BSEP-87-0181, Semiannual Radioactive Effluent Release Rept Jul-Dec 1986
| ML20211P544 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/31/1986 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BSEP-87-0181, BSEP-87-181, NUDOCS 8703020384 | |
| Download: ML20211P544 (58) | |
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( *p Brunswick Steam El ectr i c P1 ant Semiannual Radioactive Effluent Release Report July 1, to Decmber 31, 1986 ATTACHMENTS : PAGES :
- 1. Supplemental Information 1/1 to 1/4
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- 2. Effluent and Waste Disposal Data 2/1 to 2/15 f
- 4. Environmental Monitoring Program 4/1 to 4/3
- 5. Inoperable Effluent Instrumentation 5/1 to 5/4 f
- 6. Major Modifications to Radicactive Waste Treatment Systems 6/1
- 7. Meteorological Data 7/1 j 8. P o t,en t i a l Dose Assessment 8/1 to 8/7 t
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.s ATTACHiiENT 1 Supplemental Information July 1, to December 31, 1986 l
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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plant Licensee: Carolina Power 6 Light Company
- 1. Regulatory Limits A. rission and activation gases (Technical Specification 3.11.2.2)
X(1) Calendar Quarter (a) 10 mrad gamma (b) 20 mrad beta (2) Calender Year (a) 20 mrad gamma (b) 40 mrad beta D. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.31
- (1) Calendar Guarter (a) 15 mrem to any organ (2) Calendar Year (a) 30 mrem to any organ C. Liquid ef fl uen ts (Technical Specification 3.11.1.2)
- (1) Calendar Guarter (a) 3 mrem to total body (b) 10 mrem to any organ (2) Calendar Year (a) 6 mnem to total body (b) 20 mrem to any organ NOTE: Dose calculations are determined in accordance with the Off-site Dose Calculation Manual (ODCM).
- Used for percent of technical specification limit determinations in Table 1A.
M* Used for percent of technical soecification limit determinations in Table 2A.
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- 2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and ac'tivation gases (Technical Specification 3.11.2.1.a)
(1) 500 mrom / gear to total body (2) 3000 mrem / year to the skin B. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.1.b)
(1) 1300 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, Table II, column 2, for radionuclides other than noble gases.
- 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. Liquid Effluents Analysis for specific radionuclides of individual releases by gamma spectroscopy.
- Used as applicable limits for Table 2A 1/3
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Nuclear counting statistics are reported utilizing 1-sigma error. Total error where reported represents a best effort to approximate the total of all individual and sampling errors.
- 4. Batch Releases A. Liquid (1) Number of batch releases: 1.48E+02 (2) Total time period for batch r el eases : 1.76E+04 Minutes (3) Maximum time period for a batch release: 1.62E+02 Minutes (4) Average time period for a batch release: 1.19E+02 Minutes (5) Minimum time period for a batch release: 1.30E+01 Minutes (6) Average stream flow during periods of release of ef fl uen t into a flowing stream: 7.48E+05 G.P.M.
B. Gaseous (1) Number of batch releases: 0.00E 00 (2) Total time period for a batch release: 0.00E 00 Minutes (3) Maximum time period for a batch release: 0.00E 00 Minutes (4) Average time period for a batch release: 0.00E 00 Minutes (5) Minimum time period for a batch release: 0.00E 00 Minutes
- 5. Abnormal releases A. Liquid (1) Number of releases: 0.00E 00 (2) Total activity released: 0.00E 00 Ci B. Gaseous (1) Number of releases: 0.00E 00 (2) . Total activity released: 0.00E-00 Ci 1/4
ATTACHMEf4T 2 Effluent and Waste Disposal Data Brunswick Steam Electric Plant July 1, to December 31, 1986 Enclosure 1 Table 1A: Gaseous Effluents - Summation of All Releases Table 1B: Gaseous Effluents - Elevated Releases Table 1C: Gaseous Effluents - Ground Level Releases Table 2A: Liquid Effluents - Summation of All Releases Table 20: Liquid Effluents Lower Limits of Detection Table 3: Solid Waste and Irradiated Fuel Shipments Enclosure 2: Combustion of Waste Oil 2/1
Table 1A Effluent and Waste Disposal Semiannual Rennrt Year 1986 Gaseous Effluents - Summation of All Releases Est.
Total Unit Gtr 3 Otr 4 Error %
A. Fission and activation gases
- 1. Total release Ci 1.34E 04 1.11E 04 1.15E 02
- 2. Average release rate uCi/sec 1.68E 03 1.40E 03 for period
- 3. Percent of technical specification limit % 5.19E-01 3.76E-01
- 8. Iodined
- 1. Total iodine-131 Ci 8.89E-03 5.24E-03 7.00E 01
- 2. Average release rate uCi/sec 1.12E-03 6.59E-04 for oeriod C. Particulated
- 1. Total release Ci 9.36E-03 1.55E-02 7.00E 01
- 2. Average release rate uCi/sec 1.18E-03 1.95E-03 for period
- 3. Gross alpha Ci 7.96E-05 7.20E-03 D. Tritium
- 1. Total release Ci 1.99E 00 2.13E 00 7.00E 01
- 2. Average release rate uCi/ set 2.50E-01 2.68E-01 for oeriod E. Iodine-131 Iodine-133, Tritium and Particulates
- 1. Total release Ci 2.04E 00 2.17E 00
- 2. Average release rate uCi/sec 2.37E-01 2.73E-01 for period
- 3. Percent of t.echnical % 3.27E-01 1.99E-01 specification limit 2/2
Table 1B Effluent and Waste Disposal Semiannual Reoort Year 1986 Gaseous Effluents - Elevated Release Continuous Release Nuclides' Released Unit Otr 3 glr 4
- 1. Fission Gases argon-41 Ci 1.89E 01 1.33E 01 krypton-85m Ci 5.35E 00 2.67E 00 krypton-87 Ci 4.51E-01 3.35E 00 krypton-88 Ci 3.06E 00 5.34E 00 xenon-133 Ci 8.96E 00 9.94E 00 xenon-135m Ci 1.64E 01 3.78E 01 xenon-135 Ci 5.63E 00 4.36E 01 xenon-137 Ci 9.26E 01 9.96E 01 xenon-138 Ci 4.16E 01 4.91E 01 total for period Ci 1.93E O2 2.65E 02
- 2. Iodines iodine-131 Ci 5.57E-03 3.26E-03 iodine-132 Ci 8.11E-03 6.07E-03 iodine-133 Ci 1.80E-02 1.17E-02 iodine-133 Ci 1.06E-02 7.66E-03 total for period Ci 4.23E-02 2.87E-02 3.Particulates chromium-51 Ci 1.41E-04 3.92E-04 manganese-54 Ci 3.36E-05 3.60E-05 cobalt-58 Ci 5.90E-06 1.17E-05 cobalt-60 Ci 5.93E-05 5.10E-05 strontium-89 Ci 5.17E-04 9.56E-04 strontium-90 Ci 1.96E-06 3.67E-06 cesium-137 Ci 1.27E-05 2.61E-05 barium-140 Ci 6.80E-04 1.23E-03 lanthanum-140 Ci 4.83E-04 8.71E-04 total for period Ci 1.93E-03 3.58E-03
- 4. Tritium hydrogen-3 Ci 7.06E-01 3.70E-01 2/3
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. '1 Table 1C
- Effluent and Waste Discosal Semiannual Report Year 1986 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Otr 3 Otr 4
- 1. Fission Gases krypton-85m Ci 7.59E-02 <-LLD krypton-88 Ci 3.60E-01 < LLD xenon-133m Ci 1.03E 02 < LLD xenon-133 Ci 2.34E 03 4.23E 03 xenon-135m Ci 3.36E-01 < LLD xenon-135 Cl 1.07E 04 '6.60E 03
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total for period Ci 1.31E 04 1.08E 04
- 2. Iodines lodine-131 Ci 3.32E-03 1.98E-03 iodine-132 Ci 1.67E-02 1.14E-02 iodine-133 Ci 1.79E-02 1.13E-02 iodine-135 Ci 2.02E-02 1.09E-02 total for period Ci 5.81E-02 3.56E-02 3.Particulates chromium-51 Ci 6.02E-03 1.01E-02 manganese-54 Ci 3.5GE-04 4.77E-04 cobalt-58 Ci 1.24E-04 2.32E-04 iron-59 Ci < LLD 0.44E-05 cobalt-60 Ci 5.54E-04 8.30E-04 strontium-09 Ci 6.97E-05 4.38E-05 strontium-90 Ci 6.39E-07 2.36E-07 cesium-137 Ci 7.08E-06 1.96E-05 barium-lanthanum-140 Ci 2.47E-04 5.70E-05 silver-110m Ci 4.19E-05 < LLD zinc-65 Ci < LLD 6.37E-05 total for period Ci 7.42E-03 1.19E-02
- 4. Tritium hydrogen-3 Ci 1.20E 00 1.76E 00 .
