ML20153G276

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Semiannual Radioactive Effluent Rept for Jan-June 1988
ML20153G276
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/30/1988
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20153G130 List:
References
NUDOCS 8809080100
Download: ML20153G276 (31)
v • d • e


Text

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Brunswick Steam Electric Plant Semiannual Radioactive Effluent Report January 1.

1988 to June 30 1988 ATTACHMEt4TS:

PAGES:

1. Supplemental Information 1/1 to 1/4 2.

Effluent and Waste Disposal Data 2/1 to 2/14

3. ODCH and PCP Hevisions 3/1 4.

Enviromental Monitoring Program 4/1 to 4/3 S.

Inoperable Effluent Instrumentation S/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

9. Supplement to Previous Semiannual 9/1 to 9/3 Report i

l 8809080100 880826 i

](([Lfhij(i PDR ADOCK 05000324 R

PDC

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ATTACHMENT 1 Supplemental Information January 1, to June 30, 1988 i

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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 l

A.

Fission and activation gases (Technical Spec. 3.11.2.2) 1 t

  • (1) Calendar Quarter l

(a) 10 mrad gamma f

I (b) 20 mrad beta (2) Calendar Year (a) 20 mrad gamma (b) 40 mrad beta l

B.

Iodine-131, iodine-133, tritium, and particulates with half-r lives greater than eight days (Technical Spec. 3.11.2.3)

  • (1) Calendar Quarter (a) 15 mrem to any organ e

(2) Calendar Year i

(a) 30 mrem to any organ C.

Liquid effluents (Technical Specification 3.11.1.2)

    • (1) Calendar Quarter f

i (a) 3 mrem to total body (b) 10 mrem to any organ f

(2) Calendar Year (a) 6 arem to total body (b) 20 mrem to any organ NOTE:

Dose calculations are determined in accorcance 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

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2. Maximum permissible concentrations and dose rates which determine 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 I

B.

Iodine-131, iodine-133, tritium, and particulates with half-l lives greater than eight days (Technical specification 3.11.2.1.b) 1 (1) 1500 mrem / year to any organ 1

C. Liquid ef fluents (Technical Specification 3.11.1.1) l The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution in the dischaege canal shall be limited to the concentrations specified in 10CFR20, Appendix B.

Table II, column 2 for radionuclides l

other than noble gases.

    • (1) Tritium:

MPC = 3 E-03 uC1/ml and

    • (2) Dissolved and entrained gases:

HPC = 2 E-04 uCi/ml

3. Measurements and Approximations of Total Radioactivity l

A.

Fission and activation gases Analysis for specific radionuclides in representative grab samples by gamma spectroscopy.

D.

Iodines Analysis for specific radionuclides collected on charcoal I

cartridges by gamma spectroscopy.

C.

Particulates 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

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Nuclear counting statistics are reported utilizing 1-sigma error.

Total error where reported represants a

best effort to approximate the total of all individual and sampling errors.

4.

Batch Releases A.

Liquid (1) Number releases:

3.06E 02 (2) Total t.

vd for batch releases:

3.31E 04 Minutes (3) Maximum 'cime period for a batch release:

2.45E 02 Minutes (4) Average time period for a batch release:

1.08E 02 Minutes (5) Minimum time period for a batch release:

6.00E 00 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream :

6.49E 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 Minutes (4) Average time period for a batch release:

0.00E 00 i

Minutes (5) Minimum cime pe'/iod for a batch release:

0.00E VO Minut'a 5.

Abnormal releases A.

Liquid (1) Number of releases:

0.00E 00 (2) Total activity released:

0.00E 00 Curies B.

Oaseous j

(1) Number of raiemses:

0.00E 00 (2) Total activity released:

0.00E 00 Curies 1/4 l

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ATTACHMENT 2 l

Effluent and. Waste Disposal' Data l.

l Brunswick Steam Electric Plant

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January 1, 1988 to June 30, 1988 1

Table 1A:

Gaseous Effluents - Summation of all Releases Table 18:

Gaseous Effluents - Elevated Releases Table 1C:

Gaseous Effluents - Ground Level Releases Table 2A:

Liquid Effluents - Summation of all Releases Table 28:

Liquid Effluents Lower Limits of Letection Table 3:

Solid Waste and Irradiated Fuel Shipments Combustion of Waste Oil 2/1

Table.1A Effluent and Waste Disposal Semiannual Report Year.1988 Gaseous' Effluents - Sumnation of all Releases Est.

Total Unil Otr 1 Otr 2' Error.%

A.

