ML20059B902

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Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML20059B902
Person / Time
Site: Brunswick  
Issue date: 06/30/1990
From: Harness J
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-90-570, NUDOCS 9008300157
Download: ML20059B902 (33)
v • d • e


Text

,

o Carolina Pove 7 & Light Company N

Brunswick Nuclear Project P. O. Box 10429 Southport, N.C.

28461 0429 August 23, 1990 FILE:

B09-135100 SERIAL:

BSEP/90 570 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk.

Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PIANT UNITS 1 AND 2 DOCKET NOS. 50 325 AND 50 324 LICENSE NOS. DPR.71 AND DPR-62 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

?

Gentlemen:

Enclosed is the Semiannual Radioactive Effluent Release Report for Brunswick Steam Electric Plant, covering the period from January 1,1990, through June 30,

1990, This report is submitted for the Brunswick Steam Electric Plant in accordance with Technical Specification 6.9.1.8.

Very truly yours, 3

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J. L. Ilarness, General Manager Brunswick Nuclear Project JD/th Enclosure cc:

Mr. S. D. Ebneter Mr. N. B. Le BSEP NRC Resident Office

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Brunswick Steam Electric Plant Semiannual Radioacti'Je Effluent Report January 1, to June 30, 1990 ATTACHMENTS:

PAGES:

1.

Supplemental Information 2-5 2.

Effluent and Waste Disposal Data 6 - 19 i

3. ODCM and PCP Revisions 20 nvironmental Monitoring Program 21 - 23 4.

r 5.

Effluent Instrumentation 24 - 27

6. Major Modification to Radioactive Waste 28 Treatment Systems
7. Meteorological Data 29
8. Annual Dose Assessment 30
9. Supplement to Previous Semiannual Report 31 - 32 i

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-.1 Page 2 ATTACHMENT 1 Supplemental Information January 1, to June 30, 1990 i

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EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT l

Supplemental Information Facility:

Brunswick Steam Electric Plant i

Licensee Carolina Power and Light Company

1. Regulatory Limits A.

Fission and activation gases (Technical Spec. 3.11.2.2) l

  • (1) Calendar Quarter (a) 10 mrad gamma (b) 20 mrad' beta (2) Calendar Year (a) 20 mrad gamma 3

(b) 40 mrad beta l

B. Jodine-131, iodine-133, tritium, and particulates 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 mrom to any organ (3) Calendar Quarter for Burning Contaminated Oil (a) 436 PCi I-(4) Calendar Year for Burning Contaminated Oil (a) 872'dCi C.-Liquid effluento (Technical Specification 3.11.1.2)
    • (1) Calendar Quarter (a)- 3 mrom to total body (b) 10 mrem to any organ i

(2) Calendar Year I

(a) 6 mrem 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 determinations L

in Table 2A.

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2. Maximum permissible concentrations and dose rates which determine maxir'am 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 particulates with half-lives greater than eight days (Technical Specification 3.11.2.1.b)

(1) 1500 mrem / year to any organ i

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 rndionuclides other than noble gases.

    • (1) Tritium:

MPC = 3 E-03 uCi/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 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.

Particulates for Burning Oil Analysis for specific radionuclides by grab samples of each batch of oil to be burned.

E.

Liquids Effluents l

l Analysis for specific radionuclides of individual releases by gamma spectroscopy.

    • Used as applicable limits for Table 2A

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i Page 5 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.

1 4.

