BSEP-86-1218, Semiannual Radioactive Effluent Release Rept,Jan-June 1986
| ML20197B142 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1986 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| BSEP-86-1218, NUDOCS 8610280088 | |
| Download: ML20197B142 (48) | |
Text
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7-t' Brunswick Steam Electric Plant Semiannual Radioactive Effluent Release Reoort January 1 . to June 30 , 1936 ATTACHMENTS : PAGES :
- 1. Supplemental Information 1/1 to 1/4
- 2. Effluent and Waste Disposal Data 2/1 to 2/15
- 4. Environmental Monitoring Proaram 4/1 to 4/3
- 5. Inoperable Effluent Instrumentation 5/1 to 5/4
- 6. Ma.ior Modifications to Radioactive Waste Treatment Systems 6/1
- 7. Meteorolooical Data 7/1
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ATTACHMENT 1 Supplemental Information January 1 , to June 30 . 1986 1/1
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EFFLUENT WASTE DISPOSAL' SEMIANNUAL REPORT Supolemental Information Facilitv: Brunswick Steam Electric Plant Licensee: Carolina Power & Licht Company
- 1. Reculatory Limits A. Fission and activation cases (Technical Specification 3.11.2.2)
- (1) Calendar Quarter (a) 10 mrad camma (b) 20 mrad beta (2) Calender Year (a) 20 mrad gamma (b) 40 mrad beta B. Iodine-131. iodine-133, tritium, and particulates with half-lives greater than eicht davs (Technical Specification 3.11.2.3)
- (1) Calendar Quarter
{a) 15 mrem to any organ (2) Calendar Year (a) 30 mrem to any organ C. Liquid effluents (Technical Specification 3.11.1.2)
- * (1) Calendar Quarter (a) 3 mrem to total body (b) 10. mrem to any orcan (2) Calendar Year (a) 6 mrem to total body (b) 20 mrem to any organ NOTE: Dose calculations are determined in accordance with the Of f-site Dose Calculation Manual ' (ODCM) .
- Used for percent of technical specification limit determinations in Table 1A.
- Used for percent of technical specification limit determinations in Table 2A.
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- 2. Maximum cermissible concentrations and dose rates which determine maximum instantaneous release rates.
A. Fission and activation cases (Technical Specification 3.11.2.1.a)
(1) 500 mrem / vear to total body (2) 3000 mrem / vear to the skin B. Iodine-131. iodine-133. tritium, and particulates with half-lives creater than eight davs (Technical Specification 3.11.2.1.b)
(1) 1500 mrem / vear to any organ C.-Liouid 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.
- (2) Dissolved and entrained cases: MFC = 2 x 10E-04 uCi/ml
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation cases Analysis for specific radionuclides. in representative grab samples by camma spectroscopy.
B. Iodines Analysis for specific radionuclides collected on charcoal j 1
cartridaes by camma spectroscopy.
C. Particulates Analysis for specific radionuclides collected on filter papers by camma spectrosconv.
D. Liouid Effluents Analysis for specific radionuclides of individual releases bv camma spectroscopy.
- Used as applicable limits for Table 2A 1/3
-w ww-
O Nuclear countina statistics are reported utili:ina 1-sioma error. Total error where reported represents a best effort to aporoximate the total of all individual and samplino errors.
- 4. Batch Releases A. Liquid (1) Number of batch releases: 1.34E+02 (2) Total time period for batch releases: 1.37E+04 Minutes (3) Maximum time period for a batch release: 2.09E+02 Minutes (4) Averaae time period for a batch release: 1.02E+02 Minutes (5) Minimum time period for a batch release: 1.00E 00 Minutes (6) Average stream flow during periods of release of effluent into a flowina stream: 4.38E+05 G.P.M.
- 5. 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) Averaae time ceriod for a batch release: 0.00E 00 Minutes (5) Minimum time period for a batch release: 0.00E 00 Minutes
- 5. Abnormal releases Y
A. Liquid (1) Number of releases: 0.00E 00 (2) Total activity released: 0.00E 00 Ci B. Gaseous 1
(1) Number of releases: 1.00E 00 (2) Total activity released: 1.20E-05 Ci (3) On March 19. 1986 a clothes dryer thermostat failed causina 14 coverals to catch fire. The fire lasted approximately 20 minutes'. No contamination was monitored in the air samples i taken durina or after the incident. Assumptions were made
! that the coverals were contaminated , and that 10% of the l contaminat:an became airborne as Co-60.
