Text

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1987
	ML20196F279
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/31/1987
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20196F278	List: ML20196F272; ML20196F279;
References
	NUDOCS 8803020150
	Download: ML20196F279 (50)
	v • d • e

MCCUlRE NUCLEAR STATION EFFLUENT M0 WAlft DISPOSAL SUPPLEENTAL INFORMAi!UN REPORT DATE:

02/121:3 PERIOD COVERED: 5 FART DAY e 001 ST0p OAT e 365

!. REGULATORT LIMITS A. NOSLE CASE 5 - AIR 005E

8. LIBUID EFFLUENT 5 - 00$E 1, CALENDAR GUARTER - CAMA 005E

5 MRA3

1. CALENDAR GUARTER - TOTAL 900T 005E = 1.5 MREM

2. CALENDAR 004RTER - BETA 005E = 10 MRAD

2. CALENDAR QUARTER - CRCAN CO5E

= 3 PREM

3. CALENDAR TEAR

- CAMMA 005E = 10 MaAD

3. CALENDAR TEAR

- TOTAL 900T 00$E = 3 MREM

4. CALENDAR TEAR

- BETA 00$E = 20 MRA0

4. CALENDAR TEAR

- ORGAN Co$E a to MREM C.100!NE - 131 AND 133 TRITIUM, PART!Ct' LATE 5 Wlf ilt ) 8 DAYS - CtCAN C0$E

1. CALENCAR SUARTER = 7.5 MAEM

2. CALENDAR TEAR

= IS MREM

!!. MAI! MUM PERMI551pLE CONCENTRATIONS A. C45E005 EFFLUENil - INFORMAT!0N FOUNO IN OFFl!TE 00SE CALCULATION MANUAL

8. LIGUID EFFLUEN15 - INFORMATICN FOUNO IN 10CFR20, APPEN0!K B. TA4LE !!, COLUMN 2

!!!. AVERACE ENERCT - NOT APPLICABLE IV. MEA 5UREMENT$ ANO APPR0XIMATICN1 0F TOTAL RA0!CACTIVITY INFORMAi!0N FOUND IN OFF51TE 005E CALCULATICN MANUAL Y. BATCH RELEASES A. LIQUID EFFLUENT

1. 1.09Et03 = TOTAL NUMBER OF BATCH RELEASES

2. 3.50Et0S = TOTAL TIMEIMIN.I FOR BATCH RELEASES.

3 1.01E104 = MAI! MUM TIME (MIN.) FOR A SATCH RELEASE.

4. 3.2 set 02 = AYERAGE TIMEIMIN.I FOR A BATCH RELEA!E.

S. 1.00Et00 = MIN! MUM TIMEIMIN.i FOR A BATCH RELEASE.

6. 5.10Et0B = AVERACE DILUTION WATER FLOW DURING RELEASE 5tCPM).

B. CASEQU$ EFFLUENT

1. 6.37Et02 = TOTAL NUMBER OF BATCH RELEASES.

2. 1.02Et06 = TOTAL TIMEIMIN.) FOR SATCH RELEASES.

3. 1.29Et04 = MAI! MUM TIMEIMIN.) FOR A BATCH RELEASE.

4. 1.40Et03 = AVERACE TIMEIMIN.) FOR A BATCH RELEASE.

S. 1.00Et00 s MINIMUM TIMElMIN.I FOR A DATCH RELEA5E.

VI. ABNOR#AL RELEASES A. LIQUID

1. NUMBER OF RELEASE 5 2.TOTALACTIVITTRELEiif5iC0 li's.7.2........

B. CASEQU5

1. NUMBER OF RELEASE 5 0

2. TOTAL ACTIVITT REltilt5T50i!!!i'..Q 8803020150 800229 DR ADOCK 0500 9

SUPPLEMENTAL REPORT McGUIRE NUCLEAR STATION Values represented by "0.00E+00" within the body of the semi-annual and/or annual report are below the minimum detectable limits of the McGuire counting systems.

