BSEP-84-1773, Semiannual Radioactive Effluent Release Rept,Jan-June 1984
| ML20112K107 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1984 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| BSEP-84-1773, NUDOCS 8504090336 | |
| Download: ML20112K107 (223) | |
Text
Brunswick Steam Electric Plant Semiannual Radioactive Effluent Release Report l l January i to June 30, 1984 1
Attachments ;
- 1. Supplemental Information
- 2. Effluent and Waste Disposal Data
- 4. Environmental Monitoring Program
- 5. Inoperable Effluent Instrumentation
- 6. Major Modifications to Radioactive Waste Treatment Systems j 7. Meteorological Data
- 8. Potential Dose Assessments 3
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ATTAClefENT 1 Supplemental Information Brunswick Steam Electric Plant January - June,1984 1
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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plant Licensee Carolina Power & Light company
- 1. Regulatory Limits
- a. Fission and activation gases (Technical Specification 3.11.2.2)
- (1) Calendar Quarter (a) 10 mrad gamma (b) 20 mrad beta (2) Calendar Year (a) 20 mrad gamma (b) 40 mrad beta
- b. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days (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 (e) 3 mrem to total body .
(b) 10 mrem to any organ (2) Calendar Year 4
(a) 6 mrom to total body (b) 20 arem 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.
- used for percent of technical specification limit determination in Table 2A.
- 2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.
- a. Fission and activation gases (Technical Specification 3.ll.2.1.a)
(1) 500 mrem / year 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.ll.2.1.b)
(1) 1500 mrem / year to any organ
- c. Liquid effluents (Technical Specification 3.11.1.1)
The concentration of ra ?.ioactive 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.
- (1) Tritium: MPC = 3 x 10
- pCi/mlr and
- (2) Dissolved and entrained gases: MPC = 2 x 10-4 pCi/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. Liquid Effluents Analysis for specific radionuclides by individual releases by gamma spectroscopy.
- f. **used as applicable limits for Table 2A. ,
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Relative variance for each measurerent used in calculating activity values were combined using the additive property of variance. The square root of the combined variance was extracted to obtain an estimate of the standard deviation of the multistep process. The standard deviation was used to evaluate the error in the calculated activitie: at the 95% confidence level.
- 4. Batch Release
- a. Liquid (1) Number of batch releases: 219 (2) Total time period for batch releases: 2.85E04 (3) Maximum time period for a batch release: 1.59E03 (4) Average time period for batch release: 1.28E02 (5) Minimum time period for a batch release: 1.00E00 (6) Average stream flow during periods of release of effluent into a flowing stream: N/A
- b. Gaseous (1) Number of batch release: None (2) Total time period for a batch release: 0.00E00 (3) Maximum time period for a batch release: 0.00E00 (4) Average time period for a batch release: 0.00E00 (5) Minimum time period for a batch release: 0.00E00
- 5. Abnormal Releases ,
- s. Liquid (1) Number of releases: None (2) Total activity released: None
- b. Gaseous (1) Number of releases: None (2) Total activity released: None e.
l ATTACEMENT 2 l
Effluent and Waste Disposal Data Brunswick Steam Electric Plant i
January - June, 1984 l Table IA: Gaseous Effluents - Summation of All Releases Table IB: Gaseous Effluents - Elevated Releases Table IC: Gaseous Effluents - Ground Level Releases Table 2A: Liquid Effluents - Summation of All Releases Table 25: Liquid Effluents Lower Limits of Detections Table 3: Solid Waste and Irridated Fuel Shipments
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- Table 1A Effluent and Waste Disposal Semiannual. Report Year 1984 9 Caseous Effluents - Summation of All Releases Est.
Total Unit Qtr 1 Qtr 2 Error, 4 A. Fission and activation gases
- 1. Total release ci 1.50E 05 3.90E 03 1.09E 01
- 2. Average release rate for pCi/see 1.91E 04 4.96E 02 period
- 3. Percent of technical % 3.05E 01 2.03E-01 specification limit B. Iodines
- 1. Total iodine-131 Ci 1.48E-01 1.56E-04 2.36E 01
- 2. Average release rate for pCi/see 1.88E-02 1.99E-05 period C. Particulates
- l. Particulates with half- Ci 1.64E-01 1.23E-02 1.24E 01 lives of greater than eight days
- 2. Average release rate for pCi/see 2.09E-02 1.57E-03 period
- 3. Gross alpha radioactivity Ci O.00E 00 0.00E 00 .
D. Tritium
- 1. Total release ci 3.79E 00 4.54E 00 9.26E 00
- 2. Average release rate for poi /sec 4.82E-01 5.77E-01 period E. Iodine-131, Iodine-133, Tritium l and Particulates
- 1. Total release Ci 5.17E 00 4.55E 00
- 2. Average release rate for pCi/sec 6.46E-01 5.79E-01 period
- 3. Percent of technical n 1.73E 00 3.13E-02 specification limit
Table IB Effluent and Waste Disposal Semiannual Report Year 1984
_ Gaseous Effluents - Elevated Release l Continuous Release l Nuclides Released Unit Qtr 1 Qtr 2 l
- 1. Fission 01ses argon-41 Ci 1.45E 01 8.90E-01 krypton-85m Ci 5.00E 03 1.48E 01 krypton-87 Ci 1.56E 04 4.35E 01 krypton-88 Ci 1.44E 04 4.09E 01 xenon-131m Ci 6.59E 03 < LLD xenon-133 Ci 6.31E 03 1.89E 01
- xenon-135m C1 1.36E 04 2.86E 01 xenon-135 C1 2.49E 04 7.56E 01 xenon-137 Ci 6.74E 03 < LLD xenon-138 Ci 5.08E 04 9.79E 01 unidentified Ci 2.41E 03 3.58E 00 total for period Ci 1.47E 05 3.25E 02
- 2. Gaseous Iodines iodine-131 Ci 1.46E-01 9.12E-05 iodine-132 Ci 7.65E-01 < LLD iodine-133 Ci 1.06E 00 2.94E-04 iodine-134 Ci 1.22E 01 < LLD iodine-135 Ci 1.63E 00 < LLD unidentified Ci 1.94E-01 9.25E-05 total for period Ci 1.60E 01 4.78E-04 i
- 3. Particulates i
chromium-51 Ci 1.75E-03 3.59E-03 .
manganese-54 C1 2.64E-03 1.41E-04 cobalt-58 Ci 3.69E-04 3.78E-05
- cobalt-60 Ci 2.31E-04 1.04E-03
, strontium-89 Ci 1.32E-03 4.08E-05 strontium-90 Ci 2.35E-06 6.84E-07 sirconium-niobium-95 Ci 2.05E-04 < LLD iodine-131 Ci 1.46E-01 9.12E-05 l cesium-134 Ci 1.19E-05 3.94E-06 l cesium-137 Ci 8.49E-05 8.18E-05 barium-lanthanum-lio ci 7.45E-04 < LLD i unidentified C1 1.46E-03 3.30E-04 .
total for period Ci 1.55E-01 5.40E-03
Table IC Effluent and Waste Disposal Semiannual Report Year 1984 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Qtr 1 Qtr 2
- 1. Fission Gases krypton-85m Ci 1.51E 00 4.78E-01 krypton-88 Ci 8.02E 00 2.27E 00 xenon-133m Ci 1.20E 02 1.37E 02 xenon-133 Ci 2.49E 03 2.59E 03 xenon-135m Ci 7.48E 00 2.12E 00 menon-135 Ci 7.05E 02 6.97E 02 unidentified Ci 1.76E 02 1.53E 02 total for period Ci 3.51E 03 3.58E 03 e
- 2. Gaseous Iodines lodine-131 Ci 1.12E-03 4.00E-05 iodine-132 Ci 7.75E-04 < LLD iodine-133 Ci 7.39E-03 6.05E-05 iodine-135 Ci 9.15E-03 < LLD unidentified Ci 1.00E-03 3.55E-05 total for period C1 1.94E-02 1.36E-04
- 3. Particulates chromium-51 -
Ci 6.23E-03 2.55E-03
. manganese-54 Ci 1.90E-04 8.20E-04 cobalt-58 Ci 4.85E-05 1.48E-04 iron-59 Ci 2.48E-05 7.68E-05 cobalt-60 Ci 1.01E-03 2.56E-03 strontium-89 Ci 5.44E-05 3.93E-06 ,
- strontium-90 Ci 1.24E-06 7.14E-07
! zirconium-niobium-95 Ci < LLD 3.08E-07 iodine-131 Ci 1.12E-03 4.00E-05 1
cesium-134 Ci 7.12E-07 3.91E-05 cesium-137 C1 2.93E-05 1.39E-04
. cerium-144 Ci 1.27E-07 < LLD unidentified Ci 5.46E-04 4.16E-04 total for period Ci 5.52E-04 4.28E-04 i 4. Tritium hydrogen-3 Ci 3.23E 00 4.12E 00 f
Table 2A Effluent and Waste Disposal Semiannual Report Year 1984 Liquid Effluents - Summation of All Releases Est.
Total Unit Qtr 1 Qtr 2 Error, 4 A. Fission and activation products
- 1. Total release (not including 2.56E-01 1.52E-01 1.30E 01 tritium, gases, alpha)
- 2. Average diluted concentra- pCi/ml 3.35E-09 5.15E-09 during period
- 3. Percent of applicable 4 2.72E-01 4.02E-01 limit i
B. Tritium
- 1. Total release C1 2.24E 01 6.73E 00 1.04E 00
- 2. Average diluted concen- pCi/ml 2.93E-07 2.46E-07 tration during period
- 3. Percent of applicable t 9.80E-03 8.20E-03 limit C. Dissolved and entrained gases
- 1. Total release ci 1.40E 00 8.33E-04 2.99E 01
- 2. Average diluted concen- pCi/ml 1.83E-08 3.04E-11 tration during period ,
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- 3. Percent of applicable t 9.16E-03 1.52E-05 limit D. Gross alpha radioactivity
- 1. Total release Ci 0.00E 00 0.00E 00 5.12E 00 E. Volume of waste released liters 8.31E 06 5.05E 06 1.25E 01 (prior to dilution)
F. Volume of dilution water liters 7.64E 10 2.74E 10 9.73E 00
, used during period E
Table 28 Effluent and Weste Disposal Semiannual Report Year 1984 Liquid Effluents - Batch Mode Nuclides Released Unit Qtr 1 Qtr 2
- 1. Fission and Activation Products l fluorine-18 Ci 3.23E-03 6.43E-06 sodium-24 Ci 2. ole-02 5.81E-05 chromium-51 Ci 7.71E-02 2.77E-03
( manganese-54 Ci 1.07E-02 1.59E-02 l l iron-55 Ci 5.59E-03 9.62E-03 j cobalt-58 Ci 1.99E-03 3.24E-03 iron-59 Ci 2.10E-04 1.65E-04 cobalt-60 Ci 3.48E-02 8.58E-02 sine-65 Ci 1.57E-04 < LLD sine-69m Ci 5.57E-06 < LLD arsenic-76 C1 3.16E-03 1.78E-05 strontium-89 Ci 8.98E-05 9.62E-04 strontium-90 Co 5.95E-05 1.82E-04 yttrium-91m Ci 6.42E-04 < LLD yttrium-92 Ci 1.75E-02 < LLD strontium-92 Ci 1.17E-04 1.26E-05 zirconium-niobium-95 Ci 1.24E-05 4.76E-06 niobium-97 Ci 1.93E-03 < LLD molybdenum-99 Ci 1.51E-03 < LLD technetium-99m Ci 8.62E-03 5.71E-06 technetium-101 Ci 1.31E-03 < LLD ruthenium-103 Ci 1.09E-04 1.04E-05 technetium-104 C1 4.33E-03 < LLD ruthenium-105 Ci 1.44E-02 < LLD silver-110m Ci 2.46E-04 4.60E-05 silver-111 C1 4.76E-04 < LLD iodine-131 Ci 3.32E-03 < LLD ,
iodine-132 Ci 8.02E-05 < LLD iodine-133 C1 3.00E-03 < LLD cesium-134 Ci 2.97E-03 8.09E-03 iodine-135 Ci 9.07E-04 < LLD cesium-137 Ci 6.81E-03 2.04E-02 cesium-138 Ci < LLD 2.97E-06 barium-lanthanum-140 C1 1.64E-02 < LLD cerium-141 Ci < LLD 8.64E-07 lanthanum-141 Ci 1.29E-03 < LLD lanthanum-142 Ci 6.77E-04 < LLD unidentified Ci 1.21E-02 4.40E-03 total for period Ci 2.56E-01 1.52E-01 I
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,_.a:.+ u _ , a Table 2B (continued)
Effluent and Waste Disposal Semiannual Report Year 1984 Liquid Effluents - Batch Mode Nuclides Released Unit Qtr 1 Qtr 2
- 2. Dissolved and Entrained Gases argon-41 Ci 5.21E-05 < LLD xenon-133 Ci 2.82E-01 1.50E-04 xenon-133m Ci 1.14E-02 < LLD xenon-135 Ci 1.10E 00 4.82E-04 xenon-135m Ci 1.91E-03 < LLD unidentified Ci 8.94E-03 2.01E-04 total for period Ci 1.40E 00 8.33E-04 i
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Lower Limits of Detection DCi/ml
- 1. Liquid Releases En-65 1.06E-07 En-69m 3.44E-08 Y-91m 6.59E-08 Y-92 7.57E-07 Mo-99 4.34E-07 Tc-101 2.23E-07 Tc-104 9.46E-08 Ru-105 9.25E-08 Ag-lll 5.51E-07 I-131 5.26E-08 I-132 6.87E-08 I-135 3.20E-07 La-140 1.llE-07 La-141 1.96E-06 La-142 1.34E-07 Ar-41 5.47E-08 Xe-133m 3.10E-07 Xe-135m 2.58E-07 Cs-138 1.26E-07 Ce-141 4.18E-08
- 2. Gaseous Releases Xe-131m 8.76E-07 Xe-137 5.44E-06
- 3. Iodines and Particulates Er-95 4.27E-13 ,
Nb-95 2.37E-13 Ba-140 9.01E-13 La-140 7.04E-13 I-132 4.18E-12 I-134 9.14E-12 I-135 7.56E-12 Co-144 9.49E-13 NOTE: The above tables present typical "a priori" LLDs for radionuclides where values of "less .than LLD" are indicated in Tables IA, IB, IC, 2A and 2B. .
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TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (6-MO. PERIOD) 1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS j 1. Summary of all shipments January thru June 1984
- Total volume shipped, m' 3.95E O2 Est. of total error, t 1.75E 01 Total Ci quantity, 8. ole O2 Waste class, A a
Est. of total error, t 1.75E 01
- 2. Type of waste Unit 6-month period est. total error, t
- a. Spent resins, filter sludgest m i 1.58E O2 Ci 7.95E O2 1.50E 01 4
- b. Dry active waste, compacted, m8 2.37E O2 non-compacted: ci 6.36E 00 2.OOE 01
- c. Irradiated components: m8 0.OOE 00 Ci O.OOE 00 O.OOE 00
- d. Other (describe): a8 0.OOE 00 Ci O.OOE 00 0.00E 00
- 3. Estimate of major radionuclide composition (by type of waste) a.______________________________ _ _ _ _C_r_. 5_1_ _ . _ _ _4__ .. ._ _ _ _ __ _1_._0_2_E__0
_ _ _ .. . .. . ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .. _ __ _ _M_n_ _5_4_ _ _ _ _ _. 4.._ _ _ _ _ _ _ _ _ _1_._3 0.E. 01
_ _. ..__ _ _ _ _ _ . _ _ _ _ _ _ _ __. .. _ _ __ _ _ __ __F_e_ _5_9_ _. ..._t_ ..... . ..__ _8 _2_0_E_ _01 01
_ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _...._ _ _ _ _ _ _ _ __ __ _F_e_ _5_5_
...._______...______.._____________.Co__5_8_____.__t____________2_._7_5_E__
. _ _ _ _ . . . .. . ._ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _.._ _._C_o_ _6_0_ _ _ _ _ _..t. .. _ _ _...._4_._6_0_E_ _01 .
_ _ _ _ _ _ _ ._ _ _ . ._ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _E_n_ _6_5_ __ _ _ _ _ _4.. ._ _ _ _ _. .. 9_._4_0_E_ _O
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. ._ _ _ __ ... _ _ _ _ _ __ _ _ _I_ _1_3_1__... ._4_ _ _ _ _.._ _ _ _ _2_._l_O_E_ _0 0
___ _ _ _. .. ..._ _ _ _ _ _..__.._ ____ _ _ _ _ _C_s_ _1_3_4_ _.. ._ _4_ __ __ _.. _ __ _1_._l_O_E_ _0 0
_ _ _ _ _ .. ._ _ _ _ _ _ __ _ _ _ __.. _ _ _ _ _ _.__ .._C_s_ _1_3_7_ _ ___ _.4.... .._ _ _ __ _3_._3_7_E_ _0 0
._ _... . .. .... _ _ _ _ _ __..._ _ _ _ ...._ _ _. N_i__6_3__ _ __ _ _ _4.._ __ _ _ _._ __4_._2_4_E. 0 0
_ ___ _ _ __ _ _ _ _ _ __ _. . ..__ _ . . . . . .._ _ _ _ _ _B_a_ _1_4_0....__ _t__ _ __ _ _ _ _ _ _ _1_._4_1_E__0 0
_ _ __ _ _ _ .. ...__ _ _ _ _ _ _ _ _ _. . _ _ _ _ _ _ _ _L_a..14 0_ __ __..t__..._ _ _..._1_._l_O_E_ _0 0
_ _ _ _ _ __ _ _ _. ..._ _ _ _ _ _.. ._ __ _ _ _ _ .. .X.e_ _1_3_1_m_ _ _ _. 4.._ __...... 2_._8_0_E_.0 0 -
b.___________________ ._________________ ..._____ .______ ____....
_ _ __... _ _ _ _ __ __ .._ _. ._...__ __ _ _ _ _ ___C_r_ _5_1_. _ _ _ _ _4_ _ _.._ _ _ _ _ __1_._6_0_E_ _0 0
_ _ __ _ . . .. .. ._ _..._ _ _ _ _. ._ _ . ._ _ _ _ _ _M_n_ _5_4__...__ _4_ _ _ _ _ _ _ __ _ _8_._8_0_E_.00 i
_ _ __..._ _w_. ___..__ _ _..__ _ _ _ __ _ __ __F_e__5_5. .. ._ _ _ _4_ _. . ._ _ _ _ _ _ _5_._8_1_E_ .01
' . _ _ . .. ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ __ _ _ _ _ _ _C_o_ _6_0_ __ ._ _ _ _t_ __ _ _ _ . _. __ _2_. 4 8_E_ _01
.._ _ _ ___ _ _ _ _..... _ _ _ _ _ _._ _ _ _ _ _ _ _ _ _..C.s__1_3_4_ _ _ _ _ __4. ...... _ _ _ _2_._O_O_E_ _0 0
. _ _ _ _ _ _ _ .. . ....._ __ _ _ _. .. . _ _ _. . .. -_s_ _1_3_7_ C _ _ _ _ _ _4_ _ _ _. . . .._ _.4_._5_0_E_ _0 0
.________________ ______.___ ______ .___________m_____________...
_____.. __.______________.....__.....__..__. __.______e_...____...
, ,_y-- - . . . - - - . - - , , - - , - . , , , _ _ . , - - . -- -, , -
. TABLE 3 (continued) ,
O NASTE CLASS: A
- 4. Cross reference table, waste stream, form, container type.
I Form Container Type No. shipments Stream i
- a. Resin Dewatered TypeA/ Type B 29/2 l Solidified No solidified wastes shipped 1/t.4 thru l 6/84 l
- b. Dry active waste compacted compacted /non LE6dEIE....__. ... ...---._8_ _ . __-..
material
- c. Irradiated components N/A N/A
- d. Other N/A N/A
- 5. Shipment Disposition
- a. Solid Maste Number of Shipments Mode of Transportation Destination 39 sole use vehicle Chem-Nuclear Systems, Inc..
Barnwell, SC
- b. Irradiated Fuel Number of Shipments Mode of Transportation Destination N/A N/A N/A ,
a
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TABLE OF CONTENTS
-Section Title Page Li st of Ef fec ti ve Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
{
Table of Contents........................................... 11 List of Tab 1es.............................................. .
iii List of Figures............................................. viii
1.0 INTRODUCTION
................................................ 1-1 2.0 LIQUID EFFLUENTS............................................ 2-1 2.1 Compl i ance wi th 10CFR20 (Li qui ds) . . . . . . . . . . . . . . . . . . . . 2-1 (Alarm / Trip Setpoint Determination) 2.2 Compl iance wi th 10CFR50 (Li qui ds ) . . . . . . . . . . . . . . . . . . . . 2-11 3.0 GASEOUS EFFLUENTS........................................... 3-1 3.1 Moni to r Al arm Setpoi n t Dete rrii nati o n. . . . . . . . . . . . . . . . . 3-1 3.2 Compl i ance wi th 10CFR20 (Ga seous ) . . . . . . . . . . . . . . . . . . . . 3-15 3.3 Compl iance wi th 10CFR50 (Ga seous ) . . . . . . . . . . . . . . . . . . . . 3-34 4.0 RADIOLOGICAL ENVIRONMENTAL.................................. 4-1 MONITORING PROGRAM 5.0 INTERLABORATORY COM PARISON PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 6.0 TOTAL DOSE (40CFR190 CONFORMANCE)........................... 6-1 A PPE NDI X A - Me teo rol ogic al Di s pe rsi on Fa c to r. . . . . . . . . . . . . . . A-1 Computations APPENDIX B - Calculation.of Bt and V4 Val ue s . . . . . . . . . . . . . . . . B-1 for the Elevated Plume APPENDIX C - Dose Parameters for Radiofodines,.............. C-1 Particulates, and Tritium i
APPENDIX 0 - Lower Limi t of Detection (LLD ) . . . . . . . . . . . . . . . . . D-1 l
APPENDIX E - Radioactive Liquid and Gaseous................. E-1 Effluent Monitoring Instrumentation Numbers l
1 APPENDIX F - Liquid and Gaseous Effluent System ............ F-1 Diagrams A PPE NDI X G - ODCM Sof tware Package. . . . . . . . . . . . . . . . . . . . . . . . . . G-1 l
Rev. 1
i LIST OF TABLES No. Title Page 2.1-1 MPCs for Sel ected Radi onucl i des. . . . . . . . . . . . . . . . . . . . . . . . . 2-10 2.2-1 Aj , Val ues for the Adul t. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-14 i 3.1-1 Gaseous Source Terms.................................... 3-12 3.1-2 Dose Factors and Constants.............................. 3-13 4
3.2-1 Releases from Brunswick Steam Electric Plant............ 3-28 3.2-2 Distance to Controlling Locations as Measured........... 3-29 from the Brunswick Plant Center I 3.2-3 Distance to Site Boundaries Based Upon Brunswick........ 3-30 Plant Center and Direction from the Stack l 3.2-4 Dose Factors for Noble Gases and Daughters. .. .. . .. . . . . .. 3-31 3.2-5 P4 Values for an Infant for the Brunswick Steam......... 3-32 i
Electric Plant .
, 3.3-1 thru R Values for the Brunswick Steam Electric Plant......... 3-49 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 Yalues 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-6 D/Q Values at the Standard Distances for Releases....... A-10 from the Turbine Buildings A-7 X/Q Yalues at the Special Locations for Releases........ A-11 from the Reactor Buildings ODCM (BSEP) 111 Rev. 1
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 Buf1 dings A-10 X/Q Values at the Standard Distances for Releases....... A-14 4 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 Yalues at the Standard Distances for Releases....... A-16 from the Reactor Buildings
, A-13 X/Q Yalues at the Special Locations for Releases........ A-17 from the Stack A-14 Depleted X/Q Values at the Special Locations for........ A Releases from the Stack A-15 D/Q Yalues at the Special Locations for Releases........ A-19 from the Stack A-16 X/Q Yalues.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 Yalues at the Standard Distances for Releases....... A-22 from the Stack A-19 Brunswick Plant Site Infomation to be Used for......... A-23 Ground Level Calculations with NRC "X0QD0Q" Program A-20 Brunswick Plant Site Infomation to be Used for......... A-26 Elevated Release Calculations with NRC "X0QD0Q" Program B-1 Dose Parameters for Finite Elevated Plumes ENE.......... B-2 Site Boundary l 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 !
l 1
LIST OF TABLES (continued) j No. Title Page B-4 Joint Frequency Distribution for N Sector (%)........... B-5 l 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 l 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 B-16 Joint Frequency 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 i Boundary i
LIST 'N TABLES (continued)
No. ,Ti t1 e Page 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 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*
Period 1-1-77 through 12-31-77, Brunswick Steam 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 B-31 Dose Parameters for Finite Elevated Plumes NNW.......... B-32 Site Boundary ODCM (BSEP) vi Rev. 1
l LIST OF TABLES (continued)
No. Title Page B-32 Joint Frequency Distribution for NNW Sector (%)......... B-33 i Period 1-1-77 through 12-31-77, Brunswick Steam l Electric Plant C-1 Pa ramete rs fo r Cow and Goa t Mi l k Pa thway s . . . . . . . . . . . . . . . C-16 C-2 Parame ters for the Meat Pathway. . . . . . . . . . . . . . . . . . . . . . . . . C-17 C-3 Parameters for Vege tabl e Pathway . . . . . . . . . . . . . . . . . . . . . . . . C-18 ODCM (BSEP) vii l Rev. 1
LIST OF FIGURES
_No. Title Page 4.0-1a BSE P Sampl e Poi nt Locati o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-5 4.0-lb BSE P Sampl e Poi nt Loca tions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-6 4.0-1c BSE P Sampl e Poin t Locati ons. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-7 4.0-id BSE P Sampl e Point Loca tions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-8 F-1 Li qui d Radwa ste Ef fl uent System. . . . . . . . . . . . . . . . . . . . . . . . . . . . F-2 F-2 Gaseous Radwa s te E f fl uent System. . . . . . . . . . . . . . . . . . . . . . . . . . . F-3 i
I i .
1.0 INTRODUCTION
This Off-Site Dose Calculation Manual (0DCM) provides the infomation and methodologies to be used by Brunswick Steam Electric Plant (BSEP) to assure compliance with certain portions of BSEP's operating technical specifica-tions. These portions are those related to liquid and gaseous radiological effluents. They are intended to show compliance with 10CFR20,10CFR50.36a, and Appendix I of 10CFR50.
The 00CM is based on " Radiological Effluent Technical Specifications for BWRs" (NUREG 0473, Draft), " Preparation of Radiological Effluent Technical Specifi-cations for Nuclear Power Plants" (NUREG 0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant procedures for implementation of this manual are provided elsewhere. These procedures will be utilized by the operating staff of BSEP to assure compliance with technical specifications.
The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCM will be expected in the future. Any such changes will be properly reviewed and approved as indicated in the Administration Control Section of the BSEP Technical Specifications.
1 t
2.0 LIQUID EFFLUENT l 2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS) 2.1.1 ~ Batch Releases j
A batch release is the discharge of liquid waste of a discrete volume. Batch releases from the BSEP liquid radwaste system may occur from the waste sample tank, floor drain sample tank, detergent drain tank and, when declared fully operational, the salt water tanks. The maximum release rate possible due to pump capacity is 200 GPM from all release tanks except the detergent drain i
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 l differ by more than 15% upon approval of the ESC Supervisor or equivalent.
The maximum release rate is determined such that 10CFR Part 20 limits are not exceeded after dilution in the discharge canal.
4 The sampling and analysis frequency and the type of analysis required by the 4
BSEP Technical Specifications is given in Table 4.11.1-1. All applicable instrument numbers may be found in Appendix E.
i i 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 Specifica-l tions. Compliance with 10CFR Part 20 will be shown in the following manner: '
d E
i 4
j -00CM (BSEP) 2-1 Rev. 0
- a. Minimum acceptable dilution factor:
DF o = EI i (Eq. 2.1-1)
N Where:
DF o = Minimum acceptable dilution factor determined from analysis of itquid effluent to be released 4
C4
=
Concentration of radionuclide i in the batch to be released, pCi/ml MPCg = Maximum permissible concentration of radionuclide i from Appendix B, Table II, Column 2 of 10CFR Part 20, pCf /ml
=
DF B (10) (DFo) (Eq. 2.1-2)
, Where:
- 'DF B =
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 Part 20 limits as speci-fied in Appendix B, Table II, Column 2. This , factor represents one layer of conservatism for all releases at l.
=
OF o Minimum acceptable dilution factor per Equation 2.1-1
- b. Maximum release rate:
MRR = n-1 (RPFCW) + p-1 (R 'YSW) (Eq. 2.1-3) 2 (DFB I t
Where:
MRR = Maximum release rate of the batch to be released, GPM j n = Number of operating circulating water pumps p = Number of operating service water pumps
=
RPFCW Minimum rated pump flow of each circulating water pump
= 1.357 E5 GPM RPF3 g = Rated pump flow of each service water pump
= 8 E3 GPM
=
2 Engineering factor to prevent spurious alarms caused by deviations in the mixtures of radionuclides which affect the monitor response DFB
= Minimum acceptable dilution factor (DF )o ir.ade conserva-tive by a factor of 10 per Equation 2.1-2
- 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, Table II, Column 2, for radionuclides i
other than dissolved or entrained noble gases. An MPC of '
2 E-4 pCi/ml has been established for noble gases dissolved or entrained in liquid effluents, based on the assumption that Xenon- l 135 is the controlling radionuclide.
1
=
CT (E,) [(n-1) (RPFCW) + (p-1) (RPF39)] l SP RR + kg. ;
(Eo. 2.1-4)
t Where:
SP = Monitor alarm / trip setpoint, cps t
i Em = The monitor efficiency for the mixture of radionuclides in the liquid effluent prior to dilution, cps / Ci/ml
= 3 E-7 pCi/ml; engineering factor to ensure that the CT 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
= 1.357 E5 GPM RPFCW RPFsg = 8 E3 GPM RR = 200 GP!1; maximum design release rate Bkg. = Background count rate due to internal contamination and i the radiation levels in the area in which the monitor is !
installed when the detector sample chamber is filled with an uncontaminated fluid, cps
=
3 E-7 (E*) [(n-1) (1.357 ES) + (p-1) (8.0 E3)) l SP ggg + Bkg. l (Eq. 2.1-5)
- d. Calculated concentration at unrestricted area:
1
= (Cg) (MRR) (Eq. 2.1-6)
Conej (n-1) (RPFCW) + (p-1) (RPFsg) l ODCM (BSEP) 2-4 Rev. 1
l Where:
=
Conct Calculated concentration of radionuclide i at the unre-stricted area, pCi/ml C, =
Concentration of radionuclide i in the batch to be released, pCi/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
= 1.357 E5 GPM RPFCW RPFS y = 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 perfomed. If the calculated dilution factor at the unrestricted area is less than or equal to 1, then 10CFR' Part 20 limits have been met. The following equation must be true:
f(Concj /MN)I i 1 (Eq. 2.1-7)
Where:
=
Conci Concentration of radionuclide i at the unrestricted area per Equation 2.1-6, pC1/ml MPCg = Maximum pemissible concentration of radionuclide i from Appendix B, Table II, Column 2, of 10CFR Part 20,pCi/ml ODCM (BSEP) 2-5 Rev. 1
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 fol-lows:
- a. Actual concentration at unrestricted area:
Concik
, (Cg) (V,ff,) (Eq. 2.1-8)
V dil .
Where:
=
Concik The actual concentration of radionuclide i at the unre-stricted area during release k, pCi/ml
=
Cj Concentration of radionuclide i in the batch released, pCi/ml
~
V,ff =
Actual volume of liquid effluent released, gal
=
V dil. Actual volume of dilution water during release k, gal
=
[ n (RPFCW) + p (RPF5g)] (tk I Where:
n =
Number of operating circulating water pumps a
4 p =
Number of operating service water pumps l
=- 1.357 ES GPM RPFCW I RPF5 g = 8 E3 GPM l
tk = Total release time, min I l
00CM (BSEP) P.6 Rev. 1
- b. 10CFR Part 20 Postrelease Compliance Check:
To show final compliance with 10CFR Part 20, the following relation-ship must hold:
I (Conc ik /MPCg ) < 1 (Eq. 2.1-9)
Where:
Concik
= The actual concentration of radionuclide i during release k (from Equation 2.1-9), pCi/ml 1
MPCt
= Maximum pemissible concentration of radionuclide i from Appendix B, Table II, Column 2, of 10CcR Part 20,pC1/ml 2.1.2 Continuous Releases A continuous release is the discharge of liquid wastes of a nondiscrete vol-ume; e.g., from a volume or system that has an input flow during the contin-uous release. Planned continuous releases do not presently occur at BSEP, although the potential does exist in the service water system. Weekly tests are perfomed 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 j being the concentration of radionuclide i in the 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 MPC must again be less than 1.
l l
1 4
2.1.2.1 Service Water Effluent Monitor Setpoint Determination This procedure determines the monitor alarm setpoints that indicate the abnor-
. mal 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 nonitor efficiency factor, EF, in " fp!f EF =
(E ,) (Cf ) (Eq. 2.1-10)
Where:
E, =
The detector efficiency (dpm/ml/ cps) from the appro-priate PT Cf
= Conversion factor, (1 pCi/2.22 x 10 6dpm)
- b. Determine the monitor trigger level setpoint, TLS, in cps TLS = TL/EF + Bkg (Eq. 2.1-11)
Where:
I TL = The alarm trigger level (C1/ml) as per Technical Specification 3/4.11.1.1.
=
5.0 x 10-6 C1/ml Bkg = Monitor background, (cps) 2.1.3 Stabilization Pond Releases Prerelease and post-release compliance checks similar to those of Section 2.1.1 may be performed for releases from the stabilization pond. Prerelease calculations will be based on a gamma isotopic assay of a grab sample prior to 00CM (BSEP) 2-8 Rev. 1
release. Post-release calculations will be based on a composite sample that is collected in. proportion to flow during the release period (if possible).
Dilution flow will be estimated from the minimum number of circulating water and service water pumps that were in use during the release period. Typical release times are on the order of days. (Note: Calculated doses as in Section 2.2 will be compiled along with those resulting from normal radwaste j
discharges.)
f 4
e I
TABLE 2.1-1 i
MPCs FDR SELECTED RADIONUCLIDES Radionuclide MPCi (pCi/al)*
H-3 3 E-3 Na-24 3 E-5 l Cr-51 2 E-3 Mn-54 1 E-4 Co-58 9 E-5 Fe-59 5 E-5 Co-60 3 E-5 Cu-64 2 E-4 Zn-69m 6 E-5 Sr-89 3 E-6 Sr-90 3 E-7 Sr-91 5 E-5 Zr-95 6 E-5 Mo-99 4 E-5 I-131 3 E-7 I-132 8 E-6 I-133 1 E-6 Cs-134 9 E-6 I-134 2 E-5 I-135 4 E-6 Cs-137 2 E-5 La-141 3 E-6 Np-239 1 E-4 Noble Gases 2 E-4
- Soluble or insoluble whichever is most restrictive.
- l l
l 2.2 COMPLIANCE WITH 10CFR PART 50 l 2.2.1 Cumulation of Doses i
- - 1 Technical Specification ~ 4.11.1.2 requires that the cumulative dose contributions from liquid effluents be determined at least once per 31 days, and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarter. The cumulative dose contributions will l . consider the dose contributions from the maximum exposed individual's
! consumption of fish and invertebrates. At BSEP the adult is considered as the maximum exposed individual. The dose or dose commitment limits based on 10CFR
! Part - 50, ' Appendix I, are defined in Technical Specification 3.11.1.2 a and
- b. Since only batch releases occur at BSEP, the equations in the following i
sections pertain only to batch releases. The dose contribution for all batch releases for the quarter will be calculated using the following equation:
Dt =
[ f ( A, 9
t k
C g F) k (Eq. 2.2-1) f
)
! Where:
4 Dt =
The cumulative dose commitment to the total body or any organ t, from the liquid effluents releases, mrem
- =
tk The length of time of release k over which Cik and Fk are averaged for all liquid releases, hours Cik
=
The concentration of radionuclide i in the undiluted l
, liquid effluent during release k from any liquid :
release,pCi/ml Agt = The site-related ingestion dose commitment factor to the i total body or any organ 5 for each identified gamma and
- beta emitter 1 (as presented in Table 2.2-1). Values are for an adult, mrem-m1 per hr- Ci-
=
1.14 ES (5 BIj + 21 BFj ) DCFg t ODCM (BSEP) 2-11 Rev. O
Where:
6 3 1.14 E5 = 10 10 - hr 5 = Maximum adult invertebrate consumption rate from Table E-5 of Regulatory Guide 1.109, Rev.1, kg/yr BIj = Bioaccumulation factor for radionuclide i in inverte-brates from Table A-1 of Regulatory Guide 1.109, Rev.1, pC1/kg per pC1/1 21 = Maximum adult fish consumption rate from Table E-5 of i Regulatory Guide 1.109, Rev.1, kg/yr BFj =
Bioaccumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109, Rev.1, pCf/kg per DCFjs =
Dose conversion factor for radionuclide i for adults for
, a particular organ 5 from Table E-11 of Regulatory Guide 1.109, Rev. 1, mrem /pC1.
=
Fk The near-field average dilution factor for Cik during any liquid effluent release. It 8s defined as the ratio of the volume of undiluted liquid waste released to the .
product of the dilution volume from the site discharge to unrestricted receiving water times 1. (1 is the site-specific applicable factor for the mixing effect of the BSEP discharge structure as defined in NUREG 0133.)
Y
= eff. (See Equation 2.1-8).
Vejj, 4
6,m .u . , s. _ _a a &.a. _. .._.,,_a .a a_- a:-,:q.ea-.
2.2.2 Projection of Doses Dose projections for this section are required at least once per 31 days in Technical Specification 4.11.1.3.
The projection of doses for liquid effluents can be accomplished by projecting the dose (s) computed for the current month into the next month. The doses will be projected using Equation 2.2-1. Where possible, credit for expected operational evolutions (i.e., major planned liquid releases, etc.), can be i taken in the dose projections. This may be accomplished by using the source-tem data from similar historical operating experiences where practical.
i i
I I
i l
4 1
00CM (BSEP) 2-13 p,y, 1
l TABLE 2.2-1 Ag, VALUES FOR TE ADULT l
(MtEM/HR PER MICRO-CI/M.)
