ML20082H738
| ML20082H738 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20082H725 | List: |
| References | |
| NUDOCS 9108260254 | |
| Download: ML20082H738 (24) | |
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i Brunswick Steam Electric Plant [ r Semiannual Radioactive Effluent Report f i January 1, to June 30, 1991 l r ATTACHMENTS: PAGES:
- 1. Supplemental Information 2 -6 ,
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- 2. Effluent and Waste Disposal Data 7 -20 j
.3. ODCM and PCP Revisions 21 - 43
- 4. Environmental Monitoring Program 44 - 46 i
- 5. Effluent Instrumentation 47 - 50 i
-6. Major Modification to Radioactive Waste 51 (
Treatment Systems {
- 7. Meteorological Data 52
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- 8. Annual Dose Assessment 53 j
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. 9108260254 910821 i
.PDR- ADOCK 05000324 R POR
r s _,: + i ATTACl! MENT 1 Supplemental Information > January 1, to June 30, 1991 1 I k 1 7 r T i 4 1
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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility: Brunswick Steam Electric Plant Licensee: Carolina Power and Light Company
- 1. Regulatory Limits A. Fission and activation gases (Technical Spec. 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 Spec. 3.11.2.3)
*(1) Calendar Quarter (a) 15 mrom to any organ (2) Calendar Year (a)-30 mrom to any crgan (3) Calendar Quarter for Burning Contaminated Oil (a) 436 uCi (4) Calendar Year for Burning Contaminated 011
.(a)_872 uCi C. Liquid effluents (Technical Specification 3.11.1.2)
**(1) Calendar Quarter (a)- 3 mrem to total-body (b) 10 mrem to any organ (2) Calendar Year (a) 6 mrem to total body (b)'20 mrem to any organ NOTE: Dose calculations are determined in accordance with the Off-Site Dose Calculation Manual (ODCM)
*Used for percent of technical specification limit determinations in Table-1A.
**Used for percent of technical specification limit determinations in Table 2A.
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- 2. Maximum permissible concentrations and dose rates which detcrmine maximum instantaneous release rates.
A. Fission and activation gases (Technical Specification 3.11.2.1.a) (1) 500 mrem / year to total body (2) 3000 mrem / year to the skin B. Iodin 3-131, iodine-133, tritium, and particulates with half-lives greater than eight days (Technical Specification 3.11.2.1.b) (1) 1500 mrom/ year to any organ C. Liquid effluents (Technical Specification 3.11.1.1) The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to the concentrations specified in 10CFR20, Appendix D, Table II, column 2, for radionuclides other than noble gases.
* * (1) . Tritium: MPC = 3 E-03 uC1/ml and
**(2) Dissolved and entrained gases: MPC = 2 E-04 uCi/ml
- 3. Measurements and Approximations of Total Radioactivity A. Fission and activation gases o Analysis for specific radionuclides in representative grab l samples by gamma spectroscopy.
B. Iodines Analysis for specific radionuclides collected cnr charcoal cartridges.by gamma spectroscopy. C.-Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy, t , D. Particulates for Burning oil ; Analysis for specific-radionuclides by grab samples of each batch of oil to be burned. E. Liquids-Effluet.Ms Analysis for specific radionuclides of individual releasoa by gamma spectroscopy.
** Used as applicable limits for Table 2A Page 4
Nuclear counting _ statistics are reported utilizing 1-sigma error. Total error where reported represents a best effort to approximate the' total of all-individual and sampling errors.
- 4. Batch Releases v
A. Liquid (1) Number of batch releases: 1.06E+02 i (2) Total time period for batch releases: 1.12E+04 ! Minutes l (3) Maximum time period for a batch release: 1.70E+02 [ Minutes I (4) Average time period for a batch release: 1.06E+02 Minutes j (5) Minimum time period for a batch release: 1.30E+01 [ Minutes ; (6) Average stream flow during periods of release of effluent into a flowing i stream : 5.31E+05 } GPM ! B. Gaseous (1) Number of' batch releases: 0.00E 00 . Minutes { (2) Total time period for a batch release: 5 0.00E 00 ' Minutes (3) Maximum time period for a batch release: 0.00E 00 Minutes , (4) Average time period for a batch release: .0.00E 00- f Minutes ! (5) Minimum time period for a batch release: .0.00E 00 ;
-Minutes j
- 15. .'.bnormal releases'* i JL-Liquid 1 (1)-Number of releases: 0.00E+00 :
(2)-Total: activity released: 0.00E+00 :
-Curies B. Gaseous (1)~ Number-of releases: 0.00E+00 !