Typical MDA's for the McGuire counting systems are listed below:

ISOTOPE ENERGY AVERAGE MDA Liquid XE-133 80 4.9E-8 CE-144 133 1.0E-7 KR-88 196 1.4E-7 XE-135 249 2.4E KR-87 402 2.6E-7 CS-137 661 2.5E-8 MO-99 778 4.1E-7 MN-54 834 1.8E-8 ZN-65 1115 5.5E-8 CO-60 1332 4.6E-8 GAS XE-133 80 2.6E-8 Kr-85m 151 1.2E-8 Xe-131M 163 3.8E-7 Kr-38 196 4.0E-8 Xe-133m 233 8.3E-8 Xe-135 250 1.3E-8 Xe-138 258 4.4E-6 Kr-87 402 6.2E-8 Kr-85 514 3.1E-6 Xe-135M 526 1.8E-6 Ar-41 1293 3.7E-8 1

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t The estimated percentage of error for both Liquid and Gaseous ef fluent release data at McGusg( Nuclear Station has been determined to be +31%.

This number was derived by summing the following individual estimates'of errors:

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1) Flow rate determining devices = +13%

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= +15%

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SET 10 NEW PACE AND PRE 55 RETUEN PCCUllE NUCLE'] 11AT10N UNIT 1 R:.Il0 ACTIVE EFFLL'ENT RELEA5El CATE 02I!!I88

!!. Altt0tNE RELEASES 1

1987 UN!il 151 OTR th0 OTR 323 BTR 4tW Oft TOTAL 1.

TOTAL N0tLE CAlti cut!El 3.04E+02 5.13E+02 7.4CE+02 4.79t+02 2.04E+03 2.

TOTAL NALOCEN5 Chm,El 5.26E-03 6.32E-03 6.8CE 03 4.87E 04 1.89E-02 3.

TOTAL PARTICULATE CRC 55 8tTA CAMPA Cut!El 2.20E 03 3.89E 02 7.51E 04 1.06E 14 4.19!-02 4 TOTAL ?31110M CURIE 5 5.22E+00 6.29Eff0 5.68E+00 7.83E+00 2 50F+01 5.

TOTAL PARittVLATE CROS5 ALPHA ACTIV11Y CURIES 0.0tE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.

MAIIMU9 MOBLE CAS RELEASE RATE DC!l5EC 1.60E+03 1.60E+03 1.60E+03 1.6CE+03 1.40E+03 7.

RADICNVCL10E5 CELEASED CURIE 5 PARTICULATES NA-24 6.48E-04 4,78E 04 5.02E-05 0.00E+00 1.2tE-03 CL-38 2.46E-08 1.95E-08 2.31E-08 3.52E 08 1.02E-07 E 40 4.45E-04 1.39E-04 6.14E-05 1.33E-05 6.58E-04 CR-51 0.00E+00 0.00E+00 8.95E 06 0.00E+00 8.95E 06 PN-54 9.99E-07 3.91E-06 3.10E-10 0.00E+00 4.91E-06 MM-54 1.15E-09 0.0CE+00 0.CCE+00 0.00E+00 1.15E-09 C0-57 0.00E+00 0.00E+00 3.21E 07 0.00Et00 3.21E-07 CD-58 0.00E+00 4.85E 06 1.13E 04 2.42E C5 1.42E-04 CD-60 9.58E-06 5.26E-06 2.25E-05 1.21E 05 4.95E-05 80 S2 2.39E 09 4.9CE-10 8.39E-09 5 82E 09 1.71E-08 E9 89 1.03E-03 1.19E 03 3.16E-04 4.3?[-05 2.57E-03 50 89 4.85E-07 2.22E-t6 0.00E+00 0.00E+00 2.71E-06 50-92 8.57E-09 1.28E-08 6.37E-09 3.7&E-10 2.81E-08 T-91M 1.79E 10 0.COE+00 0.CCEf00 1.47E 09 1.65E-09 T-93 0.00E+00 2.52E-12 0.00E+00 0.0CE+00 2.52E-12 2D-95 0.00E+00 0.00E+C0 3.94E-10 0.00E+d6 3.94E-10 20-97 0.00E+00 0.00E+C0 7.56E-10 0.00E400 7.56E-10 hl-95 0.00Ef00 0.00E+C0 5.9CE-10 7.72E-11 6.67E-10 TC-99M 1.34E-05 4.61E-05 2.29E-06 0.0CE+00 4.18E-05 RU-ils 1.53E 10 0.0CE+00 9.18E-*'

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i 58-122 0.00E+D0 0.00E+00 4.19E-10 0.0CE+00 4.19E-10 SN-113 0.CCE+00 0.00E+0a 8.19E Il 8.32E 07 8.33E-07 C5 134 0.00E+0*

