BSEP-89-0746, Semiannual Radioactive Effluent Release Rept for Brunswick for Jan-June 1989
| ML20246K884 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1989 |
| From: | Harness J CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BSEP-89-0746, BSEP-89-746, NUDOCS 8909060151 | |
| Download: ML20246K884 (31) | |
Text
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K ~ Carolina Power & Light Company.
!- -- hp ' Brunswick Nuclear Project-
, P. O. Box 10429 Southport, NC 28461-0429 August 25, 1989-
, , ~ FILE: B09-13510C SERIAL: BSEP/89-0746
~
.U.S.: Nuclear Regulatory Commission.
- ATI'N: Document Control. Desk Washington, DC L20555 BRUNSWICK STE AM ELECTRIC PLANT. UNITS 1 AND 2
- DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71~AND DPR-62 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
-Gentlemen:
Enclosed is the Semiannual Radioactive Effluent Release Report for' Brunswick Steam Electric Plant covering the period' from January 1, '1989, through -
June 30, 1989.
4, This report.is submitted for the Brunswick Steam Electric Plant in'accordance with. Technical Specification 6.9.1.8.
Very truly yours,
&!ew J. L. Harness, Genera Manager Brunswick Nuclear Project MJP/mcg Enclosure cc: Mr. S. D. Ebneter Mr. E. G. Tourigny BSEP NRC Resident Office 1'
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Brunswick Steam Electric Plant Semiannual Radioactive Effluent Beport January 1, 1989 to June 30, 1989 ATTACHMENTS: PAGES:
- 1. Supplemental Information 1/1 to 1/4
- 2. Effluent and Waste Disposal Data 2/1 to 2/14
- 4. Environmental Monitoring Program 4/1 to 4/3
- 5. Inoperable Effluent Instrumentation 5/1 to 5/4
- 6. Major Modification to Radioactive Waste 6/1 Treatment Systems
- 7. Meteorological Data 7/1
- 8. Potential Dose Assessment 8/1
ATTACHMENT 1 Supplemental Information January 1, to June 30, 1989 1/1
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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT 'I
- ' Supplemental.Information '!
Facility: . Brunswick' Steam Electric Plant-Licensee: Carolina Power and Light Company:
- i. Regulatory Limits l 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 particulate with half -
lives greater than eight days (Technical ~ Spec. 3.11 2.3)
- (1) Calendar Quarter (a)'15 mrem to any organ (2)-Calendar Year (a) 30' mrem to any organ C.' Liquid effluents (Technical Specification 3.11.1.2)
- (1) Calendar. Quarter-(a) 3 mrem to total body (b) 10 mrem to any 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.
l-1/2 ;
L-__-_--_-__-- ._ -- _
IL. - M ximum ' permissible concentrations ' and dose' rates which determine
[ maximun-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. Iodine-131, iodine-133, tritium, and particulate with half-
' lives greater than eight days (Technical Specification L 3.11.2.1.b) l (1) 1500 mrem / year to any organ C. Liquid effluents (Technical Specification 3.11.1.1)
The concentration of radioactive material released in liquid
, effluents to unrestricted areas after dilution in the discharge canal shall be limited to the concentrations specified in 10CFR20 Appendix B, Table II, column 2, for radionuclides other.than noble gases.
- (1) Trit ium: MPC = 3 E-03 uC1/ml and
- (2)-Dissolved and entrained gases: MPC = 2 E-04 uC1/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. Particulate Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.
D. Liquids Effluents Analysis for specific radionuclides of individual releases.
by gamma spectroscopy.
- Used as applicable limits for Table 2A 1/3
. e to.
Nuclear counting statistics are reported utilizing 1-sigma error.
Total' error- where. reported represents a best effort 'to
. approximate the total of'all individual and' sampling errors.
