BSEP-96-0076, Semiannual Radioactive Effluent Release Rept, for BSEP Units 1 & 2,covering Period from 950701-1231

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Semiannual Radioactive Effluent Release Rept, for BSEP Units 1 & 2,covering Period from 950701-1231
ML20100K327
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/31/1995
From: Levis W
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-96-0076, BSEP-96-76, NUDOCS 9603010111
Download: ML20100K327 (60)
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Carolina Power & Light Company P.O. Box 10429 Southport, NC 28461 l SERIAL: BSEP 96-0076 FEB 261996 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk l Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 l I

DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & 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 July 1,1995 through December 31, 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 letter to Ms. Jackie Gawron at (910) 457-2447.

Sincerely, W. Levis - Director Site Operations Brunswick Steam Electric Plant 1

WGR/gmt

Enclosure:

1. Report
2. List of Regulatory Commitments cc: Mr. S. D. Ebneter, NRC Regional Administrator, Region 11 Mr. C. A. Patterson, NRC Senior Resident inspector - Brunswick Plant i Mr. D. C. Trimble, Jr., NRR Project Manager - Brunswick Plant The Honorable H. Wells, Chairman - North Carolina Utilities Commission 01pera _

9603010111 951231 PDR ADOCK 05000324 PDR p(/D

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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 l

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

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59 Pages Enclosed

i EXECUTIVE

SUMMARY

Dose Assessment Summarv:

A summary of gaseous and liquid effluents during the period from July, 1 1995 to December 31, 1995 is contained within this report. Also included is the results of a comprehensive off-site dose assessment for the year of 1995 using such information as location of nearby residents, recreational uses of the area, actual wind speed and direction, and water flows. The assessment estimated the likely most exposed individual could have received 0.04 mrem from gaseous effluents and 0.007 mrem from liquid effluents discharged from the plant in 1995. Environmental studies conducted prior to the operation of the plant (1972-1975) determined that measured natural background radiation level for this area is approximately 50 mrem per year. It is concluded that the environmental impact due to radiological effluents from the plant in 1995 was negligible.

Manacement Philosophy:

Radiological effluents at the Brunswick Steam Electric Plant are managed and monitored to ensure that radioactivity released to the environment is minimal and within regulatory limits.

Radiological environmental factors are an integral part of planning, design, construction, and operational decisions. By practicing this philosophy, Brunswick minimizes the impact to the environment and ensures that exposures are maintained below regulatory limits.

Effluent Accountability 1 Plant systems are designed to control and minimize effluent discharges by such means as filtration and decay of radioactive constituents. Effluent streams are carefully monitored to ensure accurate accountability of any radioactive effluents that may be released. Monitoring is conducted by both plant instrumentation and laboratory analyses of effluent samples. Data is routinely compiled for assessment of the radiological impact to the public and for compliance with federal regulations using the conservative methodology contained in the plant Off-Site Dose Calculation Manual (ODCM).

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i Brunswick Steam Electric Plant Semiannual Radioactive Effluent Report .

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July 1, to December 31, 1995 l

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ATTACHMENTS: PAGES:

1. Supplemental Information 2 - 6
2. Effluent and Waste Disposal Data 7 - 20 l l

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3. Environmental Monitoring Program 21 - 23 l l
4. Effluent Instrumentation 24 - 27 l
5. Major Modification to Radioactive Waste 28 Treatment Systems
6. Meteorological Data 29 1
7. Annual Dose Assessment 30 - 46
8. ODCM and PCP Revisions 47 - 58 l

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ATTACHMENT 1 1

Supplemental Information l

l July 1, to December 31, 1995 1

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information 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-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 (4) Calendar Year for Burning Contaminated Oil (a) 872 uCi C. Liquid effluents (Technical Specification 3.11.1.2)
  • * (1) Calendar Quarter (a) 3 mrem to total body (b) 10 mrem to any organ (2) Calendar Year (a) 6 mrem to total body (b) 20 mrem to any organ r

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.

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 i liquid effluents to unrestricted areas after dilution in the discharge canal shall be limited to the concentrations specified in 10CFR20, Appendix B.

  • * (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 I

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

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

l E. Liquids Effluents l

Analysis for specific radionuclides of individual releases by gamma spectroscopy.

  • Used as applicable limits for Table 2A l

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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 A. Liquid l (1) Number of batch releases: 1.08E+02 (2) Total time period for batch releases: 1.61E+04 Minutes (3) Maximum time period for a batch release: 3.77E+02 Minutes (4) Average time period for a batch release: 1.49E+02 l Minutes (5) Minimum time period for a batch release: 1.00E+01 Minutes (6) Average stream flow during periods l of release of effluent into a. flowing

! stream : 8.14E+05 GPM B. Gaseous l (1) Number of batch releases: 0.00E+00 I

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L (2) Total time period for a batch release: 0.00E+00 Minutes l- (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 l S. Abnormal releases

  • A. Liquid

'(1) Number of releases: 0.00E+00 (2) Total activity released: 0.00E+00 Curies l- B. Gaseous

, (1) Number of releases: 0.00E+00 (2) Total activity released: 0.00E+00 Curies 4

  • There were no abnormal releases that exceeded 10CFR20 or 10CFR50 limits. See Page 6 for a ciscussion of release events tMt ocmarred, i

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1. Discussion of Tritium in the Storm Drain Collection Pond Approximately 1.92E+07 gallons containing 7.88E+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 i permitted release point.

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

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

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l Discussion of Noble Gas Released i

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t Noble gas curies discharged were higher than usual during '

this report period. On July 25, 1995 Uldt 2 developed fuel l leaks. It-is estimated that 3 fuel rod leaks were present I in the core. The effects of these leaks were mitigated by l power suppression (by control rod insertion) in two areas of the  !

core. Additionally, it was found that a small portion of the l total off-gas flow was being bypassed around the Augmented Off-l l Gas System (AOG) due to a defect in the 2-AOG-HCV-V102 (AOG bypass valve). A temporary modification was implemented that significantly reduced the impact of this condition.

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  • j ATTACHMENT 2 Effluent and Waste Disposal Data Brunswick Steam Electric Plant July 1, to December 31, 1995 Enclosure 1 Table 1A: Gaseous Effluents - Summatica 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 Table 2B: Liquid Effluents - Batch Mode Appendix A: 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 l l

Table 3C: Solid Waste and Irradiated Fuel Shipments l

Waste Class C l

Enclosure 2 Combustion of Waste Oil i

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! Effluent and Waste Disposal Semiannual Report for Year 1995 j Gaseous Effluents - Summation of all Releases Est. Tot.

Unit Otr 3 Otr 4 Error %

A. FISSION AND ACTIVATION GASES

1. Total release Ci 3.46E+03 7.28E+02 4.50E+01
2. Average release uCi/sec 4.36E+02 9.16E+01 l rate for period
3. Percent of technical specification limit  % 5.27E-01 1.10E-01 B. IODINES
1. Total.I-131 Ci 2.07E-03 1.88E-03 3.50E+01 l

l 2. Average release uCi/sec 2.60E-04 2.36E-04 l rate for period l C .. PARTICULATES Eq!T__1 l 1. Total release Ci 2.72E-03 1.86E-03 3.50E+01

2. Average release uCi/sec 3.42E-04 2.34E-04 L rate for period
3. Gross alpha Ci 1.22E-06 1.27E-06 D. Triti.um
1. Total release Ci 1.13E+01 1.24E+01 3.00E+01
2. Average. release uCi/sec 1.42E+00 1.56E+00 rate for period E. IODINE-131. IODINE-133, TRITIUM AND PARTICULATES wmr t
1. Total Release Ci 1.13E+01 1.24E+01
2. Average release uCi/sec 1.42E+00 1.56E+00 rate for period
3. Percent of technical specification limit  % 7.20E-02 7.20E-02 F. PARTICULATES VIA BURNING CONTAMINATED OIL
1. Total Release Ci 0.00E+00 2.42E-05
2. Average release rate for period uCi/sec 0.00E+00 3.05E-06 I 3. Percent of technical specification limit  % 0.00E+00 5.55E+00 NOTF 1 This includes the number of curies released via incineration.

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L TABLE 1B l Effluent and Waste Disposal Semiannual Report for Year 1995 l Gaseous Effluents - Elevated Releases i

Continuous Release i

Nuclides Released Unit Otr 3 Otr 4

1. FISSION GASES l

l krypton-85m Ci 3.01E+02 7.64E+01

! krypton-87 Ci 3.33E+02 2.93E+01 l krypton-88 Ci 5.93E+02 7.19E+01 xenon-133 Ci 1.04E+03 3.81E+02  :

xenon-135 Ci 9.99E+02 8.73E+01 '

! xenon-135m Ci 5.14E+01 2.01E+01 l xenon-137 Ci < LLD 5.36E+00 xenon-138 gi 1.40E+02 4.28E+01 l total for period Ci 3.46E+03 7.14E+02

2. IODINES i

l lodine-131 Ci 1.66E-03 1.15E-03 Ci iodine-132 8.00E-04 5.26E-03 iodine-133 Ci 2.36E-03 5.50E-03 iodine-135 Ci 8.97E-04 7.08E-03 total for period Ci 5.71E-03 1.90E-02 l

3. PARTI CULAL"".

chromium-51 Ci 1.41E-04 5.32E-05 manganese-54 Ci 1.11E-05 1.64E-06 cobalt-60 Ci 5.44E-06 9.35E-06 strontium-89 Ci 2.20E-05 1.28E-04 strontium-90 Ci 1.69E-07 8.08E-07 cesium-137 Ci < LLD. 2.20E-06 barium-140 Ci 7.74E-06 8.61E-05 lanthanum-140' Ci < LLD 1.06E-04 l hafnium-181 Ci < LLD 1 82E-06 l total for period Ci 1.87E-04 3.90E-04

4. TRITIUM hydrogen-3 Ci 4.28E+00 2.75E+00 l

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l TABLE 1C Effluent and Waste Disposal Semiannual Report for Year 1995 l Gaseous Effluents - Ground Level Releases 1 Continuous Release Nuclides Released Unit Otr 3 Otr 4

