ML20238C679

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Solid Radwaste Shipped to Disposal Facility Rept for Jan- June 1987. Related Info Encl
ML20238C679
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 06/30/1987
From:
DUKE POWER CO.
To:
Shared Package
ML20238C675 List:
References
NUDOCS 8709100295
Download: ML20238C679 (70)


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l CAT EBA NUCLEAR STATION EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION REPO9T DATE: 08/27187 l PERIOD COVERED: START DAY = 001 STOP DAY = 181 '

I. REGULATORY LIMITS A. NDBLE CASE 5 - AIR DD5E B. L! AVID EFFLUENTS - DOSE

1. CAllNDAR QUARTER - GAMMA DOSE = 5 MRAD 1. CALENDAR QUARTER - TOTAL BODY DD5E = 1.5 MREN I
2. CALENDAR QUARTER - BETA DOSE = 10 NRAD 2. CALENDAR QUARTER - ORGAN DOSE = 5 MREM
3. CALENDAR YEAR - GAMMA DO5E = 10 MRAD 3. CALENDAR YEAR - TOTAL B0DY DDSE = 3 MREM
4. CALENDAR YEAR - BETA 105E = 20 MRAD 4. CALENDAR YEAR - ORGAN 005E = 10 MREM C.10 DINE - 131 AND 133, TRITIL'n, PARTICULATE WIT 112 ) 8 DAYS - ORGAN D05E i
1. CALENDAR QUARTER = T.5 M.1EM l
2. CALENDAR YEAR = 15 MREM l II. MAXIMUM PERMISSIBLE CONCENTRATIONS A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFF5ITE DOSE CALCULATION MANUAL ,

B. LIQUID F.FFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE II, COLUMN 2 J III. AVE.1 AGE ENERGY - NOT APPLICABLE IY. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL i

V. BATCH RELEASES A. LIQUID EFFLUENT 3.04E+02 = TOTAL NUMBER OF BATCH RELEASE 5 1.8BE+05 = TOTAL TIMEtMIN.) FOR BATCH RELEASES.

3. 4.46E+04 = MAXIMUM TIMEIMIN.) FOR A BATCH RELEASE.

4, 6.19E+02 = APERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. S.POE+00 = MINIMUM TIMEtMIN.) FOR A BATCH RELEASE.
6. 2.70E+06 = AYERAGE DILUTIDN WATER FLOW DURING RELEASE 5tCPM).

B. CASEQU5 EFFLUENT

1. 1.54E+02 = TOTAL NUKBER OF BATCH RELEASE 5.
2. 5.21E+05 = TOTAL TIMEIMIN.) FOR BATCH RELEASES.

B. 4.32E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 3.38E+03 = AVERACE TIMEIMIN.I FOR A BATCH RELEASE.
5. 8.0fE+01 = MINIMUM TIMEIMIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES g

2.TOTALACTIVITYRELE55EDIC0iilE5I~,,,,,,,0 ,,,,_ ,

B. GASEQU5

1. NUMBER OF RELEASES O 2.TOTALACT!YITYRELEi5E6ICURiggi- 0 l 1 l

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SUPPLEP. ENTAL REPORT PACE 2

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CAIAb8A NUCLEAR STATION YALUE5 REPRESENTED BT *0,00E400* W!iHIN THE BODY OF THE SEMI-ANNUAL AND/OR ANNUAL REPORT ARE BELOW THE MININUM DETECTABLE LIMITS OF THE CATAWBA COUNTINO ST5fEMS. ITPICAL MDA'$ TOR THE CAIAWBA CDUNTING SYSTEM'S ARE LISTED BELCW:

AVERACE 150iCPE ENERCTitevi MDA IE-133 80 3.30E-08 CE-144 133 3.00E-Of ER-88 196 3.60E-08 XE-!!5 247 1.1 E-08 KR-B7 402 3.15E-08 C5-137 461 2.50E-0B MD 99 778 1.45E-07 MN-!4 834 2.65E-08 l IN-65 1115 6.85E 08 C0-60 1332 2.95E-0B e o O

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l CATAWBA NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseous effluent release data at Catawba Nuclear Station has been determined to be +23%. This number was derived by summing the following individual estimates of errors:

. 1) Flow rate' determining devices'= f 5%

2) Counting error

= f15% _

3) Sample preparation error = + 3%

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UNIT 1 j RADI0 ACTIVE EFFLUENT RELEASE 5 DATE 08/25/87

1. LIQUID RELEASES YEAR . 1987 I

UNITS 15T OTR 2ND OTR SUBTOTAL .

