Text

Semiannual Radioactive Effluent Rept,940701-1231
	ML20080M870
Person / Time
Site:	Brunswick
Issue date:	12/31/1994
From:	Richard Anderson; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	BSEP-95-0057, BSEP-95-57, NUDOCS 9503060072
	Download: ML20080M870 (61)
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CP&L

< Carolino Power & Light Company Roy A. Anderson PO Box 10429 Vice President Southport NC 28461 Brunswick Nuclear Plant

- 910 457-2496 Files- BO9-13510C-Serial: BSEP 95-0057.

FEB 2 81995 U. S. Nuclear Regulatory Commission.

ATTN: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:

Enclosed is the Semiannual Radioactive Effluent' Release Report for the Brunswick Steam Electric Plant Units 1 & 2, covering the period from July 1, 1994, through December 31, 1994.

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

If you have any questions regarding this submittal please contact Ms. Jackie Gawron at (910) 457-2447 Very truly yours, N

A. Anderson WGR/dm Enclosure cci Mr. S. D. Ebneter, Region II - Administrator Mr. D. C. Trimble, NRR Senior Project Manager - Brunswick (Acting)

Mr. C. A. Patterson, Brunswick NRC Senior Resident Inspector The Honorable H. Wells, Chairman-North Carolina Utilities Commission 4

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ENCLOSURE BRUNSWICK STEAM ELECTRIC PLANT, UNITS '1 AND 2 ' ,

NRC DOCKET NOS. 50-325 & 50-324

, , , OPERATING LICENSE HOS. DPR-71 & DPR-62

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 l intended or pla.nned actions by Carolina Power & Light Company. . These actions are

' described to the NRC for the staff's information and are not re0ulatory commitments.

Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any '

questions regarding this document or any associated regulatory commitments.- s Committed

' Commitment date or outage'

1. None NA.

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-Brunswick' Steam Electric Plant I

Semiannual Radioactive Effluent Report July 1, to December ~31, 1994 ATTACHMENTS: PAGES:

1. Supplemental Information 2 6

2. Effluent and Waste Disposal Data 7- 21

3. Environmental' Monitoring Program '22 - 24

4. Effluent Instrumentation 25 - 28

5. Major Modification to Radioactive Waste 29 Treatment Systems

6. Meteorological Data 30

7. Annual Dose Assessment 31 - 47'

8. ODCM and PCP Revisions 48.- 61 l

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. ATTACHMENT 1-Supplemental-Information July 1, to December 31', 1994 Page 2

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 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 I

B. Ic~ine-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.

* (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 AnvJ -sis for specific radionuclides collected on charcoal car. r r iges by gamma spectroscopy.

C. Particulates Analysis for specific radionuclides collected =on filter papers by gamma spectroscopy.

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

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-i E. Liquids Effluents Analysis for specific radionuclides of individual releares by gamma spectroscopy.

Used as applicable limits for Table 2A Page 4 I

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.. i iNuclear counting statistics are reported utilizing 1-sigma error.:

, 1 i ' Total-error'where reported represents _a best' effort-~to {

Eapproximate;the:totalfof..alllindividual and sampling l errors. .j 4.-. Batch Releases

i A.. Liquid' i , ,

(1)J Number of , batch releases: 1.46E+02 (2) Total time period for batch releases: .2.04E+04-Minutes- .

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(3) . Maximum time' period for a batch-release: 2.60E+02 Minutes 4 (4) Average' time period for a batch release: '1.40E+02 Minutes "

(5) Minimum time period for a batch release: 1.10E+02-Minutes'. ,

(6) Average stream flow during periods of release of effluent.into a' flowing stream : 8.98E+05-

GPM l B. Gaseous ]

(1) : Number of' batcht 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 l

-l (4) _ Average time period for a batch release: 0.00E+00 1 Minutes' (5) Minimum time period for a batch release: 0.00E+00 , ,

Minutes :1

5. Abnormal releases

i A. Liquid '

(1) Number of relea'ses: O.00E+00 l

(2) Total activity released: 0.00E+00 Curies l B. Gaseous (1) Number of releases: 0.00Fs00 (2) Total activity released: 0.00Ec00 Curies

There were no abnormal releases that exceeded 10CFR20 or 10CFR50 limits. See Page 6 for a discussion of 'l release events that occurred. j Page 5 1

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1. -Discussion of Tritium in the Storm Drain Collection Pond Approximately 1.74E+07 gallons containing 4.68E+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 totale are included in the quarterly sumaries in Table 2A and 2B.

NOTE 2: The quantity of zainwater released f rou: the Storm Drain Collection Basin and/or the Storm Drain Collection Pond is not included in voim E OF WASTE on Table 2A.

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ATTACHMENT 2- ..

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vg; 4 Effluent:and; Waste' Disposal. Data Brunswick Steam' Electric P ?nts

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July: 1, to December 31, 1994 >

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, fg - Table 1A: ' Gaseous Effluents'-LSummation'of'all Releases !

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Table 1B: . Gaseous Effluents Elevated Rel' eases

' 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

, Table 2B: Liquid Effluents - Batch Mode

, Appendix'A: Lower Limits of Detection Table.3: Sclid Waste and Irradiated Fuel Shipments. ,

Enclosure 2 Combustion of Waste Oil

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TABLE ~1A TEffluentfand Waste ~Di's~posal Semiannual Report'forLYear 1994 i ,

.x- . Gaseous. Effluent 91 . Summation-ofTall Releases

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Est.ETot.>

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Unit Otr 3 Otr 4' Error"%1 A.-FISSION AND ACTIVATION'-

GASES- :

1. : Total release Ci 1.26E+02 9.37E+01- 4.50E+01.

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2. Average release uCi/sec ~1.59E+01 l'.18E+01

. rate for period

3. Percent of technical >

specification limit % 2'.93E-02 1.86E-02 '

B. IODINES .

5.35E-04 :6.73E-04'. 3.50E+01-

1. Total I-131 Ci ;

2. Average release uCi/sec 6.73E-05 8.47E-05 rate for period C. PARTICULATES tem i 1.-Total release Ci 2.99E-03 2.91E-03 3.50E+01-

g. .

2. Average release uCi/sec 3.76E-04 3.66E-04 rate for period ,

3. Gross alpha Ci 4.45E-06 -2.95E-06--

s.

D. Tritium

'1. Total release Ci 6.27E+00 5.09E+00 ;3.00E+01

2. Average release uCi/sec 7.89E-01'.6.40E-01 ,

rate for period E. IODINE-131~. IODINE-133. TRITIUM AND PARTICULATES' E2D_1 '

1. Total Release- Ci 6.27E+00 5.10E+00-4 2. Average release uCi/sec- 7.89E-01 6.42E-01 rate for period

'~

. 3. Percent of technical specification-limit % 2.15E-02 2.82E-02>

c F. PARTICULATES VIA BURNING CONTAMINATED OIL

1. Total Releace Ci 2.51E-06 0.00E+00

.2. Average release rate for period uCi/sec 3.16E-07 0.00E+00

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3. Percent of technical specification' limit % 5.76E-01 0.00E+00 M This includes the number of curies released via incineration. ~J l

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l TABLE 1B Effluent and Waste Disposal Semiannual Report for Year 1994 Gaseous Effluents - Elevated Releases Continuous Release Nuclides Released Unit Otr 3- Otr 4

1. FISSION GASES argon-41 Ci 1.86E+00 < LLD krypton-85m Ci 9.36E+00 9.29E+00' krypton-87 Ci 1.48E+01- 1.12E+01 krypton-88 Ci 1.81E+01 1.60E+01 xenon-133 Ci 6.81E+00 7.08E+00 xenon-135 Ci 1.71E+01 1.42E+01 xenon-135m Ci 1.08E+01 4.70E+00 xenon-137 Ci 2.84E+00- < LLD xenon-138 Ci 2.52E+01 7.35E+00 total for period Ci 1.07E+02 6.99E+01

2. IODINES iodine-131 Ci 2.86E-04 2.52E-04 iodine-132 Ci 2.54E-04 1.13E-04 iodine-133 Ci 1.11E-03 1.03E-03 iodine-135 Ci 2.76E-04 < LLD total for period Ci 1.92E-03 1.40E-03

3. PARTICULATES chromium-51 Ci 3.53E-05 1.14E-04 manganese-54 Ci 6.56E-06 < LLD cobalt-60 Ci 1.77E-05 1.72E-06 strontium-89 Ci 3.04E-05 2.86E-05 strontium-90 Ci 4.18E-07 1.64E-07 cesium-137 Ci 2.18E-06 < LLD barium-140 Ci 8.37E-05 5.54E-05 lanthanum-140 Ci 1.19E-04 7.43E-05 total for period Ci 2.95E-04 2.74E-04

4. TRITIUM hydrogen-3 Ci 3.31E+00 1.91E+00 i

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TABLE 1C Effluent and Waste Disposal Semiannual Report for Year 1994 )

Gaseous Effluents - Ground Level Releases Continuous. Release Nuclides Released Unit Otr 3 Otr 4'

1. FISSION GASES krypton-85m Ci 1.84E+00 9.87E-01 i xenon-133 Ci 4.04E+00 < LLD l xenon-135 C1 1.35E+01 2.28E+01 total for period Ci 1.94E+01 2.38E+01 {

2. IODINES I iodine-131 Ci 2.49E-04 4.21E-04 iodine-132 Ci 1.40E-03 5.89E-03 iodine-133 Ci 2.78E-03 4.71E-03 iodine-135 Ci 1.41E-Q1 6.18E-03 total for period Ci 5.84E-03 1.72E-02 I

3. PARTICULATES chromium-51 Ci 2.01E-03 2.13E-03 manganese-54 Ci 3.54E-05 3.33E-05 cobalt-58 Ci 5.65E-05 5.16E-05 cobalt-60' Ci 5.61E-04 4.08E-04 strontium-89 Ci 1.17E-05 7.17E-06 strontium-90 Ci 3.11E-08 2.20E-08 cesium-137 Ci 2.17E-05 3.44E-06 barium-140 Ci 7.05E-08 8.30E-07 lanthanum-140 Ci 6.26E-08 1.11E-06 total for period Ci 2.70E-03 2.64E-03

4. TRITIUM hydrogen-3 Ci 2.96E+00 3.19E+00 TABLE 1D Effluent and Waste Disposal Semiannual Report for Year 1994 Gaseous Effluents - Ground Level Releases For Burning Contaminated Oil Nuclides Released Unit Otr 3 Otr 4

1. PARTICULATES cobalt-60 Ci 2.20E-06 0.00E+00 cesium-137 C1 3.07E-07 0.00E+00 total for period Ci 2.51E-06 0.00E+00 Page 10

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. TABLE 2A--

< l Effluent and Waste Disposal. Semiannual Report _for Year ~1994 Liquid Effluents.- Summation'of all Releases-Unit Otr 3- Otr 4 Est-Tot

-% Error

.A. FISSION AND ACTIVATION' P R O D U C T S rzra.1 ,

, 1. Total release'(excluding Ci 1.34E-02 4.01E 4.00E+01' tritium, gases,'& alpha)

!!9IH_1 .

uCi/ml

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2. Avg. diluted' conc, 4.21E-10' 1.06E-10

3. Percent limit % 1.59E-02 4.40E-03 a

!!21E 1 c

/: B. TRITIUM.