Batch Releases A. Liquid (1) Number of batch releases:

8.60E+01 (2) Total time period for batch releases:

9.00E+03 Minutes (3) Maximum time period for a batch release:

1.57E+02 Minutes (4) Average time period for a batch release:

1.05E+02 Minutes (5) Minimum time period for a batch release:

1.40E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream :

6.56E+05 GPM B. Gaseous (1) Number of batch 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 1

Minutes j

(4) Average time period for a batch release:

0.00E 00 Minutes j

(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

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i Page 6 ATTAtHT.eC I

Ef fluent und '

posal Data Brunswice; oceam Electric Plant January 1, to June 30, 1990

)

i Encl',ure 1 Table 1At Gaseous Effluents - Summation of all Releases Table 1Bt Gascous Effluents - Elevated Releases Table 1C:

Gaseous Effluents - Ground Level Releases Table 2At Liquid Effluents - Summation of all Releases Table 3Bt Liquid Effluents Lower Limits of Detection Table 31 Solid Waste and Irradiated Fuel Shipments Combustion of Waste Oil

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t Page 7 TABLE 1A Effluent and Waste Disposal Semiannual Report for Year 1990 1

Gapsous Effluents - Summation of all Releases Est. Tot.

Unit Otr 1 Otr 2 Error %

A.

FISSION AND ACTIVATIQH GASES

1. Total release ci 2.45E+02 2.89E+02 1.15E 02
2. Average release uCi/sec 3.15E+01 3.68E+01 rate for period 3.

Percent of technical specification limit 7.50E-02 5.80E-02 B.

IODINES

1. Total I-131 C1 1.63E-03 2.07E-03 7.00E 01
2. Average release uCi/sec 2.09E-04 2.63E-04 rate for period C.

PARTICULATES I

1. Total release Ci 1.25E-03 2.85E-03 7.00E 01
2. Average release uCi/sec 1.61E-04 3.63E-04 rate for period
3. Gross alpha C1 1.82E-06 3.24E-06 D. Tritium
1. Total release Ci 7.81E-01 5.83E+00 7.00E 01
2. Average release uCi/sec 1.00E-01 7.42E-01 l

rate for period E. IODINE-131. IODINE-133. TRITIUM AND PARTICULATES

1. Total Release Ci 7.93E-01 5.85E+00
2. Average release uCi/sec 1.02E-01 7.44E-01 rate for period 3.

Percent of technical L

specification limit 6.00E-02 8.00E-02 F.

PARTICULATES VIA BURNING CONTAMINATED OIL

1. Total Release Ci 0.00E+00 0.00E+00
2. Average release rate for period uCi/sec 0.00E+00 0.00E+00 3.

Percent of technical specification limit 0.00E+00 0.00E*00

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Page 8 TABLE IB Effluent and Waste Disposal Semiannual Report for Year 1990 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 1 Otr 2

1. FISSON GASEE argon-41 Ci 4.01E+00 3.91E+00

'1 krypton-85m Ci

<LLD 7.27E-01 krypton-87 C1 1.38E+00 7.81E-01 xenon-133 Ci 3.32E+00 4.04E+00 xenon-135m C1 2.14E+01 1.79E*01 xenon-135 Ci 1.91E+01 1.27E,J1 xenon-137 Ci 5.87E+01 8.62E+01 Kgnon-138 Ci 4.08E+01 3.44E+01 total for period C1 1.49E+02 1.61E+02 2.

IODINES iodine-131 C1 1.40E-03 1.72E-03 iodine-132 Ci 3.86E-03 6.24E-03 iodine-133 Ci 7.20E-03 1.08E-02 iodine-135 gi 8.96E-03 1.25E-02 total for period Ci 2.14E-02 3.13E-02 3.

PARTICULATES chromium-51 Ci

<LLD 4.26E-05 manganese-54 Ci 2.33E-05 9.70E-06 cobalt-58 Ci

<LLD 4.47E-06 cobalt-60 Ci 5.15E-05 2.97E-05 strontium-89 C1 1.52E-04~

2.45E-04 strontium-90 Ci 5.90E-07 1.15E-06 cesium-137 Ci 1.54E-05 1.10E-05 barium-140 Ci 1.12E-04 3.15E-04 lanthanum-140 Ci 7.41E-05 2.28E-04 hafnium-181 C1 1.13E-07

