ML20081F525

Radioactive Effluent Releases,Jan-June 1982

ML20081F525
Person / Time
Site:	McGuire
Issue date:	06/30/1982
From:	Tucker H DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8311030117
Download: ML20081F525 (9)

Text

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. . NCGDIRE NUCLEAR 5TATION i c 8A3101CT!vE EFFLUEIT REttAsts L

/ h EAltS SAft I 08/17/82 A} .

'- \ TEAR 3 1982 Us!t8 ist sie 2:3 stR sa:QtAt

1. 010$$ Ba8!OACf!V!ff A. IDTAL ttLEASE CUR!!S 2.12E 01 2.32E-Cl 4.44E-Of

8. AVERAGE CONCENTRAf!0N RELEASIS UC!/aL 8.44I-10 7.54E-10 s.04E-10 C. mAzinun CONCENTEAi!0s RELEASE 8 - UCI/AL 2,231 07 2.2ft Of 2.27t-07

2. It!!!U9 '

A. TOTAL RELEASE tut!!5 8.37E*00 3.40!*01 4.24Ee01

8. AVE & ACE ComCENitAi!CN RTLEA5tB UCI/ML 3.41C-08 1.11E-07 7.67t-08

3. 815SCLVt3 Nalit SASIS A. 10iAi LEitASE CU1!ES 2.78t-04 7.70t-04 1.05E-03

8. AVERAGE CONCENTRA!!CN RELEASID UCI/ni 1.13E-12 2.51E-12 1.90t-12

4. GEC$$ ALFLA 4 f!U!!T A. TOTAL EELEASE CUR!ES 0.00E*00 0.001600 0.00E+00

8. AVIEA0t CCsCIETRAT!CN RittA3t3 UC!/nL 0.00E+00 0.00E+00 0.00t400

5. VOLUnt CT LIO"!D WAITE 10 835CMARGE CANAL t!iERS 1.48t*04 2.44t*04 4.12(406

4. VOLUnt OT SILUTION WATER LITERS 2.45tell 3.07Ce18 5.52E*ll

7. BA310EUCLIGES AtttA3I3 CURIES F-18 0.00E*00 0.00C+00 0.00t*00

_ , , NA-24 2.54I-04 2.45E-03 2.ftE-03 AR-41 1.44t-04 1.21E-04 2.85t-04 CR 4.11E-02 3.13E-03 4.42E-02 RN-54 2.481-03 2.04E-03 4.52E-03 AN-56 0.00E*00 0.00E*00 0.00t+00 CQ-57 2.1tE-05 2.54E-05 4.74E-05 C0-58 _ l.04E-01 1.14E-01 2.18E-01

' CD-40 1.82E-02 f.5&E-03 2.7BE-02 FE 59 3.291-03 f.7tE-04 4.17E-03 N!-45 0.00E*00 0.00E*00 0.00E*00 2N-65 0.00E+00 0.00E*00 0.00t+00 ER-85 0.00E*00 0.00t+00 0.00t+00 RR-85n 0.00E*00 0.00E*00 0.00C+00 EA-87 0.00t+00 0.00Ee00 0.00E*00 RR-88 0.00E*00 0.00E+00 0.00E+00 T-88 0.00E*00 0.00E*00 0.00t*0:

1-92 . 0.00t*00 0.00E*00 0.00E*00 SR-89 0.00t*00 1.52E-04 ,, 1.52E-04 Sk-90 0.00E*00 4.ftt-06 -

4.ftt-04

$R-fl 0.00t*00 0.00E*00 0.00E+00 SR-92 4.41t-04 4.641-05 7.07E-04 N8-95 1.40E-03 3.90E-04 1.7tE-03 h8-97 0.00E+00 0.00E*00 0.00t400 IR-95 f.74t-04 f.9&E-04 1.17t-03 2R-77 0.00E+00 0.00E+00 0.00t+00 NO ft 0.00t*00 0.00t*00 0.00E+00

