BSEP-94-0075, Semiannual Radioactive Effluent Rept Jul-Dec 1993
| ML20067D006 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/31/1993 |
| From: | Cowan J CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BSEP-94-0075, BSEP-94-75, NUDOCS 9403070239 | |
| Download: ML20067D006 (77) | |
Text
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CP&L . . , , .
Carolina Power & Light Company suem---mwmemamm j' Brunswick Nuclear Plant P. O. Box 10429 Southport, NC 28461-0249 FEB 251994 l
File: B09-13510C Serial: BSEP 94-0075 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, DC 20555- 4 1
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1' AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen: j Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick Steam Electric Plant, covering the period from July 1,1993, through December 31,1993.
This Report is submitted for the Brunswick Steam Electric Plant in accordance with Technical l
Specification 6.9.1.8.
Very truly yours, )
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M MC---- J J.Cowan Acting Director - Site Operations SHC/shc (BSEP 94-0075.000)
Enclosure .
1 cc: Mr. S. D. Ebneter, Region 11 - Administrator Mr. P. D. Milano, NRC/NRR Senior Project Manager - Brunswick Mr. R. L. Prevatte, NRC Senior Resident inspector - Brunswick (
9403070239 931231 7 PDR ADOCK 05000324 R
PDR dl _
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Brunswick Steam Electric Plant Semiannual Radioactive Effluent Report July 1, to December 31, 1993 l
ATTACHMENTS: PAGES: ,
l 1.~ Supplemental Information 2 - 6
- 2. Effluent and Waste Disposal Data 7- 21
- 3. Environmental Monitoring Program 22 - 24
- 4. Effluent Instrumentation 25 - 28
- 5. Major Modification to Radioactive Waste 29 i Treatment Systems l
- 6. Meteorological Data 30
- 7. Annual Dose Assessment 31 - 49
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! ATTACHMENT 1
! Supplemental Information a
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l July 1, to December 31, 1993 i
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l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plarr Licensee: Carolina Power and Light Company.
' 1. Regulatory Limits I
A. Fission and activation gases (Technical Spec. 3.11.2.2)
- (1) Calendar Quarter 1 (a) 10 mrad gamma (b) 20 mrad beta (2) Calendar Year (a) 20 mrad gamma (b) 40 mrad beta B. Iodine-131, iodine-131, tritium, and particulates with half-lives greater than eight days (Technical Spec. 3.11.2.3)
- (1) Calendar Quarter i
(a) 15 mrem to any organ (2) Calendar Year (a) 30 mrem to any organ
- (3) Calendar Quarter for Burning Contaminated Oil (a) 436 uCi (4) Calendar Year for Burning Contaminated Oil (a) 872 uCi C. Liquid effluents (Technical Specification 3.11.1.2)
- * (1) Calendar Quarter (a) 3 mrem to total body (b) 10 mrem to any organ l
(2) Calendar Year (a) 6 mrem to total body (b) 20 mrem to any organ NOTE: Dose calculations are determined in accordance with the l Off-Site Dose Calculation Manual (ODCM)
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- Used for percent of Technical Specification limit determinations in Table 1A,
- *Used for percent of Technical Specification limit determinations in Table 2A, i Page 3
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- 2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and activation gases (Technical Specification 3.11.2.1.a)
(1) 500 mrem / year to total body j (2) 3000 mrem / year to the skin j l
B. Iodine-131, iodine-133, tritium, and particulates with half- !
lives greater than eight days (Technical Specification !
3.11.2.1.b)
(1) 1500 mrem / year to any organ C. Liquid effluents (Technical Specification 3.11.1.1)
The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to the concentrations specified in 10CFR20, Appendix B.
- * (1) Tritium: limit = 1 E-03 uCi/ml and
- (2) Dissolved and entrained gases: limit = 2 E-04 uCi/ml
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases Analysis for specific radionuclides in representative grab samples by gamma spectroscopy.
B. Iodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.
C. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.
D. Particulates for Burning Oil Analysis for specific radionuclides by grab samples of each batch of oil to be burned.
E. Liquids Effluents I
Analysis for specific radionuclides of individual releases by gamma spectroscopy.
- Used as applicable limits for Table 2A Page 4
Nuclear counting statistics are reported utilizing 1-sigma error.
Total error where reported represents a best ef fort to approximate the total of all individual and sampling errors.
- 4. Batch Releases A. Liquid (1) Number of batch releases: 2.27E+02 (2) Total time period for batch releases: 2.29E+04 Minutes (3) Maximum time period for a batch release: 1.65E+02 Minutes (4) Average time period for a batch release: 1.01E+02 l Minutes (5) Minimum time period for a batch release: 1.40E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream : 6.01E+05 GPM B. Gaseous l
l (1) Number of batch releases: 0.00E+00
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(2) Total time period for a batch release: 0.00E+00 Minutes 1
(3) Maximum time period for a batch release: 0.00E+00 l l Minutes )
I (4) Average time period for a batch release: 0.00E+00 Minutes (5) Minimum time period for a batch release: 0.00E+00 l Minutes
- 5. Abnormal releases
- A. Liquid (1) Number of releases: 0.00E+00 (2) Total activity released: 0.00E+00 Curies B. Gaseous (1) Number of releases: 0.00E+00 (2) Total activity released: 0.00E+00 Curies
- There were no abnormal releases that exceeded 10CTR20 or 10CFR50 limite. See Page 6 for a discussion of release events that occurred.
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- 1. Discussion of Tritium in the Storm Drain Collection Pond Approximately -1.67E+07 gallons containing 1.31E+00 curies of tritium were released from the Storm Drain Collection Pond (SDCP) to the Intake Canal during this reporting period. The SDCP is a permitted release point.
NOTE 1: Curie totals are included in the quarterly summaries in Table 2A and 2B.
NOTE 21 The quantity of rainwater released from the Storm Drain Collection Basin and/or the Storin Drain Collection Pond is not included in VOf.tME OF WASTE on Table 2A.
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4 ATTACHMENT 2 Effluent and Waste Disposal Data Brunswick Steam Electric Plant July 1, to December 31, 1993 Enclosure 1 Table 1A: Gaseous Effluents - Summation of all Releases Table 1B: Gaseous Effluents - Elevated Releases Table 1C: Gaseous Effluents - Ground Level Releases ,
Table 1D: Gaseous Effluents - Ground Level Releases for Burning' Contaminated Oil Table 2A: Liquid Effluents - Summation of all Releases Table 2B: Liquid Effluents - Batch Mode Appendix A: Lower Limits of Detection Table 3: Solid Waste and Irradiated Fuel Shipments Enclosure 2 1
Combustion of Waste 011 1 l
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- TABLE 1A i Effluent and Waste Disposal Semiannual Report for Year 1993 Gaseous Effluents - Summation of all Releases 1
Est. Tot.
i Unit Otr 3 Otr 4 Error %
, A. FISSION AND ACTIVATION GASES
- 1. Total release Ci 1.38E+02 1.06E+02 4.50E 01
- 2. Average release uCi/sec 1.74E+01 1.33E+01 rate for period
- 3. Percent of technical
- 2. Average release uCi/sec 1.72E-05 1.36E-05 rate for period C. PARTICULATES
- 1. Total, release Ci 7.57E-04 4.76E-03 3.50E 01
- 2. Average release uCi/sec 9.52E-05 5.99E-04 rate for period
- 3. Gross alpha Ci 1.17E-05 7.46E-06 D. Tritium
- 1. Total release Ci 4.80E+00 1.34E+01 3.00E 01 l
- 2. Average release uCi/sec 6.03E-01 1.69E+00 rate for period E. IODINE-131. TODINE-133, TRITIUM AND PARTICULATES
- 1. Total Release Ci 4.80E+00 1.34E+01
- 2. Average release uCi/sec 6.03E-01 1.69E+00 rate for period
- 3. Percent of technical specification limit % 5.42E-03 8.07E-03 F. PARTICULATES VIA BURNING CONTAMINATED OIL
- 1. Total Release Ci 0.00E+00 0.00E+00
- 2. Average release rate for period uCi/sec 0.00E+00 0.00E+00
- 3. Percent of technical specification limit % 0.00E+00 0.00E+00 Page 8 e- ., . . . , . - .. - ,- _ . . . , . _ . , . .
4 TABLE 1B Effluent and Waste Disposal Semiannual Report for Year 1993 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 3 Otr 4
- 1. FISSION GASES krypton-85m Ci 5.09E+00 6.04E+00
- krypton-87 C1 2.02E+01 1.55E+01 krypton-88 Ci 1.74E+01 1.62E+01
, xenon-133 Ci < LLD 6.87E-01 xenon-135 Ci 2.51E+01 2.26E+01 xenon-135m Ci 1.11E+01 6.64E+00 xenon-138 C1 3.10E+01 1.72E+01 i 1 total for period Ci 1.10E+02 8.49E+01 l l
- 2. IODINES iodine-131 Ci 1.35E-04 1.08E-04 ,
, iodine-133 Ci 6.93E-04 6.37E-04 l total for period Ci 8.27E-04 7.45E-04 l 1
- 3. PARTICULATES
! cobalt-60 Ci 5.20E-06 1.93E-04 l strontium-89 Ci 2.20E-05 4.81E-05 strontium-90 Ci 3.85E-07 1.39E-06 4 cesium-137 Ci 6.50E-06 6.60E-04 l barium-140 Ci 3.69E-05 5.96E-05 i lanthium-140 Ci 3.33E-05 2.65E-05 !
total for period Ci 1.04E-04 9.89E-04 f
- 4. TRITIUM hydrogen-3 Ci 4.08E+00 1.14E+01 Page 9
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TABLE 1C Effluent and Waste Disposal Semiannual Report for Year 1993 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Otr 3 Otr 4 ,
- 1. FISSION GASES krypton-85m Ci 3.23E-01 6.45E-01 xenon-135 Ci 2.43E+01 1.58E+01 xenon-135m gi 3.56E+00 4.52E+00 total for period Ci 2.81E+01 2.09E+01
- 2. IODINES iodine-131 Ci 2.12E-06 9.36E-08 iodine-133 Ci 6.07E-05 2.21E-05 total for period Ci 6.29E-05 2.22E-05
- 3. EARTICULATES chromium-51 Ci 1.62E-04 8.14E-04 manganese-54 Ci 2.31E-05 2.51E-05 cobalt-58 Ci 1.47E-05 4.65E-05 cobalt-60 Ci 4.44E-04 2.88E-03 strontium-89 Ci 2.63E-06 2.44E-06 cesium-137 Ci 2.80E-06 2.00E-06 americium-241 Ci 2.84E-06 < LLD l total for period Ci 6.53E-04 3.77E-03
- 4. TRITIUM hydrogen-3 Ci 7.18E-01 1.95E+00 TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1993 Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released Unit Otr 3 Otr 4
- 1. PARTICULATES total for period Ci 0.00E+00 0.00E+00 Page 10
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4 TABLE 2A Effluer.t and Waste Disposal Semiannual Report for Year 1993 Liquid Effluents - Summation of all Releases Unit Otr 3 Qtr 4 Est Tot
% Error A. FISSION AND ACTIVATION PRODUCTS NoTEi 1." -
release (excluding Ci 2.59E-02 4.94E-02 4,00E01 t ri . gases, & alpha)
NOTE 2
- 2. Avg. diluted conc. uCi/ml 1.10E-09 1.74E-09
- 3. Percent limit % 5.89E-02 6.42E-02 E9r B. TRITIUM
- 1. Total release Ci 1.09E+01 2.71E+01 4.50E 01 NOTE 2
- 2. Avg. diluted conc. uCi/ml 4.61E-07 9.56E-07
- 3. Percent limit % 4.61E-02 9.56E-02 l
C. DISSOLVED ENTRAINED GASES ggig_1
- 1. Total release Ci 2.21E-03 3.30E-03 4.00E 01 NOTE 2
- 2. Avg. diluted conc. uCi/ml 9.36E-11 1.16E-10
- 3. Percent limit % 4.68E-05 5.80E-05 D. GROSS ALPHA RADIOACTIVITY
- 1. Total release Ci < LLD < LLD 4.00E 01 NOTE 2 E. VOLUME OF WASTE liters 6.40E+06 7.13E+06 1.50E 01 1
l F. TOTAL OF DILUTION WATER i (used durina release for averace dil. conc.) liters 2.36E+10 2.83E+10 1.30E 01 G. VOLUME OF COOLING WATER liters 2.87E+11 3.28E+11 DISCHARGED FROM PLANT NOTE la Includes radionuclides released via abnormal and/or non-routine release.
