BSEP-93-0130, Effluent Rept for Jan-June 1993

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Effluent Rept for Jan-June 1993
ML20056F942
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/30/1993
From: Hinnant C
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-93-0130, BSEP-93-130, NUDOCS 9309010058
Download: ML20056F942 (32)
v • d • e


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CP&L trr:tesEL"*Panmen:rrassarTcan Caro!!na Power & Ught Company r.h=ame==memass Brunswick Nuclear Plant l P.O. Box 10429 Southport, N. C. 28461-0249 AUG 2 51993 File: B09-13510C Serial: BSEP-93-0130 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk .

Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 l DOCKET NOS. 50-325 AND 50-324 i l LICENSE NOS. DPR-71 AND DPR-62 l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

l Gentlemen:

i Enclosed is the Semiannual Radioactive Effluent Release Report  :

for Brunswick Steam Electric Plant, covering the_ period from -

January 1, 1993 through June 30, 1993.

This report is submitted for the Brunswick Steam Electric Plant  ;

in accordance with Technical Specification 6.9.1.8.  ;

l Very truly yours, osHu. r C. S. Hinnant, Director Site Operations Enclosure l cc: Mr. S. D. Ebneter I i Mr. P. D. Milano l BSEP NRC Resid.ent Office  !

l 93090200ss 930630 #

hDR ADOCK 05000324 P@h}

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Brunswick Steam Electric Plant i i

Semiannual Radioactive Effluent Report f

January 1, to June 30, 1993 l

l j ATTACHMENTS: PAGES: l

1. Supplemental Information 2 - 6'
2. Effluent and Waste Disposal Data 7 -R20 [

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3. Environmental Monitoring Program 21 - 23 [

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4. Effluent Instrumentation 24 - 27 '
5. Major Modification to Radioactive Waste 28 f Treatment Systems j l
6. Meteorological Data 29 1
7. Annual Dose Assessment 30

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8. ODCM and PCP Revisions 31 i

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ATTACHMEN"' 1 Supplemental Information l i

January 1, to June 30, 1993- l l

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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information t

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- t lives greater than eight days (Technical Spec. 3.11.2.3)

  • (1) Calendar Quarter (a) 15 mrem to any organ j (2) Calendar Year l

I (a) 30 mrem to any organ j

  • (3) Calendar Quarter for Burning Contaminated Oil j (a) 436 uCi f (4) Calendar Year for Burning Contaminated Oil  !

(a) 872 uCi r

C. Liquid effluents (Technical Specification 3.11.1.2)  !

  • * (1) Calendar Quarter i (a) 3 mrem to total body j (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 (iODCM)
  • Used for percent of Technical Specification limit determinations in Table 1A.
    • Used f or percent of Technical Specification limit determinations in Table 2A.

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2. Maximum permissible concentrations and dose rates which j determine maximum instantaneous release rates.  !

i A. Fission and activation gases (Technical Specification l 3.11.2.1.a) i I

(1) 500 mrem / year to total body l (2) 3000 mrem / year to the skin j l

B. Iodine-131, iodine-133, tritium, and particulates with half- ,

lives greater than eight days (Technical Specification  :

3.11.2.1.b)

(1) 1500 mrem / year to any organ C. Liquid effluents (Technical Specification 3.11.1.1)

The concentration of radioactive material releared in liquid  :

effluents to unrestricted areas after dilution in the  !

discharge canal shall be limited to the concentrations l l specified in 10CFR20, Appendix B, for radionuclides other than noble gases. l'

  • * (1) Tritium: limit = 1 E-03 uCi/ml and h
  • * (2) Dissolved and entrained gases: limit = 2 E-04 uCi/ml [

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3. Measurements and Approximations of Total Radioactivity f f

A. Fission and activation gases  !

Analysis for specific radionuclides in representative grab samples by gamma spectroscopy.

B. Iodines f i

Analysis for specific radionuclides collected on charcoal  !

cartridges by gamma spectroscopy.

C. Particulates  ;

Analysis for specific radionuclides collected on filter '

papers by gamma spectroscopy.

l D. Particulates for Burning Oil j Analysis for specific radionuclides by grab samples of each  :

batch of oil to be burned.

