, Average Release Rate for Period pCi/sec <LLD <LLD Particulates-
- 1. Particulates with Half-Lives
. >8' days Ci 6.78E-05 5.09E-05
- 2. Estimated Total Error % 4.00E+01 4.00E+01
.3. Average Release Rate for Period Ci/sec 8.53E-06 L40E-06
- 4. ' Gross Alpha Radioactivity Ci <LLD <LLD
' Tritium
- 1. Total Release ci 1.59E+00 8.22E-01
- 2. Estimated Total Error- % 3.00E+01 3.00E+01 l
- 3. Average Release Rate for Period- _ pCi/sec 2.00E 1.03E-01'
! . Percent.ofL10CFR50,' Appendix I
~
Quarte rly Limit t Organ Lune % 3.57E-01 2.01E-01.
Annual Limit Organ Lune % 3 . 9 6 E- 01* 4 , 9 6 E- 01 *
- Cumulative total for the year-to-date..using;the methodology in the ODCM.
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Enclosure 1 to Serial: RNPD/92-0409
_j_ ,. .Page 14 of 54-TABLE III-B EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT - 1991 GASEOUS EFFLUENTS - CROUND LEVEL AND MIXED MODE RELEAS.1 CONTINUOUS MODE BATCH MODE UNITS 3RD OUARTER 4TH OUARTER 3RD OUARTER 4TH OUARTEP,
-1. FISSION GASES
-Ar-41 Ci 4.20E-01 <LLD 1.75E-01 6.21E-02
~Kr-85 Ci 2.53E-03 <LLD <LLD <LLD '
Xe-133 Ci 1.89E-05 <LLD 9.67E 03 8.22E 03 Xe-133m- Ci <LLD <LLD 7.07E-06 8.70E-06 Xe-135 Ci <LLD <LLD 2.53E-06 <LLD Total'for 'Ci 4.23E-01 <LLD 1.85E-01 7.03E-02
- Period-
- 2. 10 DINES 1 1-131 Ci <LLD <LLD <LLD <LLD I-133 Ci <LLD <LLD <LLD <LLD I-135- Ci <LLD <LLD <LLD <LLD Total for Ci <LLD <LLD <LLD <LLD Period
- 3, PARTICULATES1 Co-60 Ci <LLD <tLD 6.66E-05 4.95E-05 Cs-137 Ci- <LLD 4.52E 08 1.23E-06 1.37E-06 Total for Ci <LLD 4.52E-08 6.78E 5.09E 05
-Period I
MixedfMode. Continuous Accountability includes Mixed . Mode . Batch Accountability
.(excludes H-3).
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EnclosureEl to Serial: -RNPD/92-0409
- y. _. ,.
Page 15 of 54-TABLE III-C TYPICAL LOWER L1MITS OF DETECTION FOR GASEOUS EFFLUENTS NUCLIDE LLD (uci/ce)
H-3 1,00E-06 Ar 41 5.83E-09 Mn 54 1.00E-11 Co 58 1.00E 11 Fe-59 1.00E 11 Co-60 1.00E 11 Zn-65 1.00E-11 Kr-85 2.88E-06 Kr-85m 6.49E-09 Kr-87 1.00E-04 -
Kr 88 1.00E-04 Sr-89 1.00E-11 Sr-90 1.00E-11 Mo 99 1.00E-11
, 1-131- 1.00E-12 1-133 1.00E-10 Xe-133 1.00E-04 Xe-133m 1.00E-04 Cs-134 1.00E-11 1-135 2.87E-10 Xe-135 1.00E-04
.Xe-135m 2.28E-07 Cs-137 1.00E-11 Xe-138 1,00E-04 Ba-140 2.69E-14 La-140 7.55E-14 Ce-141 -liOOE-11
-Cc-144 1.00E-11.
Gross Alpha -1.00E-11 _
mm. .
-Enclosure 1 to Serial: 'RNPD/92-0409
- Page 16 of 54 IV. LIQUID EFFLUENTS A. Batch Releases
- 1. Number of Batch Releases 5.00E+01
- 2. Total Time Period for Batch Releases 9.57E403 Min
'3. Maximum Time Period for a Batch Release 3. 31 E+02 Min 4 Average Time Period for Batch Releases 1.91E+02 Min
- 5. Minimum Time Period for a Batch Release 1.80E+01 Min
- 6. Average Stream Flow During Release Periods 5.28E+05 GPM B. Abnormal Releases
- 1. Number of Releases 0.00E400
- 2. Total Activity Released 0.00E+00 Ci _
C. Data Tables The following tables provide the details of liquid releases:
Table IV-A Summation of all Releases Table IV-B Liquid Effluents Table IV-C Lower Limits of Detection
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Enclosure'1 to Serial:
RNPD/92 0409 Page 17 of 54 TABLE IV-A
,FJJJUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1991 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES UNITS 3RD OUARTER 4TH OUARTER A. FISSION AND ACTIVATION PRODUCTS
- 1. Total Release- Ci 6.08E-02 5.11E-02
- 2. Estimated Total Error % 2.00E+01 2.00E+01 .
- 3. Average Diluted Concentration pCi/ml 2.26E-10 1.96E-10 B. TRITIUM
- 1. Total Release Ci 5.86E+01 1.09E+02
- 2. Estimated Total Error % 1.00E+01 1.00E+01
- 3. Average Diluted Concentration pCi/ml 2.18E-07 4.18E-07 C. DISSOLVED AND ENTRAINED GASES
- 1. Total Release Ci 9.56E-03 1.14E-02
- 2. Estimated Total Error % 2.00E+01 2,00E401
- 3. Average Diluted Concentration pCi/ml 3.56E-1) 4.38E-11
- 4. Percent of Applicable Limit % 1.78E-05 2.19E-05 D. GROSS ALPHA RADIOACTIVITY.