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s ATTACHMENT 2 Effluent and Waste Disposal Data Brunswick Steam Electric Plant January 1. to June 30, 1986 Enclosure 1 Table 1A: Gaseous Effluents - Summation of All Releases Table 18: Gaseous Effluents - Elevated Releases Table IC: Gaseous Effluents - Ground Level Releases Table 2A: Liauid Effluents - Summation of All Releases Table 2B: Liquid Effluents Lower Limits of Detection Table 3: Solid Waste and Irradiated Fuel Shipments Enclosure 2: Combustion of Waste Oil i
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Table 1A Effluent and Waste Disposal Semiannual Report Year 1986 Gaseous Effluents - Summation of All Releases Est.
Total Unit Otr 1 Otr 2 Error.%
A. Fission and activation gases
- 1. Total release Ci 6.70E 03 1.39E 04 4.00E 01
- 2. Averaae release rate uCi/sec 8.62E 02 1.77E 03 for period
- 3. Percent of technical specification limit % 1.51E-01 2.18E-01 B. Iodines
- 1. Total iodine-131 Ci 8.03E-05 3.97E-04 4.00E 01
- 2. Averace release rate uCi/sec 1.03E-05 5.05E-05 for period C. Particulates
- 1. Total release Ci 2.92E-03 4.51E-03
- 2. Average release rate uCi/sec 3.75E-04 5.73E-04 for period
- 3. Gross alpha Ci 5.56E-05 6.52E-05 D. Tritium
- 1. Total release Ci 1.44E 00 1.51E 00 4.00E 01
- 2. Averaae release rate uCi/sec 1.85E-01 1.92E-01 for period E. Iodine-131. Iodine-133. Tritium and Particulates
- 1. Total release Ci 1.44E 00 1.52E 00
- 2. Averaae release rate uCi/sec 1.85E-01 1.93E-01 for period
- 3. Percent of technical % 4.87E-03 1.70E-02 specification limit 2/2
4 Table 1B Effluent and Waste Disposal Semiannual Report Year 1986 Gaseous Effluents - Elevated Release Continuous Release Nuclides Released Unit Otr 1 Otr 2
- 1. Fission Gases argon-41 Ci 2.43E-02 1.24E 01 krypton-85m Ci 1.31E-01 1.17E 00 krypton-87 Ci 6.29E-01 1.46E 00 krypton-88 Ci 4.18E-01 4.27E-01 xenon-135m Ci 2.02E 00 7.38E 00 xenon-135 Ci 6.15E-01 2.09E 00 xenon-137 Ci 1.79E 01 7.08E 01 xenon-138 Ci 8.37E 00 3.47E 01 total for period Ci 3.01E 01 1.30E 02
- 2. Iodines iodine-131 Ci 7.04E-05 3.20E-04 iodine-132 Ci < LLD 9.79E-04 iodine-133 Ci 1.12E-04 2.27E-03 iodine-135 Ci < LLD 2.59E-03 total for period Ci 1.82E-04 6.16E-03 3.Particulates 5.09E-05 chromium-51 Ci 1.76E-04 manganese-54 Ci 3.58E-05 3.97E-05 cobalt-58 Ci 1.43E-05 2.14E-07 cobalt-60 Ci 2.68E-04 2.22E-04 strontium-89 Ci 1.21E-05 9.29E-05 strontium-90 Ci' 2.19E-07 7.64E-07 cesium-134 Ci 8.69E-06 2.67E-05 cesium-137 Ci 5.53E-05 1.56E-04 barium-140 Ci < LLD 7.71E-05 lanthanum-140 Ci < LLD 3.80E-05
=
total for period Ci 4.45E-04 8.29E-04 i~ 4. Tritium hvdrogen-3 Ci 9.10E-02 2.03E-01 2/3
Table 1C Effluent and Waste Disposal Semiannual Report Year 1986 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Otr 1 Otr 2
- 1. Fission Gases krypton-85m Ci 4.45E-01 2.28E-01 krypton-88 Ci 2.11E 00 1.08E 00 xenon-133m Ci 2.42E 02 6.22E 02 xenon-133 Ci 4.89E 03 1.09E 04 xenon-135m Ci 1.97E 00 1.01E 00 xenon-135 Ci 1.54E 03 2.29E 03 total for period Ci 6.67E 03 1.38E 04
- 2. Iodines iodine-131 Ci 9.93E-J6 7.73E-05 iodine-133 Ci 2. 40E- 05 4.60E-04 total for period Ci 3.48E 05 5.37E-04 3.Particulates chromium-51 Ci 7. 61E -04 1.02E-03 y manaanese-54 Ci 2.84E-04 6.48E-04 cobalt-57 Ci 2.10E-07 < LLD 1 cobalt-58 Ci 3.45E-05 4.33E-05 e iron-59 Ci 1.36E-05 5.20E-05 ,
cobalt-60 Ci 1.17E-03 1.58E-03 strontium-89 Ci 3.29E-06 1.87E-05 strontiun-90 Ci 4.36E-07 7.41E-07 niobium-95 Ci < LLD 1.90E-06 cesium-134 Ci 2.63E-05 6.04E-05 cesium-137 Ci 1.65E-04 2.54E-04 cerium-144 Ci 1.68E-05 < LLD total for period Ci 2.47E-03 3.6bE-03
- 4. Tritium hydrogen-3 Ci 1.35E 00 1.31E 00 2/4 i
TABLE 2A Ef fluent and Waste Disposal Semiannual Report Year 1986 Liquid Ef fluents - Summation of All Releases Unit Otr 1 Otr 2 Est Tot.