- TC-f?M 0.00te00 f.471-05 f.4?E-05 RU-103 0.00E*00 0.00t<00 0.00Ee00 10-1034 . 0.00E+00 0.00E*00 0.00E*00 RU'106 0.00E*00 0.00E*00 0.00E*00 A0-10eR 0.00E*00 0.00t+00 0.00E*00 AG-110M 1.00t-03 2.7tt-05 l.03E-03 CD-809 0.00E*00 0.00E+00 0.00E*00 CD 115 0.00E*00 0.00t*00 0.00E*00 C3-1158 0.00E*00 0.00(*00 0.00E+00 Ill-115R 0.00E*00 0.00E*00 0.0CI+00 58-122 0.00E+00 1.42E-03 1.42E-03

$8-124 4.8tt-03 3.43E-03 1.02E-02 18-125 0.00E*00 0.00E*00 0.00E*00 sn-123n 0.00Ee00 0.00t+00 0,0ggs00

.k $N-125 0.00E+00 0.00!*00 0.00E*00 1 131 0.00E+00 2.50E-04 2.50E-04

, OT I-132 0.00t*00 0.00E*00 0.00t+00

'QqQ I-133 0.00t+00 8.48E-04 8.481-04

, O('!(L, . I-134 0.00E+00 0.00E*00 0.00E*00 1

1 135 2.55[-03 0.00E+00 2.551-03 IE-13tn 0.00E+00 0.00t*00 0.00E*00 IE-133 4.70E-05 2.8tE-04 3.54E-04 E II-133N 0.00E*00 0.00E+00 0.00E*00

~

C st-135 4.74t-05 3.60t-04 4.08E-04 CE-134 0.00t*00 0.00E*00 0.00t*00 g CE-141 0.00E*00 0.00E+00 0.00E*00

,n CE-144 0.00t+00 3.11E 04 3.1tE-04 ng CS-134 0.00Ee00 0.00E+00 0.00E*00

'CS-335A

'n4

.w CS*134 0.00E+00 0.00Ee40 0.00E MO 0.00E+00 0.00E+00 0.00t*00

w g' CS-137 0.00E+00 0.00!+00

~

0.00t+00 MQ C5-138 0.00!+00 0.00E+00 ' O.00t+00

. Git!.(E 8A 837 0.00E600 0.00E+00 0.00E+00 SA-LA 840 0.00E*00 0.00E+00 0.00t+00

• *i-187 0.00E *00 ' 3.77E-04 3.77E-04 kP-239 0.00E+00 0.00E*00 0.00E*00 P-32 1.23t-02 4.37t-02 7.ett-02 II'55 1.6fE 02 2.80E-02 4.43E-;2

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' LADTAP il (Liquid Annual Doses To All Persons) is a code developed by the Nuclear Regulatory Commission which calculates individual and population doses from liquid pathways. This . computer code is based'on-the following standards:

Calculation of Annual Doses Reg. Guide 1.109, Rev. 1

.to Man f rom Routine Releases October 1977 of Reactor Effluents for the Purposes of Evaluating Canpliance with 10 CFR Part 50,

. Appendix i Estimating Aquatic Dispersion Reg. Guide 1.113, Rev. 1

-of Effluents from Accidental April 1977 and Routine Reactor Releases for the Purpose' of implementing Appendix l The LADTAP. Il computer program was placed in service September 28, 1981.

CALCULATED DOSES TO THE GENERAL PUBLIC FROM EFFLUENT RELEASES AT MCGUIRE NUCLEAR STATION FOR THE FIRST HALF OF 1982 MREM FLUID WASTES (wi th P-32 included and using a bioaccumulation factor for P-32 of 1.0E+05')

WHOLE BODY SKIN GI-LLI THYROID B0NE LIVER KlDNEY LUNG Calculated Max. 1.45 1.13E-3 3.03 5.64E-03 37.6 1.81 4. 30E- 03 4.48E-3 Age Group Child Teen Adult Infant Child Teen Child Child Critical Pathway Fish Shore Fish Drink Fish Fish Drink Drink Haior Contributors F-32 Co-60 P-32 H-3, 1-131, P-32 P-32 H-3, MN-54, H-3 I-133 Na-24 FLUID WASTES (no P-32 included)