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TABLE 2A Et' fluent and Waste Di sposal Semiannual Report Year 1986 Liquid Effluents - Summation of All Releases Unit Otr 3 Otr 4 Est Tot.
Error, %
A. Fission and activation products
- 1. Total release (excluding Ci 1.81E-02 2.50E-02 3.50E 01 tritium, gases, alpha) 2.Av. diluted concentration uCi/ml 9.10E-10 9.12E-10
- 3. Percent limit % 2.00E-02 2.50E-02 B. Tritium
- 1. Total release Ci 7.51E-01 2.40E 00 4.00E 01 2.Av. diluted concentration uCi/ml 3.77E-08 8.76E-08
- 3. Percent limit % 1.26E-03 2.92E-03 C. Dissolved and entrained gases
- 1. Total release Ci 5.10E-03 3.92E-02 3.50E 01 2.Av. diluted concei.tration uCi/mi 2.56E-10 1.43E-09
- 3. Percent limit % 1.20E-04 7.15E-04 D. Gross alpha radioactivitg
- 1. Total release Ci 1.54E-03 0.00E 00 4.00E 01 E. Volume of waste liters 3.71E 06 6.00E 06 1.25E 01 F. Total volume of dilution water (L)
(used during released for av.
diluted concentration) liters 1.99E 10 2.74E 10 1.30E 01 G. Volume of cooling water discharged from plant liters 4.22E 11 2.94E 11 I 2/5
TABLE 2B Effluent and Waste Disposal Semiannual Report Year 1986 Liquid Effluents - Batch Mode o
Nuclides Released Unit Gtr 3 Otr 4
- 1. Fission and activation products undium-24 Ci < LLD 5.38E-06 chromium-51 Ci 9.95E-04 1.63E-02 manganese-54 Ci 4.27E-03 1.46E-03 iron-55 Ci 4.08E-03 1.45E-03 manganese-56 Ci < LLD 7.00E-05 cobalt-58 Ci 3.10E-04 1.51E-04 Iron-59 Ci 6.16E-05 5.90E-05 cobalt-60 Ci 5.18E-03 3.13E-03 arsenic-76 Ci 6.44E-06 2.56E-04 strontium-90 Ci 2.06E-05 2.27E-05 strontium-92 Ci < LLD 4.94E-05 yttrium-91m Ci 1.83E-05 < LLD uttrium-92 Ci '7.04E-05 4.90E-05 ;
niobium-97 Ci < LLD 2.91E-05 technetium-99m Ci 1.10E-06 4.32E-06 technetium-104 Ci < LLD 1.17E-05 ruthenium-105 Ci < LLD 7.00E-05 silver-110m Ci < LLD 1.95E-04 iodine-131 Ci 2.09E-04 4.39E-04 iodine-133 Ci 1.40E-04 1.59E-04 cesium-134 Ci 3.45E-04 8.46E-05 cesium-137 Ci 2.33E-03 9.06E-04
. lanthanum-140 Ci < LLD 1.49E-05 tungsten-107 Ci ( LLD 1.76E-05
- - - . - - . - . - . - - - - - - - - - - - - - - - - . - - - - . . - ~ ~ . - - - - - - - - - - - - - - - - - - - - - -
total for period Ci 1.81E-02 2.50E-02 2/6
TABLE 2B (cont)
Ef fluent and Waste Disposal Semiannual Report Year 1986 Liquid Effluents - Batch Mode
- 2. Gases argon-41 Ci 2.59E-05 ( LLD krypton-85 Ci 5.16E-04 < LLD krypton-87 Ci < LLD 8.88E-06 xenon-133 Ci 5.62E-04 1.26E-02 xenon-133m Ci < LLD 3.18E-04 xenon-135m Ci 1.40E-05 5.00E-06 xenon-135 Ci 3.98E-03 2.63E-02 total for period Ci 5.10E-03 3.92E-02 r;
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Lower Limits of Detection uCi/ml
- 1. Liould Releases 2. Baseous Releases Na-24 2.71E-08 Kr-85m 2.15E-08 Mn-56 7.13E-08 Kr-88 6.23E-08 Y-91m 2.97E-08 Xe-133m 9.94E-08 Gr-92 2.94E-08 Xe-135m 7.09E-08 Nb-97 2.23E-06 Tc-104 6.04E-08 3. Iodines and Particulates Ru-105 4.46E-08 Ag-110m 6.81E-08 Fe-59 7.75E-14 La-140 4.15E-08 Zn-65 4.35E-14 W-187 3.67E-08 Ag-110m 7.79E-14 Ar-41 2.68E-08 Kr-85 5.27E-06 Kr-87 4.29E-08 Xe-133m 1.06E-07 G-Alpha 2.85E-08 NOTES 1: The above values represent typical 'a priori' LLDs for isotopes where values of '< LLD' are indicated in Tables 1A, 10, 1C,2A and 20.
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 Year 1986 Solid Waste and Irradiated Fuel Shipments Waste Class A July through December
- 1. Total volume shipped, cubic meters 3.65E 02 Total Ci quantity (estimated) 1.17E 03
- 2. Type of Waste Units Six-Month Est. Total Period Error, %
- a. Spent resins, filter sludges cubic meters 1.64E 02 Curies 1.16E 03 1.00E 01
- b. Dry active waste, compacted, cubic meters 1.93E 02 noncompacted Curies 1.18E 01 1.00E 01
- c. Irradiated components: cubic meters N/A Curies N/A N/A d .Others( sol i d i f i ed o i l ) cubic meters 0.30E 00 Curies 5.87E-02 1.00E 01 e
- 3. Estimate of major radionuclide composition
- a. Cc-51 1.02E 01 %
Mn-54 1.67E 01 %
Fe-55 2.72E 01 %
Co-50 3.12E 00 %
Co-60 3.45E 01 %
Ni-63 2.34E 00 %
Cs-137 3.94E 00 %
- b. Mn-54 5.02E 00 %
Fe-55 4.23E 01 %
Co-60 4.12E 01 %
Ni-63 9.90E-01 %
Sr-09 2.00E 00 %
Cs-137 5.35E 00 %
- c. N/A N/A
- d. Fe-55 4.47E 01 %
Co-60 2.70E 01 %
Sr-09 1.41E 01 %
Gr-90 0.64E 00 %
Pu-241 4.65E 00 %
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TABLE 3A (cont)
Effluent and Waste Disposal Semiannual Report Year 1906 Solid Waste and Irradiated Fuel Shipments
- 4. Cross reference table, waste str eam, form,conta iner type.