1. FISSION GASES krypton-85m Ci 1.67E-01 9.71E-01 krypton-87 Ci 1.47E-01 < LLD' l krypton-88 Ci 6.14E-01 1.78E+00 '

l xenon-133 Ci 2.61E+00 1.36E+00  ;

xenon-135m Ci < LLD 5.62E-01 i xenon-135 Ci 3.28E+00 9.66E+00 total for period Ci 6.81E+00 1.43E+01 2.IRDlHES I iodine-131 Ci 4.10E-04 7.32E-04 Ci iodine-132 2.54E-04 2.44E-03 iodine-133 Ci 8.88E-04 4.23E-03 iodine-134 Ci 1.93E-08 5.34E-05 i iodine-135 C1 2.53E-05 2.58E-03 I total for period Ci 1.58E-03 1.00E-02 ,

3. PARTICULATES chromium-51 Ci 1.93E-03 1.39E-04 manganese-54 Ci 8.46E-05 1.02E-04

[ cobalt-58 Ci 4.56E-05 3.53E-05 l cobalt-60 Ci 4.11E-04 7.76E-04

' strontium-89 Ci 2.14E-05 9.49E-05 strontium-90 Ci 1.20E-06 2.29E-06 cesium-134 Ci 1.84E-05 9.66E-06 cesium-137 Ci 2.39E-05 3.21E-05 barium-140 Ci 2.93E-07 1.07E-04

! lanthanum-140 Ci 4.44E-07 1.70E-04 total for period Ci 2.53E-03 1.47E-03

4. TRITIUM

{ hydrogen-3 Ci 6.98E+00 9.63E+00 t

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L TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1995 Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released Unit Otr 3 Otr 4

1. PARTICULATES l cobalt-60 Ci 0.00E+00 2.05E-05 I

cesium-137 Ci 0.00E+00 3.74E-06 total for period Ci 0.00E+00 2.42E-05 9

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TABLE 2A Effluent and Waste Disposal Semiannual Report for Year 1995

' Liquid Effluents - Summation of all Releases j 1

Unit Otr 3 Otr 4 Est Tot

% Error A. FISSION AND ACTIVATION l PRODUCTS Nore t

1. Total release (excluding Ci 5.86E-03 7.95E-03 4.00E+01 ,

tritium, gases, & alpha) i NoTr a 4

2. Avg. diluted conc. uCi/ml 2.87E-10 2.72E-10 l
3. Percent limit  % 8.74E-03 1.21E-02 E2IE 1 I B. TRITIUM l
1. Total release Ci 1.39E+01 1.29E+01 4.50E+01 i E2IE_2
2. Avg. diluted conc. .uCi/ml 6.81E-07 4.40E-07 l
3. Percent limit  % 6.81E-02 4.40E-02 C. DISSOLVED AND ENTRAINED GASES wors1
1. Total release Ci 1.09E-03 3.45E-03 4.00E+01  ;

NOTE 2 i

2. Avg. diluted conc. uCi/ml 5.36E-11 1.18E-10 1
3. Percent limit  % 2.68E-05 5.90E-05 D.' GROSS ALPHA RADIOACTIVITY
1. Total release Ci < LLD < LLD 4.00E+01 E9IE 1 E. VOLUME OF WASTE liters 3.14E+06 4.65E+06 1.50E+01 F. TOTAL OF D1LUTION WATER (used durina release for averace dil. conc.) liters 2.04E+10 2.92E+10 1.30E+01 G. VOLUME OF COOLING WATER -liters 4.90E+11 4.21E+11 DISCHARGED FROM PLANT NOTE 1: Includes radionuclides released via abnormal and/or non-aoutine release.

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

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l TABLE 2B I Effluent and Waste Disposal Semiannual Report for Year 1995 l Liquid Effluents - Batch Mode Nuclides Released Unit Otr 3 Otr 4 i 1. FISSION AND ACTIVATION PRODUCTS I

l sodium-54 Ci 2.74E-06 < LLD l chromium-51 Ci 2.85E-04 1.74E-05

! manganese-54 Ci 2.632-04 3.41E-05  ;

iron-55 Ci < LLD 2.50E-03 i cobalt-58 Ci 3.97E-05 < LLD l cobalt-60 Ci 5.01E-03 4.56E-03 '

zinc-65 Ci < LLD 3.64E-06 i j iodine-131 Ci 1.10E-05 1.33E-04  ;

iodine-133 Ci < LLD 1.20E-04 cesium-134 Ci 1.05E-05 1.07E-06 l cesium-137 C1 2.35E-04 5.84E-04 l

total for period Ci 5.86E-03 7.95E-03 l

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2. DISSOLVED AND ENTRAINED GASES:

Nuclides Released Unit Otr 3 Otr 4

2. GASES xenon-133 Ci 3.02E-04 6.12E-04 xenon-135 Ci 7.90E-04 2.84E-03 total for period Ci 1.09E-03 3.45E-03 i

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APPENDIX A i

! Lower Limits of Detection July through December 1995 l uCi/ml

1. Licuid Releases 2. Gaseous Releases Na-24 2.34E-08 Mn-54 1.44E-08 Kr-87 2.40E-08 Fe-55 5.42E-08 Kr-88 2.45E-08 l Co-58 2.30E-08 Xe-133 i.53E-08 l Fe-59 3.29E-08 Xe-133m 4.33E-08 l Co-60 1.95E-08 Xe-135 5.55E-09 l

Zn-65 4.55E-08 Xe-135m 1.34E-07 L Sr-89 1.98E-08 Xe-137 3.89E-05 Sr-90 1.26E-08 Xe-138 2.49E-07 Mo-99 9.78E-08

, I-131 2.00E-08 l- I-133 1.65E-08 3. Iodines and Particulates j Cs-134 2.13E-08 Cs-137 Mn-54 1.68E-08 4.46E-14 Ce-141 1.44E-08 Co-58 3.09E-14 Ce-144 8.79E-08 Fe-59 1.04E-13 Co-60 4.38E-14 Alpha 9.99E-08 Zn-65 8.23E-14 Kr-87 4.38E-08 Sr-89 2.69E-15  ;

Kr 4.44E-08 Sr-90 1.58E-15 i Xe-133m 1.06E-07 I-131 8.66E-14  !

'Xe-135 1.24E-08 Cs-134 3.53E-14 H Xe-138 1.84E-07 'Cs-137 2.95E-14 l Xe-133 3.76E-08 La-140 7.95E-14 Ce-141 1.76E-14 Ce-144 9.59E-14 Hf-181 3.15E-14 i

i 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 j specified in Technical Specifications.

l 2: Where activity for any nuclide is reported as " Less than j LLD", that nuclide is considered not present and the LLD  ;

4 activity listed is nct considered in summary data. j i

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l TABLE 3A Effluent and Waste Disposal Semiannual Report for Year 1995 '

Solid Waste and Irradiated Fuel Shipments Waste Class A July throuch December  !

1. Total volume shicoed (cubic meters) 0.00E+00 t

Total Curie quantity (estimated) 0.00E+00

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

Units Period  % Error

a. Spent resins, filter sludges meters3 0.00 E0 N/A Curies 0.00 E0
b. Dry active waste, compacted metersa 0.00 E0 N/A and noncompacted Curies 0.00 E0
c. Irradiated components meters3 0.00 EO N/A Curies 0.00 E0
d. Others (describe) meters3 0.00 E0 N/A Curies 0.00 EO
3. Estimate of maior radionuclide composition 1 -
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Solid Radioactive Waste was shipped for processing, however, not for final disposal during the report period. Access to the l burial facility at Barnwell, South Carolina was not available. '

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TABLE 3A (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 shipments

a. Resin Dewatered & Type A/ Type B N/A Solidified *
b. Dry active Compacted /non- N/A N/A 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) N/A
5. Shioment Discosition
a. Solid Waste Number of Shioments Mode of Transportation Destination 0 N/A- N/A
b. Irradiated Fuel Number of Shioments Mode of Transoortation Destination 0 N/A N/A Page 15

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

j Waste Class B July throuch December i

1. Total volume shioned (cubic meters) 0.00 E0 t

Total Curie quantity (estimated) 0.00 E0

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

Units Period t Error

a. Spent resins, filter sludges meters 3 0.00 EO N/A Curies 0.00 E0
b. Dry active waste, compacted, meters' O.00 EO N/A l and noncompacted Curies 0.00 E0 l c. Irradiated components meters' O.00 EO N/A Curies 0.00 E0 l d. Others (describe) meters 0.00 EO N/A l Curies 0.00 E0 l
3. Estimate of maior radionuclide comoosition  ;

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a. N/A
b. N/A ]!
c. N/A
d. N/A l

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Solid Radioactive Waste was shipped for processing, however, not for final disposal during the report period. Access to the burial facility at Barnwell, South Carolina was not available.

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l TABLE 3B (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 shipments
a. Resin Dewatered & Type A/ Type B N/A Solidified *
b. Dry active Compacted /non- N/A N/A waste compacted waste l l
c. Irradiated N/A N/A l components I 1
d. Other N/A N/A
  • Solidification agent or absorbent 1 (e.g., cement, urea formaldehyde) N/A  ;

5.Shioment Discosition

a. Solid Waste Number of Shioments Mode of Transportation Destination 0 N/A N/A
b. Irradiated Fuel Number of Shioments Mode of Transportation Destination 0 N/A N/A l

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TABLE 3C Effluent and Waste Disposal Semiannual Report for Year 1995 Solid Waste and Irradiated Fuel Shipments Waste Class C July throuch December

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

Units Period  % Error

a. Spent resins, filter sludges meters' O.00 E0 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' O.00 EO N/A Curies 0.00 E0
d. Others (describe) meters' O.00 E0 N/A Curies 0.00 EO
3. Estimate of maior radionuclide comoosition
a. N/A
b. N/A
c. N/A
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TABLE 3C (cont.)