1 CR055 RADI0 ACTIVITY A. TOTAL RELEASE CURIES 1.81E-01 5.20E-02 2.33E-01 i

8. AVERACE CONCENTRATION RELEASE 0 UCI/ML 7.13E-09 2.16E-09 4.72E-09 C. MAXIMUM CONCENTRATION RELEASED UCIIML 6.28E-08 1.31E-08 6.28E-08
2. Tk! TIUM A. TOTAL RELEASE CURIES 9.80Ef01 5.16Ef01 1.50Ef02
8. AVERAGE CONCENTRA110N RELEASED UCIIML 3.87E-06 2.15E-06 3.03E-06
3. DI5 SOLVED N08LE GASES A. TOTAL RELEASE CURIES 2.95E-02 1.64E-02 4.59E-02
8. AVERACE CONCENTRAT!DN RELEASED UCIIML 1.16E-09 6.82E-10 9.30E-10
4. CROSS ALPHA ACTIVITY A. TOTAL RELEASE CURIES D.00Ef00 0.00Ef00 0.00Ef00
8. AVERAGE CONCENTRATION RELEASED UCIlNL 0.00Ef00 0.00Et00 0.00Et00
5. VOLUME OF LIQUID WASTE 10 DISCHARGE CANAL LITER 5 1.01Et08 2.67Et07 1.28Ef08 i
6. VDLUME OF DILUTION WATER LITERS 2.54Ef10 2.40Ef10 4.94Ef10
7. RADIONUCLIDES RELEASED CURIES 8E-7 3.37E-04 1.11E-05 3.48E-04 F-18 1.83E-03 6.96E-05 1.90E-03 NA-24 1.92E-05 3.21E-04 3.40E-04 CR-51 4 45E-03 1.05E-03 5.49E-03 MN-54 6.44E-03 2.15E-03 8.59E-uS FE-55 1.09E-01 7.58E-03 1.17E-01 FE-59 1.07E-03 4.11E-04 1.40E-03 C0-57 2.23E-04 7.76E 3.00E-04 CD-58 1.70E-02 2.33E-02 4.03E-02 00-60 2.32E-02 9.19E-03 3.24E-02 ZN-65 8.35E-04 2.39E-04 1.07E-03 5E-75 4.02E-06 0.00E+00 4.02E-06 BR-F2 4.75E-06 1.53E-05 2.01E-05 BR-84 0.00Ef00 7.10E-06 7.10E-06 R8-88 0.00Ef00 1.67E-05 1.67E-05 SR-92 3.61E-06 0.00E+00 3.61E-06 Y-93 1.44E-05 0.00Et00 1.44E-05 ZR-95 1.07E-03 2.06E-04 1.27E-03 N8-95 1.66E-Oh 3.58E-04 2.02E-03 NB-97 1.22E-04 1.18E-05 1.34E-04 N8-97M 1,00E-G 0.00E400 1.00E-05 TC-99M 5.91E-05 1.04E-05 6.95E-05 RU-103 7.87E-07 0.00Ef00 7.87E-07 AG-10BM 0.00E400 1.99E-06 1.99E-06 AG-110M 7.07E-06 0.00E+00 7.87E-06 I-131 5.08r *- 1.37E-03 7.21E-03 1-132 8.59E-07 2.57E-05 I-133 a. m 4 2.80E-C4 1.10E-03 1-135 1.10E-04 0.00Et00 1.10E-04 SB-122 7.79E-06 4.44E-05 5.22E-05 58-124 3.82E-05 1.14E-03 1.17E-03 50-125 2.89E-03 1.36E-03 4.25E-03 5N-113 3.09E-04 7.58E-05 3.85E-04 C5-134 7.23E-04 8.36E-04 1.56E-03 C5-137 1.33E-03 1.61E-03 2.93E-03 LA-140 2.83E-04 2.63E-05 3.09E-04 1 W-107 3.37E-05 4.94E-05 8.31E-05 Bl*214 9.83E-06 3.12E-06 1.30E-05 PB-212 3.98E-06 2.89E-06 6.87E-06 PB-214 2.22E-05 1.84E-05 4.06E-05 l TL-208 1.43E-06 1.16E-06 2.59E-06 l AC-228 8.48E-06 0.00E400 8,48E-06 TH-228 1.0$E-03 8.65E-05 . 1.13E-03 SC-46 5.39E-06 1.62E-06 7.01E-06 i HF-181 7.23E-06 3.43E 06 1.07E-05 58-126 0.00E+00 1.71E-06 1.71E-06 FR-85M 1.83E-06 1.12E-05 1.30E-05 XE-131M 2.19E 04 0.00Ef00- 2.19E-04 XE-133 2.34E-02 1.31E-02 3.65E-02 XE-133M 3.12E-04 4.86E-05 3.61E-04 XE-135 5.59E-03 2.87E-03 8.46E-03 XE-135M 2.53E-05 4.69E-06 3.00E-05 l XE-138 0.00Et00 3.11E-04 3.11E-04