Error. %
A. Fission and activation products
- 1. Total release (excluding Ci 3.39E-02 4.89E-02 3.50E 01 tritium. cases. alpha) 2.Av. diluted concentration uCi/ml 4.81E-09 3.13E-09
- 3. Percent limit % 1.28E-01 8.60E-02 B. Tritium
- 1. Total release C1 1.36E 00 1.27E 00 3.50E 01 2.Av. diluted concentration uCi/ml 1.93E-07 8.14E-08
- 3. Percent limit % 6.43E-03 2.71E-03 C. Dissolved and entrained gases
- 1. Total release Ci 7.42E-04 1.45E-03 3.50E 01 2.Av. diluted concentration uCi/ml 1.05E-10 9.29E-11
- 3. Percent limit % 5.25E-05 4.65E-05 D. Gross alpha radioactivity
- 1. Total release Ci 7.83E-04 3.79E-04 1.50E 01 E. Volume of waste liters 3.99E 06 4.28E 06 1.25E 01 F. Total volume of dilution water (used durino released for av.
diluted concentration) liters 7.05E 09 1.56E 10 1.30E 01 G. Volume of cooling water discharoed from plant liters 1.28E 11 2.80E 11 2/5
TABLE 2B Effluent and Waste Disposal Semiannual Report Year 1986 ,
Liquid Effluents - Batch Mode Nuclides Released Unit Otr 1 Otr 2
- 1. Fission and activation products sodium-24 Ci 1.15E-03 < LLD chromium-51 Ci 3.78E-03 8.47E-03 manganese-54 Ci 4.88E-03 6.75E-03 ircn-55 Ci 1.14E-02 1.07E-02 cobalt-58 Ci 6.27E-04 4.15E-04 iron-59 Ci 1.42E-04 3.49E-05 cobalt-60 Ci 9.90E-03 1.82E-02 zinc-65 Ci 1.63E-05 7.60E-06 arsenic-76 Ci 2.28E-05 5.32E-05 strontium-90 Ci 1.38E-05 4.75E-06 strontium-92 Ci 5.71E-06 1.47E-05 niobium-95m Ci < LLD 4.54E-06 niobium-95 Ci 4.07E-06 < LLD niobium-97 Ci 1.94E-04 1.28E-04 technetium-99m Ci 5.99E-05 < LLD ruthenium-103 C1 c.65E-05 < LLD iodine-131 Ci < LLD 2.37E-05 iodine-133 Ci 4.89E-05 2.99E-05 cesium-134 Ci 2.74E-04 6.40E-04 cesium-137 Ci 1.38E-03 3.42E-03 cerium-141 Ci 3.11E-06 < LLD cerium-144 Ci 1.42E-05 < LLD total for period Ci 3.39E-02 4.89E-02 2/6 1
TABLE 2B (cont)
Effluent and Waste Disposal Semiannual Report Year 1986 Liquid Effluents - Batch Mode
- 2. Dissolved and Entrained Unit Otr 1 Otr 2 Gases xenon-133 Ci 9.57E-05 2.20E-04 xenon-135 Ci 6.46E-04 1.23E-03 total for period Ci 7.42E-04 1.45E-03 2/7 i
Lower Limits of Detection uCi/ml
- 1. Liquid Releases 2. Gaseous Releases Na-24 3.12E-08 No < LLD Gases Nb-95m 5.11E-08 Nb-95 1.85E-08 Tc-99m 1.39E-08 Ru-103 2.27E-08 3. Iodines and Particulates I-131 1.57E-08 Ce-141 2.33E-08 Co-57 1.97E-14 Ce-144 7.86E-08 No-95 3.18E-14
!-132 3.43E-13 1-135 5.80E-13 Ea-140 1.46E-13 La-140 9.83E-14 Ce-144 1.50E-13 NOTES 1: The above values represent typical "a priori" LLDs for isotopes snare values of "< LLD" are indicated in Tables 1A. 1B, 1C.2A and 2B.
