BSEP-95-0410, Semiannual Radioactive Effluent Rept Jan- June 1995

Semiannual Radioactive Effluent Rept Jan- June 1995

ML20091P216
Person / Time
Site:	Brunswick
Issue date:	06/30/1995
From:	Levis W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-95-0410, BSEP-95-410, NUDOCS 9509010080
Download: ML20091P216 (32)

Text

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4 CP&L i

' Carolina Power & Ught Company.

l P.O. Box 10429 Southport, NC 28461 0429 AUG 2 81995 SERIAL: BSEP 95-0410

. FILE: B0913510C .

U. S Nuclear Regulatory Commission '

' ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS,1 AND 2

DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT L Gentlemen

Enclosed is the Semi-Annual Radioactive Effluent Release Report for the Brunswick Steam Electric Plant, Units 1 and 2 covering the period from January 1,1995 through June 30,1995.

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

Please refer any questions regarding this submittal to Ms. Jackie Gawron at (910) 457-2447.

Sincerely,-

W. Levis Plant General Manager Brunswick Nuclear Plant WRM/wrm Enclosure Mr. S. D. Ebneter, Regional Administrator, Region il

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Mr. D. C. Trimble, NRR Project Manager - Brunswick Units 1 and 2 Mr, C. A; Patterson, NRC Senior Resident inspector- Brunswick Units 1 and 2

- The Honorable H. Wells, Chairman - North Carolina Utilities Commission

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Brunswick Nuclear Plant Semiannual Radioactive Effluent Report January 1, to June 30, 1995 ATTACHMENTS: PAGES:

1. Supplemental Information 2-6

2. Effluent and Waste Disposal Data 7- 20

3. Environmental Monitoring Program 21 - 23

4. Effluent Instrumentation 24 - 27

5. Major Modification to Radioactive Waste 28 Treatment Systems

6. Meteorological Data 29

7. Annual Dose Assessment 30

8. ODCM and PCP Revisions 31 1

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ATTACHMENT 1 Supplemental Information January 1, to June 30, 1995 2 age 2

EFFLUENT WASTE DISPOSAL SEMIANNUAL REPORT

Supplemental Information l l

Facility: Brunswick Nuclear Plant Licensee: Carolina Power and Light Company 3

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 b

.(2) Calendar Year (a) 20 mrad gamma (b) 40 mrad beta i B. Iodine-131, iodine-133, tritium, and particulates with half lives greater than eight days (Technical Spec. 3.11.2.3)

• (1) Calendar Quarter (a) 15 mrem to any organ (2) Calendar Year (a) 30 mrem to any organ

• (3) Calendar Quarter for Burning Contaminated Oil (a) 436 uCi I

(4) Calendar Year for Burning Contaminated Oil i

(a) 872 uCi C. Liquid effluents (Technical Specification 3.11.1.2)

• * (1) Calendar Quarter l (a) 3 mrem to total body (b) 10 mrem to any organ (2) Calendar Year (a) 6 mrem to total body (b) 20 mrem to any organ NOTE: Dose calculations are determined in accordance with the Off-Site Dose Calculation Manual (ODCM)

• Used for percent of Technical Specification limit determinations in Table 1A.

• Used for percent of Technical Specification limit determinations in Table 2A.

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

i 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 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, for radionuclides other ,

than noble gases.

• * (1) Tritium: limit = 1 E-03 uCi/ml and

• * (2) Dissolved and entrained gases: limit = 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 i

! Analysis for specific radionuclides collected on filter ,

papers by gamma spectroscopy.

I D. Particulates for Burning 011 Analysis for specific radionuclides by grab camples of each batch of oil to be burned.

d E. Liquids Effluents Analysis for specific radionuclides of individual releases

• by gamma spectroscopy.

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• Used as applicable limits for Table 2A, t

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,, .  :-- - , . . . - - - - -- - = -

i 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 j R

A. Liquid (1) Number of. batch releases: 1.38E+02 (2) Total time period for. batch releases: 1.78E+04 Minutes (3) Maximum time period for a~ batch release: 3.13E+02 Minutes (4) Average time period for a batch release: 1.29Ev02 Minutes

'(5) Minimum time period for a batch release: 1.20E+01 Minutes (6) Average stream flow during periods of release of effluent into a flowing stream : 7.50E+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 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 act.ivity 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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1 Discussion of Tritium in the Storm Drain Collection Pond Approximately 1.49E+07 gallons containing 7.63E+00 curies of tritium were released from the Storm Drain Collection Pond (SDCP) to the Intake Canal during this reporting period. The SDCP is a permitted release point.