NOTE 2: Does not include rainwater released (ie. Storm Drain Collection Basin and/or Storm Drain Collection Pond.
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TABLE 2B Effluent and Waste Disposal Semiannual Report for Year 1993 Liquid Effluents - Batch Mode Nuclides Released Unit Otr 3 Otr 4
- 1. FISSION AND ACTIVATION PRODUCTS sodium-24 Ci 5.80E-06 < LLD chromium-51 Ci 4.05E-04 1.97E-02 manganese-54 Ci 2.29E-04 8.54E-04 iron-55 Ci 2.51E-03 < LLD manganese-56 Ci < LLD 7.99E-04 cobalt-58 Ci < LLD 1.32E-03 cobalt-60 Ci 2.19E-02 2.44E-02 arsenic-76 Ci 4.47E-05 1.22E-04 strontium-92 Ci < LLD 6.22E-06 technetium-99m Ci < LLD 6.97E-04 silver-110m Ci < LLD 2.83E-05 antimony-125 Ci < LLD 1.77E-04 iodine-131 Ci < LLD 1.18E-06 iodine-133 Ci < LLD 3.54E-07
! cesium-134 Ci 1.53E-04 2.92E-05 Ci cesium-137 6.42E-04 2.65E-04 barium-140 Ci 4.28E-06 < LLD ,
cerium-144 Ci < LLD 2.20E-05 !
tunasten-187 Ci < LLD 1.06E-03 total for period Ci 2.59E-02 4.94E-02 l
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TABLE 2B (continued)
Effluent and Waste Disposal Semiannual Report for Year 1993 Liquid Effluents - Batch Mode Nuclides Released Unit Otr 3 Otr 4
- 2. GASES krypton-85m Ci < LLD 4.23E-06 xe-133 Ci. 3.80E-04 6.80E-04 xe-135m Ci < LLD 1.36E-05 xe-135 Ci 1.83E-03 2.61E-03 total for period Ci 2.21E-03 3.30E-03
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9 APPENDIX A Lower Limits of Detection July through December 1993 uCi/ml
- 1. Licuid Releases 2. Gaseous Releases Na-24 2.01E-08 Xe-133 2.84E-08 Fe-55 2.02E-07 Xe-133m 6.75E-08 Mn-56 9.55E-08 Co-58 1.97E-08 Fe-59 3.90E-08 Zn-65 4.48E-08 Sr-89 2.21E-08 Sr-90 1.14E-08 l Sr-92 4.45E-08 l Mo-99 9.41E-08 Tc-99m 1.50E-08
, Ag-110m 5.31E-08 Sb-125 6.36E-08 3. Iodines and Particulates I-131 1.84E-08 I-133 1.59E-08 Fe-59 7.81E-14 Ba-140 5.49E-08 Zn-65 6.75E-14 Ce-141 2.48E-08 Sr-89 2.40E-15 i
Ce-144 1.38E-07 Sr-90 1.13E-15 W-187 7.05E-08 Mo-99 8.01E-13 Alpha 2.43E-08 Cs-134 5.85E-14 Kr-85m 2.18E-08 Ce-141 3.98E-14 Kr-87 3.86E-08 Ce-144 2.31E-13 Kr-88 6.38E-08 Am-241 1.62E-13 Xe-133m 1.33E-07 Xe-135m 7.28E-08 Xe-138 1.99E-07 l
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NOTES 1: The above values represent typical "a priori" LLDs for isotopes where values of "<LLD" are indicated in Tables 1A, 1B, 1C, 2A, and 2B. Also included are isotopes specified in Technical Specifications.
2: Where activity for any nuclide is reported as " Less than LLD", that nuclide is considered not present and the LLD activity listed is not considered in summary data.
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TABLE 3A Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments Waste Class A July throuch December
- 1. Total volume shinned (cubic meters) 2.24 E2 Total Curie quantity (estimated) 1.05 E3
- 2. Tvoe of Waste Six-month Est. Total Units Period % Error
- a. Spent resins, filter sludges meters3 1.08 E2 Curies 1.05 E3 1.00E1
- b. Dry active waste, compacted meters2 1.16 E2 noncompacted Curies- 4.32 E0 1.00E1
- c. Irradiated components meters3 0.00 E0 Curies 0.00 EO N/A
- d. Others (describe) metersa 0.00 E0 Curies 0.00 EO N/A
- 3. Estimate of maior radionuclide comoosition
- a. Fe-55 6.46 El%
Co-60 2.37 El%
l Ni-63 1.08 E0%
Cs-137 1.15 E0%
Ni-63 2.25 E0%
- c. N/A N/A
- d. N/A N/A 1
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i TABLE 3A (cont.)
Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments
- 4. Cross reference table, waste stream, form, and container tvoe ,
Stream Form Container tvoe No. of shioments
- a. Resin Dewatered & Type A/ Type B 23/0 Solidified *
- b. Dry active Compacted /non- STP 28 l waste compacted waste I c. Irradiated N/A 0 l components l
- d. Other N/A 0
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- Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A
- 5. Sbioment Discosition
- a. Solid Waste Number of Shioments Mode of Transoortation Destination 51 Sole Use CNSI/Barnwell, SC
- b. Irradiated Components Number of Shioments Mode of Transoortation Destination 0 N/A N/A Page 16
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TABLE 3B Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments Waste Class B July throuch December l 1. Total volume shicoed (cubic meters) 2.69 El Total Curie quantity (estimated) 7.58 E2
- 2. Type of Waste Six-month Est. Total Units Period % Error
- a. Spent resins, filter sludges meters 3 0.00 EO N/A Curies 0.00-E0
- b. Dry active waste, compacted, meters 0.00 EO N/A and noncompacted Curies 0.00 E0
- c. Irradiated components meters 3 2.69 El 1.00 El Curies 7.58 E2
- 3. Estimate of maior radionuclide comoosition-
- a. N/A N/A
- b. N/A N/A
- c. Fe-55 3.14 El%
l Co-60 6.57 El% j
! Ni-63 2.84 EO% )
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- d. N/A N/A )
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l TABLE 3B (cont.) l Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments
- 4. Cross reference table, waste stream, form and container tvoe l Stream Form Container tvoe No. of shipments
- a. Resin Dewatered & Type A/ Type B 0/0 Solidified
- 4 l
- b. Dry active Compacted /non- N/A 0 compacted waste
- c. Irradiated Type B 7 components
- d. Other N/A 0 l
- Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A
- 5. Shipment DisDosition
- a. Solid Waste Number of Shioments Mode of Transoortation Destination i
7 Sole Use CNSI/Barnwell, S.C.
- b. Irradiated Fuel Number of Shioments Mode of Transportation Destination 0 N/A N/A Page 18
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i TABLE 3C Effluent and Waste Disposal Semiannual Report for Year 1993 l
Solid Waste and Irradiated Fuel Shipments I
Waste Class C July throuch December i
- 1. Total volume shioned (cubic meters) 4.16 E0 Total Curie quantity (estimated) 2.73 E2
. 2. Type of Waste .Six-month Est. Tot.
Units Period % Error
- a. Spent resins,' filter sludges meters 3 0.00 E0 N/A Curies 0.00 EO
. b. Dry active waste, compacted meters 2 0.00 EO N/A and noncompacted Curies 0.00 E0
- c. Irradiated components meters' 4.16 E0 1.00 El Curies 2.73 E2
- 3. Estimate of maior radionuglide comoosition
- a. N/A N/A
- b. N/A N/A
- c. Fe-55 3.16 El%
Co-60 6.56 El%
Ni-63 2.81 E0%
- d. N/A N/A Page 19
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TABLE 3C (cont.)
Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments l
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- 4. Cross reference table, waste stream, form and container tvoe l l
Stream Form Container Tvoe No. of shipments
- a. Resin Dewatered & Type A/ Type B 0/0 Solidified *
- b. Dry active Compacted /non- N/A 0 waste compacted
- c. Irradiated (Noncompacted Type B 2 components waste; solid oxides)
- d. Others N/A 0
- Solidification agent or absorbent (e.g., cement, urea formaildehyde) N/A
- 5. Shioment Discosition
- a. Solid Waste Number of Shioments Mode of Transoortation Destination 2 Type B Cask CNSI/Barnwell, SC
- b. Irradiated Fuel Number of Shioments Mode of Transportation Destination 8 Rail Car CP&L/SHNNP IF-300 Cask Sole Use i
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ATTACHMENT 2 (cont.)
ENCLOSURE 2 Combustion of Waste Oil July 1, to December 31, 1993' l
During this reporting period, there was no contaminated waste oil l 1
incinerated in the on site incinerator. l
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ATTACHMENT 3 Environmental' Monitoring Program July 1, to December 31, 1993 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census l i
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ATTACHMENT 3 (cont.) 1 ENCLOSURE 1 Milk and Vegetation Sample Locations ,
1 July 1, to December 31, 1993 1 1
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i No milk animals were identified during the,last Land Use Census, I therefore, no milk sample locations were available during this time l l
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Vegetation sample locations remained unchanged. j i
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ATTACHMENT 3 (cont.)
ENCLOSURE 2 Land Use Census July 1, to December 31, 1993 l
The 1993 Land Use Census was performed during the period of June 9 1 to June 10, 1993. No locations were identified that are reportable.in the Semiannual Radioactive Effluent Release Report.
Land Use Census updates are included with the ODCM revision 15 in Attachment 8.
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ATTACHMENT 4 Effluent Instrumentation July 1, to December 31, 1993 l Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation.
l Enclosure 2: Radioactive Gaseous Effluent Monitoring I
I Enclosure 3: Liquid Hold-Up' Tank l
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ATTACHMENT 4 (cont.)
ENCLOSURE 1 July 1, to December 31, 1993 Radioactive Liquid Effluent Monitoring Instrumentation No Radioactive Liquid Effluent Monitoring Instrumentation was inoperable for greater than 30 days.
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ATTACHMENT 4 (cont.)
ENCLOSURE 2 July 1, to December 31, 1993 Radioactive Gaseous Effluent Monitoring Instrumentation No Radioactive Gaseous Effluent Monitoring Instrumentation was inoperable for greater than 30 days.
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I ATTACHMENT 4 (cont.)
ENCLOSURE 3 Liquid Hold-Up Tank July 1, to December 31, 1993 No liquid hold-up tank exceeded the 10 Ci limit during this reporting period.
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4 ATTACHMENT 5 Major-Modifications to the Radioactive Waste Treatment System July 1, to December 31, 1993 l
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As per footnote 7 to Technical Specification'6.15, a discussion )
of any major modifications to the. radioactive waste treatment systems will be submitted with the Final Safety Analysis Report j update.
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,. ,r + .r.e a ,
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! ATTACHMENT 6 1
Meteorological Data
. July 1, to December 31, 1993 4
As per Technical Specification 6.9.1.10.a footnote 6, the annual summary of meteorological data collected over the calendar year will be submitted to a file and will be available for NRC review upon request.