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

4. Cross reference table, waste stream, form and container tvDe l

Stream Form Container Type No. of shipments

a. Resin Dewatered & Type A/ Type B 0/0 Solidified *
b. Dry active Compacted /non- N/A 0/0 waste compacted
c. Irradiated N/A 0/0 components
d. Others N/A 0
  • Solidification agent or absorbent (e.g., cement, urea formaldehyde) N/A
5. Shioment Disposition
a. Solid Waste Number of Shioments Mode of Transoortation Destination
b. Irradiated Fuel Number of Shipments Mode of Transportation Destination 4 Rail Car / CP&L/SHNNP l IF-300 Cask Sole Use 1

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O ATTACHMENT 2 (cont.)

ENCLOSURE 2 Combustion of Waste Oil July 1, to December 31, 1995 During this reporting period, approximately 780 gallons of contaminated waste oil were incinerated in the on site oil incinerator. The total activity contained in this quantity of waste oil included 2.0SE-05 curies of Cobalt-60 and 3.74E-06 curies of Cesium-137.

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ATTACHMENT 3 Environmental Monitoring Program July 1, to December 31, 1995 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census l

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ATTACHMENT 3 (cont.)

ENCLOSURE 1 Milk and Vegetation Sample Locations July 1, to December 31, 1995 No milk animals were identified during the last Land Use Census, therefore, no milk sample locations were available during this time period.

Vegetation sample locations remained unchanged.

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l Page 22 l

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9 ATTACHMENT 3 (cont.) l ENCLOSURE 2 Land Use Census July 1, to December 31, 1995 The 1995 Land Use Census was performed during the period of July 12 to July 13, 1995. No locations were identified that are reportable in the Semiannual Radioactive Effluent Release Report.

An update of the Land Use census is included with the ODCM revision 17 in Attachment 8.

1 Page 23 I

ATTACHMENT 4 Effluent Instrumentation July 1, to December 31, 1995 Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation Enclosure 3: Liquid Hold-Up Tanks Page 24

l l ATTACHMENT 4 (cont.)

l 1

l ENCLOSURE 1 l

1 July 1, to December 31, 1995 Radioactive Liquid Effluent Monitoring Instrumentation I

No Radioactive Liquid Effluent Monitoring Instrumentation was

! inoperable for a period greater than 30 days.

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ATTACHMENT 4 (cont.)

ENCLOSURE 2 July 1, to December 31, 1995 Radioactive Gaseous Effluent Monitoring Instrumentation No Radioactive Gaseous Effluent Monitoring Instrumentation was inoperable for a period greater than 30 days.

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Page 26

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. 1 ATTACHMENT 4 (cont.)

ENCLOSURE 3 Liquid Hold-Up Tanks July 1, to December 31, 1995 No liquid hold-up tank exceeded the 10 Ci limit during this reporting period.

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l ATTACHMENT 5 Major Modifications to the Radioactive Waste Treatment System July 1, to December 31, 1995 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 Meteorological Data July 1, to December 31, 1995 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.

Page 29

l <

l ATTACHMENT 7 Annual Dose Assessment January 1, to December 31, 1995 Attached is the annual dose assessment for the Brunswick Steam l

Electric Plant for the time period of January 1 to December 31, 1995.

l l

Enclosure 1: Annual Liquid Dose Assessment Enclosure 2: Annual Gaseous Dose Assessment l Enclosure 3: Dose Assessment Summary l

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l Page 30 I

ATTACHMENT 7 (cont.)

ENCLOSURE 1 Annual Liquid Dose Assessment INCLUDED ARE:

Site Specific Data Source Term As Low As Reasonably Achievable Maximum Individual Dose Summary - Total Integrated and Recreation Population Dose f

Page 31 i

1 BSEP UNITS 1 AND 2 LIQUID RELEASES 1995, DISCHARGE =1.87E+03 CFS SOURCE TERM MUL TIPLIER=1.00E+00 SALTWATER SITE NO RECONCENTRATION MODEL

, 50-MILE POPULATION =2.82E+05 FRACTION --- ADULT =0.71 TEENAGER =0.11 CHILD =0.18 DOSE FACTOR LIBRARY CONTAINS 698 ENTRIES 3

I h

cd b0 i $~

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1 3 E

4 1

9

+

. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ __ _..______._.m-_ ._ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ . _ . _ _ _ . _ _ _ - _ _ _ ________.-_.___m_ __._____.__ _.___ ___ . ..- ._ ____ _ - _ _ ___. _ _ _ _ _ _ . _-_-_w .- .-. v-- w - . _ _ _ _ ___

  • *
  • COST-BENEFIT ANALYSIS * *
  • NUCLIDE I RELEASE I PERSON-REM DOSE l___ PERSON-REM PER CURIE __l l CI/YR 1 TOTAL BODY l THYROID l TOTAL BDDY l THYROID 1 1H 3 1 5.52E+01 1 1.47E-96 l 1.47E-06 l 2.66E-98 1 2.66E-08 l 11NA 24 l 2.74E-06 l 2.03E-10 1 2.03E-10 1 7.40E-05 1 7.40E-05 1 24CR 51 1 6.09E-02 l 2.43E-07 l 2.36E-97 1 3.99E-06 1 3.88E-96 1 25MN 54 l 1.29E-02 1 1.47E-95 1 1.28E-05 1 1.14E-03 l 9.90E-04 l 26FE 55 l 9.94E-03 1 4.49E-06 1 5.34E-12 1 4.51E-04 l 5.36E-10 1 26FE 59 1 1.34E-05 1 4.65E-88 1 2.83E-09 1 3.47E-03 1 2.11E-04 l 27CO 58 l 8.89E-94 l 2.96E-07 l 2.52E-07 1 3.33E-94 l 2.83E-04 l 27CO 60 1 3.21E-01 1 4.93E-03 1 4.88E-03 1 1.54E-02 1 1.52E-02 1 30ZN 65 1 3.64E-06 l 1.90E-98 l 1.95E-09 I 5.21E-03 1 5.36E-94 I i

30ZN 69M i 1.31E-06 l 9.43E-12 1 9.43E-12 1 7.20E-06 1 7.20E-96 1 36KR 85M l 1.76E-05 1 0.99E+00 1 9.90E+00 1 0.00E+00 1 0.90E+00 1 41NB 95 1 2.55E-06 1 3.14E-10 1 2.77E-10 1 1.23E-04 l 1.09E-04 1 43TC 99M i 3.85E-05 1 8.26E-11 1 8.26E-11 1 2.15E-06 1 2.15E-06 1 53I 131 1 1.78E-94 1 4.13E-99 l 4.59E-07 l 2.32E-05 1 2.58E-03 I

. 53I 133 1 1.36E-94 l 1.33E-99 l 1.39E-09 l 9.88E-06 l 1.02E-05 1 54XE 133 l 1.06E-03 1 0.90E+00 1 0.09E+99 1 0.00E+00 1 0.99E+99 l 54XE 133M i 1.12E-04 1 9.00E+00 1 0.00E+00 1 0.00E+00 1 0.00E+00 1 54XE 135 1 4.96E-03 1 0290E+00 1 0.09E+08 1 0.00E+00 1 0.00E+00 1 54XE 135M i 1.79E-05 l 9.90E+00 1 0.00E+99 1 0.09E+00 1 0.00E+09 l 55Cs 134 1 2.02E-03 l 1.22E-05 l 9.80E-06 1 6.06E-03 1 4.85E-03 l g 55CS 137 l 9.46E-03 1 7.57E-05 l 6.89E-05 1 8.90E-03 1 7.29E-03 l en 4 72HF 181 1 2.19E-04 1 3.27E-98 1 3.22E-08 l 1.49E-04 l 1.47E-04 l F1 g 95AM 241 1 1.30E-05 l 1.05E-88 1 4.74E-09 1 8.88E-94 1 3.65E-04 l g y TOTAL 5.94E-03 4.98E-03 $$

b e

e

_ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ - _ - - _ _ _ _ _ _ - _ . _ _ _ . _ - _ _ _ _ . _ _ _ _ _ _ _ _ ________.__.____m _ - -= e n% __- _ _ _ _ _ _ _

t i

  • *
  • AS LOW AS REASONABLY ACHIEVABLE * *
  • ADULT D0SES (MREM PER YEAR INTAKE)

DOSE PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 6.87E-95 1.27E-94 1.25E-94 5.96E-96 1.92E-95 2.51E-05 8.46E-04 i o INVERT 8.47E-95 1.67E-94 2.39E-94 3.39E-96 4.51E-96 3.22E-95 1.94E-93

m SHDRELINE 5.41E-93 4.69E-93 4.69E-93 4.69E-93 4.69E-03 4.69E-93 4.69E-93 4.69E-93 d$ SWIMMING 3.93E-06 3.93E-96 3.93E-96 3.93E-06 3.03E-06 3.93E-06 3.03E-96 i BOATING 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-06 1.52E-96

]jTOTAL 5.41E-93 4.75E-03 4.89E-03 4.96E-93 4.61E-93 4.62E-93 4.66E-93 7.39E-93 p

3> FISH USAGE (MG/YR,HR/YR) 29.2 DILUTION 39.9 TIME (HR) 24.99 SHOREWIDTH FACTOR =9.5 "y INVERT 7.3 39.9 24.99 H

c SHORELINE 599.9 39.9 9.99 SWIMMING 199.9 30.9 9.99 g BDATING 199.9 39.9 9.99 M TEEN D0SES (MREM PER YEAR INTAKE)

N x DOSE s ..

J4 PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Yb Q FISH 9.48E-95 1.79E-94 1.54E-94 5.55E-96 2.47E-95 3.83E-95 7.71E-94 as 2.24E-94 3.89E-96 5.52E-96 5.12E-95 1.77E-03 W

> INVERT 1.16E-94 3.29E-94

  • SHORELINE 5.41E-93 4.6BE-93 4.69E-93 4.69E-93 4.69E-93 4.69E-93 4.69E-93 4.69E-93 $

4 SWIMMING 3.93E-96 3.93E-96 3.93E-96 3.93E-96 3.03E-96 3.93E-96 3.93E-96 jfBOATING 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-06 1.52E-96

! TOTAL 5.41E-93 4.81E-93 4.99E-93 5.07E-03 4.61E-93 4.63E-93 4.69E-93 7.14E-93 i  ?