WHOLE BODY SKIN GI-LLI THYROID B0NE LIVER KIDNEY LUNG Calculated Max. 4.82E-03 1.13E-03 2.81E-02 5.64E-03 1.45E-03 4.94E-03 4.30E-03 4.48E-03 Age Group Child Teen Adult Infant Teen Child Child Child Cri tical Pathway Fish Shore Fish Drink Shore Drink Drink Drink Maior Contributors Fe-55, H-3, Co-60 Nb-95 H-3, 1-131, Co-60 H-3 H-3 H-3 Mn-54, Fe-59 l-133

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MCOUllE ff9 CLEAR STATIB3

. RA310 ACTIVE EFFLUt27 RELIASE3 g

. g t BITE 98/14/I2 . s

\ / \

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s 1992

!!. Alt #0tNE ttLEASES %/ '

• UNITS IST Oft 2N3 Oft $Utf0fAL

1. TOTAL N08LE 0A$tS Cut!!S 4.04t*02 3.93t*02 7.ff!*02 2.. TOTAL HAL40tNS Cut!!S 0.00E*00 3.52t-04 3.32t-04

3. ' TOTAL Pati!CULAft 68033 alTA-GAnna CURIES 5.84t-04 1.03E-08 5.84t-04

4. TOTAL ft!!!UN Cut!ES 4.38E-02 1.02E-03 4.48E-02

- 5. TOTAL PAff!CULATE

,j f$20$3ALPNAACf!Viff. cut!ES  ?.04E-10 0.00E*00 9.04E-10 l 4. RAI! NUN N09tt SAS' RELEA$t A4ft UCI/ SIC 1.40E*03 1.40E*03 1.40E*03 l

7. RA3!ONUCLIMS REtteSE8 cut!!S PARf!CULAfts

'i C-14 0.00E*00 ' O.00t*00 0.00E*00 P-32 0.00t*00 0.00t*00 0.00E*00

'Ct-51 0.00E*00 0.00E+00 a.00E*00

, AN-34 f.77E-04 0.00E*00 1.7.'t-0 4 I FE-55 0.00E*00 0.00t*00 0.00E+00 FE-59 0.00t*00 0.00E+00 0.00E*00 C0-50 5.84E-04 0.00t+00 5.84t-04 CO-40 0.00t*00 0.00t*00 0.00E*00 4 N!-43 0.00E*00 0.00t*00 0.00E*00 2N-45 ' O.00E*00 0.00E*00 0.00t*00 23-84 0.00E*00 0.00E*00 0.00E*00 52-87 0.00t*00 f.5ft-Of 9.5tE-07 St-90 4.08E-Il 7.4tE-10 8.2fE-10 T-fi 6.00E*00 0.00E*00 0.00E+00 2R-95 0.00t+00 0.00t*00 0.00E*00 NB-95 0.00t*00 0.00E*00 0.00E*CB MO-ft 0.00t*C0 0.OCE*00 0.00E*00 25 103 0.00E*00 0.00t*00 0.00E+00 RU-IO4 0.00t+00 0.00E*00 0.00E+0B A3-lles 0.00E*00 0.00E*00 0.00E*00 CD-fl5N 0.00!*00 0.00t*00 0.00t*00 SN-123 0.00t*00 0.00E*00 0.0CI*00 -

Su-124 0.00E*00 0.00t*00 0.00Ee00

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- MtWe - 0.00E*00 -

0.~0bE*00*

$3-825 0.00E*00 0.00t*00 0.00t+00 .