- 1. Total. Release Ci <tLD__ <LLD
- 2. Estimated Total Error % 6.00E+01 6.00E+01
.E. - VOLUME OF WASTE RELEASED Liters 8.12E+05 6.43E+05
-F.
=
LVOLUME OF DILUTION WATER Liters 2.69E+11 2.61E+11 E. G PERCENT OF 10CFR50;-APPENDIX I Quarterly Limit-Organ GI-LLI- 5 5.03E-02. NA Organ' LIVER -% NA 2.42E-02
. Total Body % 1.02E-01 -5.34E-02 -!
-Annual Limit Organ GI-LLI % -- - 4. 44E- 01* 4. 5 2 E-01*
Total' Body.. % 7.44E-01* 7 . 71 E-01*
'* Cumulative total-for the year-to date using the' methodology in the- I ODCH:
Enclosure 1 to Serial: RNPD/92 0409~
Page 18 of 54 TABLE IV-B '
EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT - 1991 L10UID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES CONTINUOUS MODE BATCll MODE
.1. PARTICULATES U.JITS 3RD OUARTER 4TH OUARTER 3RD OUARTER 4TH OUARTER F-18 Ci <tLD <LLD 3.41E-06 <LLD Cr-51 Ci <LLD_ <LLD 9.30E 05 <LLD Mn 54 Ci <LLD <LLD 1.14E-03 2.70E-06 Fe 55 Ci <LLD <LLD L15E-04 4.74E-02 Co-57 Ci <LLD <LLD 5.63E 05 <LLD Co-58 Ci <LLD <LLD 5.04E-03 1.48E-04 Co-60 Ci <LLD < LIB 3.64E-02 2.45E-03 Nb 95 Ci <LLD <LLD 9.66E 06 1.66E-05 Zr 97 Ci <L1.D <LLD 4.74E-04 <LLD Ru-106 Ci <LIS <LLD 1.02E-04 <LLD Ag 110m -Ci <LLD <LLD 9.70E-03 '.81E-04 Sn-113 Ci <LLD <LI.D 6.17E-05 <LLD Sb 125 Ci <LLD <LLD 6.46E-03 .78E-04 Cs-134 Ci <LLD <l.LD 1.66E-06 t.80E-06 Cs-137 Ci < tim <LLD_ 3.04E-04 ,22E-04 Total for. Ci <LLD <LLD f,LJ}8 E-02 5.11E-02 Period
- 2. CASES Xe-133 Ci <LLD <LLD L4 3E-03 1.12E-02 Xe-133m Ci <LIS <tLD 1.20E-04 1.62E 04 Xe-135 Ci- <LLD <LLD 8.67E-06 2.29E-05 p.atal for Period Ci <tLD <LLD 9.56E-03 1.14E-02 l
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Enclosure 1 to Serial: RNPD/92 0409 Page 19 of $4 TABL2 IV C TYPICAL IDWER LIMITS OF DETECTION FOR L10U1D EFFIAIENTS NUCLlDE L1.D (nCi/ce) 11 3 1.00E 05 F 18- 1.61E 07 Cr-51 9.91E 08 Mn 54 5.00E 07 Fe 55 1.00E 06 Co 57 6.32E 09 Co 58 5.00E 07 Fe 59 5.00E 07 Co 60 5.00E 07 .
Zn 6$ 5.00E 07 Sr 89 5.00E 08 " ~ '
Sr 90 5,00E 08 Nb-95 2.21L-08 Zr 95 3.97E 0B Zr 97 2.00E 07 Mo 99 5.00E 07 Tc 99m 1.54E 08 Ru 106- 1.84E 07-Ag 110m 2.01E 08 Sn 113 1.81E408 Sb 125 4.33E 08 131 1.00E 06 Xe 133 1.00E 05 Xe 133m 1.00E 05 Cs 134 5.00E 07 Xe 135 1.00E 05 Cs 137 5,00E 07 Ba 140 6.72E 08 La 9 'O 5.27E 08 Ce-141 5.00E 07 Ce 144 5.00E 07 Cross Alpha 1.00E 07 i
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Enclosure 1 to Serial: RNPD/92-0409 Page 20 of 54 V. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS REPORT TIME PERIOD JULY 1 THROUGH DECEMBER 31. 1991 A. SOLID WASTE SHIPPED OFFSITE FOR EL' RIAL OR DISPOSAL (not irrad.ated fuel)
VASTE CLASS A Type of Vaste Unit 6-Month Est.. Total Solid. Cont. Form No.
i Period Error (%) Agent Type Ship.
- a. Spent resins, filter sludges, m3 8.47E+00 2.00E+01 NA HIC Dewatered 2 evaporator bottoms, etc Ci 9.43E+00 2.00E+01 Resin
- b. Dry compressible waste, m3 9.25E+00 2.00E+01 NA STP Compacted / 17 contaminated equip, etc ci 3.74E-01 2.00E+01 Uncompacted
- c. Irradiated components, cot. trol m3 NA NA NA NA NA NA rods, etc Ci
- d. Other (describe) m3 NA NA NA NA NA NA Ci HIC - High Inte5rity Container STP - Strong Tight Package
Enclosare 1 to Serial: RNPD/92-0409 Page 21 of 54 .
Estimate of major nuclide composition (by type of waste) 3. Solid k'aste Disposition s 2 ..
Number of Shipments 19 l
Mode of Transportation Sole Use 'lehicle l Destination B.,rnwell. S.C.
% Ci I !