- 4. Batch Releases A. Liquid (1) Number of batch releases: 2.62E+02
.(2) Total time period for batch releases: 2.86E+04 Minutes
, (3) Maximum: time period for-a batch release: 2.91E+02 Minutes-(4) Average time period for a batch release: 1.09E+02 Minutes (5). Minimum time period for a batch release: 1.00E+00 Minutes-(6). Average stream flow during periods of release of effluent into a flowing stream : 6.53E405 GPM B. Gaseous (1) Number of baten releases: 0.00E 00 Minutes (2) Total time period for a batch release: 0.00E 00 Minutes (3) Maximum time period for'a batch release: 0.00E 00 Minutes
-(4) Average time period for a batch release: 0.00E 00 Minutes (5) Minimum time period for a batch release: 0.00E 00 Minutes
- 5. Abnormal releases A. Liquid (1) Number of releases: 0.00E 00 (2) Total activity released: 0.00E 00 Curies B. Gaseous (1) Number of releases: 0.00E 00 (2) Total activity released: 0.00E 00 Curies 1/4
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~ , 't ATTACHMENT 2 Effluent and Waste Disposal-Data Brunswick Steam Electric Plant January 1, 1989 to June 30, 1989
Enclosure:
1-Table 1A: Gaseous Effluents - Summation of all Releases Table 18: Gaseous Effluents - Elevated Releases-(note 1)
Table 1C: Gaseous Effluents - Ground Level Releases (note 1)
Table 2A: Liquid Effluents - Summation of all Releases Table 28: Liquid Effluents (note 1)
Lower Limits of Detection Table 3: Solid Waste and Irradiated Fuel Shipments Enclosure 2 Combustion of Waste Oil (NOTE 1)
'The Sr-89 and Sr-90 values reported for the second quarter gaseous and liquid effluents are estimated using the average of the previous three quarters. This is necessary due to unavoidable delays in performing the analyses. When determined, if the actual values are significantly different from the estimated values then a supplement will be issued to report the actual values.
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. ETable 1A'.
Effluent.and1WasteLDisposal Semiannual Report , Year 1989
-Gaseous Effluents - Summation of all Releases _
r Est.
Total Unit' Otr 1 .Otr 2 Error.M i A, Fission and Activation Gases-1 .. Total release Ci 2.60E+02 3.92E+02 1.15E 02 L
- 2. Average release uCi/sec 3.34E+01 4.99E+01 rate for period 3 .. Percent of technical specification limit % 2.72E-02 6.60E-02 B. Iodines
- 1. Total I-131 Ci 7.26E-04 7.97E-03 7.00E 01
- 2. Average release UCi/sec 9.34E-05 1.01E-03 rate for period C.. Particulate
- 1. Total release Ci 8.48E-03 1.44E-02 7.00E 01
- 2. Average release uCi/sec 1,.09E-03 1.83E-03 rate for. period
~2. Average release uCi/sec 1.S2E-01 1.73E-01 rate for period E. Jp, dine-131 Lodine-1_332 Tritium and Particulate
- 1. Total Release C1 1.19E+00 1.42E+00
- 2. Average release UCi/sec 1.53E-01 1.81E-01 rate for period
- 3. Percent of technical specification limit % 3.20E-02 2.81E-01 2/2 M -__.-----.s------------ - . - - - - - - - - - - - - - . - _ _ - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
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., ' Table.1B Effluent'and Waste Disposal: Semiannual Report Year 1989 Gaseous Effluents - Elevated Releases Continuous Release, Nuclides Released Unit otr 1 otr 2
- 1. Fission Gases
- argon Ci < LLD 2.96E+00 krypton-85m Ci 1.49E+01 2.44E+01 krypton-87 Ci 6.41E-01 2.79E+00 krypton-88 C1 1.48E+01 l'. 21E+ 01
- xenon-133 Ci 4.27E+01 1.09E+02 xenon-135m Ci 1.09E+01- 1.99E+01' xenon-135 Ci 1.29E+01 '1.44E+01 xenon-137 Ci 4.73E+01 1.06E+02 xenon-138 Ci 1.23E+01 4.60E+01 total for period Ci 1.56E+02 3.38E+02
- 2. Iodines
' iodine-131 C1 4.60E-04 7.20E-03 iodine-132. Ci- 5.83E-04 1.71E-02 iodine-133 C1 2.51E-03 3.41E-02 iodine-134 Ci < LLD 3.02E-04 iodine-135- Ci_ 1.11E-03 3.31E-02 total for period Ci 4.66E-03' 9.18E-02
- 3. Particulate chromium-51 Ci 2.75E-05 9.07E-04 manganese-54 C1 1.70E-05 1.21E-05 cobalt-58 Ci < LLD 1.41E-05 cobalt-60 Ci '4.18E-05 2.51E-05 strontium-89 C1 1.'00E-04 2.61E-04
= strontium-90 Ci 4.57E-07 1.30E-06~
cesium-134 Ci < LLD 1.74E-05 cesium-137 Ci 1.01E-05 2.41E-05 barium-140 Ci 2.07E-05 4.44E-04 lanthanum-140 C1 3.99E-06 3.21E-04 total for period C1 2.22E-04 2.03E-03
- 4. Tritium hydrogen-3 Ci 7.49E-01 6.76E-01 2/3
4 .