Note: Nuclides not listed in this table are assigned a value of zero.
l Nuclide Bone Liver T. Body Thyroid Kidney M GI-LLI H 3 0.00E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 C 14 1.45E 04 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 NA 24 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 P 32 1.67E 07 1.04E 06 6.45E 05 0.00E-01 0.00E-01 0.00E-01 1.89E 06 CR 51 0.00E-01 0.00E-01 5.58E 00 3.34E 00 1.23E 00 7.40E 00 1.40E 03 MN 54 0.00E-01 7.06E 03 1.35E 03 0.00E-01 2.10E 03 0.00E-01 2.16E 04 MN 56 0.00E-01 1.78E 02 3.15E 01 0.00E-01 2.26E 02 0.00E-01 5.67E 03 FE 55 5.11E 04 3.53E 04 8.23E 03 0.00E-01 0.00E-01 1.97E 04 2.03E 04 FE 59 8.06E 04 1.90E 05 7.27E 04 0.00E-01 0.00E-01 5.30E 04 6.32E 05 C0 57 0.00E-01 1.42E 02 2.36E 02 0.00E-01 0.00E-01 0.00E-01 3.59E 03 l CO 58 0.00E-01 6.03E 02 1.35E 03 0.00E-01 0.00E-01 0.00E-01 1.22E 04 CO 60 0.00E-01 1.73E 03 3.82E 03 0.00E-01 0.00E-01 0.00E-01 3.25E 04 NI 63 4.96E 04 3.44E 03 1.67E 03 0.00E-01 0.00E-01 0.00E-01 7.10E 02 NI 65 2.02E 02 2.62E 01 1.20E 01 0.00E-01 0.00E-01 0.00E-01 6.65E 02 CU 64 0.00E-01 2.14E 02 1.01E 02 0.00E-01 5.40E 02 0.00E-01 1.83E 04 ZN 65 1.61E 05 5.13E 05 2.32E 05 0.00E-01 3.43E 05 0.00E-01 3.23E 05 ZN 69 3.43E 02 6.56E 02 4.56E 01 0.00E-01 4.26E 02 0.00E-01 9.85E 01 8R 83 0.00E-01 0.00E-01 7.25E-02 0.00E-01 0.00E-01 0.00E-01 1.04E-01 BR 84 0.00E-01 0.00E-01 9.39E-02 0.00E-01 0.00E-01 0.00E-01 7.37E-07 BR 85 0.00E-01 0.00E-01 3.86E-03 0.00E-01 0.00E-01 0.00E-01 1.80E-18 RB 86 0.00E-01 6.24E 02 2.91E 02 0.00E-01 0.00E-01 0.00E-01 1.23E 02 RB 88 0.00E-01 1.79E 00 9.49E-01 0.00E-01 0.00E-01 0.00E-01 2.47E 11 RD 89 0.00E-01 1.19E 00 8.34E-01 0.00E-01 0.00E-01 0.00E-01 6.89E-14 SR 89 4.99E 03 0.00E-01 1.43E 02 0.00E-01 0.00E-01 0.00E-01 8.00E 02 SR 90 1.23E 05 0.00E-01 3.01E 04 0.00E-01 0.00E-01 0.00E-01 3.55E 03 SR 91 9.18E 01 0.00E-01 3.71E 00 0.00E-01 0.00E-01 0.00E-01 4.37E 02 SR 92 3.48E 01 0.00E-01 1.51E 00 0.00E-01 0.00E-01 0.00E-01 6.90E 02 Y 90 6.06E 00 0.00E-01 1. 63E-01 0.00E-01 0.00E-01 0.00E-01 6.42E 04 Y 91M 5.73E-02 0.00E-01 2.22E-03 0.00E-01 0.00E-01 0.00E-01 1.68E-01 Y 91 8.88E 01 0.00E-01 2.37E 00 0.00E-01 0.00E-01 0.00E-01 4.89E 04 Y 92 5.32E-01 0.00E-01 1.56E-02 0.00E-01 0.00E-01 0.00E-01 9.32E 03 Y 93 1.69E 00 0.00E-01 4.66E-02 0.00E-01 0.00E-01 0.00E-01 5.35E 04 ZR 95 1.59E 01 5.11E 00 3.46E 00 0.00E-01 8.02E 00 0.00E-01 1.62E 04 00CM (BSEP) 2-14 Rev. 1
i TABLE 2.2-1 (continued)
Iluclide tone Liver T. Body Thyroid Kidney ,L_ung, GI-LLI ZR 97 8.81E-01 1.78E-01 8.13E-02 0.00E-01 2.68E-01 0.00E-01 5.51E 04 NB 95 4.47E 02 2.49E 02 1.34E 0? 0.00E-01 2.46E 02 0.00E-01 1.51E 06 MD 99 0.00E-01 1.28E 02 2.43E 01 0.00E-01 2.89E 02 0.00E-01 2.96E 02 TC 99M 1.30E-02 3.66E-02 4.66E-01 0.00E-01 5.56E-01 1.79E-02 2.17E 01 i TC 101 1.33E-02 1.92E-02 1.88E-01 0.00E-01 3.4 6E-01 9.81E-03 5.77E-14 RU 103 1.07E 02 0.00E-01 4.60E 01 0.00E-01 4.07E 02 0.00E-01 1.25E 04 RU 105 8.89E 00 0.00E-01 3.51E 00 0.00E-01 1.15E 02 0.00E-01 5.44E 03 RU 106 1.59E 03 0.00E-01 2.01E 02 0.00E-01 3.06E 03 0.00E-01 1.03E 05 AG 110M 1.56E 03 1.45E 03 8.60E 02 0.00E-01 2.85E 03 0.00E-01 5.91E 05 TE 125M 2.17E 02 7.86E 01 2.91E 01 6.52E 01 8.82E 02 0.00E-01 8.66E 02 TE 127M 5.48E 02 1.96E 02 6.68E 01 1.40E 02 2.23E 03 0.00E-01 1.84E 03 TE 127 8.90E 00 3.20E 00 1.93E 00 6.60E 00 3.63E 01 0.00E-01 7.03E 02 TE 129M 9.31E 02 3.47E 02 1.47E 02 3.20E 02 3.89E 03 0.00E-01 4.69E 03 TE 129 2.54E 00 9.55E-01 6.19E-01 1.95E 00 1.07E 01 0.00E-01 1.92E 00 TE 131M 1.40E 02 6.85E 01 4
5.71E 01 1.08E 02 6.94E 02 0.00E-01 6.80E 03 TE 131 1.59E 00 6.66E-01 5.03E-01 1.31E 00 6.99E 00 0.00E-01 2.26E-01 TE 132 2.04E 02 1.32E 02 1.24E 02 1.46E 02 1.27E 03 0.00E-01 6.24E 03 1 130 3.96E 01 1.17E 02 4.61E 01 9.91E 03 1.82E 02 0.00E-01 1.01E 02 I 131 2.18E 02 3.12E 02 1.79E 02 1.02E 05 5.35E 02 0.00E-01 8.23E 01 1 132 1.06E 01 2.85E 01 9.96E 00 9.96E 02 4.54E 01 0.00E-01 5.35E 00 1 133 7.45E 01 1.30E 02 3.95E 01 1.90E 04 2.26E 02 0.00E-01 1.16E 02 1 134 5.56E 00 1.51E 01 5.40E 00 2.62E 02 2.40E 01 0.00E-01 1.32E-02 1 135 2.32E 01 6.08E 01 2.24E 01 4.01E 03 9.75E 01 0.00E-01 6.87E 01 CS 134 6.84E 03 1.63E 04 1.33E 04 0.00E-01 5.27E 03 1.75E 03 2.85E 02 CS 136 7.16E 02 2.83E 03 2.04E'03 0.00E-01 1.57E 03 2.16E 02 3.21E 02 CS 137 8.77E 03 1.20E 04 7.85E 03 0.00E-01 4.07E 03 1.35E 03 2.32E 02 CS 138 6.07E 00 1.20E 01 5.94E 00 0.00E-01 8.81E 00 8.70E-01 5.12E-05 8A 139 7.85E 00 5.59E-03 2.30E-01 0.00E-01 5.23E-03 3.17E-03 1.39E 01 8A 140 1.64E 03 2.06E 00 1.08E 02 0.00E-01 7.02E-01 1.18E 00 3.38E 03
, 8A 141 3.81E 00 2.88E-03 1.29E-01 0.00E-01 2. 68E-03 1.63E 03 1.80E-09 8A 142 1.72E 00 1.77E-03 1.08E-01 0.00E-01 1.50E-03 1.00E-03 2.43E-18 LA 140 1.57E 00 7.94E-01 2.10E-01 0.00E-01 0.00E-01 0.00E-01 5.83E 04 LA 142 8.06E-02 3.67E-02 9.13E-03 0.00E-01 0.00E-01 0.00E-01 2.68E 02 CE 141 3.43E 00 2.32E 00 2. 63E-01 0.00E-01 1.08E 00 0.00E-01 8.86E 03 CE 143 6.04E-01 4.46E 02 4.94E-02 0.00E-01 1.97E-01 0.00E-01 1.67E 04 CE 144 1.79E 02 7.47E 01 9.59E 00 0.00E-01 4.43E 01 0.00E-01 6.04E 04 PR 143 5.79E 00 2.32E 00 2.87E-01 0.00E-01 1.34E 00 0.00E-01 2.54E 04 ODCM (BSEP) 2-15 Rev. 1
I TABLE 2.2-1 (continued)
Huclide Bone Liver T. Body Thyroid Kidney M GI-LLI PR 144 1.90E-02 7.87E-03 9. 64E-04 0.00E-01 4.44E-03 0.00E-01 2.73E-09 ND 147 3.96E 00 4.58E 00 2.74E-01 0.00E-01 2.68E 00 0.00E-01 2.20E 04 W 187 9.16E 00 7.66E 00 2.68E 00 0.00E-01 0.00E-01 0.00E-01 2.51E 03
, NP 239 3.53E-02 3.47E-03 1.91E-03 0.00E-01 1.08E-02 0.00E-01 7.11E02l F 18 6.66E 00 0.00E-01 7.38E-01 0.00E-01 0.00E-01 0.00E-01 1.97E-01 S8 124 2.76E 02 5.22E 00 1.09E 02 6. 70E-01 0.00E-01 2.15E 02 7.84E 03 1
l J
4 i
.-w -----we - - -wv
3.0 GASE0US EFFLUENTS 1
3.1 MONITOR ALARM SETPOINT DETERMINATION l
- This procedure determines the monitor alarm setpoint that indicates if the j dose rate in : the unrestricted areas due to noble gas radionuclides in the j gaseous effluent released from the site to areas at and beyond the site l boundary exceeds 500 arem/ year to the whole body or exceeds 3000 mrem / year to l the skin.
l If two -simultaneous gaseous releases out of one vent occur, calculate the
) setpoint for each type of release and use the lowest setpoint obtained.
i i
! 3.1.1 Setpoint Based on Conservative Radionuclide Mix (Ground and Mixed 1
! Mode Releases) i j The following method applies to gaseous releases via the Units 1 and 2 Turbine
] Building Vents and via the Units 1 and 2 Reactor Building Vents when j determining the high alarm setpoint for the Turbine Building Vent Gas Monitors
{ and Reactor Building Vent Gas Monitors.
3.1.1.1 Detemine the " mix" (noble gas radi.onuclide composition) of the l gaseous effluent (the " mix" can be determined from actual data or by '
using GALE code results of Table 3.1-1):
{
l l a. Detemine the gaseous source terms that are representative of the
" mix" of the gaseous effluent. Gaseous source terms are the noble gas activities in the effluent.
! Gaseous source terms can be obtained from:
, Table 3.1-1; Turbine Butiding Vent Release Table 3.1-1; Reactor Building Vent Release i b. Detemine Si (the fraction of the total noble gas radioactivity i in the gaseous effluent comprised by noble gas radionuclide 1)
) for each individual noble gas radionuclide in the ganeous effluent.
j 00CM (BSEP) 3-1 Rev. 1 1
I Ag !
Sj =
ggj (3.1-1) j i
Aj .= The radioactivity of noble gas radionuclide i in the gaseous effluent from Table 3.1-1, Turbine Building Vent Release; Table 3.1-1, Reactor Building Vent Release; or from analysis of gaseous effluent
+
3.1.1.2 Detemine the Qt (the maximum acceptable total release rate of all
. noble gas radionuclides in the gaseous effluent [pCi/Sec]) based upon t
the whole body exposure limit.
500 1
Qt
= (3.1-2)
(x/Q) r(K S T i\ i 1/
( W tb = The highest calculated annual average relative concentration of effluents released via the Turbine Building Vent for any area at or beyond the site boundary for all sectors (sec/m3) from Table A-1, Appendix A
=
7.60 E-6 sec/m3
@ rb = The highest calculated annual average relative concentration of effluents released via the Reactbr Building Vent for any area at or beyond the site boundary for all sectors (sec/m 3) from Table A-7, Appendix A
= 1.72 E-7 sec/m 3 NOTE: Use the x/Q that applies to the monitor for which the alarm setpoint is being calculated.
00CM (BSEP) 3-2 Rev. 1
4 Kj = The total whole body dose factor due to gamma emissions from noble gas radionuclide 1 (mrem /
year /pCi/m3 ) from Table 3.1-2 3.1.1.3 Determine Qt based upon the skin exposure limit.
3000 Qt (xfg) g -(L + 1.1 M )S '
i .1 i 1 L1+1.1Mg = The total skin dose factor due to emissions from noble gas radionuclide 1 (mrem / year /pC1/m3) from Table 3.1-2 1
3.1.1.4 Determine Ct (the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the gaseous effluent
[pCi/sec/cfm]).
Ot Ct 7 (3.1-4)
NOTE:
Use the lower of the Qt values obtained in Sections 3.1.1.2 and 3.1.1.3.
f = The maximum acceptable effluent flow rate at tha point of release (cfm) based on design flow rates
= 15,000 cfm (Turbine Building Vent)
= 172,800 cfm (Reactor Building Vent) 3.1.1.5 Determine the monitor high alarm setpoint above background:
- a. Detemine CR (the calculated monitor count rate above background attributed to the noble gas radionuclides [ net cpm]).
1 00CM (BSEP) 3-3 Rev. O
,, = - ,
5 CR '= (3.1-5)
Em = The detection efficiency of the monitor for the
" mix" of noble gas radionuclides in the gaseous effluent (pCi/sec/cfm cpm) from E8RC files
- b. Detennine HSP (the monitor high alarm setpoint with background
[ cpm]).
=
HSP Tm CR + Bkg (3.1-6)
= Fraction of the radioactivity from the site that Tm may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways
= 0.10 for the Unit 1 Turbine Building Vent Gas Monitor l
= 0.10 for the Unit 2 Turbine Building Vent Gas Monitor
= 0.20 for the Unit 1 Reactor Building Vent Gas Monitor
= 0.20 for the Unit 2 Reactor Building Vent. Gas Monitor l Bkg = The background count rate (cpm) due to internal contamination and the radiation levels in the area I l
in which the monitor is installed when the detector sample chamber is filled with uncontaminated air
- c. The monitor high alarm setpoint including background (cpm) shall be set at or below the HSP value determined above.
3.1.2- Setpoint Based on Conservative Radionuclide Mix (Long-Tem Elevated Release)
- The following method applies to gaseous releases via the stack when deter-mining the high-high alarm setpoint for the Stack Monitor during continuous l )
release via the stack. ,
l 3.1.2.1 Determine the " mix" (noble gases and composition) of the gaseous effluent:
- a. Detemine the gaseous source tems that are representative of the
" mix" of the gaseous effluent. Gaseous. source terms are the noble gases radionuclide activity concentrations in the effluent.
- b. Determine Sj (the fraction of the total radioactivity in the i gaseous effluent comprised by noble gas radionuclide 1) for each individual noble gas radionuclide in the gaseous effluent.
Aj
=
- Si 3 3 (3.1-7) i Aj = The radioactivity of noble gas radionuclide i in the gaseous effluent from the Stack Table 3.1-1 or i from analysis of the gaseous effluent being released 4
3.1.2.2 Determine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent [pC1/sec]) based upon the whole body exposure limit.
500 Qt g -y3 - .(3.1-8) i _i1 V
i = The constant for noble gas radionuclide i accounting for the gama radiation from the elevated finite plume (mrem / year /pCi/sec) from Table 3.1-2 ODCM (BSEP) 3-5: Rev. 1
l l
3.1.2.3 Determine Qt based upon the skin exposure limit.
3000 Ot
- g -(L (x/Q) + 1.1 B )S '
1 1 s i 1.
Li(x/Q)s + 1.1 Bt = The total skin dose constant for long-term releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) due to emissions from noble gas radionuclide 1 (mrem / year /pC1/sec) from Table 3.1-2 3.1.2.4 Determine Ct (the total maximum acceptable radioactivity con-centration of noble gas radionuclides in the gaseous effluent
[pCi/sec/cfm]).
=
Ct (3.1-10)
NOTE: Use the lowest of the Qt values obtained in Sections 3.1.2.2 and 3.1.2.3.
f = The maximum acceptable effuent flow rate at the point of release (cfm) based on design flow rates
= 86,000 cfm (stack) 1 3.1.2.5 Determine the monitor high-high alarm setpoint above backgrou'nd:
- a. Determine the CR (the calculated monitor count rate above background attributed to the noble gas radionuclides [ net cps]).
C
= t CR E
(3.1-11) m ODCM (BSEP) 3-6 Rev. 1
Em = The detection efficiency of the monitor for the
" mix" of noble gas radionuclides in the gaseous effluent (pCi/sec/cfm cps) from ESRC files
- b. Determine HHSP (the monitor high-high alam setpoint with '
background [ cps]).
HHSP = Tm CR + Bkg (3.1-12)
Tm
= Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways
= 0.40 for the Stack Monitor l Bkg = The background ' count rate (cps) 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 uncontaminated air
- c. The monitor high-high alarm setpoint including background (cps) shall be set at or below the HHSP value detemined above.
3.1.3 Condenser Air Ejector Monitor Alam Setpoint Determination This procedure determines the alarm setpoint for the Condenser Air Ejector Monitor that will provide reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10CFR100 in the event of an inadvertent release via the condenser air ejector.
00CM (BSEP) 3-7 Rev. 1 l
3.1.3.1 The following method applies to gaseous releases via the Units 1 and 2 condenser air ejectors when determining the maximum allowable alarm setpoint for the Condenser Off-gas Radiation Monitors.
- a. Determine Q, the allowable release rate (pCi/sec) at the air l
ejector for the noble gas radionuclides.
Specification 3.11.2.7 limits the gross radioactivity rate of l noble gases measured at the main condenser air ejector to less than or equal to 243,600 pCi/sec (after 30 minutes' decay).
Assume that the noble gas concentrations at the air ejector (t = 0) are representative of the GALE code. Since the holdup time between the air ejector and the stack (down the 30 minute holdup line) can vary due to operational conditions, the mix of the noble gases at the stack should be determined based on the actual decay time not to exceed 30 minutes. This mix can then be applied to the 243,600 pC1/sec limit and then back calculated to determine the allowable release rate at the air ejector, Q. As an example, assume that the holdup time -is 30 minutes. The mix of the noble gases after 30 minutes' decay (t = 30 minutes) can be determined by the following table.
GAlf Code Fraction Steen (pC1/p) Steam (pC1/gn) pC1/Sec* e-At pC1/sec of Mix itselide t=0 t=0 t=0 t = 30m t = 3Qn t=3Qn for 3400 pelt for 2436 pett Kr-83m 9.1E-4 6.5E-4 8.58E+2 8.3E-1 7.1E+2 2.9E-2 Kr-85m 1. E-3 1.1E-3 1.45E+3 9.2E-1 1.3E+3 5.3E-2 Kr-85 5.0E-6 3.E-6 4.75E+0 1.0E+0 4.8E+0 2.0E-4 Kr-87 5.5E-3 3.9E-3 5.15E+3 7.E-1 3.9E+3 1.E-1 Kr-88 5.5E-3 3.9E-3 5.15E+3 8.8E-1 4.5E+3 1.8E-1 Kr-89 3.4E-2 2.4E-2 3.17E+4 1.5E-3 4.7E+1 1.9E-3 Kr-90 7.5E-2 5.4E-2 7.13E+4 3.8E-17 2.7E-12 1.1E-16 Xe-131m 3.9E-6 2.8E-6 3.70E+0 1.0E+0 3.7E+0 1.5E-4 Xe-133m 7.5E-5 5.4E-5 7.13E+1 9.9E-1 7.0E+1 2.8E-3 Xe-133 2.1E-3 1.5E-3 1.98E+3 1.0E+0 2.0E+3 8.1E-2 Xe-135m 7.0E-3 5.0E-3 6.60E+3 2.E-1 1.7E+3 6.9E-2 Xe-135 6.0E-3 4.3E-3 5.68E+3 9.E-1 5.4E+3 2.2E-1 Xe-137 3.9E-2 2.8E-2 '3.70E+4 4.2E-3 1. E+2 6.5E-3 Xe-138 2.3E-2 1. E-2 2.11E+4 2.3E-1 2.0E-1
_4_.8E+3 TOTAL 2.4E+4 1.0E+0
- Steam Flow = (10,470,524 Ibs h, ) (0.1260 c) 7 = 1.32E+6 h Applying this mix to 243,600 pCi/sec (after 30 minutes' delay) and back calculating to t = 0 will yield the allowable pCi/sec per noble gases at the air ejectors; i.e.:
)
i l
1 l
Fraction Tech Spec Tech Spec of Mix (pC1/sec) e-At (pct /sec) ;
Nuclide t=30 min t=30 min t=30 min t=0 i
Kr-83m 2.9E-2 7.06E+3 8.3E-1 8.51E+3 Kr-85m 5.3E-2 1.29E+4 9.2E-1 1.40E+4 Kr-85 2.0E-4 4.87E+1 1.0E+0 4.87E+1 Kr-87 1.6E-1 3.90E+4 7.6E-1 5.13E+4 Kr-88 1.8E-1 4.38E+4 8.8E-1 4.98E+4 Kr-89 1.9E-3 4.63E+2 1.5E-3 3.09E+5 Kr-90 1.1E-16 2.68E-11 3.8E-17 7.05E+5 Xe-131m ^1.5E-4 3.65E+1 1.0E+0 3.65E+1 Xe-133m 2.8E-3 6.82E+2 9.9E-1 6.89E+2 Xe-133 8.1E-2 1.97E+4 1.0E+0 1.97E+4 Xe-135m 6.9E-2 1.68E+4 2.6E-1 6.46E+4 Xe-133 2.2E-1 5.36E+4 9.6E-1 5.58E+4 Xe-137 6.5E-3 1.58E+3 4.2E-3 3.76E+5 Xe-138 2.0E-1 4.87E+4 2.3E-1 2.12E+5 TOTALS 1.0E+0 2.44E+5 1.87E+6 Therefore:
Q = 1.87E+6 Ci/sec (for 30 minutes' holdup) l
- b. Detemine Cm (the total radioactivity concentration of noble gases) in the condenser air ejector gas (pCi/sec/scfm).
Cm
= (Eq. 3.1-13)
= the allowable release rate (pCi/sec) at the air Q
ejector for noble gases f = the main condenser air inleakage rate plus the radiolytic gas flow rate f
'l
- c. Determine the monitor high-high alarm setpoint above background.
(1) Determine MR [the calculated monitor response attributed to the noble gas radionuclides (mR/hr)].
(Eq. 3.1-14)
MR =
[C m
E = The detection efficiency of the monitor for m
the " mix" of noble gas radionuclides in the i
- gaseous stream [(pCi/sec)/(mR/hr
- cfm)] from EARC files (2) The monitor high-high alarm setpoint (mR/hr) should be set at or below the MR value determined above.
3 i
i
- l -
i l
Rev. 1
3.1.4 Condenser Off-Gas Treatment System (A0G) Monitor Alarm Setpoint Determination This method detennines the monitor alarm setpoint that includes sufficient [
noble gas activity to cause an alarm at the stack effluent noble gas monitor. I 3.1.4.1 Detennine Qt (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent [ Ci/sec]) based upon the whole body exposure (see equation 3.1-8) and skin exposure (see equation 3.1-9)
Note: Use the lowest of the Qt values obtained.
3.1.4.2 Determine Qs (the site adjusted maximum release rate [pCi/sec] for effluent releases via the stack).
Qs
=
QtxTm (Eq. 3.1-15)
Tm
= Fraction of radioactivity from the site that may be released via the stack to ensure that the site boundary limit is not exceeded during simultaneous releases from several pathways.
= 0.4 for the stack monitor.
3.1.4.3 Determine HSP (high alarm setpoint in Ci/cc)
HSP =
Qs + f (Eq. 3.1-16) i f = Maximum design flow rate of the A0G System
=
70800 cc/sec (150 cfm) 3.1.4.4 The monitor high alam setpoint shal". be set at or below the HSP value determined above.
TABLE 3.1-1 GASEOUS SOURCE TERMSI Turbine Bldg Vent Reactor Bldg Vent Stack Radionuclide Ai (Ci/yr) St Ai (Ci/yr) St Ai (Ci/yr) St Kr-83m *
- 3.0E+4 2.86E-2 Kr-85m 6.8E+1 2.02E-2 6.0E0 1.73E-2 5.8E+4 5.52E-2 Kr-85 *
- 2.0E+2 1.90E-4 Kr-87 1.3E+2 3.87E-2 6.0E0 1.73E-2 1.7E+5 1.62E-1 Kr-88 2.3E+2 6.85E-2 6.0E0 1.73E-2 1.9E+5 1.81E-1 Kr-89 *
- 2.0E+3 1.90E-3 Xe-131m *
- 1.6E+2 1.52E-4 Xe-133m *
- 3.0E+3 2.86E-3 Xe-133 2.5E+2 7.44E-2 1.3E+2 3.75E-1 8.6E+4 8.19E-2 Xe-135m 6.5E+2 1.93E-1 9.2E+1 2.65E-1 7.4E+3 7.05E-3 Xe-135 6.3E+2 1.88E-1 6.8E+1 1.%E-1 2.3E+5 2.19E-1 Xe-137 *
- 6.8E+3 6.48E-3 Xe-138 1.4E+3 4.17E-1 1.4E+1 4.03E-2 2.7E+5 2.57E-1 Ar-41 *
- 2.5E+1 7.20E-2 Total 3.36E+3 3.47E+2 1.05E+6
- <1.0E-1 1
Source tenns are based upon GALE code and not actual releases.
l 1
TABLE 3.1-2 DDSE FACTURS A10 CDNSTANTS
?
Total Bo @ Total Skin Dose Total leiole Bo@ Total Skin Dose Constant For Constant for Dose Factor Dose Factor Long-Tem Releases Long-Tem Releases (Kg) (Lj + 1.1 Mg) (Vj) (Lj(X/Q)s + 1.181 )
Radionuclide (aren/yr/pci/m ) 3 (aren/yr/ pct /m3 ) (aren/yr/pci/sec) (unm/yr/pci/sec)
Kr-83m 7.56E-2 2.12E+1 1.66E-9 1.54E-7 Kr-85m 1.17E+3 2.81E+3 9.18E-5 2.14E-4 Kr-85 1.61E+1 1.36E+3 1.36E-6 6.12E-5 Kr-87 5.92E+3 1.65E+4 4.17E-4 1.12E-3 Kr-88 1.47E+4 1.91E+4 1.08E-3 1.89E-3 Kr-89 1.66E+4 2.91E+4 6.55E-4 1.53E-3 Xe-131m 9.15E+1 6.48E+2 2.17E-5 5.84E-5 Xe-133m 2.51E+2 1.35E+3 1.64E-5 7.30E-5 Xe-133 2.94E+2 6.94E+2 1.72E-5 4.28E-5 Xe-135m 3.12E+3 4.41E+3 2.17E-4 3.93E-4 Xe-135 1.81E+3 3.97E+3 1.47E-4 3.25E-4 Xe-137 1.42E+3 1.39E+4 5.64E-4 6.30E-4 Xe-138 8.83E+3 1.43E44 6.61E-4 1.27E-3 Ar-41 8.84E+3 1.29E+4 7.86E-4 1.42E-3 00CM (BSEP) 3-14 Rev. 1 i _
3.2 COMPLIANCE WITH 10CFR20 (GASEOUS) 3.2.1 Noble Gases 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 actually be met. Therefore, the following methodology has been prov'idad 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 NUREG 0133, the following are used to show compliance with 10CFR20.
Ej VgQj + Kj (x/Q)y Qj <500 mrem /yr (3.2-1)
_ s v.
Ij[j Lg(iM)s+1.1Bj t
Qg + (L g+ 1.1 Mg ) (i M) , Q4 Q 3000 mWyr (3.2-2) t _
s v i where:
Ki = The total body dose factor due to gamma emissions for noble gas radionuclide 1, mrem / year per pCi/m3 Li =
The skin dose factor due to beta emissions for noble gas radionuclide i, mrem / year per pCi/m3 Mi
= The air dose factor due to gamma emissions for noble gas radionuclide 1, mrad / year per C1/m3 <
Vi = The constant for 'each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume mrem / year per pC1/sec .
00CM (BSEP) 3-15 Rev. 1 I _ . _ . _ . _ . .
i 1
Bj = The constant for long-term releases (greater than l 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume in mrad / year per pCi/sec 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem / mrad
= .The release rate of noble gas radionuclide i in Qj s
gaseous effluents from free-standing stack, pC1/sec 4
4 The release rate of noble gas radionuclide i in
=
Qj v
gaseous effluents from all vent releases, pCi/sec At the Brunswick Steam Electric Plant (BSEP) gaseous releases may occur from:
- 1. The turbine building vent
- 2. The reactor building vent
- 3. The stack Releases from the turbine building are ground level. The sources of these
^
releases are steam leakage through valve stems, pump seal s, and flanged connections. Releases from the reactor building are considered mixed mode in nature, and the source .is also leakage through valve stems, _ pump seals, and flanged connections. Releases from the stack.are considered elevated. _Their sources are the main condenser's steam jet air ejectors, radwaste building and A0G building . ventilation system exhausts, mechanical vacuum pump exhausts during start-up, and gland seal off-gases. .
l Noble gas releases may occur from all three points. To show compliance with 10CFR20, Expressions 3.2-1 and 3.2-2 are now in terms of the actual release points for BSEP.
00CM (BSEP) 16 Rev. 1 i
y y .-.m . - - _ - - - . , - . _ , . - - . . . . . . _ - - ,,
For the total body dose:
EjVjhg + EjKi (iN)rb i + IX/QItb i 300 mrem / year (3.2-3) s ,
rb tb, For the skin dose:
Ej Lj (iM)s+1.1 Bt Qi + E j Lj+ 1.1 Mg (iM)rb Qi + IINItb Qi .13000 mrem /yr
. . s . .- rt tb- (3.2-4) where:
hg = Release rate of radionuclide i from the stack, s
Ci/sec Qt
=
Release rate of radionuclide i from the two reactor rb buildings, pCi/sec Qt
=
Release rate of radionuclide i from the two turbine buildings, C1/sec (37Qls = Annual average relative concentration for releases from the stack, sec/m3 (iM)rb = Annual average relative concentration for releases from the reactor buildings, sec/m3 (iM)tb = Annual average relative concentration for releases from the turbine buildings, sec/m3 All other terms remain the same as those defined previously.
00CM (BSEP) 3-17 Rev. 1
The determination of controlling location for implementation of 10CFR20 for noble gases is a function of the radionuclide mix, the isotopic release rate, and the meteorology.
The incorporation of these variables into Expressions 3.2-3 and 3.2-4 result in the following expressions for the controlling locations for the BSEP. This location is the ENE site boundary.
For the total body:
Ig Yhg g
+EK'gj (7.2 x 10'8 hg + 4.2 x 10-6 hg ) <500 mrem /yr (3.2-5) s it tb For the skin:
Eg (6.3 x 10-9 L j+ 1.1 Bg) Q +E j (Lg + 1.1 jM ) (7.2 x 10-8 fj ,
s rb 4.2 x 10-6g k)' <
_3000 mrem /yr (3.2-6) tb -
The radionuclide mix was based upon source terms calculated using the NRC GALE code. They were calculated based upon the present operating mode of BSEP.
l They are presented in Table 3.2-1 as a function of release point. It should be noted, however, that the releases in Table 3.2-1 do not reflect the actual BSEP release data to date. The releases to date have been substantially less. This table was used as a calculational tool to determine the controlling location.
The x/Q values utilized in the equations for implementation of 10CFR20 are based upon the maximum long-term annual average (x/Q) in the unrestricted
~
area. Table 3.2-2 presents the distances from the reactor and turbine buildings to the nearest unrestricted area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and beef animal.
Table 3.2-3. presents the distances and directions from the stack to the same site boundaries of Table 3.2-2. Note that only distance has changed in relation to Table 3.2-2.
?
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. WQ values at the limiting site boundarf 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 FQvalues 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
! FQvalue may not decrease with distance; i.e., the site boundary may not have j the highest x/Q values. Therefore, long-tenn annual average x/Q values were calculated at the midpoint of the 10 standard distances as given in Table A-4 4
of Appendix A. The highest two or three 7Q 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 controlling location is at the ENE site boundary.
l Values for Kj, Lj, and Mj, which were. used in the determination of the controlling locations and which are to be used by BSEP in Expressions 3.2-5 l and 3.2-6 to show compliance with 10CFR20, are presented in Table 3.2-4.
These values originate from NUREG 0472, Revision 0, and were taken from Table l B-1 of the . NRC Regulatory Guide 1.109, Revision 1. The values have been l multiplied by 10 6 to convert microcuries to picocuries for use in Expressions 3.2-5 and 3.2-6.
i Values for Vi and Bi for the finite plume model can be expressed as shown in Equations 3.2 and 3.2-8. They were calculated at the site boundary of each of the 16 sectors using the NRC code RABFIN. Values for Vj and Bj for each of
- the 16 sectors are presented in Appendix B.
K I
jk A
li "a II Bj = rrr 3gi (3.2-7) r d oj I = The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (uj) and atmospheric stability class "k" for i a particular wind direction K = A numerical constant representing unit conversions :
3
" 16 sectors 260 mradsec(radians) (Mev) LC1) (m 1 (transformation)
- 2x radian 10 Ci
- 3.15 yr x 107 sec pCi
= 2.1 x 104 mrad (m3 ) (transformation)/ year (Mev)
(pCi) rd
= The distance from the release point to the receptor location, meters uj = The mean wind speed assigned to the jth wind speed class, meters /sec fjk = The joint frequency .of occurrence of the jth wind
- speed class and kth stability class (dimensionless) i
, Aj 1
= The number of photons of energy corresponding to the 1th energy group emitted per transformation of the ith radionuclide, number / transformation I-
! Ej = The energy assigned to the 1th energy group, Mev The energy absorption coefficient in air for photon pa =
energy E1 , meters-1 00CM (BSEP) 3-20 Rev. 1 l
I i
l J
The Vj factor is computed with conversion from air dose to tissue depth dose, thus; Vj = 1.1 (3.2-8)
E)E Ekl u where:
HT = The tissue energy absorption coefficient for photons of energy Ej, cm2/gm Td
= 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 Radiciodine and Particulates The dose rate in unrestricted areas resulting from the release of radiotodines and particulates with hal f-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.
Ej Pj (W3 hj + W y hg) < 1500 mrem /yr (3.2-9) s v -
where:
Pj =
Dose parameter for radiof odines and particulates with half-lives greater than 8 days based upon the critical crgan and the most restrictive age group
= mrem / year per pC1/m3 for inhalation pathways and for tritium ODCM (BSEP) 3-21 Rev. 1
= mrem / year per pCi/sec per m-2 for food and ground plane pathways 1 . 1
= The release rate of radionuclide i in gaseous I Qt s l effluents from free-standing stack, pCi/sec '
Qi
= The release rate of radionuclide i in gaseous effluents from all vents releases, pCi/sec Wy = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all vent releases 3
Wy = sec/m for the inhalation pathway Wy = meters-2 for the food and ground plane pathways W3 =
The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to stack releases W3 = sec/m3 for the inhalation pathway l
Ws = meters-2 for the food and ground plane pathways Radiciodines and particulates may be released from the stack, reactor
, buildings, and turbine buildings at BSEP. Radiofodines and particulates -may i also be released from decontamination operations .in the Hot Shop. Effluents from the Hot Shop roof vent -are combined with the turbine building's vent releases. To show compliance with 10CFR20, Expression 3.2-9 is now modified to incorporate the various release points for BSEP:
Ej Pj (W 3 hj+W 4 hj + We hj ) 11500 mrem /yr (3.2-10) s 6 2 where:
W 3
=. The annual average dispersion parameter for the stack Wrb
= The annual average dispersion parameter for the reactor buildings Wtb
Annual average dispersion parameter for the turbine buildings Qj
Release of radionuclide i from the two reactor rb buildings, pC1/sec hg =
Release of radionuclide i from the two turbine buildings,pCi/sec Qj = Release of radionuclide i from the stack, pC1/sec All other terms are the same as those defined previously.
In the calculation to show compliance with 10CFR20, only the inhalation, ground plane, cow milk, and goat milk pathways are considered for BSEP. In determining the dose at a particular location, W is a function of pathway.
For the food and ground plane pathways, W is in terms of D/Q (i.e.,
deposition). If the inhalation pathway is considered, W is in terms of x/Q.
Incorporation of the various pathways into Expression 3.2-10 results in the following:
i l
Ej Pj I
(x/Q)s 01 s
+
IX/Ob 01 2
+
IXNI@ Oi +E i (P j + Pj)
- m. G M (D M)s 01 + IIINI 01
+
IDN)2 01 <1500 mren/yr (3.2-11) s 2 m e_
where:
Pj = Dose parameter for radionuclide i for the inhalation pathway, mrem / year per C1/sec3 Pj = Dose parameter for radionuclide i for the ground plane pathway, mrem / year per pCi/sec per m-2
= Dose parameter for radionuclide i for either the Pj cow milk or goat milk pathway, mrem / year per pCi/sec per m-2 (x/Q)rb
= Annual average relative concentrations for releases from the reactor buildings, sec/m3 (x/Q) tb = Annual average relative concentration for releases from the turbine buildings, sec/m3
=
(x/Q)s Annual relative concentration for releases from the stack, sec/m3 I
(D/Q) rb = Annual average deposition for releases from the reactor buildings, m-2 (D/Q) tb = Annual average deposition for releases from the turbine buildings, m-2 l
(D/Q) $
= Annual average deposition for releases from the stack, m-2 t
In the case of tritium, the W parameter for the food pathway (cow or goat milk) is based upon x/Q. Since tritium is a weak beta emitter, the ground plane contribution is zero for tritium. Therefore, the left-hand side of Expression 3.2-10 can be written as the following:
For tritium:
b T
= (P T +P T I IINI s T+ IINI b n T+ IINI tb T (3.2-12)
I M .
s it tb.
where:
bT = Dose rate due to tritium releases, mrem / year Py = Dose parameter for tritium for the inhalation pathway, mrem / year per pCi/m3 PT DOSE Parameter for tritium for the milk pathway, mrem / year per Ci/m3 QT s Release rate of tritium from the stack, pCi/sec QTg
=
Release rate of tritium from the two reactor buildings, Ci/sec QT g
=
Release rate of tritium from the two turbine buildings,pCi/sec l
Since Pj for tritium equals 647 and Pj equals 2380, Equation 3.2-12 reduces to: '
i bT = 3.0 x 10 (x/Q)s T + IX/QI 6 + IX/0I 2 (3.2-13)
T T
, s 6 2.
To show compliance with 10CFR20, Expressions 3.2-11 and 3.2-13 are evaluated first at the limiting site boundary. It should be noted that the sum of the dose rates from radiolodines and particulates and from tritium must be summed and their combined dose rates less than 1500 mrem / year to show compliance with 10CFR20. If the 1500 mrem / year limit is exceeded at the limiting site boundary when all pathways are considered present at the site boundary but the inhalation pathway contributes less than 1500 mrem / year, then Expressions 3.2-11 and 3.2-13 are evaluated at the limiting real pathway location.