,o USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR =0.5

$ FISH 29.2 39.9 24.99 o INVERT 7.3 30.0 24.99 1 y SHORELINE 599.9 39.9 9.99 e SWIMMING 199.9 39.9 9.99 N BOATING 199.9 39.9 9.99 0 GHILD D0SES (MREM PER YEAR INTAKE) j DOSE ,.

jjPATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI l

, FISH 2.84E-94 3.44E-94 3.58E-94 1.19E-95 4.67E-95 7.64E-95 6.21E-94

' INVERT 3.59E-94 4.52E-94 7.94E-94 9.93E-96 1.99E-95 1.94E-94 1.42E-93 l SHDRELINE 5.41E-93 4.69E-93 4.69E-93 4.69E-93 4.69E-03 4.69E-03 4.69E-93 4.69E-93 SWIMMING 3.93E-06 3.03E-06 3.93E-96 3.93E-06 3.93E-96 3.93E-96 3.93E-06

, BOATING 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-96

, TOTAL 5.41E-93 5.23E-93 5.40E-03 5.75E-93 4.62E-93 4.66E-93 4.78E-93 6.65E-93 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIPTH FACTOR =0.5 FISH 29.2 39.9 24.99 INVERT 7.3 39.9 24.99

SHORELINE 599.9 30.9 9.99 SWIMMING 199.9 39.9 9.99 BOATING 199.9 30.9 9.99

--.--,vm s _ . _ - _

CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 LADTAP RADIATION DOSES FROM LIQUID EFFLUENTS- RUN TIME: 10:42:22 i

TOTAL INTEGRATED AND RECREATION POPULATION DOSES FROM LIQUID EFFLUENTS (PERSON-REM)

PATHWAY BONE LIVER TOTAL 800Y THYROID KIDNEY LtNG GI-LLI SKIN SPORT FISH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+09 0.OOGE+00 0.000E+00 A

n COM FISH 3.859E-05 6.538E-05 6.447E-05 1.919E-06 9.707E-06 1.341E-05 3.700E-04 0.000E+00 o

$os SPORT INVERT 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 g COM INVERT 7.834E-07 1.419E-06 2.114E-06 1.559E-08 3.669E-08 2.878E-07 1.395E-05 0.000E+00 A.

M DRINKING WATER 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 i

$ SHORELINE 4.963E-03 4.963E-03 4.963E-03 4.963E-03 4.963E-03 4.963E-03 4.963E-03 5.838E-03 o

SWD#4ING 8.645E-06 8.645E-06 8.645E-06 8.645E-06 8.645E-06 8.645E-06 8.645E-06 0.000E+00 $

A

. o

$ BOATING 4.095E-06 4.095E-06 4.095E-06 4.095E-06 4.095E-06 4.095E-06 4.095E-06 0.000E+00 IRRI VEG 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 e

@ IRRI LEAFY VEG O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 y IRRI MILK 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 e

(

IRRI HEAT 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+06 0.000E+00 0.000E+00 4

ALL PATHWAYS 5.015E-03 5.043E-03 ~5.043E-03 4.978E-03 4.986E-03 4.990E 5.360E-03 5.838E-03

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l ATTACHMENT 7 (cont)

ENCLOSURE 2 Annual Gaseous Dose Assessment l

INCLUDED ARE:

, Source term for the three release modes and the site aggregate.

Total 50 mile Integrated Population Dose by pathways and organs.

Hypothetical maximum individual organ dose due to Iodines, Particulates, and Tritium for a cow milk pathway at 4.75 miles Northeast.

l Maximum site boundary dose by age group and organs for all pathways.

i Estimated individual organ dose using the 1995 Land Use Census for the worst sector and existing pathways.

Maximum site boundary dose due to Iodines, Particulates, and

- Tritium for existing pathways.

Source term for incinerated waste oil.

Integrated Population Dose by pathways and organs due to incinerated waste oil.

Maximum site boundary dose due to incinerated waste oil.

I i

4 Page 36

.- - - - _. _ _ _ _ _ _ . . _ _ ,._ _ - _ = - - - - _ - - _ _ _ _ _ - _ - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . _ _ _ - - _ _

I CPCL SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 GASRPT INPUT SOURCE TERMS RUN TIME: 08:18:42 1995 SOURCE TERM (ELEVATED MODE) BSEP UNITS 142 SOURCE TERM (GROUND LEVEL) 1995 BSEP UNITS 1 AND 2 1H- 3 1.010E+01 1H- 3 2.010E+01 18 AR- 41 4.250E+00 24 CR- 51 9.580E-07 24 CR- 51 3.030E-04 25 MN- 54 2.699E-09 o 25 MN- 54 1.860E-05 27 CD- 60 1.040E-OS

$to 27 CD- 58 1.980E-06 36 KR- 85 M 1.610E+00

, 27 CD- 60 5.680E-05 36 KR- 87 1.470E-01 4

  • 36 KR- 85 M 3.910E+02 36 KR- 88 2.390E+00 et 36 KR- 87 3.850E+02 38 SR- 89 6.910E-05

$f 36 KR- 88 6.910E+02 38 SR- 90 3.888E-07 38 SR- 89 1.930E-04 53 I -131 1.780E-04

$ 3S SR- 90 1.430E-06 53 I -132 5.170E-04

  • 53 I -131 3.410E-03 53 I -133 3.840E-04

" 8.130E-03 53 I -134 3.810E-04 53 I -132 o 53 I -133 1.090E-02 53 I -135 4.099E-04 53 I -135 1.100E-02 54 XE-133 3.970E+00

'S 54 XE-135 8.929E+ee J 54 XE-133 1.430E+03 54 XE-135 1.110E+03 55 CS-137 2.360E-08

. 'E 56 BA-140 4.350E-06 j af 54 XE-135 M 7.670E+01 m 54 XE-137 5.368E+00 57 LA-148 6.470E-06 j'

o 54 XE-138 1.860E+92 55 CS-137 2.200E-06 e

'8 AGGREGATE SOURCE TERM m H 56 BA-140 1.600E-04 1.940E-04 e e 57 LA-140 1H- 3 3.6468E+01 to m 72 HF-181 1.820E-06 y 18 AR- 41 4.2500E+00 $

H BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1995 24 CR- 51 1.3004E-02 j

e 25 MN- 54 1.2886E-03 26 FE- 59 3.1500E-04 1H- 3 6.250E+00 27 CO- 58 7.1398E-04

$ 27 CO- 60 5.0272E-03 b 24 CR- 51 1.270E-02 36 KR- 85 M 4

25 MN- 54 1.270E-03 3.9275E+02

-$ 36 KR- 87 3.8515E+02 1 26 FE- 59 3.150E-04 36 KR- 88

,0 27 CD- 58 7.120E-04 6.9339E+02 38 SR- 89 l

27 CD- 60 4.960E-03 3.2610E-04

+'. 36 KR- 85 M 1.420E-01 38 SR- 90 6.2188E-06 s.

o 38 SR- 89 6.400E-05 41 NS- 95 6.1000E-05

" 38 SR- 90 4.400E-06 44 RU-103 5.0100E-04 G 41 NS- 95 6.100E-05 44 RU-106 3.1800E-04

$ 44 RU-103 5.010E-04 53 I -131 5.3088E-03 o' 53 I -132 1.9247E-Oe 44 RU-106 3.180E-04 53 I -131 1.729E-03 53 I -133 2.1784E-92 e 53 I -134 3.8100E-94 o 53 I -132 1.968E-02 53 I -135 1.958E-92 2.2809E-82

$ 53 I -133 54 XE-133 1.4348E+03 o 53 I -135 1.1%E-92 54 XE-135 54 XE-133 8.529E-91 1.1393E+03 54 XE-135 1.149E+91 54 XE-135 M 8.1629E+01 4.320E+00 54 XE-137 5.3699E+98 54 XE-135 M 54 XE-138

! 55 CS-134 2.819E-95 1.8600E+92 5.818E-95 55 CS-134 2.8190E-05 55 CS-137 55 CS-137 6.9324E-OS 56 BA-148 1.95eE-94 2.6935E-04 57 LA-148 1.679E-04 56 BA-149 72 HF-181 9.300E-96 57 LA-148 3.6747E-04 95 AM-241 1.129E-93 72 HF-181 1.1120E-05 95 AM-241 1.1296E-05 L

CP&L SEMI-ANNUAL RADIDLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 GASRPT ALARA ANNUAL INTEGRATED POPULATION DOSE

SUMMARY

(MANREM) RUN TIME: 08:18:42 1995 SOURCE TERM (ELEVATED MDDE) BSEP UNITS 162 SOURCE TERM (GROUND LEVEL) 1995 BSEP UNITS 1 AND 2 BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1995 E

d TOTAL BDDY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN N GO TOTAL ** 1.629E-01 1.636E-01 1.590E-01 1.658E-01 1.640E-01 1.726E-01 1.662E-01 3.364E-01 o

e PLUME 1.410E-01 1.410E-01 1.410E-01 1.410E-01 1.410E-01 1.410E-01 1.431E-01 3.126E-01

@ 86.575 86.185 88.665 85.065 85.965 81.685 86.125 92,915 Q GROUND PLANE 1.301E-02 1.301E-02 1.301E-02 1.301E-02 1.301E-02 1.301E-02 1.301E-02 1.530E-02 g 7.995 7.955 8.185 7.855 7.935 7.545 7.835 4.555 N INHALATION 6.664E-03 6.541E-03 4.688E-03 9.576E-03 7.864E-03 1.078E-02 7.971E-03 6.461E-03 gl 4.095 4.005 2.955 5.785 4.795 6.245 4.805 1.925 h VEGETATION 1.987E-03 2.327E-03 3.260E-04 1.965E-03 1.926E-03 7.144E-03 1.881E-03 1.877E-03 1.225 1.425 0.215 1.195 1.175 4.145 1.135 0.565 COW MILK 5.294E-05 5.308E-05 2.872E-06 5.389E-05 5.3SOE-05 4.263E-G4 5.160E-05 5.146E-05 ao A 0.035 0.035 e.005 0.035 0.035 0.255 0.035 0.025 "1 a o O MEAT k POULTRY 1.649E-04 6.747E-04 1.229E-05 1.607E-04 1.718E-04 2.652E-S4 1.550E-04 1.545E-04 W 5 0.105 0.415 0.015 0.105 0.105 0.155 0.095 0.055 53 ii