2.81E-05 4 09E-05 1.30E-06 7.02E45 C5-136 0.00E+00 6.26E-06 4.15E 06 0.00E+00 1.04E-05 C5-137 1.87E-05 6.68E-05 5.89E-05 3.73E-06 1.4BE-04 C1-138 k.64E-06 8.98E-03 9.57E 08 7.93E-C8 2.9CE-06 84-139 3.16E-10 0.CCE+00 0.00E+00 1.BSE-09 2.2CE-09 8A-140 0.0CE+t0 0.Ctt+00 0.0CE+00 1.35E-10 1.35E-10 CE-141 0.00E+00 0.0CE+C0 9.95E-07 0.CCE+C0 9.95E-07 CE-143 4.31E-C6 4.64E-08 2.43E-10 2.04E-10 4.36E-06 CE-144 7.10E-06 4.16E-06 2.28E-05 1 05E-09 3.4CE-05 W-187 0.00E+00 0.0tE+00 3.37E-05 0.00E+00 3.37E-05

!!-214 1.44E-07 5.77E-06 9.46E-06 3.84E-te 1.92E-05 F9-212 0.15(+00 1.92E-06 0.0CE+00 0.0CE+00 1.92E 06 98-214 1.45E-27 3.69E-02 4.78E-06 3.12E 04 3.69E-02 HAL3CEM5 I-131 1.87E-03 2.27E-03 3 58E-03 4.!!E-04 8.14E-03 I 132 0.00E+00 1.07E-03 3.29E-04 7.41E-07 1.40E-03 1-133 3.39E-03 2.63E-03 2.77E-03 7.09E-05 8.87E-03 1 134 0.00Ef00 0.0CE+00 1.65E-08 3.90E-09 2.04I-08 1-135 0 OCE+00 3.47E-04 1.12E-04 1.42E C8 4.59E-04

ASES AR-41 3.3?E+00 2.19E+00 2.52E+00 1.36E+00 9.4CE+00 10-85 3 23E+00 5.55E+00 6 11Ef00 7.52E+00 2.24Et31 10-859 9 87E-01 9.4EE 01 7 86E-01 7.41E-01 3.5CE+00 st-87 1 35E 01 9.04E-02 7.69E C2 1.04E 01 4.08E-01 80-88 9.t!E-01 8 02E-01 5.89E 01 6.71E C1 2.97E+00 RE-131M 1 26E+00 2.33E+00 3.29E+00 2.32E+tl 9 2CE+00 IE-133

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-UNIT 2 RA0!OACT2VE EFFLUENT RE'. EASES DATE 02/11/88 II. AIRBORNE RELEASES YEAR : 1987 UNITS 15T OTR 2ND OTR 3R6 GTR 4TH OTR TOTAL 1.

TOTAL NOBLE CASES CURIES 3.04Et02 5.13Ef02 7.40Et02 4.79Et02 2.04Et03 2.

TOTAL HALOCENS CURIES 5.26E-03 6.32E-03 6.80E-03 4.87E-04 1.89E-02 3.

TOTAL PARTICULATE CROSS BETA-CAMMA CURIES 2.20E-03 3.89E-02 7.51E-04 1.06E-04 4.19E-02 4.

TOTAL TRIT!UM CURIES 5.22Et00 6.29Et00 5.6 bet 00 7.83Et00 2.50Ef01 5.

TOTAL PARTICULATE CROSS ALPHA ACTIVITY CURIE 5 0.00Et00 0.00E100 0.00Ef00 0.00Ef00 0.00Ef00 6.

MAXIhUM NDBLE CAS RELEASE RATE UCIISEC 1.60Ef03 1.60Et03 1.60Et03 1.60Ef03 1.40Ef03 7.