Stream Form Container Type No. Shipments
- a. Resin Dewatered & Type A/ Type B 33/00 Solidified *
- b. Dry active Compacted /non-waste compacted LSA/STP 9 waste
- c. Irradiated N/A N/A components
- d. Other Solidified Oil
- Type A 1
- Solidification agent or absorbent (e.g.,
cement, urea formaldehyde, etc.) CEMENT
- 5. Shipment Disposition
- a. Solid Waste Number of Shipments Mode of Transportation Destination 38 Sole Use Chem-Nuclear Barnwell, SC 5 Sole Use U.S. Ecology Richland, WA
- b. Irradiated Fuel Number of Shipments Mode of Transportation Destination N/A N/A N/A 9
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TABLE 3B Effluent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments Waste Class B July through December
- 1. Total volume shipped, cubic meters 0.00E 00 Total Ci quantity (estimated! O.30E 00
- 2. Type _of Waste Units Six-Month Est. Total Period Error, %
- a. Spent resins, filter sludges cubic meters N/A Curies N/A N/A
- b. Dry active waste, compacted, cubic meters N/A noncompacted Curies N/A N/A
- c. Irradiated components: cubic meters N/A Curies N/A N/A d.Others(describe): cubic meters N/A Curies N/A N/A
- 3. Estimate of major radionuclide composition
- a. N/A N/A
- b. N/A N/A
- c. N/A N/A
- d. N/A N/A
- 4. Cross reference table, waste stream, form, container type.
Stream Form Container Type No. Shipments
- a. Resin Dewatered & N/A N/A Golidified
- Dry active Compacted /non-waste compacted N/A N/A s waste
- c. Irradiated N/A components
- d. Other N/A
- Solidification agent or absorbent (e.g.,
l cement, urea formaldehyde,etc.) N/A 2/11 J
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TABLE 30 (cont) e Effluent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments
- 5. Shipment Disposition
- a. Solid Waste Number of Shipments Mode of Transportation Destination N/A N/A N/A
- b. Irradiated Fuel Number of Shipments Mode of Transporation Destination N/A N/A N/A 2/12
. -. - - . . - _ = _ _ - . _ . - - -
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i-TABLE 3C Effulent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments Waste Class C July through December l
- 1. Total volume shipped, cubic meters 2.25E 00 Total Ci quanity-(estimated) 7.77E 03
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- 2. Type of Waste Units Six-Month Est. Total Period Error, %
j a. Spent resins, filter sludges cubic meters N/A Curies N/A N/A i
- b. Dry active waste, compacted, cubic meters N/A !
i noncompacted Curies N/A N/A
- c. Irradiated components: cubic meters 2.25E 00 Curies 7.77E 03 1.00E 01 d.Others(describe): cubic meters F/A I Curies N/A N/A
, 3. Estimate of major radionucildes composition t a. N/A N/A l
- b. N/A N/A i
i c. Fe-55 4.39E 01 >
Co-60 5.00E 01 Ni-63 5.07E 00 ;
j d. N/A N/A l 4. Cross reference table, waste stream, form, container type.
i Stream Form Container Type No. Shipments i a. Resin Dewatered 6 Type A/ Type B N/A I
- Solidified
- l b. Dry active Compacted /non-I waste compacted N/A N/A i waste
- l. c. Irradiated Type B 2 components
- d. Others N/A N/A i
- Solidification agent or absorbent (e.g.,
! cement, urea formaldehyde, etc.) N/A o
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TABLE 3C (cont)
Effluent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments
- 5. Shipment Disposition a.Golid Waste Number of Shipments Mode of Transportation Destination N/A N/A N/A
- b. Irradiated Components Number of Shipments Mode of Transporation Destination 2 Sole Use Chem Nuclear Barnwell, SC i
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- - ENCLOSURE 2 i
Combustion of Waste Oil I
- During the third and fourth quarters 0.00 gallons of waste oil were -
i I disposed of by incineration.
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q ATTACHMENT 3 Off-site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions I
- July 1, to December 31, 1986
> Brunswick Steam Electric Plant 4
f Enclosure 1: Revisions to the Off-site Dose Calculation Manual (ODCM)
Enc 1osure 2: Revisions to the Process Contr01 Progeam (PCP) i i-i 1
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ENCLOSURE 1
. Revision 6 of the Offsite Dose Calculation Manual
. Section 3.2.1, pages 3-19 were revised to clarify the' determinant factor in the selection of the control location for compliance with 10CFR20 for noble gases.
Footnotes were added to Sections 3.2.2, pages 3-21 and 3.3.2, pages 3-40, to clarify the I-133 values used in the ODCM for effluent accountability.
Section 3.2.2, pages 3-27 were revised to clarify the determinant factor in the selection of the control location for compilance with
! Table 3.2-2 " Distance to Controlling Locations as Measured from the
^
Brunswick Plant Center (MI)" was revised to be consistent with the
! current Land Use Census.
2 Sec tion 3.3.1, pages 3-39 were revised to clar ify the determinant !
factor in the selection of the control location for compliance with 10CFR50 for noble gases.
1 Table 4.0-1 was revised to correct a typographical error in Gample j 3 ID No.700.
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! AI-61, Attachment 1, has been included to provido documentation of !
i PNGC review i :
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ATTACHMENT 1 REQUEST FOR OFF SITE DOSE CALCULATION MANUAL CHANGE Originator: he M /. /M /.~ f Date: /o /2 r /F4' s
Pages and sections revised: 3 2/ , 3-30 3 - </o v . <,r
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a 3 2 1,3-3, e
Reason for change: 3 7/1/,, /., u, f,' , 3. 7. 2 ../ 3. 3. 2 -.,. ,. J./ A .. ,
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- 5. S L /., ss s
.ab f.*.'$.1,'a:bU1.$rT .'t. W # "*' *"** B "'" ***' *
Safety Analysis Complete fo /2 3 /yg (RCI-03.1 Attach:.ent 1): I MM Date: _fe /;z@ E k
Tsf Party Nu.: leal Safety Reviewer
/ ommende / Mot N ore: ended Date: 10/31/E
/ ' !
, 4_. ( Recomme W L enerended Date: / if y/p b d Pr!.-ty Su.lcar Safety heviewe'r- D -
b m ,Not Recommended Dan: _ / / ") !
Fff s(p5 isor mu [h_ C o ra ~ r. ' dot Recoe. mended Date: /[iM C ProTecFSpecialis t g 3 APPROVALS:
V Recommende .!ot Recommended Date: ///
Manager - E&RC 1 t' f_ h .u -
Recoeciended/Not-hcocaendei Date: e!-c AC PNSC Chairman
/
i (km ,fO Approved /No @ proved Date: b 7 3 t' -
j,,, General Manager . _ .
1 .
9 BSEP/Vol. I/AI-61 3 Rev. 2
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BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)
REVISION 6 .