1. Total release Ci 1.62E+01 2.15E+01 4.50E+01

!!2IE 1

2. Avg. diluted conc. uCi/ml' 5.09E-07 5.71E-07

-3. Percent limit -% 5.09E-02 5.71E-02

. C. . DISSOLVED AND ENTRAINED GASES ggIg_t

1. Total release. Ci 6.46E-03 6.62E-03 4.00E+01

!!9IE_1

'2. Avg. diluted conc. uCi/ml 2.03E-10 1.76E-10

3. Percent limit % 1.02E-04 8.79E-05 D. GROSS' ALPHA RADIOACTIVITY

1. Total release 'Ci < LLD < LLD 4.00E+01 t!2IE_1 E. VOLUME OF WASTE liters 4.77E+06 6.00E+06 1.50E+01 F. TOTAL OF DILUTION WATER (used durina celease for averace dil. conc.) liters 3.18E+10 3.77E+10' 1.30E+01 G. V_LUMEO OF COOLING WATER liters 5.05E+11 4.62E+11 DISCHARGED FROi4 PLANT

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' TABLE 2B

' Effluent and Waste Disposal Semiannual Report for Year 1994 ,

Liquid Effluents.- Batch Mode Nuclides~ Released- Unit Otr 3- . Otr 4 '

1.l FISSION AND ACTIVATION PRODUCTS ,

chromium-51' Ci 2.80E 1.47E manganese-54 Ci 3.67E-04' 6.02E-05 iron-55 Ci 9.54E-04 < LLD cobalt-58 Ci 1.97E-04 3.97E-06

. cobalt-60 Ci 8.75E-03 2.27E-03 arsenic-76 Ci 2.01E-06 6.97E-06 technetium-99m Ci 4.79E-06 e'LLD antimony-125 Ci 8.05E-06 '1LLD iodine-131 Ci < LLD 1.45E-05 iodine-133 Ci < LLD

. 1.38E-05 cesium-134 Ci 1.21E-05 . 5.80E-05 cesium-137 Ci 2.62E-04 1.~4 4 E- 03 barium-140 Ci < LLD .4.23E cerium-144 C1 2.60E-05 < LLD total for period Ci 1.34E-02 4.01E-03 4

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TABLE 2B. '(continued)

.' Effluent and Waste-Disposal Semiannual. Report for Year 1994

. Liquid Effluents - Batch Mode, N

Nucl' ides Released Unit Otr'3 Otr 4

2. GASES .

_ , krypton-87 Ci < LLD'- 2.64E-06' xenon-133 Ci ~1.82E 1.73E-03L 3.18E-05 < LLD 'L' xenon-135m Ci xenon-135 _Qi ' 4.60E 4.89E-03 total for period Ci 6.46E-03 6.62E ,

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' Lower Limits'of Detection: =l 1 ,

' July through December?1994

-uCi/ml' 1.-Licuid Releases 2.' Gaseous Releases-R Fe-55l 4.32E-08 Ar-41 5.'02E-09 JFe 2.34E-08 Xe-133 1.79E-08 Zn-65 4.47E-08 'Xe-133m 3.55E Sr-89: 2.67E "Xe-137 4.82E-05 Sr-90_ _1.32E-08 s Mo-99 1.57E-07 Tc-99m 1.12E-08 ,. i Sb-125 5.12E-08 3. Iodines and Particulates I-131 1.26E-08.

I-133 1.80E-08' Mn-54 3.07E-14 Ba-140 7.13E-08 Fe-59 .1.53E-14' Ce-141 1.57E-08 Zn-65 l'.14E-13 Ce-144 7.31E-08 Cs-134. 6.74E-14 LAlphaL 4.28E-08_ I-135 8.37E-13 Kr-87 4.03E-08 Cs-137 :1.82E-14 Kr-88 5.21E-08 Ce-141 3.08E-14

.Xe-133m- 1.08E-07 Ce-144~ 11.27E-13 Xe-135m- 7.~57E-08 Xe-138 1.41E-07 N

4 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'., j

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- . Effluent:and Waste Disposal Semiannual Report?for Year 1994'

' Solid Waste and Irradiated Fuel' Shipments d

Waste Class A- 'Julv throuch December

-1. Total volume 'shioned (cubic meters)- l2.45 E2 Total ' Curie quantity (estimated). 1.98 E2-

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

a. Spent resins, filter sludges. meters3 1.02LE2

' Curies- 1.37 E2' 1.00E1

b. Dry active waste, compacted meters3 1.30 E2 and noncompacted Curies. 2.67 El' 1.00E1

c. Irradiated components meters2 1.28 El >

Curies '3. 4 0 ' El- '1.00El-

d. Others (describe) meters' l0. 00 EO

-Curies 0.00 E0 N/A

3. Estimate of maior radionuclide-comoosition r

a. Cr-51 1.61 E0%L Fe-55 6.-16 El% ;

Co-60 3.14'El%

Ni-63 1.70 E0%-

Sb-125 .1.97-E0%

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b. ~Mn-54' 1.20 EO%

Fe-55 .7.99 El%

Co-60 1.63 El%

Ni-63 1.80 EO%-

c. Mn-54 2.55 E0%

Fe-55 3.32'El%

Co-60 6.18 El%

Ni-63 1.98 EO%

d. N/A N/A Page 15-

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TABLE-3A-(cont.)-

N .Efflu'ent-and Waste' Disposal SemiannuallReport forLYear 1994-Solid Waste"and Irradiated FueltShipmentss s

4. Cross' reference' table,' waste stream, f o r m ,- and container tvoe.

<- - Stream Form Container tvoe No.'of^shinments

a. ' Resin- Dewatered &. ' Type A/ Type B ;18/2 Solidified *~

b. Dry active Compacted /non-- ' 6/O' 6 Noncompacted'

. waste c'ompacted waste

c. Irradiated 3 / 0_- -3/0' ,

components

d. Other 0 0

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

5. Jhioment Discosition

a. Solid Waste Number of Shioments -Mode of Transoortation Destirlation 29 Sole Use- CNSI/Barnwell, SC i

b.~ Irradiated Fuel Number of Shioments Mode of Transoortation Destination 0 N/A 'N/A

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TABLE 3B Effluent and Waste' Disposal Semiannual. Report for Year 1994 Solid Waste and Irradiated Fuel Shipments Waste Class B July throuch December

1. Total volume sbioned (cubic meters) 3.41 EO Total Curie quantity -(estimated) 7.61 El

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

a. Spent resins, filter sludges meters 2 0.00 EO N/A Curies 0.00 E0

b. Dry active waste, compacted, - meters 2 0.00 EO N/A and noncompacted Curies 0.00 E0

c. Irradiated components meters 2 3.41 E0 1.00E1 Curies 7.61 El

d. Others (describe) meters 2 0.00 E0 N/A Curies 0.00 EO

3. Estimate of maior radionuclide composition

a. N/A N/A

b. N/A N/A

c. Mn-54 3.03 E0%

Fe-55 5.68 El%-

Co-60 3.73 El%

Ni-63 2.74 EO%

d. N/A N/A Page 17

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^tf l TABLE 3B (cont.) -

- Effluent- and Waste Disposal- ~ Semiannual Report for Year 1994 Solid' Waste and. Irradiated Fuel Shipments

4. Cross reference table, waste stream, form and container tvoe Stream Form Container tvoe tk), of shioments

a. Resin Dewatered & Type ~A/ Type B. 0/0 Solidified

b Dry active Compacted /non- N/A- 0/0 waste compacted waste T c. Irradiated 0/1 0 /1' components

d. Other N/A 0

Solidification agent or absorbent (e.g., cement, urea formaldehyde)- N/A-5.Shioment Discosition

a. Solid Waste Number of Shioments Mode of_Transoortation Destination 1 Sole Use CNSI/Barnwell, S.C.

b. Irradiated Fuel Number of Shioments- Mode of Transoortation Destination O N/A N/A d

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, TABLE 3C Effluent and. Waste Disposal Semiannual Report-for Year 1994-Solid Waste and Irradiated Fuel Shipments Waste Class C July throuch December

1. Total-volume shicoed (cubic meters) 2.97 EO

-Total Curie quantity (estimated) 6.71.E4'

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

Units. Period % Error'

a. Spent resins, filter sludges ' meters 2 0.00 EO N/A t Curies 0.00 E0

b. Dry active waste, compacted meters 2 0.00 EO- N/A '

and noncompacted Curies- 0.00 EO -

c. Irradiated components meters 2 2.97 E0 1.00El.

Curies 6.71 E4-d.'Others-(describe) meters 2 0.00,EO N/A Curies .0.00 EO.

3. Estimate of maior radionuclide composition '

a. N/A- N/A A

b. N/A N/A ,

c. Mn-54 1.95 E0%

Fe-55 5.41 El%

Co-60 4.06 El%

Ni-63 3.07 E0%.

d. N/A N/A l

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TABLE-3C J(cont.)