- a. C-14 2.47E+00 2.33E-01_-
Fe-55 4.39E+01 4.14E+00 co-58 2.30E400 2.17E-01 Co-60 3.58E+01 3.38E+0C Ni-63 8.02E+00 7.57E-01 Sb-125 1.88E+00 1.77E-01
- Others 5.62E+00 5.30E-01
- b. Cr-51 4.14E+00 1.55E-02 Fe-55 6.74E+01 2.52E-01 l Co-58 5.83E+00 2.18E-02 Co-60 1.30E+01 4.85E-02 Ni-63 8.26E+00 3.09E-02 Nb-95 1.39E400 5.20E-03 I-129 3.?3E-02 1.21E-04
- Others 3.23E-02 1.21E-04
- Others include: H-3, Mn-54 Tc-99, I-129, Cs-134 Cs-137, Ce-144, Pu-238, Pu-239, Pu-240, Am-241, Pu-241, cm-243, Cm-244
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i F.nclosure 1 to Serial: RNPD/92 0409 ;
Page 24 of 54 r VI. ANNUAL CATEOUS DOSE ASSESSMENTS ;
A. Population Distribution i i
The population dist ribution was taken itom the Updated FSAR 2.1.3 based on the 1980 j U.S. Bureau of the Census data projected for the year 1986, t
B. Food Production Distribution !
Food yields of agricultural commodities were calculated with the aid of factors published by the USDA . The input parameters for commodities were based on a l
den araphic study performed in September 1987 by the Operations Training and Technical Services Department at the Shearon llarris Energy and Environroental Center. ;
i C. Food Production Totals i
The total quantity of vegetable products within a 50 mile radius of the Robinson Plant is 1.793E408 kilograms per year. .
The total quantity of meat and egg production within a 50 mile radius of the Plant is 9.45E407 kilograms per year. ;
The total quantity of milk production within a 50 mile radius of the Plant is 3.56E407 liters per year.
- D. Source Terms and Meteorological Inputs ,
The annual source terms were segregated by modes of release (mixed mode batch, mixed mode continuous, ground level continuous, and ground 1cvel batch) for dose calculations.
The concurrent meteorology calculations ware performed using the XOQD0Q program with open terrain / recirculation factors (derived from 1978 Dames and Moore study) to compliment the above modes of releases. The inixed mode batch release meteorology ,
used the appropriate X/Q probability level to adjust for more adverse dif fusion conditions since batch releases are not random.
The dissolved-and entrained noble gas source terms of liquid ef fluents were included with the gaseous source terta of ground level continuous airborne effluents for dose assessments.
E. Maximum '.ndividual Doses To demonstrate conformance with 10CPR50, Appendix 1, doses were calculated for all sectors -for the hypothetical raaximum individual at the site boundary, the '
hypothetical ' maximum onsite member of the public and the true offsite maximum individual with nearest resident, garden and meat pathways. The doses from the cow / goat in11k man pathways were excluded since there is no known milk production within a five toile radius of the 11. B. Robinson site based-on 1985 through 1991 land ,
use-census reports.
2 0SDA:EPsS, " Conversion Factors and Weights and Measures for agricultural Commodities and Their Products," Statistical Bulletin No. 362 (June 1963).
, _ _ . , _ _ _ , . - ,a, _ _ . _ _ . _ _ _ _._ . _ _ _ , . _ _ _ _ _ _ , _ , _ _ . _ _ _ _. _ _ _a
Enclosure 1 to Serial: RNPD/92 0409 Page 25 of 54 The flypothetical Maximt.m ludividual at the site boundary (SSE Sector) used for I Technical Specification cortpliance has the highest doses (Table VI A). The true i offsite maximtun individual doses are stunmariz ed in Table VI B. The onsite hypothetical rnaximtun teember of the public doses are summarized in Table VI C. 1 F. Integrated Population Doses i
i Since there is no known railk production within the five raile radius of the H. B. Robinson site, the inilk productions, listed in Section C (Food Production Totals), were used beyond the five taile radius for the integrated population doses.
The offsite annual integrated population doses are sunanarized in Table VI D.
C. Onsite Integrated and Recreational Population Doses for 1991.
3
- 1. The as se s sin nt of the radiation doses from radioactive gaseous effluents to members of the public due to their activities inside the site boundary are listed in Table VI E.
t l
l l
A, A m , vnen ,---, ,- -, , ~,_.. ,-~~---,,n.-,~,~--,..
l Enclosure 1 to Serial: RNPD/92 0409 Page 26 of 54 .
The following assumptions / site specific data were used to assess the onsite total integrated and recreational population doses from gaseous effluents during }
1991. }
ESTIMATED SITE USAGE DATA l 6CTIVITY LOCATION USAGE Spouses in East Lot 6 people / day, 15 min./ day, 240 days /yr Parking Lot West Lot 2 people / day, 15 min./ day, 240 days /yr Picnicking Picnic Area 10 picnics /yr, 100 peopic/ picnic, 4 hrs / picnic !
Occupational Darlington 17 employees, 240 days /yr, 8 hrs / day Co, Plant Visitor Ctr. 1 employee, 240 days /yr, 8 hrs / day Visits Visitor Ctr. 4000 visitors, 2 hr/ visit Swimming Lake Robinson 1000 people / day, 180 days /yr, 2 hrs / day hoating Lake Robinson 100 boatc/ day, 4 people / boat, 365 days /yr t
Shoreline Lake Robinson -1000 people / day, 180 days /yr, 4 hrs / day .
l
-Fishing Lake Robinson 14 people / day, 365 days /yr, 6 hrs / day
- 2. The following exposure. pathways were used for the dose assessment based on the activities listed below:
ACTIVITY EXPOSURE PATHWAY Spouses in Parking Ground Plane, Inhalation, Plume lo t -
Picnicking' Ground Plane, Inhalation, Plume occupational Ground Plane, Inhalation, Plume Visits - Ground Plane, Inhalation, Plume ,
Swidming Inhalation, Plume i
Boating Inhalation, Plume Shoreline Ground Plane,: Inhalation, Plume.