DOCKET NOS. 50-324 50-325 9
h CAROLINA POWER & LIGHT COMPANY t
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LIST OF EFFECTIVE PAGES ODCM l
Page(s) Revision i
I i-ix 6 1-1 0 2 2-2 0 2 2-6 1 2-7 0 2 2-10 1 2 2-12 0 l- 2 2-16 1
! 3 3-12 4 l 3-13 1 3-14 4 l 3-15 5
' 3 3-18 4 3-19 6 3-20 1 3-21 6 3 3-23 1 3-24 4 3-25
- 1 3-26 4 3-27 6 3-28 4 3-29 1 3-30 6 3-31 4 3 3-36 1 3 3-38 4 3 3-40 6 3 3-45 1
! 3 3-48 4 3 3-68 1 4-1 1 i 4 4-3 5 l 4-4 6 l 4-5 4
! 4 4-7 3 j 5-1 0 6 6-2 0 6-3 4 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 A A-21 0 ODCM (BSEP) i Rev. 6 l l
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LIST OF EFFECTIVE PAGES (Continued)
ODCM o
Page(s) Revision A-22 4 A A-28 0 B B-33 0 C C-18 0 D D-2 1 E-1 4 E-2 3 E-3 4 F F-3 0 G-1 1 ,
TABLE OF CONTENTS Section , Title Page List of Effective Pages..................................... i Table of Contents........................................... iii List of Tab 1es.............................................. iv List of Figures............................................. ix
1.0 INTRODUCTION
................................................ 1-1 2.0 LIQUID EFFLUENTS............................................ 2-1 2.1 Compliance with 10CFR20 (Liquids).................... 2-1 (Alarm / Trip Setpoint Determination) 2.2 Compliance with 10CFR50 (Liquids).................... 2-11 3.0 G AS EOU S EF FLU ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.1 Monitor Alarm Setpoint Determination................. 3-1 3.2 Compliance with 10CFR20 (Gaseous).................... 3-15 3.3 Compliance with 10CFR50 (Gaseous).................... 3-34 4.0 RADIOLOGICAL ENVIRONMENTAL.................................. 4-1 MONITORING PROGRAM 5.0 INTERLABORATORY COMPARISON PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 6.0 TOTAL DOSE (40CFR190 CONFORMANCE)........................... 6-1 APPENDIX A - Meteorological Dispersion Factor. . . . . . . . . . . . . . . A-1 Computations APPENDIX B - Calculation of B and Vf Values................ B-1 for the Elevated lume APPENDIX C - Dose Parameters for Radioiodines............... C-1 Particulates, and Tritium APPENDIX D - Lower Limit of Detection (LLD)................. D-1 APPENDIX E - Radioactive Liquid and Gaseous................. E-1 Effluent Monitoring Instrumentation Numbers APPENDIX F - Liquid and Gaseous Effluent System ............ F-1 Diagrams APPENDIX G - ODCM Software Package.......................... G-1 ODCM (BSEP) 111 Rev. 6 l
LIST OF TABLES No. ,
Title Pg 2.1-1 MPCs for Selected Radionuclides......................... 2-10 2.2-1 Ag Values for the Adult................................ 2-14 3.1-1 Gaseous Source Terms.................................... 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 Distance to Controlling Locations as Measured........... 3-30 from the Brunswick Plant Center 3.2-3 Distance to Site Boundaries Based Upon Brunswick. . . .. . . . 3-31 Plant Center and Direction from the Stack 3.2-4 Dose Factors for Noble Gases and Daughters.............. 3-32 3.2-5 P, Values for an Inf ant for the Brunswick Steam. . .. . .. . . 3-33 EIectric Plant 3.3-1 thru R Values for the Brunswick Steam Electric Plant......... 3-50 3.3-19 4.0-1 Radiological Environmental Monitoring Program........... 4-2 A-1 X/Q Values at the Special Locations for Releases........ A-5 from the Turbine Buildings A-2 Depleted X/Q Values at the Special Locations for........ A-6 Releases from the Turbine Buildings A-3 D/Q Values at the Special Locations for Releases........ A-7 from the Turbine Buildings A-4 X/Q Values at the Standard Distances for Releases....... A-8 from the Turbine Buildings A-5 Depleted X/Q Values at the Standard Distances for....... A-9 Releases from ,the Turbine Buildings
,A-10 A-6 D/Q Values at the Standard Distances for Releases.......
from the Turbine Buildings A-7 X/Q Values at the Special Locations for Releases........ A-11 from the Reactor Buildings .
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'e LIST OF TABLES (continued)
No. , Title Page A-8 Depleted X/Q Values at the Special Locations for........ A-12 Releases from the Reactor Buildings
. A-9 D/Q Values at the Special Locations for Releases........ A-13 from the Reactor Buildings A-10 X/Q Values at the Standard Distances for Releases....... A-14 from the Reactor Buildings A-11 Depleted X/Q Values at the Standard Distances for....... A-15 Releases from the Reactor Buildings A-12 , D/Q Values at the Standard Distances for Releases....... A-16 from the Reactor Buildings t -
A-13 X/Q Values at the Special Locations for Releases........ A-17 from the Stack A-14 Depleted X/Q Values at the Special Locations for........ A-18 Releases from the Stack A-15 D/Q Values at the Special Locations for Releases........ A-19 from the Stack A-16 X/Q Values at the Standard Distances for Releases....... A-20 from the Stack A-17 Depleted X/Q Values at the Standard Distances for....... A-21 Releases from the Stack A-18 D/Q Values at the Standard Distances for Releases....... A-22 from the Stack .
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A- 19 Brunswick Plant Site Information to be'Used for......... A-23 Ground Level Calculations with NRC "XOQD0Q" Program A-20 Brunswick Plant Site Information to be Used for......... A-26 Elevated Release Calculations with NRC "XOQD0Q" Program -
B-1 Dose Parameters for Finite Elevated Plumes ENE.......... B-2 Site Boundary 1 B-2 Joint Frequency Distribution for ENE Sector (%) . . . . . . . . . B-3 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant .
B-3 Dose Parameters for Finite Elevated Plumes N Site....... B-4 Boundary ODCM (ESEP) v Rev. 6 l l l
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LIST OF TABLES (continued)
No. , Title Page B-4 Joint Frequency Distribution for N Sector (%)........... B-5 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-5 Dose Parameters for Finite Elevated Plumes NNE.......... B-6 Site Boundary B-6 Joint Frequency Distribution for the NNE Sector (%)..... B-7 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-7 Dose Parameters for Finite Elevated Plumes NE Site. .. . . . B-8 Boundary B-8 Joint Frequency Distribution for NE Sector (%) ......... B-9 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-9 Dose Parameters for Finite Elevated-Plumes E Site....... B-10 Boundary B-10 Joint Frequency Distribution for E' Sector (%)...........- B-11 Period 1-1-77.through 12-31-77, Brunswick Steam Electric Plant B-11 Dose Parameters for Finite Elevated Plumes ESE.......... B-12 Site Boundary B-12 Joint Frequency Distribution for ESE Sector (%) . . . . . . . . . B-13 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-13 Dose Parameters for Finite Elevated Plumes SE Site...... B-14 Boundary B-14 Joint Frequency Distribution for SE Sector (%).......... B-15 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-15 Dose Parameters for Finite Elevated Plumes SSE Site..... B-16 Boundary i
B-16 Joint 7requency Distribution for SSE Sector (%) .. ..... .. B-17 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-17 Dose Parameters for Finite Elevated Plumes S Site....... B-18 Boundary ODCM (BSEP) vi Rev. 6 l
LIST OF TABLES (continued)
No.