E. Liquids Effluents Analysis for specific radionuclides of individual releases by gamma spectroscopy. ,

  • Used as applicable limits for Table 2A. ,

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Nuclear counting statistics are reported utilizing 1-sigma error. l Total error where reported represents a best effort to approximate  !

the total of all individual and sampling errors.  !

4. Batch Releases  ;

A. Liquid i (1) Number of batch releases: 2.29E+02  !

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(2) Total time period for batch releases: 2.40E+04 Minutes (3) Maximum time period for a batch release:

1.77E+02 i Minutes  ;

i (4) Average time period for a batch release: 1.05E+02 l Minutes (5) Minimum time period for a batch release: 8.00E+00 Minutes l l (6) Average stream flow during periods l of release of effluent into a flowing l stream : 5.44E+05 GPM B. Gaseous (1) Number of batch releases: 0.00E 00 i Minutes l; (2) Total time period for a batch release: 0.00E 00  ;

Minutes (3) Maximum time period for a batch release: 0.00E 00 i Minutes [

(4) Average time period for a batch release: 0.00E 00 l 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
  • There were no abnormal releases that exceeded 10CFR20 or 10CFR50 limits. See page 6 for a discussion of release events that occurred.

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l Discussion of Tritium in the Storm Drain Collection Pond I l

Approximately 3.12E+07 gallons containing 1.67 curies of tritium were released from the Storm Drain Collection l Pond (SDCP) to_the Intake Canal during this reporting l

period. The SDCP is a permitted release point.

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NOTE 1: Curie totals are included in the quarterly summaries in Table 2A and 2B. l l I l

l NOTE 2: The quantity of rainwater released from the Storm Drain Collection Basin and/or the Storm Drain Collection Pond is not included in VOLUME OF WASTE I on Table 2A. f i

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ATTACHMENT 2 j 1

Effluent and Waste Disposal Data j Brunswick Steam Electric Plant January 1, to June 30, 1993 i Enclosure 1 Table 1A: Gaseous Effluents - Summation of all Releases Table 1B: Gaseous Effluents - Elevated Releases Table 1C: Gaseous Effluents - Ground Level Releases-Table 1D: Gaseous Effluents - Ground Level Releases for -

Burning Contaminated Oil.

Table 2A: Liquid Effluents - Summation of all Releases l I

Table 2B: Liquid Effluents . Batch Mode j Appendix A: Lower Limits of Detection j l

( Table 3: Solid Waste and Irradiated Fuel Shipments j I

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Combustion of Waste Oil ,

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TABLE 1A Effluent and Waste Disposal Semiannual Report for Year 1993 j Gaseous Effluents - Summation of all Releases j Est. Tot.

Unit Otr 1 Otr 2 Error %

A. FISSION AND ACTIVATION GASES

1. Total release Ci < LLD 9.70E+01 4.50E+01
2. Average release uCi/sec < LLD 1.23E+01 rate for period
3. Percent of technical specification limit  % 0.00E+00 1.96E-02 B. IODINES
1. Total I-131 Ci < LLD B.27E-05 3.50E+01
2. Average release uCi/sec < LLD 1.05E-05 rate for period C. PARTICULATES NOTE 1
1. Total release Ci 4.36E-04 1.68E-03 3.50E+01
2. Average release uCi/sec 5.61E-05 2.14E-04 rate for period
3. Gross alpha Ci 1.02E-05 7.67E-06 D. Tritium
1. Total release Ci 1.08E-01 1.65E+00 3.00E+01 l 2. Average release uCi/sec 1.39E-02 2.10E-01 rate for period l E. IODINE-131, IODINE-133, TRITIUM AND PARTIC' LATES NOTE 1
1. Total Release Ci 1.09E-01 1.65E+DO
2. Average release uCi/sec 1.40E-02 2.10E-01 l rate for period I
3. Percent of technical l specification limit  % 8.33E-04 4.73E-03 i

t F. PARTICULATES VIA BURNING CONTAMINATED OIL

1. Total Release Ci 9.12E-07 2.14E-06
2. Average release rate for period uCi/sec 1.17E-07 2.72E-07
3. Percent of technical specification limit  % 2.09E-01 4.91E-01 NOTE 1: This includes the number of curies released via incineration.