4 9
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Page 30
- * " - ^ ~ - - - > - " - , -.
.. - - . - .. .. . - _ . ._. ~- .. _ . _ . _ - - _ _ _ _ .
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I ATTACHMENT 7 Annual Dose Assessment January 1, to December 31, 1993 l Attached is the annual dose assessment for the Brunswick Steam Electric Plant for the time period of January 1 to December 31, 1993.
Enclosure 1: Annual Liquid Dose Assessment Enclosure 2: Annual Gaseous Dose Assessment Enclosure 3: Dose Assessment Summary l
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Page 31 I .
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l ATTACHMENT 7 (cont.)
ENCLOSURE 1 Annual Liquid Dose Assessment INCLUDED ARE:
Site. Specific Data Source Term As Low As Reasonably Achievable Maximum Individual Dose Summary - Total Integrated and Recreation Population Dose I
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Page 32
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BSEP UNITS 1 AND 2 LIQUID RELEASES 1993 DISCHARGE =1.25E+03 CFS SOURCE TERM MULTIPLIER =1.00E+00
!L SALTWATER SITE I
NO RECONCENTRATION MODEL i i
50-MILE POPULATIONr2.82E+05 FRACTION ~~- ADULT =0.71 ;
TEENAGER =0.11 [
CHILD =0.18 i DOSE FACTOR LIBRARY CONTAINS 698 ENTRIES ,
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HUCLIDE l RELEASE PERSON-REM DOSE I PERSON-REM PER CURIE [
l CI/YR TOTAL B00Y THYRO 10 l TOTAL B00Y j THVROID )
1H 3 1 4.72E+01 1.87E-06 1.87E-06 j 3.96E-08 i 3.96E-08 i 11NA 24 5.80E-06 6.39E-10 6.39E-10 1.10E-04 I 1.10E-04 [
i 24CR 51 2.01E-02 1.19E-07 1.16E-07 5.94E-06 5.77E-06 t 25MN 54- 2.11E-03 3.57E-06 3.11E-06 1.69E-03 1.47E-03 [
25MN 56 7.99E-04 3.27E-08 3.27E-08 4.10E-05 4.10E-05 l 26FE 55 3.65E-03 2.45E-06 2.92E-12 6.72E-04 8.00E-10 -
27CO 58 1.32E-03 6.54E-07 5.57E-07 4.96E-04 4.22E-04
- 27CO 60 7.22E-02 1.65E-03 1.64E-03 2.29E-02 2.26E-02 I 36KR 85M 4.23E-06 0.00E+00 l 0.00E+00 0.COE+00 G.00E+00 l 385R 92 6.22E-06 2.07E-10 2.07E-10 3.33E-05 3.33E-05 5 41NB 95 6.50E-06 1.19E-09 1.05E-09 1.83E-04 1.62E-04 -
43TC 99M 6.97E-04 2.23E-09 2.23E-09 3.19E-06 3.19E-06 {
47AG 110M 2.83E-05 1.08E-07 1.04E-07 3.82E-03 3.69E-03 i 5158 125 1.77E-04 4.38E-07 4.37E-07 2.48E-03 2.47E-03 l 531 131 1.18E-06 { 4.07E-11 4.53E-09 3.45E-05 3.84E-03 :
, 53I 133 3.54E-07 l 5.16E-12 5.37E-12 1.46E-05 1.52E-05 !
54xE 133 1.26E-03 I 0.00E+00 0.00E+00 0.00E+00 0.00E+00 54XE 135 1 5.74E-03 O.00E+00 0.00E+00 0.00E+00 0.00E+00 }
54xE 135M 1.36E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t 55CS 134 2.93E-04 2.64E-06 2.12E-06 9.02E-03 7.22E-03 j 55CS 137 1.72E-03 2.05E-05 1.87E-05 1.19E-02 1.08E-02 i 56BA 140 4.28E-06 'l 1.35E-10 1.19E-10 3.16E-05 2.77E-05 !
! 58CE 144 2.20E-05 l 1.64E-09 1.63E-09 7.44E-05 7.42E-05 l 74W 187 l 1.06E-03 l 1.36E-08 1.36E-08 '
1.29E-05 1.29E-05 fi s I h TOTAL 1.68E-03 1.66E-03 e .
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- i A DULT DOSES (MREM PER YEAR INTAKE) l DOSE l I
PATHWAV SKIN BONE LIVER TOTAL BODY THVROID KIDNEY LUNG GI-LLI I
, FISH 3.16E-05 4.81E-05 4.43E-05 3.91E-06 7.97E-06 1.49E-05 2.96E-04 f i INVERT 4.44E-05 6.70E-05 8.36E-05 1.04E-06 1.6SE-06 1.80E-05 6.63E-04 ,
I SHORELINE 1.80E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03
! SWIMMING 1.03E-06 1.03E-06 1.03E-06 1.03E-06 1.03E-06 1.03E-06 1.03E-06 l BOATING 5.14E-07 5.14E-07 5.14E-07 5.14E-07 5.14E-07 5.14E-07 5.14E-07 l
- TOTAL 1.80E-03 1.61E-03 1.65E-03 1.66E-03 1.54E-03 1 54E-03 1.57E-03 2.49E-03 t
i USAGE (KG/YR.HR/YR) OILUTION TIME (HR) SHOREWIDTH FACTOR =0.5 ,
j FISH 29.2 30.0 24.00
- INVERT 7.3 30.0 24.00 ;
SHORELINE 500.0 30.0 0.00 O SWIMMING 100.0 30.0 0.00 -
I
- $ BOATING- 100.0 30.0 'O.OO Q >
- g T E E N D0SE S (MREM PER VEAR INTAKE) d '
- 3 DOSE i 6
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> PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LONG GI-LLI
- FISH 4.35E-05 6.40E-05 5.51E-05 3.95E-06 9.39E-06 2.16E-05 2.71E-04
)'d INVERT 6.11E-05 9.06E-05 1,12E-04 1.06E-06 1.92E-06 2.82E-05 6.06E-04 i i H SHORELINE SWIMMING 1.80E-03 1.53E-03 1.03E-06 1.53E-03 1.03E-06 1.53E-03 1.03E-06 1.53E-03 1.03E-06 1.53E-03 1.03E-06 1.53E-03 1.03E-06 1.53E-03 1.03E-06
$ i j '
BOATING TOTAL 1.80E-03 5.14E-07 1.64E-03 5.14E-07 1.69E-03 5.14E-07 1.70E-03 5.14E-07 1.54E-03 5.14E-07 1.55E-03 5.14E-07 1.58E-03 5.14E-07 2.41E-03 d
l y O< +
2 d USAGE (KG/YR,HR/VR) DILUTION TIME (HR) SHOREWIDTH FACTOR =0.5 ,
Z FISH 29.2 30.0 24.00 o INVERT 7.3 30.0 24.00 i*
ri SHORELINE 500.0 30.0 0.00
$> SWIMMING BOATING 100.0 100.0 30.0 30.0 0.00 0.00 0 i
- t JO CHI LD DOSES (MREM PER YEAR INTAKE) o
- DOSE h
j PATHWAV SKIN BONE LIVER TOTAL BODY THvROID KIONEY 1.79E-05 LONG 4.30E-05 GI-LLI 2.23E-04 c FISH 1.31E-04 1.32E-04 1.31E-04 7.58E-06 INVERT 1.86E-04 1.88E-04 2.79E-04 2.05E-06 3.65E-06 5.71E-05 4.90E-04 h SHORELINE 1.80E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 1.53E-03 m
, d SWIMMING 1.03E-06 1.03E-06 1.03E-06 1.03E-06 1.03E-06 1.03E-06 1.03E-06 BOATING 5.14E-07 5.14E-07 5.14E-07 5.14E-07 5.14E-07 5.14E-07 5.14E-07 i TOTAL 1.80E-03 1.85E-03 1.85E-03 1.94E-03 '1.54E-03 1.56E-03 1.63E-03 2.25E-03 [
m
< USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR =0.5 ,
> FISH 29.2 30.0 24.00 0 INVERT SHORELINE 500.0 7.3 30.0 30.0 24.00 0.00 6 SWIMMING 100.0 30.0 0.00
~1 BOATING 100.0 30.0 0.00 i . r O
_ _ _ . _ . . _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _.__ ..______.______m_ _ _ _ _ _ _ _ _ _ _
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( ATTACHMENT 7 (cont)
ENCLOSURE 2 Annual Gaseous Dose Assessment INCLUDED ARE:
Source term for the three release modes and the site aggregate.
Total 50 mile Integrated Population Dose by pathways and organs.
Hypothetical maximum individual organ dose due to Iodines, Particulates, - and Tritium for a cow milk pathway at 4.75 miles Northeast.
Maximum site boundary dose by age group and organs for all
, pathways.
l Estimated individual organ dose using the 1993 Land Use Census for the worst sector and existing pathways.
Maximum site boundary dose due to Iodines, Particulates, and Tritium for existing pathways.
Source term for incinerated waste oil.
1 pathways and due Integrated Population Dose by organs to incinerated waste oil.