Tablei1C
-Effluent. and Waste, Disposal-Semiannual 1 Report! Year.1989 Gaseous' Effluents - Ground Level-Releases Continuous Release Nuclides Released Unit'- 'Otr 1 Otr 2
- 1. Fission Gases.
-xenon-133 Ci '5.43E+01 '3.64E+00 xenon-135m Ci < LLD 7.65E+00 Xenon-135 Ci 4.99E+01 4.27E+01 totaJ. for~ period C1 1.04E+02' 5.40E+01
- 2. Iodines-
- iodine-131- Ci- 2.66E-04 7.71E-04 iodine-132 Ci < LLD 5.69E iodine-133 Ci '2.19E-03 5.53E-03 iodine-134 Ci < LLD 1.06E-03 iodine-135 .
C1 6.18E-03 7.13E-03 total.for period Ci 8.64E-03 2.02E-02
- 3. E_ articulates chromium-51 Ci 5,59E-03 1.16E-02 maganese Ci 6.87E-04 .1.76E-04 cobalt-57 Ci 2.35E-07 2.76E cobalt-58 Ci 1.92E-04 1.85E-04 cobalt-60 C1 1.71E-03 3.93E-04.
firon Ci 1.63E-05 < LLD strontium-89 Ci 8.02E-06 6.84E-06 strontium-90 Ci < LLD 1.57E-06 niobium-95 Ci 5.37E-06 < LLD ruthenium-103 Ci 6.27E-06 < LLD cesium-134 Ci 9.11E-06' < LLD cesium-137 C1 4.01E-06 6.32E-07 barium-140 Ci < LLD 4.77E-05 lanthanum-140 Ci < LLD 3'50E-05 cerium-141 C1 <-LLD 3.51E-07' cerium-14'4 Ci 2.16E-05 ( LLD hafnlum-181 Ci 1.10E-05 < LLD total for period C1- 8.26E-03 1.24E-02
b, 0; '. -
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'g Table 2A J 'Efflu'ent.and Waste < Disposal-' Semiannual Report Year 1989
- t. LLiquid Effluents - Summation of all. Releases Unit OE f Qt_r_ R st Tot
/A.' Fission and Activation Products
- 11. Tot'al release (excluding Ci 6 27E-01 - 7. 44E 3.50E 01-tritium.cgases, & alpha)
- 2. Avg.~--diluted conc. uC1/ml 2.16E-08 1-.78E-08 3' . Percent limitL % '5.11E-01 -2.48E-01.
B. Tritium
- 1. Total release- C1 -2.79E+00 4.66E+00 4.00E'00
'2. Avg'. diluted conc. - uCi/ml' 9.62E-08 1.12E-07
- 3. Percent limit % 3.21E-03 3.73E-03 C.-Dissolved and' Entrained Gases 1 Total-release Ci 6.10E-02 5.64E-02 3.50E 01 l..
2 Avg. diluted conc. uC1/ml 2.10E-09 1.35E-09-.
l
- 3. Percent' limit % 1.05E-03 6.75E-04 D. Gross alpha radioactivity-
- 1. Total release Ci < LLD 7.70E-05 4.00E 01 1
E.~ Volume of waste liters 9.93E+06 9.47E+06 1.25E 01 F. Total o_f dilution-water
. (used during released for. average dil. cone.) liters 2.90E+10 4.17E+10 1.30E 01-G. Volume of cooling water liters 2.65E+11 4.16E+11 i
discharged from plant 1
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TABLE 23.
. Effluent 1and Waste Disposal Semiannual Report Year 1989 L Liquid Effluents - Batch Mode-hi--
Nuclides Released
~
Unit Otr 1 Otr 2
- 1. Fission and activation products sodium-24 Ci 7.99E-03 2.98E-03 >
chromium-51 C1 2.86E-01 5.62E-01 manganese-54. Ci 5.70E-02 3.92E-02 iron-55 C1 2,.50E-03 1.50E-03 manganese-56 C1 4.70E-04 6.65E-04 cobalt Ci 1.62E-02 1.25E-02 l iron-59 Ci 3.62E-04 8.11E-04 y cobalt C1 1.11E-01 5.44E-02 l zinc Ci 4.19E-04 6.77E-05 g . arsenic-76 Ci 9.82E-04' 7.64E-04 f strontium-89 Ci 9.10E-04 4.93E-04 strontium-90 Ci '2.30E-04 1.47E-04 yttrium-91m Ci < LLD 3.64E-05 yttrium-91: Ci 9.61E-04 4 LLD yttrium-92 Ci < LLD 1.10E - strontium-92 Ci <.LLD 3.71E-05 niobium-95 Ci 1.02E-05 5.99E-06' molybdenum-99 C1 1.06E-04 < LLD ,
technetium-99m- C1 2.59E-02 2.22E-02 l technetium-104~ Ci _
<: LLD 6.70E-05 l -ruthenium-105- C1 _2.76E-04 3.61E-05 silver-110m: C1. < LLD 6.84E-05.