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-CATAWBA NUCLEAR STATION 1 UNIT 2 RADI0 ACTIVE EFFLUENT RELEASES

.DATE

  • 08/25187
1. LIEUID RELEASE 5 YEAR . 1987 UNIT 5 IST OTR END OTR SUBTOTAL 1- GROSS RACIDACT!YITY A. TOTAL RELEASE CURIE 5 1.81E-01 5 20E-02 2.33E-91
8. AVERAGE CONCENTRATION RELEASED UCIIML 7.13E-09 2.16E-09 4.72E-09 C. MAXIMUM CONCENTRATION RELIASED UCIIML 6.28E-08 1.31E-08 6.28E-08
2. TRITIUM A. TOTAL EELEA5E CURIES 9.80Ef01 ".16Ef01 1.50Ef02 B. AVERAGE CONCENTRATION RELEASED UCIlML 3.87E-06 2.15E-06 3.03E-06
3. DISSOLVED NOBLE GASES A. TOTAL RELEASE CURIE 5 2.95E-02 1.64E-02 4.59E-02 i
8. AVERACE CONCENTRATION RELEASED UCIIML 1.16E-09 6.82E-10 9.30E-10
4. GR055 ALPHA ACTIVITY A. TOTAL RELEASE CURIE 5 0.00Ef00 0.00Ef00 0.00Ef00
8. AVERACE CONCENTRATION RELEASED UCI/ML 0.00Ef00 0.00Ef00 0.00Ef00
5. VDLUME OF LIQUID WASTE 10 DISCHARCE CANAL LITERS 1.01Ef08 2.67Et07 1.28Ef08
6. VOLUME OF DILUTION WATER LITERS 2.54Ef!0 2.40Ef10 '4.94Ef10
7. RADIONUCLIDES RELEASED CURIES BE-7 3.37E-04 1.11E-05 3.48E-04 F-18 1.83E-03 6.96E-05 1.90E-03 NA-24 1.92E-05 3.21E-04 3.40E-04 CR-51 4.45E-03 1.05E-03 5.49E-03 l MN-54 6.44E-03 2.15E-03 8.59E-03 I

FE-55 1.09E-01 7.58E-03 1.17E-01 FE-59 1.07E-03 4.11E-04 1.48E-03 CD-57 2.23E-04 7.76E-05 3.00E-04 C0-58 1.70E-02 2.33E-02 4.03E-02 CD-60 2 J2E-02 9.19E-03 3.24E-02 ZN-65 8.35E-04 2.39E-04 1.07E-03 SE-75 4.02E-06 0.'00E t00 4.02E-06 BR-82 4.75E-06 1.53E-05 2.01E-05 BR-84 0.00Ef6b 7,10E-06 7.10E-06 R8-88 0.00Ef00 1.67E-05 1.67E-05 5R-92 3.61E-06 0.00Ef00 3.61E-06 Y-93 1.44E-05 0.00Cf00 2R-95 1.44E-05 1.07E-03 2.06E-04 1.27E-03 NB-95 1.66E-03 3.58E-04 2.02E-03 NO-97 1.22E-04 1.13E-05 1.34E-04 NB-97M 1.00E-05 0.00Ef00 1.00E-05 TC-99M 5.91E-05 1.04E-05 6.95E-05 RU-103 7.87E-07 0.00Ef00 7.87E-07 AG-108M 0JJ0Ef00 1.99E-06 AG-110M 1.99E-06 7 87E-06 0.00000 7.87E-06 1-131 5.84C-03 1.37E-03 1-132 7.21E-03 2.49E-05 8.59E-07 2.57E-05 1-133 8.15E-04 2.80E-04 1-135 1.10E-03 1.10E-04 0.00Ef00 1.10E-04 5B-122 7.79E-06 4.44E-05 58-124 5.22E-05 3.82E-05 1 14E-03 1.17E-09 58-125 2.89E-03 1.36E-03 5N-113 4.25E-03 3.09E-04 7.50E-05 3.85E-04 C5-134 7.23E-04 8.30E-04 C5-137 1.56E-03 1.33E-03 1.61E-03 2.93E-03 LA-140 2.83E-04 2.63E-05 W-107 3.09E-94 3.37E-05 4.94E-05 8.31E-05 81-214 9.83E-06 3.12E-06 1.30E-05 F8-212 3,9BE-06 2.89E-06 6.87E-06 PB-214 2.22E-05 1.84E-05 4.06E-05 TL-208 1.43E-06 1.16E-06 2.59E-06 AC-228 8.4BE-06 0.00Ef00 8.48E-06 TH-2?B 1.05E-03 .8.45E-05 ,