TE-127N 0.00t*00 0.00E*00 0.00E*00 - -

TE-1275 0.00E*00 0.00E*00 0.00E*00 CS-134 0.00E*00 0.00E*00 0.00E*00 CS-136 0.00E+00 0.00E*00 0.00E*00 CS-137 0.00t*00 0.00t*00 0.00E*00 34-140 - 0.00t*00 0.00E*00 0.00E*00 CE-141 0.00t*00 0.00t*00 0.00E*00 CE-144 0.00E*00 0.00E*00 0.00E*00 I- l J- HALOGENS s

) 1-131. 0.00E*00 4.!5E-05 4.55E-05 3.04t 3.06E-94 I-133 0.00E*00 ..

SA$t$

'e' s kt-834 0.00t*00 0.00f*00 0.00E*00 kt-45N 4.80t*00 4.0lE-01 5.4CE+00 kt-85 0.00E*00 1.05t*00 1.05t*00

. Et-87 0.00E*00 0.00t*00 0.00E*0s

• tt-te 0.00E+00 0.00E*00 0.00E*00 KR-89 0.00E*00 0.00E*00 0.00t*00 Et *0 0.00E*00 0.00E*00 0.00E+00 It-8384 0.00E*00 0.00E*00 0.00E*00 1E-133N . 1.97E-04 3.57E-Of 3.57E-Of IE-833 1.92t*02 3.80t*02 3.?t E *02 Il-1354 2.32E f.33E-02 3.25E-08 IE-135 7.90E*01 4.fot*01 1.2fE*02 31-137 0.00E*00 0.00t*00 0.00E *00

.IE-130 0.00E*00 0.00t*00 0.00E+00 42-41 l.3tE*02 1.49t*02 2.72E*02 1

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GASPAR is' a code developed by the Nuclear Regulatory Commission for the .

- evaluation'of radiological impacts resulting from' the release of radio-

. active material to the atmosphere during.nonnal operation of light water

-reactors.- In particular, the code implements'the radiological. impact models of Regulatory Guide 1.109, Rev. 1,-for atmospheric releases.' The code.is presently used by the NRC in reactor IIcensing evaluations to estimate (1) the. collective or population dose (person-rem) to the popula-tion within a 50-mile radius- of a facility ,(referred to as ALARA dose);

. (2) the total collective dose to the U.S. population (the NEPA dose); and

. (3) - the maximum individual doses at selected locations in -the vicini ty of

~ the plant.

The GASPAR computer program was placed in service November' 9,1981. ,

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GASEOUS WASTE WHOLE BODY SKIN GI-LLI THYROID BONE LIVER KIDNEY LUNG Calculated Max. Infant Adult 0.618 1.07 0.618 0.629 0.618 0.618 0.618 0.618 0.620 Age Group All All All Infant Adult All All All All Critical Pathway Plume Plume Plume Plume, Plume Plume Plume Plume Plume Goat Major Contributors Ar-41, Ar-41, Ar-41, Ar-41, Ar-41, A r-41, Ar-41, Ar-41, Ar-41, Xe-135 Xe-135 Xe-135 Xe-135, Xe-135 Xe-135 Xe-135 Xe-135 Xe-135 l-131 e

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_ , 4 l982'

. McGUIRE NUCLEAR STATION n ;.. RADI0 ACTIVE EFFLUENT RELEASES

• SOLID' WASTES' 1ST SEMI-ANNUAL REPORT- 3

~

'Totalivolume of solid wa'sIe packaged (cubic maters) 25.3 for 1st six months of 1982.

Total-estimated activity involved (curies)-0.??.9 for 1st six months of 1982. .

Disposal of materials- shipped off-site:' All 2_' shipments were made to Chem-Nuclear Systems waste disposal facility at' Barnwel3, . South Carolina.

.s - Number of- Volune . Total

' Types of Wastes' Shipments (Cubic Meters) Activity CI

< 1. : Wastes from Liquid Systems (A)(Powdex_ Resins-. 0 0 0:

(B) ,-Spent . Resins & Bead ' Resins 0- 0 0 (C) Evaporator Concentrates 0 0 0 12.~ Dry Solid Wastes \_e

~ (A)- Spent Filters

- :(B). Dry Compreseble Wastes

[ ~?