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TABLE IB Effluent and Waste Disposal Semiannual Report for Year 1993 ,

j Gaseous Effluents - Elevated Releases i Continuous Release  :

Nuclides Released Unit Otr 1 Otr 2 l

1. FISSION GASES l

krypton-85m Ci <LLD 4.64E+00 l krypton-87 Ci <LLD 1.46E+01 l

krypton-88 Ci <LLD 1.09E+01 xenon-133 Ci <LLD 2.81E-01 l

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xenon-135m Ci <LLD 7.93E+00 xenon-135 Ci <LLD 2.14E+01 xenon-138 Ci <LLD 4.71E+00 total for period Ci <LLD 6.45E+01 ,

i l 2. IODINES iodine-131 Ci <LLD 8.27E-05 i iodine-133 Ci <LLD 5.08E-04 l total for period Ci <LLD 5.91E-04
3. PARTICULATES cobalt-60 Ci 3.33E-06 2.04E-06 strontium-89 Ci <LLD 2.24E-05 strontium-90 Ci <LLD 2.43E-07 cesium-137 Ci <LLD 1.54E-06 barium-140 Ci <LLD 1.83E-06 l total for period Ci 3.33E-06 2.81E-05  !

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4. TRITIUM hydrogen-3 Ci 5.14E-02 1.22E+00 I Page 9

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Effluent and Waste Disposal Semiannual Report for Year 1993 i Gaseous Effluents - Ground Level Releases Continuous Release i Nuclides Releas+ Unit Otr 1 Otr 2 i

1. FISSION GASES  !

xenon-133 Ci <LLD 4.04E+00  ;

xenon-135m Ci <LLD 3.64E+00  ;

xenon-135 Ci <LLD 2.50E+01 i total for period Ci (LLD 3.27E+01 [

2. IODINES ,

iodine-131 Ci <LLD 8.52E-08 iodine-133 Ci <LLD 9.08E-07 ,

total for period Ci <LLD 9.93E-07

3. PARTICULATES NOTE 1 manganese-54 Ci 4.38E-05 1.60E-04 cobalt-60 Ci 3.55E-04 1.49E-03 .

strontium-89 Ci <LLD 1.07E-06 strontium-90 Ci 4.28E-07 2.24E-07 cesium-137 Ci 2.48E-05 2.67E-07 r americium-241 Ci 8.56E-06 <LLD total for period Ci 4.33E-04 1.66E-03 i

4. TRITIUM hydrogen-3 Ci 5.69E-02 4.24E-01 I

NOTE 1: This includes the number of curies released via incineration.

TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1993 Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released Unit Otr 1 Qtr 2

1. PT,RTICULATES cobalc-60 Ci 7.12E-07 1.79E-06 manganese-54 Ci 8.33E-08 8.33E-08 cesium-137 Ci 1.17E-07 2.67E-07 total for period Ci 9.12E-07 2.14E-06 l

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i TABLE 2A Effluent and Waste Disposal Semiannual Report for Year 1993 Liquid Effluents - Summation of all Releases Unit Qt r 1 Otr 2 Est Tot I

% Error A. FISSION AND ACTIVATION  :

PRODUCTS NOTE 1 l 1. Total release (excluding Ci 9.90E-03 1.91E-02 4.00E 01 '

l tritium, gases, & alpha)

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2. Avg. diluted conc. uCi/ml 5.00E-10 6.45E-10: ,
3. Percent limit  % 2.58E-02 4.78E-02 B. TRITIUM NOTE 1 l t

l 1. Total release Ci 3.43E+00 5.80E+00 4.50E 01  !

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2. Avg. diluted conc. uCi/ml 1.73E-07 1.96E-07 ,

( 3. Percent limit  % 1.73E-02 1.96E-02 i

C. DISSOLVED AND ENTRAINED GASES NOTE 1

! 1. Total release Ci < LLD 1.50E-03 4.00E 01 l NOTE 2

2. Avg. diluted conc. uCi/ml < LLD 5.07E-11
3. Percent limit  % 0.00E+00 2.54E-05

! D. GROSS ALPHA RADIOACTIVITY

1. Total release Ci < LLD < LLD 4.00E 01

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! E. VOLUME OF WASTE NOTE 2 liters 5.92E+06 8.53E+06 1.50E 01 l r I I F. TOTAL OF DILUTION WATER  !