tellurium-129m. Ci 6.56E-05 < LLD iodine-131 Ci 1.45E-03 5.39E-03
. iodine-132 Ci < LLD 5.11E-05 tellurium-132 Ci 2.08E-05 1.67E-04 iodine-133 Ci 2.60E-03 1 65E-03 cesium-134 Ci 5.63E-02 1.78E-02
- iodine-135 Ci 7.51E-04 6.85E-04 cesium-136 Ci < LLD 7.58E-04 cesium-137 Ci 5,38E-02 1.69E-02 cesium-138 C1 4.50E-05 < LLD cer.ium-144 C1 1.38E-05 4.58E-05 hafnium-181 C1 1.85E-05 < LLD tungsten-187 Ci 4.61E-04 1.42E-03 neatunium-239- C1 2.00E-04 1.35E-03 total for period Ci 6.27E-01 7 44E-01
- 2. Gases argon-41 C1 4.21E-05 < LLD krypton-85m Ci < LLD 8.46E-06 L ' xenon-133 C1 1.10E-02 9.26E-03 l- xenon-135r C1 1.75E-04 5.58E-04 l xenon-135- Ci 4.98E-02 4.66E-02 total for period Ci 6.10E-02 5.64E-02
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Lower Limits ofcDetection
., J tt January through' July 1989
- i. uC1/ml1 l . l'. Liouid Releases ,2. Gaseous Eglegseg Ar-41 2.86E Ar-41 1.08E-OS Kr-85m 1.30E-08 Xe-135m 4.72E-08 Y-91m 2.59E-08 Y-91 3.64E-06
.Sr-92 3.18E-08 '3., Iodines and Particulate Y-92 1.41E 07 No-99 1.12E-07 Co-58 3.4SE-14
.Tc-104 2.87E-08 Fe-59 8.07E-14
'Ag-110m' 5.01E-08 Nb-95 3.27E-14'
- l. -Te-129m -4.60E-07 Ru-103 ~ 3.89E-14 l
I-132 1.63E-08 'I-132 2.94E-13 Cs-136- 1.74E-08 1-134 T1/2 Too short Cs-138 4.65E-08 Cs-134 5.66E-14 Hf-181 1.69E-08 Ba-140 1.50E-13 Alpha 2.24E-08 La-140 9.32E-14 i
Ce-141 3.77E-14 L Ce-144 1.93E-13 '
Hf-181 4.06E-14 Sr-90 4.88E-16 NOTES' 1: The abave values represent typical '"a priori" LLDs for isotopes where values of "<LLD" are indicated in Tables IA, 18, 1C, 2A, and'28, 2: Where activity.for any nuclice is reported as " Less than l
LLD". that nuclide is considered not present and the LLD activity listed is not considered in summary data.
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.. 1 Table 3A~
Effluent and WasteLDisposal Semiannual Report- Year 1989- l l .: - Solid' Waste and Irradiated Fuel Shipments m;u I
Waste Class f- January through Lug fr 1. Total volume shipped (cubic meters) 3.82 E2 1 ..
1 Total Curie quantity (estimated) 5.86 E2 1 2. Tyng of Waste Units si_x-month Est. Total Period Error.%
- a. Spent resins. filter sludges meters 3 1655 E2 Curies- S.72 E2 1. 00E1.
meters 3 2.31 22'
~
- b. Dry active. waste. compacted noncompacted Curies 1,43 El 1.00E1
- 3. Estimate of major radi.onuclide composition
- a. Cr-51 S.90 EO%
Mn-54 1.21 E17.
Fe-55 3.6'7'E1%
Co-58 1.22 E07.