Title Py B-18 Joint Frequency Distribution for S Sector (%)........... B-19 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-19 Dose Parameters for Finite Elevated Plumes SSW.......... B-20 Site Boundary B-20 Joint Frequency Distribution - for SSW Sector (%) . . . . . . . . . B-21 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-21 Dose Parameters for Finite Elevated Plumes SW........... B-22 Site Boundary B-22 . Joint Frequency Distribution for SW Sector (%) . . . . . . . . . . B-23 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-23 Dose Parameters for Finite Elevated Plumes WSW.......... B-24 Site Boundary B-24 Joint Frequency Distribution for WSW Sector (%)......... B-25 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-25 Dose Parameters for Finite Elevated Plumes W Site....... B-26 i Boundary B-26 Joint Frequency Distribution for W Sector (%) . . . . . . . . . . . B-27 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant B-27 Dose Parameters for Finite Elevated Plumes WNW.......... B-28 Site Boundary B-28 Joint Frequency Distribution for WNW Sector (%) . . . . . . . . . B-29 l
Period 1-1-77 through 12-31-77, Brunswick Steam l Electric Plant B-29 Dose Parameters for Finite Elevated Plumes NW Site...... B-30 Boundary B-30 Joint Frequency Distribution for NW Sector (%).......... B-31 Period 1-1-77 through 12-31-77, Brunswick Steam
. Electric Plant I
- B-31 Dose Parameters for Finite Elevated Plumes NNW.......... B-32 l- Site Boundary ODCM (BSEP) vii Rev. 6 l
LIST OF TABLES (continued)
No. ,
Title Py B-32 Joint Frequency Distribution for NNW Sector (%)......... B-33 Period 1-1-77 through 12-31-77, Brunswick Steam Electric Plant C-1 Parameters for Cow and Goat Milk Pathways............... C-16 C-2 Parameters for the Meat Pathway......................... C-17 C-3 Parameters for Vegetable Pathway........................ C-18 l
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LIST OF FIGURES No. Title Page 4.0-1a' BSEP Sample Point Locations................................ 4-5
, 4.0-lb BSEP Sample Point Locations................................ 4-6 4.0-1c BSEP Sample Point Locations................................ 4-7 4.0-Id BSEP Sample Point Locations................................ 4-8 F-1 Liquid Radwaste Effluent System............................ F-2 F-3 4
F-2 Gaseous Radwaste Effluent System...........................
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Long-term annual (X/Q) values for the stack, Reactor Building, and Turbine Building release points from BSEP to the special locations in Table 3.2-2 are presented in Appendix A. A description of the derivation is also provided in this appendix. X/Q values at the limiting site boundary for releases from the Turbine Building, Reactor Building, and stack were obtained from Tables A-1, A-7, and A-13, respectively, of the appendix.
To determine the controlling location for implementation of 10CFR20, the two or three highest site boundary X/Q values for each release point were utilized in conjunction with the radionuclide mix and release rate for each release point. Since mixed mode and elevated releases occur from BSEP, their maximum X/Q value may not decrease with distance; i.e. , the site boundary may not have the highest X/O values. Therefore, long . term annual average X/Q values were calculated at the midpoint of the 10 standard distances as given in Table A-4 of Appendix A. The highest two or three X/Q values for each release point at a distance greater than the site boundary were used in conjunction with the radionuclide mix to determine the controlling location. A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For BSEP, it is the stack, and the dominant factor in determining a control location becomes the V values. The controlling location is at the ENE at the site boundary due to its higher V 1
values.
Values for K , L , and M , which were used in the determination of the g g controlling locations and which are to be used by BSEP in Expressions 3.2-5 and 3.2-6 to show compliance with 10CFR20, are presente'd in Table 3.2-4.
These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of the NRC Regulatory Guide 1.109 Revision 1. The values have been 6 ~1 multiplied by 10 to convert picoeuries to microcuries for use in Expressions 3.2-5 and 3.2-6.
Values for Vg and B for the finite plume model can be expressed as shown in Equations 3.2-7 and 3.2-8. They were calculated at the site boundary of each of the 16 sectors using the NRC code RABFIN. Values for V an'd B for each of the 16 sectors are presented in Appendix B.
The Vg factor is computed with conversion from air dose to tissue depth dose, thus; ,
V = 1.1 K/r d jzrr kl (3.2-7)
.i where:
u T
= The tissue energy absorption coefficient for photons of energy Ey , cm 2/gm T
d
= The tissue density thickness taken to represent the total body dose '(5 gm/cm2 )
1.1 = The ratio of the tissue to air absorption coefficients over.the energy range of photons of interest, mrem / mrad 3.2.2 I-131, I-133, Particulates, an'd Tritium
- l The dose rate in unrestricted areas resulting from the release of radio-iodines and particulates with half-lives greater than 8 days is limited to 1500 mrem / year to any organ. Based upon NUREG 0133, the following is used to show compliance with 10CFR20.
3 E P (W,h g +W , h) g s 1500 mrem /yr (3.2-9) s V where:
P = Dont parameter for radioiodines and particulates with
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half-lives greater than 8 days based upon the critical organ and the most restrictive age group s -
= mrem / year per pCi/m for inhalation pathways and for tritium
For tritium, at the limiting site boundary, Equation .3.2-13 becomes:
For tritium:
bT = 3.0 x 10 8 (2.5 x 10 8 h + 2.0 x 10 7 h g + 2.9 x 10 8 h e ) (3.2-16) s rb tb At the " hypothetical" limiting real pathway location, Equation 3.2-13 becomes:
For tritium:
DT = 3.0 x 103 (2.4 x 10 8 9 + 4,y x to_8 Q g + 1.4 x 10 7 O g ) (3.2-17) s rb tb The determination of controlling location for implementation of 10CFR20 for radioiodines and particulates is a function of the same two parameters as for noble gases plus a' third receptor pathway location. The radionuclide mix was again based upon the source terms calculated using the GALE code. The mix and the source terms are presented in Table 3.2-1 as a function of release point.
In the determination of the controlling site boundary location, the highest two or three site boundary X/Q and D/Q values for each release point were l utilized in conjunction with the radionuclide mix and the release rate for each release point. At BSEP, the release rate which dominates comes from the l stack. The higher values for X/Q and D/Q for the- NE sector at the site boundary make it.the dominant meterological sector and the control location.
In the determination of receptor controlling. location, the highest two or three D/Q values from each release point to the pathway locations of.
Table 3.2-2 are utilized in conjunction with the radionuclide mix and reledse rate for each release point. For BSEP, the controlling location is a hypothetical cow milk pathway 4.75 miles NE of the Reactor Building and Turbine Buildings.
TABLE 3.2-2
, DISTANCE TO CONTROLLING LOCATIONS AS MEASLTED FROM THE BRITSWICK PLANT CENTER (Mi)
Site Milk Milk Meat Nearest Nearest Sector Boundary Cow Coat Animal Resident Garden NNE 0.7 - -
1.3' 1.2 1.2 l NE 0.7 4.75* - - - -
ENE 0.7 - - - - -
E 0.7 - -
0.7 - -
l ESE 0.7 - -
0.6 1.6 1.5 l SE 0.7 - -
0.6 0.9 -
l SSE 0.7 - -
0.7 2.3 -
l S 0.8 - -
1.1 1.5 1.7 l SSW 0.8 - -
1.4 1.4 1.4 l SW 0.7 - - -
1.0 1.0 l WSW 0.7 - -
2.0 1.1 1.0 l W 0.7 -- - -
0.8 0.9 l WNW 0.6 - - -
0.9 0.9 NW 0.6 - - - 0.9 1.1 l NNW 0.6 - - -
0.9 0.9 N 0.7 - - - - -
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- A " hypothetical" cow milk pathway is located at this point in accordance with S.3.1 of NUREG 0133.
3 and elevated releases occur from BSEP and their maximum x/Q values may not decrease with distance (i.e., the site boundary may not have the highest X/Q values); X/0 values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest X/0 values were considered in conjunction with the radionuclide mix and releases to determine the controlling location.
In the determination of the controlling location, annual average X/0 values are utilized. These values are presented in tables in Appendix A. X/Q values at the limiting site boundary location for releases from the Turbine Buildings, Reactor Buildings, and stack were obtained from Tables A-1, A-7, and A-13, respectively, of Appendix A. A description of the derivation of X/Q values is also presented in Appendix A.