(2) Total activity released: 0. 00E4 00 { Curies !
- There were no abnormal releases that exceeded-10CFR50-1-imits See Page 6 for a discussion of release events that occurred. !
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5 Non-Routinq_Releason Liquid Releases - Total Releases = 1.00E+00 , Total Curies = 1.47E-04
- 1. Storm
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Drain Basin - The Storm Drain Basin was released to the discharge canal via the emergency dischargo line during a period of heavy rainfall. It was necessary to open the emergency discharge line for approximately 183 minutes. The amount of water Teleased via this pathway is approximately 4.80E+06 liters containing an estimated 1.47E-04 Ci of I-133, 1 l l-Page 6
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j I ATTACHMENT 2 Effluent and Waste Disposal Data i Brunswick Steam Electric Plant , I January 1, to June 30, 1991 i Enclosure 1 ; Table 1A: Gaseous Effluents - Summation of all Releases i i Table 1B:- Gaseous Effluents - Elevated Releases { Table 1C: Gaseous Ef fluents - Ground Level Releases f Table 1D: Gaseous Effluents - Burning Contaminated 011 [ Tablo 2A: Liquid Effluents - Summation of all Releases [ Table 2B: ' Liquid Effluent j Lower Limits of Detection j
-Table 3: Solid Waste and Irradiated Fuel Shipments i Enclosure 2 l 1
Combustion of Waste 011 ' b
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TABLE 1A Effluent and Waste Disposal Semiannual Report for Year 1991 Gascott Effluents - Summation of all Releases Est, Tot. Uni.t Qtr._1 Otr_2 Error % A. F1SSION AND ACTIVATION GASES-
- 1. Total release C1 1.68E+02 2.07E+02 1.15E 02
- 2. Average release uCi/sec 2.16E+01 2.63E+01 rate for period
- 3. Percent of technical specification limit % 1.40E-02 3.50E-02 B. IODINES
- 1. Total I-131 C1 1.62E-03 8.74E-04 7.00E 01
- 2. Average release uci/sec 2.08E-04 1.11E-04 rate for period C. PARTICUIATES
- 1. Total release Ci 2.96E-03 1.31E-03 7.00E 01
- 2. Average release uCi/sec 3.81E-04 1.67E-04 rate for period
- 3. Gross alpha Ci -1.77E-06 1.70E-06 D. Tritium
- 1. Total release Ci 3.48E+00 5.47E+00 7.00E 01
- 2. Average release uC1/sec 4.47E-01 6.96E-01 rate for period E. IODINE-131. IODINE-133. TRITIUM AND PARTICULATES
- 1. Total Release Ci 3.49E+00 5.48E+00
- 2. Average release UCi/sec 4.49E-01 6.97E-01 rate for period
- 3. Percent ~of technical specification limit % 5.80E-02 3.30E-02 L F. PARTICULATES VIA BURNING CONTAMINATED OIL L
- 1. Total Release Ci 0.00E-00 0.00E-00
- 2. Average _ release rate for period uci/sec 0.00E-00 0.00E !
l -- 3. Percent of technical specification limit % 0.00E+00 0.00E+00 Page 8
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. TABLE 1B Effluent and Waste Disposal Semiannual-Report for-Year 1991 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 1 Otr 2
- 1. FISSION GASES argon-41 Ci- 5.67E-01 1.26E+01 krypton-85m. Ci 9.87E+00 2.54E+01 krypton-87 Ci 6.06E+00 5.45E+00 l krypton-88 Ci 7.40E+00 3.55E+01 !
xenon-133 Ci 4.92E+01 4.53E+01 ! xenon-135m Ci 2.96E+00 8.30E+00 i xenon-135 C1 1.38E+01 4.59E+01 i xenon-137 C1 1.38E+01 3.11E+00 l xenon-138 Qi 6.80E+00 6.71E+00 l total for period Ci 1.10E+02 1.88E+02 l
- 2. IODINES- f iodino-131- C1 1.46E-03 6.06E-04 !
iodine-132 Ci 1.24E-03 9.09E-04 iodine-133 Ci 3.32E-03 2.33E-03 ! iodine-135 C1 2.71E-03 2.'3P-Q1 2 [ total for period Ci 8.73E-03 5.98E-03 !