Fission and Activation Gases 1,

Total release C1 2.01E 02 2.26E 02 1.15E 02 2.

Average release UCi/sec 2.56E 01 2.87E.01 rate for period 3.

Percent of techriical specification limit

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4.e8E-02 5.58E-02 B.

Iodines 1.

Total I-131 C1 1.90E-03 1.67E-03 7.00E 01

2. Average release uC1/sec 2.42E-04 2.12E-04 rate for period C.

Particulates 1.

Total release C1 1.08E-02 6.95E-02 7.00E 01 2.

Average release uC1/sec 1.37E-03 8.84E-03 4

rate for period

3. Gross alpha Ci 5.27E-06 4.80E-06 D.

Tritium 1.

Total release C1 1.04E 00 1.24E 00 7.00E 01 2.

Average release UC1/sec 1.32E-01 1.57E-01 rate for period E.

IAd_1ae _131.

Ig,d_1ne-133. ~(r_1 t_iu_m.

a_qd_ P_a r t i c u l a tqs.

1.

Total Release C1 1.06E 00 1.32E 00 l

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Avera<e release uC1/sec 1.34E-01 1.68E-01 I

I rate f.':

ceriod 3.

Percent of technical specification limit

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7.27E-02 6.93E-02 2/2 1

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Table AB Effluent and Waste Disposal Semiannual Report

. Year 1988 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 1 Otr 2 1.

Fission Gases argon-41 C1 4.72E-01 8.64E-01 krypton-85m C1 5.45E 00 1.52E 01 krypton-87 Ci

< LLD 2.34E-01 krypton-88 Ci 2.21E 00 1.20E 01 Xenon-133 C1 3.22E 01 8.79E 01 xenon-135m Ci

< LLD 1.73E 00 xenon-135 Ci 7.84E-01 1.80E 00 xenon-137 Ci

< LLD 5.20E 00 xenon-138 Ci

< LLD 4.32E-01, total for period C1 4.11E 01 1.25E 02 2.

Iodines iodine-131 C1 1.46E-03 5.98E-04 iodine-132 Ci

< LLD 2.37E-03 lodine-133 Ci 3.39E-03 3.55E-03 iodine-134 Ci

< LLD 2.16E-04 iodine-135 Ci

< LLD 4.02E-03 total for period C1 4.85E-03 1.08E-02 3.

Particulates chromium-51 C1 1.88E-04 1.42E-05 manganese-54 C1 2.90E-04 4.51E-05 cobalt-58 Ci 7.63E-05 1.59E-06 cobalt-60 C1 2.48E-04 4.21E-05 strontiute89 C1 1.80E-05 1.83E-04 strontium-90 C1 3.95E-07 8.93E-07 cesium-137 C1 1.09E-05 7.47E-06 barium-140 Ci

< LLD 1.63E-04 lanthanum-140 Ci kLD 1.31E-04 total for period Ci 8.32E-04 5.88E-04 4.

Tritium hydrogen-3 C1 5.80E-02 4.88E-01 2/3

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Table 1C Effluent and Waste Disposal Semiannual Report Year 1988 Gaseous Effluents - Ground Level Releases Continuous Release Nuclides Released Unit Qtr 1 0.tr 2 1.

Fission Gases _

i xenon-133 C1 1.31E 01 3.78E-00 Kenon-135_

Ci 1.47E OR 9.70R R1, total for period C1 1.60E 02 1.01E 02 2.

Iodines _

iodine-131 Ci 4.42E-04 1.07E-03 iodine-132 Ci

< LLD-1.15E-02 iodine-133 Ci 5.24E-04 8.81E-03 iodine-134 Ci

< LLD 2.06E-02 iodine-135

C_1, 1, (LQ

.L22E-02 total for period Ci 9.66E-04 5.47E-02 3.

Particulates chromium-51 Ci 4.18E-03 6.35E-02 manganese-54 C1 2.06E-03 1.57E-03 cobalt-58 C1 3.60E-04 1.25E-03 cobalt-60 C1 2.16E-03 1.49E-03 iron-59 C1 1.02E-03 1.05E-04 i

strontium-89 C1 3.9CE-06 9.08E-05 I

strontium-90 Ci

< LLD 1.27E-06 I

niobium-95 C1 1.03E-05

< LLD cesium-134 C1

< LLD o.53E-06 cesium-136 Ci

< LLP 1.89E-08 cesium-137 Ci 4.810-05 2.47E-04 I

barium-140 C1 4.01E-05 4.09E-04

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lanthanum-140 Ci

/,.30E-05 2.46E-04 cerium-144 9_i_

2.._0_6E-O_5

< LLQ total for period Ci 9.95E-03 6.89E-02

4. Tritium hydrogen-3 Ci 9.85E-01 7.47E-01 2/4

0 Table 2A Effluent and Waste Disposal Semiannual Report Year. 1988 Liquid Effluents - Summation of all Releases Qnit Rtc 1 Otr 2 Est Tot K Xttot A.