Maximum site boundary dose due to incinerated waste oil. )
Page 37
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CPGL SEMI-ANMUAL RADIOLOGICAL EFFLUEMT REPORTING RUN DATE: 02/15/94 GASRPT INPUT SOURCE TERMS RUN TIME: 10:49:29 SOURCE TERM (GROUND LEVEL) 1993 BSEP UNITS 1 AND 2 1 H - 3 1.650E+00 25 MN- 54 1.670E-07 27 CO- 60 1.680E-05 36 KR- 85 M 9.680E-01 38 SR- 89 3.300E-06 38 SR- 90 6.500E-08
!- 53 I -131 2.300E-06 53 I -133 1,360E-05 54 XE-135 7.760E+00 55 CS-137 3.840E-07 O
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CP&L SEMI-ANMUAL RADIOLOGICAL EFFLUENT REPORTIMG RUN OATE: 02/15/94 CASRPT- INPUT SOURCE TERMS RUN TIME: 13:42:08
,{
i 1993' SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 1 H- 3 1.680E+01 27 CO- 60 2.030E-04 4 36 KR- 85 M 1.580E+01 36 KR- 87 5.020E+01' 36 KR- 88 4.450E+01 I
38 SR- 89 9.250E-05 38 SR- 90 2.020E-06 53 1 -131 3.250E-04 53 I -133 1.840E-03 64 XE-133 9.670E-01 0 54 XE-135- 6.910E+01 9 54 XE-135 M 2.570E+01 h 54 XE-138 5.280E+01 55 C5-137 6.680E-04 8 56 BA-140 9.830E-05 d 57 LA-140 5.980E-05' O
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_ _ _ _ _ - _ _ . - - - _ _ _ _ _ _ _ - _ _ - _ - - _ . _ _ _ _ _ _ - _ _ _ - _ _ _ . _,_ _ ._ . - - _ __ . _ _ _ _ - _ _ _ - _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ ._ . - _ - _ _ _ _ _ - _ _ = _ _ _ _ _ _ _ _ _ _ _
CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/15/94 GASRPT INPUT SOURCE TERMS RUN TIME: 13:42:08
' BRUNSWICK UNITS 1 AND 2 MIXE0 MODE CONTINUOUS GASEOUS RELEASES, 1993 1 H- 3 1.490E+00 24 CR- 51 9.760E-04
! 25 MN- 54 2.520E-04 27 CO- 58 6.120E-05 i' 27 CO- 60 5.160E-03
- 38 SR- 89 2.850E-06 e 38 SR- 90 5.870E-07 60 53 I -133 .7,010E-05 k 54 XE-133 4.040E+00
^
60 54 XE-135 5.730E+01 Df 54 XE-135 M 1.170E+01 55 CS-137 2.950E-05 0 95 AM-241 1.140E-05 M AGGREGATE SOURCE TERM a
qy 1 H - 3 1.9940E+01' c 24 CR- 51 9.7600E-04 d 25 MN- 54 2.5217E-04 e 27 CO- 58 6.1200E-05 qs 27 CO- 60 5.3798E-03 -
y 36 KR- 85 M 1.6768E+01 36 36 KR- 87 5.0200E+01 0 36 KR- 88 4.4500E+01 $$
$ 38 SR- 89 9.8650E-05 of e 38 SR- 90 2.6720E-06 A jj 53 53 1 -131 I -133 3.2730E-04 1.9237E-03 4
54 XE-133 5.0070E+00
]$ 54 XE-135 1.3416E+02 8 54 XE-135 M 3.7400E+01 y 54 55 XE-138 CS-137 5.2800E+01 6.9788E-04 4 56 BA-140 9.8300E-05 0 57 95 LA-140 AM-241 5.9800E-05 1.1400E-05 e -
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SEMI-ANNUAL RODIOLOGICOL EFFLUENT REPORTING RUN OATE: 02/15/94 CP&L -
RUN TIME: 10:49:29 GASRPT ALARA ANNUAL INTEGRATED POPULATION DOSE
SUMMARY
(MANREM) 1993 SOURCE TERM (ELEVATED M00E) BSEP UNITS 1&2 m SOURCE TERM (GROUND LEVEL) 1993 BSEP UNITS 1 AND 2 BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1993 g
ta0 4
BONE LIVER KIDNEY THYROID LONG SKIN O TOTAL BODY GI-TRACT 3.060E-02 4.896E-02 2.943E-02 .2.949E-02 3.255E-02 3.240E-02 3.051E-02 2.967E-02
,3 ** TOTAL **
C 1.097E-02 1.116E-02 2.792E-02 U 1.097E-02 1.097E-02 1.097E-02 1.097E-02. 1.097E-02 PLUME 36.97% 36.46% 57.03%
37.27% 37.18% 33.69% 33.85% 35.94%
m A 1.666E-02 1.959E-02 1.666E-02 1.666E-02 1.666E-02 1.666E-02 1.666E-02 1.666E-02 h GROUND PLANE 56.14% 54.43% 40.00%
51.17% 51.41% 54.59%
g 56.60% 56.47%
1.018E-03 4.123E-03 2.388E-03 1.231E-03 2.332E-03 k INHALATION 1.215E-03 4.13%
1.063E-03 3.60%
4.664E-03 14.33% 12.72% 7.82% 4.15% 7.62% 2.08%
g 10 2.484E-04 5.960E-04 4.569E-04 7.406E-04 4.111E-04 3.918E-04 VEGETATION 5.322E-04 7.132E-04 1.34% 0.60%
1.81% 2.42% 0.76% 1.84% 1.50% 2.50%
O 1.347E-05 3.555E-05 1.168E-05 1.077E-05
'5 COW MILK 1.400E-05 1.196E-05 7.137E-06 1.865E-05 0.02% 0.06% 0.04% 0.12% 0.04% 0.02%
0.05% 0.04%
c O 3.760E-05 3.123E-05 3.040E-05 4.194E-05 8.297E-05 6.292E-06 4.088E-05 3.286E-05
$d MEAT 8. POULTRY 0.11% 0.13% 0.10% 0.06%
0.14% 0.28% 0.02% 0.13% r4
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CPM SECI-QWNUQL RADIOLOGICAL EFFLUEMT REPORTING RUN DATE: 02/15/94 NAO!All0N DOSES AT SELE CTED L OC A T 10N5 RilN TIMTg 10:49379 GA>wei
,y 1993 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 9 SOURCE TERM (GROUND LEVEL) 1993 BSEP UNITS 1 AND 2 BRUNSWICK UNITS 1 AND 2 MIXED MODE CONTINUOUS GASEOUS RELEASES, 1993 o SPECIAL LOCATION METERS DIR PL GR IN V CM GM M l!e F41 COW MILK 7644.0 NE O 1 1 1 1 0 0
, ANNUAL BETA AIR DOSE = 8.323E-04 MILLRADS O ANNUAL GAMMA AIR DOSE = 1.060E-03 MILLRAOS O
TOTAL 800Y GI-TRACT BONE LIVER KIONEY THVROID LUNG SKIN Y 1.460E-03 1.457E-03 1.511E-03 1.375E-03 1.537E-03 1.339E-03 1.499E-03
-4 ADULT 1.386E-03 3 )$ GROUND PLANE 1.194E-03 3.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03' 1.403E-03 4 INHALATION 3.445E-05 2.959E-05 1.562E-04 1.331E-04 7.480E-05 3.381E-05 6.675E-05 2.792E-05 VEGETATION 1.092E-04 2.076E-04 7.136E-05 1.200E-04 7.282E-05 1.075E-04 5.663E-05 5.040E-05 h 4.887E-05 2.944E-05 3.578E-05 6.399E-05 3.358E-05 2.024E-04 2.218E-05 1.701E-05 g4 cow MILK 1.414E-03 1.651E-03 1.382E-03 1.511E-03 d
O TEENAGER 1.403E-03 1.480E-03 1.528E-03 1.601E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.403E-03 M GROUND PLANE 2.810E-05 t INHALATION 3.498E-05 2.963E-05 1.647E-04 1.399E-04 7.764E-05 3.572E-05 8.639E-05 O VEGETATION 1.207E-04 2.200E-04 1.048E-04 1.630E-04 9.120E-05 1.052E-04 6.901E-05 5.770E-05 5.344E-05 3.694E-05 6.456E-05 1.050E-04 5.146E-05 3.161E-04 3.284E-05 2.216E-05 COW MILM O N
# 1.461E-03 1.459E-03 1.703E-03 1.739E-03 1.477E-03 2.010E-03 1.424E-03 1.553E-03 CHILD :t O 1.194E-03 1.403E-03 e 3 GROUND PLANE 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 7.288E-05 2.485E-05 bC D INHALATION 3.039E-05 2.542E-05 1.281E-04 1.043E-04 5.777E-05 3.416E-05 1.752E-04 1.948E-04 2.263E-04 2.629E-04 1.419E-04 1.623E-04 1.064E-04 8.93BE-05 j3 0 VEGETATION 5.142E-05 3.501E-05 COW MILA 6.191E-05 4.498E-05 1.548E-04 1.784E-04 8.365E-05 6.203E-04 t 1.471E-03
]NFANT 1.293E-03 1.270E-03 1.493E-03 1.574E-03 1.353E-03 2.692E-03 1.322E-03 d m 1.194E-03 1.403E-03 bC O GROUND PLANE 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03 1.194E-03
' 1.652E-05 1.448E-05 5.152E-05 4.631E-05 2.730E-05 2.285E-05 4.609E-05 1.429E-05 o d INHALATION 8.270E-05 6.200E-05 2.483E-04 3.340E-04 1.317E-04 1.476E-03 8.281E-05 5.312E-05 d cow MILK H
d u% 3 b-t - wA ;t n4 9 td C H h d
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~5MI-QNNUOL R ADIOLOGICAL EFFLUENT REPORTING RUN DOTE: 02/15/94 CP&L RUN TIME: 10:49:29 GASRPT PAOIATION DOSES AT SELECTED LOCATIONS 1993 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 1993 BSEP UNITS 1 AND 2 BRUNSWICK UNITS 1 AND 2 MIXED MODE CONTINUOUS GASEOUS RELEASES. 1993 m SPECIAL LOCATION METERS DIR PL GR IN V CM GM M
>s s 3 SITE BOUNDARY 1127.0 NE 1 1 1 1 1 1 1 d
fh ANNUAL BETA AIR 00SE = 4.655E-03 MILLRA05
+2 ANNUAL GAMMA AIR DOSE = 5.115E-03 MILLRADS d
TOTAL BODV GI-TRACT BONE LIVER KIONEY THVROID LUNG SKIN
;j ADULT 2.451E-02 2.498E-02 2.381E-02 2.569E-02 2.317E-02 2.856E-02 2.236E-02 2.917E-02 d 3.410E-03 3.410E-03 3.410E-03 3.457E-03 7.730E-03 PLUME 3.410E-03 3.410E-03 3.410E-03 1.705E-02 1.705E-02 1.70SE-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 2.005E-02 h GROUND PLANE' 3.701E-04 2.829E-04
% INHALATION 2.960E-04 2.868E-04 3.084E-04 4.901E-04 3.753E-04 3.038E-04 1.339F-03 2.763E-03 1.029E-03 1.479E-03 8.219E-04 1.324E-03 5.967E-04 5.106E-04 g VEGETATION 2.438E-04 1.724E-04 COW MILK F.141E-04 3.500E-04 4.983E-04 8.227E-04 4.019E-04 2.810E-03 c 4.169E-04 1.457E-03 2.262E-03 1.014E-03 3.517E-03 5.660E-04 3.516E-04 d GOAT MILK 1.612E-03 1.905E-04 7 011E-04 5.411E-05 1.726E-04 9.615E-05 1.423E-04 8.075E-05 7 339E-05 f MEAT & POULTRY O 3.201E-02 2.290E-02 2.937E-02 TEEMI.GER 2.466E-02 2.502E-02 2.587E-02 2.834E-02 2.421E-02 C 3.410E-03 3.410E-03 3.410E-03 3.457E-03 7.730E-03 d PLUME 3.410E-03 3.410E-03 3.410E-03 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 2.005E-02 g3 gg GROUND PLANE 2.847E-04 at 2.984E-04 2.883E-04 3.253E-04 5.050E-04 3.824E-04 3.118E-04 4.153E-04 p INHALATION 5.846E-04 O VEGETATION 1.477E-03 2.910E-03 1.507E-03 2.049E-03 1.049E-03 1.261E-03 7.410E-04 ,
4.408E-03 3.722E-04 2.245E-04 b0 6.590E-04 4.359E-04 8.987E-04 1.371E-03 6.306E-04 d to COW MILK 5.411E-04 2.632E-03 3.828E-03 1.629E-03 5.479E-03 9.OIOE-04 4.580E-04 "* GOAT MILK 1.650E-03 4.378E-05 fg MEAT & POULTRV 1.210E-04 3.816E-04 4.432E-05 1.228E-04 6.217E-05 9.370E-05 5.075E-05 e 4.222E-02 2.405E-02 3.006E-02 CHILD 2.537E-02 2.463E-02 3.250E-02 3.324E-02 2.618E-02 p,
.O 3.410E-03 3.457E-03 7.730E-03 PLUME 3.410E-03 3.410E-03 3.410E-03 3.410E-03 3.410E-03 2.005E-02 GROUND PLANE 1.705E-02 1.705E-02 1.705E 02 1.705E-02 1.705E-02 1.705E-02 1.705E-02
$ 2.628E-04 2.531E-04 2.533E-04 4.084E-04 3.167E-04 2.848E-04 3.593E-04 2.517E-04 O INHALATION 1.944E-03 1.141E-03 9.055E-04 D VEGETATION 2.134E-03 2.416E-03 3.242E-03 3.318E-03 1.634E-03 2.153E-03 2.339E-03 1.029E-03 8.686E-03 5.817E-04 3.547E-04 h cow MILK 7.305E-04 4.972E-04 1.405E-03 7.236E-04 1.627E-03 7.853E-04 6.316E-03 6.565E-03 2.668E-03 1.072E-02 4 GOAT MILK jj MEAT & POULTRY 1.545E-04 2.236E-04 8.045E-05 1.539E-04 7.617E-05 1.282E-04 6.107E-05 5.289E-05 C 2.649E-02 6.681E-02 2.40CE-02 2.956E-02 2.353E-02 2.243E-02 3.413E-02 3.761E-02 y INFANT 3.410E-03 3.410E-03 3.410E-03 3.410E-03 3.457E-03 7.730E-03 PLUME 3.410E-03 3.410E-03 1.705E-02 2.005E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02
[ GROUND PLANE 1.705E-04 1.752E-04 2.159E-04 1.448E-04
,4 INHALATION 1.492E-04 1.452E-04 1.020E-04 2.081E-04 3.456E-03 4.427E-03 1.628E-03 2.079E-02 9.489E-04 5.382E-04 5 m COW MILK 9.531E-04 6.652E-04 1.098E-03 g GOAT MILK 1.974E-03 1.157E-03 1.011E-02 1.252E-02 4.231E-03 2.539E-02 2.330E-03 B
,HA M
d _Z 9 .______ ______. _m _ __ _..__m_.._____ _ _ _ ___ ______ _ _ _ __ _ ____.__.___ _ _ - ____________ _._...__._...m__. __ _ _ _ _ _ _ . .
SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUM OQTE: 02/15/94 CP&L RUN TIME: 10:49:29 RA01ATION DOSES AT SELECTED LOCATIONS h GASRPT 9 U
$ 1993 SOURCE TERM (ELEVATED MODE) 8SEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 1993 BSEP UNITS 1 AND 2 N BRUNSWICK UNITS 1 AND 2, MIXE0 MODE CONTINUOUS GASEOUS RELEASES. 1993 L
j SPECIAL LOCATION METERS OIR PL GR IN V CM GM M
*18 RESIDENCE 1609.0 NNE 1 1 1 1 0 0 0 0
f) ANNUAL BETA AIR DOSE = 1.550E-03 MILLRAOS ANNUAL GAMMA AIR DOSE = 1.896E-03 MILLRADS 4 GI-TRACT 80NE LIVER MIDNEY THVROID LUNG SKIN
$3 TOTAL BODY 1.071E-02 ADULT 8.342E-03 8.941E-03 8.312E-03 8.460E-03 8.198E-03 8.312E-03 8.136E-03 m
1.268E-03 1.268E-03 1.268E-03 1.268E-03 1.268E-03 1.268E-03 1.283E-03 2.755E-03 h PLUME 6.594E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 7.754E-03 C GROUND PLANE 6.594E-03 6.594E-03 7.102E-05 7.646E-05 7.254E-05 1.275E-04 1.568E-04 1.093E-04 7.933E-05 1.050E-04 [l INHALATION 4.045E-04 1.007E-03 3.234E-04 4.416E-04 2.275E-04 3.718E-04 1.544E-04 1.282E-04 VEGETATION 0 TEENAGER 8.393E-03 8.988E-03 8.467E-03 8.642E-03 8.267E-03 8.293E-03 8.194E-03 1.073E-02 1.268E-03 1.268E-03 1.268E-03 1.268E-03 1.268E-03 1.283E-03 2.755E-03 l! PLUME 1.268E-03 7.754E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 d GROUNO PLANE 8.223E-05 1.225E-04 7.147E-05
*l INHALATION F1 VEGETATION 7.716E-05 4.542E-04 7.287E-05 1.054E-03 1.345E-04 4.707E-04 1.627E-04 6.184E-04 1.119E-04 2.938E-04 3.494E-04 1.945E-04 1.468E-04 jj cs 1.080E-02 O 8.970E-03 8.988E-03 8.407E-03 8.476E-03 8.28tE-03 f) CHILD 8.601E-03 8.741E-03 to 2.755E-03 df jjp PLUME GROUND PLANE 1.268E-03' 6.594E-03 1.268E-03 6.594E-03 1.268E-03 6.594E-03 1.268E-03 6.594E-03 1.268E-03 6.594E-03 1.268E-03 6.594E-03 1.283E-03 6.594E-03 7.754E-03 6.373E-05 1.048E-04 1.281E-04 9.010E-05 7,634E-05 1.052E-04 6.320E-05 INHAL A T ION 6.777E-05 2.992E-04 2.273E-04 6.718E-04 8.164E-04 1.003E-03 9.985E-04' 4.559E-04 5.383E-04
[ VEGETATION 7.898E-03 7.903E-03 7.924E-03 7.908E-03 7.910E-03 7.941E-03 1.055E-02 INFANT 7.899E-03
]
1.268E-03 1.268E-03 1.268E-03 1 268E-03 1.268E-03 1.283E-03 2.755E-03 O PLUME 1.268E-03 6.594E-03 7.754E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03 6.594E-03
$ GROUND PLANE 3.652E-05 4.220E-05 6.257E-05 4.700E-05 4.843E-05 6.416E-05 3.634E-05 13 INHALATION 3.819E-05 C
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** TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN j ADULT 1.734E-02 1.734E-02 1.736E-02 1.754E-02 1.742E-02 1.735E-02 1.742E-02 2.033E-02 4
+2 GROUpiD PLANE 1.705E-02 1.705E-02 .1.705E-02 1.705E-02. 1.705E-02 1.705E-02
, 1.705E-02 2.005E-02 l g INtOLATION 2.960E-04 2.868E-04 3.084E-04 4.901E-04 3.753E-04 3.038E-04 3.701E-04 2.829E-04 C d TEENAGER 1.735E-02 1.734E-02 1.737E-02 1.755E-02 1.743E-02 1.736E-02 1.746E-02 2.033E-02 o m GROUND PLANE 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 2.00SE-02
-h1HMALATION 2.984E-04 2.883E-04 3.253E-04 5.050E-04 3.824E-04 3.118E-04 4.153E-04 2.847E-04
'd j CHILD 1.731E-02 1.730E-02 1.730E-02 1.746E-02 1.737E-02 1.733E-02 1.741E-02 2.030E-02 U
v4 GROUND PLANE 1.705E-02 1.705E-02 1.705E-02 1.70SE-02 1.705E-02 1.705E-02 1.705E-02 2.005E-02 us (IMHOLATION 2.628E-04 2.531E-04 2.533E-04 4.084E-04 3.167E-04 2.848E-04 3.593E-04 2.517E-04 4 e e IN INFANT 1.720E-02 1.719E-02 1.715E-02 1.726E-02 1.722E-02 1.722E-02 1.726E-02 2.019E-02 60 OGROUND PLANE 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 1.705E-02 2.005E-02
$ INHALATION 1.492E-04 1.452E-04 1.020E-04 2.081E-04 l.705E-04 1.752E-04 2.159E-04 1.448E-04 D
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CP&L SERI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/15/94 GASRPT RAOIATION DOSES AT SELECTED LOCATIONS RUN TIME: 17:51:21 SOURCE TERM (INCINERATED OIL 1993 BSEP UNITS 1 AND 2 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M s3 SITE BOUNDARY 1127.0 NE 1 1 1 1 0 0 1 ANNUAL BETA AIR DOSE = 0.000E+00 MILLRADS ANNUAL GAMMA AIR DOSE = 0.000E+00 MILLRADS TOTAL 800Y GI-TRACT BONE LIVER KIDNEY 1HVROID LUNG SKIN ADULT 5.205E-05 5.725E-05 5.134E-05 5.262E-05 5.017E-05 4.912E-05 5.102E-05 5.775E-05 GROUND PLANE 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 5.775E-05 INHALATION 2.077E-08 7.473E-08 1.885E-08 2.810E-08 8.933E-09 0.000E+00 1.55BE-06 0.OOOE+00 VEGETATION 2.546E-06 6.283E-06 2.033E-06 3.145E-06 9.555E-07 0.OOOE+00 3.137E-07 0.OODE+00 MEAT & POULTRY 3.626E-07 1.769E-06 1.737E-07 3.321E-07 8.087E-08 0.000E+00 2.681E-08 0.000E+00 TEENAGER 5.197E-05 5.662E-05 5.253E-05 5.427E-05 5.068E-05 4.912E-05 5.199E-05 5.775E-05 I$ GROUND PLANE 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 5.775E-05 INHALATION 1.750E-08 6.798E-08 2.642E-08. 3.818E-08 1.220E-08 0.000E+00 2.276E-06 0.000E+00 h VEGETATION 2.602E-06 6.478E-06 3.239E-06 4.850E-06 1.483E-06 0.000E+00 5.697E-07 0.000E+00 m MEAT & POULTRY 2.309E-07 9.517E-07 1.442E-07 2.652E-07 6.547E-08 0.000E+00 2.537E-08 0.000E+00 d
> 5.382E-05 5.707E-05 5.764E-05 5.162E-05 4.912E-05 5.185E-05 5.775E-05 CHILD 5.270E-05 00 at y
+2 GROUND plt.NE 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 5.775E-05 U
d INHALATION 1.103E-08 2.522E-08 3.573E-08 3.662E-08 1.130E-08 0.000E+00 1.844E-06 0.000E+00 w e VEGETATION 3.273E-06 4.193E-06 7.647E-06 8.141E-06 2.409E-06 0.000E+00 8.583E-07 0.000E+00 e 0.000E+00 2.981E-08 0.000E+00 D* c MEAT & POULTRY 2.925E-07 4.807E-07 2.656E-07 3.413E-07 8.304E-08 INFANT 4.912E-05 4.913E-05 4.914E-05 4.915E-05 4.913E-05 4.912E-05 5.030E-05 5.775E-05 O GROUND PLANE 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 4.912E-05 5.775E-05
+3 1NHALATION 4.899E-09 8.363E-09 2.163E-08 2.660E-08 6.872E-09 0.OOOE+00 1.177E-06 0.000E+00 0
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9 ATTACHMENT 7 (cont) ENCLOSURE 3 Dose Assessment Summary I. Liquid Effluents: Maximum Dose to Individual: (mrem) Adult GI-LLI 2.49E-03 Child Total Body 1.94E-03 II. Gaseous Effluents: Noble Gas Air Dose at Site Boundary: (mrad) Gamma 6.78E-03 Beta 8.38E-03 Iodine-131. Iodine 133, Tritium and Particulates: (mrem) i Maximum dose at site boundary: Infant thyroid 6.68E-02 Maximum hypothetical dose at 4.75 miles for cow pathway Infant thyroid 2.69E-03 Estimated dose for existing pathways Child skin 1.08E-02 i i l Page 49
l ATTACHMENT 8 Off-Site Dose Calculation Manual (ODCM) and l Process Control Program (PCP) Revisions July 1, to December 31, 1993 Brunswick Steam Electric Plant There were no revisions made to the Process Control Program during
- this reporting period.
l f Revision 15 was made to the Off-Site Dose Calculation Manual during this time period. This revision included the following changes:
- 1. Pages 2-2 through 2-8 and page 2-10 were revised to delete references to MPC values for liquid effluents. Revision 14, approved prior to the end of 1992, incorporated Environmental l Concentration (EC) limits to allow methodology for calculating discharge-flow rates for batch liquid releases to comply with the new revision to 10CFR20. MPC values were maintained for use until the end of 1992 after which the new EC limits were used.
l
- 2. Pages 3-22 and 3-42 were revised to delete reference to incineration of scintillation vials. This practice is no longer necessary.
1 I
- 3. Page 3-30 was revised to update Table 3.2-2 to include new garden locations determined from the most recent Land Use Census.
- 4. Page E-2 was updated to change the Reactor Building Ventilation Monitoring System sampler flow rate measurement device to match that designated in post modification plant drawings.