, ' Effluent and-Waste Disposal Semiannual Report forJYear.1994

. Solid Waste and Irradiated Fuel Shipments o

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

a. Resin Dewatered & . Type?A/ Type {B 0/01 Solidified *

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

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c. Irradiated 0/4 0/4 components l d. Others _N/A '

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

5. Shioment Discosition a.: Solid Waste 1

Number of Shioments Mode of Transoortation' Destination 4 Sole Use ..CNSI/Barnwell,LSC ,

b. Irradiated Fuel-Number of Shioments Mode of Transoortation Destination 7 Rail Car / . CP&L/SHNNP IF-300 Cask t I

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" - ATTACHMENT 2((cont.);

~, r cf.

4: " ENCLOSURE 2

,l ,

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, . Combustion 1of' Waste oil.

July 1(.to' December 31,-'19941 :

c u During'this reporting ^ period, approximately.756Lgallons of ,

contaminated waste' oil waseincinerated:in the on' site oil -

t .

' incinerator.- The-. total. activity contained in this quantity of

, waste oil included 2.20E-06 curies.of Cobalt-60 and 3.07E-07:

curies of-Cesium-137.

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Page 21 s.

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ATTACHMENT 3 Environmental Monitoring Program July 1, to December 31, 1994 Enclosure 1: Milk and Vegetable Sample Locations Enclosure 2: Land Use Census Page 22

a i l

ATTACHMENT 3 (cont.)

ENCLOSURE 1 Milk and Vegetation Sample Locations July 1, to December 31, 1994 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'.

Page 23

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J, 4 .

ENCLOSURE.2' l 1

m , Land Use-Census.- .

)

.Q July 1, to December 31,=.1994; 4

i 1

i k

The.1994~. Land'Use Census was performed'during'the period ofl: June K 6 to. June 13, 1994. .'No~. locations-were identified thatfare q

reportable in the' Semiannual Radioactive Effluent Release Reporth Land Use Census. updates are included with the ODCM revision-16 in-ll Attachment.8.

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s ATTACHMENT 4-Effluent Instrumentation-July 1, to December 31, 1994 Enclosure 1: Radioactive Liquid Effluent Monitoring Instrumentation Enclosure 2: Radioactive Gaseous Effluent Monitoring Instrumentation Enclosure 3: Liquid Hold-Up. Tanks

, Page 25 i

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ATTACHMENT 4 (cont.)

ENCLOSURE 1 ,

July _.1, to December 31, 1994 Radioactive Liquid Effluent' Monitoring Iristrumentation No Radioactive Liquid Effluent Monitoring Instrumentation was inoperable for greater than 30 days.

P l

1 i

Page 26 1

1

ATTACHMENT 4 (cont )

,- ENCLOSURE 2 July 1, to December 31, 1994 i- Radioactive Gaseous Effluent Monitoring Instrumentation No Radioactive Gaseous Ef21uent Monitoring Instrumentation was inoperable for greater than 30 days.

Page 27

=

v

.f r-ATTACHMENT'4 (cont.)

ENCLOSURE 3 Liquid Hold-Up Tanks July 1, to. December 31, 1994 No liquid hold-up tank exceeded the 10 Ci limit during this reporting period.

Page 28 l

7

-ATTACHMENT 5 Major Modifications to the' Radioactive Waste Treatment System July 1, to December 31,_1994 As per footnote 7 to Technical Specification 6.15, a discussion of-any major modifications to the radioactive waste treatment r systems will be submitted with the Final Safety Analysis Report update.

Page 29

l

- ATTACHMEITT 6 Meteorological. Data July 1, to December 31, 1994 As per Technical Specification 6.9.1.10.a footnote 6, the. annual summary of meteorological data collected over the calendar year will be submitted to a file and will be available for NRC review upon request.

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Page 30 1

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5,i $f:G ,o-ATTACHMENT 7-

/

Annual Dose Assessment

~

January 1, to December 31,_1994 Attached'is the annual dose assessment for the. Brunswick Steam-

~

. Electric Plant for the time: period of January 1-to Decemb er 31, 1994.

Enclosure 1: Annual Liquid Dose Assessment-

-Enclosure 2: ~ Annual Gaseous Dose Assessment -

Enclosure'3: Dose Assessment Summary r

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Page 31 l

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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 Page 32

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CSEP' UNITS 1 Alm'2 LIQUID RELEASES 1994,

~

DISCHARGE =1.72E+93 CFS- . SOURCE TERM MULTIPLIER =1.90E+99 SALTWATER SITE - -

NO RECONCENTRATIDN MODEL -

50-MILE POPULATION =2.82E+95 FRACTION ---; -ADULT =9.71 TEENAGER =9.11 CHILD =9.18~ .

DOSE FACTOR LIBRARY CONTAINS 698 ENTRIES h

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'O -0 IO COST-BENEFIT ANALYSIS OL 0: 0 _

NUCLIDE I RELEASE i . PERSON-PEM DOSr l PERSON-REM PER CURIE __l '

l CI/YR. I TOTAL 800Y I THYROID l TOTAL BODY l THYROID l-1H 3 1 6.96E+91 1 2.91E-96 l- 2.91E-96 l 2.89E-08 l 2.99E-98 1l 11NA 24 1 5.27E-96 I .4.24E l 4.24E-10 l 8.94E-95 l8.04E-05 24CR 51 1 1.97E-92 1 4.64E l 4.51E-08. I 4.34E-06 1 4.22E-06 1 25MN .54 1 8.03E-04 1 9.93E-07 l 8.64E-07 l 1.24E-03 't 1.08E-03 1 4.02E-04 1 1.29E-08 l 1.29E-08 1 2.99E-05 :t 2.99E-05 l

~

25MN 56 1 26FE 55 1 9.54E-04 1 4.68E-07 1 5.57E-13 1 4.91E-04' l1 5.84E-10 3.08E-04.

1 27C0 58 I 8.28E-04 1 3.00E-07 -l 2.55E-07 l- 3.62E-04 ,

. 27C0 60 1 2.57E-02 1 4.29E-04 1 4.25E-04 _l- 1.67E-02 l 1.65E-02 11 36KR 87 I 2.64E-96 l 9.00E+00 1 0.00E+00- 1 0.00E+09 i 0.00E+00 39Y 91h ! 2.13E-06 1 1.96E-11 1 1.96E-11 l 9.21E-06 -l' 9.21E-06 1 43TC 99M i 2.77E-04 1 6.46E-10 .I 6.46E-10 1 2.33E-06 l 2.33E-96 11 5158 125 1 2.97E-03 1 3.74E-06 1 3.73E-06 1 1.81E-03 l -1.89E-03 53I .131 1 1.45E-95 1 3.65E-10 1 4.06E-08 l- 2.52E-05. I 2.89E-03 1 53I 133 1 2.12E-95 1 2.26E-19 l 2.35E-10 1 1.06E-05 l 1.11E-05 .I 54XE 133 J 1.14E-92 1 9.00E+99 - l 0.00E+00 1- 9.00E+00 1 0.00E+90 -l 54XE 135 1 4.79E-92 1 9.00E+99 i 0.99E+99 . I 9.00E+99 1l 0.99E+99 0.00E+90 l

54XE'135M i 8.66E-95 l- 0.00E+99 l 9.00E+99 l 'O.00E+90' I 55c5 134 5 1.52E-04 1 .1.00E-06 I 8.01E-07 1 6.59E-03 1 5.27E-03 1 55cS 137 1 2.67E-93 l- 2.32E-95 1 2.11E-05. I 8.79E-03" l 7.92E-03 I a 568A 140 1 1.39E-95 1 3.29E-10 1 2.81E-19 l- 2.31E-05 1 2.02E-05 I h 1 3.65E-95 l 1.98E-99 I 1.98E-09 I 5.43E-05 I 5.42E-05 l- ."*'

".v.

74W 187

(( 5BCE 144 l 1.07E-94 l 1.00E l 1.99E-99 l 9.39E-06 I 9.39E-06 I

j@

8 TOTAL 4.61E-04 4.54E-04' . a.

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#' O.!AS LOW AS REASONABLY ACHIEVABLE * * -#- .

A D U L-T- D 0 S E S. _(MREM PER YEAR INTAKE) 44-i

! DOSE a BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PATHWAY SKIN .

.7.94E-95 FISH 1.97E-95 2.94E-95 1.83E-95 4.36E - 7.25E-96: -7.97E-96 9.21E-06 1.71E-95 2.28E-95 1.32E-96 ' 1.57E-96 ' 4.44E-96 1.74E-94 3

INVERT 4.17E-94 c4.17E-941 SHORELINE 4.91E-94 4.17E-94 4.17E-94 4.17E-04 .4.17E-94 4.17E 2.78E-97 2.78E-97. 2.78E-97 2.78E-97 2.78E - 2.78E 2.78E-97-' ,

SWIMMING 1.39E-97 1.39E BOATING .1.39E-97 1.39E-972 1.39E-07 1.39E-97 1.39E-97 i

4.59E-04 4.23E-94 4.27E-94 . 4.29E-94' 6.71E-94; l TOTAL 4.91E-94 4.38E-04 4.55E-94

$ USAGE (MG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR =9.5 '

l j [j FISH 29.2 . 39.9 24.99 INVERT 7.3 30.9 24.99 '

, "j SHORELINE 599.9 30.9 9.99 '

3 SWIMMING 199.9 39.9 9.99

$.E0ATING 199.9 39.9. 0.99

[ y T E"E N D0SES (MREM PER YEAR INTAKE) . . ,

! c .

H DOSE THYROID KIDNEY ILUNG -GI-LLI *-

LIVER TOTAL 800Y PATHWAY SKIN BONE 1.49E-95 2.62E-95 2.90E-95 4.45E-96 8.39E-96 8.86E-96 7.29E If ; .

,4 FISH 6.4eE -1.59E-94 n+!

'y INVERT 1.27E-95 2.28E-05 2.98E-95 1.38E-96 1.76E-06 4.91E-94 4.17E-94 4.17E-94 4.17E-94 4.17E-94 4.17E-94 4.17E 4.17E-94 i E SHORELINE 2.7EE-97 2.78E-97 2.78E-97. - 2.78E-97 SWIMMING 2.78E-97 2.78E-97 2.78E-97 1.39E-97 1.39E-97 1.39E-97 1.39E-97 . 1.39E-97 1.39E-97' '1.39E-97 e4 -80ATING 4.28E 4.33E-94 6.49E-04:

4.91E-94 4.45E-94 4.67E-94 4.67E-04 '4.24E-94 ,

Q . TOTAL j$ USAGE (MG/YR,HR/YR) DILUTION' ; TIME (HR) SHOREWIDTH F ACTOR =0.5 ' .