Fission and Activa _tign Products

1. Total release (excluding C1 1.80E-01 3.48E-01 3.50E 01 tritium, gases, & alpha).
2. Avg. diluted conc.

uCi/ml 6.55E-09 7.79E-09 3.

Percent limit 5.52E-01 8.46E-01 B.

Tritium 1.

Total release Ci 6.59E 00 4.62E 00 4.00E 00 2.

Avg. dilu'.ed conc.

uC1/ml 2.49E-07 1.03E-07 3.

Percent limit 8.00E-03 3.43E-03 C. D_issolved and Entrained Gases 3

1.

Total release C1 2.08E-03 1.57E-02 3.50E 01 2.

Avg. diluted conc.

uC1/ml 7.56E-11 3.51E-10 3.

Percent limit 3.78E-05 1.76E-04 i

D. Gross al.p_ba t.adioactiviXy_

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Total release 0.00E 00 0.00E 00 4.00E 01 1

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Vqlu_mg 2.( waste liters 1.21E 07 1.06E 07 1.2SE 01 4

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To t a l_ pff_ d_i_1u t io n wa tel Iuseq during rqJeases, j

[qn average dilu conc.)

liters 2.75E 10 4.47E 10 1.30E 01 r

G. Volumq q( goollDE WA1_et liters 2.05E 11 4.31E 11 discharged [tga elaat 1

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7 TABLE 2B Effluent and Waste Disposal Semiannual Report Year 1988 Liquid Effluents - Batch Mode Nuclides Released Unit Ot.r_.1 OLr 2 1.

Fission and activation products sodium-24 C1 1.19E-03 6.13E-03 chromium-51 C1 8.76E-03 3.47E-02 manganese-54 C1 4.21E-02 7.93E-02 iron-55 C1 1.87E-02 6.57E-03 cobalt-58 C1 8.21E-03 1.56E-02 iron-59 C1 2.85E-03 7.70E-03 cobalt-60 C1 3.72E-02 1.28E 11 arsenic '!6 Ci 1.52E-04 4.00E-04 strontium-89 C1 1.86E-04 1.69E-03 strontium-91 C1

< LLD 9.92E-05 yttrium-91m Ci 3.47E-06 9.75E-05 strontium-92 Ci 3.67E-05 4.33E-05 niobium-95m C1 2.99E-Oc

< LLD niobium-95 Ci LLD 2.16E-05 nolybdenum-99 C1

< LLD 1.92E-04 technetium-99m C1 3.50E-05 9.05E-04 silver-110m Ci 6.95E-05 4.90E-05 antimony-125 C1 1.24E-04

< LLD iodine-131 Ci 7.34E-04 1.19E-03 iodine-132 Ci

< LLD 8.52E-05 iodine-133 C1 1.23E-04 1.19E-03 lodine-134 C1 1.2eE-05 2.15E-05 cesium-134 Ci 1.01E-02 1.02E-02 iodine-135 Ci

< LLD 8.15E-04 cesium-137 C1 4.88E-02 5.33E-02 Cerium-144 C1 7.99E-04

< LLD Au_Lasten-187 Ci 7.15E-05

< LLD total for period C1 1.80E-01 3.48E-01 2.

Gases argon-41 Ci 5.40E-06

< LLD xenon-133 C1 3.0bE-04 2.97E-03 xenon-135m C1

< LLD b.05E-04 gengn-135 Ci lu77E-03 1.22E-02

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total for period C1 2.08E-03 1.57E-02 l

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v Lower Limits of Detection uCi/ml 1.

Liquid Releases Sr-90 4.97E-09 Sr-91 8.14E-08 Nb-95m 4.76E-08 Nb-95 1.84E-08 Mo-99 1.28E-07 Sb-12S 4.61E-08 I-132 2.01E-08 I-135 4.29E-08 Ce-144 8.8SE-08 W-187 8.09E-08 Ar-41 1.46E-08 Xe-135m 7.87E-Oe 2.

Gaseous Releases Kr-87 1.97E-08 Xe-135m 4.17E-08 Xe-138 9.82E-08 3.