Fishing Inhalation, Plume
..__._.a_u,. . , _ ~ . _ . _ . ~ _ . , _ - . -a_-___,, _ - . ,
_. _ . _ _ . . ~ _ _ __ __._. -_____ - _ _ _ _ . ._ .._ _ . _ .m_ _
Enclosure 1 to Serial: RNPD/92 0409 Page 27 of 54
- 3. The assumptions below were used for the doso assest. ment of the maximum onsite individual,
- a. The maximum onsite individual is an adult.
- b. The exposure pathways are the same as in 2 above.
- c. The site usage assumptions are as follows:
- DISTANCE ACTIVITY OR LOCATION METERS SECTOR TOTAL ll0URS Swimming 803 E 6.80E+01 803 ENE 6.80E401 803 NE 6.80E+01 2414 NNE 6.80E401 3219 N 6.80E401 Boating 803 E 3.80E+01 803 ENE 3.80E401 803 NE 3.80E401 2414 NNE 3.80E401 3219 N 3. 80E4 01 Fishing 803 E 8.00E+01 803 ENE 6.00E401 803 NE 8.00E401 2414 NNE 8.00E401 3219 N 8.00E401 Shoreline 1303 ENE 1.70E402 i 2529 NE 1.70E402 Visitor Center 302 S 2.00E+00 Darlington Co. Plant 1062 NNW 1.92E403 Picnic Area 402 SE 4.00E401 West Parkin6 Lot. 402 SW _6.00E401 East Parking Lot 201 SE 6.00E401- !
- 4. The following data was used in assessing, integrated onsite dose. 1 LAKE ROBINSON DISTANCE: ,
METERS SECTOR (TOTAL llRS) (% 1AKE SURFACE) - Il0URS PERSON YRS
.3219 N 1. 25E4 06 0.71 - 8.875E405 101 2414 NNE' 1. 25E4 06 0.13 - 1.62SE+05 19 803 NE. 1.25E406 0.08 - 1.000E+05 11 803 ENE 1. 25E4 06 0.06 - 7.500E+04 9.
603 E 1.25E406 0.02 - 2. 500E4 04 - 3 TOTAL -
1.250E+06 143 ,
t
--,,_..m.. - . .-,y... . , , - ,e~ ,,_.m , --n, ,-_.%,,r. . ~_w vm . ,,m., -, ,. . , _ y . ,e
Enclosure 1 to Serial: RNPD/92 0409 Page 28 of $4 OCCtfPATIONAL DISTANCE METERS - l# CATION SECTOR 101AL 110URS PERSON YRS 1062 Darlington NNW- 3.26E404 4 Co. Plant i 302 Visitor Center 5 1. 92 E4 03 1 i
DTilFR l DISTANCE !
METERS }pqCATION SECTOR TOTAL liot)JRM ffRSON-YRS 201 East Lot SE 3.608402 0.1 402- West Lot SW 1.20E402 1 l 402 Picnic Area -SE 4.00E403 0.9 .
302 Visitor Center S 8.00E+03 1 2529 Easterlings/ -NE 3.63E405 42 Atkinsons Landing 1303 Johnson Landing ENE 3.63E405 41 11 . DATA TABLES -
+
The following tablea provide the details of the Annual Gaseous Dose Assessments:
Table VI A Ilypothetical Site Boundary Maximum Individual Doses for 1991 Table VI-B True Offsite Maximum Individual Doses for 1991
~ Table.VI-C Onsite llypothetical Maximum Individuni Doses for 1991 Table VI D Offsite Annual Integrated Popalation Doso Summary for 1991 Table VI E Onsite Annual Integrated and Recreational Population Doses for 1991 9
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L 85529 5 L 85213 8 23968 5 23175 5 _
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4 32224 2 323 2 00000 0 000 0 G - - - - - - G - - - -
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0 A T 32323 2 T 323 2 .
4 C C 00000 0 C 000 0 0 I A - - - - - - A - - - -
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O 23318 5 O 231 4 o T T t4 5
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D ENLT L N ENL L L MUAET A A MUA A I UOHGA T F UOH T H LRNEE O N LRN O C PGIVM T I PGI T
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T8 I EEE E I EEE E U4 K 207 8 K 209 8 O S 532 1 S 532 1 S : . .
E 533 4 533 4
- C RN OA TT 323 2 22 2 CS 000 0 00 0 EI G - - - - G - - - -
SD N EEE E EEE U 412 7 3 t 41 1 E
s L 789 8 L 780
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227 3 221 4 D 323 2 D 323 2 I 000 0 I 000 0 O EEE E O EEE E R 31 7 1 R 319 1 1 Y 782 4 Y 782 4 9 H H 9 T 223 3 T 223 3 1 .
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323 2 323 2 I T IV N_l 000 0 000 0 V A I 1 R - - - - R - - - -
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_ A E U ( 223 3 223 3 -
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E N EEE E N EEE E T O 319 8 O 319 8 I B 784 0 . B 780 0 S .
F 225 3 229 3 .
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2 LL R EEE E R EEE E 9 LL T 319 3 T- 319 3
/ I I - 784 4 784 4 I I D MM G 223 3 G 223 3 P '
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532 4 531 4 2 3 23 2 3 23 0 000 0 000
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3 225 3 228 2 323 2 323 D 0 D 000 0 I 000 -
I O E O EEE E R EEE 7 F 317 5 31 1 Y 1 Y 7 89 3 H 786 2 0 H T 3 9 T 222 3 221 1
R O 323 2 3 23 2 F Y 000 0 Y 000 0 - - - -
S E - - - - E E N EEE E E N EEE 7 D 317 5 S D 31 1 I 7 86 2 78 9 3 O I E .
D E 3 221 3 222 Y L A A
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E EEE E n P ID R E EEE E V 31 9 5 i
I L V 313 7 I S N E I 3 7 86 2 L t L 7 89 L n U I L .