The limiting site boundary location is 0.91 miles NE. Expression 3.2-11 becomes:
For radiotodines and particulates:
IP gg (3.3 x 10-8 h g + 1.7 x 10-7 hg + 1.9 x 10-6j f) ,gj {pj,pj)
I s 6 2 G M (1.3x10-9hg+3.3x10-9hg +1.2x10-9hg ) <1500 mrem /yr (3.2-14) s rb tb For BSEP the limiting real pathway location is the cow milk pathway 0.79 miles SSE. At this location, Expression 3.2-11 becomes:
EgPg I
(1.0 x 10-8 hg + 6.8 x 104 hg + 7.0 x 10-6 f j ),
s rb tb gj (pj,pj)
G M (5.4 x 10-10 6 4 + 6.0 x 10-10 6 9 s 6
+ 1.4 x 10 4 6)24 11500 mrem /yr (3.2-15)
For tritium at the limiting site boundary Equation 3.2-13 becomes- l l
For tritium:
bT= 3.0 x 103 (3.3 x 10-8 6 + 1.7 x 10-7 h + 1.9 x 10-6 h ) (3.2-16)
At the limiting real pathway location Equation 3.2-13 becomes:
For tritium:
DT = 3.0 x 10 3 (1.0 x 10-8 h + 6.8 x 104 hT + 7.0 x 10-6 h) (3.2-17) s - rt> tb The determination of controlling location for implementation of 10CFR20 for radiotodines and particulates is a function of the same two parameters as for j noble gases plus a third, actual receptor pathway location. T' ' incorporation
- of these parameters into Expression 3.2-11 results in the respective
- expressions at the controlling locations. The radionuclide. mix was again based upon the source terms calculated using the GALE code. The mix and the i 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 D/Q values for each release point were utilized in
- conjunction with the radionuclide mix and the release rate for each release j point. At BSEP the combination of meteorology and release rate which dominates comes from the sta'ck.
l In the determination of actual receptor controlling location, the highest two j or three D/Q values from each release point to the pathway locations of Table j ,3.2-2 are utilized in conjunction with the radionuclide mix and release rate j for each release point. For BSEP the controlling location is the cow milk l pathway 0.79 miles SSE of the reactor building and turbine buildings.
[ Values for Pj were calculated for an infant for various radionuclides for the i
t inhalation, ground plane, cow milk, and goat milk pathways using the
- methodology of NUREG 0133. The.Pj values are presented in Table 3.2-5. The j values of Pj reflect, for each radionuclide, the maximum Pi value for any i organ for each individual pathway of exposure. Because, the goat milk pathway
) is not present at BSEP, the cow milk pathway Pi values were utilized in the
- determination of the various controlling locations. For the case of an infant
{ being present at the site boundary or at the real pathway location, the grou'nd i
plane pathway is not considered as a reasonable exposure pathway for the infant (i.e., Pg = 0). However, Pt values are presented in Table 3.2-5 for
, 00CM (BSEP) 3-27 Rev. 1 i
1
. - - , , - , - ,-,..n. .-.------,-n - - - . - - - - - - - - . - . - - , - - , - - - - - --
k completeness. Appendix C presents the methodology which was utilized in calculating Pj values.
Annual average I)T values at the special locations for the stack, reactor building, and turbine building release points, respectively, which were utilized in Expressions 3.2-14 through 3.2-17 were obtair.ed from the tables presented in Appendix A. The x/Q values in Expressions 3.2-14 through 3.2-17 were also obtained from the tables presented in Appendix A. D/Q values at the limiting site boundary location and the limiting real pathway location for releases from the turbine buildings, the reactor buildings, and the stack were obtained from Tables A-3, A-9, and A-15, respectively, of Appendix A. x/Q values at these same locations for these same release points were obtained j from Tables A-1, A-7, and A-13 of Appendix A. A description of the derivation of the x/Q and D/Q values is provided in Appendix A.
I 1
I i
i 1
s e
00CM (BSEP) 3-28 Rev. 1
i l
Table 3.2-1 RELEASES FROM BRUNSWICK STEAM ELECTRIC PLANT (C1/yr per unit)
Turbine Building Reactor Building Stack Isotope (Ground Level) (Mixed Mode) (Elevated)
Kr-83m -
0 0 3.0E4 Kr-85m 6.8E1 6.0 5.8E4 Kr-85 0 0 2.0E2 Kr-87 1.3E2 6.0 1.7E5 Kr-88 2.3E2 6.0 1.9E5 Kr-89 0 0 2.9E3 Xe-131m 0 0 1.6E2 Xe-133m 0 0 3.0E3 Xe-133 2.5E2 1.3E2 8.8E4 Xe-135m 6.5E2 9.2E1 7.4E3 Xe-135 6.3E2 6.8E1 2.3E5 Xe-137 0 0 7.9E3 Xe-138 1.4E3 1.4E1 2.7E5 Ar-41 0 2.5El 0 I-131 1.9E-2 3.4E-1 5.1 1-133 7.6E-2 1.4 2.1El Cr-51 1.3E-4 6.0E-4 9.0E-3 Mn-54 6.0E-6 6.0E-6 3.0E-2 Fe-59 5.0E-6 8.0E-4 1.5E-2 Co-58 6.0E-6 1.2E-3 4.5E-3 Co-60 2.0E-5 2.0E-2 9.0E-2 Zn-65 2.0E-6 4.0E-3 1.5E-3 Sr-89 6.0E-5 1.8E-4 4.5E-4 Sr-90 2.0E-7 1.0E-5 3.0E-4 Zr-95 1.0E-6 8.0E-4 5.0E-5 Sb-124 3.0E-6 4.0E-4 5.0E-5 Cs-134 3.0E-6 8.0E-3 4.5E-3 Cs-136 5.0E-7 6.0E-4 4.5E-4 Cs-137 6.0E-6 1.1E-2 9.0E-3 Ba-140 1.1E-4 8.0E-4 1.1E-4 Ce-141 6.0E-6 2.0E-4 2.6E-3 C-14 0 0 9.5 H-3 0 3.0E1 0
- Calculations based upon GALE code and not actual releases.
00CM (BSEP) 3-29 Rev. 1
TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS E ASURED FROM THE BRUNSWICK PLANT CENTER (Mi)
Site Milk Milk Meat Nearest Nearest Sector Boundary Cow Goat Animal Resident Garden NNE 0.64 - -
1.0 0.91 1.39 NE 0.91 - - - 2.24 -
ENE 0.64 - - - - -
E 0.68 - - -
0.94 -
ESE 0.68 - - - - -
SE 0.67 - -
0.79 0.82 0.94 SSE 0.74 0.79 -
0.80 0.79 -
S 1.04 - - -
1.48 1.57 SSW 0.96 - - -
1.44 1.44 SW 0.89 - -
1.70 0.89 1.04 WSW 0.74 - - -
1.00 1.00 W 0.69 - -
1.08 0.87 0.87 WNW 0.64 - - -
0.79 0.81 NW 0.70 - - -
0.80 5.00 NNW 0.64 - - -
0.85 0.97 N 0.64 - - -
0.88 0.G5 i
1 l
I 1
i I
! 1 1
00CM (BSEP) 3-30 Rev. 1 )
l TABLE 3.2-3 DISTANCE TO SITE BOUNDARIES BASED UPON BRUNSWICK PLANT CENTER AND DIRECTIONS FROM THE STACK Based on Center of From Stack to Site Boundaries Brunswick Plant of Table 3.2-2 Site Boundary Direction Distance (Mi) Direction Distance (Mi)
NNE 0.64 NNE 0.74 NE 0.91 NE 0.97 ENE 0.67 ENE 0.69 E 0.68 E 0.66 ESE 0.68 ESE 0.61 SE 0.67 SE 0.57 SSE 0.74 SSE 0.55 S 1.04 S 0.92 SSW 0.96 SSW 0.87 SW 0.89 SW 0.84 WSW 0.74 WSW 0.75 W 0.69 W 0.73 WNW 0.64 WNW 0.72 NW 0.70 NW 0.81 NNW 0.64 NNW 0.76 N 0.64 N 0.76 l
l l
TA8tE 3.2-4 I
DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- Total Body Skin Gamma Air Beta Air j Dose Factor Dose Factor Dose Factor Dose Factor Kg Lg Mg Ng (ares /yr (arem/yr (mrad /yr (arad/yr ,
Radionuclide per pC1/m3 ) per pC1/m3 ) per pC1/m3 ) per pCi/m3 ) l Kr-83m 7.56E-02** ---
1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- The listed dose factors are for radionuclides that may be detected in gaseous effluents.
- 7.56E-02 = 7.56 x 10-2,
't l
00CM (BSEP) 3-32 Rev. 1
Y TABLE 3.2-5 Pj VALUES FOR AN INFANT FOR THE I
BRUNSWICK STEAM ELECTRIC PLANT
- Isotope Inhalation Ground Plane Cow Milk Goat Milk H-3 6.47E2 0 2.38E3 4.86E3 P-32 2.03E6 0 1.60E11 1.93E11 Cr-51 1.28E4 6.67E6 4.79E6 5.65ES Mn-54 1.00E6 1.09E9 3.89E7 4.68E6 Fe-59 1.02E6 3.92E8 3.93E8 5.11E6 Co-58 7.77ES 5.29E8 6.06E7 7.28E6 Co-60 4.51E6 4.40E9 2.10E8 2.52E7 Zn-65 6.47E5 6.89E8 1.90E10 2.29E9 Rb-86 1.90E5 1.28E7 2.22E10 2.67E9 Sr 2.03E6 3.16E4 1.27E10 2.66E10 Sr-90 4.09E7 -
1.21E11 2.55E11 Y-91 2.45E6 1.52E6 5.26E6 6.32E5 Zr-95 1.75E6 3.48E8 8.28E5 9.95E4 Nb-95 4.79ES 1.95E8 2.06E8 2.48E7 Ru-103 5.52E5 1.55E8 1.05E5 1.27E4 Ru-106 1.16E7 2.99E8 .1.44E6 1.73E5 Ag-110m 3.67E6 3.14E9 1.46E10 1.75E9 Te-127m 1.31E6 1.18E5 1.04E9 1.24E8 Te-129m .
1.68E6 2.86E7 1.40E9 1.68E8 Cs-134 7.03E5 2.81E9 6.79E10 2.04E11 4
Cs-136 1.35E5 2.13E8 5.76E9 1.73E10
, Cs-137 6.12E5 1.15E9 6.02E10 1.81E11 Ba-140 1.60E6 2.94E7 2.41E8 2.89E7 Ce-141 5.17E5 1.98E7 1.37E7 1.65E6 Ce-144 9.84E6 5.84E7 1.33E8 1.60E7 I-131 1.48E7 2.46E7 1.06E12 1.27E12 I-132 1.69ES 1.78E6 1.39E2 1.64E2 I-133 3.56E6 3.54E6 9.80E9 1.18E10 I-135 6.96E5 3.67E6 2.27E7 2.68E7
- Units are arem/yr 3 mrem /yr per pCi/sec per m-ger pCi/m for the food andfor H-3 andplane ground the inhalation pathways. pathway and 1
- - , .-._ ,- ,-e - r
3.3 COMPLIANCE WITH 10CFR50 (GASEOUS) 3.3.1 Noble Gases 3.3.1.1 Cumulation of DosesSection II.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. Based upon NUREG 0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following expressions:
During any calendar quarter, for gama radiation:
3.17 x 10 Ej Mg (iiM),Qjy+(iM),qjy +BQj is + bj gis $5 mrad (3.3-1)
During any calendar quarter, for beta radiation:
3.17 x 10-8 EjNg (iiM),Qjy + (iM),q +jy(i7(T),Q + (3.3-2) is IIiI9I 9s 1s 510 mrad 1
During any calendar year, for gamma radiation:
3.17 x 10-8 E j< M j (iM)Qgy+(iM)gj + B Q + bj gis $10 mrad (3.3-3) 1 During any calendar year, for beta radiation:
3.17 x 10-8 EjNg (iM)yQjy + (if/q),qjy+(iM),Qis+I5NI9s 1s 5.20 mrad (3.3-4) 00CM (BSEP) 3-34 Rev. 1
I l
where:.
Mi
= The air dose factor due to gama emissions for each identified noble gas radionuclide 1, mrad / year per 4
pCi/m3 Ni
=
The air dose factor due to beta emissions for each identified noble gas radionuclide i, mrad / year per pCi/m3 (iM)y = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases (greater .than 500 hrs / year), sec/m3 (iM)v = The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year),
sec/m3 (iM)s = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term, free-standing stack releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), sec/m3 (iM)s = The relative concentration for areas at or beyond the unrestricted area boundary for short-term, free-standing stack releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> year), sec/m3 qis = The average release of noble gas radionuclide i in gaseous effluents for short-tem stack releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), Ci ODCM (BSEP) 3-35 Rev. 1
1 qiy = The average release of noble gas radionuclide i in gaseous effluents for short-term vent releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), pC1 Qis
= The average release of noble gas radionuclide i in gaseous effluents for long-term, free-standing stack releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), pCi Qiy = The average release of noble gas radionuclide i in i gaseous effluents for long-term vent releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), pCi Bj = The constant for long-term releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) for each identified noble gas radionuclide i accounting for the gamma radiation from the elevated finite plume, mrad / year per
'Ci/sec bj = The constant for short-term releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year) for each identified noble gas radionuclide i accounting- for the gamma radiation from the elevated finite plume, mrad / year per pCi/sec 3.17 x 10-8 =
The inverse of the number of seconds in a year For BSEP all releases are considered long-term. The incorporation of the stack, reactor building, and turbine building release points into Expressions 3.3-1 through 3.3-4 results in the following expressions for two units to show compliance with 10CFR50.
During any calendar quarter or year:
Gama radiation:
3.17 x 10 a l
)+ (i7tT)tb IO i +Of )
Ej lMj (i7(D4 (Qg + Qj + B 9 Qg' l . rb1 rb2 tb1 tb2 s l
<10 mrad (per quarter ) or 20 mrad (per year) (3.3-5)
Beta radiation:
3.17 x 10 Ej Ng (i7(D4 (Qj + Qj )+(i7tT)tb IOi tb1 +Of tb2 I+ X7!IIs1 0
rbi rb2 s
<20 mrad (per quarter) or 40 mrad (per year) (3.3-6) where:
i (i7(Drb = Annual average relative concentration for releases from the reactor building, sec/m3 (i7tT)tb = Annual average relative concentration for releases from the turbine building, sec/m3 (i7(Ds = Annual average relative concentration for releases from the stack, sec/m3 Qjrb1, Q I rb2
=
Release of radionuclide i from Reactor Buildings 1 and 2, respectively, pCi Qt , Qj =
Release of radionuclide i from Turbine Buildings 1 and 2, respectively, Ci Qj =
Release of radionuclide i from the stack, Ci At BSEP the limiting location for noble gases is 0.67 miles ENE. Substitution of the appropriate x/Q values into Expressions 3.3-5 and 3.3-6 results in the following:
4 00CM (BSEP) 3-37 Rev. 1
) - !.
__ _ _ _ _ ___ ~._ , _ ._.
During any calendar quarter or year:
Gamma radiation:
-6 3.17 x 10 I bM 7.2 x 10 -8 (Qj + Qg ) + 4.2 x 10 gg j .q j ) +BQ 49 gdj rb1 rb2 tb1 tb2 - s
< 10 mrad (per' quarter) or 20 mrad (per year) (3.3-7)
Beta radiation:
3.17 x 10-8 IjNg 7.2 x 10~0 (Qg + Qg ) + 4.2 x 10 -6 gg j ,
rbi rb2 tb1,9 j tb)2
-9 6.3 x 10 Q, 30 mrad (per quarter) or 40 mrad (per year) (3.3-8) i The determination of the controlling locations for implementation of 10CFR50
~
is a function of parameters such as radionucide mix, isotopic release, and meteorology.
1 The incorporation ' of these parameters into Expressions 3.3-1 through 3.3-4 resulted in the expressions for the controlling locations as presented in Expressions 3.3-7 and 3.3-8. The radionuclide mix was based upon source terms
- calculated using the NRC GALE Code and is presented in Table. 3.2-1 as a function of release point.
, The two or three highest site boundary WQ values for each release point were utilized in conjunction with the radionuclide mix and release for each release point to determine - the controlling site boundary location. Since mixed mode and elevated releases occur frcm 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/Q values were calculated at the midpoint of 10 standard distance intervals out to a distance of 5 miles. The two or three highest x/Q values for those distances, greater than the site boundary, were also considered in conjunction with the radionuclide mix and releases to determine the controlling location.
00CM (BSEP) 3-38 Rev. 1 4
-- , , _ . - - , . .,- ~ , - - - ,, , . - - -
l l
l In the determination of the controlling location, annual average T/Q values are utilized. These values are presented in tables in Appendix A. WQvalues 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 riix and meteorology dominates in the f'
determination of the controlling location. For BSEP the controlling release point is the stack.
Values for Mj and N{, which were used in the determination of the controlling 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 Regulatory Guide 1.109, Revision 1. The values have been multiplied by 10 6 to convert from picocuries 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 1 10 mrad (3.3-9)
Ds 1 20 mrad (3.3-10)
For the calendar year:
Dy 1 20 mrad (3.3-11)
DS 1 40 mrad (3.3-12) i <
where:
j Dy = The air dose from gamma radiation, mrad
.Ds = The air dose fra 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.
L 3.3.2 Radiciodines and Particulates 3.3.2.1 Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radiciodines and I
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 hal f-lives greater than 8 days. in gaseous effluents released to unrestricted areas, can be deternined by the following expression:
t i
During any calendar quarter or year:
i
-8 3.17 x 10 Ej Rg (Ws0s +
Ws 9fs + Wg iv + (3.3-13) 1 Wy14 v) 17.5 mrem (per quarter) or i15 mrem (per calendar year) 4 I
j- where:
Qsi = Release of radionuclide i for long-term, - free-standing stack releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), pCi Qyi = Release of radionuclide i for long-term vent releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), Ci qis = Release of radionuclide i for short-term, free-standing' stack releases (equal to or less than 500 I
hours / year), pCi qjy = Release of radionuclide i for short-term vent releases - (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year),
, pCi I
Ws = Dispersion parameter for estimating dose to an individual at the controlling location for long-tem, free-standing stack releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year)
= sec/m3 for the inhalation pathway and tritium
=- meters-2 for the food and ground plane pathway Wy = The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases (greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year)-
3
- = sec/m for the inhalation pathway and tritium
= meters-2 for the food and ground plane pathway
- ws = Dispersion parameter for estimating the dose to an individual at the controlling location for short-tem stack releases (equal to or less than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year)
E 00CM (BSEP) 3-41 Rev. 1
3
= sec/m for the inhalation pathway and tritium f
= meters-2 for the food and ground plane pathway
, wy = 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 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year)
=- sec/m 3 for the inhalation pathway and tritium
= meters-2 for the food and ground plane pathwy 3.17 x 10-8 = The inverse of the number of seconds in a year Rj = The dose factor for each identified radionuclide i of the organ of interest, mrem /yr per Ci/sec per m-2 or mrem /yr per pCi/m3 Radiotodines and particulates may be released from the stack, reactor buildings, and turbine buildings at BSEP. Radioiodines and particulates may also be released from decontamination operations in the Hop Shop. Effluents from the Hot Shop roof vent are combined with the turbine building's vent releases. 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 expression to show compliance with 10CFR50 for a particular organ:
-8 3.17 x 10 Ij R j W s O+W i 6 I0 f +Qi rb2 I+WeOi I +Qi tb2 I s rb1 tb1
<15.0 mrem (per quarter) or 30 mrem (per year) (3.3-14)
?
- 00CM (BSEP) 3-42 Rev. 1 l
2 where:
W s
= Dispersion parameter for releases from the stack Wrb
= Dispersion parameter for releases from the reactor bt.ilding Wtb
= Dispersior parameter for releases from the turbine building Qj,
= Release of radionuclide i from the stack, pCi ggrb1, Qg rb2
= Release of radionuclide i from reactor buildings 1 and 2, respectively, pCi QItb1, Qg tb2
= Release of radionuclide i from turbine buildings 1 and 2, respectively, pCi In determining the dose at a particular location, W (as in Section 3.2.2) is a function of the pathway. For the food and ground plane pathway, W is in terms
'of D/Q. If the inhalation pathway is considered, W is in terms of x/Q.
Incorporation of the various pathways into Expression 3.3-14 results in the following:
l 3.17 x 10-8 E 9 ;(R9+R9+R+R9)
G M 9
V B (57(T)s 01 s+ (U7(II4 IO i rbi *0 1 rb2 I i
+ O + + 0+
tb i tb1 I 22 , II s 1 s
'D (Qj +09 ) + @ tb IQ 1 +01 I rbi rb2 tb1 tb2
<15 mrem (per quarter) or 30 mrem (per year) (3.3-15) i t-i
1 where: l Rj = Dose factor for an organ for radionuclide i for the ground plane exposure pathway, mrem /yr per pC1/sec per m-2
= Dose factor for an organ for radionuclide i for R$
either the cow milk or goat milk pathway, mrem /yr per pCf/sec per m-2 Rj = Dose factor for an organ for radionuclide i for the vegetable pathway, mrem /yr per pC1/sec per m-2 RjB
= Dose factor for an organ for radionuclide i for the meat pathway. mrem /yr per pC1/sec per m-2 R$
= Dose factor for an organ for radionuclide i for the inhalation pathway, mrem /yr per pC1/m3 (T/ Orb = Annual average deposition for releases from the reactor buildings, m-2 4
(D/Q)tb = Annual average deposition for releases from the tu'rbine buildings, m-2 (TM)s = Annual average deposition for releases from the stack, m-2 As discussed in Section 3.2.2, for tritium the parameter W for the food pathway is based upon x/Q. The ground plane pathway is not appropriate for tritium. Therefore, the lef t-hand portion of Expression 3.3-15 may be *
, modified for tritium as:
I For tritium:
DT= 3.17 x 10-8 T (R + RT+RT+RT I IENI sQ+O2 T IO T +OT I M V B I s rb1 rb2
+ ) (3.3-16)
+ (iM)tb IQT OT tb1 tb2 where:
Dose resulting from tritium, mrem DT
= Dose factor for an organ for tritium for the slik RT pathway, mrem /yr per pCi/sec3
= Dose factor for an organ for tritium for the RT vegetable pathway, mrem /yr per pC1/m3 RT
= Dose factor for an organ for tritium for the beef pathway, mrem /yr per pC1/m3
= Dose factor for an organ for tritium for the RT
, inhalation pathway, mrem /yr per pC1/m3 QT
= Release of tritium from the stack, Ci s
QTg*Q T g
=
Release of tritium from Reactor Buildings 1 and 2, respectively, pCi QTm'QTg = Release of tritium from Turbine Buildings 1 and 2, respectively, pCi i 00CM (BSEP) 3-45 Rev. 1
, To show compliance with 10CFR50, Expression 3.3-15 is evaluated at the
' ~
. controlling pathway location. At BSEP the controlling location is a milk cow j 0.79 miles in the SSE sector. Expression 3.3-15 becomes:
-10 ,g ) ,
3.17 x 10 Ig (Rj G+ R9) 5.4 x 10-10 Qg + 6.0 x 10 gg
- M s rb1 rb2 1.4 x 10 ) + Ry 1.0 x 10 4 + 6.8 x 10-8 gg j +g j ) ,
4 (Q,tb1+Q,tb2 I Q
9 s rb1 rb2
~
7.0 x 10-0 (Qg +Q9 ) 115 mren (per quarter) or 30 mren (per year) tb1 tb2 (3.3-17) i i For tritium, Equation 3.3.-16 reduces to:
-8 -8 DT = 3.17 x 10-8 M(RT+RT) 1.0 x 10 Q + 6.8 x 10 gg ,g ) ,
I s rb1 rt2 4
7.0 x 10 (QT +OT ) (3.3-18) tb1 tb2 i
The detennination of a controlling location for implementation of 10CFR50 for l radiciodines and particulates is a function of:
(1) Radionuclide mix and isotopic release (2) Meteorology j (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Expression 3.3-14 results in the respective equations at the controlling location.
In the determination of the controlling location, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using l the GALE code. This mix was presented in Table 3.2-1 as a function of release point.
00CM (BSEP) 3-46 Rev. 1
i In the determination of the controlling location, all of the exposure pathways, as presented .in Table 3.2-2, were evaluated. These include cow milk, goat milk, beef and vegetable ingestion, and inhalation ground plane exposure.- An infant was assumed to be present at all milk pathway j locations. A child was assumed to be present at all vegetable garden and beef
- animal. locations. The ground plane exposure pathway was only considered to be present where an infant was not present. Naturally, inhalation was present everywhere an individual was present.
1
{
For the determination of the controlling location, the highest D/Q values for each release . point and release mode for the vegetable garden, cow milk, and goat milk pathways were selected. The thyroid dose was calculated at each of these locations using the radionuclide mix and releases of Table 3.2-1. Based upon these calculations, it was determined that the controlling receptor pathway is the cow milk-infant pathway. Since no infant child or teen are j consuming milk at the controlling pathway location (0.79 miles in the SSE
! sector), the compliance dose calculations are determined for the cow milk-
) adult pathway. The Ri value for each pathway is included in Expression 3.3-15 l in the event that the annual land use census should indicate that an infant, a child, a teen, or an adult is the critical receptor at the controlling locations (in which case the controlling receptor pathway will be changed).
i At BSEP, the controlling release point and mix is the stack.
I j Tables 3.3-1 through 3.3-19 present Ri values for the total body, GI tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, j inhalation, cow milk, goat milk, and vegetable and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the l pathways. These values were calculated using the methodology described in NUREG 0133 using a grazing period of eight months. A discussion of their calculation is presented in Appendix C. .
! In the determination 'of the controlling location annual averaged [Qand l x/Q values are utilized. D/Q values at the limiting real pathway locations for releases from the turbine buildings, reactor buildings, and the stack were obtained from Tables A-3, A-9, and . A-15, respectively, of Appendix A. x/Q 00CM (BSEP) 3-47 Rev. 1
values at the same location for these same release points were obtained from Tables A-1, A-7, and A-13 of Appendix A. A description of the derivation of the various x/Q and D/Q values is presented in Appendix A.
Long-tenn 0/Q values for the stack, reactor buildings, and turbine buildings are provided for the midpoints of the following distances:
0.0-0.5 mi. 0.5-1.0 mi. 1.0-1.5 mi. 1.5-2.0 mi.
2.0-2.5 mi. 2.5-3.0 mi. 3.0-3.5 mi. 3.5-4.0 mi.
4.0-4.5 mi. 4.5-5.0 mi.
These values appear in tables in Appendix A. They may be utilized if an 4
additional special location arises different from those presented in the special locations of Table 3.2-2.
j The following relationships should hold for BSEP to show compliance with BSEP Radiological Effluent Technical Specification 3.11.2.3.
For the calendar quarter: '
DT 1 15 mrem (3.3-19)
For the calendar year:
Dr 1 30 mrem (3.3-20) where:
Dt = The . dose to any organ t from radioiodines and particulates, mrem The quarterly limits given above represent one-hal f the annual design objective of Section II.C of Appendix I of 10CFR50. If any of the >11mits of l Expressions 3.3-19 or 3.3-20 are exceeded, a special report pursuant to Section IV.A of Appendix ! of 10CFR50 must be filed with the NRC.
3.3.2.2 Projection of Doses Dose projections for this section are required at least once per 31 days in Technical Specification 4.11.2.5.
The doses will be projected using Expressions 3.3-17. When the operational conditions are expected to be the same as for the current month, the source tenn inputs into the equation for the projection can be taken directly from the current month's data. Where possible, credit for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.
This may be accomplished by using projected reactor-days of operation. For example:
If Unit I had 28 reactor-days of operation and the dose to the bone was 0.05 mrem (remember there are 6 organs to consider) and Unit 2 was down at 0 reactor-days, then obtain from Planning & Scheduling the projected number of reactor-days for both Units 1 and 2 in the upcoming month. Suppose that the projected reactor-days for Unit 1 will be 10 reactor-days and for Unit 2, 21 reactor-days.- To calculate the projected dose "x":
28/2 + 0/2 , 10/2 + 21/2 0.05 x x = 0.06 mrem to the bone This projected dose to the bone is less than the 0.6 mrem dose limit to any organ. If the dose to the bone or. any other organ exceeds 0.6 mrem, the turbine building ventilation exhaust treatment system must be operational in the ensuing month. j i
l TABLE 3.3-1 R IN.ES RR TE BRialSWICK STEAM ELICTRIC R. ANT
- PATWAY = Ground Nuclide GI-Tract Liver T. Body Bone Kidney 1hyroid M Skin CR 51- 4.6E 06 4.6E 06 4.6E 06 4.6E 06 4.6E 06 4.6E 06 4.6E 06 5.51E 06 m 54 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.57E 09 FE 59 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 08 3.23E 08 C0 58 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 4.44E 09 C0 60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.52E 10 ZN 65 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 7.49E 08 8.61E 08 RB 86 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 8.99E 06 1.03E 07 SR 89 2.2% 04 2.23E 04 2.23E 04 2.23E 04 '2.23E 04 2.23E 04 2.23E 04 2.'58E 04 Y 91 1.00E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.08E 06 1.22E 06 ZR 95 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.49E 08 2.89E 08 le 95 1.3E 08 1.3E 08 1.3E 08 1.3E 08 1.3E 08 1.3E 08 1.3E 08 1.60E 08 RU103 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.09E 08 1.2E 08 RU106 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 4.19E 08 5.03E 08 AG110M 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 3.48E 09 4.0E 09 TE127M 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 9.15E 04 1.08E 05 TE129M 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.00E 07 2.34E 07 I 131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 I 132 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.24E 06 1.4E 06 I 133 2.47E 06 2.47E 06 2.47E 06 2.47E 06 2.4E 06 2.47E 06 2.47E 06 3.00E 06 I 135 2.5E 06 2.5E 06 2.5E 06 2.5E 06 2.5E 06 2.5E 06 2.5E 06 2.99E 06 CS134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 7.9E 09 CS136 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.49E 08 1.69E 08 CS137 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 BA140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.34E 07 CE141 1.3E 07 1.3E 07 1.3E 07 1.3E 07 1.3E 07 1.3E 07 1.3E 07 1.53E 07 CE144 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 6.95E 07 8.03E 07 i
i
- R Values in units of mrun/yr per micro-Cf/m**3 for inhalation and tritiun, and in
- units of M**2-mrem /yr per micro-Cf/sec for all others.
00CM (BSEP) 3-50 Rev. 1
,- - - . , - . - , , , , . . , . - -, -,-(.c. .,, , . , , , , .- , . , - - - . - , , . , , . , - - - - - . . , ,. ,-r - - . . -
TABLE 3.3-2 R 1RLLES FGt TE BNiatSWICK STEAM ELECTRIC R. ANT
- PATHWAY = Veget AGE GROUP = Adult Nuclide T.Bo@ GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 2.28E 03 2.28E 03 0.00E 01 2.28E 03 2.28E 03 2.28E 03 2.28E 03 2.28E 03 P 32 5.91E 07 1.72E 08 1.53E 09 9.51E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 4.60E 04 1.1E 07 0.00E 01 0.00E 01 1.01E 04 2.75E 04 6.1E 04 0.00E 01 MN 54 5.83E 07 9.3E 08 0.00E 01 3.05E 08 9.09E 07 0.00E 01 0.00E 01 0.00E 01 FE 59 1.12E 08 9.75E 08 1.24E 08 2.93E 08 0.00E 01 0.00E 01 8.17E 07 0.00E 01 CO 58 6.71E 07 6.07E 08 0.00E 01 2.99E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 C0 60 3.67E 08 3.12E 09 0.00E 01 1.6E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZN 65 5.77E 08 8.04E 08 4.01E 08 1.28E 09 8.54E 08 0.00E 01 0.00E 01 0.00E 01 T~ 1.03E 08 4.3E 07 0.00E 01 2.21E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01
- O 2.87E 08 1.60E 09 1.00E 10 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01
] SR 9J 1.64E 11 1.93E 10 6.70E 11 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01
- Y a 1.34E 05 2.76E 09 5.01E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZR 6 2.51E 05 1.1E 09 1.1E 06 3.71E 05 5.82E 05 0.00E 01 0.00E 01 0.00E 01 2 95 4.19E 04 4.73E 08 1.40E 05 7.79E 04 7.70E 04 0.00E 01 0.00E 01 0.00E 01 j RU103 2.04E 06 5.53E 08 4.74E 06 0.00E 01 1.81E 07 0.00E 01 0.00E 01 0.00E 01 I RU106 2.46E 07 1.2E 10 1.94E 08 0.00E 01 3.75E 08 0.00E 01 0.00E 01 0.00E 01 AG110M 6.23E 06 4.28E 09 1.13E 07 1.05E 07 2.0E 07 0.00E 01 0.00E 01 0.00E 01 TE127M 6.12E 07 1.6BE 09 5.02E 08 1.80E 08 2.04E 09 1.28E 08 0.00E 01 0.00E 01 i TE129M 4.71E 07 1.50E 09 2.98E 08 1.11E 08 1.24E 09 1.02E 08 0.00E 01 0.00E 01 1 131 6.61E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 0.00E 01 0.00E 01 I 132 5.21E 01 2.80E 01 5.57E 01 1.49E 02 2.37E 02 5.21E 03 0.00E 01 0.00E 01 I 133 1.12E 06 3.30E 06 2.11E 06 3.67E 06 6.40E 06 5.39E 08 0.00E 01 0.00E 01 1 135 3.91E 04 1.2E 05 4.05E 04 1.0E 05 1.70E 05 7.00E 06 0.00E 01 0.00E 01
- CS134 8.83E 09 1.89E 08 4.54E 09 1.08E 10 3.49E 09 0.00E 01 1.16E 09 0.00E 01
- CS136 1.19E 08 1.88E 07 4.19E 07 1.6E 08 9.21E 07 0.0E 01 1.2E 07 0.0E 01 CS137 5.94E 09 1.76E 08 6. OE 09 9.07E 09 3.08E 09 0.00E 01 1.02E 09 0.00E 01 BA140 8.4E 06 2.64E 08 1.28E 08 1.61E 05 5.47E 04 0.00E 01 9.22E 04 0.00E 01 CE141 1.48E 04 4.99E 08 1.93E 05 1.31E 05 6.07E 04 0.00E 01 0.00E 01 0.00E 01 CE144 1.69E 06 1.0E 10 3.15E 07 1.32E 07 7.8% 06 0.00E 01 0.00E 01 0.00E 01
- R Values in units of mnim/yr per micro-Cf/m**3 for inhalation and tritiun, and in units of M**2-mrem /yr per micro-Ci/sec for all others.
00CM (BSEP) 3-51 Rev. 1
TABLE 3.3-3 R BLLES FOR 1}E BlutSWICK STEAM ELECTRIC RM*
l PATHWAY = Ve9et l AE GROUP = Teen - '
Nuclide GI-Tract Liver T.Bo@ Bone Kidney Thyroid M Skin H 3 2.61E 03 2.61E 03 0.00E 01 2.61E 03 2.61E 03 2.61E 03 2.61E 03 2.61E 03 P 32 6.80E 07 1.47E 08 1.75E 09 1.09E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 6.11E 04 1.01 07 0.00E 01 0.00E 01 1.34E 04 3.39E 04 8.72E 04 0.00E 01 MN 54 8.79E 07 9.09E 08 0.00E 01 4.43E 08 1.32E 08 0.00E 01 0.00E 01 0.00E 01 FE 59 1.60E 08 9.78E 08 1.77E 08 4.14E 06 0.00E 01 0.00E 01 1.30E 08 0.00E 01 CO 58 9.79E 07 5.85E 08 0.00E 01 4.25E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 C0 E) 5.57E 08 3.22E 09 0.00E 01 2.47E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZN 65 8.68E 08 7.88E 08 5.3E 08 1.86E 09 1.19E 09 0.00E 01 0.00E 01 0.00E 01 RB 86 1.30E 08 4.09E 07 0.00E 01 2.7E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 89 4.36E 08 1.81E 09 1.52E 10 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 90 2.05E 11. 2.3I 10 8.32E 11 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y 91 2.0E 05 3.15E 09 7.68E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZR 95 3.68E 05 1.2I 09 1.69E 06 5.35E 05 7.8E 05 0.00E 01 0.00E 01 0.00E 01 2 95 5.77E 04 4.48E 08 1.89E 05 1.05E 05 1.02E 05 0.00E 01 0.00E 01 0.00E 01 RU103 2.90E 06 5.6E 08 6.78E 06 0.00E 01 2.39E 07 0.00E 01 0.00E 01 0.00E 01 RU106 3.93E 07 1.50E 10 3.12E 08 0.00E 01 6.02E 08 0.00E 01 0.00E 01 0.00E 01 AG110M 9.39E 06 4.34E 09 1.63E 07 1.54E 07 2.95E 07 0.00E 01 0.00E 01 0.00E 01 TE127M 9.44E 07 1.98E 09 7.93E 08 2.81E 08 3.22E 09 1.89E 08 0.00E 01 0.00E 01 TE129M 6.79E 07 1.61E 09 4.29E 08 1.59E 08 1.79E 08 1.38E 08 0.00E 01 0.00E 01 1 131 5.77E 07 2.1I 07 7.6BE 07 1.07E 08 1.85E 08 3.14E 10 0.00E 01 0.00E 01 I 132 4.72E 01 5.72E 01 5.02E 01 1.31E 02 2.07E 02 4.41 03 0.00E 01 0.00E 01 I 133 1.01E 06 2.51E 06 1.96E 06 3.32E 06 5.83E 06 4.64E 08 0.00E 01 0.00E 01 I 135 3.49E 04 1.04E 05 3.6E 04 9.42E 04 1.49E 05 6.0E 06 0.00E 01 0.00E 01 CS134 7.54E 09 2.02E 08 6.90E 09 1.62E 10 5.1E 09 0.00E 01 1.97E 09 0.00E 01 CS136 1.11 08 1.35E 07 4.28E 07 1.68E 08 9.1E 07 0.00E 01 1.44E 07 0.00E 01 CS137 4.90E 09 2.00E 08 1.0E 10 1.41E 10 4.78E 09 0.00E 01 1.86E 09 0.00E 01 BA140 8.88E 06 2.12E 08 1.38E 08 1.69E 05 5.72E 04 0.00E 01 1.14E 05 0.00E 01 CE141 2.12E 04 5.29E 08 2.77E 05 1.85E 05 8.70E 04 0.00E 01 0.00E 01 0.00E 01 CE144 2.71E 06 1.27E 10 5.04E 07 2.09E 07 1.25E 07 0.00E 01 0.00E 01 0.0% 01
- R Values in units of mrem /yr per micro-C1/ne*3 for inhalation and trittun, and in units of M**2-mrern/yr per micro-Ct/see for all others.
00CM (BSEP) 3-52 Rev. 1
TABLE 3.3-4 R 1RLES FOR TE BRLMSWICK STEAM ELECTRIC R.AIK*
PATHWAY = Ve9et !