(used durina release for averaae dil. conc.) liters 1.98E+10 2.96E+10 1.30E 01 G. VOLUME OF COOLING WATER liters 2.42E+11 2.62E+11 DISCHARGED FROM PLATTT NOTE 1: includes radionuclides released via abnormal and/or nonroutine releases.

NOTE 2: Does not include rainwater released (ie. Storm Drain Collection Basin and/or Storm Drain Collection Pond )

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TABLE 2B Effluent and Waste Disposal Semiannual Report for Year 1993 Liquid Effluents - Batch Mode Nuclides Released Unit Otr 1 Otr 2  ;

1. FISSION AND ACTIVATION PRODUCTS  !

manganese-54 Ci 6.60E-04 3.68E-04 '

l iron-55 Ci 1.14E-03 < LLD cobalt-60 Ci 7.83E-03 1.81E-02 i niobium-95 Ci 4.73E-06 1.76E-06 '

cesium-134 Ci < LLD 1.11E-04 cesium-137 gi 2.69E-04 5.40E-04 ,

total for period Ci 9.90E-03 1.91E-02 >

2. DISSOLVED AND ENTRAINED GASES  !

xenon-133 Ci < LLD 2.03E-04 xenon-135 Ci < LLD 1.30E-03  :

total for period Ci < LLD 1.50E-03

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l APPENDIX A Lower Limits of Detection j l

January 1, to June 30, 1993 l i

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l l 1. Liauid Releases 2. Gaseous Releases l i l Fe-55 2.03E-07 Kr-85m 9.24E-09 ,

l Co-58 2.18E-08 Kr-87 2.26E-08 ,

l Fe-59 4.57E-08 Kr-88 3.31E-08 l

Zn-65 4.82E-08 Xe-133 2.88E-08  ;

Sr-89 3.33E-08 Xe-133m 6.20E-08 l Sr-90 6.54E-09 Xe-135 6.46E-09  :

Mo-99 1.82E-07 Xe-135m 1.57E-07 i I-131 2.49E-08 Xe-138 3.09E-07 i Cs-134 2.25E-08 l Ce-141 2.63E-08 3. Iodines and Particulates l Ce-144 1.37E-07  !

Alpha 1.74E-08 Co-58 4.45E-14 l Kr-87 3.85E-08 Fe-59 2.46E-15  !

Kr-88 6.38E-08 Zn-65 8.08E-14  !

i Xe-133 5.66E-08 Sr-89 4.58E-15  !

Xe-133m 1.46E-07 Sr-90 5 05E-15 i i Xe-135 1.52E-08 Mo-99 3.97E-13 l Xe-138 2.17E-07 I-131 6.48E-14 ,

I-133 9.69E-14 l Cs-134 5.07E-14 '!

Cs-137 7.36E-14 Ba-140 1.06E-13 l Ce-141 3.92E-14 i l Ce-144 2.25E-13. )

i Am-241 2.10E-13 'l

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NOTES 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. Also included are isotopes specified in Technical Specifications.

2: Where activity for any nuclide is reported as " Less than LLD", that nuclide is considered not present and the LLD activity listed is not considered in summary data.

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1 Table 3A Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments Waste Class A January throuch June

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1. Total volume shipped (cubic meters) 1.37 E2  !

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Total Curie quantity (estimated) 1.40 El

2. Tvoe of Waste Six-month Est. Total  !

Units Period  % Error .;

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a. Spent resins, filter sludges meters 8 5.89 E0 Curies 2.53 E0 1.00E1
b. Dry active waste, compacted meters3 1.31 E2  ;

noncompacted Curies 1.14 El 1.00E1  !

c. Irradiate 2 components meters3 0.00 EO  !

Curies 0.00 EO N/A l d. Others (oil) meters' O . 00 EO

! Curies 0.00 EO N/A '

l 3. Estimate of maior radionuclide comoosition l a. Cr-51 2.46 E0%

Mn-54 6.72 E0%

l Fe-55 4.60 El%

l Co-58 1.11 EO%

Co-60 3.73 El%

i Ni-63 1.19 E0%

Cs-137 2.49 E0% >

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l b. Mn-54 6.12 EO%

Fe-55 6.57 El% l l Co-58 3.17 E0% i l Co-60 2.19 El%

Ni-63 1.69 E0%

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c. N/A N/A
d. N/A N/A i

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I Table 3A (cont.) l Effluent and Waste Disposal Semiannual Report for Year 1993 J Solid Waste and Irradiated Fuel Shipments

4. Cross reference table, waste stream, form, and container tvoe, (

Stream Form Container tvoe No. of shioments I

a. Resin Dewatered & Type A/ Type B 1/0  !