Iodines and Particulates I-132 4.16E-13 I-13S 2.51E-13 Sr-90 3.59E-16 Nb-95 2.27E-14 Cs-134 4.75E-14 Cs-13o 3.88E-14 Ba-140 9.34E-14 La-140 6.48E-14 Ce-144 1.76E-13 WUTES 1:

The above values represent typical "a priori" LLDs for isotopes where values ot

"<LLD" are indicatec in Tables 1A, 18, 1C, 2A, and 28.

2:

Where activity for any nuclide is reported as " Less than LLD",

that nuclide is considered not present anc the LLD activity listeo is riot considered in summary data.

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.v Table 3A Effluent and Waste Disposal Semiannual Report Year 1988 Solid Waste and Irradiated Fuel Shipments Waste Class A January through June 1.

Total volume shipped (cubic meters) 4.13 E2 Total Curie quantity (estimated) 1.25 E3 2.

Type of Waste Units Six-month Est. Total Period Error,%

a. Spent resins, filter sludges meters 3 1.99 E2 Curies 1.23 E5 1.00E1 b.

Dry active waste. compacted, meters 3 2.14 E2 noncompacted Curies 2.14 El 1.00E1 c.

Irradiated components meters 3 0.00 EO Curies 0.00 EO N/A d.

Others (oil) meters 3 0.00 EO Curies 0.00 EO N/A 3.

Estimate of major radionuclide composition a.

Cr-51 2.77 EO%

Mn-54 1.66 El%

Fe-SS 4.60 El%

Co-58 1.42 80%

Co-60 2.86 El%

Ni-63 1.12 E0%

Cs-137 2.50 EO%

b.

Cr-51 1.40 EO%

Mn-54 1.11 El%

Fe-55 6.47 El%

Co-58 1.20 EO%

Co-60 1.89 El%

Ni-63

.97 EO%

c.

N/A N/A

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N/A N/A 2/8

a Table 3A (cont.)

Effluent and Waste Disposal Semiannual Report Year 1988 Solid Waste and Irradiated Fuel Shipments 4

Cross reference table. Waste stream, form, and container type.

Stream Form Conta1 Der, type No. of shipments a.

Resin Dewatered &

Type A/ Type B 39/00 Solidified

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Dry active Compacted /non-STP 27 waste compacted waste c.

Irradiated N/A N/A components d.

Other N/A N/A

  • solidification agent or absorbent (e.g.,

cement, urea formaldehyde)

CEMENT 5.

Shipment Disoosition a.

Solid Waste Number of Shipmants Mode of Transportation Destination 40 Sole Use CNSI/Barnwell SC 2e Sole Use SEG/ Oak Ridge TN b.

Irradiated Components Number of Shipments Mode of Transportation Destination 0

N/A N/A i

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Table 3B Effluent and Waste Disposal Semiannual Report Year 1988 I

Solid Waste and Irradiated Fuel Shipments Waste Class B Jcnucry through June 1.

Total volume shipped, (cubic meters) 0.( 0 EO Total Ci quantity (estimated)

2. Type of Waste Units Six-month Est. Total Period Error.f.

a.

Spent resins, filter sludges meters 3 N/A N/A Curies 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 radionuclide composition a.

N/A N/A b.

N/A N/A c.

ti/A N/A d.

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4 Cross reference table, waste stream, form and container type

@lr_eam, Eofm Contaileft type No. g f. shiplnerLts_

a.

Resin Dewatered &

ti/A N/A Solidified

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Dry active Compacted /non-N/A N/A compacted l

Waste c.

Irradiated N/A components

d. Other N/A Solidification agent or absorbent (e.g.,

coment, urea formaldehyde) 14/A 2/10

Table 38 (cont.)

Effluent and Waste Disposal Semiannual Report Year 1988

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Solid Waste and Irradiated Fuel Shipments S.

Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination N/A N/A N/A b.

Irradiated Fuel Number of Shipments Mode of Transportation Destination N/A N/A N/A l

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e Table 3C Effluent and Waste Disposal Semiannual Report Year 1988 Solid Waste and Irradiated Fuel Shipments Waste Class C January through June 1

1.

Total volume shipped, (cubic meters) 0.00 EO Total C1 quantity (estimated) 2.

Type of Waste Unit Six-month Est. Total Period Error,%

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a. Spent resins, filter sludges meters 3 N/A l

Curies l

b. Dry active waste, compacted meters 3 N/A and noncompacted c.