AGE GROUP = Child i
Ibclide T.Bo@ GI-Tract Bone Liver Kidney Thymid M Skin H 3 4.04E 03 4.04E 03 0.00E 01 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 P 32 1.42E 08 1.01E 08 3.67E 09 1.72E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 1.1E 05 6.15E 06 0.00E 01 0.00E 01 1.7E 04 6.44E 04 1.18E 05 0.00E 01 MN 54 1.73E 08 5.44E 08 0.00E'01 6.49E 08 1.82E 08 0.00E 01 0.00E 01 0.00E 01 FE 59 3.17E 08 6.62E 08 3.93E 08 6.3E 08 0.00E 01 0.00E 01 1.84E 08 0.00E 01 CO 58 1.92E 08 3.6E 08 0.00E 01 6.27E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 C0 60 1.11E 09 2.08E 09 0.00E 01 3.7E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 IN 65 1.70E 09 4.81E 08 1.03E 09 2.74E 09 1.73E 09 0.00E 01 0.00E 01 0.00E 01 RB 86 2.81E 08 2.94E 07 0.00E 01 4.5E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 89 1.03E 09 1.40E 09 3.62E 10 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 90 3.49E 11 1.8E 10 1.38E 12 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y 91 4.89E 05 2.44E 09 1.83E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 2R 95 7.44E 05 8.7;E 08 3.80E 06 8.35E 05 1.20E 06 0.00E 01 0.00E 01 0.00E 01 2 95 1.12E 05 2.95.E 08 4.04E 05 1.57E 05 1.48E 05 0.00E 01 0.00E 01 0.00E 01 RU103 5.8E 06 3.94E 08 1.52E 07 0.00E 01 3.84E 07 0.00E 01 0.00E 01 0.00E 01 RU106 9.38E 07 1.17E 10 7.52E 08 0.00E 01 1.02E 09 0.00E 01 0.00E 01 0.00E 01 AG110M 1.87E 07 2.78E 09 3.4E 07 2.34E 07 4.35E 07 0.00E 01 0.00E 01 0.00E 01 TE127M 2.2E 08 1.54E 09 1.90E 09 5.12E 08 5.42E 09 4.55E 08 0.00E 01 0.00E 01 TE129M 1.55E 08 1.22E 09 9.98E 08 2.79E 08 2.93E 09 3.22E 08 0.00E 01 0.00E 01 I 131 8.1E 07 1.23E 07 1.43E 08 1.44E 08 2.3E 08 4.75E 10 0.00E 01 0.00E 01
- I 132 7.53E 01 1.93E 02 8.91E 01 1.64E 02 2.51E 02 7.60E 03 0.00E 01 0.00E 01 I 133 1.67E 06 1.78E 06 3.57E 06 4.42E 06 7.3E 06 8.21E 08 0.00E 01 0.00E 01 !
I 135 5.54E 04 8.92E 04 6.5E 04 1.17E 05 1.79E 05 1.04E 07 0.00E 01 0.00E 01 CS134 5.40E 09 1.38E 08 1.5E 10 2.5E 10 7.93E 09 0.00E 01 2.84i 09 0.00E 01 CS136 1.43E 08 7.77E 06 8.04E 07 2.21E 08 1.18E 08 0.00E 01 1.7E 07 0.00E 01 CS137 3.52E 09 1.50E 08 2.49E 10 2.39E 10 7.78E 09 0.00E 01 2.80E 09 0.00E 01 BA140 1.61E 07 1.40E 08 2.7E 08 2.42E 05 7.87E 04 0.00E 01 1.44E 05 0.00E 01 CE141 4.75E 04 3.99E 08 6.42E 05 3.20E 05 1.40E 05 0.00E 01 0.00E 01 0.00E 01 CE144 6.49E 06 9.94E 09 1.22E 08 3.81E 07 2.11E 07 0.00E 01 0.00E 01 0.00E 01
- R Values in units of mrem /yr per micro-Ci/m**3 for inhalation and tritiun, and in units of M**2-mrem /yr per micro-C1/see for all others.
00CM (BSEP) 3-53 Rev. 1 l
TABLE 3.3-5 R 1RLLES FtR TE 81MISWICK STEAM E1ICTRIC R. ANT *
! PATHWAY = Meat AGE GROUP = Adult Nuclide T.Bo@ GI-Tract Bone Liver Kidney ,
lhyroid M Skin H 3 3.2E 02 3.27E 02 0.00E 01 3.27E 02 3.2 E 02 3.27E 02 3.2 K 02 3.27E 02 P 32 1.18E 08 3.43E 08 3.05E 09 1.89E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 4.2E 03 1.08E 06 0.00E 01 0.00E 01 9.42E 02 2.5E 03 5.6E 03 0.00E 01 MN 54 1.0E 06 1.71E 07 0.00E 01 5.57E 06 1.66E 06 0.00E 01 0.00E 01 0.00E 01 FE 59 1.43E 08 1.2SE 09 1.59E 08 3.74E 08 0.00E 01 0.00E 01 1.04E 08 0.00E 01 C0 58 2.43E 07 2.20E 08 0.00E 01 1.00E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CO 60 1.03E 08 8.7E 08 0.00E 01 4.6E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 i
ZN 65 3.58E 08 4.98E 08 2.49E 08 7.91E 08 5.29E 08 0.00E 01 0.00E 01 0.00E 01 E 86 1.42E 08 6.00E 07 0.00E 01 3.04E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 89 5.23E 06 2.92E 07 1.82E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 90 2.02E 09 2.38E 08 8.22E 09 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y 91 1.80E 04 3.71E 08 6.75E 05 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZR 95 2.43E 05 1.14E 09 1.12E 06 3.59E 05 5.64E 05 0.00E 01 0.00E 01 0.00E 01 2 95 4.12E 05 4.65E 09 1.38E 06 7.6E 05 7.58E 05 0.00E 01 0.00E 01 0.00E 01 RU103 2.72E 07 7.38E 09 6.32E 07 0.00E 01 2.41E 08 0.00E 01 0.00E 01 0.00E 01 RU106 2.19E 08 1.12E 11 1.73E 09 0.00E 01 3.35E 09 0.00E 01 0.00E 01 0.00E 01 AG110M 2.34E 06 1.61E 09 4.2K 06 3.95E 06 7.7E 06 0.00E 01 0.00E 01 0.00E 01 TE127M 1.00E C3 2.76E 09 8.22E 08 2.94E 08 3.34E 09 2.10E 08 0.00E 01 0.00E 01 TE129M 1.1E 08 3.73E 09 7.4E 08 2.7E 08 3.09E 09 2.54E 08 0.00E 01 0.00E 01 1 131 5.77E 06 2.6E 06 7.04E 06 1.01E 07 1.73E 07 3.30E 09 0.00E 01 0.00E 01 1 133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.6E-01 7.29E 01 0.0E 01 0.00E 01 1 135 6.07E-17 1.8E-16 6.28E-17 1.64E-16 2.64E-16 1.00E-14 0.00E 01 0.00E 01 CS134 7.81E 08 1.67E 07 4.01E 08 9.55E 08 3.09E 08 0.00E 01 1.03E 08 0.00E 01 CS136 2.14E 07 3.33E 06 7.53E 06 2.97E 07 1.65E 07 0.00E 01 2.2E 06 0.00E 01 CS137 4.99E 08 1.4E 07 5.57E 08 7.61E 08 2.56E 08 0.00E 01 8.59E 07 0.00E 01 BA140 1.20E 06 3.77E 07 1.83E 07 2.30E 04 7.82E 03 0.00E 01 1.32E 04 0.00E 01 CE141 6.4E 02 2.18E 07 8.42E 03 5.69E 03 2.65E 03 0.00E 01 0.00E 01 0.00E 01 CE144 4.70E 04 2.96E 08 8.75E 05 3.6E 05 2.1E 05 0.00E 01 0.00E 01 0.00E 01 1
- R Values in units of mrum/yr per micro-Ci/m**3 for inhalation and tritiin, and in units of M**2-mrem /yr per micro-Cf/sec for all others.
00CM(BSEP) 3-54 Rev. 1
TABLE 3.3-6 R 1RLES FtR TE BRBISWICK STEAM ElICTRIC FUWT*
PATHWAY = Neat AGE GROUP = Teen Nuclide T.Bo@ GI-Tract Bone Liver Kidney Thymid M Skin H 3 1.95E 02 1.95E 02 0.00E 01 1.95E 02 1.95E 02 1.95E 02 1.95E 02 1.95E 02 P 32 9.98E 07 2.1E 08 2.58E 09 1.EDE 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 3.42E 03 5.75E 05 0.00E 01 0.00E 01 7.49E 02 1.90E 03 4.88E 03 0.00E 01 MN 54 8.43E 05 8.72E 06 0.00E 01 4.25E 06 1.27E 06 0.00E 01 0.00E 01 0.00E 01 FE 59 1.15E 08 7.02E 08 1.27E 08 2.9E 08 0.00E 01 0.00E 01 9.3E 07 0.00E 01 CO 58 1.93E 07 1.15E 08 0.00E 01 8.3E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 C0 (D 8.15E 07 4.71E 08 0.00E 01 3.62E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 IN 65 2.83E 08 2.5E 08 1.75E 08 6.0E 08 3.89E 08 0.00E 01 0.00E 01 0.00E 01 RB 86 1.19E 08 3.7E 07 0.00E 01 2.54E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 89 4.40E 06 1.83E 07 1.54E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 90 1.31E 09 1.49E 08 5.32E 09 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y 91 1.52E 04 2.33E 08 5.68E 05 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZR 95 1.95E 05 6.5 I 08 8.9 E 05 2.83E 05 4.1E 05 0.00E 01 0.0E 01 0.00E 01 2 95 3.29E 05 2.55E 09 1.00E 06 5.97E 05 5.79E 05 0.00E 01 0.00E 01 0.00E 01 RU103 2.20E 07 4.30E 09 5.15E 07 0.00E 01 1.82E 08 0.00E 01 0.00E 01 0.00E 01 RU106 1.84E 08 7.00E 10 1.4E 09 0.00E 01 2.81E 09 0.00E 01 0.00E Ol' O.00E 01 AG110M 1.8E 06 8.59E 08 3.23E 06 3.0E 06 5.83E 06 0.00E 01 0.00E 01 0.00E 01 TE127M 8.2SE 07 1.73E 09 6.94E 08 2.4E 08 2.81E 09 1.65E 08 0.00E 01 0.00E 01 TE129M 9.81E 07 2.33E 09 6.20E 08 2.30E 08, 2.59E 09 2.00E 08 0.00E 01 0.00E 01 1 131 4.40E 06 1.62E 06 5.85E 06 8.20E 06 1.41E 07 2.39E 09 0.00E 01 0.00E 01 1 133 1.23E-01 3.0E-01 2.39E-01 4.05E-01 7.10E-01 5.65E 01 0.00E 01 0.00E 01 I 135 4.88E-17 1.4E-16 5.11E-17 1.32E-16 2.08E-16 8.4E-15 0.00E 01 0.00E 01 CS134 3.48E 08 9.34E 06 3.19E 08 7.51E 08 2.39E 08 0.00E 01 9.11E 07 0.00E 01 CS136 1.55E 07 1.86E 06 5.87E 06 2.31E 07 1.2E 07 0.00E 01 1.98E 06 0.00E 01 CS137 2.14E 08 8.75E 06 4.62E 08 6.15E 08 2.09E 08 0.00E 01 8.13E 07 0.00E 01 8A140 9.76E 05 2.34E 07 1.51E 07 1.86E 04 6.29E 03 0.00E 01 1.25E 04 0.0% 01 CE141 5.42E 02 1.35E 07 7.0E 03 4.72E 03 2.22E 03 0.00E 01 0.00E 01 0.00E 01 CE144 3.96E 04 1.85E 08 7.3E 05 3.05E 05 1.82E 05 0.00E 01 0.00E 01 0.00E 01
- R Values in units of mren/yr per micm-C1/m**3 for inhalation and trititsn, and in units of M**2-mrem /yr per micro-Ci/sec for all others.
00CM (BSEP) 3-55 Rev. 1
TABLE 3.3-7 R WLLES FtR TE BmatSWICK STEAM ELECTRIC RM*
PATHWAY = Meat AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney 1hyroid Lg, Skin H 3 2.3E 02 2.3E 02 0.00E 01 2.3E 02 2.3E 02 2.3E 02 2.3E 02 2.3E 02 P 32 1.87E 08 1.34E 08 4.86E 09 2.27E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 CR 51 5.31 03 2.83E 05 0.00E 01 0.00E 01 8.09E 02 2.9E 03 5.40E 03 0.00E 01 MN 54 1.30E 06 4.08E 06 0.00E 01 4.8E 06 1.3E 06 0.00E 01 0.00E 01 0.00E 01 FE 59 1.82E 08 3.80E 08 2.25E 08 3.65E 08 0.00E 01 0.00E 01 1.0E 08 0.00E 01 CO 53 2.99E 07 5.70E 07 0.00E 01 9.7E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 C0 0 1.27E 08 2.38E 08 0.00E 01 4.30E 07 0.00E 01 0.00E 01 0.00E 01 0.00E 01 IN 65 4.35E 08 1.23E 08 2.62E 08 6.99E 08 4.40E 08 0.00E 01 0.00E 01 0.00E 01 RB 86 2.21E 08 2.32E 07 0.00E 01 3.60E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 89 8.31E 06 1.13E 07 2.91E 08 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 SR 90 1.74E 09 9.2E 07 6.87E 09 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 Y 91 2.87E 04 1.43E 08 1.07E 06 0.00E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 ZR 95 3.12E 05 3.65E 08 1.59E 06 3.50E 05 5.01E 05 0.00E 01 0.0E 01 0.00E 01 E 95 5.17E 05 1.34E 09 1.86E 06 7.23E 05 6.80E 05 0.00E 01 0.00E 01 0.00E 01 RU103 3.58E 07 2.41E 09 9.31E 07 0.00E 01 2.34E 08 0.00E 01 0.00E 01 0.00E 01 RU106 3.43E 08 4.27E 10 2.75E 09 0.00E 01 3.71E 09 0.00E 01 0.00E 01 0.00E 01 l AG110M 2.89E 06 4.30E 08 5.3E 06 3.62E 06 6.74E 06 0.00E 01 0.00E 01 0.00E 01 TE127M 1.55E 08 1.0E 09 1.31E 09 3.52E 08 3.73E 09 3.13E 08 0.00E 01 0.00E 01 TE129M 1.81E 08 1.42E 09 1.17E 09 3.2E 08 3.43E 09 3.77E 08 0.00E 01 0.00E 01 1 131 6.2 % 06 9.72E 05 1.09E 07 1.09E 07 1.79E 07 3.61E 09 0.00E 01 0.00E 01 1 133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E 02 0.00E 01 0.00E 01 1 135 7.87E-17 1.27E-16 9.25E-17 1.6E-16 2.55E-16 1.47E-14 0.00E 01 0.00E 01 CS134 1.95E 08 4.93E 06 5.63E 08 9.23E 08 2.8E 08 0.00E 01 1.03E 08 0.00E 01 CS136 1.80E 07 9.78E 05 1.01E 07 2.78E 07 1.48E 07 0.00E 01 2.21E 06 0.00E 01 CS137 1.20E 08 5.1E 06 8.51E 08 8.15E 08 2.65E 08 0.00E 01 9.55E 07 0.00E 01 BA140 1.OE 06 1.42E 07 2.80E 07 2.45E 04 7.97E 03 0.00E 01 1.4E 04 0.00E 01 CE141 9.8E 02 8.28E 06 1.33E 04 6.64E 03 2.91E 03 0.00E 01 0.0% 01 0.00E 01 CE144 7.42E 04 1.14E 08 1.39E 06 4.3E 05 2.41E 05 0.00E 01 0.00E 01 0.00E 01
- R Values in units of mrem /yr per micro-Ci/m**3 for inhaletion and tritiin, and in units of M**2-mrer1/yr per micro-Ci/sec for all others.
00CM (BSEP) 3-56 Rev. 1
TABLE 3.3-8 R MLES F(R TE BlutSWICK STEAM E1ICTRIC RM*
PATHWAY = Cow Milk AGE GROUP = Adult Huclide T.Bo@ GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 7.69E 02 7.69E 02 0.00E-01 7.69E 02 7.69E 02 7.69E 02 7.69E 02 7.69E 02 P 32 4.32E 08 1.2E 09 1.12E 10 6.95E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 1.73E 04 4.3E 06 0.00E-01 0.00E-01 3.82E 03 1.04E 04 2.30E 04 0.00E-01 MN 54 9.76E 05 1.57E 07 0.00E-01 5.11E 06 1.52E 06 0.00E-01 0.00E-01 0.00E-01 FE 59 1.60E 07 1.39E 08 1.7E 07 4.17E 07 0.00E-01 0.00E-01 1.17E 07 0.00E-01 C0 50 6.28E 06 5.68E 07 0.00E-01 2.80E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 C0 60 2.24E 07 1.91E 08 0.00E-01 1.02E 07 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 1.38E 09 1.92E 09 9.59E 08 3.05E 09 2.04E 09 0.00E-01 0.00E-01 0.00E-01 RB 86 7.54E 08 3.19E 08 0.00E-01 1.62E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.50E 07 1.40E 08 8.70E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 7.59E 09 8.94E 08 3.09E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.37E 02 2.81E 06 5.11E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZR 95 1.22E 02 5.71E 05 5.62E 02 1.80E 02 2.83E 02 0.00E-01 0.00E-01 0.00E-01 2 95 1.48E 04 1.67E 08 4.95E 04 2.75E 04 2.72E 04 0.00E-01 0.00E-01 0.00E-01 RU 103 2.63E 02 7.14E 04 6.11E 02 0.00E-01 2.33E 03 0.00E-01 0.00E-01 0.00E-01 RU 106 1.EE 03 8.17E 05 1.2E 04 0.00E-01 2.44E 04 0.00E-01 0.00E-01 0.00,:-01 AG110M 2.04E 07 1.40E 10 3.71E 07 3.44E 07 6.7E 07 0.00E-01 0.00E-01 0.00E-01 TE127M 4.11E 06 1.13E 08 3.3E 07 1.21E 07 1.37E 08 8.62E 06 0.00E-01 0.00E-01 TE129M 6.19E 06 1.9E 08 3.91E 07 1.4E 07 1.63E 08 1.34E 07 0.00E-01 0.00E-01 I 131 1.59E 08 7.32E 07 1.94E 08 2.77E 08 4.76E 08 9.09E 10 0.00E-01 0.00E-01 1 132 1.03E-01 5.51E-02 1.10E-01 2.93E-01 4.67E-01 1.03E 01 0.00E-01 0.00E-01 1 133 1.40E 06 4.11 06 2.64E 06 4.59E 06 8.01E 06 6.75E 08 0.00E-01 0.00E-01 I 135 9.03E 03 2.7E 04 9.34E 03 2.45E 04 3.92E 04 1.61E 06 0.00E-01 0.00E-01 CS 134 6.71E 09 1.44E 08 3.45E 09 3.21E 09 2.6E 09 0.00E-01 8.82E 08 0.00E-01 CS 136 4.73E 08 7.4E 07 1.6E 08 6.5K 08 3.65E 08 0.00E-01 5.01E 07 0.00E-01 CS 137 4.22E 09 1.25E 08 4.71E 09 6.44E 09 2.19E 09 0.00E-01 7.27E 08 0.00E-01 BA 140 1.12E 06 3.53E 07 1.71E 07 2.15E 04 7.32E 03 0.00E-01 1.23E 04 0.00E-01 CE 141 2.23E 02 7.52E 06 2.91E 03 1.97E 03 9.14E 02 0.00E-01 0.00E-01 0.00E-01 CE 144 1.15E 04 7.2E 07 2.15E 05 8.97E 04 5.32E 04 0.00E-01 0.00E-01 0.00E-01
- R Values in units of mrem /yr per micro-Ci/re*3 for inhalation and tritiun, and in units of M**2-mrem /yr per micro-Cf/sec for all others.
00CM (BSEP) 3-57 Rev. 1
TABLE 3.3-9 R MES RR TE BRMSWICK STEAM ELECTRIC R.AE*
l PATHWAY = Cow Milk AGE GROUP = Teen Nisclide T. Body GI-Tract Bone Liver Kidney Thyroid Lug Skin i
i 1.00E 03 0.00E-01 1.00E 03 1.00E 03 1.00E 03 1.00E 03 1.00E 03 H 3 1.00E 03 P 32 8.00E 08 1.73E 09 2.0E 10 1.28E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01
, CR 51 3.02E 04 5.00E 06 0.00E-01 0.00E-01 6.63E 03 1.68E 04 4.32E 04 0.00E-01 MN 54 1.69E 06 1.75E 07 0.00E-01 8.52E 06 2.54E 06 0.00E-01 0.00E-01 0.00E-01 FE 59 2.79E 07 1.71E 08 3.10E 07 7.2 I 07 0.00E-01 0.00E-01 2.28E 07 0.00E-01 C0 58 1.09E 07 6.50E 07 0.00E-01 4.72E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 C0 60 3.88E 07 2.25E 08 0.00E-01 1.72E 07 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 2.38E 09 2.1E 09 1.4E 09 5.11E 09 3.27E 09 0.00E-01 0.00E-01 0.00E-01 i RB 86 1.39E 09 4.37E 08 0.00E-01 2.95E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 4.59E 07 1.91E 08 1. EE 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 1.08E 10 1.21 09 4.37E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 2.52E 02 3.85E 06 9.40E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01
! ZR 95 2.13E 02 7.1E 06 9.83E 02 3.10E 02 4.5E 02 0.00E-01 0.00E-01 0.00E-01 2 95 2.58E 04 2.00E 08 8.45E 04 4.68E 04 4.54E 04 0.00E-01 0.00E-01 0.00E-01 RU 103 4.65E 02 9.0E 04 1.09E 03 0.00E-01 3.83E 03 0.00E-01 0.00E-01 0.00E-01 RU 106 2.93E 03 1.11E 06 2.32E 04 0.00E-01 4.48E 04 0.00E-01 0.00E-01 0.00E-01 AG110M 3.53E 07 1.63E 10 6.14E 07 5.81E 07 1.11E 08 0.00E-01 0.00E-01 0.00E-01 TE127M 7.39E 06 1.55E 08 6.22E 07 2.21E 07 2.52E 08 1.48E 07 0.00E-01 0.00E-01 TE129M 1.13E 07 2.69E 08 7.15E 07 2.65E 07 2.99E 08 2.31E 07 0.00E-01 0.00E-01
- I 131 2.65E 08 9.75E 07 3.52E 08 4.93E 08 8.48E 08 1.44E 11 0.00E-01 0.00E-01 1 132 1.83E-01 2.22E-01 1.94E-01 5.09E-01 8.02E-01 1.71E 01 0.00E-01 0.00E-01 I 133 2.49E 06 6.19E 06 4.82E 06 8.18E 06 1.43E 07 1.14E 09 0.00E-01 0.00E-01 4
I 135 1.58E 04 4.74E 04 1.6E 04 4.27E 04 6.75E 04 2.75E 06 0.00E-01 0.00E-01 CS 134 6.54E 09 1.75E 08 5.99E 09 1.41E 10 4.48E 09 0.00E-01 1.71E 09 0.00E-01 CS 136 7.48E 08 8.97E 07 2.83E 08 1.11E 09 6.07E 08 0.00E-01 9.5E 07 0.00E-01 CS 137 3.96E 09 1.62E 08 8.54E 09 1.14E 10 3.87E 09 0.00E-01 1.50E 09 0.00E-01 BA 140 1.99E 06 4.77E 07 3.09E 07 3.79E 04 1.28E 04 0.00E-01 2.55E 04 0.00E-01 -
CE 141 4.09E 02 1.02E 07 6.33E 03 3.5E 03 1.68E 03 0.00E-01 0.00E-01 0.00E-01
- CE 144 2.12E 04 9.93E 07 3.95E 05 1.61 05 9.7E 04 0.00E-01 0.00E-01 0.00E-01
- R Values in units of mrem /yr per micro-Ci/re*3 for inhalation and tritita, and in units of M**2-mrem /yr per micro-C1/sec for all others.
1 1
00CM (BSEP) 3-58 Rev.1 i
4
- TABLE 3.3-10 R ELES FtR TE BitalSWICK STEAM ELECTRIC PUllE*
PATWAY = Cow Milk AGE GROUP = Child i
Nuclide T. Body GI-Tract Bone Liver Kidney Thymid M Skin l H 3 1.5E 03 1.58E 03- 0.00E-01 1.5K 03 1.5E 03 1.5E 03 1.5E 03 1.5E 03 l P 32 1.96E 09 1.41E 09 5.09E 10 2.38E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01
[ CR 51 6.17E 04 3.27E 06 0.00E-01 0.00E-01 9.3E 03 '3.42E 04 6.25E 04 0.00E-01 l - MN 54 3.39E 06 1.0E 07 0.00E-01 1.27E 07 3.57E 06 0.00E-01 0.00E-01 0.00E-01 FE 59 5.79E 07 1.21E 08 7.1E 07 1.1E 08 0.00E-01 0.00E-01 3.3?E 07 0.00E-01 l C0 58 2.21E 07 4.20E 07 0.00E-01 7.21E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 C0 m 7.9E 07 1.4E 08 0.00E-01 2.6E 07 0.00E-01 0.00E-01 0.00E-01 0.00E-01
-ZN 65 4.79E 09 1.35E 09 2.89E 09 7.70E 09 4.85E 09 0.00E-01 0.00E-01 0.00E-01 i RB 86 3.3E 09 3.52E 08 0.00E-01 5.47E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 1.13E 08 1.54E 08 3.97E 09 0.00E-01 0.0E-01 0.00E-01 0.00E-01 0.00E-01 i- SR 90 1.87E 10 9.95E 08 7.38E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 Y 91 6.21E 02 3.09E 06 2.32E 04 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l ZR 95 4.4E 02 5.21 05 2.2E 03 5.02E 02 7.1E 02 0.00E-01 0.00E-01 0.00E-01.
l W 95 5.31E 04 1.37E 08 1.91E 05 7.42E 04 6.98E 04 0.00E-01 0.00E-01 0.00E-01 j RU 103 9.88E 02 6.65E 04 2.57E 03 0.00E-01 6.47E 03 0.00E-01 0.00E-01 0.00E-01
! RU 106 7.14E 03 8.90E 05 5.72E 04 0.00E-01 7.72E 04 0.00E-01 0.00E-01 0.00E-01 AG110M 7.19E 07 1.07E 10 1.3 I 08 9.0E 07 1.6E 08 0.00E-01 0.00E-01 0.00E-01 TE127M 1.82E 07 1.24E 08 1.53E 08 4.13E 07 4.37E 08 3.6E 07 0.00E-01 0.00E-01
- TE129M 2.74E 07 2.15E 08 1.7E 08 4.92E 07 5.1E 08 5.68E 07 0.00E-01 0.00E-01
, I 131 4.88E 08 7.64E 07 8.54E 08 8.59E 08 1.41E 09 2.84E 11 0.00E-01 0.00E-01 l I 132 3.89E-01 9.95E-01 4.60E-01 8.45E-01 1.29E 00 3.92E 01 0.00E-01 0.00E-01 l I 133 - 5.48E 06 5.84E 06 1.17E 07 1.45E 07 2.41E 07 2.69E 09 0.'00E-01 0.00E-01 I 135 3.35E 04 5.39E 04 3.9I 04 7.07E 04 1.0E 05 6.2E 06 0.00E-01 0.00E-01 CS 134 .4.78E 09 1.22E 08 1.38E 10 2.27E 10 7.03E 09 0.00E-01 2.52E 09 0.00E-01
- . CS 136 1.14E 09 6.17E 07 6.39E 08 1.7E 09 9.3E 08 0.00E-01 1.4E 08 0.00E-01 l CS 137 2.91E 09 1.21 08 2.0E 10 1.97E 10 6.42E 09 0.00E-01 2.31E 09 0.0E-01
- BA 140 4.3E 06 - 3.7E 07 7.47E 07 6.54E 04 2.1 1 04 0.00E 3.9E 04 0.00E-01 CE 141 9.73E 02 8.17E 06 1.31E 04 6.55E 03 2.87E 03 0.00E-01 0.0E-01 0.0E-01 CE 144' 5.2E 04 7.9E 07 9.74E 05 3.05E 05 1.69E 05 0.00E-01 0.00E-01 0.00E-01 i
- R Values in units of mrum/yr per micro-Ci/m**3 for inhalation and tritiin, and in units of M**2-erem/yr per micro-C1/sec for all others.
y _ _ . ~ _
00CM (BSEP) 3-59 Rev. 1
TABLE 3.3-11 R IN.ES RR TE BRBISWICK STEAM ELECTRIC FUUfI*
4 PAT}MAY = Cow Milk AGE GROUP = Infant l
Nuclide T.Bocty GI-Tract Bone t.iver Kidney Thyroid Lung Skin H 3 2.40E 03 2.40E 03 0.00E-01 2.40E 03 2.40E 03 2.40E 03 2.4 % 03 2.4 E 03 P 32 4.0E 09 1.42E 09 1.05E 11 6.17E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 9.77E 04 2.85E 06 0.00E-01 0.00E-01 1.39E 04 6.38E 04 1.24E 05 0.00E-01 MN 54 5.37E 06 8.71E 06 0.00E-01 2.37E 07 5.25E 06 0.00E-01 0.00E-01 0.00E-01 FE 59 9.23E 07 1.12E 08 1.34E 08 2.34E 08 0.00E-01 0.00E-01 6.92E 07 0.00E-01 CO 58 3.(DE 07 3.59E 07 0.00E-01 1.44E 07 0.00E-01 0.00E-01 0.00E-01 0.00E-01 C0 60 1.29E 08 1.30E 08 0.00E-01 5.47E 07 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 6.14E 09 1.12E 10 3.88E 09 1.33E 10 6.45E 09 0.00E-01 0.00E-01 0.00E-01 RB 86 6.8E 09 3.55E 08 0.00E-01 1.39E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.17E 08 1.55E 08 7.55E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 2.05E 10 1.00E 09 8.04E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.1E 08 3.12E 06 4.3E 04 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZR 95 7.01E 02 4.92E 05 4.05E 03 9.88E 02 1.0E 03 0.00E-01 0.00E-01 0.00E-01 2 95 8.48E 04 1.24E 0* 3.5E 05 1.47E 05 1.05E 05 0.00E-01 0.00E-01 0.00E-01 RU 103 1.74E 03 6.3I 04 5.21E 03 0.00E-01 1.08E 04 0.00E-01 0.00E-01 0.00E-01 RU 106 1.47E 04 8.95E 05 1.18E 05 0.00E-01 1.39E 05 0.00E-01 0.00E-01 0.00E-01 AG110M 1.19E 08 9.32E 09 2.4E 08 1.80E 08 2.57E 08 0.00E-01 0.00E-01 0.00E-01 TE127M 3.75E 07 1.25E 08 3.10E 08 1.03E 08 7.64E 08 8.96E 07 0.00E-01 0.00E-01 TE129M 5.57E 07 2.1E 08 3.62E 08 1.24E 08 9.05E 08 1.39E 08 0.00E-01 0.00E-01 I 131 9.23E 08 7.49E 07 1.78E 09 2.10E 09 2.45E 09 6.90E 11 0.00E-01 0.00E-01 I 132 6.90E-01 1.57E-00 9.55E-01 1.94E 00 2.1E 00 9.09E 01 0.00E-01 0.00E-01 1 133 1.05E 07 6.09E 06 2.47E 07 3.fDE 07 4.23E 07 6.55E 09 0.00E-01 .0.00E-01 I 135 5.93E 04 5.83E 04 8.17E 04 1.63E 05 1.81E 05 1.4E 07 0.00E-01 0.00E-01 C5 134 4.19E 09 1.13E 08 2.23E 10 4.15E 10 1.07E 10 0.00E-01 4.38E 09 0.00E-01 CS 136 1.37E 09 5.58E 07 1.25E 09 3.67E 09 1.4E 09 0.00E-01 2.99E 08 0.00E-01 CS 137 2.72E 09 1.20E 08 3.28E 10 3.84E 10 1.03E 10 0.00E-01 4.18E 09 0.00E-01 BA 140 7.91E 06 3.77E 07 1.54E 08 1.54E 05 3.65E 04 0.00E-01 9.43E 04 0.00E-01 l CE 141 1.87E 03 3.21E 06 2.(DE 04 1.59E 04 4.90E 03 0.00E-01 0.00E-01 0.00E-01 l 7.82E 04 CE 144 8.01E 07 1.40E 06 5.71E 05 2.31E 05 0.00E-01 0.00E-01 0.00E-01 l
l
- R Values in units of mrem /yr per micro-Ci/m"3 for inhalation and tritita and in units of M"2-mrem /yr per micro-C1/sec for all others.
00CM (BSEP) 3-60 Rev. 1
TABLE 3.3-12 R MLtES F(R T}E BRiatSWICK STEAM ELECTRIC RM*
PATHWAY = Goat Milk AGE GROUP = Adult Ibc11de T.Bo@ GI-Tract Bone Liver Kidney 1hyroid M Skin H 3 1.57E 03 1.5E 03 0.00E-01 1.5E 03 1.57E 03 1.5E 03 1.5E 03 1.57E 03 P 32 5.19E 08 1.51E 09 1.34E 10 8.34E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 2.08E 03 5.23E 05 0.00E-01 0.00E-01 4.58E 02 1.24E 03 2.7E 03 0.00E-01 MN 54 1.1E 05 1.88E 06 0.00E-01 6.14E 05 1.83E 05 0.00E-01 0.00E-01 0.00E-01 FE 59 2.08E 05 1.81E 06 2.31E 05 5.42E 05 0.00E-01 0.00E-01 1.51E 05 0.00E-01 C0 58 7.54E 05 6.82E 06 0.00E-01 3.3E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CO (D 2.69E 06 2.29E 07 0.00E-01 1.22E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 1.65E 08 2.31E 08 1.15E 08 3.6E 08 2.45E 08 0.00E-01 0.00E-01 0.00E-01 RB 86 9.05E. 07 3.83E 07 0.00E-01 1.94E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 5.24E 07 2.93E 08 1.83E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 1.59E 10 1.88E 09 6.49E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.64E 01 3.37E 05 6.13E 02 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZR 95 1.4E 01 6.85E 04 6.74E 01 2.1E 01 3.39E 01 0.00E-01 0.00E-01 0.00E-01 IB 95 1.78E 03 2.01E 07 5.94E 03 3.31E 03 3.27E 03 0.00E-01 0.00E-01 0.00E-01 RU 103 3.1E 01 8.5E 03 7.33E 01 0.00E-01 2.80E 02 0.00E-01 0.00E-01 0.00E-01 RU 106 1.92E 02 9.81E 04 1.52E 03 0.00E-01 2.93E 03 0.00E-01 0.00E-01 0.00E-01 4.4E 06 AG110M 2.45E 06 1.68E 09 4.12E 06 8.11E 06 0.00E-01 0.00E-01 0.00E-01 TE127M 4.93E 05 1.3E 07 4.05E 06 1.45E 06 1.64E 07 1.03E 06 0.00E-01 0.00E-01 TE129M 7.4I 05 2.3d 07 4.69E 06 1.75E 06 1.9E 07 1.61E 06 0.00E-01 0.00E-01 ,
I 131 1.91E 08 8.78E 07 2.33E 08 3.33E 08 5.71E 08 1.09E 11 0.00E-01 0.00E-01 ;
I 132 1.23E-01 6.61E-02 1.32E-01 3.52E-01 5.61E-01 1.2 I 01 0.00E-01 0.00E-01 l I 133 1.68E 06 4.95E 06 3.1?E 06 5.51E 06 9.61E 06 8.10E 08 0.00E-01 0.00E-01 1 135 1.08E 04 3.32E 04 1.12E 04 2.94E 04 4.71E 04 1.94E 06 0.00E-01 0.00E-01 CS 134 2.01E 10 4.31E 08 1.03E 10 2.4E 10 7.97E 09 0.00E-01 2.65E 09 0.00E-01 CS 136 1.42E 09 2.24E 08 4.99E 08 1.97E 09 1.10E 09 0.00E-01 1.5E 08 0.00E-01 CS 137 1.27E 10 3.74E 08 1.41E 10 1.93E 10 6.5E 09 0.00E-01 2.18E 09 0.00E-01 BA 140 1.35E 05 4.23E 06 2.0E 06 2.58E 03 8.78E 02 0.00E-01 1.4E 03 0.00E-01 CE 141 2.68E 01 9.03E 05 3.49E 02 2.3E 02 1.10E 02 0.00E-01 0.00E-01 0.00E-01 CE 144 1.38E 03 8.71E 06 2.58E N 1.0E 04 6.39E 03 0.00E-01 0.00E-01 0.00E-01 l
- R Values in units of mrmm/yr per micro-Ci/m**3 for inhalation and tritium, and in units of M**2-mrem /yr per micro-C1/sec for all others.
l 00CM (BSEP) 3-61 Rev. 1 l
TABLE 3.3-13 R MES FOR TE BRL9tSWICK STEAM EECTRIC R. ANT
- PATiMAY = Goat Milk AE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin 1
H 3 2.04E 03 2.04E 03 0.00E-01 2.04E 03 2.04E 03 2.04E 03 2.04E 03 2.04E 03 P 32 9.OE 08 2.08E 09 2.48E 10 1.53E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 3. E 03 6.10E 05 0.00E-01 0.00E-01 7.95E 02 2.02E 03 5.18E 03 0.00E-01 MN 54 2.03E 05 2.10E 06 0.00E-01 1.02E 06 3.05E 05 0.00E-01 0.00E-01 0.00E-01 FE 59 3.63E 05 2.22E 06 4.03E 05 9.40E 05 0.00E-01 0.00E-01 2.9E 05 0.00E-01 C0 58 1.30E 06 7.80E 06 0.00E41 5.6E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 C0 60 4.6E 06 2.69E 07 0.00E-01 2.07E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 2.86E 08 2.60E 08 1.77E 08 6.13E 08 3.93E 08 0.00E-01 0.00E-01 0.00E-01 RB 86 1.6E 08 5.24E 07 0.00E-01 3.54E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 9.65E 07 4.01E 08 3.37E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 2.27E 10 2.58E 09 9.18E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 3.02E 01 4.62E 05 1.13E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZR 95 2.5E 01 8.59E 04 1.18E 02 3.72E 01 5.47E 01 0.00E-01 0.00E-01 0.00E-01 2 95 3.09E 03 2.40E 07 1.01E 04 5.62E 03 5.45E 03 0.00E-01 0.00E-01 0.00E-01 RU 103 5.58E 01 1.09E 04 1.30E 02 0.00E-01 4.60E 02 0.00E-01 0.00E-01 0.00E-01 RU 106 3.51E 02 1.34E 05 2.79E 03 0.00E-01 5.38E 03 0.00E-01 0.00E-01 0.00E-01 AG110M 4.24E 06 1.9E 09 7.37E 06 6.97E 06 1.33E 07 0.00E-01 0.00E-01 0.00E-01 TE127M 8.87E 05 1.86E 07 7.4E 06 2.65E 06 3.02E 07 1.77E 06 0.00E-01 0.00E-01 TE129M 1.3E 06 3.22E 07 8.58E 06 3.19E 06 3.59E 07 2.77E 06 0.00E-01 0.00E-01 1 131 3.18E 08 1.17E 08 4.22E 08 5.91E 08 1.02E 09 1.73E 11 0.00E-01 0.00E-01 I 132 2.19E-01 2.66E-01 2.33E-01 6.11E-01 9.62E-01 2.0E 01 0.00E-01 0.00E-01 I 133 2.99E 06 7.43E 06 5.79E 06 9.81E 06 1.72E 07 1.37E 09 0.00E-01 0.00E-01 I 135 1.90E 04 5.63E 04 1.99E 04 5.11 04 8.10E 04 3.30E 06 0.00E-01 0.00E-01 CS 134 1.96E 10 5.2E 08 1.80E 10 4.23E 10 1.34E 10 0.00E-01 5.13E 09 0.00E-01 CS 136 2.25E 09 2.69E 07 8.50E 08 3.34E 09 1.82E 09 0.00E-01 2.87E 08 0.00E-01 CS 137 1.19E 10 4.85E 08 2.5E 10 3.41E 10 1.1E 10 0.00E-01 4.51E 09 0.00E-01 BA 140 2.39E 05 5.72E 06 3.71E 06 4.55E 03 1.54E 03 0.00E-01 3.0E 03 0.00E-01 CE 141 4.91E 01 1.22E 06 6.40E 02 4.27E 02 2.01E 02 0.00E-01 0.00E-01 0.00E-01 CE 144 2.55E 03 1.19E 07 4.74E 04 1.9E 04 1.17E 04 0.00E-01 0.00E-01 0.00E-01 l
l
- R Values in units of mren/yr per micro-Ci/m**3 for inhalation and tritiisn, and in units of M**2-mreri/yr per micro-Ci/sec for all others.