4: ' FISH 29.2 30.9 24.99 jj INVERT . '7.3 - 39.9 24.99 SHORELINE 598.9 39.9 -9.99-199.9 39.9 9.99 37 SWIMMING 9.99

, g BOATING 199.9 30.0 CHILD D0SES (MREM PER YEAR INTAKE) ,

S. -

$ DGSE CG SKIN BONE' . . LIVER TOTAL BODY- THYROID- KIDNEY' LUNG GI-LLI-m PATHWAY - 1.63E-95 11.72E-95 6.33E-95" 4 FISH 4.43E-95 5.36E-95 4.16E 8.65E-96 3.84E-95' 4.64E-95 '7.28E-95 .2.81E-96 3.40E-96 1.30E-95 1.29E > INVERT 4.17E-94 4.17E-94# - 4.17E-94 :4.17F-94 j$ SHORELINE 4.91E-94 4.17E 4.17E-04 4.17E-94 "'

2.78E-97' 2.78E -2.78E 22.78E 2.78E-97 12.78E '2.78E-97o i- SWIMMING 1.39E-97 1.39E-97

' j@ EDATING 1.39E-97 ' 1.39E 1.39E-97 1.39E-97 ' 1.39E-97

-5.99E-94 5.18E-94 5.32E-94 ~4.29E-94' - 4.37E-04'

.4.48E-94 6.10E-94 .

a' TOTAL 4.91E-94 USAGE'(MG/YR,HR/YR) -DILUTION' TIME (HR): - SHOREWIDTH FACTOR =0.5~

, FISH -29.2- 30.9 24.99 INVERT 7.3 39.9 24.99 "

L . SHORELINE 599.9 39.9 9.99 SWIMMING 199.9 : 30.9 c 9.99 '

BOATING 199.9- 39.9 - 9.99 l

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ATTACHMENT 7 (cont)-

- ENCLOSURE 2 ,

~

- Annual l Gaseous DosefAssessment ' r y

INCLUDED ARE:

Source. term for:the three release modes'and.the siteiaggregate. .

Total 50' mile' Integrated Population' Dose.by pathways.and, organs.

Hypothetical maximum. individual organ dose.due to Iodines,.

.Particulates,1 and Tritium for a cow milk pathway at 4.75 miles Northeast.

Maximum site boundary dose by age group and' organs for'~all-pathways.

~

Estimated individual organ dose using.the 1994. 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.

9 d r Page 37 ,

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' c RUN DATE: '92/17/95Y CP&L- . SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING ,

' RtNI TI8E: 13:26:55-iINPUT SOURCE TERMS'- .

.9

.GASRPT.

ll1994 SOURCE TERM (ELEVATED MODE) SSEP UNITS 142 BRUNSWICK UNITS 1 AND 2$ MIXED MODE CONTINUGUS CASEOUS RELEASES,71 994r

-g.

E 1H- '3- 1.239E+91 1H- 3 3.279E+09 ac 18 AR- 41 1.939E+09 24 CR- 51 5.840E-93

$ 24 CR- 51 1.890E-94 25 MN- 54 2.719E-94 25 MN- 54 2.389E-95 27 CD- 58 1.230E-93 ll 27 CD- 58 1.319E-06 27 CD- 69 1.190E-92 S 27 CD- 69 4.470E-94 38 SR- 89 1.740E 36 KR- 85 M 3.829Et91 38 SR- 99 5.729E-97

36 KR- 87 4.340E+91 53 I -131 9.539E-94' is 36 KR- 88 6.530E&91 53 I -132 7.999E-93 '

i 38 SR- 89 1.659E-94 53 I -133 1.919E '

34 38 SR. 99 1.739E-06 53 I -133 7.790E-93 53 I -131- 1.169E-93 54 XE-133 2.359E+61 m 53 I -132 8.679E-94 54 XE-135 7.389E+61.

53 I -133- 4.710E-03 r 54 XE-135 M 2.589E+61

t. l$ 53 I -135 4.579E-94 55 CS-137 8.540E-05 S 54 XE-133 3.429E+61 95 AM-241 1.469E-94 o 54 XE-135 6.429E+91 AGGREGATE SDURCE TERM.

S 54 XE-135 M 3.840E+91 :ag ;.

$ 54 XE-137 2.849E+99- 1H- 3 2.2569E+91 _

. H 54 XE-138 5.690E+91 - 18 AR- 41 1.9390E+99 $

f C 2.799E-05 55 CS-137 24 CR- 51 6.9290E-03 e 56 BA-140 2.959E-04 25 MN- 54 2.9489E-94 ' A

$ 57 LA-140 4.249E-94 27 Co- 58 1.2313E-93 _

u 27 C0- 69 1.2352E-92 36 KR- 85 M 4.3589E+91 t

SOURCE TERM (GROUND LEVEL) 1994 8SEP UNITS 1 AND 2 36 KR 4.3490E+91 "jj 36 KR- 88 6.5390E+91

+> 38 SR- 89 2.1569E-94 u . 38 SR- 99 2.4169E-96 o 53 I -131 2.1392E-93 -

% 1H- 3 6.999E+pe 53 I -132 8.9453E-93 a 24 CR- 51 3.259E-98 53 I -133 1.4986E '

b 27 Co- 69 4.859E-96 53'I -135 8.3559E-93 0 36 KR- 85 M 5.389E+99 54 XE-133 5.7790E+91

, 38 SR- 89' .3.320E-95 54 XE-135 1.4174E+02 o 38 SR- 99 1.140E-97 54 XE-135 M 6.4200E+91:

g 53 I -131 2.620E-95 54 XE-137 2.8400E+99-53 I.-132 o :8.830E-05 54 XE-138 5.6800E+91-

u) 53 I -133 1.769E 1.1382E-94 55 CS-137J i 53 I -135 1.983E-94 56 BA-149 2.9618E 54 XE-135 3.740E+09 57 LA-149 4.2519E-04 55 CS-1371 15.230E-97 58 CE-144 1.6800E-96' 56 8A-149 1.180E-96 95 AM-241 _1.4690E-94 57 LA-149 1.199E-96.

L 58 CE-144 1.680E-96

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-.__...___________________________..__r-__ - -

_m m-1-_ m - * / % 9 - + ~ . - 4

CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING' .

-RUN DATE: - 02/23/95

-CASRPT 'ALARA ANNUAL INTEGRATED POPULATION DOSE

SUMMARY

(MANREM) RUN TIME: 16:47:31 -

1994 SOURCE TERM (ELEVATED M30E) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 1994 BSEP UNITS 1 AND 2 m BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS CASEOUS RELEASES, 1994 5

3 N TOTAw BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG'- SKIN = .

O ** TOTAL ** 7.029E-02 6.801E-02 1.416E-01 1.191E-01 8.995E-02 7.203E-02 7.395E-02 '9.884E-02 e

$ PLUME 1.771E-02 1.771E-02 1.771E-02 1.771E-02 1.771E-02 1.771E-02 1.798E-02 4.158E-02'

, 25.195 26.04% 12.511 14.875 19.68% 24.58% 24.32% 42.075 s fCROUNDPLANE 4.556E-02 ro.556E-02 4.556E-02 4.556E-02 4.556E-02 4.556E-02 14.556E-02 .5.360E-02 x 64.825 66.99% 32.18%- 38.265 50.65% 63.25% 61.61% 54.23%

e kINHALATION 5.989E-03 2.986E-03 7.794E-02 5.469E-02 2.573E-02 5.356E-03 9.575E-03' 2.838E-03 8.52% 4.39%. 55.045 45.935 28.61% 7.441 12.955- 2.875 VEGETATION 9.364E-04 1.554E-03 3.898E-04 1.026E-03 8.760E-04 3.151E-03 7.561E-04 7.526E-04 8 1.33% 2.28% 0.285 0.865- 0.975 4.375 1.02% ; 9.765 -

d COW MILK 1.737E-05 1.865E-05. 1.793E-06 1.792E-05 1.729E-05 ~ 1.499E-04 1.636E-05' .1.623E-05 '$

g 0.02% 0.03% 0.00% .- 0.02% 0.02% 0.215 0.02% 0.02% . ,

U MEAT & POULTRY 7.778E-05 1.848E-04 2.528E-06 6.810E-05 5.930E-05 1.060E-04 5.854E-05 5.840E-05 N

,$ .0.11% 0.27% 0.00% 0.06% 0.07% 0.15% 0.085 0.06%

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CP&L SEMI-ANNUAL-RADIOLOGICAL EFFLUENT REPORTING RUN DATE: -02/23/95 g CASRPT ttADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 16:47:31

$ 1994 Soup CE TERM (ELEVATED MODE) BSEP UNITS 1&2 j SOURCE TERM (GROUND U: VEL) 1994 BSEP UNITS 1 AND 2 w BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES, 1994 SPECIAL LOCATION ttETERS DIR PL GR IN Y CM GM M y #36 COW MILK 7644.0 NE O 1 1 1 1 0 0 e