Co-60 2.96 El%
Hi-63 2.64 EO%
Cs-134' S.02 EO%
Cs-137 6.07 EO%
- b. Mn-54 6.55 EO%
Fe-55 6.99 El%
Co-60 1.94 El%
Ni-63 0.97 EO%
Cs-134 1.05 EO%
l Cs-137 1.27 EO%
- c. N/A N/A
- d. N/A N/A 2/8 1
p $NN .. , .. -
- h. .
-Table 3A (cont.)
Effluent and Waste Disposal Semiannual Heport Year 1989
. Solid Waste and Irradiated' Fuel Shipments ~
4 Cross reference table. waste stream. Lorm, and contaiggr_ type.
Stream Form Container 1;yppe No. of, ,s_ffipments
- a. Resin. Dewatered & Type A/ Type B 20/10 Solidified *
- b. Dry active Compacted /non- STP 13 waste compacted waste
- c. Irradiated ~ N/A N/A components 4
N/A
'd, Other N/A
- solidification agent.or absorbent (e.g,, cement, urea formaldehyde) NONE
- 5. S_hipment Disposition
- a. Solid Waste
. Number of Shipments- Mode pff_ Transportation!1 Destination 30 Sole Use CNSI/Barnwell SC
.13 Sole Use- SEG/ Oak Ridge TN
- b. Irradiated Components Number of Shipments Mode of Transportation Desti3ation O' N/A N/A
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=. _ - _ . _ _ _ _ _ _ _ _ - _ _ i
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b* Table 13B
.t Effluent and Waste. Disposal Semiannual Report Year 1989 Solia 4Sste and Irradiated Fuel Shipments Waste Class.R' lanuary through June
- 1. Total ~ volume shipped (cubic meters) 1.16 El Total: Curie quantity ~(estimated) _1.73 E3
- 2. Type of Waste Units Six-month Est' Total Period Error.%
- a. Spent resins, filter sludges meters 3 1:.16 El 1.00E1 Curies 1.73 E3 b.' Dry active waste, compacted, ' meters 3 N/A N/A and noncompacted Curies
- c. Irradiated components meters 3 -N/A N/A Curies
- d. Others (describe) meters 3 N/A N/A Curies
- 3. Estimate of major radionuclides composition
- a. Cr-51 1.53 El%
Mn-54 8.54 EO%
Fe-55 5.24 E;%
Co-58 1.99 EO%
Co-60 1.60 El%
Ni-63 1.61 EO%
Cs-134 2.10 EO%
Cs-137 1.94 EO%
- b. N/A N/A
- c. N/A N/A
- d. N/A N/A 4 Cross reference tablet waste stream, form and container type Stream Form Container type No. of shipments
- a. Resin Dewatered & Type A/ Type B 1 /2 Solidified 1'
- b. Dry active Compacted /non- N/A N/A compacted waste
- c. Irradiated N/A i .
components I
- d. Other N/A
- Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A 2/10
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Table 3B tcont.)
F>ffluent and Waste Disposal Semiannual Report Year 1989 Solid Waste and Irradiated Fuel Shipments 5, Shipment Disposition
- a. Solid Waste Number of Shipments Mode'of Transportation Destination 3 sole use CNSI/Barnwell-SC
- b. Irradiated Fuel 14 umber g Shipments. Mode o._[ Transportation Destination O. 14/A N/A 1
l l
2/11 uc ___a._____:__m_m___. -______ m__m-.m_ _ _ - _ . _ _ _ _ _____.-..m_ __ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
e -
Table 3C Effluent and Waste-Disposal. Semiannual Report . Year 1989 L Solid Waste and Irradiated Fuel Shipments Waste Class Q. January through June i
- 1. Total. volume shipped (cubic meters) 1.41'El L
Total Curie quantity (estimated) 2.00 E3
- 2. Typo'of Waste Unit Six-month Est. Total Period Error.%
- a. Spent resins, filter sludges meters 3 N/A Curies
- b. C.y-active waste, compacted meters 3 N/A-and noncompacted
- c. Irradiated components meters 3 1.41 El 1.00E1 Curles 2.00 E3 d.-Others (describe) meters 3 N/A Curies
- 3. Estimate of major radionuclides composition
- a. N/A
- b. N/A
- c. Fe-55 1.35 El%
Co-60 3.14 El%
Hi-63 1.32 EO%
Sb-1'25 S.37 El%
- d. N/A
- 4. Cross reference table, waste stream, form and container type Stream Form Container Typ_g No. of shipments
- a. Hesin Dewatered & N/A N/A Solidified *
- b. Dry active Compacted /non- N/A N/A waste. compacted
- c. Irradiated Type B 3 components
'd. Others N/A N/A
- Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A 2/12
~
i.