- 5. Page E-3 was updated to delete obsolete equipment designations for the Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System -- Hydrogen Monitors. These designations were changed due to plant modifications.
l [ A copy of Revision 15 to the ODCM is included as a part of this attachment. Page 50
l ATTACHMENT A REQUEST FOR OFF SITE DOSE CALCULATION MANUAL CHANGE Originator: bren d 9 n W f Date: \Ll%(9T. Rev. LE Pages and Sections Revised: J e e+ ib .2. . O ( o s s e s 2 -2 Wu 'Z-to } 6
- e a, .3 -2 L. , i one 1 50 o ct a e_
i , A-yt ,_ m,e,, #-2 t Reason for Change: U n hk Teb\e *L.'l 'E 4e InhAe dok* 4'm R $** M W e C&s w O D e h4- e bit. kk teR-tuee % 69t'i- ' b&b 'L.0 , @ 0 e_t . A c (eleic. ore -% msk u Ma n 4 c'ese$MM u 6As ,- @ ce w h ! e e u 6 ew* w+ deds w eA L % r h %\h w % Wc9%w r=Ae u e s,- wu-3 , 4k4.b. .
@ ce.wJi
,y. me.nt<k* Apneio n %'c H sd (ogi.n r% n's% es,, .
Safety Analysis Complete: d Date: 12_/ B l 9 3 REVIEWS: connnen ot Recomended Date: 12.[B [9A st Safe Reviewer
/4 . -
nunend t Recomended Date: /2 l/ 8 73 2nd Safet/f Reviewer (' 'R e u" ame ot Recommended Date: / /0!b ,
./ E&C Project Specialist j
_I Reconsnanded ot Recommended Date: M 7.3
'- S ec al Projects ' .
Operatio
~
comme at Reconumended Date: /N/Yh E&C Manager APPROVALS: l :- ; b b_ 4.- nunend ot Reconumended Date: / "Af2d/13 Mana8er - E&RC t Reconumended Date: /V2 t / s/3 m a_ (Recommendedpot Reconunended Date: / ~2.-2 t-9 3 Plant General Manager 0-E&RC-4261 Rev. 1 Page 6 of:7 l 9
ATTACHMENT 2 (Cont'd) REVISION 3 10CFR50.59 PROGRAM MANUAL Page 55 ATTACHMENT A CF&L SAFETY REVIE'4 PACKAGE Page i of 9 SAFETY REVIIY COVER SHEET DOCURENT ::0. ODC h - - REV. ;0. t& DESCRIPTION OR TITLE: O 0-b'4e D ose Cdwak6 hmd
- 1. Assigned Responsibilities:
Safety Analysis Preparar: 0-ce& Rutf"- Lead 1st Safety Reviewer: Cs r omt- 9 03Att"-- 2nd Safety Reviewer: $swo My#thdi
- 2. Safety Analysis Preparar: Comp to PART I. SAFETY ANALYSIS Safety Analysis Preparer t d" / lt. [8 I9 ~5 dAvaatuna unra.
- 3. Lead 1st Safety Reviewer: Complete Part II. Item Classification.
4 Land 1st Safety Reviewer: Part III may be completed. If either question i 2 is "yee,a than Parr IV is not required.
- 5. Land 1st Safety Reviewer: Determine which DISCIPLINES are required for rev:
of this item (including own) and mark the appropriata block (s) below. DISCIPLINES Reauired: (Print Nama) Simnature/ Data (Sten [] Nuclear Plant Operations [] Nuclear Engineering () Meehanical () Electrical "
~~ ' '
() Instrumentation & Control {] Structural () Metallurgy , k) Chemistry /Radiochamiatry (~ N O akt.<" 3d M [ d [l'L 4 t5 [] Health Phys'ics. [] Administrative Controla
- 6. A QUALIFIED SAFETT REVIEEEE will be assigned for each DISCIPLIII marked in s 5 and his Each persest-liated s 1 perform a/her namn erinted in the space providad.SAFEET RtVIEW and provida in Fackage. .
r
- 7. The Imad 1st Safety Reviewer will assure that a Part III or Part-Itis.
egleted (see person step in listed 4 above) and as Partand step 5 shall VI ifdata requirednest to(see his/her 9.4usuma-in:st of Fart:II) 5, indicating completion of a SAFETY EE.
- 8. 2nd Safety Reviewer: Pa a -in accordance with Section 8.
2nd Safety Reviewer I/8Me'ff4>' Data T2 f b# DISCIFLINE: [l/w/[dE////gn
- 9. FESC review required? If "yes,I attach Part V and mark reason Igg &
below: Mi [ ] ~' Potential URRETIEEED SAFETT QUESTICE Question 9 of Fart IV answered "Yes" . . O AI-109 Rev 00N*(** . ' r*5* IZ 'E **
s i ATTACHMENT 2 (conc'd) RITI8 ION 3 10CFR50.59 PROGRAM MANUAL Page 56 AITACHMENT A CP&L SAFETY REVIEW PACKAGE Page 7- of 9 PART I: SAFETT AM& LYSIS (See inscructions in Seccion 8.4.1) (Attach additional sheets as necessary.) , l l DOCUMENT N0'. h e c_N\ REY. NO. I { DESCRIPTION OF CHANCE: 4Wd Tedale M.f.-7 Ofs 9*e e 3-10 *tir be j te dtuas& S W \nhty LoM (ke C crssus R e .s s h oss.% i n.s: l as % A An s .o +o e \dm M e. req ec= ce c_ta, % ' tht t.' sisNuss .
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T- b \t 5. t.- 7 "bii hec % t.s nA e \\ko L.oem Ms. ns o.t fn e o.w e A Fee,w-tnt. E e v w s s c. ( k s n t c.z m e- ( m M
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REFERENCES:
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ll:'S N C - T<mMe et h%ts - s e w. s ' 6'~ , hh v2. Tech Le c_ % s . Vqi ri , '!!l'f 4. f f;24 d4. t2,7 . (s. 4 g;3 .. l 0 AI-109 Rev. 002 Page 73.o086 -
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i . ATTACHMENT 2 (Cont'd) i i RETTSTON 3 10CFR50.59 PROGRAM MANUAL Page 57 ATTACHMENT A I ! CP&L SAFETY REVIEW PACKAGE Page d of i i h PART II: ITEM CIASSIFICATION i i DOCUMENT NO. O Chtw REY. NO. \7
' IRA !!1- .
l
- 1. Does this item represent
-a. A change to the facility as described in the-SAFETY [] M ANALYSIS REPORT 7 ,
- b. A change to the procedures as described in the SAFETY () .N- I ANALYSIS REPORT 7 )
- c. A test or experiaanc not described in the SAFETY [] p[ l ANALYSIS REPORT 7
- 2. Does this item involve a change to the individual plant [] M 'i operating License or to its Technical Specifications? '
- 3. Does this item require a revision to the FSAR7 [] $
4 Does this item involve a change to the off. Site-Dose N' []* e=1~1 = tion Mammal ? ,
- 5. Does this item constitute a change to the Process Control (] M4 1 Progrant !
- 6. Does this item involve a major change to a Radwaste Treatment [] M-Systaaf
- 7. Does this item involve a change to the Technical () M1 -l Specification Equipment List (BSEP and SEEFF only)? ;
Does this item impact the NPDES Permit (all 3 sites) or
- 8. [] #F constituta an "unreviewed environmental question" (SENFP Enviromaantal Plan. Seation 3.1) or aa significanc '.
environmental impast* (BSEP)? "
- 9. Does this ium involve a change to a previously accepted:
a. Di l QualityAssuranceProkan W b. Seeurity Plan (inetud Training, Qualification, and tDie , Contingency Flans)? wo; I
- c. Emergency Plan? 42 d.
g(Ifadent yes," Spent Fuel refer to Storage Section 8.4.2,Installation license?
" Question 9," for .~ -
A special considerations. Completa Part VI in accordance % with Section 8.4.6) E SEE SECTION 8.4.2 FOR INSTEDCTIONS FOR EACH "YES* AMSUIE. g@@ REFERENCES. questions 19 List FSAE above. and Technical Specification references used to:ansmer: I answer. Tec.h Chee is .4% ODekA *' s ., a O AI.109 Rev. 002 Page 74 o0 56. . _ - .. - - . . - - . -.x__
4 ATTACHMENT 2 (Cont'd) i I l REVISION 3 10CFR50.59 PROGRAM MANUAL Page 58 ATTACHMENT A CP&I. SAFETY REVIEV PACKACE PaE* # of T PART III: UNREVIIVED SAFETT QUESTION DETERMINATION SCREEN DOCUMENT NO. 6DLA REY. NO. t E"" IRA E9.
- 1. Is this change f,gily, addressed by another completed [] .vt UNREVIEVED SAFETY QUESTION determination? (See Sections 7.2.1. 7.2.2.5. and 7.9.1.1)
REFEZENCE DOCUMENT: REV. NO. ISE E9.
- 2. For procedures, is the change a non-intent change which 9,niz (check all that apply): (See section 7.2.2.3) [] Pk
[] Corrects typographical errors which do not alter the meaning or intent of the procedure; or, . [] Adds or revises steps for clarification (provided they are consistant with the original purpose or applicability of the procedure); or, [] Chan6es the title of an organizational position; or, [] Changes names, addresses, or telephone numbers of persons; or, () Changes the designation of an item of equipment where the equipment is the same as the original equipment or is an 4 authorized replaa====e; or, [] Changes a specified tool or instrument to an equivalent ~G~
. substitute; or, j
[] Changes the format of a procedure without altering the .y
---- W , intent, or content; or- ~*P
() Deletes a part or all of a procedure, the deleted portions of-which are wholly covered by approved plant procedurest If the answer to either Question 1 or question 2 in PART III is "Yes," then PARTTI' need not be completed. 1 0 AI-109 Rev. 002 Page 75 of. 86 ! 1 d
j. fi ATTACHKENT 2 (Cont'd) }. 1 j REYTSION 3 10CFR50.59 PROGRAM MANUAL Page 59 i ATTACHMENT A j CP&L SAFETY REVIEW PACKAGE Page' h of 9 1 ! PART IV: UNREVIEVED SAFETT QUESTION DETERMINATION
- DOCUMENT NO. @ t_'tf\ REY. NO. i %~
l Using the SAFETY ANALYSIS developed for the chan6e, cost or experiment, as well ad j other required references (LICENSING BASIS DOCUMENTATION, Design Drawings, Desi5 n
- Basis Documents, codes, etc.), the preparer of the'Unreviewed Safety Quascion
{ Determination must directly answer each of the following seven questions and asks a 4 determination of whether an UNREVIEVED SAFETY QUESTION exists. J A WRITTEN BASIS IS REQUIRED FOR EACE ANSWER i 18A . d.9 .. i ) j 1. May the proposed activity increase the probability of [] g 4 1 occurrence of an accident evaluated previously in the j SAFETY ANALYSIS REPORT 7 wr 4wec) . i { . l , 2. May the proposed activity increase the consequences of an [] M accident evaluated previously in the SAFETT ANALYSIS REPORT 7 . ]
- %e Wad t
- 3. May the proposed activity increase the probability of . () W
[ occurrence of a malfunction of equipment important to. ! safety evaluated previously in the SAFETT ANALYSIS REFORT7 l h ^<-; sc.u._wd t
- 4. May the proposed activity increase the consequence of a [] )(*
! aalfunction of equipment important to safety evaluated jreviously in the SAFETT ANALYSIS REPORT 7 g, ; mm %eb i I
- 5. May the proposed activity creata the possibility of an () jds i accident of a different type than any evaluated previously in the SAFETT ANALYSIS 4EFORT7 l- Mt_. wAJ
[ 0 AI-109 Rev. 002 Page 76 of 86 l r 4
y . . . l- ATTACHMENT 2 (Cont'd) REVISION 3 10CFRSO .59 PROGRAM MANUAL 'Page 60
- AT.?ACHMENT A
! CP&L SAFETY REVIEV PACKAGE Page ~~7 of $ i k l PART IV: (Continued) l 2 DOCUMENT No. e tw 4 REV. No. IC 4 ! ISA ER j 6. May the proposed activity create the possibility of. a [] g i malfunction of equipment important to safety of a different. l type than any evaluated previously in the SAFETY ANALYSIS ; i REPORT 7 he.e_ A% hb i
- 7. Does the proposed activity reduce the margin of safety as [] H l_ defined in the basis of any Technical Specification?