ANNUAL BETA AIR DOSE = 9.380E-04 MILLRADS aI ANNUAL CAMMA AIR DOSE = 1.296E-03 MILLRADS o

$ TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN ADULT 2.603E-03 2.808E-03 4.399E-03 3.955E-03 3.133E-03 3.906E-03 2.618E-03 2.853E-03 y GROUND PLANE 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.603E-03 L INHALATION 1.564E-04 7.760E-05 2.074E-03 1.468E-03 6.958E 1.333E-04 2.275E-04 7.320E-05 g VECETATION 1.820E-04 4.492E-04 1.027E-04 2.185E-04 1.718E-04 4.602E-04 1.330E-04 1.321E-04 COW MILK 5.367E-05 6.902E-05 1.011E-05 5.587E-05 5.273E-05 1.101E-03 4.535E-05 4.460E-05 TEENAGER 2.665E-03 2.856E-03 4.547E-03 4.109E-03 3.216E-03 4.523E-03 2.745E-03 2.886E-03 C o GROUND PLANE 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.603E-03 4 E INHALATION 1.618E-04 7.778E-05 2.185E-03 1.555E-03 7.311E-04 1.522E-04 3.196E-04 7.367E-05 e VEGETATION 2.206E-04 4.7B8E-04 1.316E-04 2.628E-04 1.995E-04 4.243E-04 1.529E-04 1.513E-04 y j COW MILK 7.019E-05 8.709E-05 1.812E-05 7.793E-05 7.257E-05 1.734E-03 5.965E-05 5.810E-05 A CHILD 2.822 E-03 2.838E-03 4.175E-03 3.841E-03 3.123E-03 6.462E-03 2.818E-03 2.994E-03 GROUND PLANE 2.212 E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.603E-03

$ INHALATION 1.365E-04 6.676E-05 1.696E-03 1.116E-03 5.015E-04 1.623E-04 2.748E-04 6.514E-05 "0 VEGETATION 3.627E-04 4.477E-04 2.232E-04 3.866E-04 2.928E-04 6.541E-04 2.368E-04 2.343E-04 COW MILK 1.105E-04 1.113E-04 4.326E-05 1.259E-04 1.158E-04 3.434E-03 9.417E-05 9.179E-05 c

INFANT 2.448E-03 2.407E-03 2.970E-03 2.883E-03 2.602E-03 1.060E-02 2.542E-03 2.780E-03 0

GROUND PLANE 2.212E-03 2.212E-03' 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.212E-03 2.603E-03 H INHALATION 6.60f.E-05 3.802E-05 6.809E-04 4.592E-04 2.095E-04 1.266E-04 1.858E-04 3.746E-05

$ COW MILK 1.692 E-04 1.566E-04 7.640E-05 2.113E-04 1.802E-04 8.261E-03 1.436E-04 1.393E-04 .

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, ' CP&L' - SEMI-ANNUAL RADIOLOGICAL EFFLUENT ~ REPORTING RUN DA'TE: 92/23/951 l GASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME:.- 16:47:31' 1 1994 SOURCE TERM (ELEVATED MOEE) SSEP UNITS 1&2 X" SOURCE TERM (GROUND LEVEL) 1994 8SEP UNITS 1 AND 2 BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEOUS RELEASES,.1994 a

- y; SPECIAL LOCATIDN METERS DIR PL GR IN . V CM GM M.

2 SITE BCUNDARY 1127.0 NME 1 1 1 1 1 1 1 e

d ANNUAL BETA AIR DOSE = 4.246E-93 MILLRADS

" ANNUAL GAMMA AIR DOSE = 4.939E-03 MILLRADS -:

i. e4

, Y TOTAL BODY GI-TRACT BONE LIVER- KIDNEY THYROID ~ ' LUNG SKIN ADULT 4.222E-02 4.728E-02 4.221E-02 4.529E-02 4.288E-02 7.984E 4.119E-02 5.947E-02 o

% PLUME 3.296E-03 3.296E-03 3.296E-03 3.296E-03' 3.296E-03 3.296E-03; 3.339E-93 7.186E-93 m GROUND PLANE 3.282E-02 3.282E-02 3.282E-02 3.282E-02 '3.282E-92 3.282E 3.282E-92? 3.861E-92. '

C INHALATION 1.198E-03 9.617E-04 3.893E-03 ' 3.570E-93 2.121E-03 1.138E-03" 1.259E-93~ 9.519E-04 :

$ VEGETATION 2.463E-93 6.445E-03 1.659E-93 3.099E-03 2.308E-93 .6.487E-03 "1.731E-03 1.718E-93' 4 COW MILK 7.135E-04. -9.442E-94 1.629E-04 7.448E-04 6.985E-94 1.59eE-02~ 5.999E-04 -5.799E-04-- -

GOAT MILK 1.419E-03 1.265E-03 3.715E-94 1.536E-93 .1.384E-03 1.956E-92 1.216E ' 1.183E-03 y MEAT k POULTRY 4.083E-94 1.556E 2.286E-05' 3.317E-04 2.548E-04 6.439E-04 2.481E-84 -2.469E-94 TEENAGER 4.324E-92 4.762E-02 4.333E-92 4.699E-02 4.401E-92 9.947E-02' 4.211E-02' 5.116E-02 $.

O PLUME 3.296E-03 3.296E-03 3.296E-03 3.296E-03 3.296E-03 3.296E-03 3.339E-03 7.186E-93 * .

F . $ GROUND PLANE 3.282E-92 3.282E-92~ 3.282E-02 3.282E-92 3.282E-92 3.282E 3.282E-92-- 3.861E-92 ?

INHALATION 1.124E-93 4.192E-93 .3.738E ' 2.192E-03

VEGETATION 9.673E-94 1.202E-93 1.433E-93. 9.579E-94' 3.9%E-03 6.854E-03 2.139E-93 3.623E-93 2.683E-03 5.937E-93 1.991E-93L '1.967E-93;

' N COW MILK 9.349E-04 1.188E-03 2.997E-94 1.946E-93 19.663E-94 2.597E-92 7.781E-94 : 7.554E-04 x GOAT MILK 1.795 E 1.645E-83. '6.673E-94 2.164E 1.899E-93 3.071E-92 1.699E-93 1.541E .o MEAT & POULTRY 2.727E-04' 8.516E-94' 1.773E-95 2.128E-94 1.533E-04 4.342E-04~ 1.484E-94' 1.473E-94 C e -

g CHILD _ 4.661E-92 '4.773E-92 ~4.536E-92 - 4.970E-92 4.645E-92 1.574E-91 4.444E '5.356E-02 o

PLUME 3.296E-93 '3.296E '3.296E-03 3.296E-03 3.296E-03 3.296E-93' 3.339E-93. 7.~186E-93.

D GROUND PLANE 3.282E-02 3.282E-92 :3.282E -

3.282E-02 3.282E-92 ~3.282E-02 3.282E-92; 3.861E-92:

d INHALATION -9.813E-04 '8.599E-94 3.186E-03 2.820E-93 1.667E-93 11.148E-93 . 1.252E-93 ;8.471E-941

$ VEGETATION 4.969E-93 6.234E-03' 3.737E-93' 15.396E 3.915E-03: :9.155E-931 ' 3.983E-03e 3.047E p COW MILK 1.471E 1.485E-03 6.951E-94' '1.692E-93 1.544E-03 4.970E-92 1.228E-93 1.194E-93'

,8 COAT MILK 2.710E-93 2.512E-93 1.597E-93. 3.516E-93 3.929E-03 J6.964E-92 '2.539E-93 .2.435E ~

, MEAT & POULTRY 3.698E-94 a5.336E-94 2.999E i 2.565E-94 " 1.859E-94 6.110E-94~ 1.792E 11.779E -

3 o .

'y INFANT 4.2980-02 4.244E-02 4.137E-92 4.615E-02 4.492E-92' 3.017E-94 4.269E : 5.179E-02 L

!' PLUME -3.296E-93 3.296E-03'L 3.296E - 3.296E-03' 13.296E-93: 3.296E-93 .3.339E-03' -. 7.186E-93 .

GROUNO PLANE 3.282E-92 3.282E-921 '3.282E-92J 3.282E-92 -3.282E-02 3.282E-92 3.282E 3.861E-92

- INHALATION .5.411E-94 ' 4.885E-04'. :1.289E-03 '1.279E . 8.195E .7.539E-04 :7.752E-94 4.871E-04:

; COW MILK 2.254E-93 -2.971E-93~ 1.234E-93: :2.864E-93' ~2.498E-931 '1.197E-91 1.874E-93 1.811E-93 l $ GOAT MILK '4.975E-93 '3.768E-93 2.742E-93: 5.896E-93 '4.699E-93: 1.452E-91: '3.883E 13.694E-93 i

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CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING ftUN DATE: 02/23/95 E CASRPT RADIATION DOSES AT SELECTED LOCATIONS 'H!N TIME: 16:47:31 e

b 3o 1994 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 SOURCE TERM (GROUND LEVEL) 1994 BSEP UNITS 1 AND 2 g BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS GASEDUS RELEASES, 1994

SPECIAL LOCATION METERS DIR PL GR IN V CM CM M

$ #18 RESIDENCE 1448.0 NNE 1 1 1 0 0 0 0 ANNUAL BETA AIR DOSE = 3.228E-03 MILLRADS ANNUAL CAHMA AIR DOSE = 4.010E-03 MILLRADS TOTAL BODY CI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN o ADULT 2.779E-02 2.768E-02 2.993E-02 2.960E-02 2.853E-02 2.781E-02 2.792E-02 3.498E-02 m PLUME 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.712E-03 5.686E-03 D CROUND PLANE 2.437E-02 2,437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.867E-02

$ INHALATION 7.361E-04 6.279E-04 2.875E-03 2.554E-03 1.484E-03 7.578E 8.406E-04 6.206E-04 o

U TEENAGER 2.780E-02 2.768E-02 3.008E-02 2.973E-02 2.859E-02 2.785E-02 2.806E-02 3.498E-02 e

$ PLUME 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.712E-03 5.686E-03 GROUND PLAN'? 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02' 2.437E-02 2.867E-02 W 3 INHALATION 7.469 E-04 6.315E-04 3.029E-03 2.678E-03 1.536E-03. 8.036E-04. 9.753E-04 6.245E-04 e S 4

_e CHILD 2.770E-02 2.761E-02 2.940E-02 2.906E-02 2.821E-02 2.782E-02 2.793E-02 3.491E-02 $

A.