- 3. . PARTICULATES ;
chromium-51 Ci 1.38E-04 3.32E-05 1 manganese-54 Ci 1.23E-05 2.71E-06 I cobalt-57 Ci <LLD 7.43E-07 - cobalt-58. Ci- 4.35E-06 <LLD cobalt-60 Ci 9.45E-05 1.60E-05 E strontium-89 Ci 2.59E-04 '2.08E-04 I L strontium-9C Ci 9.61E-07 5.37E-07 !
- l. cesium-137 Ci '
. 15E-05 4.91E-06 !
L barium-140 Ci 2.75E-04 2.16E-04 { l
~ lanthanum-140 gi 4.57E-04 3.88E-04 L total for period C1 -1.25E-03 8.70E-04 ;
L 4. TRITIUM t hydrogen-3 C1 1.74E+00 2.67E+00 [ i I f Page 9
TABLE 1C Effluent and Waste Disposal Semiannual Report for Year 1991 Gaceous Ef fluents - Ground Level Releases Continuous Release Huglides Release.d Unit Otr 1 Otr 2
'1. FISSION GASES krypton-88 Ci 5.04E-01 <LLD I xenon-133 C1 1. 3 8E4 01 1.06E+01 '
xenon-135m C1 1.07E+01 <LLD xenon-135 C1 3.32E+01 8.45E+00 total for period Ci 5.82E+01 1.91E+01
- 2. IODINES iodine-131 C1 1.59E-04 2.68E-04 i iodine-132 Ci 1.64E-03 2.84E-03 I iodine-133 Ci 1.17E-03 2 . '.! 6 E- 0 3 iodine-134 Ci 9.04E-04 <LLD iodine-135 C1 1.98E-03 3.29E-03 total for period Ci 5.85E-03 8.66E-03
- 3. PARTICULATES
-chromium-51 Ci 9.56E-04 2.69E-04 manganese-54 C1 1.34E-04 2.33E-05 cobalt-57 Ci 5.07E-07 5.96E-07 cobalt-58 Ci 5.61E-05 9.40E-06 cobalt-60 Ci 5.61E-04 1.38E-04 strontium-89 C1 3.06E-07 1.60E-06 strontium-90 Ci <LLD 1.54E-07 ruthenium-103 Ci <LLD 4.84E-08 cesium-137 Ci 6.68E-07 1.12E-06 gg.rium-144 C1 4.10E-07 <LLD total for period C1 1.71E-03 4.43E-04
- 4. TRITIUM hydrogen-3 C1 1.74E+00 2.80E+00 TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1991 Gaseous Effluents - Ground Level Releases For Burning-Contaminated Oil Nuclides-Released Unit Otr 1 -Otr 2
- 1. PARTICULATES
- C1 N/A N/A
*No contaminated oil was incinerated during this reporting period.