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

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ATTACHMENT'2

-Effluent and Waste Disposal Data

-Brunswick Nuclear Plant January 1,"to June 30, 1995 Table 1A: Gaseous Effluents - Summation of all Releases Table 1B: Gaseous' Effluents - Elevated Releases

. Table 1C: Gaseous Effluents - Ground Level Releases Table 3D: Gaseous Effluents - Ground Level Releases for Burning Contaminated Oil.

Table 2A: Liquid Effluents - Summation of all Releases Table 2B: Liquid Effluents - Batch Mode Lower Limits of Detection Table 3A: Solid Waste and Irradiated Fuel Shipments - Waste Class A Table 3B: Solid Waste and Irradiated Fuel Shipments - Waste Class B Table 3C: Solid Waste and Irradiated Fuel Shipments - Waste Class C Combustion of Waste Oil Page 7 s.

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TABLE 1A Effluent and WasteLDisposal Semiannual Report for Year 1995 Gaseous Effluents - Summation of all Releases Est.. Tot.

Unit Otr 1 Otr 2 Error %

A; FISSION AND ACTIVATION GASES ,

1. Total release Ci 6.77E+01 5.72E+01 4.50E+01

2. Average release uCi/sec 8.71E+00 7.28E+00 rate for-period

3. Percent of technical specification limit  % 1.51E-02 1.49E-02 B. IODINES

1. Total I-131- Ci 8.96E-04 4.71E-04 3.50E+01

2. Average release uCi/sec 1.15E-04 5.99E-05 rate for period C. PARTICULATES NOTE 1

1. Total release Ci 5.07E-03 1.27E-02 3.50E+01

2. Average release uCi/sec 6.53E-04 1.62E-03 rate for period

3. Gross alpha Ci 2.48E-06 1.30E-06 D. TRITIUM

1. Total release Ci 7.07E+00 5.78E+00 3.00E+01

2. Average release uCi/sec 9.09E-01 7.35E-01 rate for period E. IODINE-131, IODINE-133. TRITIUM AND PARTICULATES NOTE 1

1. Total Release Ci 7.08E+00 5.79E+00

2. Average release uCi/sec 9.10E-01 7.37E-01 rate for period

3. Percent of technical specification limit  % 3.77E-02 2.77E-02 F. PARTICULATES VIA BURNING CONTAMINATED OIL

1. Total Release Ci 0.00E+00 0.00E+00  ;

2. Average release l rate for period uCi/sec 0.00E+00 0.00E+00 {

3. Percent of technical I specification limit  % 0.00E+00 0.00E+00 l NOTE t This includes the number of curies released via incineration.

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TABLE 1B Effluent and Waste Disposal Semiannual Report for Year 1995 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 1 Otr 2

1. FISSION GASES argon-41 Ci 2.64E+00 1.61E+00 krypton-85m Ci 7.21E+00 7.24E+00 krypton-87 Ci 9.66E+00 1.27E+01 krypton-88 Ci 1.18E+01 1.51E+01 xenon-133 Ci 7.38E+00 1.13E+00 xenon-135m Ci 2.77E+00 2.48E+00 xenon-135 Ci 1.12E+01 1.51E+01 xenon-138 gi 3.61E+00 6.99E-01 total for period Ci 5.62E+01 5.61E+01

2. IODINES iodine-131 Ci 4.08E-04 1.99E-04 iodine-132 Ci 1.91E-03 1.56E-04 iodine-133 Ci 2.40E-03 6.37E-04 iodine-135 gi 3.06E-03 < LLD total for period Ci 7.78E-03 9.92E-04

3. PARTICULATES chromium-51 Ci 6.46E-05 4.51E-05 manganese-54 Ci 2.82E-06 3.13E-06 cobalt-58 Ci 1.98E-06 < LLD cobalt-60 Ci 1.83E-05 2.38E-05 strontium-89 Ci 2.84E-05 1.42E-05 strontium-90 Ci 2.37E-07 2.12E-07 barium-140 Ci 6.28E-05 3.13E-06 lanthanum-140 gi 8.21E-05 6.04E-06 total for period Ci 2.61E-04 9.56E-05

4. TRITIUM hydrogen-3 Ci 1.32E+00 1.76E+00 Page 9

TABLE 1C Effluent and Waste Disposal. Semiannual. Report for. Year 1995 Gaseous Effluents - Ground Level Releases ,

Continuous Release  !