<LLD total for_ period C1 4.29E-04 8.87E-04 I

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4. TRITIUM l

hydrogen-3 Ci 4.95E-01 3.56E+00 l-

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.o Page 9 TABLE 1C Effluent and Waste Disposal Semiannual Report for Year 1990 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Otr 1 QtI,_2 1.. FISSION GAEEE xenon-133 Ci 7.46E+00 7.88E+01 xenon-135m Ci 1.59E+01 3.14E+01 xenon-135 Qi 7.23E+01 1.73E+Q1 total for period Ci 9.57E+01 1.28E+02

2. IODINES lodine-131 Ci 2.27E-04 3.47E-04 iodine-132 Ci 9.79E-04 2.27E-03 iodine-133 Ci 1.88E-03 2.92E-03 H

iodine-134 Ci

<LLD-3.20E-04 lodine-135 Ci 7.00E-04 2.45E-03 total for period Ci 3.79E-03 8.31E-03 3.

PARTICULATES chromium-51 Ci 8.57E-05 1.57E-03 maganese-54 Ci 3.49E-04 1.14E-04 cobalt-58 C1 1.06E-04 5.60E-05 cobalt-60 Ci 2.68E-04 2.06E-04 strontium-89 C1 1.60E-06 3.75E-06 strontium-90 C1 1.86E-07 3.06E-07 cesium-137 Qi 8.18E-06 8.51E-06 i

total for period Ci 8.19E-04 1.96E-03 l

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TRITIUM hydrogen-3 Ci 2.86E-01 2.27E+00 i

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A Page 10 TABLE 2A

~ Effluent and Waste Disposal Semiannual Report for. Year-1990 j

Liquid Effluents - Summation of all Releases i

Unit Otr 1 Otr 2 Est Tot.

% Error A. EISSION AND ACTIVATION PRODUCTS

1. Total release (excluding:

Ci 1.23E-01 2.45E-02 3.50E 01 j

j tritium, gases, & alpha) i

2. Avg. diluted conc.

uCi/ml 7.94E-09 3.57E-09 3.

Percent limit 1.87E-01 1.98E-02.

1 B. TRITIUM

1. Total. release Ci 1.95E+00

-6.99E+00 4.00E 00 i.

2. Avg. diluted conc.

uCi/ml 1.26E-07 1.02E-06 l

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L-3.

Percent limit-4.20E-03 3.40E-02 il L

C.

DISSOLVED AND ENTRAINED GASES L

1. Total release-Ci 9.35E-02 4.02E-02~ 3.50E 01 p

L

2. Avg. diluted conc.

uC1/ml

6. 0.s E

'9 5.86E-09 l

3.

Percent limit 3.'

E-03 2c ^3E-03 f

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D. GRQSS ALPHA RADIOACTIVITY h

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1. Total release Ci

_LD 4.00E 01 E. VOLUME OF WASTE liters 4.53E+0e 1.84E+0i 1.25E 01 F. TOTAL'OF DILUTION WATER (used durina release for averace dil. conc.)

liters 1.55E+'0 6.86E+09 1.30E 01 i

G. VOLUME OF COOLING WATER liters 3.10E+11 3.96E+11 q

DISCHARGED FROM PLANT

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Page 11 TABLE 2B

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Effluent and Waste Disposal Semiannual Report for Year 1990 Liquid Effluents - Batch Mode i

Nuclides Released Unit Otr 1 Qttl

'{

1.

FISSION AND ACTIVATION PRODUCTS sodium-24 Ci Jed6E-03

<LLD i

chromium-51 C1

1. 74E-02

?.67E [

manganese-54 Ci 2.15E-02 2.0&E-03' iron-55 Ci

<LLD 7.35B-04 cobalt-57 C1 1.27E-05

<LLD i

-cobalt-58 Ci 6.29E-03 1.56E-04 iron-59 Ci 6.19E-05

<LLD i

cobalt-60 C1 4.10E-02 7.00E-03 arsenic-76 Ci 5.00E-05

<LLD strontium-90 Ci 3.44E-05

<LLD yttrium-91m Ci 3.18E-04 6.34E-04 yttrium-92 Ci 5.01E-03 8.26E-03 yttrium Ci

<LLD 2.59E-04 strontium-92 Ci 2.94E-05 1.14E-05 technetium-99m C1 1.83E-04 4.13E-04 1