00CM (BSEP) 3-62 Rev. 1
TABLE 3.3-14 R ELLES FGt 1}E BlutSWICK STEAM ELICTRIC R. ANT
- PATHWAY = Goat Milk AE GROUP = Child Nuclide T.Bo@ GI-Tract Bone Liver Kidney Thyroid Lung Skin H 3 3.2I 03 3.2I 03 0.00E-01 3.2 1 03 3.21 03 3.23E 03 3.23E 03 3.2I 03 P 32 2.35E 09 1.69E 09 6.11E 10 2.86E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01
~
CR 51 7.40E 03 3.9 I 05 0.00E-01 0.00E-01 1.12E 03 4.11E 03 7.50E 03 0.00E-01 MN 54 4.0E 05 1.28E 06 0.00E-01 1.53E 06 4.29E 05 0.00E-01 0.00E-01 0.00E-01 i
FE 59 7.52E 05 1.5E 06 9.34E 05 1.51E 06 0.00E-01 0.00E-01 4.38E 05 0.00E-01 i
C0 58 2.65E 06 5.05E 06 0.00E-01 8.65E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 C0 O 9.4E 06 1.7E 07 0.00E-01 3.21E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN E 5.74E 08 1.62E 08 3.4E 08 9.24E 08 5.82E 08 0.00E-01 0.00E-01 0.00E-01 i RB 86 4.04E 08 4.22E 07 0.00E-01 6.5E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.38E 08 3.2I 08 8.34E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 3.91 10 2.09E 09 1.55E 11 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 7.45E 01 3.71E 05 2.79E 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZR 95 5.3E 01 6.28E 04 2.74E 02 6.02E 01 8.62E 01 0.00E-01 0.00E-01 0.00E-01 2 95 6.37E 03 1.65E 07 2.29E 04 8.91E 03 8.37E 03 0.00E-01 0.0E-01 0.00E-01 RU 103 1.19E 02 7.98E 03 3.09E 02 0.00E-01 7.7E 02 0.00E-01 0.00E-01 0.00E-01 RU 106 8.5E 02 1.0E 05 6.8E 03 0.00E-01 9.27E 03 0.00E-01 0.00E-01 0.00E-01 AG110M 8.6I 06 1.2E 09 1.60E 07 1.0E 07 2.01E 07 0.00E-01 0.00E-01 0.00E-01 TE127M 2.18E 06 1.49E 07 1.84E 07 4.95E 06 5.24E 07 4.40E 06 0.00E-01 0.00E-01 TE129M 3.28E 06 2.5E 07 2.12E 07 5.91E 06 6.21E 07 6.82E 06 0.00E-01 0.00E-01 1 131 5.85E 08 9.17E 07 1.02E 09 1.03E 09 1.69E 09 3.41E 11 0.00E-01 0.00E-01 1 132 4.67E-01 1.19E 00 5.52E-01 1.01E 00 1.55E 00 4.71E 01 0.00E-01 0.00E-01 I 133 6.58E 06 7.00E 06 1.41E 07 1.74E 07 2.90E 07 3.23E 09 0.00E-01 0.00E-01 1 135 4.01E 04 6.47E 04 4.72E 04 8.49E 04 1.30E 05 7.52E 06 0.00E-01 0.00E-01 CS 134 1.43E 10 3.67E 08 4.14E 10 6.80E 10 2.11E 10 0.00E-01 7.5E 09 0.00E-01 CS 136 3.41E 09 1.8E 08 1.92E 09 5.2 K 09 2.81E 09 0.00E-01 4.19E 08 0.00E-01 CS 137 8.72E 09 3.70E 08 6.17E 10 5.91E 10 1.93E 10 0.00E-01 6.93E 09 0.00E-01 BA 140 5.21 05 4.54E 05 8.9E 06 7.85E 03 2.5E 03 0.00E-01 4.68E 03 0.00E-01 ;
CE 141 1.17E 02 9.81E 05 1.53E 03 7.3E 02 3.45E 02 0.00E-01 0.00E-01 0.00E-01 l CE 144 6.24E 03 9.55E 06 1.1E 05 3.6E 04 2.03E 04 0.00E-01 0.00E-01 0.00E-01
- l l
l
\
i
- R Values in units of mren/yr per micro-Ci/m**3 for inhalation and tritita, and in units of M**2-mres/yr per micro-Cf/sec for all others.
00CM (BSEP) 3-63 Rev. 1 ;
v
- TABLE 3.3-15 R 1EES FtR TE BitalSWICK STEAM ELECTRIC R.AE*
1 l PATWAY = Goat Milk l i AE Gt0VP = infant Nuclide T.8ody GI-Tract gone Liver Kidney Thyroid g Skin i H 3 4.9E 03 4.9E 03 0.00E-01 4.9E 03 4.9E 03 4.9E 03 4.9E 03 4.90E 03 i P 32 4.88E 09 1.70E 09 1.2E 11 7.4E 09 0.00E-01 0.00E-01 0.0E-01 0.00E-01 CR 51 1.1E 04 3.42E 05 0.00E-01 0.00E-01 1.6E 03 7.65E 03 1.49E 04 0.00E-01 MN 54 6.45E 05 1.04E 06 0.00E-01 2.84E 06 6.30E 05 0.00E-01 0.00E-01 0.00E-01 FE 59 1.2T 06 1.45E 06 1.74E 06 3.04E 06 0.00E-01 0.00E-01 9.0E 05 0.00E-01 CO 58 4.31E 06 4.31E 06 0.00E-01 1.73E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CO O 1.55E 07 1.5E 07 0.00E-01 6.5E 06 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZN 65 7.3E 08 1.35E 09 4.6E 08 1. OE 09 7.74E 08 0.00E-01 0.00E-01 0.00E-01
- RB 86 8.2 1 08 4.2E 07 0.00E-01 1.6E 09 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 4.55E 08 3.2E 08 1.59E 10 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 90 4.3E 10 2.11E 09 1.69E 11 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.39E 02 3.75E 05 5.21 03 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ZR 95 8.41E 01 5.90E 04 4.85E 02 1.19E 02 1.2E 02 0.00E-01 0.00E-01 0.00E-01 18 95 1.02E 04 1.4E 07 4.2K 04 1.76E 04 1.2E 04 0.00E-01 0.00E-01 0.00E-01 RU 103 2.09E 02 7.60E 03 6.25E 02 0.00E-01 1.3E 03 0.00E-01 0.00E-01 0.00E-01
, RU 106 1.7E 03 1.0E 05 1.41E 04 0.00E-01 1.67E 04 0.00E-01 0.00E-01 0.00E-01 AG110M 1.41 07 1.12E 09 2.95E 07 2.1E 07 3.0E 07 0.00E-01 0.00E-01 0.00E-01 TE12?M 4.51E 06 1.50E 07 3.72E 07 1.23E 07 9.1E 07 1.00E 07 0.00E-01 0.00E-01 l TE129M 6.69E 06 2.59E 07 4.34E 07 1.49E 07 1.09E 08 1.6E 07 0.00E-01 0.00E-01
. I 131 1.11E 09 8.99E 07 2.14E 09 2.52E 09 2.94E 09 8.2E 11 - 0.00E-01 0.00E-01 I 132 8.28E-01 1.8E 00 1.15E 00 2.31 00 2.59E 00 1.09E 02 0.00E-01 0.00E-01 1 133- 1.2K 07 7.31E 06 2.97E 07 4.32E 07 5.08E 07 7.86E 09 0.00E-01 0.00E-01 1
I 135 7.11E 04 7.0E 04 9.81E 04 1.95E 05. 2.1E 05 1.75E 07 0.00E-01 0.00E-01 CS 134 1.2E 10 3.38E 08 6.6BE 10 1.2SE 11 3.21E 10 0.00E-01 1.31E 10 0.00E-01 CS 136 4.11E 09 1.6K 08 3.75E 09 1.1E 10 4.39E 09 0.00E-01 8.98E 08 0.00E-01 CS 137 8.17E 09 3.61E 08 9.85E 10 1.15E 11 3.10E 10 0.00E-01 1.25E 10 0.00E-01 BA 140 9.50E 05 4.51 06 1.84E 07 1.84E 04 4.3E 03 0.00E-01 1.1 1 04- 0.00E-01 CE 141 2.24E 02 9.85E 05 3.11 03 1.91E 03 5.88E 02 0.00E-01 0.00E-01 0.00E-01 CE 144 9.39E 03 ~ 9.61E 06 1.67E 05 6.8E 04 2.77E 04 0.00E-01 0.00E-01 0.00E-01 l
- R Values in units of mnun/yr per micro-Ci/w'*3 for inhalation and tritiun, and in units of Ma*2-areWyr per micro-C1/sec for all others.
(ECM (BSEP) 3 Rev. 1
TABE 3.3-16 R IN.ES FtR TE BRMSWICK S1EAM E1ECTRIC R. ANT
- PATWAY = Inhal i
AGE GROUP = Adult Huclide T.Bo@ E -Tract Bone Liver Kidney Thymid g Skin H 3 1.2E 03 1.2E 03 0.00E-01 1.2E 03 1.2E 03 1.2E 03 1.2E 03 1.2E 03 P 32 5.00E 04 8. E 04 1.32E 06 7.70E 04 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 9.99E 01 3.32E 03 0.00E-01 0.00E-01 2.2E 01 5.94E 01 1.44E 04 0.00E-01 MN 54 6.29E 03 7.72E 04 0.00E-01 3.95E 04 9.83E 03 0.00E-01 1.40E 06 0.00E-01 FE 59 1.05E 04 1.88E 05 1.1E 04 2.7E 04 0.00E-01 0.00E-01 1.01E 06 0.00E-01 CO 58 2.0E 03 1.0E 05 0.00E-01 1.58E 03- 0.00E-01 0.00E-01 9.2E 05 0.00E-01 C0 (D 1.4E 04 2.84E 05 0.00E-01 1.15E 04 0.00E-01 0.00E-01 5.9E 06 0.00E-01 l
- ZN E5 4.65E 04 5.34E 04 3.24E 04 1.03E 05 6.89E 04 0.00E-01 8. E 05 0.00E-01 ,
! RB 86 5.89E 04 1.6E 04 0.00E-01 1.35E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 8.71E 03 3.49E 05 3.04E 05 0.00E-01 0.00E-01 0.00E-01 1.40E 06 0.00E-01
- SR 90 6.09E 06 7.21E 05 9.91E 07 0.00E-01 0.00E-01 0.00E-01 9.59E 06 0.00E-01 Y 91 1.24E 04 3.84E 05 4.62E 05 0.00E-01 0.00E-01 0.00E-01 1.70E 06 0.00E-01 ZR 95 2.32E 04 1.50E 05 1.0K 05 3.44E 04 5.41E 04 0.00E-01 1.7E 06 0.00E-01 2 95 4.20E 03 1.04E 05 1.41E 04 7.80E 03 7.72E 03 0.00E-01 5.04E 05 0.00E-01 RU 1m 6.5K 02 1.1 E 05 1.53E 03 0.00E-01 5.82E 03 0.00E-01 '5.04E 05 0.00E-01
- RU 106 8.71E 03 9.11E 05 6.90E 04 0.00E-01 1.33E 05 0.00D01 9.35E 06 0.00E-01 AGil(N 5.94E 03 3.02E 05 1.08E 04 9.99E 03 1.9E 04 0.00t-01 4. E 06 0.00E-01 TE127M- 1.5E 03 1.49E 05 1.2E 04 5.7E 03 4.5E 04 3.2E 03 9.59E 05 0.00E-01 l TE129M 1.58E 03 3.8I 05 9.75E 03 4.67E 03 3.65E 04 3.44E 03 1.1E 06 0.00E-01
! I 131 2.05E 04 6.2K 03 2.52E 04 3.57E 04 6.12E 04 1.19E 07' O.00E-01 0.00E-01 I 132 1.1E 03 4.0E 02 1.1E 03 3.25E 03 5.18E 03 1.14E 05 0.00E-01 0.00E-01 I 133 4.51E 03 8.87E 03 8. E 03 1.48E 04 2.58E 04 2.15E 06 0.00E-01 0.00E-01 I 135 2.5E 03 5.24E 03 2.68E 03 6.9E 03 1.11E 04 4.4K 05 0.00E-01 0.00E-01 CS 134 7.27E 05 1.04E 04 3.72E 05 8.4E 05 2.87E 05 0.00E-01 9.75E 04 0.00E-01 CS 136 1.1E 05 1.17E 04 3.90E 04 1.4E 05 8.55E 04 0.00E-01 1.2 E 04 0.00E CS 137 4.27E 05 8.39E 03 4.78E 05 6.20E 05 2.22E 05 0.00E-01 7.51E 04 0.00E-01 I
BA 140 2.5E 03 2.1E 05 3.90E 04 4.9E 01 1.67E 01 0.00E-01 1.2X 06 0.00E-01 CE 141 1.53E 03 1.20E 05 1.99E 04 1.35E 04 6.25E 03 0.00E-01 3.61E 05 0.00E-01 l CE 144 1.84E 05 8.15E OS 3.41 06 1.41 06 -8.47E 05 0.00E-01 7.7E 06 0.00E-01 i
i i
- R: Values in units of mrem /yr per micro-Ci/nF*3 for inhalation and tritiun, and in units of M**2-mrem /yr per micro-Ci/sec for all others.
00CM (BSEP) 3-65 Rev. 1
TABLE 3.3-17 R IN.lES FGt llE BRWSWICK STEAM ELECTRIC R. ANT
- i PATWAY = Inhal AGE Gt0VP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney 1hymid M Skin H 3 1.2 K 03 1.2 K 03 0.00E-01 1.27E 03 1.2 E 03 1.2E 03 1.2 K 03 1.2 K 03 P 32 7.15E 04 9.27E 04 1.89E 06 1.09E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 1.35E 02 3.00E 03 0.00E-01 0.00E-01 3.07E 01 7.49E 01 2.09E 04 0.00E-01 MN 54 8.39E 03 6.6E 04 0.00E-01 5.10E 04 1.27E 04 0.00E-01 1.98E 06 0.00E-01 FE 59 1.41 04 1.7E 05 1.59E 04 3.69E 04 0.00E-01 0.00E-01 1.5I 06 0.00E-01 C0 58 2.77E 03 9.51E 04 0.00E-01 2.07E 03 0.00E-01 0.00E-01 1.34E 06 0.00E-01 C0 E) 1.98E 04 2.59E 05 0.00E-01 1.51E 04 0.00E-01 0.00E-01 8.71E 06 0.00E-01 ZN 65 6.23E 04 4.6E 04 3.85E 04 1.33E 05 8. OE 04 0.00E-01 1.24E 06 0.00E-01 RB 86 8.39E 04 1.7E 04 0.00E-01 1.9E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 1.25E 04 3.71E 05 4.34E 05 0.00E-01 0.00E-01 0.00E-01 2.41E 06 0.00E-01 SR 90 6.67E 06 7.64E 05 1.08E 08 0.00E-01 0.00E-01 0.00E-01 1.65E 07 0.00E-01 Y 91 1.77E 04 4.08E 05 6.fDE 05 0.00E-01 0.00E-01 0.00E-01 2.93E 06 0.00E-01 ZR 95 3.15E 04 1.49E 05 1.45E 05 4.58E 04 6.72 04 0.00E-01 2.6E 06 0.00E-01 M3 95 5.6E 03 9.67E 04 1.85E 04 1.03E 04 9.99E 03 0.00E-01 7.50E 05 0.00E-01 RU 103 8.95E 02 1.09E 05 2.1 % 03 0.00E-01 7.42E 03 0.00E-01 7.82E 05 0.00E-01 RU 106 1.24E 04 9.59E 05 9.83E 04 0.00E-01 1.90E 05 0.00E-01 1.61E 07 0.00E-01 AG110M 7.98E 03 2.72E 05 1.38E 04 1.31E 04 2.5E 04 0.00E-01 6.74E 06 0.00E-01 TE127M 2.18E 03 1.59E 05 1.80E 04 8.15E 03 6.53E 04 4.38E 03 1.65E 06 0.00E-01 TE129M 2.24E 03 4.04E 05 1.39E 04 6.5 K 03 5.18E 04 4.5?E 03 1.97E 06 0.00E-01 l I 131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.4E 07 0.00E-01 0.00E-01
- I 132 1.57E 03 1.2 K 03 1.59E 03 4.37E 03 6.91E 03 1.51E 05 0.00E-01 0.00E-01 I 133 6.21E 03 1.03E 04 1.21E 04 2.05E 04 3.59E 04 2.92E 06 0.00E-01 0.00E-01 l I 135 3.48E 03 6.94E 03 3.69E 03 9.43E 03 1.49E 04 6.20E 05 0.00E-01 0.00E-01 CS 134 5.48E 05 9.75E 03 5.02E 05 1.11 06 3.75E 05 0.00E-01 1.4E 05 0.00E-01 CS 136 1.37E 05 1.09E 04 5.14E 04 1.9I 05 1.1E 05 0.00E-01 1.7E 04 0.00E-01 CS 137 3.11E 05 8.48E 03 6.69E 05 8.47E 05 3.04E 05 0.00E-01 1.21E 05 0.00E-01 BA 140 3.51E 03 2.2E 05 5.4E 04 6.69E 01 2.28E 01 0.00E-01 2.01 06 0.00E-01 CE 141 2.1E 03 1.2E 05 2.84E 04 1.89E 04 8.87E 03 0.00E-01 6.11 05 0.00E-01 i CE 144 2.62E 05 8.63E 05 4.88E 06 2.02E 06 1.21E 06 0.00E-01 1.3I 07 0.00E-01 l
- R Values in units of unm/yr per micm-Ci/#*3 for inhalation and tritita, and in units of Ma*2-mrem /yr per micro-Ci/sec for all others.
00CM (BSEP) 3-66 Rev.'1
TABLE 3.3-18 R ELES FGt TE BRlatSWICK STEAM D.EC1RIC R. ANT
- PATmiAY = Inhal AE GROUP = Child Nuclide T.Bo@ GI-Tract Bone Liver Kidney Thyroid g Skin H 3 1.12E 03 1.12E 03 0.00E-01 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 P 32 9.86E 04 4.21E 04 2.6DE 06 1.14E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 1.54E 02 1.08E 03 0.00E-01 0.00E-01 2.43E 01 8.51 01 1.70E 04 0.00E-01 MN 54 9.50E 03 2.29E 04 0.00E-01 4.29E 04 1.00E 04 0.00E-01 1.57E 06 0.00E-01 FE 59 1.67E 04 7.0E 04 2.072 04 3.34E 04 0.00E-01 0.00E-01 1.2X 06 0.00E-01 C0 58 3.1E 03 3.43E 04 0.00E-01 1.77E 03 0.00E-01 0.00E-01 1.10E 06 0.00E-01 C0 60 2.2E 04 9.61E 04 0.00E-01 1.31E 04 0.00E-01 0.00E-01 7.0E 06 0.00E-01 ZN 65 7.02E 04 1.8E 04 4.25E 04 1.13E 05 7.13E 04 0.00E-01 9.94E 05 0.00E-01 RB 86 1.14E 05 7.9E 03 0.00E-01 1.98E 05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 1.72E 04 1.67E 05 5.99E 05 0.00E-01 0.00E-01 0.00E-01 2.15E 06 0.00E-01 SR 90 L.4I 06 3.41 05 1.01E 08 0.00E-01 0.00E-01 0.00E-01 1.47E 07 0.00E-01 Y 91 2.43E 04 1.84E 05 9.!.3E 05 0.00E-01 0.00E-01 0.00E-01 2.62E 06 0.00E-01 ZR 95 3.69E 04 6.1E 04 1.90E 05 4.1X 04 5.95E 04 0.00E-01 2.21 06 0.00E-01 16 95 6.54E 03 3.69E 04 2.25E 04 9.1E 03 8.61E 03 0.00E-01 6.13E 05 0.00E-01 RU 103 1.07E 03 4.47E 04 2.79C 03 0.00E-01 7.02E 03 0.00E-01 6.61E 05 0.00E-01 RU 106 1.69E 04 4.29E 05 1.3E 05 0.00E-01 1.84E 05 0.00E-01 1.43E 07 0.00E-01 AG110M 9.13E 03 1.0E 05 1.68E 04 1.14E 04 2.12E 04 0.00E-01 5.47E 06 0.00E-01 TE127M 3.01E 03 7.13E 04 2.48E 04 8.53E 03 6.35E 04 6.0E 03 1.48E 06 0.00E-01 TE129M 3.04E 03 1.81E 05 1.92E 04 6.84E 03 5.02E 04 6.32E 03 1.7E 06 0.00E-01 1 131 2.72E 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 0.00E-01 0.00E-01 I 132 1.87E 03 3.20E 03 2.11E 03 4.0E 03 6.24E 03 1.91 05 0.00E-01 0.00E-01 I 133 7.68E 03 5.47E 03 1.6E 04 2.03E 04 3.37E 04 3.84E 06 0.00E-01 0.00E-01 I 135 .4.14E 03 4.41 03 4.91E 03 8.72E 03 1.34E 04 7.91E 05 0.00E-01 0.00E-01 CS 134 2.24E 05 3.84E 03 6.50E 05 1.01E 06 3.3T 05 0.00E-01 1.21E 05 0.00E-01 CS 136 1.1E 05 4.17E 03 6.5% 04 1.71E 05 9.51 04 0.00E-01 1.45E 04 0.00E-01 CS 137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 0.00E-01 1.04E 05 0.00E-01 BA 140 4.32E 03 1.02E 05 7.39E 04 6.47E 01 2.11E 01 0.00E-01 1.74E 06 0.00E-01 CE 141 2.89E 03 5.65E 04 3.92E 04 1.95E 04 8.53E 03 0.00E-01 5.43E 05 0.00E-01 CE 144 3.61E 05 3.88E 05 6.7E 06 2.11E 06 1.17E 06 0.00E-01 1.19E 07 0.00E-01
- R Values in units of mnsn/yr per micro-Ci/nF*3 for inhalation and tritiun, and in units of M**2-mreWyr per micro-Ci/sec for all others.
00CM (BSEP) 3-67 Rev. 1
1 TABLE 3.3-19 R IN.ES FGt TE BRtMSWICK STEAM ELECTRIC R.ANP PATlWAY = Inhal AE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney 1hymid g Skin H 3 6.4 E 02 6.4E 02 0.00E-01 6.4E 02 6.4 E 02 6.4 E 02 6.4 E 02 6.4 E 02 P 32 7.73E 04 1.61E 04 2.03E 06 1.12E 05 0.00E41 0.00E-01 0.00E-01 0.00E-01 CR 51 8.91 01 3.5E 02 0.00E-01 0.00E-01 1.32E 01 5.75E 01 1.28E 04 0.00E-01 MN 54 4.98E 03 7.05E 03 0.00E-01 2.53E 04 4.98E 03 0.00E-01 9.98E 05 0.00E-01 FE 59 9.4E 03 2.4 E 04 1.35E 04 2.35E 04 0.00E-01 0.00E-01 1.01E 06 0.00E-01 C0 58 1.82E 03 1.11E 04 0.00E-01 1.22E 03 0.0E-01 0.00E-01 7.76E 05 0.00E-01 C0 El 1.18E 04 3.19E 04 0.00E-01 8.01E 03 0.00E-01 0.00E-01 4.5E 06 0.00E-01 4
ZN 65 3.10E 04 5.13E 04 1.93E 04 6.25E 04 3.24E 04 0.00E-01 6.4E 05 0.00E-01 RB 86 8.81E 04 3.01 03 0.00E-01 1.90E 05 0.0CE-01 0.00E-01 0.00E-01 0.00E-01 SR 89 1.14E 04 6.39E 04 3.97E 05 0.00E-01 0.0E-01 0.00E-01 2.03E 06 0.00E-01 SR 90 2.59E 06 1.31E 05 4.0E 07 0.00E-01 0.00E-01 0.00E-01 1.12E 07 0.00E-01 Y 91 1.57E 04 7.02E 04 5.87E 05 0.00E-01 0.00E-01 0.00E-01 2.45E 06 0.00E-01 ZR 95 2.03E 04 2.1E 04 1.15E 05 2.7E 04 3.10E 04 0.00E-01 1.75E 06 0.00E-01 16 95 3.77E 03 1.27E 04 1.5E 04 6.42E 03 4.71E 03 0.00E-01 4.78E 05 0.00E-01 RU 103 6.7E 02 1.61E 04 2.01E 03 0.00E-01 4.24E 03 0.00E-01 5.51E 05 0.00E-01 i
RU 106 1.09E 04 1.64E 05 8.67E 04 0.00E-01 1.0E 05 0.00E-01 1.15E 07 0.00E-01 AG110M 4.99E 03 3.30E 04 9.97E 03 7.21E 03 1.09E 04 0.00E-01 3.6E 06 0.00E-01 TE127M 2.07E 03 2.73E 04 1.6E 04 6.89E 03 3.75E 04 4.8E 03 1.31E 06
' 0.00E-01 TE129M 2.22E 03 6.89E 04 1.41E 04 6.0E 03 3.17E 04 5.47E 03 1.6E 06 0.00E-01 1 131 1.96E 04 1.0E 03 3.79E 04 4.43E 04 5.17E 04 1.48E 07 0.00E-01 0.00E-01 I 132 1.2E 03 1.90E 03 1.69E 03 3.54E 03 3.94E 03 1.69E 05 0.00E-01 0.00E-01 I 133 5.59E 03 2.15E 03 1.32E 04 1.92E 04 2.24E 04 3.55E 06 0.00E-01 0.00E-01 I 135 2.77E 03 1.83E 03 3.8E 03 7.59E 03 8.4E 03 6.95E 05 0.00E-01 0.00E-01 CS 134 7.44E 04 1.33E 03 3.96E 05 7.02E 05 1.90E 05 0.00E-01 7.95E 04 0.00E-01 CS 136 5.28E 04 1.41 03 4.82E 04 1.34E 05 5.63E 04 0.00E-01 1.17E 04 0.00E-01 CS 137 4.54E 04 1.33E 03 5.48E 05 6.11E 05 1.72E 05 0.00E-01 7.12E 04 0.00E-01 BA 140 2.89E 03 3.83E 04 5.59E 04 5.59E 01 1.34E 01 0.00E-01 1.59E 06 0.00E-01 CE 141 1.99E 03 2.15E 04 2.77E 04 1.6E 04 5.24E 03 0.00E-01 5.1E 05 0.00E-01 CE 144 1.7E 05 1.4E 05 3.19E 06 1.21E 06 5.37E 05 0.00E-01 9.8I 06 0.00E-01 l
- R Values in units of mrtm/yr per micro-Ci/e*3 for inhalation and tritiun, and in units of M*2-mrem /yr per micro-Cf/sec for all others.
1 00CM (BSEP) 3-68 Rev. 1
4.0 RADIOLOGICAL ENVIROIMENTAL MONITORING PROGRAM Table 4.0-1 contains the sample point description, sampling and collection frequency analysis, and analysis frequency for varicus exposure pathways in the vicinity of the BSEP for the radiological monitoring program. Figures 4.0-1a, 4.0-lb, 4.0-1c, and 4.0-1d show the locations of the various points.
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TARLE 4.0-1 RADIOLOGICAR. ENVIRDISENTAL IGNITORING FROGRAft Exposure rataway sampie sample reint mescription. approntmate sampilng ans analysis AnalysisI *I and/or Sample Feint (s) Distance. and Direction Collection Frequency Frequency DIRECT RADIATION 1-12(e) Refer to Figure 4.0-ta Q Q Gausa Dose-13 1.1 miles E - Refer to Figure 4.0-lb and Ffgure 4.0-Ic Q Q Gonna Dose 14 1.0 elles ESE Q Q Gausne Dose 15 0.9 alles SE Q Q Gamma Dose 16 1.1 miles SSE Q Q Gaume Dose 17 1.1 miles S Q .Q Gaassa Dose 18 1.0 miles S Q Q Gamme Dose 19 1.0 miles SW Q Q Gausna pose 20 1.2 elles W Q Q Gaasme Dose 21 1.0 miles WNW Q Q Gaussa Dose 22 - 0.9 miles NW Q Q Gassee Dose
,s, 23 0.9 alles NNW Q Q Gansna Dose 24 1.0 miles N Q Q Gansna Dose 25 1.2 miles NME Q Q Gassna Dose 26 0.5 miles NE Q Q Gasuna Dose 27 0.9 miles ENE Q Q Gasuna Dose 28 1.0 miles WSW Q Q Gaasna Dose 29 1.5 miles ESE Q Q Gausna Dose 30 -
1.7 elles SE Q Q Gansaa Dose 31 2.0 miles SSE Q Q Gaasna nose 32 2.1 miles S Q Q Gassna Dose 33 2.9 miles SSW Q Q Gausna Dose 34 5.3 miles SW Q Q Gassna Dose 35 4.6 miles WSW Q Q Gaauna Dose 36 3.0 miles W Q Q Gansen Dose 37 8.7 miles WNW Q Q Gamuna Dose 38 5.9 miles NW Q Q Gaasua Dose 39 3.8 miles NNW Q Q Gausna Dose 40 2.3 miles N Q Q Gaasna Dose 41 2.0 miles IINE Q Q Gasana Dose
, 42 2.0 miles IE Q Q Gaasna Dose y 43 2.6 miles ENE Q Q Gausna Dose
- 44 5.7 elles E near Kure Beach Q Q Gaassa Dose
- 45 4.3 elles E 9 Ferry Slip N.H. Co. Q Q Gansna Dose
8 9 '
g TABLE 4.0-1 (continued) b
~
Exposere rattuay sampie sampie Fernt gescrfptson, Jupprontmate sampitag and Analysts Collection Frequency Frequency Analysis (a)
_and/or Sample Pelat(s) Distance, and Direction 46 5.5 mIIes EE D Ft. Fisher AFB Q Q Gasma Dose DIRECT RADIATION 7.2 miles EE 9 Kure Beach Q Q Gasse Do:e (cont) 47 Gamme Dose 48 9.3 miles E 9 Carolina Beach Q Q 49 5.5 miles IAf 9 Bolling Spring Lakes Q Q Ganna Dose 11.0 miles W D Sunset Harbor Q Q Gamma Dose 50 51 5.3 miles SW 9 Youpon Beach Q Q Gassea Dose 6.9 miles WSW D Long Beach Q Q Gamma Dose 52 53 8.5 miles WSW 9 Ocean Crest Pier Q Q Gaasna Dose 54 10.9 elles WSW 9 Long Beach Pier 0 Q Gaauna Dose ,
12.0 miles WSW 9 Blue Water Point 0 Q Gaauna Dose 55 56 4.5 alles S 9 Ft. Caswell Bapt. Assy. Q Q Gasuna Dose 57 4.8 miles SSW 9 Caswell Beach Q Q Gaasna Dose 58 5.3 elles SSE 9 Bald Head Island Q Q Gassna Dose 10.0 miles NE Hwy.133 9 SR 1521 0 Q Ganoma Dose
'?w 59 60 9.5 miles N SR 1539 9 SR 1521 Q Q Gaauna Dose 61 9.5 miles E Hwy. 87 9 SR 1513 0 Q Gaasna Dose 62 10.0 alles WNW Midway Rd. 9 SR 1508 Q Q Gasuna Dose 63 11.0 miles W Hwy. 211 0 SR 1112 Q Q Gaamu Dose AIR 80RE 64 1.0 miles SW Visitors Center Continuous sampler operation W Radiofodine Canister 65 0.6 miles E FMAC with sample collected weekly I-lJ1 analysts Radiolodine 66 1.0 mIIes S Substation - Const. Rd. or as required by dust load- Particulate Sampler and Particulate 67 2.3 elles SSW Southport Substation ing. whichever is more frequent. - Gross beta radioactivity 68 23 miles NNE Sutton Plant - Control (c) analysisfollog 69 4.9 miles SSW Caswell Beach 9 Pumps filter change.
70 0.1 elles SW Discharge Weir 71 0.9 alles Bethel Church - Cemetary Q Ganna isotopic analysis 72 0.6 alles SE Spoil Pond of composite by location k
C
TABLE 4.0-1 (continued)
Esposure Fathway 5 ample 5 ample Point Descr1ytIon. ApproxImete 5ampifog and Analysis and/or Sample Point (s) Distance, and Direction Collection Frequency Frequency Analystsg ,y WATER 80ftllE
- a. Surface 73 0.7 miles IE Intake Canal - ControI ICI Compostte Sasyle(d) Monthly Gaume Isotopic - Monthly Collection - M Q Trftfue 74 4.9 miles SSW Discharge Canal 9 Still Pond
- b. Sediment 75 4.9 alles SSW 01scharge - Beach Sealannual Sealannual Ganana Isotopic
- INGESTIDIl
- a. Milk 76 0.9 mfles SE Steven's Farm WIth animals on pasture - SM Seminenthly r.a=== lsotopic (animals g
At other times - M on pasture) 77 14.5 miles leIW Johnson's Fam - Control gy Seminenthly 1-131 analyses (animals on pasture)
- Monthly Gamma Isotopic (other b times)
Monthly I-131 analysis (other times)
- b. Fish and 78 5. elles $$E Atlantic Ocean 9 Discharge When in season - Sealannual Gaume 1Sotopic on Invertebrates 79 5. miles SSE Atlantic Ocean 9 Discharge Sealannual edible portions (shrimp) 80 5. miles SSE Atlantic Ocean 9 Discharge 81 llot specified - Atlantic Ocean
- c. Broadleaf 82 0.7 miles IIE Intake Canal When available - Monthly Monthly Gaasna Isotopic Vegeta tion 83 0.6 alles SW Discharge Canal ggy Monthly 1-131 84 10 elles - Control - Location not Specified (a) The LLD for each analysis is spectfled 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 radf ation 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. Perfom gasuna scan on each sample when gross beta activity is 10 times the mean of control station.
ICI Control Station - These stations are presumed to be outside the influence of plant effluents.
(d) Compostte samples s'nal! be ecliected 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 />.
- ~
(e) These sample points are fer plant inforiaatton only and are not intended for compliance with technical specifications.
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5.0 INTERLABORATORY COMPARISON STUDIES .
5.1 OBJECTIVE i The objective of this program is to evaluate the total laboratory analysis process by comparing results with results obtained by a separate laboratory or laboratories for an equivalent sample.
5.2 ,
PROGRAM 5.2.1 Environmental Sample Analyses Comparison Program i
Environmental samples from the BSEP environs are to be analyzed by the Harris Energy & Environmental Center or by a qualified contracting laboratory. These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the laboratories' perfor-mances in the study will be provided to BSEP EARC. The results will be provided to the NRC upon request.
i 5.2.2 Effluent Release Analyses Program BSEP E&RC will perform sample analyses for gama-emitting radionuclides in effluent releases. The E8RC radiochemistry laboratory will participate annu-ally in a corporate interlaboratory comparison study or an equivalent study.
The results of these studies will be provided to the NRC upon request.
5.2.3 Abnormal Results If the'CP&L laboratory or vendor laboratory results lie at greater than.three i
sigma from the " recognized value," an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete docu-
- mentation on the evaluation will be available to BSEP and will be provided to the NRC.upon request.
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00CM (BSEP) 5-1 Rev. O i
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6.0 TOTAL DOSE (40CFR190 CONFORMANCE) ) !
6.1 Compliance with 40CFR190 as prescribed by Specification 3.11.4 is to )
be demonstrated only when one or more of Specifications 3.11.1.2.a. l 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a, and 3.11.2.3.b is exceeded by a factor of 2. Once this occurs the Company has 30 days to submit this report.
6.2 To perform the calculations to evaluate conformance with 40CFR190, an effort is made to develop doses that are realistic by removing assumptions that lead to overestimates of dose to a MEMBER OF THE PUBLIC (i.e., calculations for compliance with 10CFR50, App. I). To accomplish this the following calculational rules are used:
(1) Doses to- a MEMBER OF THE PUBLIC via the liquid release pathway are considered to be <1 mrem /yr. (Ref: NUREG 0543).
(2) Doses to a MEMBER OF THE PUBLIC due to a milk pathway will be evaluated only as can be . shown to exist. Otherwise, doses via
]
this pathway will be estimated as <1 mrem /yr.
(3) Environmental sampling data which demonstrates that no pathway exists may be used to delete a pathway to man from a calculation.
(4) To sum numbers represented as "less than" (<), use the value of the largest number in the group.
4 i
(i.e., <5 + <1 + <1 + <3 = 5)
(5) When doses via direct . radiation are added to doses via inhalation pathway, they will be calculated for the same 4
distance in the same. sector.
I' (6) The calculational locations for a EMBER OF THE PUBLIC will .only be at residences or places of employment.
]
NOTE: Additional assumptions may be used to provide situation-specific parameters, provided they are documented along with their concomitant bases.
4 6.3 CALCULATIONS OF TOTAL BODY DOSE Estimates will be.made for each of the following exposure pathways to the same location by age class. Only those age classes known to exist at a location are considered.
6.3.1 Direct Radiation ,
The component of dose to a EMBER OF THE PUBLIC due to direct radiation will be determined by:
(1) Determining the direct radiation dose at the plant boundary in each sector, D B ,0* -]
(2) Extrapolate that dose to the calculational location as follows:
D L,e =DB,e (1.49 E + 6) i (Xf.e DL ,0 = dose at calculational location in sector e.
- 1.49E+6 = square of mean distance to the site boundary (1220 m).
XL ,e = Distance to calculational locations in sector e in meters.
L i
t a
. - .- - l -. - - - . .
6.3.2 Inhalation Dose The inhalation dose will be determined at the calculational locations for each age class at risk according to the methods outlined in Section 3.3 of this manual.