'8 t

b 3

E il Pn a

b e

_ _ _ _ _ _ _ _ _ . _ _ . _ ~ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _

I

! a CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 g CASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 08:18:42 e

l $. 1995 SDURCE TERM (ELEVATED MODE) BSEP UNITS 162 1 o SOURCE TERM (GROUND LEVEL) 1995 BSEP UNITS 1 AND 2 Z BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1995 a

y SPECIAL LOCATION METERS DIR PL GR IN V CM GM M

= #35 COW MILK 7644.0 NE O 1 1 1 1 0 0 cc a ANNUAL BETA AIR DOSE = 9.368E-06 MILLRADS

$ ANNUAL GAM 4A AIR DOSE = 2.656E-05 MRLRADS e

j TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN y ADULT 1.364E-03 1.494E-03 1.038E-03 1.449E-03 1.389E-83 4.834E-03 1.361E-03 1.464E-03 5 GROUND PLANE 8.135E-94 8.135E-04 8.135E-04 8.135E-94 8.135E-94 8.135E-04 8.135E-94 9.570E-04

$ INHALATION 1.543E-04 1.510E-04 1.383E-94 2.414E-94 1.907E-94 2.592E-94 1.876E-94 1.484E-94 A VEGETATION 2.963E-04 4.261E-04 7.213E-05 2.896E-94 2.784E-94 1.963E-03 2.688E-94 2.679E-04

. COW MILK 1.002E-04 1.031E-04 1.404E-05 1.843E-04 1.963E-04 2.698E-03 9.103E-05 9.944E-05 TEENAGER 1.445E-03 1.572E-03 1.082E-03 1.541E-03 1.473E-03 6.323E-03 1.449E-03 1.531E-03

'8 GROUND PLANE 8.135E-04 8.135E 8.135E-04 8.135E-94 8.135E-04 8.135E-04 8.135E-04 9.570E-04 os M

H INHALATION 1.557E-04 1.519E-04 1.459E-04 2.484E-04 1.944E-04 2.923E-94 2.088E-04 1.494E-04 o VEGETATION 3.439E-04 4.735E-94 9.826E-05 3.365E-04 3.193E-04 9.675E-04 3.082E-94 3.968E-04 o o COW MILK 1.314E-04 1.332E-94 2.482E-05 1.423E-04 1.460E-04 4.250E-03 1.190E-84 1.178E-04 y e A

s CHILD 1.700E-03 1.732E-03 1.184E-03 1.764E-03 1.701E-03 1.099E-02 1.669E-03 1.750E-03 e

ca GROUND PLANE 8.135E-04 8.135E-94 8.135E-04 8.135E-04 8.135E-94 8.135E-04 8.135E-04 9.579E-04 8 INHALATION 1.374E-04 1.332E-04 1.138E-94 2.026E-04 1.624E-04 3.047E-04 1.814E-94 1.321E-04 e VEGETATION 5.413E-04 5.879E-04 1.980E-04 5.197E-04 4.924E-94 1.485E-03 4.773E-94 4.751E-04 g COW MILK 2.079E-04 1.970E-04 5.847E-05 2.281E-04 2.328E-94 8.392E-03 1.879E-04 1.861E-04 e

$ INFANT 1.211E-03 1.182E-03 9.681E-04 1.295E-03 1.265E-93 2.127E-02 1.209E-03 1.315E-03 o

GROUND PLANE 8.135E-04 8.135E-04 8.135E-04 8.135E-04 8.135E-94 8.135E-04 8.135E-04 9.570E-94 Y INHALATION 7.820E-05 7.636E-05 4.605E-05 1.047E-04 8.826E-95 2.338E-04 1.097E-04 7.596E-05 y COW MILK 3.194E-04 2.924E-04 1.085E-04 3.764E-04 3.629E-04 2.022E-02 2.857E-04 2.824E-04 1:

c Ro g**

E h 992 il 5 t'

- Ee 8n.

322 25 11 h! E

d 4 u__._____._.____.__.___________._______________._.___.__m___._______.-_.____.__..__________-.______m.__ _______________.__._.______._________..___________.__________________m ,w - w v ___m -_ _ _ _ _ _ _

CP&L SEMI-ANNUAL RADIDLOGICAL EFFLUENT REPORTING RUN DATE: 02/13/96 CASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 13:27:55 1995 SOURCE TERM (ELEVATED MODE) BSEP UNITS 162

! SOURCE TERM (GROUND LEVEL) 1995 BSEP UNITS 1 AND 2 i

BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1995 l

m SPECIAL LOCATION METERS DIR PL GR IN Y CM GM M g # 3 SITE BOUMDARY 1127.0 NE 1 1 1 1 1 1 1

.:: ANNUAL BETA AIR DOSE = 2.348E-02 MILLRADS

, N ANNUAL GAMMA AIR DOSE = 3.514E-02 MILLRADS A.

r4 TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN ej ADULT 4.874E-02 5.390E-02 3.567E-02 4.888E-02 4.875E-02 1.418E-01 4.828E-02 7.139E-02 b PLUME 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.379E-02 4.529E-02

, O GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 INHALATION 2.963E-03 2.961E-03 2.262E-04 3.102E-03 3.023E-03 3.486E-03 , 3.031E-03 2.953E-03

$ VEGETATION 5.714E-03 7.295E-03 1.398E-03 5.595E-03 5.464E-03 1.656E-02 5.340E-03 5.330E-03 d COW MILK 1.928E-03 1.963E-03 2.243E-94 1.983E-03 2.019E-03 3.869E-02 1.806E-03 1.799E-03

$ GOAT MILK 3.898E-03 3.757E-03 4.297E-84 3.992E-03 3.970E-03 4.794E-02 3.690E-03 3.670E-03 o MEAT & POULTRY 8.304E-94 4.519E-03 7.873E-05 8.064E-84 8.726E-B4 1.745E-03 7.695E-94 7.660E-84 E TEENAGER 5.109E-02 5.475E-02 3.668E-02 5.150E-02 5.130E-02 1.894E-01 5.049E-02 7.353E-02 PLUME 2.355E-02 2.355E-02 2.355E-e2 2.355E-02 2.355E-02 2.355E-02 2.379E-02 4.529E-02 5 GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 e b INHALATION 2.983 E-03 2.980E-03 2.490E-94 3.131E-03 3.047E-03 3.653E-03 3.093E-03 2.971E-03 o0

' W VEGETATION 6.604E-03 8.177E-03 1.814E-03 6.465E-03 6.260E-03 1.544E-02 6.119E-03 6.192E-03 $

' o COW MILK 2.528E-03 2.545E-03 3.975E-04 2.668E-03 2.135E-03 6.080E-02 2.358E-03 2.343E-03 y GOAT MILK 5.065E-03 4.896E-03 7.590E-94 5.346E-03 5.313E-03 7.492E-02 4.821E-03 4.780E-03 MEAT 4 POULTRY. 5.065E-94 2.748E-03 6.467E-05 4.887E-04 5.455E-04 1.166E-03 4.601E-04 4.570E-94 CHILD 5.897E-02 6.030E-02 4.021E-02 5.951E-02 5.920E-02 3.287E-01 5.774E-02 8.076E-02 o PLUME 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.379E-02 4.529E-02

, D GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03, 9.853E-03 9.453E-03 1.159E-02 g INHALATION 2.637E-03 2.631E-03 1.905E-64 2.742E-03 2.6800-03 3.440E 2.729E-03 2.628E-03 e VEGETATION 1.035E-02 1.086E-02 3.769E-03 9.993E-03 9.669E-03 2.370E-02 9.477E-03 9.451E-03 o CDW MILK 4.003E-03 3.846E-03 9.398E-04 4.260E-03 4.352E-03 1.197E-01 3.724E-03 3.702E-03

$ GOAT MILK 7.946E-03 7.644E-03 1.788E-03 8.522E-03 8.434E-03 1.468E-01 7.615E-03 7.553E-03 jg MEAT & POULTRY 6.284E-94 1.917E-03 1.185E-04 5.908E-04 6.681E-04 1.622E-03 5.555E-94 5.520E-94 y INFANT 5.314E-02 5.221E-02 3.846E-02 5.538E-02 5.464E-02 6.731E-01 5.245E-02 7.546E-02 i i N PLUME 2.355E-02 2.355E-?? 2.355E-02 2.355E-02 2.355E-02 2.355E-02 2.379E-02 4.529E-02 g GROUNO PLANE 9.853E-03 9.853L-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 g INHALATION 1.516E-03 1.512E-03 7.894E-05 1.559E-03 1.533E-03 2.253E-03 1.584E-03 1.511E-03 g COW MILK 6.133E-03 5.750E-03 1.752E-03 6.878E-03 6.738E-03 2.876E-01 5.657E-03 5.617E-03

, g GOAT MILK 1.209E-02 1.155E-02 3.223E-03 1.354E-02 1.297E-02 3.499E-01 1.157E-02 1.146E-02 x

D

_ . _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ . _ _ _ . . _ _ _ _ _ . . _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ __.__.ere-we e h%-wm_____ _ _ _

CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/13/96 g GASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 13:27:55 E 1995 SOURCE TERM (ELEVATED MDDE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 1995 BSEP UNITS 1 AND 2