3 B I 221 A Co O M M 222 3 E 'T f T( S M A I CX 325 2 326 2 0
A 000 0 000 -
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! Enclosure 1 to Serial:' RNPD/92-0409 ;
i Page 33 L of 54 !
~
! TABLE VI-C l' CASEOUS PATHWAY f
^
ONSITE HYPOTHETICAL MAXIMUM INDIVIDUAL DOSES FOR 1991 j i I (MILLIREM) !
I f
I
! ANNUAL' BETA ' AIR DOSE - 2.03E-04 MILLIRADS SECTOR: NORTH-NORTE'EST' l ANNUAL GAMMA AIR DOSE -- 2.98E-04 MILLIRADS DISTANCE: 1062.0 ME'lt.KS l i .
i
- j. . ADULT TOTAL BODY. -GI-TRACT BONE LIVER KIDNEY THYROID LUNC SKIN
- PLUME 1.98E-04 1.98E-04 1.98E 1.98E-04 1.98E-04 1.98E-04 1.99E-04 3.84E-04 I l' CROUND PLANE 5.17E-04 5.17E-04 5.17E-04 5.17E-04 5.17E-04 5.17E-04 5.17E-04 6.09E-04 INHALATION 1.96E-04 1.98E-04 6.68E-08 1.96E-04 1.96E-04 1.96E-04 2.43E-04 1 96E-04 l f '
i
- - TOTAL -9.12E-04 9.14E-04 7.17E-04 9.12E-04 9.12E-04 9.12E 04 9.60E-04 1.19E-03 i !
t 1
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Enclosure 1 to Serial: RNPD/92-0409 Page 35 of 54 ;
i TABLE VI-E j l
GASEOUS PATIP'AY ONSITE A'iNUAL INTEGRATED AND RECFEATIONAL POPlt\TInN DOSES FOR 1991 i
( PER S0"- RE't)
TOTAL BODY GI -TPACT BCNE LIVER KIDNEY THYROID Li'NG SMIN plt.NE 6.74E-05 6.74E-05 6.74E-05 6.74E-05 6.74E-05 6.74E-05 6.81E-05 1.6AE-04 GROUND PLANE 8.20E-05 8.20E-05 8.20E-05 S.20E-05 S.20E-05 8.20E-05 8.20E-05 9.65E-05 INHALSTION 1.31E-04 1.31E-04 2.27E-OS 1.31E-04 1.31E-04 1.31E-04 1.45E-Oi 1.31E-04 TOTAL 2 . 8 0 E - U-. 2.81E-04 1.49E-04 2.80E-04 2.80E-04 2.80E-04 2.95E-04 3.93E-04 I
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Enclosure 1 to Serial: RNPD/92 0409 Page 36 of $4 V11. M NUAL LlQUlD fl0SE ASSESSMENTS A. Envi royent al inputs and Anunigions in this section, parameters which are used in making dose calculations to individuals and populations are described. Extensive use has been inade of the parameters outlined in NRC Regulatory Guide 1.109, but these have been supplemented, particularly in the case of population doses, with the site specific information. In the calculation of population doses, considerable reliance has been placed on the selection of clearly conservative assumptions.
- 1. Mixing Ratios for all calculat ions , the mixing ratios used to determine concent rations of isotopes at the point of exposure have been conservatively estimated. For calculation of doses to individuals, the mixing ratio of 0.835 was used to account for dilution by the discharge flow, initial dilution in the lake, and accumulation in the lake, for calculation of population doses, a mixing ratio of 0.817 was used. The method of estimating concent rat ions of radionuclides in Lake Robinson and downstream of the lake are given below.
Lake Robinson is supplied by surface runoff in several creeks and discharges as a continuance of Black creek. cotulenser cooling water is drawn from the lower end of the lake and is returned near the upper end.
Liquid waste enters the lake via the condenser cooling water; since the cooling water flow exceeds the flow through the lake, complete itixing may be assumed.
Assuming zero initial concentration and complete mixing, the time dependent concentration of each radionuclide in the lake due to Plant releases will be c , p(1 -e-^t) 2 VA where: C 1 - Average concentration of each radionuclide in the lake (Ci/m ) 3 Q - Rate of addition of each radionuclide into cooling water (C1/yr)
V - Volume of water in lake (m ) 3 A - Effective loss rate constant of each radionuclide from the lake t - Time in years After equilibrium is reached, the average concentration of each radionuelide in the lake will be C"k 2
6 1:ncloc 2re 1 to Serial: RNPD/92 0409 Page 37 of 54 j e . .
Assuming removal of radioactivity from the lake by outflow, but not by !
radioactive decay, the effective loss rate constant is i f
A-j i where: f2- average volumetric flow from lake (ru'/yr)
Af ter equilibritun is reached, the concentration of each radionuclide in Lake Robinson is represented by c.2.2 3 FA t, i
The concentration of each radionuclide in the discharge canal is determined ;
by: 7 Cd< c,
- ca = c, + 79+,
where: Ca is the concentratio:t in the discharge canal (C1/m ) S C 3 is the equilibritun concentration in the lako (Ci/m3)
C, is the concentration added to the water while passing through the plant - Q/f (C1/m 3) f2 is the cooling water flow rate (m 3/yr)
Assuming each gallon of water from discharge canal is diluted with 9 gallons of lake water, the concentration at the edge of the mixing zone c,- -
is ,
C,= ( Cf9 C ) +10 3
. ( 2r + 2 + 92 } +10 3 t, t, a2+ 2-.
t, lot i The mixing ratio at the edge of the mixing zone M is the ratio:
y*, concontration at edge of mixing rono, Ce concentration in 'ilechstge canal Cs .
2 +- P-.
t, 2or 2+2 t, t, 10 f + t,3 10 ( f3 + f,)
P P
,, --- .,,d... - m. , - , - . .,.....w-,=-+ .-.,%-., -....,,---,,,,w_,..e.