A particular combination of release point mix and meteorology dominates in the determination of the controlling location. For BSEP the controlling release point is the stack. The dominate factor in determining a control location becomes the B values. The ENE sector at the site boundary is the control location because of its higher B values.
Values for M and N , which were used in the determination of the controlling g
location and which are to be used by BSEP in Expressions 3.3-7 and 3.3-8 to show compliance with 10CFR50 were presented in Table 3.2-4. These values originate from NUREG 0472, Revision 0, and were taken from Table B-1 of NRC 6
Regulatory Guide 1.109, Revision 1. The values have been multiplied by 10 to convert from picoeuries to microcuries.
The following relationship should hold for BSEP to show compliance with Radiological Effluent Technical Specification 3.11.2.2.
For the calendar quarter:
Dy 5 10 mrad (3.3-9)
DB s 20 mrad (3.3-10)
For the calendar year:
Dy 5 20 mrad (3.3-11)
DS $ 40 mrad (3.3-12) where:
Dy = The air dose from gamma radiation, mrad DB = The air dose'from beta radiation, mrad The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of Expressions 3.3-9 through 3.3-12 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10CFR50 must be filed with the NRC.
3.3.2 I-131, I-133, Particulates, and Tritium
- l 3.3.2.1 Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radiciodines and radioactive material in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG 0133, the dose to an organ of an individual from radiciodines and particulates, with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:
During any calendar quarter or year:
-8 +wy 3.17 x 10 I R1 (W, Q +w,qg +Wy Qg qf) s s v v .
s 7.5 mrem per quarter or 15 mrem per calendar year (3.3-13)
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- O TABLE 4.0-1 (Cont'd) 9 n
3 N Exposure Pathway Sample Sample Point Description, Approximate Sampilng and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis (a)
INCESTION
- a. Hilk 600 To be identified as available. Camma isotopic (animals on 601 pasture)-
I-131 analyses 602 (animals on pasture) 603 Camma isotopic (other times) 1-131 analysis (other times)
- b. Fish and 700 S.S mile SSW Atlantic Ocean (e) When in Season - Sealannual Camma isotopic l Inverte- at Discharge Semiannual on edible brates 701 portions
> (shrimp) 1 702 703-705 Not Specified - Atlantic Ocean (c)(e)
- c. Broadleaf 800 0.7 miles NE Intake Canal When available - Monthly Gamma isotopic Vegetation Monthly 801 0.6 alles SW Discharge Canal Monthly 1-131 802 10 miles - Control - Location not Specified (c)
(a) The LLD for each analysis is specified in Table 4.12.1-1 of the Technical Specifications for the Brunswick Steam Electric Plant.
(b) Particulate samples will be analyzed for gross beta radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change. Perform gespria scan on each sample when gross beta activity is 10 times the mean of the control station.
(c) Control Station - These stations are presumed to be outside the influence of plant effluents.
(d) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
n 4 (e) A sample of one free swimmer, one bottom feeder, and one shellfish (shrimp) will be collected if available. A control sample of each species collected will be obtained if available.
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ENCLOSURE 2 Revisions to the Process Control Program (PCP)
There were no new revisions to the Process Contr01 Program (PCP), ,
during this time period b
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f ATTACHMENT 4 i
Environmental Monitoring Program July 1, to December 31, 1986 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census j
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ENCLOSURE 1 Milk and Vegetable Sample Locations No milk sample locat, ions'were available during this time period.
Vegetable sample locations were unchanged during this time period.
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ENCLOSURE 2 Land Use Census No new locations were identified that are reportable in the Semiannual Rad ioactive F.ffluent Release Report as per Technical Specification 3.12.2.a and b.
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ATTACHMENT 5 Inoperable Effluent Instrumentation July 1, to December 31, 1906 Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation Enclosure 3: Liquid Hold-Up Tank 3/1
ENCLOSURE 1 Radioactive Liquid Effluent Monitoring Instrumentation Unit 2 service water radiation monitor was inoperable for more than a a 30 dau period during July 1, to December 31, 1986. Due to sporadic monitor performance it was difficult to determine the true cause of monitor inoperabi1ity. The problem was resolved and the monitar was returned to service.
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ENCLOSURE 2 Radioactive Gases Effluent Monitoring Instrumentation Unit 1 6 2 main condensor off-gas treatment system explosive gas monitors 1(2)-0G-AIT-4284 (SJAE.A.H2 Analyzer), 1(2)-0G-AIT-4285 (SJAE.A.H2 AnalyzerT, 1(2)-0G-AIT-4324 (SJAE.B.H2 Analyzer), and 1(2)-OG-AIT-4325 (SJAE.B.H2 Analyzer), were inoperable for greater than a 30 day period during July 1, to December 31, 1986. Due to design problems, these monitors were not returned to service within 30 days.
Units 1 and 2, Reactor and Turbine buildings roof vent monitor flow elements, 1-VA-FE-3356, 1-VA-FE-3358, 2-VA-FE-3356, and 2-VA-FE-3358, were inoperable for greater than a 30 day period during July 1, to December 31, 1986. Due to design problems, these monitors were not returned-to service within 30 days.
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- ENCLOSURE 3
'I Liquid Hold-Up Tank No liquid hold-up tank exceeded the 10 Ci limit between the dates of July 1, to December 31, 1986.
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i ATTALHMENT 6 Major Modifications to the Radioactive Waste Treatment Systems July 1, to December 31, 1986 Discussion of major modifications to Radioactive Waste Treatment Systems, if any, will be submitted with the Final Safety Analysis Report update as allowed by footnote 7 to Technical Specification 6.15.
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ATTACHMENT 7 j "-
Meteorological Data
, Brunswick Steam Electric Plant
- July 1, to December 31, 1986 .
r As per Technical Specification 6.9.1.10.a footnote 6, the annual
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- summary of meteorological data collected over the calendar year will-be
- submitted to a file and will be available for NRC review upon request.
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', 'e ATTACHMENT 8 Potential Dose Assessment i Brunswick Steam Electric Plant July 1, to December 31, 1986 Att, ached is the annual dose assessment for the year, 1906. Increases in the 1986 annual dose assessment, over past years, is due in part to the conservative estimation of building ventilation flow rates.