Nuclides Released Unit Otr 1 Otr 2

1. FISSION GASES krypton-85m Ci 6.14E-01 < LLD ,

xanon-133 Ci 8.52E-01 < LLD l xenon-135m Ci 3.76E+00 < LLD.

xenon-135 f1L 6.28E+00 1.12E+00 t 1

totalifor period Ci 1.15E+01 1.12E+00 f

2. IODINES

= iodine-131 Ci 4.89E-04 2.72E-04 iodine-132 Ci 7.58E-03 8.79E-04 [

iodine-133 Ci 5.46E-03 2.86E-04

• iodine-134 Cif 3.28E-04 < LLD' l iodine-135 Ci 9.20E-03 1.91E-06  !

total for period Ci 2.30E-02 1.44E-03 1

3. PARTICULATES NOTE 1 chromium-51 Ci 4.19E-03 6.49E-03 manganese-54 Ci 5.48E-05 1.03E-03 '

cobalt-58 Ci 1.10E-04 5.21E-04 iron-59 Ci < LLD 3.15E-04 cobalt-60 Ci 4.37E-04 3.37E-03  ;

strontium-89 Ci 1.22E-05 4.60E-06 strontium-90 Ci 6.23E-08 2.51E niobium-95 Ci < LLD 6.10E-05 ruthenium-103 Ci < LLD 5.01E-04 i ruthenium-106 Ci < LLD 3.18E-04 '

cesium-137 Ci 1.34E-06 4.52E-06 4 barium-140 Ci 1.06E-06 1.50E-06 lanthanum-140 Ci 2.79E-06 2.71E-07 t hafnium-181 Ci < LLD 9.30E-06 americium-241 gi < LLD 1.12E-05 .

3 total for period Ci 4.81E-03 1.26E-02 l s

4. TRITIUM j hydrogen-3 Ci 5.75E+00 4.02E+00

j. NOTE la This includes the number of curies released via incineration.

TABLE 1D

[ Effluent and Waste Disposal Semiannual Report for Year 1995 i Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nucl' ides Released Unit Otr 1 Otr 2 ,

i 1. PARTICULATES Ci 0.00E+00 0.00E+00 Page 10-

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d TABLE 2A Effluent and Waste Disposal Semiannual Report for Year 1995 I Liquid Effluents - Summation of all Releases Unit Otr 1 Otr 2 Est Tot

% Error-A. FISSION AND ACTIVATION PRODUCTS NOTE 1

1. Total-release (excluding Ci 3.88E-01 1.55E-02 4.00E 01 >

tritium, gases, & alpha)

NOTE 2 ,

2. Avg. diluted conc. uCi/ml 1.65E-08 5.74E-10

3. Percent limit  % 5.84E-01 2.93E-02  ;

B. TRITIUM NOTE 1

' 1. Total release Ci 1.67E+01 1.17E+01 4.50E 01 NOTE 2 2.. Avg. diluted conc. uCi/ml 7.11E-07 4.34E-07

3. Percent limit  % 7.11E-02 4.34E-02 C. DISSOLVED AND ENTRAINED GASES NOTE 1

1. Total release Ci 7.67E-04 8.61E-04 4.00E 01 >

NOTE 2 l

2. Avg. diluted conc. uCi/ml 3.26E-11 3.18E-11

3. Percent limit  % 1.63E-05 1.59E-05 D. GROSS ALPHA RADIOACTIVITY

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

. E. VOLIHE OF WASTE ' NOTE 2 liters 3.96E+06 4.94E+06 1.50E 01 F. TOTAL OF DILUTION WATER (used durina release for averaae dil. conc.) liters 2.35E+10 2.70E+10 1.30E 01 G. VOLUME OF COOLING WATER liters 3.84E+11 3.71E+11 i DISCHARGED FROM PLANT NOTE 1: Includes radionuclides released via abnormal and/or nonroutine releases.