$ BRUNSWICK UNITS 1 AND 2, MIXED MDDE CONTINUOUS GASEOUS RELEASES, 1995 L

$ SPECIAL LOCATION METERS DIR PL GR IN V CM GM M g #24 RESIDENCE 1609.0 SW 1 1 1 1 0 0 0

.c 9 ANNUAL BETA AIR DOSE = 1.761E-02 MILLRADS ANNUAL GAMMA AIR DOSE = 2.627E-02 MILLRADS

" TOTAL BDDY GI-TRACT LIVER KIDNEY BONE THYROID LUNG SKIN e ADULT 2.878E-02 2.970E-02 2.413E-02 2.879E-02 2.867E-02 3.466E-02 2.879E-02 4.585E-02 n

C PLUME 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.778E-02 3.388E-02

$ GROUND PLANE 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 6.765E-03 INHALATION 1.862E-03 1.861E-03 1.171E-04 1.934E-03 1.893E-03 2.199E-03 1.899E-03 1.857E-03

$ VEGETATION 3.565E-03 4.486E-03 6.604E-04 3.504E-03 3.426E-03 9.114E-03 3.357E-03 3.351E-03

=

23 TEENAGER 2.934E-02 3.026E-02 2.439E-02 2.935E-02 2.918E-02 3.428E-02 2.931E-02 4.635E-02 a a as j PLUME 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.778E-02 3.388E-02 o GR1UND PLANE 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 6.765E-63 y ER INHALATION 1.875E-03 1.873E-03 1.244E-04 1.951E-03 1.908E-03 2.306E-03 1.934E-03 1.869E-03 04 CN VEGETATION 4.117E-03 5.035E-03 9.117E-04 4.047E-03 3.926E-03 8.625E-03 3.847E-03 3.837E-03 a

jg CHILD 3.145E-02 3.176E-02 2.533E-02 3.132E-02 3.110E-02 3.878E-02 3.120E-02 4.824E-02 PLUME 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.778E-02 3.388E-02

@ GROUND PLANE 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 S.750E-03 5.750E-03 6.765E-03

-4 INHALATION 1.658E-03 1.655E-03 9.918E-05 1.711E-03 1.680E-01 2.173E-03 f.707E-03 1.652E-03 y VEGETATION 6.443E-03 6.755E-03 1.878E-03 6.257E-03 6.066E-04 1.326E-02 5.958E-03 5.943E-03 INFANT 2.430E-02 2.430E-02 2.339E-02 2.433E-02 2.431E-02 2.478E-02 2.452E-02 4.159E-02 D PLUME 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.760E-02 1.778E-02 3.388E-02 c GROUND PLANE 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 5.750E-03 6.755E-03

$ INHALATION 9.527E-04 9.510E-04 4.136E-05 9.752E-04 9.620E-04 1.426E-03 9.902E-04 9.501E-04 8

m H km 35

> d a w s a

$U 23 m =

N d 6

s--__ _ . _ _ _ _ _ _ . . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . _ . _ _ . _ . . _ . . . _ . __ _ . _ _ _ _ _ . _ _ _ _ _ _ _

i CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 GASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 08:18:42 N 1995 SOURCE TERM (ELEVATED MODE) BSEP UNITS 162 g SOURCE TERM (GROUND LEVEL) 1995 BSEP UNITS 1 AND 2 e BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1995 5e SPECIAL LOCATION METERS DIR PL GR IN V CM GM M p # 3 SITE BOUNDARY 1127.0 NE O 1 1 0 0 0 0 0

% ANNUAL BETA AIR DOSE = 2.248E-05 MILLRADS

.g ANNUAL GAM 4A AIR DOSE = 6.375E-05 MILLRADS M TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN t ADULT 1.282E-02 1.281E-02 1.008E-02 1.296E-02 1.288E-02 1.334E-02 1.288E-02 1.454E-02 E1 e GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 c: INHALATION 2.963E-03 2.961E-03 2.262E-04 3.102E-03 3.023E-03 3.486E-03 3.031E-03 2.953E-03 d

. TEENAGER 1.284E-02 1.283E-02 1.009E-02 1.298E-02 1.290E-02 1.351E-02 1.295E-02 1.456E-02 m

$ GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 m 4

$:s INHALATION 2.983E-03 2.980E-03 2.400E-04 3.131E-03 3.047E-03 3.653E-03 3.093E-03 2.971E-03 d>

0 CHILD 1.249E-02 1.248E-02 1.004E-02 1.259E-02 1.253E-02 1.329E-02 1.258E-02 1.422E-02 y 4

o c, y GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 p., INHALATION 2.637E-03 2.631E-03 1.905E-04 2.742E-03 2.680E-03 3.440E-03 2.729E-03 2.628E-03 d INFANT 1.137E-02 1.137E-02 9.932E-03 1.141E-02 1.139E-02 1.211E-02 1.144E-02 1.310E-02 GROUND PLANE 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 9.853E-03 1.159E-02 INHALATION 1.516E-03 1.512E-03 7.894E-05 1.559E-03 1.333E-03 2.253E-03 1.584E-03 1.511E-03 0

8 e

e b

a 8

8 i

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f -

i

i CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 CASRPT INPUT SOURCE TERMS RUN TIME: 09:24:03 SOURCE TERM (INCINRAT OTL) 1995 BSEP UNITS 1 AND 2 27 co- 68 2.950E-05 55 cs-137 3.740E-06 NO N 2

? e E E' m

u 8

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m___________ . _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ - _ _ . _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ . _

.___.____.___-______,.._e..m______.

Integrated population dose by pathways and ,orgqps due t% inc&neratedevastemo110o >m m o m 2 3 r o O MF

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CP&L SEMI-ANNUAL RADIDLOGICAL EFFLUENT REPORTING RUN DATE: 02/14/96 GASRPT RADIATION DOSES AT SELECTED LDCATIONS RUN TIME: 09:24:03 SOURCE TERM (INCINRAT DIL) 1995 BSEP UNITS 1 AND 2 SPECIAL LOCATION METERS DIR PL GR IN V CM CM M

  1. 3 SITE BOUNDARY 1127.0 NE 1 1 1 1 0 0 0 ANNUAL BETA AIR DOSE = 0.000E+00 MILLRADS ANNUAL GAMMA AIR DOSE = 0.000E+00 MILLRADS TOTAL B00Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN ADULT 3.612E-04 3.842E-04 3.580E-04 3.664E-04 3.490E-04 3.412E-04 3.564E-04 4.011E-04 e-t e GROUND PLANE 3.412E-94 3.412E-04 3.412E-04 3.412E-04 3.412E-04 3.412E-04 3.412E-04 4.011E-04 INHALATION 1.957E-07 6.034E-07 1.839E-07 2.629E-07 8.550E-08 0.000E+00 1.261E-05 0.000E+00 j; VEGETATION 1.978E-05 4.239E-05 1.658E-05 2.491E-05 7.699E-96 0.000Et00 2.559E-06 0.000E+00 1 TEENAGER 3.611E-04 3.855E-04 3.679E-04 3.801E-04 3.533E-64 3.412E-04 3.643E-04 4.011E-04 e GROUND PLANE 3.412E-04 3.412E-B4 3.412E-04 3.412E-04 3.412E-94 3.412E-04 3.412E-04 4.011E-04 j$ INHALATION 1.615E-07 5.495E-07 2.577E-07 3.579E-07 1.169E-07 0.000E+00 1.842E-05 0.000E+00 g VEGETATION 1.973E-05 4.376E-05 2.643E-05 3.848E-05 1.196E-05 0.000E+00 4.648E-06 0.000E+00 b CHILD 3.650E-04 3.698E-04 4.040E-04 4.063E-04 3.688E-84 3.412E-04 3.632E-04 4.011E-84 IS E o c GROUND PLANE 3.412E-04 3.412E-04 3.412E-04 3.412E-04 3.412E-04 3.412E-04 3.412E-04 4.011E-04 60

INHALATION 9.708E-08 2.041E-07 3.485E-07 3.449E-07 1.085E-07 0.000E+00 1.493E-05 0.000E+00 $

o VEGETATION 2.372E-05 2.837E-05 6.240E-05 6.478E-05 1.946E-05 0.000E+00 7.003E-06 0.000E+BO g INFANT 3.4'3E-04 3.413E-04 3.414E-04 3.415E-04 3.413E-04 3.412E-04 3.507E-04 4.011E-04 GRIUND PLANE 3.412E-04 3.412E-04 3.412E-04 3.412E-04 3.412E-B4 3.412E-04 3.412E-04 4.011E-04

$ INHALATION 4.230E-08 6.778E-08 2.110E-07 2.521E-07 6.620E-08 0.000E+00 9.527E-06 0.000E+00 O

b 5

s 5

.O

?

2 S

S s

x a

.__. . . . _ _ _ _ _ _ . . _ m . . _ _ -...__ . _ . . . __ _ .m ____.___._____ _. .- .._.._.__

l

! ATTACHMENT 7 (cont) .

ENCLOSURE 3 Dose Assessment Summary i

l I. Liquid Effluents:  !

Maximum Dose to' Individual: (mrem) Limit: (mrem) 1 Adult GI-LLI 7.39E-03 2.00E+01 l Child Total Body 5.75E-03 6.00E+00 [

1 Total Intearated and Recreation Poculation Dose: (cerson-rem) '

l Total Body 5.04E-03 l :II . Gaseous Effluents:

i Noble Gas Air Dose at Site Boundarv: (mrad) Limit: (mrad) .;

Gamma 3.51E-02 2.00E+01 i

l Beta 2.35E-02 4.00E+01  ;

I l Iodine-131. Iodine 133. Tritium and Particulates: (mrem) Limit: 3.00E+01 Maximum hypothetical dose at 6.73E-01 l j site boundary: (infant thyroid) i Maximum hypothetical dose due to iodines, particulates, and 3.14E-02 l tritium at 4.75 miles for the (infant thyroid) cow milk pathway per ODCM-l Estimated organ dose due i to iodines, particulates, and 2.11E-02 tritium for existing pathways (child thyroid) to maximum exposed individual.