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TABLE 2A Effluent and Waste Disposal Semiannual Report for Year 1991 Liquid Effluents - Summation of all Releases i Unit Otr 1 Otr R Est Tot
% ErE2r A. FISSION AND ACTIVATION PRODUCTS
- 1. Total release (excluding Ci 6.68E-02 2.79E-02 3.50E 01 tritium, gases, & alpha)
- 2. Avg. diluted conc. uCi/ml 4.81E-09 3.23E-09
- 3. Percent limit % 7.20E-02 6.10E-02 B. TRITIUM
- 1. Total release C1 1.27E+01 9.72E+00 4.00E 00
- 2. Avg. dilu ed conc. uCi/ml 9.14E-07 1.13E 66
- 3. Percent limit % 3.05E-02 3.77E-02 C. DISSOLVED AND ENTRAINED GASES
- 1. Total release Ci 7.29E-03 3.68E-03 3.50E 01
- 2. Avg. diluted conc, uCi/ml- 5.24E-10 4.26E-10
- 3. Percent limit % 2.62E-04 2.13E-04 D. GROSS ALPHA RADIOACTIVITY 1.-Total release Ci < LLD 1.49E-07 4.00E 01 E. VOLUME OF WASTE liters 4.60E+06 3.05E+06 1.25E 01 F. TOTAL OF DILUTION WATER' (used durina release for averace dil. conc.) liters 1.39E+10 8.63E+09 1.30E 01 G. VOLUME OF COOLING WATER liters 3.02E+11 3.33E+11 DISCHARGED FROM PLANT l
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i TABLE 2B l' Effluent and Waste Disposal Semiannual Report for Year 1991 Liquid Effluents - Batch Mode Nuclides Released l!nii Qtr_1 Otr 2
- 1. FISSION AND ACTIVATION PRODUCTS ;
sodium-24 Ci 6.83E-05 <LLD ! chromium-51 Ci 3.21E-02 1.03E-03 l manganese-54 Ci 3.42E-03 5.39E-03 l iron-55 Ci <LLD 1.17E-03 i manganese-56 Ci 7.19E-05 <LLD i cobalt-57 C1 1.57E-06 <LLD i cobalt-58 Ci 2.49E-03 9.12E-04 ! cobalt-60 C1 2.10E-02 1.84E-02 [ zinc-65 Ci 4.20E-06 <LLD ! zinc-69m Ci 2.48E-06 1.07E-06 [i arsenic-76 Ci 2.71E-04 1.48E-05
. yttrium-91m Ci 9.57E-06 2.15E-06 !
yttrium-92 Ci 5.87E-05 <LLD , strontium-92 Ci 8.57E-06 <LLD { technetium-99m Ci 6.20E-04 <LLD antimony-124 Ci 5.25E-04 <LLD [ antimony-125 C1 2.79E-03 <LLD t tellurium-129 Ci <LLD 6.55E-05 ; iodine-131 C1 2.62E-04 <LLD ! iodine-133 Ci 2.70E-05 <LLD i cosium-134 Ci 7.56E-04 1.05E-04 cesium-137 C1 1.84E-03 7.79E-04 lanthanum-141 Ci 2.69E-04 <LLD : cerium-144 Ci 4.84E-05 <LLD l tungsten-187 C1 1.88E-04 <LLD ! total for period Ci 6.68E-02 2.79E-32 > i
- 2. DISSOLVED AND ENTRAINED GASES 1
Nuclides Released Unit Otr 1 Otr 2 [i krypton-85 Ci <LLD 2.05E-04 krypton-87 Ci <LLD 2.56E-06 xenon-133 C1 2.18E-03 1.79E-03 xenon-135m Ci 3.76E-06 <LLD ; xenon-135 gi 5.11E-03 1.68E-03 ! l total for period Ci 7.29E-03 3.68E-03 l Page 12 l
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-Lower Limits of Detection January 1, to June 30, 1991 uci/ml
- 1. Liauld Releases 2. Gaseous Releases Na-24 2.43E-08 Kr-88 3.12E-08 Fe-55 1.76E-07 Xe-135m 1.66E-07 Mn-56 8.51E-08 Co 1.62E-08 4 Zn-65 4.32E-08 Sr-92 1.76E-08 3. Iodines and Particulaten Y-92 1.81E-07 Tc-99m 1.62E-08 Co-57 2.81E-14 Sb-124 2.52E Co-58 4.56E-14 Sb-125 5.28E-08 Ru-103 4.31E-14 Te-129 3.76E-08 I-134 tw too short I-131 1.99E-08 Ce-144 2.26E-13 I-133' 2.03E-08 La-141 8.03E-07 Ce-144 1.24E-07 W-187 '1.01E-07 Kr-85 5.29E-06 Kr-87 4.86E-08 Xe-135m 8.42E-08 Alpha 2.57E-08 NO7ES 1: ~The above values represent typical "a priori" LLDs for isotopes where values of "<LLD" are indicated ~in Tables 1A, 1B, 1C,-2A, and 2B.