Irradiated components meters 3 N/A Curies

d. Others (describe) meters 3 N/A Curies 3.

Estimate of major radionuclide composition a.

N/A b.

N/A l

c.

N/A d.

N/A 4

Cross reference table, waste stream, form and container type I

l 5tr9a_m F_orJq Q_Qnt_ajn.et Typg (Lo_, 91 s b_t p_m. eat s.

a. Resin Dewatered &

N/A N/A

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Solidified

  • b.

Dry active Compacted /non-N/A N/A waste compacted

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Irradiated N/A N/A i

components

d. Others N/A N/A Solidification agent or absorbent (e.g.,

cement, urea formaldehyde)

N/A t

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.,--.--.,-w.

.,,,.,. - -. -... ~..,

--.,.----g

r-Q Table 3C (cont.)

Effluent and Waste Disposal Semiannual Report Year 1988 Solid Waste and Irradiated Fuel Shipments 5.

Shipment Disposition

a. Solid Waste Number of Shipments Mode of Transportation Destination N/A N/A N/A b.

Irradiated Components Number of Shipments Mode of Transportation Destination 0

N/A N/A 2/13

Ef4 CLOSURE 2 Combustion of Waste Oil During the first quarter, 7.78E 02 gallons of waste oil containing 1.39E 00 uCi were disposed of by incineration.

During the second quarter, 5.78E 02 gallons of waste oil containing 8.01E-01 uci were disposed of by incineration.

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ATTACHMENT 3 Off-Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions January 1,

to June 30, 1988 Brunswick Steam Electric Plant There were no revisions made to the Off-site Dose Calculation l

Manual (ODCM) or the Process Control Program (PCP) during this time period.

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ATTACH.'iENT 4 Enviromental Monitoring Program January 1, to June 30, 1988 :

Milk and Vegetable Sample Locations :

Land Use Census l

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ENCLOSURE 1 Milk and Vegetable Sample Locations No milk sample locations were available during this time period.

Vegetable sample locations were unchanged during this time period.

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ENCLOSURE 2 Land Use Census No new locations were identified that are reportable in the Semlannual Radioactive Effluent Release Report as per Technical Specification 3.12.2.a and b.

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4 ATTACHMENT 5 Inoperable Effluent Instrumentation January 1, to June 30, 1988 :

Radioactive Liquid Effluent Monitoring Instrumentation :

Radioactive Gaseous Effluent Monitoring Instrumentation :

Liquid Hold-Up Tank i

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EliCLOSURE 1 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 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, 5/2

O ENCLOSURE 2 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 AnalV2er), 1(2)-OG-AIT-4285 (SJAE.A.H2 Analyzer), 1(2)-OG-AIT-4324 (SJAE.B.H2 Analyzer), and it2)-OG-AIT-4325 (SJAE.B.H2 Analyzer) were inoperable for greater than a 30 day period during January 1,to June 30, 1988.

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

Units 1 and 2 Reactor and Turbine buildings roof vent flow monitor l

elements; 1-VA-FE-3356.1-VA FE-3358,2-VA-FE-3356 and 2-VA-FE-3358 l

were inoperable for greater than a 30 day period during January 1,

to June 30, 1988.

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

Unit 1 Turbine building roof vent flow monitor totalizer, 1-VA-FIO-3358 was inoperable for greater than a 30 day period during January 1,

to June JO, 1986, because it Would not meet the acceptance criteria of an operational test investigations have l

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1-VA-Flo-3358 to an operable status.

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Unit 2 Main Condenser Off-Gas treatment ** stem Argumented Of f-Gas l

l (AOG) monitor 2-AOG-RI-103 was ir sperable for greatur than 30 a i

day period during January 1.

to June 30, 1988. Due to the Unit refueling outage this monitor was not returned to service within 30 days, l

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ENCLOSURE 3 Liquid Hold-Up Tank No liquid hold-up tank exceeded the 10 C1 limit during this time period.

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s ATTACHMENT 6 Major Modifications to the Radioactive Waste Treatment Systems January 1 to June 30. 1988 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, 1988 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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ATTACHMENT 8 Potential Dose Assessment Brunswick Steam Electric Plant January 1, to June 30, 1988 As required by Technical Specification 6.9.1.10.b.

an assessmer.t 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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ATTACHMENT 9

SUPPLEMENT TO PREVIOUS SEMIANNUAL RE.JRT Brunswick Steam Electric Plant i

January 1.

to June 30, 1988 l

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' : DISCUSSIC'i : DATA TABLE 9/1

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