$ PLUME 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.712E-03 5.686E-03 e-4 GROUND PLANE 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.867E-02 o INHALATION 6.514E-04 5.551E-04 2.352E-03 2.009E-03 1.158E-03 7.732E-04 8.514E-04 5.523E-04

.c INFANT 2.741E-02 2.737E-02 2.800E-02 2.795E-02 2.761E-02 2.757E-02 2.761E-02 3.468E-02 tc M PLUME 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.679E-03 2.712E-G3 5.686E-03 m GROUND PLANE

INHALATION 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2.437E-02 2,437E-02 2.437E-02 2.867E-02 3.574E-04 3.186E-04 9.448E-04 9.024E-04 5.564E-04 5.201E-04 5.301E-04 3.176E-04 8

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CP&L SEMI-ANNUAL RADIOLOGICAL EFFLUENT REPORTING RUN DATE: 02/23/95 CASRPT RADIATION DOSES AT SELECTED LOCATIONS RUN TIME: 16:47:31 1994 SOURCE TERM (ELEVATED MODE) BSEP UNITS 1&2 o SOURCE TERM (GROUND LEVEL) 1994 BSEP UNITS 1 AND 2 j BRUNSWICK UNITS 1 AND 2, MIXED MODE CONTINUOUS CASEDUS RELEASES, 1994 x

0 SPECIAL LOCATION METERS DIR PL GR IN V CM GM M 4 # 2 SITE BOUNDARY 1127.0 NNE O 1 1 0 0 0 0 o

ANNUAL BETA AIR DOSE = 4.246E-03 MILLRADS ANNUAL CA7MA AIR DOSE = 4.939E-03 MILLRADS

+2 TOTAL BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN Y ADULT 3.392E-02 3.378E-02 3.671E-02 3.639E-02 3.494E-02 3.395E-02 3.407E-02 3.956E-02 Es o G~.00ND PLANE 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.861E-02 y INHALATION 1.108E-03 9.617E-04 3.893E-03 3.570E-03 2.121E-03 1.138E-03 1.250E-03 9.519E-04 TEENAGER 3.394E-02 3.378E-02 3.692E-02 3.655E-02 3.501E-02 3.402E-02 3.425E-02 3.957E-02

$ CROUND PLANE 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.861E-02 4 INHALATION 1.124E-03 9.673E-04 4.102E-03 3.738E-03 2.192E-03 1.202E-03 1.433E-03 9.579E-04 m

s _:t M

a CHILD 3.380E-02 3.367E-02 3.600E-02 3.564E-02 3.448E-02 3.396E-02 3.407E-02 3.946E-02 e ec -

$ GROUND PLANE A INHALATION 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.282E-02 3.861E-02 $

9.813E-04 8.509E-04 3.186E-03 2.820E-03 1.667E-03 1.148E-03 1.252E-03 8.471E-04 INFANT 3.336E-02 3.330E-02 3.410E-02 3.410E-02 3.363E-02 3.358E-02 3.359E-02 3.910E-02

GROUND PLANE 3.282E-02 3.28cc. v2 ; .C;'.!

. ;C 282E-02 3.282E-02 3.282E-02 3.282E-02 3.861E-02 2 INHALATION 5.411E-04 4.885E-04 1.280E-03 1.279E-03 8.105E-04 7.630E-04 7.752E-04 4.871E-04 H

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~ O

' INPUT SOURCE TERMS RUN TIpE: - 13:26:55- -

CASRPT

~

. --.hI c

SOURCE TM'(INCINERATED OIL) :BSEP UNITS 1 ADO 2 1994 _

2. .

. 27 CO- 60 4.850E-96 ~

4

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UD LE FT 5 5867 5 5867 5 5857 5 58 FC 0 0000 0 0000 0 0000 0 - - -

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L EE EEEE E EEEE E EEEE E EE 5 20 LE V8 2200 0 2196 3 2014 AS I7 4484 8 4173 9 4101 4 44 C L5 1584 7 1895 1 1605 1 13 IT 4 GA 9 M1 8 8334 8 8453 9 8414 8 83 O 9 LS 1 OE M0 IS 2 G 5 5867 5 5867 5 5867 5 58 DD 0 0000 0 0000 -

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RN EE G IN 00 9 8113 9 8111 8 8478 8 81

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R OO T5 1743 5 1465 6 1697 1 15 _

E N DD O N O T8 8235 8 8233 8 8144 8 87 _

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ATTACHMENT 7 (cont)

ENCLOSURE 3 Dose Assessment Summary 1 I. Liquid Effluents:

Maximum Dose to Individual: (mrem) Limit: (mrem)

Adult.GI-LLI 6.71E-04 2.00E+01 l

Child Total Body 5.32E-04 .6.00E+00 II. Gaseous Effluents:

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

Gamma 5.16E-03 2.00E+01 ,

Beta 5.94E-03 4.00E+01 Iodine-131. Iodine 133. Tritium and Particulates: (mrem)

(Limit 3.00E+01 mrem)

Maximum hypothetical dose at site boundary: Infant thyroid 3.02E-01 Estimated dose for existing pathways at site boundary: Teen skin 3.96E-02 Max' mum hypothetical dose at 4.75 miles for cow milk pathway Infant thyroid 1.06E-02 Estimated dose for existing pathways Teen skin 3.49E-02 Lower total I-131 emission due to improved. fuel performance from the elevated mode, and higher total Co-60 emission from the in-vessel outage work from the mixed mode, resulted in a lower relative dose at the " hypothetical" cow milk pathway location in 1994. The source term mix, and not a change in the use of land, resulted in the locations below to have a calculated dose higher than the dose determined for the cow milk )

pathway. '

ho_qation Dose 0.9 mile NNE 3.49E-2 mrem skin 1.0 mile SW 2.78E-2 mrem skin 12 mile NNE 2.57E-2 mrem skin Page 47

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ATTACHMENT-8 Off-Site Dose Calculation Manual (ODCM) and Process ' Control Program (PCP)' Rev'isions:

~

^ -

. ; duly- '1, to December 31, 1994

.Brunswihk Steam Electric Plant There were no revisions made to the Process Control Program-during.this. reporting period.

Revision 16Ewas'made to the Off-Site Dose Calculation Manual during this time period. The'.following changes _were made:i

1. Updated' Table 3.2-2 to concur with'the_: latest' Land Use e: -

Census Data. -(page 3-30).

2.'Added approval signature and effective'date t'o'the. cover -

page,

3. Designated the equation on.page 3-6 as "3.1-8."-

4. ChangedLterminology of " Hot Shop" to'" Decontamination-Facility" to enhance accuracy of description. Also? deleted ,

o reference to tritium'being released from the1decon facility and incinerator to enhance' accuracy.. Changes were'made to' i pages 3-22 and 3-42. ,

a

5. Corrected typographical error in equation - 3.3-14.~ (page 3-42)' L

}

q A copy of Revision'16 to the ODCM'is included as a part of=this-

. attachment.

Page 48

,L- n ,.L,. .~L. w.-.-

. . . - , , , , , - ,,,,, ... ~ ,- . - . . . a > --1,,.. , ,

. i ATTACHMENT A REQUEST.FOR OFF SITE DOSE CALCULATION MANUAL CHANGE Originator: Grant Raker Date: 12-9-94 Rev. _16 Pages and Sections Revised: Cover oace eaces 3-6r 3-22r 3-30; 1-Al Reason for Change: Add sionature and ef fective date to cover oacer ' desiemmte ecuation on caoe 3-6 as "3.1-0;" chance wordino from " Hot Shoo" to

" decontamination facility" to enhance accuracy of descriotions deleted i

reference to tritium beina released from decen facility and incinerator (o3-22 and 03-42) to enhance accuraevr undated Table 3.2-2 to concur with latest fand Use Census Data _

Safety Analysis. Completes (N b Date: /2 -9 REVIEWS-A~' " ed,/Not Recomended Date /Z.! hY 1st Safety Reviewer bl.50so. b nded/No Recomended Date: /2 !/I[N -

2nd Satety Reviewer N bcommended/otRecommendedDate: / L /45 [7(

alist "E&C ProjecV S

'Y

_ mmend NotRecommendedDater/O/8f[

' Operations - pInciai Projects s0/>b mm Not Recommended Date: /7//[![k E&C #anager APPROVALS-8)tf - commended ot Recommended Date: 1 Z!ZO[9 */ -

t f [; / Man

~

r - E&RC (

V Not Recommended Date:

PNSC irman \

f ,

s mmende et Recommended Dater i Plant General Manager 0-E&RC-4261 Rev. 1 Page 6 of 7 y g n - - - - - ,

p;[ ;g.

, , ATTACHMENT 2-(Ccnc*d)- ,

RETISICW 3 ' 10CFR50.59 PROGRAM MANUAL .Page SS-ATTACHMENT A

~

IP&L 3AFETT REVIE7 FACKACE Page i of 7 SAFETT REVIEW CCVER SHEET 00CUMENT ;0. M b c b O d b h w d (DD REV. 1;0. Ib

, -DESCRIPTION OR TITLE:

1. Assigned Responsibilities:

( Safety Analysis Preparer: frf oA h%r-

. 14ad 1st safety Reviewer: ( s %We RdV~ -

2nd Safety Reviewer: foencoe E m > *. d

2. Safety Analysis Preparer: Complace FAYT

SAFETY ANALYSIS Safety Analysis ~Preparar b

a sA A ut.

/ a[fmr. t/9[

3. Lead 1st Safety Reviewer: :omoleta Part II. Ites Classification.

6 Imad 1st Safety Reviewer: Part III may be complaced. If either question 1 or-2 is *yes." then Part IV. is not required.'

5. Land 1st Safety Reviewer:

of this ites (including own) Determine and mark which DISCIPLINES the appropriate are req)uired block (s below.for review DISCIFLINES Reauired: (Prine N== ) Siem eura/n. -(Stan 74-t~ () Nuclear Plant Operations

() Nucleat Engineering

() Mechanical

() Electrical ,

' " ~ ~ ~ ~ ~

() Instrumentation & Control-() Structural

() Metallurgy h{ Chemistry / Radiochemistry- Gfd+ k V .b k1. /M84/W

() Health Phys'ics

[] Administrative Controls

6. A QUALIFIED SAFETY REVIEVER will be assigned for each DISCIPLINE marked in -

step S and his/her name erint9d in the space provided. Each person listens shall perform a SAFETY REVIEW and provida input into the Safety Review -

Package. -

7. The laad 1st Safety Reviewer will-' assure that s'Part III or Part IV is e laced (see step 4 above) and a Part VI if required (see 9.d of Part II). .

erson listed in step 5 shall sien and date next co his/her name in step 5, i cating completion of a SAFETY REVIEU.