1.13E-03 50-46 5.39E-06 1.62E-06 7.01E-06 HF-181 7.23E-06 3.43E-06 58-126 1.07E-05 0.00Ef00 1.71E-06 1.71E-06 XR-85M 1.83E-06 1.12E-05 1.30E-05 XE-131M 2.19E-04 0.00Ef00 2.19E-04 XE-133 2.34E-02 1.31E-02 3.65E-02 XE-133M 3.12E-04 4.86E-05 3.61E-04 XE-135 5.59E-03 2.87E-03 8.46E-03 XE-135ti 2.53E-05 4.69E-06 3.00E-05 XE-138 0.00Ef00 3.11E-04 3.11E-04

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II. AIRBORNE RELEA5ES YEAR ' 1987 j UNITS IST OTR 2ND QTR SU8 TOTAL

1. TOTAL NOBLE CASE 5 CURIES 1.73Ef02 1.67Ef02 3.41Ef02
2. TOTAL HALOGENS CURIES 1.01E-03 9.58E-05 1.10E-03
3. TOTAL PARTICULATE GROSS BETA-CAMMA CURIES 5.97E-03 1.33E-05 5.99E-D3 4, TOTAL TRITIUM CURIES 3.86Ef00 2.42Ef00 6.28Ef00
5. TDTAL PARTICULATE CROSS ALPHA ACTIVITY CURIES 0.00Ef00 0.00Ef00 0.00Ef00
6. MAXIMUM NOBLE GA5 RELEASE RATE UCI/5EC 1.60Ef03 1.60Ef03 1.60Ef03
7. RADIONUCLIDES RELEASED CURIES PARTICULATE F-18 7.37E-05 3.63E-07 7.40E-05 NA-24 7.31E-07 5.07E-07 1.24E-06 MN-56 3.07E-08 4.67E-09 3.54E-08 00-58 1.88E-04 5.46E-06 1.93E-04 BR-82 1.01E-08 5.27E-07 5.37E-07 RB-88 5.68E-03 6.30E-06 5.68E-03 HD-99 0.00Ef00 3.93E-09 3.93E-09 TC-9B 4.30E-09 0.00Ef00 4.30E-09 C5-134 2.75E-08 0.00E400 2.75E-08 C5-137 5.72E-08 1.15E-08 6.87E-08 C5-138 3.36E-05 1.16E-07 3.38E-05 BA-139 7.62E-08 1.05E-08 8.67E-08 W-187 7.79E-08 0.00E400 7.79E-08 BI-218 7.91E-08 1.06E-08 8.98E-08 P8-212 2.01E-10 0.00Ef00 2.ME-10 PB-214 6.96E-08 1.08E-09 7.07E-08 HALOCENS 1-131 8.70E-04 9.35E-05 9.64E-04 I-132 0.00Ef00 3 50E-08 3.50E-08 I-133 1.35E-04 2.22E-06 1.37E-04 i 1-135 2.93E-07 0.00Ef00 2.93E-07 I GASES AR-41 1.87E-01 2.81Ef00 2.99Ef00 KR-85 0.00Ef00 1.3BE-01 1.3BE-01 KR-65M 1.07E-01 3.53E-01 4.60E-01 kR-87 5.82E-03 2.22E-02 2.>00E-02 KR-B8 1.04E-01 3.41E-01 4.45E-01 XE-131M 1.67Ef00 9.66E-01 2.64Ef00 XE-133 1.67Ef02 1.55Ef02 3.22Ef02 XE-133M 2.14E400 2.43Ef00 4.57Ef00  !

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  • 1987 UNIT 5 IST OTR 2ND QTR SUBTOTAL
1. TOTAL N0BLr CASE 5 CURIEL 1.73Ef02 1.67Ef02 3.41Ef02
2. TOTAL HALDCENS cur.IES 1.01E-03 9.5BE-05 1.10E-03
3. TOTAL PARTICULATE CROSS BETA-CAMMA CURIET 5.97E-03 1.33E-05 5.99E-03
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5. TOTAL PARTICULATE CD055 ALPHA ACTIt1TY CURIES 0A0Ef00 '0.00Ef00 DICOEf00
6. MAXirJM NOBLE CA5 RELEASE FATE UCIISEC 1.60E403 1.60Ef03 1.60Ef03
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RADID4C719E EFFLUEd RELEASES II. A;.tBDANE RELEASEh DATE 07/Ps/87 s

. YEAR 1986 UNITS IST OTR 2ND GTR 3RD QTR

)

' 4TH QTR TOTAL l

I, T01AL NOBLE D%ES

, CURIES ' i.33Ef02 3.60$f2 1.12Ef03 4.67Ef01 1.66Ef03

( ., P. t TOIAL HAL&SEN5 CURIE 0 5.18E-04 1.752-03 7.4E-04 2.30E-04 3.24E-03

\i 6 4* 3. 10iAL PARTICULATE .