technetium-101 Ci

<LLD-3.48E-05 technetium-104 Ci 9.12E-05 2.57E-05 ruthenium-103 Ci 8.70E-06

<LLD l

ruthenium-105 Ci 2.35E-04 9.31E-04 antimony-125 C1 1.15E-04

<LLD iodine-131 Ci 5.60E-04

<LLD tellurium-132 Ci 3.01E-04

<LLD ti iodine-132 C1 2.61E-05

<LLD iodine-133 Ci 2.31E-03 1.63E-05 lodine-134 Ci

<LLD 3.29E-05 cesium-134 Ci 8.37E-03 1.03E-04 iodine-135 Ci 4.74E-04

<LLD cesium-137 C1 1.43E-02 4.83E-04 lanthanum-140 C1 1.69E-04 2.27E-04 lanthanium-141 Ci

<LLD 1.01E-03 lanthanum-142 Ci' 1.12E 4.65E-04 Dgotunium-239 Q1 2.33E-03

<LLD o

total for period C1 1.23E-01 2.45E-02 2.

CASES

-xenon-133 C1 1.38E-02 4.14E-03 xenon-133m C1 1.23E-04

<LLD xenon-135m Ci 4.32E-04 4.67E-05 xenon-135 Gi 7.91E-02 3.60E-02 total for period Ci 9.35E-02 4.02E-02

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.i Page 12 Lower Limits of Detection January through June 1990 uCi/ml

1. Licuid Releases
2. Gaseous Releases Na-24 2.19E-08.

Kr-85m-7.24E-09 Co-57 1.11E-08 Sr-90 3.01E-09 Fe-59 1.81E-08 As-76 4.43E-08 Y-93 1.88E-07 3.

Iodines and Particulates I-134 2.89E-08 Tc-101

-5.48E-08 Ru-103 1.51E-08 Cr-51 3.08E-13 Sb-125 4.08E-08 Co-58 2.38E-14 I-132 2'.58E-08 Hf-181 3.95E-14 V2 I-131 1.27E-08 I-134 T

Too short Alpha 3.01E-08 Fe-55 1.39E-07 Te-132 1.38E-08 I-135 7.36E-08 Np-239 8.91E-08 La-141 8.90E-07 Xe-133m 1.00E-07 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.

2:

Where activity for any nuclide is reported as " Less than 4E LLD", that nuclide is-considered not present and the LLD' activity listed is not considered in summary data.

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Page 13 Table 3A Effluent and Waste Disposal Semiannual Report for Year-1990' Solid Waste and Irradiated Fuel Shipments i-Waste Class A January throuch June d.

1. Total volume shicoed (cubic meters) 3.17 E2 l

Total. Curie quantity (estimated) 7.34 E2 6

2. Tvoe of Waste Six-month Est. Total Units Period 3 Error-3
a. Spent resins, filter sludges meters 6.88 El Curies 7.05 E2 1.00E1 3

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b. Dry active waste, compacted meters 2.49 E2 noncompacted Curies 2.88 El 1.00E1 3
c. Irradiated' components meters 0.00 E0 Curies 0.00 EO N/A 3
d. Others (oil) meters 0.00 E0 t

Curies 0.00 EO N/A 3.' Estimate of maior radionuclide composition a.

Ni-63 1.84 EO%

Mn-54 7.57 EO%-

Fe-55 5.84 El%

Co-58 7.78 EO%

l Co-60 2.01 El%

L Cs-134 1.06 E0%

Cs-137 2.19 EO%_

b.

Mn 6.09 E0%

Fe-55 8.24 El%

l Co-60 1.07.El%

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c.

N/A N/A r

a

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.d.

N/A N/A l

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Page 14 Table 3A (cont.)

Effluent and Waste Disposal Semiannual Report for Year 1990' Solid Waste and Irradiated Fuel Shipments

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

Stream Form Montainer tvoe No. of shioments a.