2: Where activity f or any nuclide is reported as "Less than LLD" that nuclide is concidered not present and the LLD activity listed is not concidered in summary data .
2/8
4 TABLE 3A Effluent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irrediated Fuel Shipments Waste Class A January through June
- 1. Total volume shipped, cubic meters 5.57E 02 Total Ci quantity (estimated) 6.70E 02
- 2. Type of Waste Units Six-Month Est. Total Period Error. %
- a. Spent resins. filter sludaes cubic meters 1.62E 02 Curies 6.49E 02 1.00E 01
- b. Dry active waste. compacted. cubic meters 3.95E 02 noncompacted Curies 2.10E 01 1.00E 01
- c. Irradiated components: cubic meters N/A Curies N/A N/A d.0thers(describe): cubic meters N/A Curies N/A N/A
- 3. Estimate of maior radionuclide composition
- a. Cr-51 1.09E 00 %
Mn-54 1.56E 01 %
Fe-55 2.95E 01 %
Co-58 1.20E 00 %
Co-60 4.38E 01 %
Ni-63 2.82E 00 %
Cs-137 4.01E 00 %
- b. Mn-54 7.55E 00 %
Fe-55 5.50E 01 %
Co-60 2.90E 01 %
Sr-89 2.09E 00 %
Cs-137 4.68E 00 %
- c. N/A N/A
- d. N/A N/A 2/9
i TABLE 3A (cont)
Effluent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments
- 4. Cross reference table, waste stream form. container type.
Stream Form Container Type No. Shipments
- a. Resin Dewatered & Type A/ Type B 17/12 Solidified *
- b. Dry active Compacted /non-waste compacted LSA/STP 15 waste
- c. Irradiated components N/A
- d. Other N/A
- Solidification acent or absorbent: Cement
- 5. Shipment Disposition
- a. Solid Waste Number of Shipments Mode of Transportation Destination 44 Sole Use Chem-Nuclear Barnwell SC
- b. Irradiated Fuel Number of Shipments Mode of Transportation Destination N/A N/A N/A 2/10 l
TABLE 3B Effluent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments i
Waste Class B January through June l'. Total volume shipped, cubic meters 1.00E 01 Total Ci quantity (estimated) 2.16E 02
- 2. Type of Waste Units Six-Month Est. Total Period Error. %
- a. Spent resins. filter sludoes cubic meters 1.00E 01
< Curies 2.16E 02 1.00E 01
- 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.0thers(describe): cubic meters N/A i
Curies N/A N/A
- 3. Estimate of major radionuclide composition r
- a. Mn-54 1.00E 01 % !
Fe-55 5.12E 01 %
Co-60 3.01E 01 %
Ni-63 5.33E 00 %
Cs-137 2.41E 00 %-
- 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 & Type A/ Type B 0/2 Solidified *
- b. Dry active Compacted /non-waste compacted N/A w'aste 2
- c. Irradiated components N/A
- d. Other N/A
- Solidification acent or absorbent: Cement t
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TABLE 3B (cont)
Ef fluent 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 i
2 Sole Use Chem-Nuclear Barnwell. SC *
- b. Irradiated Fuel Number of Shipments Mode of Transporation Destination N/A- N/A N/A 2/12
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TABLE 3C Effulent and Waste Disposal Semiannual Report Year 1986 Solid Waste and Irradiated Fuel Shipments Waste Class C Januarv through June
- 1. Total volume shipped, cubic meters 0.00E 00 Total Ci quanity (estimated) 0.00E 00
- 2. Tvoe 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.0thers(describe): cubic meters N/A Curies N/A N/A
- 3. Estimate of major radionuclides 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 T.se No. Shipments
- a. Resin Dewatered & N/A N/A Solidified *
- b. Dry active Compacted /non-waste compacted N/A N/A waste
- c. Irradiated components N/A N/A
- d. Others N/A N/A
- Solidification acent or absorbent: N/A 2/13
TABLE 3C (cont)
Ef fluent 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 Transparation Destination N/A N/A N/A
+
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E'4CLD5URE 2 Combustion of Waste Oil Durina the first auarter. 1380.28 aallons containino 1.38E 00 uCi were disposed of bv incineration.
During the second ouarter. 390.22 gallons containino 5.84E-01 uCi were disposed of bv incineration.
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ATTACHMENT 3 Off-site Dose Calculation Manual (ODCM) and Process Control Procram (PCP) Revisions January 1, to June 30, 1986 Brunswick Steam Electric Plant Enclosure 1:' Revision 5 of the Of f-site Dose Calculation Manual (ODCM)
Enclosure 2: Revision 2 of the Process Control Program (PCP) l 3/1
f ENCLOSURE 1 Revision 5 of the Off-site Dose Calculation Manual Page 3 - 15 equation (3.2-2) was revised to 3000 mrem /yr to correct a typographical error.