8, 2nd Safety Reviewer: - Perform a SAFETY REVIEW in accordance with Seation 8.0. '

2nd Safety Reviewer _b s . . L' u Date it-NM DISCIFLINE: chdab

9. PNSC review required? If "yes," attach Part V and mark reason ' Igg 'dg, below:

R' L Potential UNREVIEVED SAFETT QUESTION Question 9 of Part IV answered 'Yes" O Al-109 Rev.(

Ogther (specifv) ODLm ec4..M t o ., # 9 %c u c4.d b1 TcA e

\ rass 7 4 'E **

j

- fy, .

j

+ ~*: 1 a '

6 J' H ATTAC10ENT :2' (Cent'd) k' 1

1

i 1

, 1

.a REVISION 3 1 10CFR50.59 ' PROGRAM MANUAL Paste . 56 .

ATTAC10ENT A CPM. SAFEIY REVIEV PACKAGE Page 2-- of '

i

-i FART I: SAFETT AM& LYSIS (See instruccions in Section 8.4.1)

(Attach additional sheets: as necessary.)

DOCUMENT No. O C) c t<'\ - REY. No. It DESCRIPTION OF CHANCE: Ahe.h hee 69.e 'e (04ad.e. Dod= % c our *o.e . A.a 1,o Q '

s ~

WouM em O% % . $ "'

C' hh t db UJQ th *N a f% O hei 1*Et N Of C%Meb ~ &CtV NN f b%'T w ,,

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h chm d.A k% T(4 O O( % *

iT h f C 44;p kf sqWe h*OC [8 h th 4 W4 L& M kg k 9 thi 9 la.4,abh o e4wh *t Nk El-7 % <-4 see td%v w&uw or.aw A.A., .

ANALYSIS: he eb np mon e m -('.'6 M W o.ee h Es *A eelv t ik e cc. am.M J.o rot cche.- -Hsc 'ar m ce ee ce a wt A ,& Aou c ecuss w em me e e 4,4-A 4ie< M eest'g u h ch as.8heh an s Inn +4 tit, k u Nec4 O e' A*%e da "the.

E- O eP h % % 6 (N 8 M %NN =- b hee s Weet VAthe mcM[n e. er\ W re.ewwsrds 40 f'\ n tm3 k e. M s bitt d.u . N-

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n Of* # C' O. f- %.lo h O Mo&dit 'I'O$C. 3.1**l,, 4 (Chetd 4 M \ Mi fmin k W %_

cent.om 4's= % neares* g eds& vet g ar&<rsW EAk orv M '1 M m emus. o m E.. ,

b w ah4. h < snu s et co w*.h '., L ne. ivt4acAdJnM d m be -

cWW A \ v4<^4 a wth w ecidn(_ M 4 M r. 6 % be' uw 6 ' In % cLn n wh

~

b <.c. ew eed fb .i i4 twe+ u be u ,See m.\ In -h h % e* Mien M raAM,,.1 e c%4 ce.

oe A.h e c %d AA J,u u.b m a. *eede b I O k% N k* =

m uss eMng= s h e na t~ iA4 o.4- Ot&M wf.w e , A4,A ,wM A %+-h=4 - - -

g T he c.c4,a. b c.S .ac..n r.A % A G,4 3. ,3 t. n s\MM me6. was h,1*=n-% ' ma'*

s =* 4 elm \ %ew. , #c.cs Mc.+.' a.= (An o % n g .C* h ' tw \e %ek 4 [a, inc.nt<Eb'*o "t hMb TM b(BOT % %9% N4.

f% F @g M p3h ,{ (Ig te (Y

) u 5.

REFE13NCES:

sote - t*

v u u 4 S w m e,< s T,eh snes 3/4.iz.2_. 3/4 's. t c, . t 3

< s l'

l '

O AI 109 Rev. 002 Page 73 of 86 l

. . _. _ . . . . . =

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

' f:

J*f ATTACHHENT 2 (Canc'd)

RETIBION 3 10CFR50.59 PROGRAM MANUAL Page 57 ATTACHNINT A CP&L SAFETY REVIEV PACKAGE Page l of ,~1,,

PART II: ITEM CIAs5IFICATIDW DOCUMENT :0, O DC m REV. ::0. -\ U2 3 g- g '

a f

1. Does this ites represent:

a. A change to the facility as described in the SAFETY ANALYSIS REPORT 7 [] . P$ .

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

()- M

. c. A test or experiment-not described in the SAFETY-ANALYSIS REPORT 7 {} X ,

2. Does.this item involve a change to the individual' plant Operating License or to its Technical Specifications? (} N

3. Does this ites require a revision to the FSAR7 () M <

4 Does this ites involve a chan5e to the Off-Site Dose -

Calculation Manual? M []

'5.

Does this ites constitute a change to the Process Control' -() ($

Program?

6. Does this ices involve a majo'r change to a.Radwaste Treatment '()

Systemt (4

7. Does this ites involve 's change to the Technical-

. Specification Equipment List (BSEP and SHNPP only)? () S

8. Does this item impact the NPDES Persic-(all 3 sites) or

() (41 constitute- an "unreviewed envirotusental question" (SHNPP Enviromental Plan. Section 3.1) or a "significant environmental impact * (BSEP)?.

9. Does this ites involve a change to a previously' accepted:

a. Quality Assurance Program

b. .M.

security Plan (including Training, Qualification, and M

. Contingency Plans)7

c. Emergency Plan?

d.

Independent Spent Fuel' Storage Installation license? . ,.

f A

(If *yes." refer to Section 8.4.2 " Question 9,"_ for

.special considerations. Completa Part VI.in accordance with Section 8.4.6)

SEE SECT 40N 8.4.2 TOR INSTRUCTIONS FOR EACH "YES" ANSVER.

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

% OkM k bt A abid 4 M& q . \ u. Cusa t h w hh Cou s a i .L - t A . t . [D '

/

l O AI 109 Rev. 002 Page 74 of 86 g l

M+ "

W "'

'Q:,. '

~ *

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l

ATTACIDENT 2 (Ctne'd) . 1 Y

': $.. S' L RETTSION 3L 10CFRSO.59 PROGRAM MANU1Zs Page-58.

ATTACiOGNT A CP&I.-SAFETY REVIEW PACKAGE: .Page k of N PART III: UIREVIEWED SATITY QUESTION DETIIMINATION SCRIII

'V 1

DdCL7.ENT:0. O oc.m - : azV. ::0, ~ l (, '

I

. Y31 '21 J.

1

1. Is this change fgilt addressed by ~another completed [] -X: l UNREVIEVED SAFETY QUESTION determination? (See '

~ -

Sections 7.2.1. 7.2.2.5. and 7.1.1.1)

RETIKENCE DOCUMENT; REV ::0. l l

3 .

ISK. 'dA

2. For procedures, is the change a non-intent' change ..

which 2n11 (check all that apply);' (See Sectica 7.2.2.3)- ;[]- M i

[] Corrects typographical. errors which do' not alter '

the meaning or intent of the procedure; or,

() Adde or revises -steps for clarification (provided they are consistant with the . original purpose ~ or ' '

2 applicability of tho' procedure);. or,

[]

4 '

Changes the title of an organizational position; or.

() Changes names, addresses, or telephone numbers of persons; or.

[] Changes the designation of an ites of equipment'where the equipment is the same as the original equipment or is an ,

, authorited replacement; or. -

[] Changes s specified cool or instrument' to an equivalent -

substitute; or, E [] 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? '

11f the answer to either Question 1 or Question 2 in PART III is "Yes,a than PART 17 s ,

need not be. completed.

O AI-109 Rev. 002 Page 75 of 86.

~

l i.

T

4 f* , ,'

+. ,a .

b -ATTACHMENT.2L(Cent'd) l

.iyY .i y _

c '

RETTSION 3 10CFR50.59 PROGRAM'MANU1L ;Page 59 4

ATTACHMENT.A .

-i CP&L SAFETY RCVIEW PACKAGE' Page 1 of T PART IV: UEREVIEWID SAFETT QUESTION DZTrnu m TION DOCUMENT NO. m& REV. No. f (<3 Using the SAFETY A.utYSIS developed for the change, test or experiment, as well'as'~ '

other ;equired references (LICENSING BASIS DOCUMENTATION, Design Drawings. Design' 3 asis Docuraents. codes, etc. ), the preparer of the Unreviewed Safety Quassion Determination must directly answer each of the following seven questions and maise a determinatiot. of whether an UNREVIEVED SAFET) QUESTION exists.

A VRITTEN BASIS IS REQUIRED FOR EACE ANSWE1 IRE CL

1. May the proposed activity increase the probabilic; of

() X occurrence of an accident evaluated previously in the SAFETY ANALYSIS REPORT 7 -

Cww- % we.

stv d An.a AC.. h.1 h

%4 b_ t .h. m.o .14 me.bn A tsm %[od .

,,c,. . #u.m. w e M M .* osom w i o& A or c'e 1 6 e w hbl e.d4 . *

.,+s, hn s

2. May the proposed activity increase che' consequences of an

)

{]. . M, accident evaluassa previously in the SAFETY ANALYSIS REPORT 7 '

see .4e% ui

?

3. May the proposed activity increase the probability of -

occurrence of a malfunction of equipment important to

- (1 % ,

safety evaluated. previously in the SAFETY ANALYSIS REPORT 7

, i w. 9 o m. h c % e,.' a W .h.J. M . Ao vs. cocm

, M . M ;,,a,e su s', Q . e .cc e u t. m . d 24 . .,,_u . m a n-. Ja1 we 4 U-( tub a -

nn+ + . e . u %. n i s w 12.rt f ner o < s m,( ,J e ea\Caech 3- 3 %U ' PE 'd ' 7 c O*"

t. .

-*.4c.c h 4 w. imp.,-.4% w g,a1\ qvym-4.

' May t e proposed activity increase the consequence of a .(}' M>

malfunction of equipment important to safety evaluated previously in the SAFETT ANALYSIS REPORT 7 ,

.5 u- u3 i

?