Total 50 mile Annual Intecrated Pooulation Dose: (oerson-rem)

Total Body: 1.63E-01 I

) Thyroid: 1.73E-01 i

s Page 46

l I

ATTACHMENT 8 Off-Site Dose Calculation Manual (ODCM) and l

Process Control Program (PCP) Revisions l 1

July 1, to December 31, 1995 Brunswick Steam Electric Plant There were no revisions made to the Process Control Program l during this reporting period. I I

Revision 17 was made to the Off-Site Dose Calculation Manual during this time period to update Table 3.2-2 to concur with the latest Land Use Census Data. (page 3-30)

A copy of Revision 17 to the ODCM is included as a part of this attachment.

l 1

Page 47 l

l r

G E O _ .'. ._ O J.?

ATTACHMENT 1  !!U3 :.22:I.23 MGI ,

Page 1 of 1 o-Request for Off Site Dose Calculation Manual Chande' ! l 0 6 C C 0 0 Originator: Va Ak CL CPY Date: f)eb 9 ICM 1 Rev. /7 O 1 Pages and Sections Revised: M 3-3O I J i l

l Reason for Change: TO ( toe 3, 2 -2 hod i OD l {lR hehtNAo DO A.

Safety Analysis Complete: . I Date: /o/9 /ff" REVIEWS: i d el - /Recomme@Not Recommended Date: ttr/9/FJ  :

1st Sefety Rev,i ewer  !

ot Recommended Date: 10 27-9 [

2nd Safety Reviewer mendht Recommended Date: /* /MO' E&C Specialist I hommendM/Not Recommended Date: #-2-V  !

raffons Support o# rnavir niended ecommended Date: /6 95 l

[ E&C Managef / [/ '

/

I APPRO ALS:

/ attar 1 MmendMot Recommended Date: //hhi

' nag C- J

-}&RC N. yr Mmendpot Recommended Date:/M/Y/k PhSD Cli pn M [' -

@ecommendepot Recommended Date: /Y/I/h Manager 46nt Genela{

OE&RC-4261 Rev.2 Page 7 of 8 Page 48

d i

ATTACHMENT 2 Page 55 Of 69 10 CFR50,59 Program Manual Rev. 3 ATTACHMENT A **

CP&L SAFETY REVIEW PACKAGE Pagelof d SAFETY REVIEW COVER SHEET DOCUMENT NO. O DCM REV.NO. O DESCRIPTION OR TITLE: c. M +

  • c hw CWuW4m h"\e vd
1. Assigned Responsibilities:

Safety Analysis Preparer: G c e V hk (~

Lead 1st Safety Reviewer: (scu W k h (~

2nd Safety Reviewer: Teeoc 2aeAer

2. Safety Analyoss Preparer: Complete AftT I, S TY ANALYSIS Safety Analysis Preparer

~

SIGNATURE f (Of9 fif DATE

3. Lead 1st Safety Reviewer: Complete Part 11, item Classrfication.

j

4. Lead 1st Safety Reviewer: Part til may be completed if either question 1 or 2 is *yes,' tien Part IV is not recured.
5. Lead tot Safety Reviewer: Determme which DISCIPLINES are required for review of this item (including own) and mark the appropriate blockts) below.

DISCIPLINES Recuered (Print Name) Sienature/Date (Stoo 71

() Nuclear Plant Operations

[] Nuclear Engineering

[] Mechanical II Electrical 11 Instrumentation & Control

[] Structural _

(1 Metallurgy

.Jtthemistry/Rediochemistry Cst e t k V i b Wld%I

[] Health Physics

[] Admmistrative Controla

6. A QUALIFIED SAFETY REVIEWER will be assigned for each DISCIPLINE marked in step 5 and f Mwr imme pr!ated in the space provided. Each person listed shall perform a SAFETY REVIEW and provide input into the Safety heview Package.
7. The Lead t ot Safety Reviewer will assure that a Part lit or Part IV is completed (see stop 4 above) and a Part VI if required (see 9.d of Part II). Each person listed in step 5 shall sign and date next to his/her name in step 5, indicatmg completion of a SAFETY REVIEW. I
8. 2nd Safety Reviewer: Perform SAFETY REV in oc cordance with Section 8.0.

2nd Safety Reviewer M M Date " 2 7~ k DISCIPLINE: Nb IfL b

9. PNSC review required? If 'yes,' attach Port V and mark re,ason below: N

[] Potential UNREVIEWED SAFETY QUESTION IV answered "Y s*

g[1Other Question 9 of (specify): b Pe A 1, a bla '5.*L A he cebt et lAsdf%4 'J fA boAu khA.

I l

OAl-109 Rev.3 Page 74 Of 88 Page 49

ATTACHMENT 2 Page 56 of 69 10 CFR50.59 Program Manual Rev. 3 ATTACHMENT A CP&L SAFETY REVIEW PACKAGE Page 1 of 1 PART I: SAFETY ANALYSIS (See instructions in Section 8.4.11 (Attach additional sheets as necessary.)

DOCUMENT NO. 6mcm REV. NO. I 7 DESCRIPTION OF CHANGE: u o h d-c %E 1.1 -L -ho c <r Wc4 M 9'T W4 \)w.,

cen us d ch .

ANALYSIS: The LM b cnm e in fo < med e .i

~

.m t vJ 3 in -the o nctu

.ro i %e et n ., o d A t- nee _

u. awste met A u. -6 c=6 U a.d 4\ue fr <o m -h Csh . .- we twe il < e . u l< - \ +o Ec.nk % n e incar= W s '

t e sl& ent \ocedsh n - mrest

.fr6en I vv c.rer + ms\\ elmd Aox W L'd ( , ,-A ts re q w s e, h -4r3

\re r Q ,, Weh a e ud\%. 'Tk t L\1L o gtA r N -

A no\w eA t ar9r 16 tri.4 e 1 t %e s.

in %c n e c res+ c 4en -Ioccd-'<

A 2 e c4 o u - %e batm it he e te d ed -4e c (Dt.t+  % .i. Ae ul

\cw cLbim .

't ha rc4 4. o n (n as no imoaet- .n eJeL v4 ,L a \ em k be_

ute3 % e d e sd e&t 4 o m. % o u h s (c. d  % < cIsuwts (d Jf t oW e Tbe r cw e e i s w. t - \' ke\'sb ad of m c.e c i kt ac m n\ E nc.4'm

~

mQ s.S e, u . o m e A- dat rwt be oEtemth.

REFERENCES:

T~es h 6 , 3 . s 2._ .

FSAR 2 1.1. ( , Lhd vu h ws OAl-109 Rev.3 Page 75 of 88 Pege 50

ATTACHMENT 2 Page 57 of 69 10 CFR50.59 Program Manual Rev. 3 ATTACHMENT A CP&L SAFETY REVIEW PACKAGE Page _3,,,,,, of _g,_

PART 11: ITEM CLASSlFICATION DOCUMENT NO. O OC m REV.NO. l '7

.Y.et list

1. Does this item represent:
a. A change to the facility as described in the SAFETY ANALYSIS REPORT?

[] tt"

b. A change to the procedures as described in the SAFETY ANALYSIS REPORT 7

[] If

c. A test or experiment not described in the SAFETY ANALYSIS REPORT 7 (1 W
2. Does this item involve a change to the individual plant Operating License or to []

its Technical Specifications? It

3. Does this item require a revision to the FSAR?

() if'

4. Does this item involve a change to the Off-Site Dose Calculation Manual? It" []
5. Does this item constitute a change to the Process Control Program? () (f'

. 6. Does this item involve a major change to a Redweste Treatment System? [] If

7. Does this item involve a change to the Technical Specification Equipment List (BSEP and SHNPP only)? [] (('
8. Does this item impact the NPDES Permit (all 3 sites) or constitute an (1 R" "unreviewed environmental question" (SHNPP Environmental Plan, Section 3.1) or a "significant environmental impact" (BSEP)? ,
9. Does this item involve a change to a previously accepted:
a. Quality Assurance Program
b. Security Plan (including Training, Qualification, and Contingency Il W Plans)?

[] It'

c. Emergency Plan?
d. Independent Spent Fuel Storage installation license? (if "yes," refer to Il W  !

[] 4 j Section 8.4.2, " Question 9," for special considerations. Complete Part VI in accordance with Section 8.4.6)

SEE SECTION 8.4.2 FOR INSTRUCTIONS FOR EACH "YES" ANSWER.

REFERENCES. List FSAR and Technical Specification references used to answer questions 1-9 above. Identify specific reference sections used for any "Yes" answer.

O b t M .* Tech s.ee 1 12 n A tt LJev i

l i OAl-109 Hev. 3 Page 78 of 88 Pcge 51

f ATTACHMENT 2 Page 58 of 69 10 CFR50.59 Program Manual Rev. 3 l

l PART lil: UNREVIEWED SAFETY QUESTION DETERMINATION SCREEN DOCUMENT NO. 00cm REV.NO. 17 Y.01 M

1. Is this change fylly, addressed by another completed [] H UNREVIEWED SAFETY QUESTION determination? (See Sections 7.2.1, 7.2.2.5, and 7.9.1.1)

REFERENCE DOCUMENT: NA REV.NO.

t l

Y.91 &

2. For procedures, is the change a non-intent change l which 90lg (check all that apply): (See Section 7.2.2.3) [] []

l l [] Corrects typographical errors which do not alter l the meaning or intent of the procedure; or,

!  ?

[] Adds or revises steps for clarification (provided they are consistent with the original purpose or applicability of the procedure); or,

[] Changes the title of an organizational position; or,

[] Changes names, addresses, or telephone numbers of persons; or, l

[] Changes the designation of an item of equipment where the equipment is the same as the original equipment or is an authorized replacement; or, t [] Changes a specifi6d tool or instrument to an equivalent i substitute; or, l

, [] Changes the format of a procedure without altering the

! meaning, intent, or content; or

[] Deletes a part or all of a procedure, the deleted portions of which are wholly covered by approved plant procedures?

i If the answer to either Question 1 or Question 2 in PART lli is "Yes," then PART IV need not be

! completed.

l r

i OAl-109 Rev.3 Page 77 of 88 j Page 52  !