Page 4 - 2 Table 4.0-1 TLD-32 the direction was corrected from E to ENE.
Page 4 - 3 Table 4.0-1 TLD-33 the distance was corrected from 4.3 miles to h.0 miles.
Page 4 - 4 Table 4.0-1 item b. the distance was corrected from 0.5 miles to 5 0 miles.
The previous items were corrected during a review of the ODCM.
3/2
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REQUEST FOR OFF SITE DOSE CALCULATION MANUAL CHANGE Originator: 7epon e. A. k dtm Date: 2-25-86 Pages and sections revised: bc _q .15 .ow.d.'en [3.2-2) : pm (.J-2 TLD,-
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REVIEWS:
S. St A4/h {ecommend3NoeFe:ommended Daee: 3/h/76 1st Party Nuclear Safety Reviewer i
{.Y t' s geommendehNothenemended Date: 8dF88 2nd Party Nuclearl$afety Reviewer
</_ , . ecommen ~/Not Recommended Date: //-/ $
, " T4C46jief91sor oman J 'Not Recommended Date: 3-h/Y[
C Prbfect Specialist j
APPROVALS: '
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Manager - E&RC commend Not Recommended Date: 94 C h e ___ A-- commen Not Recommended Date: 4.f n l N PNSC Chafrman *
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LIST OF EFFECTIVE PAGES
. ODCM Page(s) Revision i 5 ii-viii 1 1-1 0 2 2-2 0 2 2-6 1 2-7 0 2 2-10 1 2 2-12 0 2 2-16 1 3 3-12 4 3-13 1 3-14 4 3-15 5 3 3-19 4 3 3-23 1 3-24 4 3-25 1 3 3-28 4 3-29 1 3 3-31 4 3 3-36 1 3 3-40 4 3 3-45 1 3 3-48 4 3 3-68 1 4-1 1 4 4-4 5 4-5 4 4 4-7 3 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 l A A-15 0 A A-19 4 A A-21 0 I A-22 4 A A-28 0 B B-33 0 C C-18 0 D D-2 1 E-1 4 i E-2 3 .
E-3 4 F F-3 0 n G-1 . 1 ODCM (BSEP) .
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3.2 COMPLIANCE WITH 10CFR20 (GASEOUS) 3.2.1 Noble Cases The gaseous effluent monitors' setpoints are utilized to show compliance with 10CFR20 for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be exceeded and yet 10CFR20 limits may not be exceeded. Therefore, the following methodology has- been provided in the event that if the alarm / trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded 10CFR20.
The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem / year to the total body and 3000 mrem / year to the skin.
Based upon NUREC 0133, the following are used to show compliance with 10CFR20.
I t
Vgth + K g(X/Q)y h g 5 500 mrem /yr (3.2-1) s y l P. .
9 l
]
I g4 Lt (X/Q) + 1.1B f Qi + (Lg + 1.1Mg)(X/Q)y Q g vs 3000 mrem /yr (3.2-2) l t
s s v
, w- -
1 l where:
i Kg = The total body dose factor due to gamma emissions for noble gas D radionuclide i, mrem / year per DCi/m 8 i
Lg = The skin dose factor due to beta emissions for noble gas
! radionuclide i, mrem / year per pC1/m 8 Mg = The air dose factor due to gamma emissions for noble gas radionuclide 1 mrad / year per pCi/m 8 g Vg = The constant for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume mrem / year per DCi/sec e
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. #' jf 9 TABLE 4.0-1
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n to cn rn RADIOLOGICAL ENVIRONNENTAL NONITORING PROCRAN .
Exposure Pathway Sample Sample Point Description, Approximate Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis (a)
DIRECT RADIATION 1 1.1 miles E - Refer to Figure 4.0-ta 0 0 Camma Dose and Figure 4.0-1b 2 1.0 miles ESE O O Camma Dose 3 0.9 elles SE 'O O Camma Dose 9 4 1.1 miles SSE O O Camma Dose 5 1.1 miles S 0 0 Canssa Dose 1 6 1.0 miles SSW Q Q Camma Dose 3 7 1.0 miles SW 0 0 Camma Dose
. - 8 1.2 miles W 0 0 Camma Dose 9 1.0 miles WNW 0 0 Comma Dose ..
10 0.9 miles NW 0 0 Camma Dose #
' 11 0.9 miles NNW 0 0 Camma Dose 12 1.0 miles N O O Camma Dose 13 1.2 miles PME O O Camme Dose '"
14 0.5 miles NE O O Camma Dose 15 0.9 miles ENE O O Camma Dose 4 16 1.0 miles WSW 0 0 Camma Dose 17 1.5 miles ESE O O Camma Dose '
18 1.7 miles SE O Q Camma Dose 77 5.3 miles SSE O O Cansna Dose 'g- ~.