.n w.s,-,, -m..-,,.n
-, _. ,,m,-4.w---y.,,-,-,, -we.w,v ,,,...-.,.,,.,-,v. ,,..r,~-w-.,,,-,_r.,--.M
Enclosure 1 to Serial: RNPD/92 0409 Fage 38 of 54 For Robinson f3 - 9.59E8 m8 /yr l and f2 - 2.15E8 m 8/yr 5 t hus f( - 0. 8 35 !
The mixing ratio for the lake in general H is the ratio Equilibrium lake concentration Cs >
Concentration in dis ^ichargo canal , ^Es A ,
, to ,_ f, _
. 9 . _P. f *I n f3 f, ;
For Robinson M3- 0.817 The validity of ignoring radioactive decay was checked by determining which isotopes were the most significant dose contributors. They were C0", Cs*,
and Cs18' All of these isotopes have decay constants which are at least 12 tin.es smaller than the loss rate constant of the lake
$ . 2.15E6m /yr = 4.24 per year .
8 V 5.06E7m' Thus, ignoring normal decay should have little effect.
l For Auburndale Plantation the equation for mixing ratio is e*02 (distance downstream [Km)). Equa':fon was derived from EPA-520/5-76 005 study, i
r 1
I I =.
_.______.m.- _. - .. _ _ - _ _ __..~ _ _.._.._ _.- . . . _ _ _ _ _ -
Enclosure 1 to Serial: RNPD/92 0409 Page 39 of 54
- 2. Potable Vate* Use l r
l There is no potable water use of any water resource which is affected by l the Robinson liquid discharge. Therefore, no pathways involving potable water are evaluated. 1 I
- 3. Irrigated Foods Located ten miles east of Robinson Site, the Auburndale Plantation uses !
water from Black Creek for irrigating during dry seasons. The following ;
are conservative assumptions that. were used for dose calculations:
- a. Meat (beef) [
- 1. No drinking water for cattle irem creek
- 2. Transit time - 1.00E40) hours
- 3. Irrigation rate - 1.00E402 liter /m / month 2 !
- 4. Non irrigated feed fraction - 9.00E 01
- 5. Total 50 mile production - 1.96E+08 kg/yr -
- 6. Total meat irrigated - 1.00E406 kg/yr
- 7. Food process time - 4.80E+00 hours
- b. Produce
- 1. Irrigation rate - 1.00E402 liters /m / month 2
- 2. Total 50 mile production - 6.10E+06.kg/yr
- 3. Total crop irrigation - 4.00E403 kg/yr ,
- c. Leafy vegetables
- 1. Irrigation rate - 1.00E+02 liter /m / month 2
- 2. Total 50 mile production - 2.59E+08 kg/yr
- 3. Total crop _ irrigated - 2.00E403 kg/yr ;
- 4. Other I thways- t ho other pathways which would be likely - to produce 10% of the dose calculated by these pathways described above were identified for the liquid discharge for 11. B. Robinson Unit No. 2.
B. Recreational Activities
- 1. Seasonal Population Variations Within the 10 mile area surrounding the Plant, there are no major seasonal ,
j population variations. _ During the entire year, Lake Robinson is used for fishing, boating, picnicking, and other recreational activities. Based on a~ 1975. creek and recreational survey, the daily summer peak transient population is approximately 550 650 people.. This figure would include people who are boating on- Lake Robinson _ as well as those using shore ,
facilities. Also, during the winter months, Lake Prestwood, located on the l north side of 11artsville, is utilized by local residents for recreation.
- Lake _ Prestwood is a comparatively small body of water, and it is estimated that 50-100 people would be using the area on a peak day. Based on this survey,- the seasonal variation did not warrant any special dose assessments.
- . - . _ , - , . _ . . _ . . . , . _ - _ _ . _ _ . _ _ . , _ _ . _ _ . _ _ . . . _ . - - . _ . _ _ , _ _ , _ ~ _ _ - - . . . _ . - .. . _ . -
- - ~ . _ . _ . . - - _ - - - . - - - . = . - . - - . - .
Enclosure 1 to Serial: RNPD/92 0409 [
Page 40 of-54
- 2. Water Recreation for Maximaw Individual Doses !
Because suitable statistics are unavailable, assumptions were made for !
purposes of assessing doses from each of the swimming, boating, and !
shoreline recreational pathways. These assumptions are summarized as ,
follows:
Boating Adult 120 days /yr x 2 hrs / day - 240 hrs /yr Teen - 180 days /yr x 2 hrs / day - 360 hrs /yr i Child - 90 days /yr x 2 hrs / day - 180 hrs /yr l
' Swimming Adult - 90 days /yr x 2 hrs / day - 180 hrs /yr Teen 180 days /yr x 2 hrs / day - 360 hrs /yr ,
Child . 90 days /yr x 3 hrs / day - 270 hrs /yr i
Fresh water fish and shoreline exposure: default to NRC Regulatory ,
Guide 1.109 values.
- 3. Population Doses The following assumptions / site specifica are listed: ,
Water Recreation Da_ta i
Activity Location Usar.e Swimming Lake Robinson 1000 people / day, 180 days /yr, 2 hr/ day IAko Prestwood- 100 people / day 180 days /yr, 2 hr/ day Black Creek 10 people / mile, 50 miles, 180 days /yr, 2 hr/ day Boating. Lake Robinson 100 boats / day, 4 people / boat, 365 days /yr, 2 hr/ day i Lake Prestwood 10 boats / day, 4 peopic/ boat, 365 days /yr, 2 hr/ day Black Creek 1 boat / day, 2- people / boat, 180 ' days /yr, 5.6 hrs / day Shoreline Lake Robinson 1000 people / day, 180 days /yr, 4 hr/ day _
Lake.Prestwood 100 people / day, 180 days /yr, 4 hr/ day Black Creek 10 people / mile, 50 miles,'365 days /yr, 4 hr/ day
- 4. Aquatic Foods (Fish)
_There are-no shellfish or aquatic plants harvested in Lake _ Robinson or within'50 miles downstream of the site. Assuming approximately 8000 fish are taken from the lake each year and-an edible yield of 1 kg per fish, this amounts to 8000 kg per year. An additional . 800 kg per. year' are assumed to come from Lake Prestwood and another 8000 kg from the Black Creek downstream of Lake Robinson.