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- Where activity for any nuclide is reported as " Less than.
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-LLD", that nuclide is considered not present and'the LLD activity listed is not considered in summary data, k
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, i Table 3A Effluent and Waste Disposal Semiannual Report for Year 1991 :
Solid Waste and Irradiated Fuel Shipments ;
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Waste Class A January throuah Juno i
- 1. Total volume shipped (cubic meters) 1.89 E2 Total Curie quantity (estimated) 2.57 E2
- 2. Tyne of W4F_t2 Six-month Est. Total Units Period % Error
- a. Spent resins, filter sludges meters 6.47 El Curiec 3 2.31 E2 1.00E1 r
- b. Dry active waste, compacted meters 1.24 E2 noncompacted Curies 3 2.58 El 1.00E1
- c. Irradiated components meters 0.00 E0 Curies 0.00 EO N/A ;
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- d. Others (oil) meters 0.00 EO ,
Curies 0.00 EO N/A
- 3. Estimate of maior radionuclido composition
- a. Fe-55 6.81 El%
Co-60 1.85 El% Mn-54 7.08 EO% Ni-63 2.42 E0% Cs-137 2.16 E0%
- b. Mn 5.81 EO%
Fe-55 8.29 El%
- Co-60 1.09 El%
- c. N/A N/A
- d. N/A N/A Page 14
e Table 3A (cont.)- Effluent and Waste Disposal Semiannual Report for Year 1991 Solid Waste and Irradiated Fuel Shipments
- 4. Cross reference table, waste stream, form. and container type.1 Stream Form Container tyDe No. of shipmento
- a. Resin Dewatered & Type A/ Type B 11/02 Solidified *
- b. Dry active Compacted /non- STP 23 waste compacted waste
- c. Irradiated 0 N/A components
- d. Other 0 N/A
- solidification agent or absorbent (e.g., coment, urea formaldehyde) NONE
- 5. Shinment Disposition
- a. Solid Wasto Number of Shipments Mode of Transportation Destination 36 -Sole Use CNSI/Barnwell SC
- b. Irradiated Components Number of Shinments Mode of Transportation Destination 0 N/A- N/A Page 15
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7 TABLE 3B ! Effluent and Waste Disposal Semiannual Report for Year 1991 f Solid Waste and Irradiated Fuel Shipments ! Waste Class B January throuch June f
- 1. Total volume shioned (cubic meters) 3.85 EO f Total curie quantity (estimated) 5.44 E2 y i
- 2. Tyne of_ Waste Six-month Est. Total
!) nits 3 Eeriod i Error
- a. Spent resins, filter sludges meters 3.85 EO i Curies 3 5.44 E2 1.00 El i
- b. Dry active waste,-compacted, noters 0.00 EO N/A and noncompacted Curies 0.00 E0 3 1
- c. Irradiated components meters 0.00 EO N/A f Curies 3 0.00 EO :
- d. Others (describe) meters 0.00 EO N/A !
Curies 0.00 E0 i
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- 3. Estimate of maior radiontulide composition !
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- a. Fe-55 5.07 E1 -
Cr-51 2.20 El- ' Co-60 1.10 El Mn-54 9.99 EO ' I Fe-59 2.61 EO Co-58 2.35 EO ;
- b. N/A N/A
- c. N/A' N/A :
- d. N/A N/A f
- 4. Cross reference table, waste stream, form and container type
{ r' Stream Form Container type No. of shinments .
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- a. Resin -Dewatered & Type A/ Type 8 0/1 3 Solidified !
l -b. Dry active ' Compacted /non- N/A 0 compacted- ; waste l
- c. Irradiated N/A 0 !
ComDonents I
- d. Other N/A 0
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- Solidification agent or absorbent +
(e.g.,.coment, urea formaldehyde) NONE l P Page 16 s L e , - . . . _ . . . . ., ., , _ - , r ,--4 ..__.,y
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{ Table 3B (cont.)- Effluent and Waste Disposal Semiannual Report for Year 1991 t Solid Waste and-Irradiated Puel Shipments !