6.3.3 Ingestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as <1 mrem /yr.
6.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as <1 mrem /yr.
6.4 THYROID DOSE The dose to the thyroid will be calculated for each sector as the sum of inhalation dose and milk ingestion dose (if existing). The calculational -
methods will be those identified in Section 3.3 of this manual.
6.5 Dose projections are to incorporate planned plant operations such as power reduction or outages for the projected period.
l l
APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS
)
Carolina Power & Light Company (CP&L) engaged the services of Dames and Moore to assest the transport and dispersion of the effluent in the atmosphere as outlined 1. Preparation of Radiological Effluent Technical -Specifications for Nuclear - Power Plants, NUREG 0133 (USNRC, 1978). The methodology for this l
. assessment was based on guidelines presented in Regulatory Guide (RG) 1.111, l Revision 1 (USNRC,1977). The results of the assessment were to provide the i , relative depositions flux and relative concentrations (undepleted and depleted) based on numercial models acceptable for use in Appendix I evalua-l tions.
- Regulatory Guide 1.111 presented three acceptable diffusion models for use in j estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-tr'ansport theory),
(2) puff-advection model (a variable trajectory model based on the statistical I
approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the 4
most widely used model based on a statistical approach). It was resolved that ,)
i for operational efficiency, the straight line described in X00000 Program for tt.e Meteorological Evaluation of Routine Effluent Releases at Nuclear Power j Stations (Draft), NUREG 0324 (USNRC, September 1977) would be used for generating the required analyses of Appendix 1. To provide a more realistic
! accounting of the variability of wind around the plant site, ter-rain / recirculation correction factors (TCF) were to be determined from a combined puff-advection/ straight-line scheme for a . one-year meteorological data base.
Dames and Moore was provided a one-year record of meteorological data from the !
i on-site meteorological program at the Brunswick Steam Electric Plant. This data consisted of all collected parameters at both the 11.46-meter ard l
104.55-meter tower levels for the year 1977. The description of the model used and the results of the computations are presented in Reference 1. The following ' tables from Reference 1 provide the basis for the meteorological dilution factor development of the Technical Specifications for Appendix I and ODCM (BSEP) A-1 Rev. 0 i
- f. e ,, . , , , , . - - - - - -, ,,, - , - , ,_ *,_..,.w-m n , , - , , - - -
V ---we ,--,,,....---u-
were the source of the X/Q_ and D/Q values utilized to show compliance with 10CFR20 and 10CFR50 for noble gases and radioiodines and particulates.
]l Tables A-1 through A-6 Relative undepleted concentration, rela-tive depleted concentration, and relative deposition flux estimates for ground- l 1evel release for both standard distances and special locations.
Tables A-7 through A-12 Relative undepleted concentration, rela-tive depleted concentration, and relative deposition flux estimates for mixed-mode
- release for both standard distances and special locations.
Tables A-13 through A-18 Relative undepleted concentration, rela-tive depleted concentration, and relative
! deposition . flux estimates for elevated i release for both standard distances and -~,
special locations.
It should be noted that the values of X/Q, depleted X/Q, and D/Q for the stack i releases to the special locations take into consideration the offset of the stack from the plant center. This is not true for the X/Q, depleted X/Q, and D/Q values at the standard distances. These values are based upon the dis-tance from the stack to the point of interest. These values should be good except for the close-in distances.
Future Operation Computations The NRC "X0QD0Q" Program (Revision 1) was obtained and installed on the CP&L computer system. For routine meteorological dispersion evaluations, the
! "X0QD0Q" Program will be run with the appropriate physical plant data, appro-I priate meteorological information for the standard distances, and special
( locations of interest without a terrain / recirculation factor. The input to "X0QD0Q" for ground-level releases are presented in Table A-19 and for ,
elevated releases in Table A-20. The resulting computations will have applied the TCFs to produce a final atmospheric diffusion estimate for the site. ])
In general, it is concluded that the straight-line model is as reasonable a projection of concentrations as the puff-advection model. By inclusion of the terrain correction factors developed by a combination of the puff-advection/
straight-line scheme with the results of the X0QD0Q Program, ready evaluation of on-site meteorological data may be made.
I i
f
A-3 Rev. 0 ,
Reference Chandler, Martin W. and George Hoopes, Revised Radiological Effluent Technical Specifications: Gaseous Effluent Dilution Factors, Prepared for Carolina Power & Light Company, Brunswick Facility, Dames and Moore, January 18, 1979.
1 i
i i
g
.)
Table A-1 A
x/Q Values at the Special Locations for Releases from the Turbine Buildings )
Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./ Cubic Meter)
Calculation Points: Special Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Ye:
Number of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident Garden NNE 3.01E-06 0. 1.15E-06 1.66E-06 7.88E-07 NE 1.93E-06 0. O. 4.63E-07 0.
ENE 4.15E-06 0. O. O. O.
E 4.40E-06 0. O. 2.51E-06 0. ])
ESE 5.91E-06 0. O. O. O.
SE 4.70E-06 0. 3.15E-06 2.86E-06 2.32E-06 SSE 7.60E-06 6.96E-06 6.76E-06 6.96E-06 0.
5 2. 34E-06 0. O. 1.28E-06 1.12E-06 SSW 1.78E-06 0. O. 1.00E-06 1.00E-06 SW 1.82E-06 0. 6.78E-07 1.82E-06 1.45E-06 WSW 1.81E-06 0. O. 1.20E-06 1.20E-06 W 1.78E-06 0. 7.48E-07 1.10E-06 1.10E-06 WNW 1.74E-06 0. O. 1.06E-06 1.01E-06 NW 1.06E-06 0. O. 8.23E-07 3.61E-08 NNW 1.96E-06 0. O. 1.06E-06 8.89E-07 N 1.67E-06 0. O. 9.63E-07 1.04E-06
- A zero indicates that this point was not calculated.
.-)
Table A-2 Depleted x/Q Values at the Special Locations for q Releases from the Turbine Buildings '
Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level Variable: Relative Depleted Concentration (Sec./ Cubic Meter)
Calculation Points: Special Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident Garden l
NNE 2.71E-06 0. 1.00E-06 1.52E-06 6.77E-07 NE 1.69E-06 0. O. 3.68E-07 0.
ENE 3.71E-06 0. O. O. O.
E ESE 3.94E-06 5.28E-06 0.
0.
O.
O.
2.23E-06 O.
0.
O.
]
SE 4.18E-06 0. 2.70E-06 2.43E-06 2.03E-06 SSE 6.68E-06 6.03E-06 6.06E-06 6.03E-06 0.
S 2.05E-06 0. O. 1.09E-06 9.44E-07 SSW 1.64E-06 0. O. 8.49E-07 8.49E-07 SW 1.62E-06 0. 5.70E-07 1.62E-06 1.27E-06 WSW 1.67E-06 0. O. 1.05E-06 1.05E-06 W 1.63E-06 0. 6.53E-07 9.72E-07 9.72E-07 WNW 1.58E-06 0. O. 9.42E-07 8.96E-07 NW 9.58E-07 0. O. 7.27E-07 2.66E-08 NNW 1.77E-06 0. O. 9.36E-07 7.82E-07 N 1.39E-06 0. O. 8.56E-07 9.17E-07
. *A zero indicates that this point was not calculated. ;
.)
Table A-3 D/Q Values at the Special Locations for Releases from the Turbine Buildings ]
Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Ground Level
- Variable: Relative Decomposition Rate (Meter **-2)
- Calculation Points: Special Model: Straight Line ( ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident Garden NNE 1.66E-08 0. 5.95E-09 8.85E-09 3.94E-09 NE 1.19E-08 0. O. 2.32E-09 0.
ENE 1.19E-08 0. O. O. O. ...
E 9.86E-09 0. O. 5.30E-09 0.
ESE 1.46E-08 0. O. O. O.
SE 1.11E-08 0. 7.35E-09 6.58E-09 5.36E-09 SSE 1.52E-08 1.39E-08 1.35E-08 1.39E-08 0.
S 4.68E-09 0. O. 2.43E-09 2.04E-09 SSW 4.79E-09 0. O. 2.47E-09 2.47E-09 SW 7.45E-09 0. 2.31E-09 7.45E-09 5.70E-09 WSW 7.24E-09 0. O. 4.59E-09 4.59E-09 W 6.08E-09 0. 2.37E-09 3.58E-09 3.58E-09 WNW 5.54E-09 0. O. 3.27E-09 3.07E-09 NW 3.92E-09 0. O. 3.02E-09 8.42E-11 NNW 7.67E-09 0. O. 3.99E-09 3.20E-09 N 7.65E-09 0. O. 4.41E-09 4.79E-09 i
- A zero indicates that this point was not calculated.
l .)
00CM (BSEP) A-7 Rev. 0
<py ,- -
~o Table A-4 8
x/Q Values at the Standard Distances for Releases from the Turbine Buildings sa k) Carolina Power & Light Company - Brunswick
-- Release Type: Annual Release. Mode: Ground Level Variable: Relative Concentration (Sec./ Cubic Meter)
Calculation Points: Standard Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers -
Design .
Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 ~
Sect Mi .40 1.21 2.01 2.82 3. 62 4.42 5.23 6.03 6.84 7. 64 NNE 0. 1.5E-05 2.3E-06 9.4E-07 5.9E-07 3.5E-07 2.4E-07 1.9E-07 1.5E-07 1.2E-07 9.0E-08 NE - 0. 2.0E-05 2.9E-06 1.3E-06 7.3E-07 4.5E-07 3.4E-07 2.7E-07 2.0E-07 1.7E-07 1.4E-07 ENE 0.- 2.1E-05 3.2E-06 1.2E-06 6.5E-07 4.8E-07 3. 6E-07 2.9E-07 2.1E-07' 1.8E-07 1.4E-07 j" E 0. 2.9E-05 ' 0E-06
. 1.5E-06 9.1E-07 6.6E-07 4.4E-07 3.5E-07 2.8E-07 2.2E-07 1.9E-07
~ '
- ESE 0. 3.2E-05 5 -06 2.2E-06 1.0E-06 6.5E-07 4.4E-07 3. 6E-07 2.9E-07 2.4E-07 1.9E-07 SE 0. 2.3E-05 ' 4t 1. 6E-06 7.9E-07 4.8E-07 3.3E-07 2.4E-07 2.2E-07 1.8E-07 1.6E-07 '
SSE Of 4.4E-05 ^ co- 3.1E-06 1.8E-06 1.2E-06 7.7E-07 5.1E-07 3.9E-07 3.2E-07 2.5E-07 S 0. 2.7E-05 3.8E-06 1. 6E-06 9.8E-07 7.2E-07 4.9E-07 3.7E-07 2.9E-07 2.2E-07 1.8E-01 SSW 0. 1.9E-05 .2.8E-06 1.2E-06 8.0E-07 4.9E-07 2.9E-07 2.3E-07 2.2E-07 1.3E-07 1.1E-07 SW 0. 1.8E-05 2.5E-06 1.1E-06 6.6E-07 4.9E-07 2.8E-07 2.2E-07 1.7E-07 1.4E-07 1.1E-07 WSW 0. 1.5E-05 1.8E-06 7.5E-07 3.8E-07 2.8E-07 1.8E-07 1.5E-07 1.2E-07 9.5E-08 7.9E-08 W 0. 1.3E-05 1.5E-06 6.9E-07 3.3E-07 2.2E-07 1.5E-07 1.1E-07 9.4E-08 8.1E-08 5.2E-08 WNW 0, 1.0E-05 1.2E-06 6.0E-07 2.8E-07 1. 6E-07 1.3E-07 8. 6E-08 7.2E-08 5.4E-08 4.4E-08 NW .0. 7.1E-06 9.7E-07 3.5E-07 2.1E-07 1. 6E-07 1.2E-07 7.8E-08 6. 6E-08 4. 6E-08 3.9E-08 NNW 0. 8.9E-06 1.3E-06 5.4E-07 2.7E-07 1.7E-07 1.3E-07 1.1E-07 9.3E-08 6. 6E-08 5.3E-08 N 0. 9.2E-06 1.4E-06 5.1E-07 3.3E-07 2.1E-07 1. 6E-07 1.3E-07 1.1E-07 8.1E-08 7.0E-08 2, Number of Valid Observations 8678 3 Number of Invalid Observations 82 Number of Calms Lower Level 125 c) Number of Calms Upper Level 0 k.- U d
o Table A-5 h Depleted x/Q Values at the Standard Distances for Releases from the Tuttine Buildings co El Carolina Power & Light Company - Brunswick 25 Release Type: Annual Release Mode: Ground Level Variable: Relative Concentration (Sec./ Cubic Meter)
Calculation Points: Standard
- Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes
- Number of Observations: 8678 Base Distance in Miles / Kilometers !
Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 _2.82 3 . 62 4.42 5.23 6.03 6.84 7. 64
.NNE 0. 1.5E-05 2.0E-06 8.1E-07 4.8E-07 2.8E-07 1.9E-07 1.5E-07 1.1E-07 8.9E-08 6.8E-08 NE 0. 1.8E-05 2. 6E-06 1.1E-06 6.1E-07 3.7E-07 2. 6E-07 2.1E-07 1.5E-07 1.2E-07 1.0E-07 ENE 0. 2.0E-05 2.9E-06 1.0E-06 5.5E-07 3.9E-07 2.8E-07 2.2E-07 1. 6E-07 1.3E-07 1.0E-07 T' E 0. 2.7E-05 3.4E-06 1.3E-06 7. 6E-07 5.3E-07 3.5E-07 2. 6E-07 2.2E-07 1.6E-07 '1.4E-07 ,
e ESE 0. 3.0E-05 4. 6E-06 1.9E-06 8.7E-07 5.3E-07 3.5E-07 2.8E-07 2.3E-07 1.7E-07 1.4E-07 SE 0. 2.2E-05 3.1E-06 1.3E-06 6. 6E-07 3.9E-07 2. 6E-07 1.9E-07 1. 6E-07 1.3E-07 1.2E-07 SSE 0. 4.2E-05 6.8E-06 2.7E-06 1.5E-06 9.9E-07 6.1E-07 4.0E-07 3.0E-07 2.4E-07 1.9E-07 S 0. 2.5E-05 3.5E-06 1.3E-06 8.1E-07 5.9E-07 3.9E-07 2.9E-07 2.2E-07 1. 6E-07 1.4E-07 SSW 0. 1.9E-05 2.5E-06 1.0E-06 6. 6E-07 4.0E-07 2.3E-07 1.8E-07 1. 6E-07 1.0E-07 8.3E-08 SW 0. 1.7E-05. 2.4E-06 9.8E-07 5.5E-07 3.9E-07 2.3E-07 1.7E-07 1.3E-07 1.1E-07 9.0E-08 WSW 0. 1.4E-05 1.5E-06 6.4E-07 3.2E-07 2.2E-07 1.4E-07 1.1E-07 9.2E-08 7.0E-08 5.9E-08 W 0. 1.2E-05 1.3E-06 5.9E-07 2.7E-07 1.8E-07 1.1E-07 8.3E-08 7.2E-08 6.1E-08 3.8E-08 WNW 0. 9.9E-06 1.1E-06 '5.2E-07 2.4E-07 1.3E-07 1.0E-07 6.6E-08 5.5E-08 4.1E-08 3.3E-08 NW 0. 6.7E-06 8.7E-07 3.0E-07 1.8E-07 1.3E-07 9.4E-08 6.1E-08 5.1E-08 3.5E-08 3.0E-08 NNW 0. 8.5E-06 1.1E-06 4.7E-07 2.2E-07 1.3E-07 1.1E-07 8.3E-08 7.2E-08 5.0E-08 3.9E-08 N 0. 8. 6E-06 1.2E-06 4.4E-07 2.8E-07 1.7E-07 1.3E-07 1.0E-07 8.2E-08 6.1E-08 5.1E .
gi Number of Valid Observations 8678
.. Number-of Invalid Observations 82 c3 Number of Calms Lower Level 125 i
Number of Calms Upper Level 0 b b d
o Table A-6 D/Q Values at the Standard Distances for Releases from the Turbine Butidings E Carolina Power & Light Company - Brunswick 25 Release Type: Annual -
- Release Mode
- Ground Level '
i Variable: Relative Decomposition Rate (Meter **-2)
Calculation Points: Standard Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3. 62 4.42 5.23 6.03 6.84 7. 64 NNE 0. 8. 6E-08 1.3E-08 4.8E-09 2.8E-09 1.5E-09 9.9E-10 7.7E-10 5.7E-10 4.3E-10 3.3E-10 NE 0. -1.3E-07 1.9E-08 7. 6E-09 4.0E-09 2.3E-09 1. 6E-09 1.3E-09 8.8E-10 6.8E-10 5.7E-10 ENE 0. 5.8E-08 9.4E-09 3.2E-09 1. 6E-09 1.1E-09 7.5E-10 5.5E-10 3.9E-10 3.0E-10 2.3E-10
> E 0. 6.2E-08 8. 6E-09 3.1E-09 1.7E-09 1.1E-09 6.9E-10 5.1E-10 3.9E-10 2.9E-10 2.3E-10 l-.
ESE 0._ 7.2E-08 1.3E-08 5.0E-09 2.2E-09 1.2E-09 7. 6E-10 6.0E-10 4.7E-10 3.5E-10 2. 6E-10 i SE 0. 5.1E-08 8.4E-09 3.3E-09 1. 6E-09 8. 6E-10 5. 6E-10 3.8E-10 3.3E-10 2. 6E-10 2.2E-10 SSE 0. -8.2E-08 1.5E-08 5.8E-09 3.0E-09 1.8E-09 1.1E-09 6.8E-10 4.9E-10 3.8E-10 2.9E-10 S 0. 5. 6E-08 8.3E-09 3.2E-09 1.8E-09 1.2E-09 7.5E-10 5.4E-10 3.9E-10 2.9E-10 2.3E-10 SSW 0, 5.2E-08 7.7E-09 3.0E-09 1.9E-09 1.1E-09 5.8E-10 4.3E-10 3.8E-10 2.2E-10 1.8E-10 SW 0. 7.5E-08 1.1E-08 4.3E-09 2.4E-09 1. 6E-09 8.8E-10 6.4E-10 4. 6E-10 3.7E-10 3.1E-10 WSW -0. 6.0E-08 7.0E-09 2.7E-09 1.3E-09 8.8E-10 5.2E-10 4.0E-10 3.3E-10 2.4E-10 2.0E-10 W 0. 4.1E-08 5.1E-09 2.0E-09 9.2E-10 5.7E-10 3. 6E-10 2. 6E-10 2.1E-10 1.7E-10 1.0E-10 WNW 0. 3.4E-08 3.8E-09 1.7E-09 7.3E-10 3.9E-10 3.0E-10 1.9E-10 1.5E-10 1.1E-10 8.4E-11 NW 0. 2.7E-08 3.5E-09 1.1E-09 6.6E-10 4.7E-10 3.3E-10 2.1E-10 1.7E-10 1.1E-10 9. 6E-11 NNW 0. 3. 6E-08 5.0E-09 1.9E-09 8.5E-10 5.0E-10 3.8E-10 2.8E-10 2.4E-10 1. 6E-10 1.3E-10 N 0. 4.4E-08 6.3E-09 2.1E-09 1.3E-09 8.0E-10 5. 6E-10 4.5E-10 3.5E-10 2.5E-10 2.1E-10
,, Number of Valid Observations 8678 g Number of Invalid Observations 82
- Number of Calms Lower Level 125 c) Number of Calms Upper Level 0
- k. U d
l Table A-7 x/Q Values at the Special Locations for Releases from the Reactor Buildings ')
Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Concentration (Sec./ Cubic Meter)
Calculation Points: Special Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number,of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident Garden NNE 1.19E-07 0. 8.06E-08 8.79E-08 7.31E-08 NE 1.72E-07 0. O. 9.39E-08 0. ,-
~
ENE 7.18E-08 0. O. O. 0. -
E 5.37E-08 0. O. 3.88E-08 0.
ESE 7.65E-08 0. O. O. O.
SE 4.24E-08 0. 2.44E-08 3.71E-08 3.55E-08 SSE 6.70E-08 6.75E-08 6.50E-08 6.75E-08 0.
S 3.81E-08 0. O. 3.16E-08 2.90E-08 SSW 4.65E-08 0. O. 4.17E-08 4.17E-08 SW 5.02E-08 0. 3.98E-08 5.02E-08 5.02E-08 WSW 4.32E-08 0. O. 4.53E-08 4.53E-08 W 2.71E-08 0. 3.32E-08 3.14E-08 3.14E-08 WNW 1.70E-08 0. O. 1.81E-08 1.84E-08 NW 1.76E-08 0. O. 2.02E-08 1.15E-08 NNW 2.94E-08 0. O. 2.49E-08 2.37E-08 N 4.84E 0. O. 3.46E-08 3.53E-08
- A zero indicates that this point was not calculated.
l l
l l
Table A-8 Depleted x/Q Values at the Special Locations for 1 Releases from the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./ Cubic Meter)
Calculation Points: Special l Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Affected Site Sector Boundary Dairy Meat Resident Garden NNE 1.09E-07 0. 7.63E-08 8.44E-08 6.89E-08 NE 1.62E-07 0. O. 8.70E-08 0.
ENE 6.68E-08 0. O. O. O.
E 4.93E-08 0. O. 3.57E-08 0.
]~
ESE 7.04E-08 0. O. O. O.
SE 3.98E-08 0. 3.50E-08 3.45E-08 3.34E-08 SSE 6.25E-08 6.28E-08 6.05E-08 6.28E-08 0.
S 3.56E-08 0. O. 2.99E-08 2.75E-08 SSW 4.38E-08 0. O. 3.99E-08 3.99E-08 SW 4.76E-08 0. 3.72E-08 4.76E-08 4.66E-08 WSW 4.09E-08 0. O. 4.36E-08 4.36E-08 W 2.64E-08 0. 3.24E-08 3.06E-08 3.06E-08 WNW 1.58E-08 0. O. 1.75E-08 1.77E-08 NW 1.69E-08 0. O. 1.87E-08 1.15E-08 NNW 2.6BE-08 0. O. 2.33E-08 2.21E-08 N 4.40E-08 0. O. 3.29E-08 3.35E-08 l
l
- A zero indicates that this point was not calculated.
.) <
00CM (BSEP) A-12 Rev. O i
Table A-9 D/Q Values at the Special Locations for Releases from the Reactor Buildings Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Mixed Mode Variable: Relative Decomposition Rate (Meter **-2)
Calculation Points: Special Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of. Observations: 8678 Affected Site Sector Boundary Dairy Meat' Resident Garden NNE 2.49E-09 0. 1.27E-09 1.58E-09 9.35E-10 NE 3.33E-09 0. O. 9.78E-10 0.
ENE E
1.30E-09 5.29E-10 0.
0.
O.
O.
O.
3.42E-10 O.
0.
]
ESE 1.22E-09 0. O. O. O.
SE 8.49E-10 0. 7.26E-10 6.63E-10 5.99E-10 SSE 1.07E-09 1.03E-09 9.93E-10 1.03E-09 0.
S 4.15E-10 0. O. 2.83E-10 2.52E-10 SSW 6.38E-10 0. O. 4.17E-10 4.17E-10 SW 8.66E-10 0. 4.16E-10 8.66E-10 7.62E-10 l WSW 9.26E-10 0. O. 7.47E-10 7.47E-10 W 5.72E-10 0. 4.37E-10 5.23E-10 5.23E-10 WNW 2.75E-10 0. O. 2.59E-10 2.56E-10 NW 3.04E-10 0. O. 3.07E-10 3.53E-11 l NNW 3.86E-10 0. O. 2.89E-10 2.53E-10 N 7.48E-10 0. O. 4.38E-10 4.56E-10
- A zero indicates that this point was not calculated.
o Table A-10 8-
. a.
x/Q Values at the Standard Distances for Releases from the Reactor Buildings 6 Carolina Power & Light Company - Brunswick l
- Release Type: Annual Release Mode: Mixed Mode Variable: Relative Concentration (Sec./ Cubic Meter)
, Calculation Points: Standard Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers 4
Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 5.6F-07 1.0E-07 7.8E-08 6.3E-08 5.2E-08 4.1E-08 3.6E-08 3.1E-08 2.7E-08 2.4E-08
- NE 0. 5.5E-07 2.0E-07 1.5E-07 1.2E-07 9.4E-08 7.6E-08 6.3E-08 5.3E-08 4.6E-08 4.1E-08 ENE 0. 1.6E-06 6.5E-08 5.8E-08 5.4E-08 4.9E-08 4.3E-08 3.9E-08 3.5E-08 3.1E-08 2.9E-08
> E 0. 2.9E-07 4.8E-08 3.5E-08 2.9E-08 2.7E-08 2.3E 2.2E-08 1.8E-08 1.7E-08 1.5E-08 4
ESE 0. 1.2E-07 6.9E-08 5.0E-08 3.9E-08 3.5E-08 3.1E-06 2.6E-08 2.3E-08 2.0E-08 1.7E-08 SE 0. 7.8E-08 4.1E-08 3.6E-06 2.7E-08 2.0E-08 1.8E-08 1.7E-08 1.5E-08 1.3E-08 1.2E-08 SSE 0. 2.2E-07 7.6E-08 5.6E-08 4.2E-08 3.5E-08 2.9E-08 2.5E-08 2.2E-08 1.9E-08 1. 6E-08 S 0. 4.2E-07 4.5E-08 3.5E-08 2.8E-08 2.5E-06 2.4E-08 2.1E-08 1.8E-08 1.6E-08 1.4E-08 SSW 0. 5.9E-07 4.7E-08 4.7E-08 4.1E-08 3.7E-08 2.9E-08 2.7E-08 2.3E-08 2.0E-08 1.8E-08 SW 0. 1.8E-07 6.4E-08 5.5E-08 4.4E-08 3.8E-08 3.1E-08 2.7E-08 2.4E-08 2.1E-08 1.9E-08 WSW 0. 8.9E-08 4.1E-08 4.3E-08 3.9E-08 3.4E-08 2.8E-08 2.5E-08 2.5E-08 2.2E-08 1.9E-08 W 0. 3.6E-08 3.4E-08 3.8E-08 3.7E-08 3.1E-08 2.8E-08 2.6E-06 2.2E-08 2.1E-08 1.8E-08
. WNW 0. 4.1E-08 1.8E-08 2.2E-08 2.4E-08 2.3E-08 2.0E-08 1.8E-08 1.6E-08 1.4E-08 1.2E-08 NW 0. 3.0E-08 1.9E-08 2.3E-08 2.0E-08 1.9E-08 1.9E-08 1.6E-08 1.4E-08 1.3E-08 1.2E-08 NNW 0. 4.9E-07 3.2E-08 2.7E-08 2.4E-08 2.0E-08 1.8E-08 1.6E-08 1.5E-08 1.4E-08 1.3E-08 N 0. 6.3E-07 4.0E-08 3.0E-08 2.9E-08 2.7E-08 2.6E-08 2.6E-08 2.1E-08 1.8E-08 1.7E-08 2
, Number of Valid Observations 8678
- Number of Invalid Observations 82 Number of Calms Lower Level 125 o Number of Calms Upper Level 0
( U ;
- . _-.- ..- - ~ . . - .. - -. . -- -_ .. .- -. . . .
-o- Table A-11 o
=
Depleted x/Q Values at the Standard Distances for Releases from the Reactor Buildings j Carolina Power 8 Light Company - Brunswick
- Release Type: Annual 1 Release Mode: Mixed Mode Variable: Relative Depleted Concentration (Sec./ Cubic Meter) 1 Calculation Points: Standard Model: Straight Line (ANNX009) ,
Application of Terrain Correction Factors: Yes Number of Observations: 8678 l
Base _ Distance in Miles /K11cueters Design . .
i
- Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 i Sect Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 5.4E-07 9.1E-08 7.8E-08 5.9E-08 4.9E-08 3.8E-08 3.3E-08 2.8E-08 2.5E-08 2.2E-08 NE 0. 5.3E-07 1.9E-07 1.4E-07 1.1E-07 8.7E-08 7.1E-08 5.9E-08 5.0E-08 4.3E-08 3.7E-08 ENE O. 1.5E-06 6.1E-08 5.6E-08 5.2E-08 4.7E-08 4.1E-08 3.7E-08 3.3E-08 3.0E-08 2.8E-08 Y E 0. 2.8E-07 4.4E-08 3.2E-08 2.7E-08 2.5E-08 2.2E-08 2.1E-08 1.8E-08 1.6E-08 1.4E-08 In ESE 0. 1.1E-07 6.4E-08 4.6E-08 3.7E-08 3.3E-08 2.9E-06 2.4E-08 2.2E-08 1.8E-08 1.6E-06 SE 0. 7.4E-08 3.8E-08 3.3E-08 2.5E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 SSE 0. 2.1E-07 7.1E-08 5.2E-08 3.9E-08 3.2E-08 2.6E-08 2.3E-08 2.0E-08 1.7E-08 1.5E-08 j S 0. 4.0E-07 4.2E-08 3.3E-08 2.7E-06 2.3E-08 2.3E-08 1.9E-08 1.7E-08 1.5E-08 1.3E-08 SSW 0. 5.9E-07 4.3E-08 4.4E-08 3.9E-08 3.5E-08 2.7E-08 2. 6E-08 2.2E-08 1.9E-08 1.7E-08 SW 0. 1.7E-07 6.0E-08 5.2E-08 4.2E-08 3.6E-08 2.9E-03 2.5E-08 2.2E-08 2.0E-08 1.7E-08 WSW 0. 8.2E-08 3.9E-08 4.2E-08 3.8E-08 3.2E-08 2.7E-08 2.4E-08 2.4E-08 2.1E-08 1.8E-08 l W 0. 3.4E-08 3.3E-08 3.6E-08 3.6E-08 3.0E-08 2.7E-08 2.5E-08 2.1E-08 2.0E-08 1.7E-08 i
l WNW -O. 3.9E-08 1.7E-08 2.1E-08 2.3E-08 2.2E-08 1.9E-08 1.7E-08 1.6E-08 1.3E-08 1.1E-08
, NW 0. 2.9E-08 1.8E-08 2.3E-08 2.0E-08 1.8E-08 1.8E-08 1.6E-08 1.4E-08 1.3E-08 1.2E-08 NNW 0. 4.5E-07 3.0E 2.5E-08 2.3E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 N 0. 5.8E-07 3.7E-08 '2.9E-08 2.8E-08 2.6E-08 2.5E-08 2.4E-08 2.0E-08 1.7E-08 1.6E-08 1
, . Number of Valid Observations 8678
$ Number of Invalid Observations 82 Number of Calms Lower Level 12 o Number of Calms Upper Level 0
- b b J
i o Table A-12 8
l D/Q Values at the Standard Distances for Releases from the Reactor Buildings a
% Carolina Power & Light Company - Brunswick 3
-- Release Type: Annual ;
i Release Mode: Mixed Mode i Variable: Relative Deposition Rate (Meter **-2)
- Calculation Points: Standard l Model: Straight Line (ANNX009)
Application of. Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3. 62 4.42 5.23 6.03 6.84 7. 64
} NNE 0. 1.1E-08 2.0E-09 1.1E-09 7.2E-10 5.0E-10 3.5E-10 2.8E-10 2.2E-10 1.7E-10 1.5E-10 j NE 0. 1.1E-08 4.3E-09 2.3E-09 1.5E-09 9.8E-10 7.2C-10 5.3E-10 4.2E-10 3.3E-10 2.7E-10 i ENE 0. 1.9E-08 1.1E-09 5.8E-10 3.9E-10 2.8E-10 2.2E-10 1.7E-10 1.4E-10 1.1E-10 9.7E-11 I
T' E 0. 2.1E-09 4. 6E-10 2.5E-10 1. 6E-10 1.2E-10 9.0E-11 7.5E-11 5.7E-11 4.8E-11 3.8E-11
- . E' ESE 0. 1.3E-09 1.1E-09 5.4E-10 3.3E-10 2.4E-10 1.9E-10 1.3E-10 1.1E-10 8.3E-11 6.9E-11
. SE 0. 1.3E-09 7. 6E-10 4.9E-10 2.8E-10 1.8E-10 1.3E-10 1.1E-10 8.9E-11 6.7E-11' 6.1E-11 SSE 0. 2.4E-09 -1.2E-09 6.7E-10 4.1E-10 2.8E-10 2.1E-10 1. 6E-10 1.3E-10 1.0E-10 8.2E-11 S 0. 3. 6E-09 5.7E-10 3.4E-10 2.3E-10 1.7E-10 1.4E-10 1.0E-10 8.2E-11 6.5E-11 5.5E-11 i
SSW 0. 8.0E-09 7.7E-10 5.2E-10 3.5E-10 2. 6E-10 1.8E-10 1.5E-10 1.1E-10 9.3E-11 7.4E-11 SW 0. 3.4E-09 1.2E-09 7.3E-10 4.5E-10 3.3E-10 2.3E-10 1.7E-10 1.4E-10 1.2E-10 9.4E-11 i WSW 0. 1.8E-09 8.9E-10 5.9E-10 4.1E-10 2.9E-10 2.1E-10 1.7E-10 1.5E-10 1.2E-10 1.0E-10 W 0. 7.9E-10 6. 6E-10 4.3E-10 2.9E-10 1.9E-10 1.5E-10 1.2E-10 8. 6E-11 7.7E-11 6.4E-11 WWW 0. 5.8E-10 2.7E-10 2.0E-10 1.7E-10 1.3E-10 8.8E-11 6.8E-11 5.5E-11 4.2E-11 3.3E-11
! NW 0. 5.4E-10 3.1E-10 2.3E-10 1.5E-10 1.1E-10 8.9E-11 6.9E-11 5.4E-11 4.4E-11 3.9E-11
! N 0. 8.7E-09 5.6E-10 2.8E-10 2.1E-10 - 1,6E-10 1.4E-10 1.1E-10 8.1E-11 6.4E-11 5.7E-11
,, Number of Valid Observations 8678 y Number of Invalid Observations 82 j
- Number of Calms Lower Level 12 c) Number of Calms Upper Level 0
Table A-13 l
x/Q Values at the Special Locations for Releases from the Stack ,
l Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Concentration Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset Affected Site Sector Boundary Dai ry Meat Resident Garden NNE 1.3E-08 0. 2.2E-08 1.9E-08 2.4E-08 NE 3.3E-08 0. O. 4.1E-08 0.
ENE 6.3E-09 0. O. O. O.
E 3.0E-09 0. O. 4.9E-09 0.
ESE 5.9E-09 0. O. O. O.
SE 5.7E-09 0. 7.5E-09 8.0E-09 9.3E-09 SSE 5.9E-09 1.0E-08 1.0E-08 1.0E-08 0.
S 6.3E-09 0. O. 9.1E-09 9.4E-09 SSW 8.7E-09 0. O. 1.4E-08 1.4E-08 SW 1.6E-08 0. 1.8E-08 1.6E-08 1.7E-08 WSW 9.0E-09 0. O. 1.4E-08 1.4E-08 W 9.7E-09 0. 1.4E-08 1.2E-08 1.2E-08 WNW 4.8E-09 0. O. 6.2E-09 6.4E-09 NW 7.0E-09 0. O. 7.8E-09 7.0E-09 NNW 4.2E-09 0. O. 6.0E-09 6.8E-09 N 4.8E-09 0. O. 6.8E-09 6.6E-09
- A zero indicates that this point was not calculated.
00CM (BSEP) A-17 Rev. O l -
i Table A-14 Depleted x/Q Values at the Special Locations for Releases from the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Relative Depleted Concentrations Calculation Points: Special Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset Affected Site Sector Boundary Dairy Meat Resident Garden NNE 1.2E-08 0. 2.1E-08 1.7E-08 2.3E-08 NE 3.2E-08 0. O. 4.0E-08 0.
ENE 6.2E-09 0. O. O. O.
E 3.0E-09 0. O. 4.9E-09 0.
ESE 5.8E-09 0. O. O. O.
SE 5.7E-07 0. 7.4E-09 7.9E-09 9.3E-09 SSE 5.8E-09 9.9E-09 9.9E-09 9.9E-09 0.
S 6.2E-09 0. O. 9.0E-09 9.3E-09 SSW 8.5E-09 0. O. 1.3E-08 1.3E-09 ;
SW 1.5E-08 0. 1.8E-08 1.6E-08 1.7E-08 WSW 8.9E-09 0. O. 1.2E-08 1.2E-08 i W 9.6E-09 0. 1.4E-08 1.2E-08 1.2E-08 j WNW 4.6E-09 0. O. 5.9E-09 6.0E-09 l NW 6.9E-09 0. O. 7.7E-09 6.7E-09 NNW 4.1E-09 0. O. 5.8E-09 6.6E-09 N 4.7E-09 0. O. 6.5E-09 6.3E-09
- A zero indicates that this point was not calculated.
i 00CM (BSEP) A-18 Rev. 0 )
l
Table A-15 j D/Q Values at the Special Locations for Releases from the Stack Carolina Power & Light Company - Brunswick Release Type: Annual Release Mode: Elevated Variable: Deposition Rate Calculation Points: Special ,
Model: Straight Line Application of Terrain Correction Factors: Yes Number of Observations: 8678 Accounting for Stack Center Offset Affected Site Sector Boundary Dairy Meat Resident Garden NNE 6.0E-10 0. 5.6E-10 5.9E-10 5.0E-10 NE 1.3E-09 0. O. 6.6E-10 0.
ENE 3.3E-10 0. O. O. O.
E 1.8E-10 0. O. 1.6E-10 0.
ESE 4.0E-10 0. O. O. O.
SE 4.4E-10 0. 4.4E-10 4.4E-10 4.2E-10 SSE 6.0E-10 5.4E-10 5.4E-10 5.4E-10 0.
S 2.0E-10 0. O. 1.7E-10 1.7E-10 SSW 2.7E-10 0. O. 2.7E-10 2.7E-10 SW 5.4E-10 0. 3.2E-10 5.4E-10 4.9E-10 WSW 3.8E-10 0. O. 3.8E-10 3.8E-10 W 3.8E-10 0. 3.1E-10 3.7E-10 3.7E-10 WNW 1.7E-10 0. O. 1.6E-10 1.6E-10 NW 2.1E-10 0. O. 2.0E-10 3.2E-11 NNW 1.5E-10 0. O. 1.4E-10 1.3E-10 N 1.9E-10 0.. O. 1.6E-10 1.7E-10
- A zero indicates that this point was not calculated.
-- . - - - . - - _ - - - ... . - _ - - ._ - . - - . . . -.= - . _ - . - - -.- - -. .- - -.
3 o Table A-16 8* x/0 Values at the Standard Distances for Releases from the Stack issi N Carolina Power & Light Company - Brunswick 3 Release Type: Annual i Release Mode: Elevated
. Variable: Relative Concentration (Sec./ Cubic Meter)
Calculation Points: Standard j Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 i
! NNE 0. 1.5E-09 1.3E-08 2.3E-08 2.5E-08 2.4E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 L NE 0. 2.5E-09 2.5E-08 4.0E-08 4.4E-08 4.2E-08 3.8E-08 3.3E-08 3.0E-08 2.6E-06 2.4E-08 i ENE 0. 8.7E-10 7.2E-09 1.6E-08 2.1E-08 2.2E-08 2.1E-08 2.0E-08 1.9E-08 1.8E-08 1.7E-08
, ? E 0. 7.5E-10 3.6E-09 7.6E-09 8.9E-09 1.0E-08 9.3E-09 9.4E-09 8.1E-09 7.6E-09
- 7.5E-09 E!