.i

5. May the proposed activity create the possibility of an . Il ~(4 +

accident of a different type than any evaluated previously +

in the SAFETY ANALYSIS REPORT 7 3 T ws. is' <6 m .s.b . 6 . c % A m w d a c a t J d e A- b ^

d < -

c.... v A ,c. - _ch u - ,. u -(ne.r -(.3

.'O AI-109.Rev. 002 Page.76'of 86 >

{

')

, , + , < ~ ~ ~ _ . . , . . . . -. .i . - ~ . . , - - . ' . _. . . . _ _ . .

_,, ,,: .. , ,~

-w - - " '~ ' -

+

, y, ,

j

, 4 ATT/.CHMENT. 2 ;(Cant' d) xs <

.e v : REVISION 3' *

- 10CFR50.59) PROGRAM MANDRI' Page:60-ATTACHMENT A' CP&L SAFETY REVIEV PACKAGE Page ,,jglL, ofi !

i'

.s FART IV: (Continued)

$ DOCUMENT NO. oOcW REV. NO. $ .

. h ~Hal -

6. w

..ay the proposea activity create the possibility of-a' []. -[4 malfunction of equipment important to safety of a different cype than any evaluated previously in tho' SAFETY ANALYSIS REPORT 7 -l i

s.. A y 4 7. Does the proposed activity reduce the margin of safety as '();

defined in the basis of any Techn!. cal Specification? 0(

'tw .1 t el.s.6 -4 6p ~ed % e ~ mdte me-unor d=AwAdaY i.

} r. w..M v i.ka.: n '

s

8. Based on the answers to questions 1 -' 7 does this item '() 'M result in an UNREVIEVED SAFETY QUESTION 7 If the answer to '

any of the questions 1-7 is "Yes," then the item is '

considered to constitute an UNREVIEVED SAFETY QUESTION. :

9. Is PNSC review required for any of the following reasons 7 () [A If, 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 scill less than the NRC ACCEPTANCE LIMIT: or, in-answering quostion 7 "No," a parameter would be closer to the NRC ACCEPTANCE LIMIT. but the end result was '

still within the NRC ACCEPTANCE LIMIT; then PNSC review is required.

, REFCRENCES:

r s a s. a-% m.o e o,m %k co .u dy . n .ih . s t <

c, .9 ,1. ?

1 This Unreviewed Safety Question Determination is for the following DISCIPLINE (s):- 4 (Additional Part IV forms may be included as appropriate.) -

Nuclear Plant Operations '

Structural !

Nuclear Engineering Metallurgy '

'l Mechanical % Chemistry / Radiochemistry Electrical ~

Health Physics Instrumentation & Control Administrative Controls j 0 AI.109 Lev. 002 Page 77. of 86 l- ;

8 i

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<x.

7. ,

i i,i ..... X * ',.

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.>1 BRUNSWICK STEAM ELECTRIC PLANT 4' OFF-SITE DOSE CALCULATION ^ MANUAL (ODCM)

- REVISION (16 DOCKET NOS. 50-324 50-325

/

CAROLINA POWER & LIGhi COMPANY Effective Date 12.-31-44 f fi Approved By:

PNSC i.

p;m- t tw ~ _

+g ,.lp, ?*.? ,

,j 4

) 45 . j u <

'"1 j

[. u '

LIST OF EFFECTIVE PAGES ODCM~

i

' Pare (s)- Revision.

.ll

l. if, >

16-1 11 -15: *

[/

t l

,-j7 iii.

ty.

'14 15, <

o .v-viii 14 '

.1-1 2-1~ 14 2-2 2 8~ 15 2-9 14 2-10 15 2 2-15 '14

~'

.3 3-5 4 '

36 e 16 ~l 1 3-7'- 3-12 '4 3-13 1 3-14 4 -

3-15 5-t 3-16 '3 4 3-19 6' 3-20 1 3-21 8 3-22 16 li >

3-23 1 3 24 4-3-25 1 3'26

- 4 1 3-27 6 't.-

3-28 8 3-29 1 I

3-30 16 3-31 .4 3-32 1 3-33 .

14 3 3-36 1 3 3-38 4 3-39 6 3-40 7 3-41 1 l 3-42 16 3 43 45 1 3 3-48 4 3 49 ' 1' 3-50 3-68 14 4 4-3 11 4 7- >

4-5 4 11 --

51 0 6 6-2 0 6-3 4 ODCM'(BSEP) i

.Rev. 16 ;

r - . .

O n _

,,;. m +

O

"' 500 ( 3.1~-8)

' De tv,Sj)

V, = The' constant for noble gas radionuclide i~ accounting.for the gamma radiation from the. elevated finite plume (ares / year /pci/sec) from Table 3.1-2.

3 3.1.2.3 Determine Q. based upon the skin exposure limit.

=

3000 (3,1 9)

De

((Ls (x/0), + 1.1Bj) Sj]

L (i7D), + 1.18 - The total skin dose constant for long-term releases i 3 (greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year) due to emissions from noble gas radionuclide 1 (aren/ year /pCi/sec) from Table 3.1-2.

HOIg: The' stack radiation monitor is d>esigned to input the monitor high-high alarm setpoint in pCi/see or pCi/cc. The monitor setpoint in pCi/see can be obtained by multiplying the lowest Q, value (obtained from Sections 3.1.2.2 and 3.1.2.3) by the T value . found :

in Section 3.1.2.5.b. The pCi/cc setpoint can be obtained by dividing the pCi/see setpoint by the design flow rate in ec/sec.

The equations for calculating the setpoint in cps are included for completeness and may be used if. desired.

3.1.2.4 Determine C (the total maximum acceptable radioactivity concentration of noble gas radionuclides in the gaseous effluent,.

pCL/sec/cfm). ,

)

3-6 Rev. 16 ODCM (BSEP)

n~

' ,3 C S* " ig - cres/yrcr_p;r pC1/ccc c-2 frr food cnd ground plcne pathways

=pj - The release' rate'of radionuclide i in gaseous effluent's

.s' h, from free-standing stack, pCi/sec

. O, -- The release rate of radionuclide i in gaseous effluents v-

'from all vents releases, pCi/see w, - The highest calculated annual average dispersion parameter for estimating-the dose to an individual-at the controlling location due to'all vent releases 4

W, - sec/m for the inhalacion pathway-2

- meters 2 forthekfoodandgroundplanepathways

~ ~

W, W, - The highest calculated annual average dispersion parameter for estimating the. dose to an individual at the controlling location due to stack releases-W, - sec/m for the inhalation pathway.

2

' W, - me ters-8 for the food and ground. plane pathways-j Radioiodines, particulates, and tritium may be released from the stack, i Reactor Buildings, and Turbine Buildings.at BSEP. -Radioiodines and l particulates may also be released from other sources such as the' ;

decontamination facility and burning waste oil in the incinerator. Effluents j from the decontamination facility and incinerator'are combined with the !

Turbine Bu(1 ding's vent releases. To show compliance with 10CFR20, (see I Appendix H for waste oil) Expression 3.2-9 is modified to incorporate'the l various release points for BSEP:

I I

i l

I ODCM (BSEP) 3-22 Rev. 16

f; J ,5 ,

TABLE 3.2-2 DISTANCE TO CONTROLLING LOCATIONS AS MEASURED FROM THE BRUNSWICK PLANT CENTER (Mi)

Site-: Milk -- . Milk. : Meat; 1 Nearest? :Nearesta

-- Sec tor '

'Goatl Animal ?Residenti fGardens l; ;., .. Cw -

-NNE 0.7 --

- - 0.9 1.2.

NE 0.7 4.75* - - - -

ENE 0.7 - - - - -

E 0.7 - - - - -

ESE 0.7 - - - 1.5 - ,

SE 0.7 - - - 0.9 -

SSE 0.7 - - - 0.9 -

S- 0.8- - - -

1.5 1.5 SSW 0.8 - - - 1.2 1.4 SW 0.7 - - -

1.0 1.9 WSW' O.7 - - - 1.0 1.0 W 0.7 -- - - 0.8 0.8 ,

. 3 WNW 0.6 - .

- 0.8 1.0 .

NW 0.6 - - - 0.9 1.0 NNW 0.6 - - - 08 0.6 N. 0.7 - - - 0.9 -

A " hypothetical" cow milk pathway is located at this point in accordance with ,

5.3.1 of NUREG 0133.

ODCM (BSEP) 3-30 Rev. 16

y, c , - . . ,. .

p, . .;

j@+

, e

? #r o @ - etc/m . for the 'inhalction ptthw:y and tritium a

meters 8 ' fori the food and ' ground plane} pathway

~' -;

^

1 vc .-

~

Th's dispersion parameter for estimating the' dose.to'en-individual at the! controlling location for.short-term vent

, releasest(equal to or lass than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months / year)-

- .sec/m ? for the inhalation pathway and tritium -

8 o .

meters 8 for the food and ground plane pathway

-3.17 x~108 - The inverse of the number of seconds ~ in- a year 4 - The dose factor for each identified radionuclida i of thel organ of interest; ares /yr per pCi/sec per a8 ,or mrom/yr:

~

per pCi/m 8 Radioiodines, particulates, and tritium may be released from the stack, Reactor Buildings, and Turbine Buildings'at'BSEP. Radiciodines'and

~

- .particulates, may also be released from other sources such as the.

decontamination facility and burning waste oil in.che. incinerator. Effluents, from the decontamination facility and incinerator are. combined with the:

Turbine Building's vent releases. Burning waste oil in t.he-incinerator is limited to 0.1% of.10CFR50 Appendix I- (see Appendix; H for methodology .and--

calculations). At BSEP all releases are considered long-term in duration.

Therefore, incorporating thevarious release points;into Expression 3.3-13 results in the following expressions;to show compliance with 10CFR50 for a particularLorgan:

-3.17 x 104 I,R[W,Q4 +

i W. (Qi + Qi. ).+ W. (Qi .+ Qi' .[

) ,

s rbi rb2' tb1' 'tb2 s 15.0 arem per quarter or 30 mrem per year' (3.3-14)

'0DCM (BSEP)' 3-42 Rev. ' l'6 -

BSEP-95-0057, Semiannual Radioactive Effluent Rept,940701-1231

Text

SUMMARY

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BSEP-95-0057, Semiannual Radioactive Effluent Rept,940701-1231

Text

SUMMARY

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