NOTE 2: Does not include rainwater rekased (i.e. Storrn Drain Collection Basin and/or Storm Drain Collection Pond.)

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TABLE 2B Effluent and Waste Disposal Semiannual Report for Year 1995 Liquid Effluents - Batch Mode

.i Nuclides Released Unit Otr 1 Qar_2

1. FISSION AND ACTIVATION PRODUCTS i chromium-51 Ci 5.83E-02 2.22E-03

' manganese-54 Ci 1.20E-02 6.06E-04 Ci 7.44E-03 < LLD iron-55 cobalt-58 Ci 6.63E-04 1.86E-04 iron Ci < LLD 1.34E-05 cobalt-60 Ci 2.99E-01 1.14E-02 zinc-69m Ci < LLD 1.31E-06 i arsenic-76 .Ci < LLD 4.01E-06 niobium-95 C1 1.42E-06 1.13E-06 3 niobium-95m Ci 1.76E-06 < LLD technetium-99m Ci 3.60E-05 2.57E-06 iodine-131 Ci 2.17E-OS 1.27E-05 iodine-133 Ci 2.38E-06 1.32E-05 i cesium-134 Ci 1.96E-03 4.68E-05 cesium-137 Ci 7.80E-03 8.45E-04 hafnium-181 Ci < LLD 2.19E-04 americium-241 gi < LLD 1.30E-05 total for period Ci 3.88E-01 1.55E-02 i

2. DISSOLVED AND ENTRAINED GASES -

krypton-85m Ci 1.76E-05 < LLD xenon-133 Ci 6.23E-05 8.39E-05 xenon-133m Ci 1.12E-04 < LLD xenon-135m Ci < LLD 1.79E-05 xenon-135 gi 5.75E-04 7.59E-04 total for period Ci 7.67E-04 8.61E-04 s

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Lower Limits of Detection January 1, to June 30, 1995 pCi/ml

1. Liauid Releases 2. Gaseous Releases Mn-54 1.73E-08 Kr-85m 5.28E-09 Fe-55 4.80E-08 Kr-87 1.22E-08 Co-58 9.76E-09 Kr-88 2.52E-08 Fe-59 3.23E-08 Xe-133 2.44E-08 Co-60 1.37E-08 Xe-133m 7.44E-08 Zn-65 3.88E-08 Xe-135 4.92E-09 Zn-69m 8.12E-09 Xe-135m 5.37E-08 As-76 4.97E-08 Xe-138 2.39E-07 Nb-95 1.95E-08 Nb-95m 4.36E-08 Mo-99 9.95E-08 3. Iodines and Particulates Cs-134 1.94E-08 Mn-54 4.35E-14 Cs-137 1.89E-08 Co-58 4.03E-14 Ce-144 7.85E-08 Fe-59 1.01E-13 Hf-181 1.63E-08 Co-60 5.15E-14 Am-241 1.18E-07 Zn-65 1.21E-13 Sr-89 2.62E-08 Sr-89 2.27E-15 Sr-90 1.36E-08 Sr-90 1.31E-15 Alpha 4.28E-08 Nb-95 2.85E-14 Kr-85m 9.99E-09 Ru-103 2.95E-14 Kr-87 3.09E-08 Ru-106 3.46E-13 Kr-88 5.39E-08 Cs-134 3.43E-14 Xe-133 4.96E-08 I-134 1.16E-11 Xe-133m 1.53E-07 I-135 5.92E-13 Xe-135 9.40E-09 Cs-137 2.88E-14 Xe-135m 4.00E-08 Ce-141 4.14E-14 Xe-138 1.69E-07 Ce-144 1.04E-13 I-131 1.69E-08 Hf-181 3.07E-14 Ce-141 1.98E-08 Am-241 1.08E-13 I-131 2.84E-14 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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i TABLE 3A Effluent and Waste Disposal Semiannual Report for Year 1995  ;