CR055 BETA-CAMA t? TIES 4.12E-03 1.35E-05 1.88E-05 1.43E-05 4.16E-03 i s

4. TOTAL TLITIUM CURIES 4.23Ef00 3.62E-01 1.31Ef00 9.31E-01 6.73Ef00

,s 5. ;1d1 AL PARTICULATE iTROSS ALPHA ACTfYITY CURIES 0.00Et00 0.00Ef00 0.00Ef00 0.00Ef00 0.00Ef00 4

6. MAXIMUN 0 3LE CA5 RELEASE RAIE UCJISEC 1.60Ef03 1.60Et03 1.60Ef03 1.60Ef03 s 8.00Ef02
7. RADIONUCLIDES RELEASED CURIES s' PARTICULATE 5

( BE-7 0.00U00 0.00E40 0.00Ef00 1.42E-09 1.42E-09

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W 88 4.46E-04 1.32E-05 3.71F-06 7.99E-06 4.71E-04 s t TL137 0.00Ef00 0.00Ef00 0.00Ef00 1.88E-08 1.EBE-08

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, W187 0. 0'C+M . 0.00Ef00 0.00Ef00 4.16E-08 4.16E-08 BI-214 1.0st 04 1.45E-07 6.12E-07 2.64E-06 1.07E-04 FB-212 4.207-05 0.00Ef00 0.00Ef00 0.00Ef00 4.20E-05 FB-214 8.63E-15 6.98E-08

' 1.13E-06 2.88E-06 9.04E-05 TL-208 1.2BE-ob 0.00Ef00 L" 7.26E-10 9.09E-09 1.28E-05 TH-228 2.29E-08 '0.00Ef00 2.84E-08 0.00Ef00 5.13E-08 NP-239 0.00Ef00 0 JOEf00 0.00Et00 2.19E-10 2.19E-10 HALUCENS l -131 '4.82E-00 1.52E-03 4.52E-04 1.15E-04 2.57E-03 1-133 337C-4 2.27E-04 2.87E-04 1.14E-04 6.65E-04

) CASES AR-41 6.03E-02

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i SET TO HEU PAGE AND PRESS RETURN CATAWBA NUCLEAR STAT 10N UNIT 2 RADIOACTIVE EFFLUENT RELEASES DATE 07/06/97 II. AIRBORNE RELEASEE YEAR 1986 UNITS IST OTR 2ND QTR 3RD QTR 4TH QTR TOTAL

1. TOTAL NOBLE CASES CURIE 5 1.33E+02 3.60Et0? 1.12Ef03 4.67Ef01- 1.66Ef03 4 l
2. TOTAL HALOGENS CURIES 5.18E-04 1.75E-03 T.40E-04 2.30E-04 3.24E-03 '
3. TOTAL PARTICULATE GR055 BETA-GAMMA CURIES 4.12E-03 1.35E-05 1.88E-05 1.43E-05 4.16E-03
4. TOTAL TRITIUM CURIES 4.23Et00 3.62E-01 1.31E+00 8.31E-01 -6.73Ef00
5. TOTAL PARTICULATE CR055 ALPHA ACTIYITY CURIES 0.00Ef00 0.00Ef00 0.00Et00 0.00Ef00 0.00Ef00
6. MAXIMUM NOFLE CA5 RELEASE RATE I

UCIl5EC 1.60E+03 1.60Ef03 1.60E+03 1.60Et03 8.00Et02

7. RADIONUCLIDES RELEASED CURIES l PARTICULATE 1

j i

BE-7 0.00Ef00 0.00Et00 0.00E100 1.42E-09 1.42E-09 F-18 5.71E-10 5.94E-09 5.14E-09 ]

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' 1.80E-08 l CD-58 0.00Ef00 5.19E-08 9.10E-06 0.00Ef00 9.15E-06 l CD-60 0.00Et00 5.31E-10 0.00E+00 0.00Ef00 5.31E-10 BR-82 0.00Ef00 0.00Ef00 1.63E-08 {