Table 3C (cont.)
Effluent and Waste Disposal Cemiannual Report Year 1989 Solid Waste and' Irradiated Fuel Shipments
- 5. Shipment Disposition
- a. Solid Waste Number of Shipments- Mode of Transportation Destination 3' sole use CNSI/Barnwell' SC
, b. Irradiated Components
- (( umber of Shi_pments Mode of _ Transportation Destination 0 N/A N/A l
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,[ ENCLOSURE 2 Combustion of Waste oil s:
January through June Year 1989.
There was no incineration of contaminated waste oil during a '
this reporting period.
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e i ATTACHMENT.3-Off-Site Dose' Calculation Manual (CDCM) and Process Control Program (PCP) Revisions'
- January 1, to June 30, 1989 Brunswick Steam Electric. Plant l
There were no revisions made to.the Off-rite Dose Calculation Manual (ODCM) or the Process Control Progrum-(PCP) during this.
. time period.. ."
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. .- ATTACHMENT 4 Environmental Monitoring Program January 1 .to June 30, 1989 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census 1:
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ENCLOSURE'1 Milk and Vegetable Sample Locations January through June Year 1989 No milk sample locations were i available during this time period.
p ' Vegetable sample loc
- ions were unchanged during this time period.
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ENCLOSURE 2 a...
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Land Use Census No new locations were identified that are reportable-in the
-:i s Semiannual Radioactive Effluent. Release Report as per Technical
- Specification 3.12.2.a and b.
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> - E- ' ATTACHMENT'5 Inoperable Effluent Instrumentation January.-1, to June 30, 1988 IEnclosure 1: -Radioactive Liquid Effluent'MonitoringL Instrumentation Enclosure 2: . Radioactive Gaseous Effluent Monitoring
- Instrumentation Enclosure 3: Liquid Ho'1d-Up Tank 5/1
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ENCLOSURE 1 Radioactive Liqb'1d Effluent Monitoring Instrumentation V
The liquid radwaste effluent flow measurement device (2-G16-FIT-N057) was inoperable- for greater than 30 days during this: time period. ,
This instrument was not returned to service within a 30 day.
Period due to the inability to calibrate the instrument within its design accuracy.
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i 4 ENCLOSURE 2 1
Radioactive Gaseous Effluent Monitoring Instrumentation p
Unit 1 & 2 Main Condenser Off-Gas treatment system explosive. gas monitors <1(2)-OG-AIT-4284 (SJAE.A.H2 Analyzer), 1(2)-OG-AIT-4285 (SJAE.A.H2 Analyzer), 1(2)-OG-AIT-4324 (SJAE.B.H2 Analyzer), and 1(2)-OG-AIT-4326 (SJAE.B.H2 Analyzer) were inoperable.for greater L than a'30 day period during January 1 to June 30, 1989. Due to design problems, *hese monitors were not' returned to service within 30 days.
Unit 2 Turbine' building roof vent monitor element 2-VA-FE-3358 and Unit 1 and 2 Reactor building roof vent monitor' element:
1(2)-VA-FE-3356 were inoperable for greater than a 30 day period during January 1 to June 30, 1989. Due to design problems Unit 2 Turbine ano Units l'and 2 Reactor building vent flow e
monitors were not returned to service within 30 days. However.,
all problems were resolved and these monitors were returned to service during this reporting period.
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ENCLOSURE'3.
Liquid Hold-Up Tank No liquid hold-up tank exceeded the 10 Ci limit during this timo
' period.
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ATTACHMENT.6 Major Modifications to the Radioactive Waste Treatment Systems January 1, to June 30', 1989 Discussion of major modifications to the Radioactive Waste Treatment.
Systems if any, will be submitted with the Final Safety Analysis Report update as allowed by footnote 7 to Technical Specification 6.15.
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ATTACHMENT 7 Meteorological Data Brunswick Steam Electric Plant January 1, to June 30, 1989 As per Technical Specification 6.9.1.10.a footnote 6, the annual summary of meteorological data collected over the calendar year will be submitted to a file and will be available for NRC review upon request.
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h ATTACHMENT 8 Potential Dose Assessment Brunswick Steam Electric Plant January 1, to June 30, 1989 As required by Technical Specification 6.9.1.10.b, an assessment of radiation doses-due to the radioactive liquid and gaseous effluents released during the calender year will be reported within'90 days after January 1 of each year, and is not included in this report.
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