! 5 c e. W wkb i . ! 8. Based on the answers to questions 1 - 7, does this itaa [] hp. t result in an UNREVIEWED SAFETY QUESTION 7 If the answer to
- any of the questions 1-7 is "Yes," then the item is
- l considered to constitute an UNREVIEWED SAFETY QUESTION.
f 9. Is PNSC review required for any of the following reasons? [] M ! "No," it was determined that tha:probabili ( If, in answering increase was smal$usstion relative1 to or the 3 uncertainties; or, in answering: question i or 4 "No," it was determined that the doses increased. . but the dese was-sti less than the NRC ACCEFIANCE LIMIT; or, in answerin6 question 7 "No," am
- parameter would be closer to the NRC ACCEPTANCE LIMIT, but the end. result 1.
i still within the NRC ACCEPTANCE LIMIT; then PNSC review is required. i l
REFERENCES:
., 3g' "
. O ts e m
- CSA t. %w e (%,&44 .
w4 6 it 17. f* 15 " 1 T et.W m faa _s eceir(e g. m T~ect J /4 ti,t 314.481 1 ' 1 14 t t. .*t b .43 b . t 1 cla d hse t. i .. .
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* .wssri, i This Un':eviewed Safety Question Determination is for the following DISCIPEINE(s):
[ (Additional Part IV forms may be included as appropriate.) w l Nuclear Plant Operations L Structural - Nucisar Engineering Metallur . . . .
- Meehanical M chemis och==4mtry ..
Health 4- Electrical ics Ad=ini=trativecontrolsM"fM 4 O AI-109l;tev. Instrumentation 002 & Control Page 77 off 86 ]: . - q 1 . . . , , _
~ - -. , _ , . . . , _ __ _ _ __ . . _ . _ . - _.
i 9 6T k I Unreviewed Safety Question Determination:
- 1. This revision does not effect any safety related systems, structures, or components. The changes update the ODCM with data from the latest Land Use census. Other changes were
! administrative only. Therefore the result of this revision l will in no way increase the probability of occurrence of any accident previously evaluated for in the FSAR.
- 2. These changes do not alter in any way, the initial conditions of any accident or effect mitigating systems, structures, or components. Therefore, these changes will not increase the consequences of any accident previously evaluated in the FSAR.
- 3. This revision incorporates data from the latest Land Use Census l that will result in more accurate dose assessment to the public from operation of the Brunswick Plant. Other changes made were administrative improvements to the Manual. This revision will not increase the probability of occurrence of a malfunction of equipment important to safety.
- 4. Equipment important to safety is in no way effected by revisions made to the ODCM. The consequences of a malfunction of equipment important to safety will not be increased.
- 5. The changes made to update Table 3.2-2 " Distance To Controlling Locations as Measured From the Brunswick Plant Center (Mi) " and other administrative. changes will not increase the possibility of an accident of a different type than any evaluated previously in the SAR.
- 6. This revision does not effect any plant equipment important to safety and therefore will not create the possibility of a malfunction of equipment important to safety of a different type than evaluated previously in the FSAR.
- 7. These changes will not reduce the margin of safety as defined by Tech Specs. Updated information from the Land Use census will enhance ability to assess dose to the public from BNP effluents, other changes remove obsolete information and one change was made to an equipment designation. g
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b b h b' 50 i coNTa;im.m 1 BRUNSWICK STEAM ELECTRIC PIANT OFF-SITE DOSE CALCULATION MANUAL (ODCM) I REVISION 15 DOCKET NOS, 50-324 50-325 CAROLINA POWER-& LIGHT COMPANY l
. 1 RECEIVED rJAN I i11994 BNP DOC, CONTROL'
. I
- f. 1 LIST OF EFFECTIVE PAGES 1 ODCM Pare (s) Revision 1-11 15 iii 14 l
l iv 15 ! v-viii 14 1-1 8 2-1 14 2 2-8 15 2-9 14 2-10 15 2 2-15 14 l 3 3-12 4 3-13 1 3-14 4 3-15 5 3 16 18 4 3-19 6 3-20 1 3-21 8 3-22 15 3-23 .1 3-24 4 3-25 1 3-26 4 3-27 6-3-28 8 3-29 1 3-30 15 3-31 '4 3-32 1 3-33 14 3 3-36 'l ! 3-37 3-38 4 l 6 I 3-39 l 3-40 7 3-41 1 3-42 15 3 3-45 1 3 3-48 4 3-49 1 3 3-68 14 , 4 4-3 11 4-4 7 4 4-6 11 5-1 0 6 6-2 0 6-3 4 Rev. 15 ODCM (BSEP) i
LIST OF EFFECTIVE PAGES (Continued) ODCM Pare (s) Revision A-1 0 A-2 4 A A 4 0 A A-7 4 A A-9 0 A A-13 4 A A-15 0 A A-19 4 e A A-21 0 A-22 4 A A-28 0 B B-33 0 C C-16 14 D D-2 1 E-1 13 E-2 15 E-3 15 F F-3 0 G-1 1 H H-5 9 l l 4 ODCM (BSEP) 11 Rev. 15
- m . _ , . _ . . _ . _ . - . . - . _ _ . _ -_ _ . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ __
y LIST OF TABLES Table No. Title Eggg. 2.1-1 ECS FOR SELECTED RADIONUCLIDES . . . . .. , . . . . . . . 2-10 l 2.2-1 Air VALUES FOR THE ADULT . . . . . . . . . . . . . . . . . 2-13 3.1-1 GASEOUS SOURCE TERM . . . . . . . . . . . . . . . . . . . 3-13 3.1-2 DOSE FACTORS AND CONSTANTS . . . . . . . . . . . . . . . . 3-14 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT . . . . . . . 3-29 3.2-2 DISTANCES TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER . . . . . .. .. . . . _ . . . . . . 3-30 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTION FROM THE STACK ,.. . .. . . . . . . . . . . 3-31 3.2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS . .. . . . . . 3-32 3.2-5 P VALUES FOR AN INFANT FOR THE BRUNSWICK STEAM ELECTRIC i PIANT . . . . . . . . . . . . . . .. .. . .. . . . . 3-33 3.3-1 THRU 3.3-19 R VALUES FOR THE BRUNSWICK STEAM ELECTRIC PLANT . . . . . 3-50 4.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . . 4-2 A-1 X/Q VALUES ~AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS . . . . . . . . ... .. . . . . . . . . A-5 A-2 DEPLETED X/Q VALUES AT THE SPECIAL LOCATIONS.FOR RELEASES
~
FROM THE TURBINE BUILDINGS , . . ., . . . . . . . . . . . A-6 A-3 D/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE TURBINE BUILDINGS . . . . . . . . . . . . . . . . . . . . A-7 A-4 X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS . . . . . . . . . . . . . . . . . . . . A-8 A-5 DEPLETED X/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE TURBINE BUILDINGS . . . . . .. . . . . . . . . . A-9 A-6 D/Q VALUES AT THE STANDARD DISTANCES FOR RELEASES FROM THE i TURBINE BUILDINGS . . . . . . . . . . . . . . . . . . . . A-10 j l A-7 X/Q VALUES AT THE SPECIAL LOCATIONS FOR RELEASES FROM THE i REACTOR BUILDINGS . . . . . . . . .. . . . . . . . .. . A-11 l i l
'l ODCM (BSEP) iv Rev. 15 l
LIST OF TABLES Table No. 4 E.3L9. SECTION 2 2,1-1 ECs FOR SELECTED RADIONUCLIDES , , , , , , . . . . . .. . 2-10 2.2-1 Aa VALUES FOR THE ADULT . , , , , , , , , , , , , , , ,, , , 2 13 4 l l 4 l l 4 ODCM (BSEP) 2-2 Rev. 15 i l
,. -.1
y j
. l LIQUID EFFLUENT l
2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS) 2.1.1 Batch Releases- i l A batch release is the discharge of liquid waste of a l discrete volume. Batch releases from the BSEP liquid l radwaste system may occur from the waste sample tank, floor drain sample tank, detergent drain tank and the salt water tanks. The maximum release rate possible due to pump capacity is 200 GPM from all release tanks except the detergent drain tank, which has a maximum release rate of 50 GPM. All of the above liquid radwaste discharges go to the circulating water discharge canal. Batch releases can also be made from the circulating water pits. After the volume of the pit is computed, two independent samples are analyzed and must be within 15% of each other before the release is approved. The two samples may differ by more than 15% upon approval of the EE Supervisor or equivalent. The maximum release rcra is determined such that 10CFR Part 20 limits are not exceeded after dilution in the discharge canal. The sampling and analysis frequency and the type of analysis required by the BSEP Technical Specifications is given in Table 4.11.1-1. All applicable instrument numbers may be found in Appendix E. 2.1.1.1 Prerelease The radioactive content of each batch release will be determined prior to release in accordance with Table 4.11.1-1 of the BSEP Technical Specifications. Compliance with 10CFR Part 20 will be shown in the following manner:
- a. Minimum acceptable dilution factor:
D F, - Ej L (Eq. 2.1-1) t sc, , Where: DF, - Minimum acceptable dilution factor determined from ; analysis of liquid effluent to be released C. - Concentration of radionuclide i in the batch to be l released, pCi/ml EC i - Annual average effluent concentration limit of l radionuclide i from Appendix B, Table 2, Column 2 of , 10CFR20, pCi/ml. I I l ODCM (BSEP) 2-3 Rev. 15
1 . I DF, - (10) (Dr o) (Eq. 2.1-2) ! I 1 Where: 1 DF, - Conservative dilution factor used by BSEP to calculate maximum release rate prior to release in order to assure compliance with 10CFR Part 20 10 - A factor of 10 less than 10CFR Patt 20 limits as specified l l l in Appendix B. This factor represents one layer of conservatism for all releases at BSEP DF. - Minimum acceptable dilution factor per Equation 2.1-1 i ! b. Maximum release rate:
- n-1 (RPFcw) + p-1 (RPF gy) (Eq. 2.1-3)
! MRR - l 2 (DF3) l l- Where: ! MRR - Maximum release rate of 1ho bat to be released, GPM I l n - Number of operating circulatkre water pumps i p - Number of operating service water pumps RPF, - Minimum rated pump flow of each circulating water pump 1.357 E5 GPM RPF., - Rated pump flow of each service water pump
- 8 E3 GPM l
2 - Engineering factor to prevent spurious alarms caused by
- deviations in the mixtures of radionuclides which affect l the monitor response L DF, - Minimum acceptable dilution factor (DF ) made conservative
! by a factor of 10 per Equation 2.1-2 l 1 l
. l i
1 ODCM (BSEP) 2-4 Rev. 15 l I
.s, . .jbf
- c. Monitor Alarm / Trip Setpoint:
Monitor alarm / trip setpoints are determined to ensure that the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas does not exceed the limits specified in 10CFR Part 20, Appendix B, for radionuclides other than dissolved or entrained noble gases. An EC of 2 E-4 pCi/ml has been established for noble gases l dissolved or entrained in liquid effluents, based on the assumption that Xenon-135 is the controlling radionuclide. 3p , C,. ( E,,) [(n-1) (RPFy) + (p-1) (RPF,y) ] + Skg (Eq. 2.1-4) RR Where: SP - Monitor alarm / trip setpoint, cps E. - The monitor efficiency for the mixture of radionuclides in the liquid effluent prior to dilution, cps /pci/ml i C, - 3 E-7 Ci/ml; engineering factor to ensure that the final concentration for the mixture of radionuclides will be - less than 10CFR Part 20 limits at unrestricted areas n - Number of operating circulating water pumps p - Number of operating service water pumps RPF. - 1.357 E5 GPM RP F,,, - 8 E3 GPM RR - 200 CPM; maximum design release rate Bkg - Background count rate due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with an uncontaminated fluid, cps gp , 3 E-7 ( E,) [(n-1) (1.357 ES) + (p-1) (8.0 E3)) .g 200 (Eq. 2.1-5)
- d. Calculated concentration at unrestricted area:
"* ~
(n-1) (RP )+ -1) (RPF,,) ODCM (BSEP) 2-5 Rev. 15 a
4 Whsre:
- Conci -
Calculated concentration of radionuclide i at the unrestricted area, pCi/ml l Ci - Concentration of radionuclide i in the batch to be released, Ci/ml MRR - Maximum release rate of the batch to be released (see Equation 2.1-3), GPM n - Number of operating circulating water pumps p - Number of operating service water pumps RPFc, - 1.357 ES GPM RPF, - 8 E3 GPM
- e. 10CFR Part 20 Prerelease Compliance Check:
Before initiating the batch release, one final check for compliance with 10CFR Part 20 will be performed. If the calculated dilution factor et the unrestricted area is-less than or equal to 1, then 10CFR Part-20 limits have been met. The following equation must be true: Es (conc,/Ecg) s1 A' *~ Where: Conci - Concentration of radionuclide i at the unrestricted area per Equation 2.1-6, pCi/ml EC i - Annual average effluent concentration limit of I radionuclide i, from Anpendix B, Table 2, Column 2 of 10CFR20, pCi/ml. I 2.1.1.2 Postrelease The actual concentration of each radionuclide following release from a batch tank will be calculated to show final compliance with 10CFR Part 20 as follows: , I l l i I l ODCM (BSEP) 2-6 Rev. 15
m
- a. Actual concentration at unrestricted area:
I Conc a - I 'I I "*"I (Eq. 2.1-8) vs ,, Where: Conc a - The actual concentration of radionuclide i at the unrestricted area during release k, pCi/ml Ci - Concentration of radionuclide i in the batch released, pCi/mi V.n - Actual volume of liquid effluent released, gal Vou - Actual volume of dilution water during release k, gal
- [n (RPF,) + p (RPF,,) ] (cm)
Where: n - Number of operating circulating water pumps p - Number of operating service water pumps RPFa - 1.357 E5 GPM RPF , - 8 E3 GPM t, - Total release time, min
- b. 10CFR Part 20 Postrelease Compliance Check:
To show final compliance with 10CFR Part 20, the following relationship must hold: 3 Ej (Conen/EC s) s 1 (Eq. 2.1-9) Where: Conc a - The actual concentration of radionuclide i during release I k (from Equation 2.1-8), pCi/ml EC, - Annual average effluent concentration limit of l' radionuclide i from Appendix B, Table 2, Column 2 of 10CFR20, pCi/ml. l l l l i 2-7 Rev. 15 ODCM (BSEP)
- 1 4
2.1.2 Continuous Releases A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that i has an input flow during the continuous release. Planned j continuous releases do not presently occur at BSEP, l although the potential does exist in the service water system. Weekly tests are performed during system operation as specified in Table 4.11.1-1 of the BSEP Technical Specifications. If a continuous release does occur, the concentration of various radionuclides in the unrestricted area would be calculated using Equation 2.1-8 with C being the concentration of radionuclide i in the i continuous release stream. To show compliance with 10CFR Part 20, the sum of the concentration of radionuclide i in the unrestricted area due to both continuous and batch releases divided by that isotope's EC must again be less than 1. 2.1.2.1 Service Water Effluent Monitor Setpoint Determination This procedure determines the monitor alarm setpoints that indicate the abnormal presence of radionuclides " in the service water liquid effluents released from the site to unrestricted areas. This procedure is applicable to any service water effluent monitor.
- a. Determine the monitor efficiency factor, EF, in #Cll"2 cps EF - ( E,) (cf) (Eq. 2.1-10)
Where: E, - The detector efficiency (dpm/ml/ cps) from the appropriate RST C, - Conversion factor, (1 pCi/2.22 x 108 dpm)
- b. Determine the monitor trigger level setpoint, TLS, in cps TLS - TL/EF + Bkg (Eq. 2.1-11)
Where: TL - The alarm trigger level (pCi/ml) as per Technical Specification 3/4.11.1.1.
- 5.0 x 10' pC1/ml Bkg - Monitor background, (cps)
ODCM (BSEP) 2-8 Rev. 15
6- n,. ifyyj TABLE 2.1-1 ECs FOR SELECTED RADIOWCLIDES Radionuclide , ECduci/ml)** ' I H-3 1E3 Na-24 5 E-5 Cr-51 5 E-4 l l Mn-54 3 E-5 Co-58 2 E-5 l Fe-59 1E5 I Co-60 3 E-6 Cu-64 2 E-4 l Zn-69m 6 E-5 l Sr-89 8 E-6 l ! Sr-90 5 E-7
- 1 l Sr-91 2 E-5 Zr-95 2 E-5 Mo-99 2 E-5 I-131 1 E-6 I-132 1 E-4 I-133 7 E-6 Cs-134 9 E-7 I-134 4 E-4 I-135 3 E-5 Cs-137 1 E-6 .
l La-141 5 E-5 Np-239 2 E-5 Am-241 2 E-8 Noble Gases 2 E-4 1 l l ODCM (BSEP) 2-10 Rev. 15
- mren/yeer par pCL/sse r8 for food and ground plans pathways 0, - The release. rate of radionuclide i in gaseous effluents s
from free standing stack, pC1/sec 0 3
- The release rate of radionuclide i in gaseous effluents v
from all vents releases, pCi/sec h4 - The highest calculated annual average dispersion paramet(r for estimating the dose to an individual at the controlling location due to all vent releases h; - sec/m for the inhalation pathway 2 h4 - meters 2 for the food and. ground. plane pathways W, - The highest calculated annual a terage dispersion parameter for estimating the dose to en individual at.the controlling location dt.e te stack releases W, - sec/m' for the inhalation pathway W, - meters 2 for the food and ground plane pathways Radiciodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP. Radioiodines, particulates, and tritium may also be released from decontamination operations in the Hot Shop and burning waste oil in the incinerator. Effluents from the Hot Shop roof vent and incinerator are combined with the. Turbine Building's vent l releases. To show compliance with 10CFR20, (see Appendix H for waste oil) Expression 3.2-9 is modified to incorporate the various release points for BSEP: l I ODCM (BSEP) 3-22 Rev. 15 j
' ,~
TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi) l
. Site - Milk Milk. Heat (Nearest Nearest-ector' Boundary Cow . Goat. . Animal Resident: Garden' j NNE 0.7 - - - 1.0 1.2 i l
NE 0.7 4.75* - - - - 1 ENE 0.7 - - - - - l ! E 0.7 - - - - - l ESE 0.7 - - - 1.5 - SE 0.7 - - 1.0 0.9 - , SSE 0.7 - - 1.0 1.0 - ! S 0.8 - - - 1.5 1.5 l SSW 0.8 - - - 1.2 1.5 ! j SW 0.7 - - - 1.0 1.0 ; WSW 0.7 - - - 1.1 1.1 W 0.7 - - - 0.8 0.8 WNW 0,6 - - - 0.9 0.9 l NW 0.6 - - - 0.9 0.9 NNW 0.6 - - - 0.8 4.3 N 0.7 - - - 0.9 - . 1 i i i l l l l l l i
*A " hypothetical" cow milk pathway is located at this point in accordance with 5.3.1 of NUREG 0133.
ODCM (BSEP) 3-30 Rev. 15
,' m3 sec/m' for the inhalation pathway and tritium
- meters 8 for the food and ground plane pathway w, - The dispersion parameter for estimating the dose to an individual at the controlling location for short-term vent releases (equal to or less than 500 hours / year)
- sec/m for the inhalation pathway and tritium 5
- meters 8 for the food and ground plane pathway 3.17 x 10' - The inverse of the number of seconds in a year R, - The dose factor for each identified radionuclide i of the i organ of interest, mrem /yr per pC1/see per m*8 or mrem /yr per pCi/m 8 Radioiodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings at BSEP. Radiciodines, particulates, and tritium may also be released from decontamination operations in the Hot Shop and burning waste oil in the incinerator. Effluents from the Hot Shop roof vent and incinerator are combined with the Turbine Building's vent releases. Burning waste oil in the incinerator is limited to 0.1% of 10CFR50 Appendix I (see Appendix H for methodology and calculations). At BSEP all releases are considered long-term in duration. Therefore, incorporating the various release points into Expression 3.3-13 results in the following expressions to show compliance with 10CFR50 for a particular organ:
3.17 x 10' I, R W, Qi + W i (Qi + Qi )+Wa (Qi + Q, ) s rbl rb2 tb1 tb2 s 15.0 mrem per quarter or 30 mrem per year (3.3-14) ODCM (BSEP) 3-42 Rev. 15
< l I II. Caseous Effluent Monitorine Instruments
- 1. Main Stack Monitoring System
- a. Noble Gas Activity Monitor 2-D12-RM-23S (2-D12-RE-4982)
- b. Iodine Sampler Cartridge IRSH35 Prefilters A or B
- c. Particulate Sampler Filter IRSH35 Prefilters A or B
- d. System Effluent Flow Rate 2-VA-FIQ-5902-1 OR Measurement Device
- e. Sampler Flow Rate Measurement 2-D12-FE-4597 l, Device 1
- 2. . Reactor Building Ventilation Monitoring System I
- a. Noble Gas Activity Monitor 1(2)-CAC-AQH-1264-3 l
l b. Iodine Sampler Cartridge 1(2)-CAC-AQH-1264-2 (collection cartridge only)
- c. Particulate Sampler Filter 1(2)-CAC-AQH-1264-1 (collection filter only)
- d. System Effluent Flow Rate 1(2)-VA-FIQ-3356 Measurement Device
- e. Sampler Flow Rate Measurement 1(2)-CAC-FI-1264 Device l 3. Turbine Building Ventilation Monitoring System
- a. Noble Gas Activity Monitor 1(2)-D12-RM-23 (l(2)-D12-RE-4563)
- b. Iodine Sampler Cartridge 1(2)-IRTB32 Prefilters A or B
- c. Particulate Sampler Filter 1(2)-IRTB32 Prefilters A or B l
- d. System Effluent Flow Rate 1(2)-VA-FIQ-3358 )
Measurement Device l
- e. Sampler Flow Rate Measurement 1(2)-D12-FE-4542 l Device l 4. Main Condenser Air Ejector Radioactivity Monitor
- a. Nolle Gas Activity Monitor 1(2)-D12-RM K601 A and B i
I 1 l ODCM (BSEP) E-2 Rev. 15 l l
l c l [ 6. Main Condanser Off-Gas Treatment System ( (A0G) Monitor i ! a. Noble Gas Activity Monitor 1(2)-A0G-RM-103 I ' 6. Main Condensor Off-Gas Treatment System Explosive Gas Monitoring System
- a. Recombiner Train A
- 1. First Hydrogen Monitor 1(2)-0G AIT 4284 -
Stream 1
- 2. Second Hydrogen Monitor 1(2)-0G-AIT-4324 -
Stream 2
- b. Recombiner Train B
- 1. First Hydrogen Monitor 1(2)-0G-AIT-4324 - ,
Stream 1 1
- 2. Second Hydrogen Monitor 1(2)-00-AIT-4284 -
Stream 2 I
- 7. Hot Shop Ventilation Monitoring System
- a. Iodino Sampler Cartridge
- b. Particulate Sampler Filter l
l l ODCM (BSEP) E-3 Rev. 15}}