RADIONUCLIOES RELEASED CURIES PARTICULATES NA-24 6.68E-04 4.78E-?1 5.02E-05 0.00E400 1.20E-03 CL-38 2.46E-08 1.95E-08 2.31E-08 3.52E-08 1.02E-07 K-40 4.45E-04 1.39E-04 6.14E-05 1.33E-05 6.58E-04 CR-51 0.00Et00 0.00Et00 8.95E-06 0.00Ef00 8.95E-06 MN-54 9.99E-07 3.91E-04 3.10E-10 0.00Ef00 4.91E-06 MN-56 1.15E-09 0.00Et00 0.00Et00 0.00Et00 1.15E-09 CD-57 0.00Et00 0.00Ef00 3.21E-07 0.00Ef00 3.21E-07 CD-58 0.00Et00 4.85E-06 1.13E-04 2.42E-05 1.42E-04 C0-60 9.5BE-06 5.26E-06 2.25E-05 1.21E 05 4.95E-05 BR-92 2.39E-09 4.90E-10 8.39E-09 5.82E-09 1.71E-08 RB-88 1.03E-03 1.19E-03 3.1&E-04 4.36E-05 2.57E-03 SR-89 4.85E-07 2.22E-06 0.00Et00 0.00Et00 2.71E-06 SR-92 8.57E-09 1.28E-08 6.37E-09 3.76E-10 2.81E-03 Y-91M 1.79E-10 0.00Ef00 0.00Ef00 1.47E-09 1.65E-09 Y-93 0.00Ef00 2.52E-12 0.00Ef00 0.00Ef00 2.52E-12 ZR-95 0.00Et00 0.00Ef00 3.94E-10 0.00Et00 3.94E-10 2R-97 0.00Ef00 0.00Ef00 7.56E-10 0.00Ef00 7.56E-10 NB-95 0.00Et00 0.00Et00 5.90E-10 7.72E-11 6.67E-10 TC-99M 1.34E-05 4.61E-05 2.29E-06 0.00Ef00 6.1EE-05 RU-103 1.53E-10 0.00Et00 9.18E-07 0.00Ef00 9.18E-07 58-122 0.00Et00 0.00Ef00 6.19E-10 0.00Et00 6.19E-10 SN-113 0.00Et00 0.00Et00 9.19E-11 8.32E-07 8.33E-07 C5-134 0.00Ef00 2.81E-05 4.09E-05 1.30E-06 7.02E-05 C5-136 0.00Ef00 6.26E-06 4.15E-06 0.00Ef00 1.04E-05 C5-137 1.87E-05 6.68E-05 5.8SE-05 3.73E-06 1.48E-04 CS-133 2.64E-04 8.98E-08 9.57E-08 7.93E-08 2.90E-06 BA-139 3.16E-10 0.00Ef00 0.00Ef00 1.88E-09 2.20E-09 BA-140 0.00Ef00 0.00Ef00 0.00Et00 1.35E-10 1.35E-10 CE-141 0.00Ef00 0.00E+00 9.95E-07 0.00Ef00 9.95E-07 CE-143 4.31E-06 4.6*E-08 2.43E-10 2.04E-10 4.36E-06 CE-144 7.10E-06 4.16E-06 2.28E-05 1.05E-09 3.40E-05 W-187 0.00Ef00 0.00Et00 3.37E-05 0.00E+00 3.37E-05 BI-214 1.64E-07 5.77E-06 9.46E-06 3.84E-06 1.92E-05 PB-212 0.00E400 1.92E-06 0.00Et00 0.00Ef00 1.92E-06 FB-214 1.45E-07 3.69E-02 4.7BE-06 3.12E-06 3.69E-02 HALO 0EN5 I-131 1.87E-03 2.27E-03 3.59E-03 4.15E-04 8.14E-03 1-132 0.00Et00 1.07E-03 3.28E-04 7.41E-07 1.40E-03 1-133 3.39E-03 2.63E-03 2.77E-03 7.09E-05 8.87E-03 1-134 0.00Ef00 0.00E+00 1.65E-08 3.90E-09 2.04E-08 I-135 0.00Et00 3.47E-04 1.12E-04 1.42E-08 4.59E-04 CASES AR-41 3.33Ef00 2.19Ef00 2.52Et00 1.36Ef00 9.40Ef00 KR-85 3.23Et00 5.55Ef00 6.11Et00 7.52Ef00 2.24Ef01 XR-85M 9.87E-01 9.68E 01 7.86E-01 7.65E-01 3.50Ef00 KR-87 1.35E-01 9.04E-02 7.69E-02 1.86E-01 4.08E-01 l

ER-29 9.05E-01 8.02E-01 5.89E-01 6.71E-01 2.97Ef00 XE-131M 1.26Ef00 2.33E+00 3.29Et00 2.32Ef00 9.20Ef00 XE-133 2.74E+02 4.74Et02 6.98Ef02 4.47Et02 1.CS Li3 XE-133M 4.14Ef00 6.75Et03 9.45Et00 5.70Ef00 2.60E+01 XE-135 1.60Et01 1.92Ef01 1.87E+01 1.37E401 6.74Et01 tE-13fh 7.91E-04 1,47Et00 5.58E-02 2.32E-04 1.53Ef00

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1 l

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McGuire NUCLEAR STATION SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD 7/1/87 THROUGH 12/31/87 TYPES OF WASTE NUMBER OF NUMBER OF WASTE CONT.

enRIAt votuMF TOTAL ACT.