Solidified *  ;

b. Dry active Compacted N/A 0 waste Noncompacted STP 43 l waste' l
c. Irradiated N/A 0 >

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d. Other N/A 0 i
  • solidification acent or absorbent I (e.g., cement, urea formaldehyde) N/A
5. Shioment Disposition
a. Solid Waste Number of Shioments Mode of Transoortation Destination  ;

44 Sole Use CNSI/Barnwell l SC 6

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i TABLE 3B Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments Waste Class B January throuch Jun

1. Total volume shioned (cubic meters) 0.00 E0 l l Total Curie quantity (estimated) 0.00 EO j i
2. Type of Waste Six-month Est. Total  :

Units Period  % Error  !

a. Spent resins, filter sludges meters 3 0.00 EO N/A Curies 0.00 EO  !
b. Dry active waste, compacted, meters) 0.00 EO N/A l and noncompacted Curies 0.00 E0
c. Irradiated conponents meters' O.00 EO N/A l l Curies 0.00 E0 l
d. Others (describe) meters' O.00 EO N/A i Curies 0.00 EO l 3. Estimate of maior radionuclide composition l a. N/A N/A t

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b. N/A N/A
c. N/A N/A
d. N/A N/A-
4. Cross reference table, waste stream, form and container type i

Stream Form Container tvoe No. of shipments i t

' a. Resin Dewatered & Type A/ Type B 0/0  ;

Solidified

b. Dry active Compacted /non- N/A 0 compacted  ;

waste  !

c. Irradiated N/A 0 . j components e
d. Other N/A 0  !
  • Solidification agent or absorbent l

(e.g., cement, urea formaldehyde)

N/A  !

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Table 3B (cont.)

Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments

5. Shipment Disposition
a. Solid Waste i Number of Shipments Mode of Transportation Destination 0 N/A N/A  ;
b. Irradiated Fuel ,

Number of Shipments Mode of Transportation Destination l 0 N/A N/A ,

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TABLE 3C '

Effluent and Waste Disposal Semiannual Report for Year 1993 Solid Waste and Irradiated Fuel Shipments i

Waste Class C January throuah June

1. Total volume shipped (cubic meters) 0.00 E0 l

Total Curie quantity (estimated) 0.00 E0

2. Tvoe of Waste Six-month Est. Tot.

Units Period  % Error

a. Spent resins, filter sludges meters) 0.00 EO N/A Curies 0.00 E0
b. Dry active waste, compacted meters' O.00 EO N/A and noncompacted Curies 0.00 E0 ,
c. Irradiated components meters 3 0.00 EO N/A -

Curies 0.00 E0

d. Others (describe) meters) 0.00 E0 N/A  ;

j Curies 0.00 EO

3. Estimate of maior radionuclide composition
a. N/A N/A-
b. N/A N/A l

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l 4. Cross reference table, waste stream, form and container tvoe Stream Form Container Tvoe No. of shioments

a. Resin Dewatered & Type A/ Type B 0/0 l Solidified *

! b. Dry active Compacted /non- N/A 0 waste compacted

c. Irradiated Non Compacted N/A 0 components Waste Equipment Solid / Oxides
d. Others N/A 0
  • Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A Page 18 I
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Table 3C (cont.)

Effluent and Waste Disposal Semiannual Report for Year 1993  !

Solid Waste and Irradiated Fuel Shipments

5. Shipment Disposition  !
a. Solid Waste ,

Number of Shipments Mode of Transportation Destination i 0 N/A N/A l

b. Irradiated Fuel (non-burial) l Number of Shipments Mode of Transportation Destination 2 Rail Car CP&L/SHNPP IF-300 Cask.

Sole Use ,

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ATTACHMENT 2 (Cont.)

ENCLOSURE ?