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- CAROLINA POWER AND LIGHT
- BRUNSWICK STEAM ELECTRIC PLANT 18 FEB 1987 8:35:44 AM MIXING RATIO = 2.69E-04, FLOW RATE = 7.85E 01 CUFT/SEC DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS SHORELINE SEDIMENT DOSE AT CANAL, MREM / PERIOD INFANT CHILD TEEN ADULT WHOLE BODY 0.00E-01 5.06E-07 2.42E-06 4.34E-07 SKIN 0.00E-01 5.95E-07 2.85E-06 5.10E-07 DOSE DUE TO EATING FISH CAUGHT IN DISCHARGE CANAL, MREM / PERIOD INFANT CHILD TEEN ADULT BONE 0.00E-01 2.84E-05 2.18E-05 2.08E-05 LIVER 0.00E-01 1.75E-05 1.84E-05 1.73E-05 T. BODY 0.00E-01 6.46E-06 6.22E-06 7.01E-06 THYROID 0.00E-01 1.00E-06 9.70E-07 1.04E-06 KIDNEY 0.00E-01 1.09E-06 1.27E-06 1.24E-06 LUNG 0.00E-01 8.02E-06 7.29E-07 7.59E-06 GI-LLI 0.00E-01 6.13E-06 1.63E-05 2.22E-05 DOSES TO MAN FROM GASEOUS EFFLUENT PATHWAYS DOSE DUE TO EATING GREEN LEAFY VEGS. FROM WORST GARDEN, MREM /PERIf INFANT CHILD TEEN ADULT BONE 0.00E-01 4.38E-04 2.47E-04 2.75E-04 LIVER 0.00E-01 2.88E-04 2.30E-04 2.79E-04 T. BODY 0.00E-01 1.85E-04 1.58E-04 2.35E-04 THYROID 0.00E-01 2.27E-02 1.51E-02 1.87E-02 KIDNEY 0.00E-01 2.27E-04 1.85E-04 2.27E-04 LUNG 0.00E-01 7.76E-05 6.59E-05 9.24E-05 GI-LLI 0.00E-01 1.97E-04 3.12E-04 5.01E-04 DOSE DUE TO EATING PRODUCE FROM WORST CASE GARDEN, MREM / PERIOD INFANT CHILD TEEN ADULT BONE 0.00E-01 3.75E-03 1.63E-03 1.01E-03 LIVER 0.00E-01 3.19E-03 1.94E-03 1.31E-03 T. BODY 0.00E-01 2.12E-03 1.44E-03 1.22E-03 THYROID 0.00E-02 2.90E-03 1.59E-03 1.16E-03 KIDNEY 0.00E-01 1.61E-03 1.01E-03 7.41E-04 LUNG 0.00E-01 1.17E-03 7.45E-04 5.68E-04 GI-LLI 0.00E-01 2.44E-03 2.84E-03 2.52E-03 F/2
- CAROLINA POWER AND LIGHT * -
BRUNSWICK STEAM ELECTRIC PLANT 18 FEB 1987 8:36:22 AM
- I-131 DOSE DUE TO DRINKING MILK, MREM / PERIOD INFANT CHILD TEEN ADULT BONE 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LIVER 0.00E-01 0.00E-01 0.00E-01 0.00E-01 T. BODY 0.00E-01 0.00E-01 0.00E-01 0.00E-01 THYROID 0.00E-01 0.00E-01 0.00E-01 0.00E-01 KIDNEY 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LUNG 0.00E-01 0.00E-01 0.00E-01 0.00E-01 GI-LLI 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- TOTAL DOSE DUE TO DRINKING MILK, MREM / PERIOD '
INFANT CHILD TEEN ADULT BONE 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LIVER 0.00E-01 0.00E-01 0.00E-01 0.00E-01 T. BODY 0.00E-01 0.00E-01 0.00E-01 0.00E-01 THYROID 0.00E-01 0.00E-01 0.00E-01 0.00E-01 KIDNEY 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LUNG 0.00E-01 0.00E-01 0.00E-01 0.00E-01 GI-LLI 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- No milk pathway exists at Brunswick Steam Electric Plant.
1-131 INHALATION DOSE AT WORST POINT ON SITE BOUNDARY, MREM / PERI @
INFANT CHILD TEEN ADULT BONE 8.03E-06 1.02E-05 7.50E-06 5.33E-06 LIVER 9.39E-06 1.02E-05 1.04E-05 7.57E-06 T. BODY 4.15E-06 5.77E-06 5.59E-06 4.33E-06 THYROID 3.14E-03 3.44E-03 3.10E-03 2.52E-03 l KIDNEY 1.10E-05 1.67E-05 1.78E-05 1.30E-05 i LUNG 0.00E-01 0.00E-01 0.00E-01 0.00E-01 GI-LLI 2.24E-07 6.01E-07 1.37E-06 1.33E-06 TOTAL INHALATION DOSE AT WORST SITE BOUNDARY, MREM / PERIOD INFANT CHILD TEEN ADULT BONE 6.73E-05 1.06E-04 6.62E-05 6.33E-05 i LIVER 3.72E-04 6.09E-04 6.80E-04 6.50E-04 T. BODY 3.17E-04 5.50E-04 6.21E-04 7.39E-04 THYROID 8.55E-03 9.54E-03 7.95E-03 C.24E-03
- KIDNEY 3.54E-04 6.05E-04 6.79E-04 6.49E-04 l
LUNG 1.97E-03 3.07E-03 3.78E-03 2.77E-03 l GI-LLI 3.15E-04 5.70E-04 7.22E-04 7.23E-04 8/3
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- CAROLINA POWER AND LIGHT
- BRUNSWICK STEAM ELECTRIC PLANT 18 FEB 1987 8:37:34 AM DOSE FROM NOBLE GAS RELEASES - SKIN MREM / PERIOD RADIAL DISTANCE, MILES
- 0. 5 1. 5 2. 5 3. 5 4. 5 S 1.31E 01 2.28E 00 1.10E 00 6.79E-01 4.72E-01 SSW 9.46E 00 1.71E 00 8.08E-01 4.91E-01 3.38E-01 SW 6.90E 00 1.24E 00 5.79E-01 3.49E-01 2.39E-01 WSW 5.06E 00 9.36E-01 4.31E-01 2.58E-01 1.75E-01 W 3.48E 00 6.37E-01 2.98E-01 1.80E-01 1.23E-01 WNW 3.67E 00 6.77E-01 3.16E-01 1.90E-01 1.30E-01 NW 3.73E 20 6.80E-01 3.17E-01 1.91E-01 1.31E-01 NNW 3.43E 00 6.27E-01 2.97E-01 1.81E-01 1.25E-01 N 3.71E 00 6.75E-01 3.16E-01 1.91E-01 1.31E-01 NNE 4.82E 00 8.66E-01 4.03E-01 2.42E-01 1.66E-01 NE 1.09E 01 1.99E 00 9.30E-01 5.61E-01 3.84E-01 ENE 8.76E 00 1.60E 00 7.61E-01 4.65E-01 3.21E-01 E 8.21E 00 1.42E 00 6.90E-01 4.27E-01 2.98E-01 ESE 6.69E 00 1.13E 00 5.53E-01 3.45E-01 2.41E-01 SE 1.18E 01 1.94E 00 9.64E-01 6.06E-01 4.27E-01 SSE 1.59E 01 2.59E 00 1.29E 00 8.14E-01 5.75E-01 DOSE FROM NOBLE GAS RELEASES - SKIN RADIAL DISTANCE, MILES
- 7. 5 15.0 25.0 35.0 45.0 S 2.25E-01 8.04E-02 3.68E-02 2.16E-02 1.44E-02 SSW 1.58E-01 5.47E-02 2.46E-02 1.43E-02 9.45E-03 SW 1.11E-01 3.68E-02 1.70E-02 9.88E-03 6.51E-03 WSW 8.00E-02 2.71E-02 1.20E-02 6.93E-03 4.56E-03 W 5.71E-02 1.97E-02 8.85E-03 5.15E-03 3.40E-03 WNW 6.01E-02 2.06E-02 9.20E-03 5.51E-03 3.50E-03 NW 6.04E-02 2.08E-02 9.34E-03 5.43E-03 3.58E-03 NNW 5.86E-02 2.06E-02 9.30E-03 5.42E-03 3.59E-03 N 6.05E-02 2.09E-02 9.40E-03 5.47E-03 3.62E-03 NNE 7.64E-02 2.63E-02 1.18E-02 6.86E-03 4.53E-03 NE 1.78E-01 6.12E-02 2.74E-02 1.60E-02 1.05E-02 ENE 1.51E-01 5.31E-02 2.41E-02 1.40E-02 9.32E-03 E 1.43E-01 5.12E-02 2.35E-02 1.39E-02 9.22E-03 ESE 1.17E-01 4.23E-02 1.96E-02 1.16E-02 7.73E-03 SE 2.09E-01 7.69E-02 3.59E-02 2.13E-02 1.43E-02 SSE 2.82E-01 1.04E-01 4.86E-02 2.89E-02 1.94E-02 8/h