- = ;
-5.Shioment-Disposition
- a. Solid Waste '
Number of Shinments Mode of Trananortation Destination j i 3 SOLE USE CNSI/BARNWELL, SC l
- b. Irradiated Puel ,
i Number of Shloments Mode of Transnortation Destination ! O N/A N/A f Page 37
i TABLE 3C Effluent and Wasto-Disposal Semiannual Report for Year 1991 Solid Waste and Irradiated Fuel Shipments Waste class C- lannary th w h June
- 1. Total volume shioned (cubic meters) 0.00 EO Total Curio quantity (estimated) 0.00 E0 ;
- 2. Type of Waste Six-month Est. Tot.
Unito Period % Error 3
- a. Spent resins, filter sludges meters 0.00 EO N/A Curies 0.00 E0 3
- b. Dry active waste, compacted motorc 0.00 EO N/A and noncompacted Curies 0.00 E0 3
- c. Irradiated components meters 0.00 EO N/A Curies 3 0.00 E0
- d. Others (describe) meters 0.00 EO N/A Curies 0.00 EO
- 3. Estimate of maior radionuclide composition
- a. N/A N/A
- b. N/A- N/A
- c. -N/A N/A
- d. N/A N/A
- 4. Cross reference table, waste stream, form and cont,giner type Stream Form Container Tvoo No. of shippients
- a. Resin Dewatered & N/A 0/0 Solidified *
- b. Dry active Compacted /non- N/A 0 I waste compacted
- c. Irradiated N/A 0 components
- d. Others N/A 0
- Solidification agent or absorbent (e.g., cement, urea formaldehyde) NONE i
Page 18
Table 3C (cont.) Effluent and Wasto_ Disposal Somiannual Report for Year 1991 Solid Waste and-Irradiated Puel Shipments
- 5. Shinment Disposition
- a. Solid Waste Hymber of Shinments Mode of Transportation Destination 0 N/A N/A ,
- b. Irradiated Fuel (non-burial)
Number of Shingents Mode of Transnortation Destination 1 Railcar/IF-300-CASK CP& L/SHNPP Sole Uso-l l l I ( l-Page-19
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ENCLOSURE 2 Combustion of Waste 011 January 1, to June 30, 1991 There was'no contaminated waste oil incinerated during this reporting period. l Page 20 l
T l 4 ATTnCHM2NT 3 ( Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions January 1, to June 30, 1991 Brunswick Steam Electric Plant Revision 03 to the Process Control Program (PCP) was approved on April 25, 1991._ This revision included
-1. Page 1, Section 3.0 was changed to reflect new organizational titles and responsibilities.
- 2. Page 3,-Step 3.3 was changed to add a step to require vendor notification for program deviations.
Revision 03 of the PCP is attached.
-Revision 11 to the Off-Site Dose Calculational Manual was approved on May 30, 1991. This revision included:
- 1. Page 4-1 of the ODCM was revised to reflect the fact that the figures (maps) in section 4.0 had been replaced with new maps.
- 2. Pages 4-2 and 4-3 were changed to add 5 additional environmental TLD's to the environmental monitoring program and to-correct the location of TLD 77.
- 3. Pages 4-5 .and 4 were changed to include the new environmental-monitoring maps. i 4._Pago_ E of Appendix E was changed to remove the- old
-instrument number for the main stack system effluent flow rate measurement device.
Revision 11 of the ODCM is attached, i Page 21 l l
f.$. : Y o l ATTACHMENT 2 REQUEST FOR PROCESS CONTROL PROGRAM CHANGE C,s iginator t _ jgd/C dOO/C D te: //-/ 8'-7/
Pages and sections revised: W m, / g ec/< N ;3, /. /dm occ f<h 3,42 - P:tnr 3 Acflk 3r3 a M&'l Reason for change: (% s,se,g ey $6 edge lvb%,df///ts crses;f AAr4 At-spp,d.dH/< h ,-11/d4/ <1U7%s M r[<e-ig%, aum/m dwur
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