ESE 0. 1.1E-09 7.7E-09 1.1E-08 1.3E-08 1.3E-08 1.3E-08 1.1E-08 1.0E-08 9.3E-09 8.5E-09
- ' SE 0. 1.6E-09 8.7E-09 1.1E-08 1.0E-08 9.1E-09 8.9E-09 8.0E-09 7.3E-09 6.5E-09 6.5E-09 SSE 0. 1.5E-09 1.2E-08 1.6E-08 1.6E-08 1.5E-08 1.3E-08 1.3E-08 1.1E-08 1.0E-08 8.9E-09 i S 0. 7.7E-10 4.7E-09 8.5d-09 9.6E-09 9.7E-09 1.1E-08 9.4E-09 8.3E-09 7.7E-09 7.2E-09 l
, SSW 0. 4.9E-10 6.0E-09 1.4E-08 1.6E-08 1.7E-08 1.4E-08 1.4E-08 1.2E-08 1.1E-08 1.0E-08 1 SW 0. 1.5E-09 1.3E-08 1.8E-08 1.8E-08 1.8E-08 1.6E-08 1.4E-08 1.3E-08 1.1E-08 1.0E-08 WSW 0. 1.5E-09 9.0E-09 1. 6E-08 1.8E-08 1.8E-08 1.6E-08 1.4E-08 1.4E-08 1.3E-08 1.2E-08 W 0. 1.4E-09 1.0E-08 1.5E-08 1.7E-08 1.6E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 1.1E-08 i
WNW 0. 8.4E-10 5.3E-09 8.4E-09 1.1E-08 1.2E-08 1.0E-08 9.3E-09 8.6E-09 7.3E-09 6.7E-09 NW 0. 1.0E-09 6.5E-09 1.0E-08 1.0E-08 1.0E-08 1.0E-08 9.5E-09 8.6E-09 7.6E-09 7.5E-09 i NNW 0. 1.1E-09 4.2E-09 7.6E-09 9.2E-09 8.5E-09 8.0E-09 7.4E-09 7.0E-09 6.9E-09 6.1E-09
! N 0. 8.1E-10 4.5E-09 8.4E-09 1.1E-08 1.2E-08 1.3E-08 1.3E-08 1.1E-08 9.3E-09 9.2E-09 l'.,* Number of Valid Observations 8678
- Number of Invalid Observations 82 I
- Number of Calms Lower Level 0 o Number of Calms Upper Level 0
8 Table A-17 9
_ Depleted x/Q Values at the Standard Distances for Releases from the Stack 5
q) Carolina Power & Light Company - Brunswick l
-- Release Type: Annual Release Mode: Elevated Variable: Relative Depleted Concentration (Sec./ Cubic Meter) ,
Calculation Points: Standard Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes Number of Observations: 8678 Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 Sect Mi .40 1.21 2.01 2.82 3. 62 4.42 5.23 6.03 '6.84 7. 64 NNE 0. 1.5E-09 1.2E-08 2.2E-08 2.4E-08 2.4E-08 2.1E-08 1.9E-08 1.7E-08 1.5E-08 1.4E-08 NE 0. 2.5E-09 2.5E-08 4.0E-08 4.3E-08 4.1E-08 3.7E-08 3.2E-08 2.9E-08 2.5E-08 2.3E-08 i
ENE 0. 8.7E-10 7.1E-09 1. 6E-08 2.1E-08 2.2E-08 2.0E-08 1.9E-08 1.8E-08 1.7E-08 1.7E-08 E 0. 7.5E-10 3. 6E-09 7. 6E-09 8.9E-09 9.3E-09 9.3E-09 9.4E-09 8.1E-09 7. 6E-09 6.8E-09 ESE 0. 1.1E-09 7.5E-09 1.1E-08 1.2E-08 1.3E-08 1.3E-08 1.1E-08 1.0E-08 9.3E-09 8.2E-09 SE 0. 1.6E-09 8.7E-09 1.1E-08 1.0E-08 8.5E-09 8.2E-09 8.0E-09 7.2E-09 6.3E-09 6.3E-09 SSE 0. 1.5E-09 1.2E-08 1. 6E-08 1.5E-08 1.4E-08 1.3E-08 1.2E-08 1.0E-08 9.3E-09 8.1E-09 i S 0. 7.7E-10 4. 6E-09 8.5E-09 9. 6E-09 9.7E-09 1.1E-08 9.4E-09 8.2E-09 7.4E-09 6.9E-09 i
SSW 0. 4.9E-10 6.0E-09 1.4E-08 1. 6E-08 1. 6E-08 1.4E-08 1.4E-08 1.1E-08 1.0E-08 9.3E-09
! SW 0. 1.5E-09 1.3E-08 1.8E-08 1.0E-08 1.8E-08 1.5E-08 1.4E-08 1.2E-08 1.1E-08 1.0E-08 WSW 0. 1.5E-09 9.0E-09 1.5E-08 9.2E-08 1.7E-08 1.5E-08 1.3E-08 1.4E-08 1.2E-08 1.1E-08 W 0. 1.4E-09 1.0E-08 1.5E-08 1.1E-08 1.5E-08 1.5E-08 1.4E-08 1.2E-08 1.2E-08 1.1E-08 i
WNW 0. 8.4E-10 5.1E-09 8.4E-09 1.1E-08 1.2E-08 1.0E-08 9.3E-09 8. 6E-09 7.3E-09 6.5E-09 NW 0. 1.0E-09 6.5E-09 1.0E-08 1.0E-08 9. 6E-09 1.0E-08 8.7E-09 7.8E-09 7.3E-09 7.12-09 i NNW 0. 1.1E-09 4.1E-09 7.5E-09 9.2E-09 8.5E-09 8.0E-09 7.3E-09 6.8E-09 6.6E-09 6.0E-09 N 0. 8.1E-10 4.5E-09 8.4E-09 1.1E-08 1.1E-08 1.3E-08 1.3E-08 1.0E-08 9.3E-09 9.2E-09
= Number of Valid Observations 8678
- Number of Invalid Observations 82 Number of Calms Lower Level 0 2
c3 Number of Calms Upper Level 0
g- Table A-18 D/Q Values at the Standard Distances for Releases fram the Stack
'k Carolina Power 8 Light Company - Brunswick Release Type: Annual i
Release Mode: Elevated
' Variable: Relative Deposition Rate (Meter **-2)
Calculation Points: Standard
-Model: Straight Line (ANNX009)
Application of Terrain Correction Factors: Yes i Number of Observations: 8678 l
- Base Distance in Miles / Kilometers Design Aftd Dist .25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 t Sect Mi .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 i
l NNE 0. 1.2E-09 6.0E-10 5.3E-10 4.3E-10 3.4E-10 2.5E-10 2.0E-10 1.6E-10 1.4E-10 1.2E-10 i NE 0. 1.4E-09 1.4E-09 1.1E-09 8.8E-10 6.7E-10 5.2E-10 3.9E-10 3.1E-10 2.6E-10 2.2E-10 ,
i ENE 0. 1.8E-09 3.2E-10 3.0E-10 2.5E-10 2.0E-10 1.6E-10 1.3E-10 1.1E-10 9.3E-11 8.1E-11 i
[ E 0. 2.2E-10 1.6E-10 1.3E-10 1.0E-10 8.7E-11 6.6E-11 5.7E-11 4.4E-11 3.7E-11' 3.1E-11 m
ESE 0. 1.9E-10 4.1E-10 2.7E-10 2.0E-10 1.7E-10 1.4E-10 1.1E-10 8.2E-11 6.6E-11 5.6E-11 SE 0. 3.2E-10 4.2E-10 3.1E-10 2.1E-10 1.4E-10 1.1E-10 8.7E-11 7.3E-11 5.8E-11 5.3E-11 l SSE 0. 5.8E-10 5.4E-10 3.9E-10 2.8E-10 2.1E-10 1.7E-10 1.4E-10 1.1E-10 8.5E-11 7.1E-11, S 0. 5.4E-10 2.0E-10 1.9E-10 1.4E-10 1.1E-10 1.1E-10 8.3E-11 6.6E-11 5.5E-11 4.6E-11'
) SSW 0. 1.1E-09 2.7E-10 2.9E-10 2.4E-10 1.9E-10 1.4E-10 1.3E-10 9.5E-11 7.9E-11 -6.5E-11 l SW 0. 7.6E-10 5.6E-10 . 4.3E-10 3.1E-10 2.4E-10 1.8E-10 1.4E-10 1.1E-10 9.5E-11 8.0E-11 i WSW 0. 4.1E-10 3.8E-10 3.6E-10 3.0E-10 2.3E-10 1.7E-10 1.4E-10 1.3E-10 1.0E-10 8.6E-11
- 0. 3.9E-10 3.0E-10 2.1E-10 1.5E-10 1.3E-10 1.0E-10 7.8E-11 6.9E-11 5.9E-11 W 2.8E-10
- WNW 0. 2.4E-10 1.7E-10 1.5E-10 1.4E-10 1.0E-10 7.4E-11 5.8E-11' 4.8E-11 3.7E-11 2.9E-11 NW 0. 2.6E-10 2.0E-10 1.7E-10 1.2E-10 8.8E-11 .7.5E-11 6.0E-11 4.8E-11 4.0E-11 3.6E-11 NNW 0. 7.2E-10 1.5E-10 1.3E-10 1.0E-10 7.3E-11 5.4E-11 4.3E-11 3.6E-11 3.2E-11 2. 6E-11 N 0. 8.1E-10 1.9E-10 1.5E-10 1.3E-10 1.1E-10 9.9E-11 7.9E-11 6.0E-11 4.9E-11 4.4E-11
! = Number of Valid Observations 8678 '
3 Number of Invalid Observations 82 i Number of Calms Lower Level 0 I Number of Calms Upper Level 0
o TABLE A-19 E
Brunswick Plant Site Information To Be Used
$ for Ground Level Calculations with MtC "X0QDOQ" Program 9
Value To Be Used Card Type Columns Description in X00000 1 1 Print input data 1 38 Calculate annual x/Qs for points of interest 1 39 Calculate annual x/Q averages for site radial segments 1 41 Print out set distance x/Qs and D/Qs 1 55 Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted x/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 2 1-80 Title card N/A 3 1-5 Number of wind velocity categories 7 3 6-10 Number of stability categories 7 A>
11-15 Number of distances within terrain data for each sector 1 16-20 Total number of hours in joint wind frequency distribution (1) 21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 11 6-20 Half-life (days) used in the x/Q calculations 101.00 2.26 8.00
) 5 N/A N/A __,
6 1-80 Joint wind frequency distribution (1)
(
o
c2 TABLE A-19 (continued) 8 Value To Be Used 5 Card Type Columns Description in 10Q000 9
i 7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond All are 0 ,
to distances in Card Type 8
?
% 101-25 Number of receptor locations for a particular re:eptor type Site boundary = 16 Dairy = 1 Meat = 5 Residence = 14 Garden = 11 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence Garden 121-80 Receptor direction and distance (See Table 1) 131-80 Title for release point whose characteristics are described (1) on Card Type 14 E
o i
o TABLE A-19 (continued) 8 x
Value To Be Used Card Type Columns Description in XDQD0Q
~
14 1-5 Vent average velocity (m/sec) 1.0 6-10 Vent inside diameter (m) 1.0 11-15 Height of vent release point (m) 0.000 16-20 Height of.the vent's building (m) 56.9 21-25 Minimum cross-sectional area for the vent's building (m2 ) 2120.0 26-30 Wind height used for vent elevated release 11.0 31-35 Vent heat emission rate (cal /sec) 0.0 15 1 Identification for release point A 2-5 Intermittent releases 0 6-10 Number of intermittent releases per year for this release point 0 11-15 Average number of hours per intermittent release 0 (1) Appropriate data to be supplied
,O i
o TABLE A-20 R
- Brunswick Plant Site Information To Be Used g for Elevated Release Calculations with IItC "X0QO00" Program o
~
Value To Be Used Card Type Columns Description in XDQD0Q 1 1 Print input data 1 4 Release to be elevated 100% of the time 1 38 Calculate annual x/Qs for points of interest 1 39 Calculate annual x/Q averages for site radial segments 1 41 Print out set distance x/Qs and D/Qs 1 Ei Calculate annual D/Q averages for the set radial segments 1 56 Allow depleted x/Qs (if Decays (1), (2), or (3) are negative) 1 58 Calculate annual D/Qs for points of interest 1 I
2 1-80 Title card N/A
? 3 1-5 Number of wind velocity categories 7 5 6-10 Number of stability categories 7 11-15 Number of distances within terrain data for each sector 1 16-20 Total- number of hours in joint wind frequency distribution (1) 21-25 Increment in % for which plotted results are to be printed 5 26-30 Number of titles of receptor types 5 31-35 Number of release exit locations 1 4 1-5 Height of the measured wind 104 6-20 Half-life (days) used in the x/Q calculations 101.00 2.26 8.00 4
5 N/A N/A _
6 1-80 Joint wind frequency distribution (1) g
?
O
o TABLE A-20 (continued) 8 x
- ' Value To Be Used Card Type Colummes Description in M)QD00 7 1-5 Wind velocity units correction 200.00 6-75 Maximum wind speed in each wind class (m/sec) 0.75 3.50 7.50 12.50 18.50 25.00 26.00 8 1-80 Distance in meters at which terrain heights are given All are 100 9 1-80 Terrain heights (in meters, above plant grade) correspond All are 0 to distances in Card Type 8 4
" 101-25 Number of receptor locations for a particular receptor type Site boundary = 16 Dairy = 1 Meat = 5 Residence = 14 Garden = 11 11 1-16 Title of receptor type for receptor locations Site Boundary Dairy Meat Residence Garden 12 1-80 Receptor direction and distance (See Table 1) 131-80 Title for release point whose characteristics are described (1) on Card Type 14 -
- =
'O
o TABt.E A-20 (continued) 8 Value To Be Used Card Type Columns Description in 100D00
~
14 1-5 Vent average velocity (m/sec) 4.66 6-10 Vent inside diameter (m) 3.58 11-15 Height of vent release point (m) 100.9 16-20 Height of the vent's butiding -(m) 0.0 21-25 Minimum cross-sectional area for the vent's building (m2 ) 0.00 26-30 . Wind height used for vent elevated release 104.0 31-35 Vent heat emission rate (cal /sec) 0.0 15 1 Identification for release point A
! 2-5 Intermittent releases 0 6-10 Number of Intermittent releases per year for this release point 0 ,
11-15 Average number of hours per intermittent release 0 (1) Appropriate data to be supplied l
l
'o
APPE WIX B Calculation of Vi and 8g Values for the Elevated Plume Values of Vj and By were calculated for the elevated plume release from the Brunswick stack using the NRC computer program RABFIN. This program was used to determine the controlling location based upon the releases of Table 3.2-1. In addition it was used to develop the Vj and 89 values for the various noble gas radionuclides at the site boundary at each of the 16 sectors. Table B-1 presents the Vj and By values for the ENE sector which is the controlling location for noble gases for showing compliance with 10CFR20 and 10CFR50. Table B-2 presents the joint frequency distribution for the ENE sector. Tables B-3 through B-32 present the Vj and By values and the joint frequency distribution for the remaining sectors.- The inputs which were utilized in the RABFIN code are presented below.
- 1. Height of Stack - 100.9 (m)
- 2. Stack Diameter - 3.6 (m)
- 3. Exit Velocity - 5.0 m/sec
- 4. Wind Height - 104.6 (m)
TABLE B-1 DOSE PARAETERS FOR FINITE ELEVATED PLtBES ENE SITE BOUNDARY
- Tota Body Air
[erad/yr)
Noble Gas Radionuclides (arem/yr) pct /sec/ \uct/sec/
Kr-83m 1.66E-09 1.40E-07 Kr-85m 9.18E-05 1.36E-04 Kr-85 1.36E-06 2.06E-06 Kr-87 4.17E-04 6.27E-04 Kr-88 1.08E-03 1.62E-03 Kr-89 6.55E-04 9.84E-04 Xe-131m 2.17E-05 3.41E-05 Xe-133m 1.64E-05 2.66E-05 Xe-133 1.72E-05 2.67E-05 Xe-135m 2.17E-04 3.29E-04 Xe-135 1.47E-04 2.21E-04 Xe-137 5.64E-05 8.52E-05 Xe-138 6.61E-04 9.93E-04 Xe-139 2.03E-05 3.05E-05 Ar-41 7.86E-04 1.18E-03
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
00CM (BSEP) B-2 Rey,o
TABLE B-2 JOINT FREQUENCY DISTRIBUTION FOR ENE SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXImlM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3 0.17 0.00 0.01 0.01 0.07 0.03 0.05 4 3.30 0.02 0.17 0.61 1.21 0.83 0.46 5 4.81 0.02 0.18 '0.81 1.63 1.39 0.78 6 1.14 0.05 0.20 0.28 0.27 0.14 0.20 7 0.46 0.01 0.12 0.15 0.09 0.09 0.00 Total 9.88 0.10 0.68 1.86 3.27 2.48 1.49 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.75 6.75 Harmonic 0.00 5.27 5.27 ODCM (BSEP) B-3 Rev. O
l TABLE B-3 DOSE PARAMETERS FOR FINITE ELEVATED PLLMES N SITE BOUNDARY
- I Vi 81 Total Body Gamma Air (arem/yr)
[arad/yr)
Noble Gas Radionuclides uct/sec/ \uct/sec/
Kr-83m 8.98E-10 1.11E-07 .
Kr-85m 4.57E-05 6.79E-05 Kr-85 6.76E-07 1.02E-06
. Kr-87 2.06E-04 3.10E-04 Kr-88 5.41E-04 8.11E-04 Kr-89 2.89E-04 4.34E-04 Xe-131m . 1.09E-05 1.72E-05 Xe-133m 8.26E-06 1.35E-05 Xe-133 8.69E-06 1.36E-05 Xe-135m 1.04E-04 1.57E-04 Xe-135 7.32E-05 1.10E-04 Xe-137 2.40E-05 3.63E-05 1 Xe-138 3.26E-04 4.89E-04 Xe-139 6.87E-06 1.03E-05 )
Ar-41 3.89E-04 5.84E-04 i
l
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
ODCM(8SEP) 8-4 Rev. O
TABLE B-4 JOINT FREQUENCY DISTRIBUTION FOR N SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM VIND SPEED (m/sec) 1.50 3.00 5.00 7.50 10.00 12.50 Stability Total 0.00 0.00 0.00 0.00 0.00 0.00 1 0.00 0.00 0.00 0.00 0.01 0.00 0.00 2 0.01 0.00 0.00 0.01 0.07 0.03 0.00 3 0.11 0.01 0.16 0.70 0.65 0.18 0.09 4 1.79 0.00 0.15 0.46 0.65 0.29 0.45 5 2.00 0.68 0.02 0.06 0.29 0.12 0.07 0.12 6
0.15 0.02 0.10 0.01 0.00 0.01 0.01 7
4.74 0.05 0.47 1.47 1.50 0.58 0.67 Total 0.00 0.00 0.00 0.00 0.00 0.00 Entrapment 0.23 0.70 1.24 1.93 2.71 3.48 Ground Velocity 0.74 2.21 3.93 6.14 8.59 11.05 Elevated Yelocity AVERAGE WIND SPEED (m/sec)
Ground Elevated Combined Mean 0.00 6.00 6.00 Arithmetic 0.00 4.61 4.61 l Harmonic i
, l l
' 1 l
00CM (bSEP) B-5 Rev. O
TABLE B-5 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES NNE SITE BOUNDARY
- Tota Body Air
/arad/yr\
Noble Gas Radionuclides (area uct/sec/yr)/ \ pc1/sec /
Kr-83m 1.78E-09 3.33E-07 ,
Kr-85m 7.77E-05 1.15E-04 Kr-85 1.13E-06 1.71E-06 Kr-87 3.45E-04 5.19E-04 Kr .88 8.91E-04 1.34E-03 Kr-89 5.42E-04 8.15E-04 Xe-131m 1.89E-05 3.00E-05 Xe-133m 1.42E-05 2.36E-05 Xe-133 1.52E-05 2.40E-05 Xe-135m 1.80E-04 2.73E-04 Xe-135 1.23E-04 1.86E-04 Xe-137 4.70E-05 7.11E-05 Xe-138 5.47E-04 8.22E-04 Xe-139 1.68E-05 2.52E-05 Ar-41 6.49E-04 9.74E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
j l
l l
l 00CM (BSEP). B-6 Rev. 0
TABLE B-6
\
JOINT FREQUENCY DISTRIBUTION FOR lStE SECTOR (5) )
PERIOD 1-1-77 THROUGH 12-31-77 f BRONSWICK STEAM ELECTRIC PUUIT l MAXIEM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.07 0.00 0.00 0.01 0.05 0.01 0.00 3 0.45 0.00 0.00 0.03 0.25 0.15 0.02 4 4.51 0.01 0.16 0.56 1.79 1.38 0.61 5 2.90 0.00 0.17' O.21 0.88 0.78 0.86 6 0.65 0.02 0.12 0.22 0.09 0.07 0.13 7 0.45 0.05 0.14 0.08 0.07 0.10 0.01 Total 9.03 0.08 0.59 1.11 3.13 2.49 1.63 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 7.13 7.13 Harmonic 0.00 5.63 5.63 ODCM (BSEP) B-7 Rev. O
TABLE B-7 1
DOSE PAIUM:TERS FOR FINITE ELEVATED PLUMES l NE SITE BOUNDARY
- Tota ' Body Air (arem/yri farad /yr)
Noble Gas Radionuclides pC1/sec/ \ pC1/sec/
Kr-83m 2.87E-09 8.70E-07 Kr-85m 9.33E-05 1.39E-04 i Kr-85 1.31E-06 1.99E-06 Kr-87 3.99E-04 6.00E-04 Kr-88 1.03E-03 1.54E-03 Kr-89 6.05E-04 9.10E-04 Xe-131m 2.37E-05 3.85E-05 Xe-133m 1.79E-05 3.05E-05 Xe-133 1.96E-05 3.15E-05
- Xe-135m 2.09E-04 3.18E-04 Xe-135 1.46E-04 2.20E-04 Xe-137 5.25E-05 7.94E-05 Xe-138 6.34E-04 9.52E-04 Xe-139 1.48E-05 2.23E-05 Ar-41 7.47E-04 1.12E-03 4
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
TABLE B-8 JOINT FREQUENCY DISTRIBUTION FOR E SECTOR (S)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.00 0.01 2 0.21 0.00 0.00 0.00 0.05 0.10 0.06 3 1.13 0.00 0.00 0.03 0.28 0.50 0.32 4 7.30 0.01 0.15 O.63 2.50 2.51 1.50 5 5.15 0.03 0.09 0.30 1.21 1.99 1.53 6 1.04 0.01 0.06 0.32 0.33 0.24 0.08 7 0.41 0.01 0.12 0.10 0.13 0.03 0.02 Total 15.26 0.06 0.42 1.38 4.51 5.37 3.52 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Yelocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combinec Arithmetic 0.00 7.81 7.81 Harmonic 0.00 6.63 6.63 ODCM (BSEP) B-9 Rev. 0
TABLE B-9 l DOSE PARAMETERS FOR FINITE ELEVATED PLUMES E SITE BOUNDARY
- V9 Sg Total Bo(y Gama Air (arm /yrT [arad/yri Noble Gas Radfor.t:lides $1/sec/ \ $1/sec/
Kr-83m 9.63E-10 7.31E-08 Kr-85m 5.94E-05 8.82E-05 Kr-85 8.93E-07 1.35E-06 Kr-87 2.73E-04 4.11E-04 Kr-88 7.17E-04 1.08E-03 Kr-89 4.02E-04 6.04E-04 Xe-131m 1.39E-05 2.17E-05 Xe-133m 1.05E-05 1.70E-05
~
Xe-133 1.09E-05 1.69E-05 Xe-135m 1.38E-04 2.10E-04 Xe-135 9.59E-04 1.44E-04 Xe-137 3.37E-05 5.10E-05 Xe-138 4.32E-04 6.49E-04 Xe-139 1.08E-05 1.62E-05 Ar-41 5.18E-04 7.77E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
TABLE B-10 JOINT FREQUENCY DISTRIBLITION FOR E SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMLM WIND SPEED (a/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.00 0.00 0.01 0.00 2 0.03 0.00 0.00 0.00 0.01 0.01 0.01 3 0.09 0.00 0.00 0.03 0.02 0.01 0.03 4 1.42 0.01 0.15 0.55 0.32 0.23 0.16 5 2.07 0.03 0.10 0.62 0.74 0.50 0.08 6 1.08 0.02 0.14 0.30 0.38 0.15 0.09 7 0.64 0.03 0.13 0.24 0.10 0.08 0.06 Total 5.34 0.09 0.52 1.74 1.57 0.99 0.43 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 5.80 5.80 Harmonic 0.00 4.41 4.41 ODCM (BSEP) B-11 Rev. O
TA8LE B-11 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES ESE SITE BOUNDARY
- Tota Body Air
[ mrad /yri Noble Gas Radionuclides (arem/yrT pC1/sec/ \ pC1/sec)
~
Kr-83m 1.08E-09 1.89E-07 Kr-85m 5.51E-05 8.18E-05 Kr-85 8.12E-07 1.23E-06 Kr-87 2.51E-04 3.78E-04 Kr-88 6.42E-04 9.63E-04 Kr-89 4.30E-04 6.46E-04 Xe-131m 1.31E-05 2.07E-05 Xe-133m 9.91E-06 1.62E-05 Xe-133 1.04E-05 1.63E-05 Xe-135m 1.34E-04 2.04E-04 Xe-135 8.81E-05 1.32E-04 Xe-137 3.79E-05 5.73E-05 Xe-138 3.99E-04 5.99E-04 Xe-139 1.70E-05 2.55E-05 Ar-41 4.73E-04 7.09E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
TABLE B-12 JOINT FREQUENCY DISTRIBUTION FOR ESE SECTOR (5)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.06 0.00 0.00 0.01 0.00 0.05 0.00 2 0.15 0.00 0.00 0.01 0.03 0.06 0.05 3 0.31 0.00 0.00 0.02 0.13 0.03 0.13 4 1.71 0.00 0.07 0.31 0.58 0.46 0.29 5 2.02 0.01 0.08 0.31 0.52 0.80 0.30 6 0.85 0.03 0.06 0.17 0.18 0.36 0.05 7 0.46 0.01 0.07 0.12 0.07 0.07 0.12 Total 5.56 0.05 0.28 0.95 1.51 1.83 0.94 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Yelocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 l
AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 7.15 7.15 Hamonic 0.00 5.67 5.67 ODCM (BSEP) B-13 Rev. O
TABLE B-13 DOSE PARAETERS FOR FINITE ELEVATED PLINES SE SITE BOUNDARY
- Tota 80 % Air
/ arad/yri Noble Gas Radionuclides (ares /yr /j
$1/sec \ $1/sec /
Kr-83m 1.36E-09 3.68E-07 Kr-85m 6.01E-05 8.93E-05 Kr-85 8.80E-07 1.33E-06 Kr-87 2.72E-04 4.10E-04 Kr-88 6.95E-04 1.04E-03 Kr-89 4.68E-04 7.04E-04 Xe-131m 1.45E-05 2.31E-05 Xe-133m 1.10E-05 1.82E-05 Xe-133 1.16E-05 1.83E-05 Xe-135m 1.46E-04 2.22E-04 Xe-135 9.58E-05 1.44E-04 Xe-137 4.14E-05 6.26E-05 Xe-138 4.33E-04 6.50E-04 Xe-139 1.87E-05 2.81E-05 Ar-41 5.12E-04 7.68E-03 4
c
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
l l
OGCM (BSEP) B-14 Rev. 0
TABLE B-14 JOINT FREQUENCY DISTRIBUTION FOR SE SECTOR (5)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 l 1 0.11 0.00 0.00 0.00 0.00 0.06 0.05 2 0.31 0.00 0.00 0.01 0.14 0.15 0.01 3 0.53 0.00 0.00 0.14 0.18 0.18 0.03 4 1.44 0.02 0.08 0.25 0.51 0.41 0.17 5 1.46 0.01 0.09 0.31 0.50 0.46 0.09 6 0.89 0.02 0.05 0.02 0.30 0.44 0.06 7 0.63 0.01 0.13 0.09 0.14 0.21 0.05 l
Total 5.37 0.06 0.35 0.82 1.77 1.91 0.46 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.78 6.78 Harmonic 0.00 5.37 5.37 ODCM (BSEP) 8-15 Rev. 0
TABLE B-15 DOSE PARAETERS FOR FINITE ELEVATED PLUMES SSE SITE BOUNDARY
- 9 Tota Bo@ Air
/ mrad /yr \
Noble Gas Radionuclides (arem/yr pC1/sec i/ \ pC1/sec)
Kr-83m 1.31E-09 2.51E-07 Kr-85m 6.46E-05 9.59E-05 Kr-85 9.55E-07 1.45E-06 Kr-87 2.96E-04 4.45E-04 Kr-88 7.58E-04 1.14E-03 Kr-89 5.11E-04 7.69E-04 Xe-131m 1.54E-05 2.43E-05 Xe-133m 1.17E-05 1.91E-05 Xe-133 1.22E-05 1.91E-05 Xe-135m 1.58E-04 2.39E-04 Xe-135 1.03E-04 1.55E-04 Xe-137 4.52E-05 6.83E-05 Xe-138 4.70E-04 7.06E-04 Xe-139 2.17E-05 3.26E-05 Ar-41 5.58E-04 8.37E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
l l l l l 1
i TABLE B-16 JOINT FREQUENCY DISTRIBUTION FOR SSE SECTOR (5)
- PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.01 0.01 0.00 2 0.13 0.00 0.00 0.02 0.02 0.09 0.00 3 0.49 0.00 0.00 0.14 0.24 0.09 0.02 4 2.35 0.05 0.16 0.32 0.80 0.70 0.32 5 1.40 0.00 0.08 0.23 0.46 0.58 0.05 6 0.84 0.02 0.05 0.13 0.18 0.31 0.15 7 0.32 0.03 0.02 0.05 0.07 0.13, 0.02 Total 5.55 0.10 0.31 0.89 1.78 1.91 0.56 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.81 6.81 Harmonic 0.00 5.21 5.21 ODCM (BSEP) B-17
__ _ 0900 @
i
)
I l
i TABLE B-17 DOSE PARAETERS FOR FINITE ELEVATED PLLMES l S SITE BOUNDARY
- Tota Body Air
/arad/yri Noble Gas Radionuclides (ares /yri/
pC1/sec \ pC1/sec /
Kr-83m 8.30E-10 1.84E-07 Kr-85m 3.54E-05 5.26E-05 Kr-85 5.20E-07 7.88E-07 Kr-87 1.54E-04 2.32E-04 Kr-88 4.18E-04 6.27E-04 Kr-89 2.00E-04 3.00E-04 Xe-131m 8.70E-06 1.39E-05 Xe-133m 6.58E-06 1.09E-05 Xe-133 7.01E-06 1.11E-05 Xe-135m 7.40E-05 1.12E-04 Xe-135 5.66E-05 8.51E-05 Xe-137 1.64E-05 2.48E-05 Xe-138 2.42E-04 3.63E-04 Xe-139 4.28E-06 6.43E-06 Ar-41 2.93E-04 4.40E-04 l
l
- The listed dose parameters are for radionuclides that may be i detected in gaseous effluents. l l
00CM (BSEP) B-18 Rev. O
TABLE B-18 JOINT FREQUENCY DISTRIBUTION FOR S SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.03 0.00 0.00 0.00 0.03 0.00 0.00 3 0.16 0.00 0.00 0.02 0.14 0.00 0.00 4 1.74 0.01 0.13 0.28 0.55 0.54 0.23 5 1.32 0.03 0.08 0.25 0.45 0.46 0.05 6 0.93 0.02 0.08 0.17 0.24 0.33 0.09 7 0.37 0.05 0.03 0.05 0.12 0.07 0.05 Total 4.55 0.11 0.32 0.77 1.53 1.40 0.42 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.57 6.57 Harmonic 0.00 4.84 4.84 l
I l
l i
! t l ODCM (BSEP) B-19 Rev. 0 --
TABLE B-19 DOSE PARAETERS FOR FINITE ELEVATED PLLMES SSW SITE BOUNDARY
- Vg Bg Total Body Gamma Air
/ mrad /yri Noble Gas Radionuclides (ares /yri/
uc1/sec \ pct /sec/
Kr-83m 1.09E-09 . 2.15E-07 Kr-85m 4.68E-05 6.95E-05 Kr-85 6.80E-07 1.03E-06 Kr-87 2.07E-04 3.11E-04 Kr-88 5.39E-04 8.09E-04 Kr-89 2.98E-04 4.48E-04 Xe-131m 1.14E-05 1.82E-05 Xe-133m 8.63E-06 1.43E-05 Xe-133 9.22E-06 1.46E-05 Xe-135m 1.06E-04 1.61E-04 Xe-135 7.44E-05 1.12E-04 Xe-137 2.52E-05 3.81E-05 Xe-138 3.28E-04 4.92E-04 Xe-139 6.80E-06 1.02E-05 Ar-41 3.89E-04 5.84E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents. l I
TABLE B-20 JOINT FREQUENCY DISTRIBUTION FOR SSW SECTOR (1)
. PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3 O.19 0.00 0.00 0.07 0.05 0.06 0.01 4 2.47 0.01 0.03 0.53 0.99 0.62 0.29 5 1.88 0.01 0.15 0.37 0.56 0.74 0.05 6 1.12 0.01 0.12 0.14 0.28 0.55 0.02 7 0.51 0.01 0.03 0.10 0.22 0.13 0.02 Total 6.17 0.04 0.33 1.21 2.* 0 2.10 0.39 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Yelocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.61 6.61 Harmonic 0.00 5.44 5.44 ODCM (BSEP) B-21 Ennm s)
TABLE B-21 DOSE PARAETERS FOR FINITE ELEVATED PLUMES SW SITE BOUNDARY
- It Total Body 89 Gamma Air (erad/yr\
Noble Gas Radionuclides (mrem /yr\
pC1/sec) _\ pC1/sec /
Kr-83m 1.35E-09 3.69E-07 Kr-85m 5.24E-05 7.79E-05 Kr-85 7.60E-07 1.15E-06 Kr-87 2.29E-04 3.45E-04 Kr-88 6.04E-04 9.06E-04 Kr-89 3.21E-04 4.82E-04 Xe-131m 1.30E-05 2.08E-05 Xe-133m 9.83E-06 1.64E-05 Xe-133 1.05E-05 1.67E-05 Xe-135m 1.15E-04 1.75E-04 Xe-135 8.33E-05 1.25E-04 Xe-137 2.69E-05 4.07E-05 Xe-138 3.63E-04 5.45E-04 Xe-139 7.09E-06 1.07E-05 Ar-41 4.33E-04 6.50E-04 l
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
4 00CM (BSEP) B-22 Rev. O _ , - . . -
l l
TABLE B-22 JOINT FREQUENCY DISTRIBUTION FOR SW SECTOR (5)
PERICO 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT I
l MAXIMim WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 ,
10.00 12.50 1 0.01 0.00 0.00 0.00 0.00 0.01 0.00 2 0.10 0.00 0.00 0.02 0.07 0.01 0.00 3 0.53 0.00 0.02 0.10 0.30 .0.09 0.02
~
4 2.32 0.01 0.14 0.50 0.98 0.52 0.17 5 1.71 0.02 0.09 0.39 0.40 c. 0.68 0.13 6 0.88 0.05 0.05 0.20 ,0.46 0.12 0.00 7 0.56 0.00 0.07 0.15 0.22 0.12 0.00 Total 6.11 0.08 0.37 1.36 2.43 1.55 0.32 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Yelocity 0.74 2.21 3.93 6.14 8.59 11.05 t
AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 6.22 6.22 Harmonic 0.00 4.98 4.98 ODCM (BSEP) 8-23 Rev. O
TABLE B-23 DOSE PARAETERS FOR FINITE ELEVATED PLLMES WSW SITE BOUNDARY
- Tota Bob Air
/ mrad /yrj Noble Gas Radionuclides (ares
$1/sec/yr)/ \ $1/sec/
Kr-83m 1.41E-09 3.28E-07 Kr-85m 5.94E-05 8.83E-05 Kr-85 8.66E-07 1.31E-06 Kr-87 2.63E-04 3.97E-04 Kr-88 6.87E-04 1.03E-03 Kr-89 3.90E-04 5.87E-04 Xe-131m 1.45E-05 2.32E-05 Xe-133m 1.10E-05 1.83E-05 Xe-133 1.17E-05 1.85E-05 Xe-135m 1.35E-04 2.05E-04 Xe-135 9.46E-05 1.42E-04 Xe-137 3.32E-05 5.03E-05 Xe-138 4.18E-04 6.27E-04 Xe-139 9.43E-06 1.42E-05 Ar-41 4.97E-04 7.45E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
)
i TABLE B-24 JOINT FREQUENCY DISTRIBUTION FOR WSW SECTOR (5)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.02 0.00 0.00 0.00 0.02 0.00 0.00 2 0.18 0.00 0.01 0.00 0.14 0.00 0.03 3 0.36 0.00 0.01 0.15 0.15 0.05 0.00 4 2.64 0.00 0.15 0.54 1.12 0.75 0.08 5 1.73 0.02 0.09 0.37 0.84 0.39 0.02 6 0.87 0.02 0.08 0.25 0.37 0.14 0.01 7 0.36 0.03 0.03 0.13 0.17 0.00 0.00 Total 6.16 0.07 0.37 1.44 2.81 1.33 0.14 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Yelocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 5.97 5.97 Harmonic 0.00 4.91 4.91 l
l l
_ __f1qqmja_
TABLE B-25 DOSE PARAETERS FOR FINITE ELEVATED PLIMES W SITE BOUNDARY
- Vg Bg Total Body Gamma Air
. / arad/yri Noble Gas Radionuclides (mrem /yri/
uct/sec \ pC1/sec /
Kr-83m 1.36E-09 2.97E-07 Kr-85m 6.29E-05 9.34E-05 Kr-85 9.33E-07 1.41E-06 Kr-87 2.81E-04 4.23E-04 Kr-88 7.49E-04 1.12E-03 Kr-89 3.82E-04 5.73E-04 Xe-131m 1.52E-05 2.42E-05 Xe-133m 1.15E-05 1.90E-05 Xe-133 1.21E-05 1.91E-05 Xe-135m 1.38E-04 2.09E-04 Xe-135 1.01E-04 1.52E-04 Xe-137 3.16E-05 4.77E-05 Xe-138 4.42E-04 6.64E-04 Xe-139 8.18E-06 1.23E-05 Ar-41 5.33E-04 8.00E-04 l
1
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
1 l
TABLE B-26 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMim WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.05 0.00 0.00 0.00 0.05 0.00 0.00 2 0.10 0.00 0.00 0.00 0.10 0.00 0.00 3 0.37 0.00 0.05 0.18 0.12 0.02 0.00 4 1.95 0.02 0.10 0.47 1.07 0.29 0.00 5 2.00 0.01 0.14 0.53 1.07 0.22 0.03 6 0.85 0.07 0.10 0.29 0.36 0.01 0.02 7 0.37 0.06 0.08 0.18 0.05 0.00 0.00 Total 5.69 0.16 0.47 1.65 2.82 0.54 0.05 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 l
AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined i
Arithmetic 0.00 5.30 5.30 Harmonic 0.00 4.13 4.13 i
l l
TABLE B-27 DOSE PARAETERS FOR FINITE ELEVATED PLLMES 1
inni SITE BOUNDARY * !