Solid Waste and Irradiated Fuel Shipments Waste Class A January throuch June i t

1. Total volume shicoed (cubic meters) 2.91E+02

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Total Curie quantity (estimated) 2.74E+02 ,

2. Tvoe of Waste Six-month Es t . 'i'otal I Units Period  % Error

a. Spent resins, filter sludges _ meters' 9. 61E+01 Curies 2.32E+02 1.00E+01

b. Dry active waste, compacted meters3 1.86E+02 i noncompacted Curies 4.03E+01 1.00E+01

c. Irradiated components meters3 8.56E+00 Curies 1.21E+00 1.00E+01

'd. Others meters' O . 00E+00 Curies 0.00E+00 N/A 3.' Estimate of maior radionuclide composition

a. Co-60 5.27E+01%

Fe-55 2.46E+01% .

Cr-51 6.50E+00% .

Ni-63 5.73E+00%

Co-58 5.06E+00%

Cs-137 3.04E+00%

Mn-54 2.03E+00% ,

b. Fe-55 5.50E+01%

Co-60 3.77E+01%

Ni-63 3.21E+00%

Cr-51 2.24E+00%

• Mn-54 9.30E-01%

Co-58 5.60E-01%-

c. Co-60 6.27E+01%

Fe-55 3.27E+01%

Mn-54 3.00E+00%

Ni-63 1.31E+00%

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d. N/A N/A l

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Table 3A (cont.)  ;

Effluent and Waste Disposal Semiannual Report for Year 1995 l Solid Waste and Irradiated Fuel Shipments I

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

Stream Form Container tvoe No. of shioments Type A/ Type B

a. Resin Dewatered & 11/7 18 Solidified *

b. Dry active Compacted / 3/1 4 waste Noncompacted waste

c. Irradiated 1/0 1 components

d. Other N/A 0

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

5. Shinment Disposition

a. Solid Waste Number of Shinments Mode of Transoortation Destination 23 Sole Use CNSI/Barnwell, SC

b. Irradiated Fuel Number of Shinments Mode of Transoortation Destination 0 N/A N/A Page 15

. TABLE 3B Effluent and Waste Disposal Semiannual Report for Year 1995 Solid Waste and Irradiated Fuel Shipments Haste Class B January throuch June

1. Total volume'shicoed (cubic meters) 3.41E+00 Total' Curie quantity (estimated) 1.11E+03

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

a. Spent resins, filter sludges meters 3 0.00E+00 Curies 0.00E+00 N/A

b. Dry active waste, compacted, meters' O.00E+00 and noncompacted Curies 0.00E+00 N/A

c. Irradiated components- meters 2 3.41E+00 Curies 1.11E+03 1.00E+01

d. Others (describe) meters' O 00E+00 Curies 0.00E+00 N/A

3. Estimate of maior radionuclide composition

a. N/A N/A

b. N/A N/A

c. Fe-55 4.99E+01%

Co-60 4.56E+01%

Ni-63 3.63E+00%

Mn-54 1.08E+00%

d. N/A N/A j

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TABLE 3B (cont.)

Effluent and' Waste Disposal Semiannual Report For Year 1995 Solid Waste and Irradiated Fuel Shipments i

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

. Stream Form Container tvoe No. of shioments I

Type A/ Type B Dewatered &

i a. Resin N/A 0 l Solidified i

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

' waste Noncompacted j waste .

i c. Irradiated 0/1 1 ,

components 4

i l d. Other N/A 0

• Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A 4

i 5.Shioment Discosition

a. Solid Waste Number of Shioments Mode of Transoortation Destination 1 Sole Use CNSI/Barnwell SC

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b. Irradiated vuel 1

I Number of Shioments Mode of Transoortation Destination 0 N/A N/A i

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I TABLE 3C .

Effluent and Waste Disposal Semiannual Report for Year 1995  !

Solid: Waste and Irradiated Fuel Shipments ,

Waste Class C Januarv'throuch June  !

1.-To'tal-volume shicoed (cubic meters)- 3.84E+00 t Total Curie quantity (estimated) 9.47E+01

2. Tyre of Waste Six-month Est. Total ,

Units Period  % Error ,

i a'. Spent resins, filter-sludges meters' '3.84E+00 Curies 9.47E+01 1.00E+01  ;

b. Dry active waste, compacted meters' O.00E+00 l and noncompacted- 0.00E+00 Curies N/A I

c. Irradiated components meters 2 0.00E+00  :

Curies 0.00E+00 N/A ,

d. Others (describe) meters 8 0.00E+00  !