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- CAROLINA POWER AND LIGHT
- BRUNSWICK STEAM ELECTRIC PLANT 18 FEB 1987 8:37:51 AM DOSE FROM NOBLE GAS RELEASES - T. BODY MREM / PERIOD RADIAL DISTANCE, MILES
- 0. 5 1. 5 2. 5 3. 5 4. 5 S 4.85E 00 8.44E-01 4.08E-01 2.52E-01 1.75E-01 SSW 3.51E 00 6.36E-01 3.00E-01 1.82E-01 1.25E-01 SW 2.56E 00 4.59E-01 2.14E-01 1.29E-01 8.85E-02 WSW 1.88E 00 3.47E-01 1.60E-01 9.53E-02 6.47E-02 W 1.29E 00 2.36E-01 1.10E-01 6.64E-02 4.55E-02 WNW 1.36E 00 2.51E-01 1.17E-01 7.05E-02 4.82E-02 NW 1.39E 00 2.52E-01 1.17E-01 7.07E-02 4.83E-02 NNW 1.27E 00 2.33E-01 1.10E-01 6.71E-02 4.62E-02 N 1.38E 00 2.50E-01 1.17E-01 7.05E-02 4.83E-02 NNE 1.79E 00 3.21E-01 1.49E-01 8.96E-02 6.12E-02 NE 4.06E 00 7.40E-01 3.44E-01 2.08E-01 1.42E-01 ENE 3.25E 00 5.93E-01 2.82E-01 1.72E-01 1.19E-01 E 3.05E 00 5.27E-01 2.56E-01 1.58E-01 1.10E-01 ESE 2.48E 00 4.19E-01 2.05E-01 1.28E-01 8.95E-02 SE 4.39E 00 7.19E-01 3.58E-01 2.25E-01 1.58E-01 SSE 5.90E 00 9.61E-01 4.80E-01 3.02E-01 2.13E-01 DOSE FROM NOBLE GAS RELEASES - T. BODY RADIAL DISTANCE, MILES
- 7. 5 15.0 25.0 35.0 45.0 S 8.35E-02 2.98E-02 1.36E-02 8.00E-03 5.31E-03 SSW 5.83E-02 2.02E-02 9.09E-03 5.28E-03 3.48E-03 SW 4.09E-02 1.36E-02 6.29E-03 3.64E-03 2.40E-03 WSW 2.95E-02 9.98E-03 4.42E-03 2.55E-03 1.67E-03 W 2.10E-02 7.25E-03 3.25E-03 1.89E-03 1.24E-03 WNW 2.22E-02 7.61E-03 3.39E-03 2.03E-03 1.28E-03 NW 2.23E-02 7.68E-03 3.44E-03 2.00E-03 1.32E-03 NNW 2.17E-02 7.58E-03 3.42E-03 1.99E-03 1.32E-03 N 2.24E-02 7.71E-03 3.46E-03 2.01E-03 1.33E-03 NNE 2.82E-02 9.67E-03 4.33E-03 2.51E-03 1.66E-03 NE 6.56E-02 2.26E-02 1.01E-02 5.87E-03 ,'3.88E LO3 ENE 5.59E-02 1.96E-02 8.87E-03 5.15E-03 , 3 4'3E-03 7
E 5.28E-02 1.89E-02 8.70E-03 5.12E-03 3.40E-03 ESE 4.32E-02 1.57E-02 7.25E-03 4.29E-03 2.86E-03 SE 7.75E-02 2.85E-02 1.33E-02 7.90E-03 5.29E-03 SSE 1.05E-01 3.86E-02 1.80E-02 1.07E-02 7.18E-03 i
8/5 4
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- CAROLINA POWER AND LIGHT
- BRUNSWICK STEAM ELECTRIC PLANT 18 FEB 1987 8:38:02 AM POPULATION INTEGRATED WHOLE BODY DOSE, MAN-REM / PERIOD RADIAL DISTANCE, MILES
- 0. 5 1. 5 2. 5 3. 5 4. 5 S 2.42E-02 3.38E-02 2.84E-01 0.00E-01 0.00E-01 SSW 0.00E-01 1.02E-01 6.17E-01 0.00E-01 1.26E-02 SW 8.20E-02 2.94E-02 0.00E-01 1.03E-03 0.00E-01 WSW 0.00E-01 2.40E-02 1.28E-03 3.05E-03 3.24E-04 W 1.03E-02 7.80E-03 1.76E-03~ 0.00E-01 0.00E-01 WNW 2.18E-02 2.01E-03 0.00E-01 0.00E-01 0.00E-01 NW 1.11E-02 0.00E-01 0.00E-01 0.00E-01 0.00E-01 NNW 1.02E-02 0.00E-01 0.00E-01 0.00E-01 0.00E-01 N 2.75E-02 0.00E-01 0.00E-01 0.00E-01 0.00E-01 NNE 0.00E-01 5.14E-03 0.00E-01 0.00E-01 0.00E-01 NE 0.00E-01 1.48E-02 0.00E-01 0.00E-01 0.00E-01 ENE 0.00E-01 7.11E-03 0.00E-01 0.00E-01 0.00E-01 E 0.00E-01 8.43E-03 0.00E-01 0.00E-01 0.00E-01 ESE 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SE 1.58E-01 8.63E-03 0.00E-01 0.00E-01 0.00E-01 SSE 0.00E-01 3.85E-03 0.00E-01 0.00E-01 0.00E-01 POPULATION INTEGRATED WHOLE BODY DOSE, MAN-REM / PERIOD RADIAL DISTANCE, MILES
- 7. 5 15.0 25.0 35.0 45.0 S 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SSW 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SW 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 WSW 5.11E-03 0.00E-01 0.00E-01 2.73E-03 3.80E-03 l W 1.07E-03 9.16E-03 1.29E-02 9.43E-03 8.47E-03 l WNW 2.76E-03 1.03E-02 5.94E-03 7.30E-03 1.81E-02
! NW 3.42E-03 1.52E-02 8.28E-03 7.19E-03 7.46E-03 NNW 3.31E-03 8.89E-03 1.22E-02 5.28E-03 4.51E-03 N 2.03E-03 7.47E-02 3.52E-02 7.40E-03 8.66E-03 NNE 7.75E-03 5.02E-01 9.94E-02 7.29E-03 3.28E-03 NE 1.42E-01 0.00E-01 0.00E-01 7.16E-04 9.52E-03 ENE 4.38E-02 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l E 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ESE 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
( 0.00E-01 0.00E-01 0.00E-01 i SE 0.00E-01 0.00E-01 l SSE 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l
l TOTAL POPULATION INTEGRATED WHOLE BODY DOSE = 2.63E 00 MAN-REM / PERIOD l
l 8/6
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- CAROLINA POWER AND LIGHT BRUNSWICK STEAM ELECTRIC PLANT-18 FEB 1987 8:39:02 AM POPULATION INTEGRATED INHALATION DOSE MAN-REM / PERIOD OR THYROID MAN-REM / PERIOD INFANT CHILD TEEN ADULT WHOLE BODY 6.09E-04 1.19E-02 9.24E-03 6.19E-02 THYROID .
, 3.03E-02 3.80E-01 2.18E-01 8.26E-01 i
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CD&L Carolina Power & Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 February 20, 1987 FILE: B09-13510C SERIAL: BSEP/87-0181 NRC Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Gentlemen:
Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick Steam Electric Plant covering the period from July 1, 1986, through December 31, 1986.
This report is submitted in accordance with Technical Specification 6.9.1.8 for Brunswick Steam Electric Plant.
Veiy truly yours,
. ld. $au ACRO C. R. Dietz, General Manager Brunswick Steam Electric Plant MJP/mcg Enclosure cc: Dr. J. N. Grace r
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