75 4.5 miles S 0 0 Camma Dose 76 4.8 miles SSW }.
0 0 Comma Dose
- 22 5.3 miles SW 0 0 Camma Dose 23 4.6 miles WSW 0 0 Camma Dose #
24 3.0 miles W 0 0 Camma Dose 25 8.7 miles WNW 0 0 Camma Dose 26 5.9 miles NW Q Q Camma Dose 27 5.0 miles NNW 0 0 Camma Dose n 79 9.5 alles N O Q Camma Dose T 78 10.0 miles NNE O O Camma Dose l@
30 2.0 miles NE O O Camma Dose ,
31 2.6 miles ENE O O Camma Dose '
32 5.7 miles ENE O O Camma Dose l ,.
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Exposure Pathway Sample Sample Point Description, Approximate Sampling and Analysis and/or Sample ID No. Distance, and Direction Collection Frequency Frequency Analysis (a)
DIRECT RADIATION 33 4.0 miles E O O Camma Dose j (Cont'd) 34 5.5 miles ENE O O Camma Dose !
81 10.0 miles WNW (C) 0 0 Camma Dose 36 9.3 miles NE O O Camma Dose
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37 5.5 miles NW 0 0 Camma Dose :
38 11.0 miles W Q 0 Camma Dose l 39 S.3 miles SW 0 0 Camma Dose 40 6.9 miles WSW Q 0 Camma Dose !
AIRBORNE
- - Radiofodine and 200 1.0 miles SW Vistors Center Continuous sampler W Radiofodine Particul ate 201 0.6 miles NE PMAC operation with sample Canister 202 1.0 miles S Substation - Const. Rd. collected weekly or as 1-131 analysis 203 2.3 miles SSW Southport Substation required by dust load- Particulate sampler
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- 204 23 miles NNE Sutton Plant - Contro1(c) ing, whichever_is more -
Gross beta radio-i frequent.
W activity analysis following filter change (b).
0 Camma isotopic analysis of composite by location.
WATERBORNE
- a. Surface 400 0.7 miles NE Intake Canal - Control (c) Composite Sample (d) Monthly Camma Isotopic-Collection - M 0 Honthly Tritium e.
401 4.9 miles SSW Discharge Canal at Still Pond
- b. Sediment 500 4.9 miles SSW Discharge - Beach Semiannual Semiannual Cama Isotopic
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TABLE 4.0-1 (Cont'd)
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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. Milk 600 To be identified as available. Camma isotopic (animals on 601 pasture)
- 1-131 analyses 602 (animals on pasture) 603 Camma isotopic (other times)
I-131 analysis (other times)
- b. Fish and 700 S.O mile SSE Atlantic Ocean (e) When in Season - Semiannual Camma isotopic l Inverte- at Discharge Semiannual on edible as brates 701 portions 8
(shrimp) 702 703-70S Not Specified - Atlantic Ocean (c)(e)
- c. Broadleaf 800 0.7 miles flE Intake Canal When available - Monthly Gamma isotopic e Vegotation Monthly 801 0.6 miles 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 wl11 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
. gamma 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.
p (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 />.
La (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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Brunswick Steam Electric Plant Revision 2 of the Process Control Program (PCP)
On June 24, 1986 revision 2 to the PCP was approved. This revision was made at the request of the NRC staff to make the Brunswick plant's PCP as similar as possible to the H. B.
Robinson plant's PCP which was approved by the NRC on May 16, 1986. The substance of the change was to clarify that the PCP applies not only to the solidification of radioactive waste liquids but also to the dewatering of these liquida. These changes were administrative clarifications which in no way reduced the overall conformance of the solidification waste product to existing criteria for solid wastes.
The completed AI-61 Request for Procesa Control Program Change form has been-included with this enclosure to provide documentation that these changes have been reviewed and found acceptable by the Plant Nuclear Safety Committee (PNSC). A complete copy of revision 2 to the PCP has also been included with this enclosure.
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REQUEST FOR PROCESS CONTROL PROGRAM CHANGE Originator: Pau/ 8. G eo.d Date: G//z/86 Pages and sections revised: p,.gy f-g
%e cins i.o- 4.o Reason for change: Te e. la s t fG tha + ,' A o. Prun ss G isel Psn. r a m a n a l, 'n es both u //d i/~oc d & x a dd d,o w'a' ie r 1 o l' s edwas te /19nids.