- - - . . - - . . . . . -.----.-.w--._-. - . . - . . . - . - . . . . . . - . . , a, -
Enclosure 1 to Serial: RNPD/92 0409 '
Vago 41 of 54 C. Maximum Individual Dose To dernonstrat,e conformance of 10CrR50, Appendix 1, doses were calculated for all the age groups for the total body and all organs using the fish, shoreline, swimining, and boating pathways. The hypothetical maxistun individual dor.cs for the liquid pathway was calculated to show compliance with Technical Specifications. These doses were onsite at the end of the discharge canal in the North sector and are summarized in Tabic Vil A, D. Onsite Inter. rated Population Doses The assessment of the radiation doses from radioactive liquid effluents to rnembers of the public due to their activities inside the site boundary are listed -
in Tabic VII-B.
E. Annuni inter. rated Population Doses The assessment of the annual radiation doses from radioactive liquid effluents within the 50 mile radius of the 11. B. Robinson site (inclusive of the onsite doses) are summarized in Table VII-C.
F. Data Tahics The following tables provide the details of the Annual Liquid Dose Assessment:
Table V11-A 11ypothetical Maximun. Individual Doses for 1991 Table V11-B Lake Robinson (onsite) Annual Integrated and Recreational Population Doses for 1991 Tabic V11-C Annual Integrated Population Dose Sununary for 1991 i
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Enclosure 1 to Serialf RNPD/92-0409 !
Page' ~43 of 54 ,
I
~
TABLE VII-A {
(Continued) r LIQUID PATHWAY [
- HYPOTHETICAL MAXIMUM INDIVIDUAL DOSES FOR 1991 !
- (MILLIREM) i CHILD DOSES i
SKIN BONE- LIVER TOTAL BODY ' THYROID KIDNEY 115G GI-LLI
)- : PATHWAY r- .
1.10E-02: 1.09E-02 2.24E-03 2.20E-04 3.57E-03 1.57E-03 2.33E-03 FISH 0.00E+00 I i SHORELINE. l- 9.21E-04 7.86E-04 7.86E-04 7.86E-04 7.86E-04 7.86E-04 7.86E-04 7.86E-04 j
{ ' SWIMMING- .0.00E+00 1.15E-04 1.15E-04 1.15E-04 1.15E-04 1.15E-04 1.15E-04 1.15E-04 BOATING 0.00E+00 3.83E-05 3.83E-05 3.83E-05 3.83E-05 3.83E-05 3.83E-05 3.83E-05 fi l~ TOTAL' 9.21E-04 1-19E-02
. 1.19E-02 3.18E-03 1.16E-03 4.51E-03 2.51E-03 3.27E-03
< t i
- j. USAGE (KG/YR, HR/YR) DILUTION TIME (HR) SHORE WIDTH FACTOR - 0.3 FISH 6.9 1.2 24.0 SHORELINE 14.0' 1.2 0.0
- SWIMMING 270.0 1.2 0.0 BOATING 180.0 1.2 0.0 -
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Enclosure'1'to Serial: .RRPD/92-0409 Page '44 of 54 TABLE VII-B-LIOUID PATINAY LAKE ROBINSON (ONSITE) ANNUAL INTEGRATED AND RECREATIONAL POPULATION DOSES FOR 1991 (PERSON-REM)
PATINAY BONE LIVER T0fAL BODY Tin ~ROID KIDNEY LLNG GI-LLI SKIN
' FISH 3.87E-03 5.18E-03 2.96E-03 1.40E-04 1.78E-03 7.63E-04 2.84E-03 .0.00E+00 SHORELINE 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.04E-02 4.74E-02
'. SWIMMING 1.53E-04 1.53E-04 1.53E-04 1.53E-04 1.53E-04 1.53E-04 1.53E-04 0.00E+00 BOATING 6.22E-05 6.22E-05 6.22E-05 6.22E-05 6.22E-05 6.22E-05 6.22E-05 0.00E+00 4.45E-02 4.09E-02 4.15E-02 4.74E-02 TOTAL 4.60E-02 4.37E-02 4.25E-02 4.38E-02
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Enclosure 1 to Serial: RNPD/92 0409 Page 46 of 54 VIII. 40CFR190 DOSE CONFORMANCE The direct radiation assessment to the most likely exposed member of the public is l reported in the Annual Radiological Environmental Operating Report. The results of the assessment demonstrate no measurable affect above background from Plant ]
l Operations. Since no 10CFRSO Appendix I limits have been exceeded and the evaluation 1 of the Independent Spent Fuel Storage Installation (refer to Addendum I) indicates [
only a small fraction e.,f the total dose to the environs, this demonstrates conformance with 40CFR190 Environmental Radiation Protection Standards for Nuclear Power '
Operation. !
IX. METEOROLOGICAL DATA A. Continuous Release Diffusion Analysis Table IX A presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological systcm during the period January 1 through December 31, 1991. 4 i
^
The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (10 meter) sensor elevation.