Curies 0.00E+00 N/A e

3. Estimate of maior radionuclide comoosition i

a. Fe-55 8.46E+01%

Co-60 1.33E+01%

Ni-63 2.10E+00%

b. N/A N/A l

c. N/A N/A

d. N/A N/A e

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• l TABL2 3C (cont.)

Effluent and-Waste Disposal Semiannual Report for Year 1995 Solid Waste and Irradiated Fuel Shipments-

4. Cross reference table, waste stream, form and container tvoe Stream Form Container Tvoe No. of shioments Type A/ Type B

a. Resin Dewatered &' -0/1 1 ,

i Solidified

• b.' Dry active Compacted N/A 0 '

waste Noncompacted waste

c. Irradiated N/A 0 components

d. Others N/A 5

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

5. Shioment Discosition

a. Solid Waste Number of Shioments Mode of Transoortation Destination 1 Sole Use CNSI/Barnwell, SC

b. Irradiated Fuel (non-burial)

Number of Shioments Mode of Transoortation Destination 5 Rail Car IF-300 Cask CP&L/SHNPP Sole Use 1

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ATTACHMENT 2 (Cont.)

Combustion of Waste Oil January 1, to June 30, 1995 There was no incineration of contaminated waste oil during this report period.

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ATTACHMENT 3 Environmental Monitoring Program January 1, to June 30, 1995 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census

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ATTACHMENT 3 (Cont.)

ENCLOSURE 1 Milk and Vegetation Sample Locations January 1, to June 30, 1995 No milk samples were identified during the last Land Use Census, therefore, no milk locations were available during this time period.

Vegetation sample locations remained unchanged.

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l ATTACEMENT 3 (Cont.)

ENCLOSURE 2 Land Use Census January 1, to June 30, 1995 l

r' The results of the 1995 Land Use Census will be reported in the 1 1

next Semiannual Radioactive Effluent Release Report. l l

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-ATTACHMENT 4. I 4

Effluent-Instrumentation  !

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, January.1, to June 30, 1995 s .

Enclosure 1: Radioactive Liquid = Effluent Monitoring ,

. Instrumentation. l

-Enclosure 2:.' Radioactive Gaseous Effluent Monitoring Enclosure 3: Liquid Hold-Up Tank l.

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. o ATTACHMENT 4 (Cont.)

ENCLOSURE 1 Radioactive Liquid Effluent Monitoring Instrumentation January 1, to June 30, 1995 No Radioactive Liquid Effluent Monitoring Instrumentation was inoperable for greater than 30 days.

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t ATTACHMENT 4 . (Cont .')

i e ENCLOSURE 2 5

Radioactive' Gaseous Effluent Monitoring Instrumentation

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January l', to June 30, 1995 -

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'.i No Radioactive Gaseous Effluent Monitoring-Instrumentation'was >

j inoperable for greater than 30 days. l

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ATTACHMENT 4 (Cont.)

ENCLOSURE 3 Liquid Hold-Up Tank January 1, to June 30, 1995 No liquid hold-up tank exceeded the 10 Ci limit during this reporting period.

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-1 ATTACHMENTS .l J

Major Modifications to the Radioactive Waste Treatment System j

- January.1, to June 30,.1995 l As per' footnote 7 to. Technical Specification 6.15, a discussion  !

of any major. modifications to the radioactive waste treatment- I systems will be submitted with the Final Safety Analysis' Report update.

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ATTACHMENT 6 Meteorological Data

. January 1, to June 30, 1995 l l

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-As per' Technical Specification 6.3.1.10.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 7 Annual Dose Assessment January 1, to June 30, 1995 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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I s . . , 1 ATTACHMENT 8 i l

l Off-Site Dose Calculation Manual (ODCM) and 1

Process Control Program (PCP) Revisions January 1, to June 30, 1995 l

There were no revisions made to the Off-Site Dose Calculation Manual or Process Control Program during this reporting period.

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