EST. TOTAL SHIPPED SHIPMENTS CONTAINERS CLASS TYPE (ft')

l (m')

Ci ERROR S 1

WASTE FROM LIQUID SYSTEMS (A) Dewatered Powdex Resins I

6 6A STC 1236 A 35.0A 1.19E-2A 10 (B) Dewatered Bead Resins 0

0 N/A N/A 0

0 0

N/A (C) Evaporator Concentrates 0

0 N/A N/A 0

0 0

N/A 2

3}g^

lI 5

I (D) Dewatered Mechanical Filters 4

25 sTc 15 l

2 (E) Dewatered Demineralizers 3

8 STc 1.

10 (F) Solidified (Cement) Oils 0

0 N/A STc 0

0 0

N/A Acids. Sludges 2

DRY S01.10 WASTE (A) Dry Active Waste (compacted) 8 90 90A STC 8280 A 234 47A 3.05A 15 6

8*

(B) Dry Active Waste (non-compacted) 13 69 STc 15 (C) Irradiated Components 0

0 N/A N/A 0

0 0

N/A 195A 14719A 416.8A 29.93A TOTALS 30 198 2n 76s 2.16s 17.5s 1c 1Rr 1.nec

??.nc

L

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION Types of Wastes Radionuclide

% Abundance 1.

Wastes from Liquid Systems (a)

Dewatered Powdex Resins Mn-54 0.2 Cs-134 27.3~

Cs-137 32.0 Fe-55 15.2 ETRU 11.0 I-131 6.9 Kr-85 7.5 Sb-122 0.3 (b)

Dewatered Bead Resins (None Shipped This Period)

(c)

Evaporator Concentrates (None Shipped This Period)

(d)

Dewatered Mechanical Filters Zn-65 0.3 Ag-110m 1.4 Mn-54 4.2 Co-58 1.0 Co-60 36.6 Sr-92 0.4 Ce-144 0.3 Nb-97 1.3 Pu-241 0.0 Fe-55 49.1 Ni-63 5.3 (e)

Dewatered Demineralizers H-3 0.6 Co-58 9.1 Co-60 23.1 Co-57 0.1 Mn-54 4.4 Cs-134 18.7 Cs-137 25.7 Ce-144 0.1 Fe-55 6.9 Ni-63 10.3 I-131 0.1 C-14 0.1 (f)

Solidified (Cement)

Acids, Oils, Sludges (None Shipped This Period) 2.

Dry Solid Waste (a)

Dry Active Waste (compacted & noncompacted)

Cr-51 5.3 Mn-54 6.0 Co-58 24.3 Co-60 30.4 Nb-95 5.4 Pu-241 0.4 Fe-55 22.2 Ni-63 3.2 Zr-95 2.98 (b)

Irradiated Components (None Shipped This Period) 9

ATTACHMENT IC METEOROLOGICAL DATA W

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W ATTACHMENT 2 INOPERABLE INSTRUMENTATION e

r ATTACHMENT II INOPERABLE EFFLUENT MONITORING INSTRUMENTATION No effluent monitoring equipeant was inoperable during the reporting period, although a technical specification-required surveillance was missed on a Waste Ga r, (WG) system tank.

Technical Specification 3/4.11.2.6 requires that material contained in each gas storage tank be sampled every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , when radioactive materials are being added to the tank, to determine that the quantity of radioactive mater-tal is less than or equal to 49,000 Curies of noble gases.

On December 30, 1987, WG Shutdown Tank B was sampled at 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months .

Shutdown Tank B continued to receive air from Recycle Holdup Tank A until 2015 hours0.0233 days 0.56 hours 0.00333 weeks 7.667075e-4 months . Due to a person-nel error, a sample was not obtained within the 24-hour interval following the December 30 sample. A sample was taken later on December 31 and verified to be well within Tech Spec limits.

For a more de. tailed description of the incident, refer to Licensee Event Re-port 369/87-37.

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