N1 0 0.

19.75 0

2.04E-01

-3 .. .

. (C)' Contaminate ( Equipment - 1, 5.55 2.50E-02

.(D) Irradiated Components 0 0 0

.StEMARY OF MAJOR RADIONOCLIDE COMPOSITION Type of Waste- Radionuclide  % Abundance

1. .Wastes from Liquid Systems ,

-(A)/ Powdex Resins _ -MN-54 0.0%

~ ~

C0-57 0.0%

C0,58. 0.0%

C0-60 0.0%

' SR-92 0.0%-

! , . NB-97 0.0%

t 4 '. _t

'AG-110M CS-134 0.0%

0.0%

~

c_ CS-137 0.0%

y.

(B) ~ Spent Resins-& Bead Resins -b MN-54 0.0%-

M x C0-57 0.0%

C0-58 0.0% ~ s '

C0-60 0.0%

SR-92 0.0%-

NB-97 0.0%

1AG-110M s 0.0%

o CS-134- 0.0%

CS-137 0.0%

i I-131 0.0%

s- TC-99M. 0.0%

i CR-51 0.0%

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.Page 2 of.2 x

V. Type'<of Waste Radionuclide  % Abundance

.N-L _

t(C)'EvaporatorConcentrates MN-54 0.0%

C0-58 0.0%

r .

C0-60 0.0%

~';

L TC-99M 0.0%

e I-131 0.0%.

~

'4' I-133 0.0%-

L 1-134 0.0%

CS-134 0.0%

CS-137 0.0%

LA-140 0.0%

2. Dry Solid Waste ,

~

-(A)~ Spent Filters AG-110M 0.0%

1 CS-134- 0.0%

• i -CS-137. 0.0%

'C0-60 0.0%-

CO-58 -0.0%-

1. -}u .

o MN-54 0.0%

L(B). Dry Compr ssible' Waste AG-110M 0.51%

% CS-134 23.65%

-.CS-137 35.83%-

C0-60 19.65%

MN-54 1.80%

C0-57 0.12%

.i. C0-58 17.40%

s3~ Q -< q NB-97 0.62%~

~

(C) : Contaminated Equipment AG-110M 0.51%

CS-134 23.65%

CS-137 35.83%

N. C0 19.65%

MN-54 1.80%

.00-57: 0.12%

C0-58 17.40%

NB-97 0.62%.

v.

i(D) . Irradiated-Components AG-110M 0.0%

e; n - ~ CS-134 0.0%

CS-137 0.0%

( T; y C0-60 MN-54 0.0%

0.0%

C0 0.0%

. w:-

f N CO-58 NB-97 0.0%

0.0%

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CHAMLOTrE, N.C. 28242

> HAL B. TUCKEN ,

tetze,eown f j: vnares v .  ? (704) 073-4 sat September 7, 1982 ce

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Mr. James P. b'Reilly, Regional Administrator

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- U '. S .# Nuclear Regulatory Commission C'd

',.. Regi$n II *

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s 101 Marietta; Street, Suite Atlanta, Georgia'30303 3100 $

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' Re:J McGuire Nuclear Station

'DocketNo.;50-363/g Semi-Annual Radioactive Effluent Release Report

Dear'Mr. O'Reilly:

Pursuant to Technical Specifications 6.9.1.8 and 6.9.1.9 attached are radioactive effluent release' reports for the period January - June, 1982. This includes "LADTAP" and "CASPAR" dose assessments, and the semi-annual Solid Waste Disposal Report for_the first six months of the year.

Picase advise us if there are any questions regarding this matter.

Very truly yours, ard b ~

Hal B. Tucker WHM/php Attachment cc: Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555- /

Mr. P. R. Bemis D

NRC Resident Inspector McGuire Nuclear Station l/

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omcua.cory.

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. . . . . - . . . _ .