I Pertinent information available from the tables is as follows:
- 1. Stability r
Percent occurrence Pasquill stability categories based on lower level (10m) f wind distribution:
A B C D E F G 2,29 3.11 4.63 35,97 31.49 10.49 12 02 2, Wind Speed 10 Meter t Average Speed (mph) 4.6 Percent Calm 1.1 Percent Less than 3.5-mph 38.4
^
- 3. Vind Direction 10 Meter Prevailing SSW Percent Occurrence 10.2
- 4. Data Recovery 10 Meter Percent Good Hours 97.4
- i l
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Enclosure 1.to Serial: RNPD/92-0409 Page'49 of 54 IX. METEOROLOGICA[fDATA B. Mixed Mode Batch Release Diffusion Analysis Table.IX B presents the number and frequency of wind direction occurrences by wind speed class as recorded at the onsite meteorological system during mixed mode -
batch releases for the period January 1 t.hrough December 31, 1991.
The frequencies are presented as a percent of total occurrences for each stability class as well as a summary for all classes for the lower (10 meter) sensor elevation, l
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Enclosure 1 to Serial: RNPD/92-0409
-Page 52 of 54 ;
-IX, METEOROLOGICAL DATA C. Ground Level Batch Release Dif fusion Analysis Table IX-C presents the number and frequency of wind direction occurrene s by wind speed class as recorded at the onsite meteorological system during ground level
~
batch releases for the period January 1 through December 31, 1991, The frequencies are presented as a percent of total occurrences for each stability
' class as well as a summary for all classes for the lower (10 meter) sensor elevation.
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Enclosure 2 to Serial: RNPD/92-0409 .
Page I of'48i i*
CHANGES TO ODCM,-PCP, AND RADIOACTIVE WASTE SYSTEMS TABLE OF CONTENTS Enclosure 2 ,
Description Pare [
r
~I. Changes to the'0DCM . . . . . . . . . . . . . . . . . . . . . . . . . . 2 II. Changes to the Radioactive Waste Systems . . . , , , . . . . , . . . 48 I I I . -- Changes to the Process Control Program . . . . . . . . . . . . . . . . . 48 IV. Changes to the Land Lee Census . . . . . . . , , , , . . . . . . . . . . 48 V. Instrument _Inoperability . . . . . . . . . . . . . . . . . . . . 48 VI. _ Liquid Holdup Tank Curie Limit . . . . . . . . . . . . , . . . . . . . 48-VII. -Waste Gas Decay Tank Curie Limit . . . . . . . . . . . . . . . . . . . 48 Independent Spent Fuel Storage Installation . . .
~
- VIII. . . . . . . . . . 48 l
- 1X. Di po1al-of Boiler Chemical Cleaning Waste . . . . . . . . . . . . . . .
- 48 9
_(-:. --
.. , .w, ,.,n.-~-;--
Enclosure [2-toSerial: RNPD/92-0409 LPage 2 of 48 -
1 1
- 1. CilANGES TO THE ODCM j Este No - Comments / Justification for channes in ODCM Revision 7 Title Page - Changed Revision 6 to Revision 7 and changed date i- See Justification A, C, and 8 2-1 See Justification A and B 2-3 See Justification A and B 2-4 See Justification A 2-5 See Justification B 2-6 See Justification A 2-14 See-Justification A and B 2-22 Corrected the headers for the columns in Table 2.3-1 (minor editorial change) 3-1 See Justification A, B, and C 3-2 See Justification D 3-3 See Justification A and C 3-4 See Justification C 3-5 See Justification C 3 See Justification A and C 3-7 See Justification C 3-8 See Justification C 3-9 See Justification D 11 See Justification A and C 3-13 See Justification A and C 3 See Justification C and.D 3-16 See Justification D 3 18 See Justification D 3-19 See Justification C 3-23 See Justification D
'3-24 See Justification D 3-27. In equation 3.3-8, the inhalation dose contribution from mixed mode batch releases was added 3 28 See Justification D 3-29 Minor editorial changes; _ the Qw added " plant vent" in lieu of " vent" 13-30 See Justification D 63 . See: Justification A 3164_ See LJustification A
- 3-65 See Justification A.
3-67 See -Justification C 3-68 - See Justification A and C 69 See Justification C-
- 70 See: Justification C 711 See Justification C =and E
=3v72 _ See Justification E 3 See Justification E 3-'74 See Justification-E
-D-li See Justification A and B D-21 See , Justification A and C -
-D-3 See Justification Af and B
-D-4 See Justification A and C d
-, - w , w a , e
Enclosure 2-to Serial: RNPD/92-0409 Page;3 of 48-Justification for Chance in ODCM Revision 7 A. The Radiation Monitoring System's nomenclature for valves is RMS # and for radiation monitors is R #. All monitors in the ODCM have been changed from RMS # to R #,
-B. Plant modification #898 replaced Steam Generator Blowdown monitor R 19 (which monitored all three steam generators) with three monitors (R-19A, _
R-19B, and R-190) one for each respective generator.
C. Plant modification #1005 replaced R-14, R-34, R-35, and R-36 with R-14A, R-14B, R-14C, R-16D, and R-14E using isokinetic sampling. R-35, R-36, R-14D, and, R-14E are accident monitors and are not germane to this document.
The modification also deleted the isolation function of R-15-(condenser vacuum pump vent) whien vented to atansphere and diverted flow to the plant vent stack upon high alarm. This modification allows continuous venting to the plant vent stack (an additional 300 cfm per pump) which is monitored by R-14A, R-14B, and R-14C. This required a Technical Specification change (Amendment No. 131). The methodology for R-15 setpoint calculation has been removed from the ODCM and is controlled by approved plant procedures. R-14A (particulate monitor) replaced the R-34 beta channel and R-14B replaced the R-34 iodine channel, D. . Robinson Plant has four types of releases; mixed mode continuous, mixed mode batch, ground level continuous, and, on rare occasions, ground level batch. For clarification purposes, the annual average relative dilution factors (X/Q) have been redefined and referenced to - the vents to .which they may apply.
E. The ~.setpoint methodology for R-u (Environmental & ' Radiation Control Building exhaust) and for R-23 (Radwnste Building exhaust) iodine and particulate channels have been included in this revision.
9 1
. , , -,n . ---