Safety Analysis Complete 9 (RCI-03.1 Attachment 1): [aud [. Date: 4 //z/f6 REVIEWS:
MM (Recommende3 Met 3 : c. .d:d Date: 6Mz/gf 1st Party Nuclear Safety Reviewer
'r_ i_. (t w QecommendebNotFccc-:.ded Date: (, /_?.4 2nd Ppyty Nuclear Safety Reviewer h omen Nn ";;; _ uded- Date: M/8(,
Q RC Supervisor Ope'r ations Recomend c: "cce r:nded Date: ['/[db upervisor - Radwast k j
/ _ 4na ended ' "------ ' '
Date: -[d d RC Principal 4;ie'cialist APPROVALS:
Recommended at Recommended Date: d!J3; Manager - E6RC (
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. s e,, Ms LQ Recommended /Not Recomended Date: le-[/J
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M.: nager l- Operatidps -
o ot Recommended Date: 6 [2.M f f'(
PNSC Chair 5an A /
- C D;p ~Appp d/Not Approved Date
- C[2 IT
- General Manater BSEP/Vol. T/AI-61 4 Rev. 3 l
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t CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT :,.
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PROCESS CONTROL PROGRAM (PCP) i i.
DOCKET NOS. 50-324 and 50-325 i
REVISION 2 1
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0 LIST OF EFFECTIVE PAGES PCP Page (s) Revision 1-3 2 PCP (BSEP) i Rev. 2 L
PROCESS CONTROL PROGRAM 1.0 Scope ,
This program establishes the management system and controls that the Brunswick Steam Electric Plant (BSEP) uses to ensure safe and effective solidification and dewatering of various low-level radioactive waste j liquids and slurries for off-site disposal.
2.0 Objective It is the objective of this program that the solidification and/or l
dewatering of various low-level radioactive waste liquids and slurries .
(including oily waste) for of f-site disposal will be performed by l qualified vendors. The quality of the solidified and/or dewatered ;
product shall meet or exceed regulatory requirements and the disposal site criteria prior to release from the Brunswick site for shallow land ;
disposal. -
3.0 Management Program 3.1 Responsibilities 3.1.1 The General Manager is responsible for ensuring that waste is shipped in accordance with the appropriate state and federal regulations.
3.1.2 The Manager - E&RC is responsible for:
- a. Advising the G.eneral Manager on the appropriate technical standards, regulations, and requirements as related to solidification, dewatering, and shipping. l 1 b. Ensuring the vendor's Process Control Program, operating procedures, and proposed contractural agreements are reviewed and advising the General Manager as to their adequacy.
- c. Retaining vendor supplied documentation for !GC inspection and review.
3.1.3 The Manager - Operations is responsible for monitoring vendor operations to assure compliance with Technical Specification 3/4.11.3, CP&L practices and procedures, as well as contractural agreements.
3.1.4 The Manager of the Radiological and Chemical Support section is responsible for advising the Manager - E&RC on:
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- a. The appropriate technical standards, regulations, and requirements as related to solidification, dewatering, and shipping. !
- b. The adequacy of the vendor's Process Control Program, operating procedures, and proposed contractural agreements.
3.2 Specification for Vendors The qualified solidification vendor will:
1 3.2.1 Provide a qualified process control program or a program ;
approved by:
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- a. NRC
- b. Disposal site licensee NOTE !
Qualified process control program has been interpreted to mean that testing of the product is underway (to meet the 10CFR Part 61 requirement) or test results have been transmitted to the Nuclear j Regulatory Commission in the form of a topical report.
3.2.2 Demonstrate the ability to meet:
- a. NRC solidification standards
- b. Disposal site specifications for solidified liquid wastes
- c. NRC dewatering standards
- d. Disposal site specification for freestanding liquids i
- e. DOT shipping regulations !
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- f. CP&L radiation protection procedures and practices j 3.2.3 Provide documentation on the following for CP&L review, evaluation, and retention:
- a. Solidification and dewatering system design including l a sketch of the processing system (s)
- b. Identification of solidification agent (s)
- c. Operating process control procedures with the process control parameters identified (including those for exothermic reactions required to be met prior to container's closure) and provisions to verify the absence of free liquids PCP (BSEP) 2 Rev. 2
- d. Results of process tests including:
(1) Identification of the representative sample of every tenth batch (2) Identification of actions taken if sample fails to verify solidification (3) Formulation used by the process
- e. Topical or qualified report for dewatering
- f. Topical or qualified report for high-integrity containers 3.3 Program Operations 3.3.1 The vendor will solidify or dewater and package the supplied liquid waste slurries (including the oily waste) according to their Process Control Program.