4.33E-09 2.07E-08 1 RB-88 4.46E-04 1.32E-05 3.71E-06 7.99E-06 4.71E-04 l C5-137 0.00Ef00 0.00Ef00 0.00Ef00 1.88E-08 1.BBE-08 C5-138 0.00Ef00 0.00E+00 0.00Ef00 2.21E-67 2.21E-07 BA-139 0.00Et00 3.60E-09 0.00E100 1.55E-09 5.15E-09 U-187 0.00Ef00 0.00E+00 0.00Et00 4.16E-08 4.16E-08 EI-214 1.04E-04 1.45E-07 6.12E-07 2.64E-06 1.07E-04 PB-212 4.20E-05 0.00Ef00 0.00Et00 0.00Ef00 4.20E-05 I PB-214 8.63E-05 6.98E-08 1.13E-06 2.88E-06 9.04E-05 TL-208 1.28E-05 0.00E+00 7.26E-10 9.09E-09 1.2BE-05 TH-223 2.29E-08 0.00Ef00 2.84E-08 0.00Ef00 5.13E-08 NP-239 0.00E+00 0.00Ef00 0.00Et00 2.19E-10 2.19E-10 HALDCEN5 I*1 4.82E 04 1.52E-03 4.52E-04 1.15E-04 I-133 2.57E-03 3.57E-05 2.27E-04 2.87E-04 1.14E-04 6.65E-04 1

CASES AR-41 6.03E-02 1.01Ef00 6.02Ef00 3.57E-01 7.45E400  !

KR-85 3.31E-02 9.26E-02 1.5?Ef01 0.00E+00 1.53Et01 :l KR-85M 1.26E-01 3.36E-01 1.79E-01 7.90E-02 7.20E-01 I KR-87 4.71E-03 3.56E-02 3.23E-04 4.18E-03 4.48E-02  !

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-..---.---------.--,-,r-ATTACIDfENT II INOPERABLE EQUIPMENT l

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C Equipment: 1 EMF 34, Unit 1 Steam Generator Blowdown Monitor out of Service for more than 30 days:

. January 31,,1986 to Present Why inoperability was not corrected within the time specified:

The EMF was taken out.of service due to flow problems.

Parts have not been readily available. . Required samples.

have been taken during this period of inoperability.

Equipment: 1 EMF 31, Unit 1 Turbine Building Sump Monitor out of Service for more-than 30 days:

. June 1, 1986 to March 18, 1987 Why.inoperability was not corrected within the time-specified:

The EMF was taken out of service because of sample pump-problems. Due to administrative problems, the EMF has.not been returned to service. Required samples have been taken during this period of inoperability.

Equipment: 1 EMF 35, 36, 37, Unit l' Vent System Noble Gas Activity Monitor, Iodine Sampler, and Particulate Sampler.

Out of Service for more than 30 days:

. February 16, 1987 to April 27, 1987 Why inoperability was not corrected within the time specified.

Parts were not readily available for these EMFs. ' Required samples were taken during this period of inoperability.

I Equipment 2 EMF 34, Unit 2. Steam Generator Blowdown. Monitors out cf Service for more than 30 days:

. May 14, 1987 to June 16, 1987 Why inoperability was not corrected within the time-specified:

The EMF was removed form service for maintenance and several components had to be replaced. Parts were not readily available. Required samples were taken during this period of inoperability.  !

l

\

Equipment: EMF 50, Noble Gas Activity Monitor Out of Service for more than 30 days.

. July 10, 1986 to July 30, 1987 Why inoperability was not corrected within the time l specified: '

l The EMF was determined to have a design problem and a plant modification was required. Required samples were taken during this period of inoperability. j

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, ATTACHMENT III .

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/ REVISION 3 0F THE CATAWBA NUCLEAR STATION PROCESS CbNTROL PROGRAM s >

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., s 7 , DUKE POWER COMPANY

, s.

CATAWBA NUCLEAR STATION

[ r PROCESS CONTROL PROGRAM 1.0 PURPOSE

.I .

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/

,,~' The purpose of the Catawba Nuclear Station Process Control Program is g/ ' to insure all requirements of the DPC Corporate Process Control Program have been met for each container of solidified or dewatered radioactive wg.:;te shipped for burial at a licensed burial facility. This PCP is l

IOplicable only to the solidification or dewatering of liquid or wet f splid radioactive waste. ,

/ 2.0 COM0SITION ,

1 t 2.1 The Catawba Nuclear Station Process Control Program shall b ,

ceasist of:

'g 2.1.1 The Duke Power Company Process Control Manual' Introduction (Section I).

', 2.1.2 The Duke Power Company Corporate Process Control Program.

, ' 2.1.3 ., A lisc of all station-specific procedures that implement

' r.he requirements of the Corporate Process Centrol Program.