ATTACHMENT 2 l Page 59 of 69 l 10 CFR50.59 Program Manual Rev. 3 ATTACHMENT A q CP&L SAFETY REVIEW PACKAGE Page ( fo __

PART IV: UNREVIEWED SAFETY QUESTION DETERMINATION DOCUMENT NO. O h t. m REV.NO. 17 Using the SAFETY ANALYSIS developed for the change, test or experiment, as well as other required references (LICENSING BASIS DOCUMENTATION, Design Drawings, Design Basis Documents, codes, etc.), the preparer of the Unreviewed Safety Question Determination must directly answer each of the following seven questions and make a determination of whether an UNREVIEWED SAFETY QUESTION exists.

A WRITTEN BASIS IS REQUIRED FOR EACH ANSWER

.Y.En Hs

1. May the proposed activity increase the probability of [] B occurrence of an accident evaluated previously in the SAFETY ANALYSIS REPORT 7 rhe -c n = o.+. N nro e eh_n uenkint w ,% wh ha W cows b b, A O ke enmsmanua+L be oew, ed . %k i n ek an a, in e)A

_r f n+2 m d K d o c In -+ LA4 'M bcVE em W A O tt en e,,Cch mA e M mW woms % pa w.4s) % oc nsequenas

2. May the proposed activity increase the consequence # ong nedMt.

s of an accident evaluated previously in the SAFETY ANALYSIS REPORT 7

[] A

%- 4 \

3. May the proposed activity increase the probability of Il di occurrence of a malfunction of equipment important to safety evaluated previously in the SAFETY ANALYSIS REPORT?

%L Aunce %M o AC% ul- et-- M um cm o s h a b,. u ., A w e u ma 4+.6

+c Ao,'..u.-u w eai,esne4 mocic e t equ s 5 m trvt- n y c4 En"t % Amf=4 ,_

4. May the proposed activity increase the consequence of a (1 4t malfunction of equipment important to safety evaluated previously in the SAFETY ANALYSIS REPORT 7

%e -W T

5. May the proposed activity create the possibility of an (1 ff' accident of a different type than any evaluated previously in the SAFETY ANALYSIS REPORT? ,

c_w.n e s m a&e .& o %%ue, ofw- % _c.c+ g he su,uw we W. ne c.re tt (c itde.nt" c:secul does th ca re c ke he an u ibd sk sm8 m Oft"4 5 VW mc % A ye . '

OAl-109 Rev.3 Page 78 of 88 Page 53 _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

J ATTACHMENT 2 Page 60 of 69 10 CFR50.59 Prograrn Manual Rev. 3 ATTACHMENT A CP&L SAFETY REVIEW PACKAGE Page.,_h , of

]_

PARTIV: (Continued)

DOCUMENT NO. OEM REV.NO. I~7 Xat Nn

6. May the proposed activity create the possibility of a [] .44-malfunction of equipment important to safety of a different type than any evaluated previously in the SAFETY ANALYSIS REPORT 7 .

h ex. kk .S~

7. Does the proposed activity reduce the margin of safety as [] & ,

defined in the basis of any Technical Specification?  !

- \

h e dn af <d4 ei m4 e M e < +ch b --M s WWe . 'The rewe u b '

tb r o s' b e e e , \ adk i t e u e c4 ase w c-lhr,e , acrtJyseu d ess au tl p.n .. i u A u,- m w e -n-

8. Based on the answers to questions 1 7, does this item [] li' l result in an UNREVIEWED SAFETY QUESTION 7 If the answer to any of the questions 1-7 is "Yes," then the item is considered to constitute an UNREVIEWED SAFETY QUESTION.
9. Is PNSC review required for any of the following reasons? [] .R I lf, in answering question 1 or 3 "No," it was determined that the probability increase was small relative to the uncertainties; or, in answering question 2 or 4 "No," it was determined that the doses increased, but the dose was still less than the NRC ACCEPTANCE UMIT: or, in answering question 7 "No," a parameter l would be closer to the NRC ACCEPTANCE LIMIT, but the end result was still within the NRC l ACCEPTANCE LIMIT: then PNSC review is required.

REFERENCES:

l FSkt c_e < 4 A A S: . o l

l This Unreviewed Safety Question Determination is for the following DISCIPLINE (s): (Additional Part IV forms may be included as appropriate.)

[] Nuclear Plant Operations [] Structural l- [] Nuclear Engineering [1 Metallurgy i

[] Mechanical [] Chemistry / Radiochemistry l [] Electrical  !! Health Physics

[] Instrumentation & Control [] Administrative Controls 4

OAl-109 Rev.3 Page 79 of 88 Page 54

7. _ _ _. - . . , _ . _ __ .-- .. __ _ . .._ ._-- _

g ATTACHMENT 2 Page 61 of 69 10 CFR50.59 Program Manual Rev. 3 ATTACHMENT A ,,,  !

CP&L SAFETY REVIEW PACKAGE Page.q._ of _

PART V: PNSC REVIEW '

l d

DOCUMENT NO. $0 -W $o-117 REV.NO. O

! Determination / Evaluation: OeA l' d A )*- 32 '

em o DS * [o f ( . . '

i le.d# b ed LLse (eum, .

,'t N

Action Taken:_ SIR Ak 31-t >

1 P

J 4 ^

0 i

Basis
T% \d tes < c .. ~ 5 -s 's '

, ,- c Li c .A ~~ i t~ o o c-

! f,< u t k k- L ~m\ k.se u,M Wd dwe To tad ,(..'i

,)

.3 5 O.13 k_ ' (k s, . k  !

A 'N ,, x

\ l PNSC Chairman: 2' /Y. / I,/$m

~ - *3C.yJe Date:

i OAl-109 Rev.3 Page 80 of 88 Pc?' 55 - _ _ _

l

o i

BRUNSWICK STEAM ELECTRIC PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)

REVISION 17 E22 M DOCKET NOS. 50-324 50-325 l

CAROLINA POWER & LIGHT COMPANY I

1 Effective Date [ ((Y[f, l

i Approved By: I% '-

'PpC

{

i 1

1 5

Page 56 i

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

l ..

LIST OF EFFECTIVE PAGES ,

I j ODCM l 1

Pare (s) Revision l l

1 17 ,

11 15 iii 14 i

iv 15 <

v-viii 14 i 1-1 8 l 2-1 14 2 2-8 15  !

2-9 14 2-10 15 '

2 2-15 14 3 3-5 4 ,

3-6 16 5 3-7 3-12 4 i 3-13 1  !

3-14 4 3-15 5 3 3-18 4 3-19 6 3-20 1 3-21 0 i 3-22 16 -

3-23 1  ;

3-24 4  ;

3-25 1 1 3-26 4 '

3-27 6 2 3 28 8 l 3-29 1 i 3-30 17  ;

3-31 4 l 3-32 1 1 3-33 14 I 3 3-36 1 I 3 3-38 4 )

3-39 6 3-40 7 3-41 1 3-42 16 3 3-45 1 3 3-48 4 3-49 1 3 3-68 14 j 4 4-3 11 4-4 7 4 4-6 11

(_ 5-1 C I 6 6-2 0 i 63 4 l

ODCM (BSEP) i Rev. 17 I i

l.

Page 57

, . . . , . - - y. _ , , , =.er.T *' v

._ . _ . _ _ _ _ . . .m _ . _ . _ _ _ . _ _ _ __ _ . . . - . . _ _ . . . _ . . . ._.___ _ _ _ _ . _ ._ __

4 i . TABLE 3.2-2 l DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE l

BRUNSWICK PIANT CENTER (Mi) l l

"CU #

Site Milk Milk Meat- Nearest- Nearest.

i Boundary Cow Goat- Animal Resident Garden NNE 0.7 - - -

0.9 -

l ,

NE 0.7 4.75* - - - -

ENE 0.7 - - - - -

E 0.7 - - - - -

1 ESE 0.7 - - -

1.5 -

l SE 0.7 - - -

0.9 -

SSE 0.7 - - -

0.9 -

S 0.8 - - -

1.5 1.5 .

I SSW 0.8 - - -

1.2 1.5 l SW 0.7 - - -

1.0 1.0 WSW 0.7 - - -

1.0 1.0 W 0.7 - - -

0.8 0.8 WNW 0.6 - - -

0.8 0.9 l l NW 0.5 - - -

0.9 1.0 I NNW 0.6 - - -

0.8 0.8 N 0.7 - - - 0.9 -

l i

i l

l i  ;

i i

  • A" hypothetical"cowmilkpathwayislocatedatthispointinaccordancehith'

/

! 5.3.1 of NUREG 0133.

Y

ODCM (BCEP) 3-30 Rev. 17 j Page 58 4

r ENCLOSURE 2 l

i BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 ,

NRC DOCKET NOS. 50-325 & 50-324  ;

OPERATING LICENSE NOS. DPR-71 & DPR-62 l

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ,

l LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Carolina Power & Light  !

Company in this document. Any other actions discussed in the submittal represent i

intended or planned actions by Carolina Power & Light Company. They are described to l the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this  !

document or any associated regulatory commitments.  !

Committed Commitment date or ,

outage None r l

l l

1 t

i 1

E2-1 i

4 .

i e ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 j SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l I

LIST OF REGULATORY COMMITMENTS ,

l The following table identifies those actions committed to by Carolina Power & Light-Company in this document. Any other actions discussed in the submittal represent I intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatcv Affairs at the Brunswick Nuclear Plant of any questions regarding this ]

document or any associated regulatory commitments.

Committed Commitment date or ,

outage I None l

l i

l I

I l

\

l i

! I

\

)'

i i i

i 4 I ,

I E2-1 l i

5

. _ _ . . . . , _ , - - -. , .-.. . . , _ , _ . , , _ . . . - . . . . _ . . _ . , ,,

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