3.3.2 The vendor will perform the tests described in their l Process Control Program. I 3.3.3 The vendor will supply the Manager - E&RC and/or the Manager - Operations with all documentation required to demonstrate compliance with solidification and/or dewatering requirements.
3.3.4 The Manager - E&RC will retain vendor supplied documentation required to demonstrate compliance with solidification and/or dewatering requirements and standards. (This does not include documentation of Technical Specification Surveillance Requirement 4.11.3 which is the responsibility of the Manager - Operations.)
4.0 Management / Contractor Interactions 4.1 The vendor is accountable to the Manager - Operations for the i solidification and/or dewatering of liquid wastes. l 4.2 The ESRC subunit handles the shipping of solidified and dewatered j wastes and maintains required shipping documentation. The vendor and the E&RC Shipping Foreman may communicate on these matters as l necessary.
ATTACHMENT 4 Environmental Monitorinc Program Janu ry 1, to June 30, 1996 Enclosure 1: Milk and Vegetable Samole Locations Enclosure 2: Land Use Census t
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Et1 CLOSURE 1 Milk and Veaetable Sample Locations No milk sample locations were available during this time period. l Vecetable sample locations were unchanged durino this time period.
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Ef1 CLOSURE 2 .
Land Use Census tio new locations were identified that are reportable in the Semiannual Radioactive Effluent Release Report as per Technical Soecification 3.12.2.a and b.
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ATTACHMENT 5 Inoperable Effluent Instrumentation January 1. to June 30. 1986 Enclosure 1: Radioactive Liauid Effluent Monitorina Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitorina Instrumentation Enclosure 3: Liquid Hold-Up Tank G
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< . t ENCLOSURE 1 Radioactive Liauid Effluent Monitorina Instrumentation tJo radwaste liquid ef fluent instrumentation was incoerable for greater than a 30 day period during January 1. to June 20. 1986.
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d b ENCLOSURE 2 Radioactive Gases Effluent Monitorina Instrumentation Unit 1 main condenser off-cas treatment system explosive cas monitors, 1-0G-AIT-4284 (SJAE.A.H2 Analv er). 1-OG-AIT-4285 (SJAE.A.H2 Analv:er).
1-0G-AIT-4324 (SJAE.B.H2 Analv:er). and 1-OG-AIT-4325 (SJAE.B.H2 Analv:er). were inoperable for greater than a 30 day period during January 1. to June 30. 1986. Due to design problems, these monitors were not returned to service within 30 days.
Units 1 and 2. Reactor and Turbine buildinos roof vent monitor flow annubars. 1-VA-FE-3356, 1-VA-FE-3358, 2-VA-FE-3356, and 2-VA-FE-3358.
were inoperable for areater than a 30 dav period during January 1. to June 30. 1986. Due to design problems, these monitors were not returned to service within 30 days.
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- o ENCLO5URE 3 Liuuid Held-Up Tank No liquid hold-oo tank exceeded the 10 Ci limit between the dates of January 1. to June 30. 1986.
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ATTACHMENT 6 Maior Modifications to the Radicactive Waste Treatment Svstems January 1. to June 30. 1986 Discussion of major modifications to Radioactive Waste Treatment Svstems, if anv. will be submitted with the Final Safety Analysis Report update as allowed bv footnote 7 to Technical Specification 6.15.
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,4 ATTACHNENT 7 Meteoroloaical Data Brunswick Steam Electric Plant January 1. to June 30. 1986 As required by Technical Specification 6.9.1.10.a footnote 6. the annual summary of meteoroloaical data will be collected over the calender year and submitted to a fil,e within 90 days of January 1.
and will be available for NRC review upon request.
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e ATTACHMENT 8 Potential Dose Assessment Brunswick Steam Electric Plant Januarv 1. to June 30. 1986 As recuired bv Technical Soecification 6.9.1.10.b. . an assessment of radiation doses due to the radioactive liquid and gaseous effluents released durina the calendar year will be reported within 90 days after January 1 of each year, and is not included in this report.
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" c . s-Cp&L Carolina Power & Light Company
, 8g2S Brunswick Steam Electric Plant k8'.
P. O. Box 10429 /8 Southport, NC 28461-0429 August 21, 1986 FILE: B09-13510C SERIAL: BSEP/86-1218 Dr. J. Nelson Grace, Administrator U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street NW Atlanta, GA 30323 BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE.NOS. DPR-71-AND.DPR-62
' SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
Dear Dr. Grace:
Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick Steam Electric Plant covering the period from January 1, 1986, through June 30, 1986. -
This report is submitted in accordance with Technical Specification 6.9.1.8 for Brunswick Steam Electric Plant.
Very truly yours, a% OJ ch h C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/mcg Enclosure cc: NRC Document Control Desk
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