l l
l Vj B 9
Total Body Gamuna Air
/mradlyr)
Noble Gas Radionuclides (arem/yri pc1/sec/ \901/sec/
Kr-83m 9.33E-10 2.26E-07 Kr-85m 4.30E-05 6.39E-05 Kr-85 6.41E-07 9.71E-07 Kr-87 1.92E-04 2.89E-04 Kr-88 5.18E-04 7.77E-04 Kr-89 2.41E-04 3.62E-04 Xe-131m 1.04E-05 1.66E-05 Xe-133m 7.92E-06 1.31E-05 Xe-133 8.31E-06 1.31E-05 Xe-135m 9.15E-05 1.39E-04 Xe-135 6.91E-05 1.04E-04 Xe-137 1.93E-05 2.92E-05 Xe-138 3.01E-04 4.53E-04 4.51E-06 Xe-139 6.77E-06 Ar-41 3.65E-04 5.48E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
\
TABLE B-28 JOINT FREQUENCY DISTRIBllTION FOR WNW SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT l
l MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.01 0.00 0.00 0.00 2 0.09 0.00 0.00 0.08 0.01 0.00 0.00 3 0.24 0.00 0.05 0.17 0.02 0.00 0.00 4 1.03 0.01 0.10 0.45 0.45 0.02 0.00 5 1.19 0.03 0.14 0.37 0.50 0.13 0.02 6 0.63 0.05 0.12 0.28 0.17 0.01 0.00 7 0.19 0.03 0.03 0.07 0.06 0.00 0.00 Total 3.38 0.12 0.44 1.43 1.21 0.16 0.02 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Yelocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 4.65 4.65 Harmonic 0.00 3.58 3.58 ODCM (BSEP) B-29 Rev. O
1 l
l TABLE B-29 DOSE PARAMETERS FOR FINITE ELEVATED PLtMES NW SITE BOUNDARY
- Vj 89 Total Body Gammia Air
[ mrad /yri Noble Gas Radionuclides (mrem /yr\
pc1/sec/ \ pc1/sec /
Kr-83m 9.87E-10 2.60E-07 Kr-85m 4.14E-05 6.14E-05 Kr-85 6.09E-07 9.23E-07 Kr-87 1.80E-04 2.72E-04 Kr-88 4.92E-04 7.38E-04 Kr-89 2.11E-04 3.17E-04 Xe-131m 1.02E-05 1.63E-05 Xe-133m 7.73E-06 1.28E-05 Xe-133 8.20E-06 1.30E-05 Xe-135m 8.45E-05 1.28E-04 Xe-135 6.62E-05 9.95E-05 Xe-137 1.65E-05 2.49E-05 Xe-138 2.83E-04 4.25E-04 Xe-139 3.74E-06 5.61E-06 Ar-41 3.43E-04 5.15E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
I l
l i
TABLE B-30 JOINT FREQUENCY DISTRIBUTION FOR W SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIftlM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.01 0.00 0.00 0.01 0.00 0.00 0.00 2 0.12 0.00 0.01 0.08 0.03 0.00 0.00 3 0.24 0.00 0.02 0.17 0.05 0.00 0.00 4 1.14 0.01 0.16 0.54 0.33 0.09 0.01 5 1.08 0.02 0.12 0.40 0.28 0.10 0.16 6 0.57 0.05 0.17 0.17' O.16 0.01 0.01 7 0.35 0.03 0.07 0.12 0.13 0.00 0.00 Total 3.51 0.11 0.55 1.49 0.98 0.20 0.18 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 Ground Yelocity 0.23 0.70 1.24 1.93 2.71 3.48 ,
Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 4.81 4.81 Harmonic 0.00 3.59 3.59 00CM (BSEP) 8-31 Rev. O !
j
TABLE B-31 DOSE PARAMETERS FOR FINITE ELEVATED PLtMES NNW SITE BOUNDARY
- Tota ' Body Air (mram/yri farad /yri Noble Gas Radionuclides uct/sec) \ uct/sec)
Kr-83m 6.84E-10 1.03E-07 Kr-85m 3.67E-05 5.44E-05 Kr-85 5.51E-07 8.35E-07 Kr-87 1.65E-04 2.48E-04 Kr-88 4.46E-04 6.70E-04 Kr-89 2.09E-04 3.14E-04
, Xe-131m 8.75E-06 1.38E-05 Xe-133m 6.63E-06 1.08E-05 Xe-133 6.91E-06 1.08E-05 Xe-135m 7.85E-05 1.19E-04 Xe-135 5.91E-05 8.89E-05 Xe-137 1.68E-05 2.54E-05 Xe-138 2.59E-04 3.89E-04 Xe-139 4.89E-06 7.34E-06 Ar-41 -
3.14E-04 4.72E-04
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
00CM (BSEP) B-32 Rev. O
TABLE B-32 JOINT FREQUENCY DISTRIBUTION FOR BON SECTOR (1)
PERIOD 1-1-77 THROUGH 12-31-77 BRUNSWICK STEAM ELECTRIC PLANT MAXIMUM WIND SPEED (m/sec)
Stability Total 1.50 3.00 5.00 7.50 10.00 12.50 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2 0.02 0.00 0.00 0.01 0.01 0.00 0.00 3 0.12 0.00 0.00 0.06 0.06 0.00 0.00 4 1.00 0.01 0.14 0.36 0.37 0.09 0.03 5 1.17 0.02 0.12 0.27 0.25 0.12 0.39 6 0.82 0.02 0.13 0.23 0.17 0.03 0.24 7 0.34 0.05 0.10 0.14 0.00 0.05 0.00 Total 3.47 0.10 0.49 1.07 0.86 0.29 0.66 Entrapment 0.00 0.00 0.00 0.00 0.00 0.00 l Ground Velocity 0.23 0.70 1.24 1.93 2.71 3.48 Elevated Velocity 0.74 2.21 3.93 6.14 8.59 11.05 AVERAGE WIND SPEED (m/sec)
Mean Ground Elevated Combined Arithmetic 0.00 5.89 5.89 Harmonic 0.00 4.02 4.02 ODCM (BSEP) B-33 Rev. O
APPENDIX C DOSE PARAMETERS FOR RADIOI0 DINES, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with 10CFR 20 and Appendix I of 10CFR50 for gaseous effluents. These dose parameters Pj and R$ were calculated using the methodology outlined in NUREG 0133 along with Regulatory Guide 1.109 Revision 1. The following sections provide the specific methodology which was utilized in calculating the Pj and
~
Rj values for the various exposure pathways.
C.1 CALCULATION OF Pt The parameter Pj contained in the radiolo^ dine and particulate portion of Section 3.2, includes pathwy transport parameters of the ith radionuclide, the receptor's usage of the pathway medio and the dosimetry of the exposure.
Pathway usage rates and the internal dosimetry are functions of the receptor's ^
age; however, the youngest age group, the infant, will always receive the maximum dose under the exposure conditions for Technical Specification 3.11.2.1(b). For the infant exposure, separate values of Pg may be calculated for the inhalation pathway which is combined with a W parameter based on (X/Q), and the food (milk) and ground pathway which is combined with a W parameter normally based on (D/Q), except for tritium. The following sections provide in detail the methodology which was used in calculating the Pt values for inNusion into this ODCM.
C.1.1 INHALATION PATHWAY Pg
= K'(BR)DFA j (C.1-1) where:
Pj = dose parameter for radionuclide i for the inhalation pathway, mrem /yr per pC1/m 3 ODCM (BSEP) C-1 Rev. 0
,o
K' = a constant of unit conversion
= 106 pC1/pCi BR = the breathing rate of the infant age group, m3/yr DFAg
= the maximum organ inhalation dose factor for the infant age group for radionuclide i, mrem /pCi
- The age group considered is the infant group. The infant's breathing rate is taken as 1400 m 3 /yr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the infant, DFAg, are presented in Table E-10 of Regulatory Guide 1.109 in units of mrem /pC1. The total body is considered as an organ in the selection of DFAj .
The incorporation of breathing rate of an infant and the unit conversion factor results in the following:
1 9
Pg =
1.4x10 0FAj (C.1-2)
C.1.2 Ground Plane Pathway
-At j
Pj =
K'K"DFGj (1-e ,
where:
l Pj = Dose parameter for radionuclide i for the ground plane pathway, mrem /yr per pCi/sec per m-2 i
K' = A constant of unit conversion 106 pCi/pCi
=
X" = A constant of unit conversion
= 8760 hr/yr
-ODCM (BSEP) C-2 Rev. 0
. 9
- f, ._.m-_ - ., , .- . _ _ , ._ #
Ag
= The radiological decay constant for radionuclide 1, sec-1 ,
t = The exposure period-
= 3.15x10 7 sec (1 year)
DFGj = The ground plane dose conversion factor for radionuclide 1, mres/hr per pC1/m 2
-The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for radionuclide 1,' DFG j , are presented in Table E-6 of Regulatory Guide 1.109, Revision 1.
Resolution of the units yields:
9 Pj = 8.76x10 0FG j (1-e' i )/Aj (C.1-4)
C.1.3 Milk K'r Qp (U, ) F* -A j t Pj = DFLj e (C.1-5) where:
c P j =
M Dose parameter for radionuclide i for the cow milk or goat milk pathway, mrem /yr per pCi/sec per m'2 K' = A constant of unit conversion i.
B = -.10 6 pCi/uCi 0F = The cow's or goat's consumption rate _ of feed, ODCM (BSEP) C-3 Rev. 0 k
kg/ day (wet weight)
- V ap = The infant's milk consumption rate, liters /yr Y
p = The agricultural croductivity by unit area, kg/m2 Fm = The stable element transfer coefficient, pCi/ liter per pC1/ day f
r = Fraction of deposited activity retained on cow's or goat's feed grass DFL j = The maximum organ ingestion dose factor for radionuclide 1, arem/pC1.
'A j = The radiological decay constant for radionuclide i sec -1 w = The decay constant for-removal of activity on leaf and plant surfaces by weathering, sec-1 4
= 5.73x10-7 sec-1 -(corresponding to a 14 day half-time) tg = The transport time from pasture to cow or goat to
~
milk to infant, sec A fraction of the airborne. deposition- is captured by the ground plant vegetation cover. The-captured material is removed from the - vegetation i (grass) by both radiological decay and weathering. processes.
- Various parameters which were utilized- to determine the.Pj values for the cow and goat milk pathways are provided in -Table' C-1. Table E-1 of Regulatory Gui.de 1.109, . Revision 1, provides the stable element transfer coefficients, F,, and Table E-14.of the same regulatory guide provides the ingestion dose factors, DFLj , for the infant's organs. The organ with the maximum value of ODCM (BSEP) C-4 Rev. O
DFLg was used in the determination of Pg for thi, pathway. The incorporation of the various constants of Table C-1 into Equation C.1-5 results in the following:
For cow's milk for radiofodines and particulates:
rF -A t 10 m DFL e II P = 2.4x10 Ag+Aw (C.1-6) iM i
. For the goat milk pathway for radioiodines and particulates:
9 rF* -At II Pg
= 2.8x10 3 DFLj e (C.1-7)
For tritium, the concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.
PTM K'K"'F,QpU,pDFLT 0.75(0.5/H) (C.1-8) where:
P T
Dose parameter for tritium for the cow milk and M
goat milk pathways, arem/yr per pC1/m 3 X"' = A constant of unit conversion
= 103 gm/kg H = Absolute humidity of the atmosphere, gm/m 3 0.75 = The fraction of total feed that is water f
0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water DFL = Maximum organ ingestion dose factor for tritium, T
mrem /pci ODCM (BSEP) C-5 Rev. 0
C.2 Calculation of R$
The Radiotodine and Particulate Technical Specification 3.11.2.3 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs. The inhalation and ground plane exposure pathways shall be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations. R$ values have been calculated for the adult, teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below.
C.2.1 Inhalation Pathway Rj =
K'(BR), (DFAj ), (C.2-1) where:
= Dose factor for each identified radionuclide i of Rj the organ of interest, mrem /yr per pCi/m3 K' = A constant of unit conversion
= 106 pCi/pCi
= Breathing rate of the receptor of age group a, (BR)a m3 fy7 (DFAj), = Organ inhalation dose factor for radionuclide i for the receptor of age group a, mrem /pCi The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109, Revision 1.
00CM (BSEP) C-6 Rev. 0
. Age Group (a) Breathing Rate (m3 /yr) ,<
l Infant 1400 Child 3700 Teen 8000 Adult 8000 ,
Inhalation dose factors (DFAj)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.
C.2.2 Ground Plane Pathway R
=
l jK'K"(SF)DFG4 (1-e )/A j (C.2-2) where:
R
= Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest, mrem /yr per pCi/sec per m-2 K' = A constant of unit conversion
= 106 pCi/pCi .
K" = A constant of unit conversion
= 8760 hr/ year A
g
= The radiological decay constant for radionuclide 1, !
sec -1 i
t = The exposure time, sec
= 4.73x108 sec (15 years)
DFGj = The ground plane dose conversion factor for radionuclide 1; mrem /hr per pC1/m2 l
l 00CM (BSEP) C-7 Rev. 0 r
SF = The shielding factor (dimensionless)
= Factor to account for fractional deposition of 14 radionuclide i I
For radionuclides other than todine, the factor 14 is equal to one. For radiciodines, the value of It may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2.
~
A shielding factor of 0.71s suggested in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation Sf DFGj. values is p, resented in Table E-6 of Regulatory Guide 1.109, Revision 1.
! .C.2.3 Grass-Cow or Goat-Milk Pathway "A t
-A t J II E
I eI BI ' (1-e )-
R, F
= -I gK'Qp U,p ,(DFL,), e fpf, + p
+ ,
"(I 'AE *e i )- -A t ih (1-ff,)p
+ B ',(1-e e (C.2-3) i e where:
R
= Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, arem/yr per pCi/sec per m-2 K' = A constant of unit conversion
= 106 pC1/uCi Qp
= The cow's or goat's feed consumption rate. kg/ day (wet weight)
U ap = The receptor's milk consumption rate for age group a, liters /yr 00CM (BSEP) C-8 Rev. O i __t._ uu . __ _ _ _ , _ - , . _ _ _
Yp = The agricultural productivity by unit area of pasture feed grass, kg/m2 Y = The agricultural productivity by unit area of s
. stored feed, kg/m2 F, = The stable element transfer coefficients, pCi/ liter per pCi/ day r = Fraction of deposited activity retained on cow's feed grass (DFLj ), = The organ ingestion dose factor for radionuclide i for the receptor.in age group a, mrem /pCi A
Eg
" A i
- AI w
A g
= The radiological decay constant for radionuclide i, sec
-1 A, = The decay constant for removal of activity on leaf and plant surfaces by weathering sec-1
= 5.73x10-7 sec-1 (corresponding to a 14 day half-life) tg = The transport time from feed to cow or goat to milk, to receptor, sec i
t h
= The transport time from harvest, to cow or goat, to consumption, see tb
= Period of time that sediment is exposed to gaseous effluents sec ODCM (BSEP) C-9 Rev. O i
=
Bjy Concentration factor for uptake of radionuclide i from the soil by the edible parts of crops, pCi/Kg (wet weight) per pC1/Kg (dry soil)
P = Effective surface density for soil, Kg (dry so11)/m2
= Fraction of the year that the cow or goat is on f
p j pasture l f
s
= Fraction of the cow feed that is pasture grass while the cow is on pasture t,
= Period of pasture grass and crop exposure during the growing season, sec 1 = Factor to account for fractional deposi tion of 9
radionuclide i '
l For radionuclides other than todine, the factor Ij is equal to one. For l radiciodines, the value of Ij may vary. However, a value of 1.0 was used in
! calculating the R values Tables 3.3-9 through 3.3-16.
4 Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f 3 was considered unity in lieu of site-specific information. The value of f was p 0.667 based upon an 8-month grazing period.
Table C-1 contains the appropriate parameter values and their source in
( Regulatory Guide 1.109, Revision 1.
The concentration' of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Rj is based on X/Q:
RT g K'KI 0 Um F ap(DFLg), 0.75(0.5/H) (C.2-4) where:
= Dose factor for the cow or goat milk pathway for RTg tritium for the organ of interest, mrem /yr per pC1/m 3 K"' = A constant of unit conversion
= 103 gm/kg H = Absolute humidity of the atmosphere, gm/m 3 0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water And other parameters and values are given above. A value for H of 8 3
grams / meter , was used in lieu of site-specific information.
C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:
-A t is 4
t, g (),, M ).
= e ff + +
Rg I gK'Qp u,p , (Eg ),
F ps A PA g
_ pE g ,
- r(1-e t
i e) +
Bgy (1-e )- -Aght )
(1-fpsf) Y PA g e (C.2-5)
, sEA i ,
i l where:
Rj = Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, mrem /yr per pC1/sec per m-2
= The stable element transfer coefficients, pCi/Kg Ff per pC1/ day U,p
= The receptor's meat consumption rate for age group a, kg/yr t
s
= The transport time from slaughter to consumption, see t
h
= The transport time from harvest to animal consumption, see t,
= Period of pasture grass and crop exposure during the growing season, sec Ij = Factor to account for fractional deposition of radionuclide i For radionuclides other than iodine, the factor lj is equal to one. For radiciodines, the value of Ij may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-6 through 3,3-8.
All other terms remain the same as defined in Equation C.2-3. Table C-2 contains the values which were used in calculating Rj for the meat pathway.
The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R$ is based on X/Q.
R T 0 u,p(DFLj ), 0.75(0.5/H)
K'K'"Ffp (C.2-6)
..~ . - . .-
I where:
$ R = Dose factor for the meat ingestion pathway for T
O
- tritium for any organ of interest, mrem /yr per pC1/m 3 All other terms are defined in Equation C.2-4 and C.2-5, above.
C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
"A t
-A t It E )-
R =
I jK'(DFLj ), h,ft e eI + BIV(1-e p +
9 1
i t
.A 3
-A gh t ~
r(1-e t
i ') O iv (I~' ib I~
U, fg e + (C.2-7) p I
where:
Rg = Dose factor for vegetable pathway for radionuclide Y
i for the organ of interest, mrem /yr per pC1/sec per m -2 K' = a constant of unit conversion; t
= 106 pC1/pCi l
U', = The consumption rate of fresh leafy vegetation by the receptor in age group a, kg/yr i
Uf
= The consumption rate of stored vegetation by the receptor in age group a, kg/yr i
ODCM (BSEP) C-13 Rev. O i -~'~::~=-
f = The fraction of the annual intake of stored t
vegetation grown locally t = The average time between harvest of leafy l
vegetation and its consumption, see t = The average time between harvest of stored h
vegetation and its consumption, sec Y,
= The vegetation area density, kg/m 2 t, = Period of leafy vegetable exposure during growing season, sec -
Ij = Factor to account for fractional deposition of radionuclide i For radionuclides other thin iodine, the factor lj is equal to one. For radiotodines, the value of Ij may vary. However, a value of 1.0 was used in Tables 3.3-3 through 3.3-5.
All other factors were defined above.
Table C-3 presents the appropriate parameter values and their course in Regulatory Guide 1.109, Revision 1.
In lieu of site-specific data default values for ft and f g, 1.0 and 0.76, respectively, were used in the calculation of Rj. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.
The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Rj is based on X/Q:
R Ty
= K 'K ' ' UfL + U,3fg (DFLj ), 0.75(0.5/H) (C.2-8) l l
l 1
I
where:
-. R = Dose factor for the vegetable pathway for tritium T
V for any organ of interest, arem/yr per pC1/m3 All other terms remain the same as those in Equations C.2-4 and C.2-7.
4 i
i
TABLE C-1 PARAMETERS FOR COW AIB GDAT MILK PAT)AIAYS Reference Parameter Value (Reg. Guide 1.109, Rev. 1)
Qp (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 Y
p (kg/m2 ) 0.7 Table E-15 tg (seconds) 1.73 x 105 (2 days) Table E-15 r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFLj)a (mrem /PC1) Each radionuclide Tables E-11 to E-14 Fm (PC1/ day per pCi/1) Each stable element Table E-1 (cow)
Table E-2 (goat) t b (seconds) 4.73 x 108 (15 yr) Table E-15 Y
s (kg/m2 ) 2.0 Table E-15 Y
p (kg/m2 ) 0.7 Table E-15 t
h (seconds) 7.78 x 106 (90 days) Table E-15 U ap (liters /yr) 330 infant Table E-5 330 child Tabic E-5 400 teen Table E-5 310 adult Table E-5 t
e (seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 106 (stored feed)
B jy pC1/Kg (wet weight) Each stable element Table E-1 per pCi/Kg (dry soil)
P Kg (dry soil)/m2 240 Table E-15 ODCM (BSEP) C-16 Rev. 0
TABLE C-2 PARAMETERS FOR TE EAT PATmiAY 1 l
Reference Parameter Value (Reg. Guide 1.109 Rev. 1) r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15
'Ff (pC1/Kg per pC1/ day) Each Stable element Table E-1 U,p (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFLj ), (mrem /pCi) Each radionuclide Tables E-11 to E-14 Y
p (kg/m2 ) 0.7 fable E-15 Y
3 (kg/m2 ) 2.0 Table E-15 tb (seconds) 4.73 x 108 (15 yr) Table E-15 t
3 (seconds) 1.73 x 106 (20 days) Table E-15 -
t h (seconds) 7.78 x 106 (90 days) Table E-15 t
e (seconds) 2.59 x 106 (pasture) Table E-15 5.18 x 106 (stored feed) 07 (kg/ day) 50 Table E-3 Bjy pC1/Kg (wet weight) Each stable element Table E-1 per pC1/Kg (dry soil)
P kg (dry soil)/m2 240 Table E-15 ODCM (BSEP) C-17 Rev. 0
TABLE C-3 PARAMETERS FOR T E VEGETABLE pal kAY Reference Parameter Value (Reg. Guide 1.109 Rev. 1) r (dimensionless) 1.0 (radiofodines) Table E-1 0.2 (part'culates) e Table E-1 (DFLj)a (mrem /C1) Each radionuclide Tables E-11 to E-14 U (kg/yr) - Infant 0 ' Table E-5
- Child 26 Table E-5
- Teen 42 Table E-5
- Adult 64 Table E-5 US (kg/yr) - Infant 0 Table E-5
- Child 520 Table E-5 l - Teen 630 Table E-5 i
- Adult 520 Table E-5 t
t, (seconds) 8.6 x 10 4 (1 day) Table E-15 th (seconds) 5.18 x 10 6 (60 days) Table E-15 Yy (kg/m2 ) 2.0 fable E-15 t, (seconds) 5.18 x 10 6 (60 days) Table E-15 tb (seconds) 4.73 x 108 (15 yr) Table E-15 P (Kg[ dry soil]/m2 ) 240 Table E-15 Bjy (pCi/Kg[ wet weight) Each stable element Table E-1 per pCi/kg [ dry soil])
APPEISIX D !
l LOWER LIMIT F DETECTION (LLD)
The following discussion of LLD is taken from NUREG-0473, Rev. 2. February 1, 1980. It represents the bases for LLD footnotes (e) in Table 4.11.1-1, (e) in Table 4.11.1-2, (a) in Table 4.11.2-1, and (b) in Table 4.12.1-1 of the BSEP Technical Specifications. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probabi'lity of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s D LLD =
E
- V
- 2.22 x 106 . y . exp (-Aat)
Where:
LLO is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
6 2.22 x 10 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and 00CM (BSEP) D-1 Rev. 1
at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of sb used in the calculation of the LLD for s detection system shall be based on the actual observed variance of the background counting
- rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and at shall be used in the calculation.
l l
, 00CM (BSEP) 0-2 Rev. 1
APPENDIX E RADI0 ACTIVE LIQUID AND GASE0US EFFLUENT DOIITORING INSTR M NTATION IM BERS I. Liquid Effluent Monitoring Instruments
- 1. Liquid Radwaste Radioactivity Monitor 2-D12-RM-K604
- 2. Liquid Radwaste Effluent Flow Measurement Device 2-G16-FIT-N057
- 3. Main Service Water Effluent Radioactivity Monitor 1(2)-D12-RM-K605
- 4. Stabilization Pond Effluent Composite Sampler 2-DST-XE-5027
- 5. Stabilization Pond Effluent Flow Measurement Device 2-DST-FE-5026
- 6. Condensate Storage Tank Level Indicating Device 1(2)-C0-LIT-1160
- 7. Service Water Effluent From Augmented Off-Gas Precooler Radioactivity Monitor 1-SW-RM-58-6
- 8. Reactor Building Component Cooling Water (Service Water) Rad Mons. (Future Installation)
l l
f II. Gaseous Effluent Monitoring Instruments '
- 1. Main Stack Monitoring System
- a. Noble Gas Activity Monitor 2-012-RM-4599-1 !
- b. Iodine Sampler Cartridge IRSH35 Prefilters A or B
- c. Particulate Sampler Filter IRSH35 Pref 11ters A or B l
- d. System Effluent Flow Rate Measurement Device 2-VA-FE-3359
- e. Sampler Flow Rate Measurement Device 2-D12-FE-4597
Monitoring System
- a. Noble Gas Activity Monitor 1(2)-CAC-AQH-1264-3
- 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 Measurement Device 1(2)-VA-FE-3356
- e. Sampler Flow Rate Measurement
- Device 1(2)-VA-FE-5091
- 3. Turbine ~ Building Ventilation Monitoring System
- a. Noble Gas Activity Monitor 1(2)-D12-RM-4548-1
- b. Iodine Sampler Cartridge 1(2)-IRTB32 Prefilters A or B
- c. Particulate Sampler Filter 1(2)-IRTB32 Prefilters A or B
- d. System Effluent Flow Rate Measurement Device 1(2)-VA-FE-3358
- e. Sampler Flow Rate Measurement Device 1(2)-D12-FE-4542
- 4. Main Condenser Air Ejector Radioactivity Monitor
- a. Noble Gas Activity Monitor 1(2)-D12-RM-K601 A and B t
1 l
l
)
- 5. Main Condenser Off-Gas Treatment l System (A0G) Monitor
- a. Noble Gas Activity Monitor 1-A0G-RM-103 l l
- 6. Main Condenser Off-Gas Treatment i System Explosive Gas Monitoring '
System
- a. Recombiner Train A
- 1. First %drogen Monitor 1-0G-AIT-4284
- 2. Second Hydrogen Monitor 1-0G-AIT-4285
- b. Recombiner Train B -
- 1. First %drogen Monitor 1-0G-AIT-4324
- 2. Second Hydrogen Monitor 1-0G.AIT-4325
- 7. Hot Shop Ventilation Monitoring System
, a. Iodine Sampler Cartridge 2-VA-AX-5092
- b. Particulate Sampler Filter 2-VA-AX-5093 i
? . - - - - _ . .
APPENDIX F Liquid and Gaseous Effluent System Diagrams ODCM(BSEP) F-1 Rev. O
.- -....---_;._--__.-.._. . - . . . . ~ -
i .
IY OI WA gg h LeDe.O WAS.E S W COL CTOct .
,mn,. -
e,WS, STEWS,,
g ,_
^
tse
! ut 1 t'f V
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- DetA80s TAseK FeLTER TAgeKS R400ATIOes h10ReseG SLOCK LeoueO STATIOes VALvf 88AU88ASM
... TO eAEET i
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- esCFet 3e i etELEASES AseO M CFR ee I ew 4200C i l EfFLutNT IMI8 DE f e teGE NT 2 :
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7 m
848 T .
SALT WATER . gag,y gayggy ,
seAltig TAsem8
- pgygg e I
' POTEseTeAL LeOueO seELEASE PATeWeAYS ;
30L 0 RADesASTE SYSNee
! I l e848N SEseveCE WAMet AseO A.O G.SERVeCE WATER t s OeSceeARoe tuer$ NAVE l COpeTeNUOUS RAOeOACieveTV eAOsteTORG. i l THE STA80Le2ATeOse POpeO Erf tutNT f
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" ----+ -
- eseNER : gueteAL TO THE eseTAKE CAMAL tesLL esAVE g iggg A PROPORTeopeAL coeWOSets SAertEnt'l WAS f t S l AssO A floes esEASURes00 DEveCEt').
l THE etEACTOst SUOLOsseG COnePONENT l l l COOLes00 WATEst OSERVeCE WAFEset t
!' SOLNHreER LeseE UseLL HAVE COpetessumsS I DeSieLLATE TO WASTE COLLECTOR TAseK ! RAceOAcTeveTV etessetORS l'i, i
! L_________J ;
i I - STEAes ELECTReC PLA80T- upsets e 4 2 i f . - seOFE:
- tsouse RAmesASTE SpeLUEmi SYSetse o reeURE p.e !
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e g Lg =
3 li.= .=l-: IH ,!! ll l !! li ! s !! !!!! s 1:a!!!!!I d!
- s i I :s i g =s t<,- Pg 1s es y; - li si t 5=
i f
2.ngg5
. 3 lc25. :- -
- 'gr'ii ' bi,: 4 ,: 4 :.8;- s l : rg8 ;-=-
g, 5l
- l 1: 1
(( 15 ! !!s .
. -:2 *i " 'I siEhll!!'Iygg ll it " -
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g I-l -
s, l
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ng Ag __ __
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,s li
>as !! !i !i
' a w a ;i :i; :
.= s.i. i=
- ~
1i18 . l'!e
!! s[ll --
eh ef efe 1 i
r,
!=
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. . a. 1; !.g .
t.i li l.i i '8
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- 1. I. . I 1
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i p I, i .!! p
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-f :I :! ~! $n1 -i :! l Il Il -
Is !5 83 i! II )
APPENDIX G I ODCM SOFTWARE PACKAGE In order to minimize calculational errors and to facilitate the use of the ODCM, BSEP has developed an ODCM software package. All applicable calculations listed in the ODCM have been included in this software.
During periods when the ODCM software is not available, the following alternate method may be used to assess dose or dose rates to the public from liquid or gaseous effluents:
Dt = (Dh x Ct)/Ch where: Dt = the unknown dose / dose rate for the time period Dh = the known dose / dose rate from historical data Ct = the total curies released for the time period Ch = the total curies used to calculate the known dose / dose rate When the 00CM software becomes available again, all doses to the public will be reassessed using the software package.
_ . . _ __ .,_ _ . . ~ . - . _ _ . . _ _ . . . .-__. . _ - ._ . ._-__._ _ _ . . .. .
2' ,
i i-i i
i t
I CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT l
e t
- PROCESS CONTROL PROGRAM l (PCP) 1 i
! DOCKET NOS. 50-324 and 50-325 T
i REVISION 1 i
I j
f 4
I MSCJ02 4
., -..,----,,---.,-,g, - . - 1.rv-.v .- ,- w - , ~ . . . ,.,-.7 r--, - ye-,, , , ,, ,. - - - , - - , .-,-,w,y . +-..y y
IZST OF EFFECTIVE PAGES PCP Page(s) Revision
, 1-3 e 1 9
PROCESS CONTROL PROGRAM 1.0 Scope This program establishes the management system and controls that the Brunswick Steam Electric Plant (BSEP) uses to assure safe and effective solidification of various low-level radioactive waste liquids and slurries for off-site disposal.
2.0 Objective It is the objective cf this program that the solidification of various low-level radioactive waste liquids and slurries (including oily waste) l for off-site disposal will be performed by approved vendors. The quality of the solidified product is to meet or exceed regulatory guidances and the disposal site criteria.
3.0 Hanagement Program 3.1 Responsibilities 3.1.1 The General Manager is responsible for verifying that the l contracted services meet CP&L standards and specifications.
3.1.2 The Manager - E&RC is responsible for:
- a. Advising the General Manager on the appropriate technical standards, regulations, and requirements as related to solidification and shipping.
- b. Reviewing the vendor's Process Control Program,.
operating procedures, and proposed contractural agreements and advising the General Manager as to their adequacy.
- c. Retaining vendor supplied documentation for NRC 1
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 Principal Specialist - Environmental of the Radiological and Chemical Support section is responsible for advising the Manager - E&RC on:
- a. The appropriate technical standards, regulations, and i
, requirements as related to solidification and shipping; and l
I
- b. The adequacy of the vendor's Process Control Program, operating procedures, and proposed contractural agreements. ,
3.2 Specifications for Vendors j 1
The qualified solidification vendor will: '
I 3.2.1 Provide a process control program approved by:
i
- a. NRC l
- b. Disposal site licensee 3.2.2 Demonstrate the ability to meet: L
- a. NRC solidification standards .
I
- b. Disposal site specifications for solidified liquid waste
- c. DOT shipping regulations j
- d. CP&L radiation protection procedures and practices ,
3.2.3 Provide documentation on the following for CP&L review, ;
evaluation, and retention:
- a. Solidification system design including a sketch of ;
the processing system (s) !
- b. Identification of solidification agent (s) f
- c. Operating process control procedures with the process j 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.
- 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 PCP (BSEP)' 2 .Rev. 1
3.3 Program Operations 3.3.1 The vendor will solidify and package the supplied liquid waste and slurries (including the oily waste) according to l approved procedures.
3.3.2 The vendor will perform the tests described in the l
approved Process Control Program.
)
3.3.3 The vendor will supply the Manager - E&RC with all documentation required to demonstrate compliance with solidification requirements.
3.3.4 The Manager - E&RC .will retain documentation required to demonstrate compliance with solidification requirements and standards.
4.0 Management / Contractor Interactions 4.1 The vendor is accountable to the Manager - Operations for the solidification of liquid waste.
4.2 The E&RC subunit handles the shipping of solidified waste and maintains required documentation. The vendor and the E&RC Shipping Foreman may communicate on these matters as necessary.
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.. s Attachment 4 Environmental Monitoring Program Brunswick Steam Electric Plant January - June 1984 Enclosure 1: Milk and . Vegetable Sample Locations
-l Enclosure 2: Land Use Census a
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Milk and Vegetable Sample Locations Milk samples from sample points 76 (0.9 miles SE Steven's Farm) and 77 (14.5 miles NNWr Johnson's Farm - Control) have become unavailable. The milk animal at sample point 76 did not produce milk during the time period from January 1, 1984, to June 30, 1984. The commercial dairy at sample point 77 is out of business and all milk animals have been sold. New milk sample locations have not been identified due to the unavailability of sample locations. Pursuant to Technical Specification Table 3.12.1-1, footnote h, broad-leaf vegetation will be sampled as indicated in Technical Specification Table 3.12.1-1, Item 4c, in lieu of milk samples.
The revision to the Off-site Dose Calculation Manual (ODCM), reflecting these changes, is in progress and will be included in the next Semiannual Radioactive Effluent Release Report.
Vegetable sample locations were unchanged during this time period.
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Enclosure 2 Land Use Census In accordance with Technical Specification 3.12.2.a, a land use census is performed once per year and has not yet been carried out. This census will be performed during the second semiannual reporting period. Results from this census will be included in the next Semiannual Radioactive Effluent Release Report.
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A*ITACHMEffT 5 INOPERABLE EITLUENT INSTRUMEhTATION January - June 1984 Brunswick Steam Electric Plant Enclosure 1: Radiodetive Liquid Effluent Monitoring Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation Enclosure 3: Liquid Hold-up Tank 9
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ENCIASURE 1 Brunswick Steam Electric Plant Radioactive Liquid Effluent Monitoring Instrumentation No radioactive liquid offluent monitoring instrumentation was inoperable over a 30-day period between the dates of January 1, 1984, and June 30, 1984.
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l ENCLOSURE 2 ,
Brunswick Steam Electric Plant Radioactive Gaseous Effluent Monitoring Instrumentation i
I. Augmented Off-Gas Monitor (1-A0G-RM-103)
At 0000 on January 19, 1984, the Unit 1 augmented off gas monitor (1-A0G-RM-103) was declared inoperable. The monitor was submerged for an extended period of time due to pipe breakage in the A0G !
Building. Delays in the allocation of parts prevented Maintenance l from repairing the monitor. These parts were installed on l February 27, 1984, and the LCO (AI-84-095) was canceled on March 1, 1984.
II. Main Condenser Off-Gas Treatment System Explosive Gas Monitoring I System Train A Hydrogen Monitors (1-0G-AR-4285 and 1-0G-AR-4284) l At 1400 on Febuary 7, 1984, the Uni.t 1 steam jet air ejector (SJAE) train A hydrogen monitor (1-OG-AR-4285) was declared inoperable (LCO 1-84-223). Maintenance discovered the problem originated from a design defect. The monitors are designed to operate under a higher pressure than the steam lines are developing. This problem was referred to Engineering for review and action. At 2000 on April 17, 1984, an LCO, 1-84-557, was issued on the second train A hydrogen monitor (1-0G-AR-4284). The same design flaw was found.
Engineering attempted to modify these monitors by installing pressure regulators in the steam lines. These regulators only further restricted steam flow and did not solve the problem.
Engineering is presently making modifications to the hydrogen monitors in the SJAE on Unit 2. If these modifications are successful on Unit 2, similar modifications will be implemented on Unit 1. ,
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ENCLOSURE 3 Brunswick Steam Electric Plant Liquid Hold-Up Tank No liquid hold-up tank exceeded the 10 Ci limit between the dates January 1, 1984, and June 30, 1984 4
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ATTACHMENT 6 MAJOR MODIFICATIONS TO RADIOACTIVE WASTE TREATMENT January-June 1984 Brunswick Steam Electric Plant
' Discussions 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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ATfACHMENT 7 Meteorological Data Brunswick Steam Electric Plant January - June, 1984 As required by Technical Specification 6.9.1.10.a. the annual summary of meteorological data will be reported within 90 days after January 1 of each year and is not included in this report.
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l ATTACHMENT 8 Potential Dose Assessment Brunswick Steam Electric Plant January - June, 1984 l
l As required by Technical Specification 6.9.1.10.b, an assessment of radiation l doses due to the radioactive liquid and gaseous effluents released during 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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- gyP 84 AUc 23 A QttMa B'runswic Electric Plant 3e<d'r Ru P. O. Box 10429 Southport, NC 28461-0429 August 21, 1984 FILE: B09-13510C SERIAL: BSEP/84-1773 Mr. James P. O'Reilly, Administrator U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street hV Atlanta, GA 30323 BRUNSWICK STEAM ELECTRIC PLAhT UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
Dear Mr. O'Reilly:
Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick '
Steam Electric Plant covering the period from January 1, 1984, through June 30, 1984.
This report is submitted in accordance with Section 6.9.1.8 of the Technical Specifications for Brunswick Steam Electric Plant.
Very truly yours,
. C. R. Dietz, General Manager Brunswick Steam Electric Plant SLV/kal/LETKAL Enclosure cc: Mr. R. C. DeYoung NRC Document Control Desk DESIGUATED ORIGINAll-Cog,itied By ,
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