Resin Dewatered &

Type A/ Type B 13/1 Solidified

  • b.

Dry active Compacted /non-STP 18 waste compacted waste c.

Irradiated N/A 0

components

'd.

Other N/A 0

  • solidification agent or absorbent (e.g., cement, urea formaldehyde)

NONE-5.

Shloment Disoosition

a. Solid Waste-Number of Shioments Mode of Transoortation Destination 32 Sole Use CNSI/Barnwell SC
b. Irradiated Components Number of Shioments Mode of Transoortation Destination-0 N/A N/A

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l Page 15 TABLE.3B Effluent.and Waste Disposal Semiannual Report ~for Year 1990 Solid Waste and Irradiated Fuel Shipments i.

i Waste Class B January throuah June

1. Total volume shioned (cubic meters)-

0.00 EO Total Curie quantity (estimated) 0.00 EO

2. Tvoe of Waste Six-month Est. Total Units Period

% Error

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a. Spent resins, filter sludges meters 0.00 EO N/A Curies 0.00 EO-3
b. Dry active waste, compacted, meters 0.00 EO N/A and'noncompacted-Curies 0.00 EO i

3

c. Irradiated components meters 0.00 EO N/A Curies
0. 00 EO, 3
d. Others (describe).

meters 0.00 EO N/A~

Curies 0.00 EO 7

3.

Estimate of maior radionuclide comoosition a.

N/A N/A l

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b.

N/A N/A c.

N/A N/A d.

N/A N/Af

'4.

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

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

components

d. Other N/A 0
  • Solidification agent or absorbent (e.g., cement, urea formaldehyde)

NONE

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' Table 3B (cont.)

Effluent'and Waste Disposal Semiannual Report for Year 1990 Solid Waste and Irradiated Fuel Shipments 5.Shioment Disoosition-

a. Solid Waste Number of Shipments Mode of Transoortation Destination.

O N/A N/A b.

Irradiated Fuel Number of Shioments Mode of Transoortation Destination O

N/A N/A i

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Page 17 TABLE 3C Effluent and Waste Disposal Semiannual Report for Year-1990 l

Solid Waste and Irradiated Puel Shipments.

Waste Class C January throuch June

1. Total volume shioned (cubic meters) 0.00-E0 Total Curie quantity (estimated) 0.00 EO
2. Tvoe of Waste Six-month Est. Tot.

Units Period

% Error.

3

a. Spent resins, filter sludges meters 0.00 EO

.N/A Curies 0.00 EO-3

b. Dry active waste, compacted meters 0.00 EO JN/A and noncompacted Curies 0.00 EO 3
c. Irradiated components meters 0.00 EO N/A Curies 0.00 E0 3
d. Others (describe) meters 0.00 EO N/A Curies 0.00 EO

'3.. Estimate of maior radionuclide comoosition a '.

N/A N/A b.

N/A N/A 7.

N/A N/A L

I d.

N/A N/A

4. Cross reference table, waste.gtream. form and container type Stream Form Container Tvoe No. of shioments L

i L

a. Resin-Dewatered &

N/A 0/0 Solidified

  • l
b. Dry active Compacted /non-N/A 0

i.

L waste compacted a

c. Irradiated Type B 0

components

d. Others N/A 0
  • Solidification agent or absorbent (e.g., coment, urea formaldehyde)

NONE b

s-1 a

Page 18

.TableL3C (cont.)

-Effluent and Waste Disposal ~ Semiannual Report.for Year 1990' Solid Waste and Irradiated Fuel' Shipments i

. 5. Shioment Disoosition

.a.

Solid Waste Number of Shioments Mode'of Transoortation Destination O

N/A N/A

b. Irradiated Fuel (non-burial)

Number of Shioments Mode of Transoortation Destination 3

sole use/ Rail CP&L/SHNPP i

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ENCLOSURE 2 Combustion of Waste Oil January 1, to June 30, 1990 t

Thnre was no incineration of-contaminated waste oil during

.7 this reporting period.