Combustion of Waste Oil January 1, to June 30, 1993  ;

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During this reporting period approximately 673 gallons of l l contaminated waste oil was incinerated in the on-site incinerator.

The total activity contained in this quantity of waste oil included _

l 2.51E-06 curies of Co-60, 3.84E-07 curies of Cs-137 and 1.67E-07

  • i curies of Mn-54. i t

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ATTACHMENT 3 Environmental Monitoring Program January 1, to June 30,-1993 i

Enclosure 1: Milk and Vegetable Sample Locations l Enclosure 2: Land Use Census k

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i l ATTACHMENT 3 (Cont.)

1 ENCLOSURE 1 Milk and Vegetation Sample Locations January 1, to June 30, 1993 Nc milk sample locations were available during this time period.

l l Vegetation sample locations remained unchanged.

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j ATTACHMENT 3 (Cont.)

ENCLOSURE 2  ;

Land Use Census l l

January 1, to June 30,,1993 l i

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The 1993 Land Use Census was performed during the period June 9,-

1993 through June 10, 1993. No locations were identified that are j f

-reportable in the Semiannual Radioactive Effluent ReleasefReport.  ;

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ATTACHMENT 4 .

Effluent Instrumentation January 1, to June 30, 1993 t

Enclosure 1: Radioactive Liquid Effluent Monitoring.  !

Instrumentation. ,

i Enclosure 2: Radioactive Gaseous Effluent Monitoring Enclosure 3: Liquid Hold-Up Tank I t

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ENCLOSURE 1 i

Radioactive Liquid Effluent Monitoring Instrumentation j l

January 1, to June 30, 1993 j No Radioactive Liquid Effluent Monitoring Instrumentation was f inoperable for greater than 30 days.

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ATTACHMENT 4 (Cont.) '

ENCLOSURE 2 l Radioactive Gaseous Effluent Monitoring Instrumentation  !

i January 1, to June 30, 1993 I r

i Unit 1 Main Condenser Off-Gas treatment system explosive gas l monitors 1-OG-AIT-4284 (SJAE.A.H 2 Analyzer) , 1-OG-AIT-4285 (SJAE.A.H2 Analyzer), 1-OG-AIT-4324 (SJAE.B.H 2Analyzer) , and 1-OG- l i

i AIT-4325 (SJAE.B.H2 Analyzer) were inoperable for greater than 30  ;

i days. However, Unit 1 was shutdown during the entire report period

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and the monitors were not required to be operable. Testing for l instrument operability requires the unit to be at power.

The Unit 2 Main Condenser Off-Gas Treatment System Explosive Gas  ;

Monitors were returned to service within 30 days following startup  !

of Unit 2. ,

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ATTACHMENT 4 (Cont.) i ENCLOSURE 3 t

Liquid Hold-Up Tank j January 1, to June 30, 1993 l r

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No liquid hold-up tank exceeded the 10 Ci limit during this l I

t reporting period.

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O ATTACHMENT 5 Major Modifications to the Radioactive Waste Treatment System January 1, to June 30, 1993 I

As per footnote 7 to Technical Specification 6.15, a discussion of any major modifications to the radioactive waste treatment ,

systems will be submitted with the Final Safety Analysis Report update.

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ATTACHMENT 6  ;

i Meteorological Data January 1, to: June ' 3 0, 1993 j s

As per Technical Specification 6.9.1.10.a footnote 6, the annual l

summary of meteorological data collected over the calendar year. j will be submitted to a file and will be available for NRC review-i upon request.

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ATTACHMENT 7 l l

Annual Dose Assessment  !

January 1, to June 30, 1993 l i

f 1

As per Technical Specification 6.9.1.10.b, an assessment of (

l i j radiation doses due to the radioactive liquid and gaseous effluents j l released during the calendar year will be reported.within 90 days t

after January 1 of each year. The annual dose assessment is not j t

included with this report. l I

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I ATTACHMENT 8 l i

i Off-Site Dose Calculation Manual (ODCM) and i e

i Process Control Program (PCP) Revisions _

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January 1, to June 30, 1993 i

Brunswick Steam Electric Plant j 1

I There were no revisions made to the Process Control Program during  !

I this reporting period. l There were no revisions made to the Off-Site Dose Calculation ,

l Manual during this reporting period.

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