2.1.4 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste e, <

/ systems and solidification and dewatering equipment.

t 1 /

?.1M Documentation of NRC approval of the initial Catawba

'.,[i!

,. Nuclear Station Process Control Program.

J 2.1.6 ', Documentation of System Radwaste Engineer, CNS Technical

' dervices' Superintendent and CNS Station Manager approval

[, of all changes to the Corporate Process Control Program.

2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the k Semi-Annual Radioactive Effluent Report.

/

i I

i c C-1 Rev. 3'

./ .  !

i a

f .

L '.

  • _..1-

s) l

  • s j SECTIO!4 2.1.1 Implementing Procedure CP/0/A/8700/03 " Chemistry Procedure for Sampling Leed!

Secondary Sample Points"

" Shipment of Radioactive F!.lters e.nd Eil ter HP/0/B/1006/09  !

Media"  !

U HP/0/B/1006/10 "Shipr.cnt of 5olicified Radwaste" HP/0/B/1006/12 " Shipment of Dewatered Resins" l HP/0/B/1006/13 " Determination of the Waste Classification for Radioactive Waste ~0ffe:cd for Shallow Land Burial" l

HP/0/B/1006/15 " Handling and Packaging of Padwaste Filte:s l and Filters Medias" '

OP/0/A/6250/16 " Operating Procedure for the Condensate Polishing Demineralized Backsash Tank Subsystem" l OP/0/B/6500/09 "Radwaste Chemistry Operating Procedure ',

for the Control and Use of Vendor;P ccedo:es" OP/0/B/6500/13 " Operating Procedure for the !1oclear Solid l

Waste (kS) Disi>osal Sys teo" OP/0/B/6500/46 "Radwaste Operating h.'ocedure f or Sol!dif1::atica.  !

and Dewattring of Radioactive Waste" ,

OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for Sampling the ECHT, ECBT, end RET Using in-Line Samples" l

DP/0/B/6500/53 "Radwaste Chemistry Operating Procedure for Dewatering Contaminated Secondary Resins" l

I s

C- 2 Rev. 3 .

1 i

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/ SECT 10!1'2. .1 2 j i

, i. . Drawing.Index

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% Plant 'Interf aces: Cf1-1566-1 4 , .,

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f'~ .  ;

i DUKE POWER COMPANY I f

CATAWBA NUCLEAR STATION ,

i I

PROCESS CONTROL PROGRAM 1.0 PURPOSE 1 l

'he purpose of the Catawba Nuclear Station Process Control Program is  ;

to insure all requirements of the DPC Corporate Process Control Program 3 have been met for each container of solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. This PCP is applicable only to the solidification or dewatering of liquid or wet l solid radioactive waste.

1 2.0 COMPOSITION 2.1 The Catawba Nuclear Station Process Control Program shall ,

consist of:

2.1.1 The Duke Power Company Process Control Manual Introduction (Section I).

2.1.2 The Duke Power Company Corporate Process Control Program.

2.1.3 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program.

2.1.4 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and solidification and dewatering equipment.

2.1.5 Documentation of HRC approval of the initial Catawba Nuclear Station Process Control Program.

2.1.6 Documentation of System Radwaste Engineer,- CNS Technical Services Superintendent and CNS Station Manager approval ,

of all changes to the Corporate Process Control Program. l 2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report.

1 I

J C-1 Rev. 3

) !

f ,

v l

SECTION 2.1.1 l

Implementing Procedure CP/0/A/8700/03 " Chemistry Procedure for Sampling Local Secondary Sample Points"  !

HP/0/B/1006/09 " Shipment of Radioactive Filters and Filter {

Media" ]

HP/0/B/1006/10 " Shipment of Solidified R*dwaste" HP/0/B/1006/12 " Shipment of Dewatered Resins" HP/0/B/1006/13 " Determination of the Waste Classification for Radioactive Waste Offered for Shallow Land Burial" HP/0/B/1006/15 " Handling and Packaging of Radwaste Filters and Filters Medins" OP/0/A/6250/16 " Operating Procedure for the Condensate i Polishing Domineralizer Backwash Tank Subsystem" OP/0/B/6500/09 "Radwaste Chemistry Operating Procedure for the Control and Use of Vendor Procedures" OP/0/B/6500/13 " Operating Procedure for the Nuclear Solid i Waste (WS) Disposal System" i OP/0/B/6500/46 "Radwaste Operating Procedure for Solidification and Dewatering of Radioactive Vaste" OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for Sampling the ECHT, ECBT, and RBT Using I In-Line Sanples" I i

OP/0/B/6500/53 "Radwaste Chemistry Operating Procedure for Dewatering Contaminated Secondary Resins"

]

s l

l.