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-I ATTACHMENT 3 1

Off-Site Dose Calculation Manual (ODCM) and

' Process Control Program (PCP) Revisions January 1, to June'30, 1990 Brunswick Steam Electric Plant' There were no revisions made to the Process Control Program during this reporting period.

e There were.no revisions made to the Off-Site Dose Calculational Manual during this reporting period.

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.Page.21:

ATTACHMENT 4 Environmental. Monitoring Program l

January 1,~to June-30,-1990 :

Milk and Vegetable Sample Locations Enclosure'2:

Land Use Census

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Page<22 ENCIDSURE 1-Milk and Vegetable Sample Locations January 1, to June 30 1990 No milk sample locations were available during this. time period.

Vegetable sample locations remained' unchanged.

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t Page 23 ENCLOSURE 2 Land Use Census January 1, to June-30,.1990 The results of the 1990 Land Use C,nsus will be reported inlthe

= July 1, to December 31, 1990'Semianrual Report.

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.i ATTACHMENT 5 Effluent Instrumentation i

January 1, to-June 30, 1990 Radioactive Liquid Effluent Monitoring

'i Instrumentation.

Radioactive Gaseous Effluent Monitoring Liquid Hold-Up Tank i

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Page 25-ENCLOSURE 1 January 1, to June 30, 1990 Radioactive Liquid Effluent Monitoring Instrumentation The liquid radwaste effluent flow measurement device (2-G16-FIT-N057) was inoperable for greater than 30 days during this period.

The 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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f Page 26 ENCLOSURE 2

-January 1, to June 30, 1990 Radioactive Gaseous. Effluent Monitoring Instrumentation 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.H Analyzer), 1(2)-OG-AIT-4324-(SJAE.B.H Analyzer), and 2

2 1(2)-OG-AIT-4325 (SJAE.B.H Analyzer) were inoperable for greater 2

than a 30 day period during January 1 to June 30, 1990.

Due_to design problems, these monitors were not returned to service within 30 days.

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Liquid' Hold-Up Tank January 1, to June 30, 1990-No liquid hold-up tank exceeded the 10 ci limit during this reporting ' period.

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ATTACHMENT 6 Major Modificatione to the Radioactive Waste Treatment-System January 1,'to June 30, 1990-1 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

'i update.

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'l Page 29 ATTACHMENT 7 Meteorological Data January 1, to June 30, 1990

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

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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Page 30 ATTACHMENT 8 Annual-Dose Assessment January 1, to June 30, 1990 As per, Technical Specification 6.9.1.10.b, an. assessment of' radiation 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.

The annual dose assessment is not included with this report.

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l Page 31; ATTACHMENT 9 SUPPLEMENT TO PREVIOUS SEMIANNUAL REPORT BRUNSWICK STEAM ELECTRIC PLANT j

'l January 1, to June 30, 1990-The attached sheet should be added to the July 1, to December 31, 1989-Semiannual Report (1989 second report)..

This information, l

concerning inoperable radioactive gasecus effluent monitoring f

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instrumentation, was inadvertently ommitted, f

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Please replace page 5/3 of - the July 1,

to December 31, 1989 j

Semiannual-Environmental and Radioactive Effluent Release Report j

with the. attached page 5/3.

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1 Page 32-ENCIDSURE 2

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July 1, to December 31, 1989 r

Radioactive Gaseous Effluent Monitoring Inctrumentation-

' Unit 1

& 2 Main Condenser Off-Gas treatment system explosive gas monitors 1(2)-OG-AIT-4284 '(SJAE. A.H Analyzer), 1(2)-OG-AIT-4285 i

2 (SJAE.A.H2 Analyzer), 1(2)-OG-AIT-4324 (SJAE.B.H2 Analyzer), and 1(2)-OG-AIT-4325 (SJAE.B.H2 Analyzer) were inoperable for greater l-than a 30 day period during July 1 to December 31, 1989.

Due to i

design problems, these monitors were not returned to service within 30 days.

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