C-2 Rev. 3 l

l h-_-__-________......____ _ _ _ _ _ _

r .. ..

q

> l SECTIoll 2.1.2 1

\

i>

Drawing Index i Plant Interfaces: Cff-1566-1.6 1

i l

)

1 l

l C-3 Rev. 1

i DUKE POWER COMPANY f

CATAWBA NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE The purpose of the Catawba Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate Process Control Program have been met for each container of solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. This PCP is applicable only to the solidification or dewatering of liquid or wet solid radioactive waste. -

2.0 COMPOSITION 2.1 The Catawba Nuclear Station Pi cess Control Program shall consist of:

2.1.1 The Duke Power Company Process Control Manual Introduction (Section I).

2.1.2 The Duke Power Company Corporate Process Control Program.

2.1.3 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program.

2.1.4 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and solidification and dewatering equipment.

2.1.5 Documentation of NRC approval of the initial Catawba Nuclear Station Process Control Program.

2.1.6 Documentation of System Radwaste Engineer, CNS Technical Services Superintendent and CNS Station Manager approval of all changes to the Corporate Process Control Program.

2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the i Semi-Annual Radioactive Effluent Report.  !

C-1 Rev. 3

i* )

I

. \

SECTION 2.1.1 Implementing Procedure CP/0/A/8700/03 " Chemistry Procedure for Sampling Local Secondary Sample Points" HP/0/B/1006/09 " Shipment of Radioactive Filters and Filter l Media" HP/0/B/1006/10 " Shipment of Solidified Radwaste" HP/0/B/1006/12 " Shipment of Dewatered Resins" HP/0/B/1006/13 " Determination of the Waste Classification for Radioactive Waste Offered for Shallow Land Burial" HP/0/B/1006/15 " Handling and Packaging of Radwaste Filters and Filters Medias" OP/0/A/6250/16 " Operating Procedure for the Condensate Polishing Demineralized Backwash Tank Subsystem" OP/0/B/6500/09 "Radwaste Chemistry Operating Procedure for the Control and Use of Vendor Procedures" OP/0/B/6500/13 " Operating Procedure for the Nuclear Solid Waste (WS) Disposal System" OP/0/B/6500/46 "Radwaste Operating Procedure for Solidification and Dewatering of Radioactive Waste" OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for Sampling the ECHT, ECBT, and RBT Using In-Line Sampics" OP/0/B/6500/53 "Radwaste Chemistry Operating Procedure for Dewatering Contaminated Secondary Resins" l

l l

I C-2 Rev. 3 I l

1

I

1. .

o SECT 10ll 2.1.2 f

Drawing Index -

Plant Interfaces: Cil-1566-1.6 i

C3 RCV- 1

f ___~ ______ _ _ _ q DUKE POWER COMPANY l

/

CATAWBA NUCLEAR STATION PROCESS CONTROL PROGRAM .

1.0 PURPOSE i

The purpose of the Catawba Nuclear Station Process Control Program is j to insure all requirements of the DPC Corporate Process Control Program j have been met for each container of solidified or dewatered radioactive '

waste shipped for burial at a licensed burial facility. This PCP is applicable only to the solidification or dewatering of liquid or wet l solid radioactive waste. j 2.0 COMPOSITION 2.1 The Catawba Nuclear Station Process Control Program shall consist of:

i 2.1.1 The Duke Power Company Process Control Manual Introduction '

(Section 1).  !

2.1.2 The Duke Power Company Corporate Process Control Program.

]

i l 2.1.3 A list of all station-specific procedures that implement l l

the requirements of the Corporate Process Control Program.

l 2.1.4 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and solidification and dewatering equipment.

I 2.1.5 Documentation of NRC approval of the initial Catawba Nuclear Station Process Control Program. l j

l 2.1.6 Documentation of System Radwaste Engineer, CNS Technical )

Services Superintendent and CNS Station Manager approval 4 of all changes to the Corporate Process Control Program.

2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report, C-1 Rev. 3

SECTION 2.1.1 Implementing Procedure CP/0/A/8700/03 " Chemistry Procedure for Sampling Local l Secondary Sample Points" HP/0/B/1006/09 " Shipment of Radioactive Filters and Filter l Media" HP/0/B/1006/10 " Shipment of Solidified Radwaste" j 1

HP/0/B/1006/12 " Shipment of Dewatered Resins" HP/0/P/1006/13 " Determination of the Waste Classification l for Radioactive Waste Offered for Shallow i l

Land Burial" i HP/0/B/1006/15 " Handling and Packaging of Radwaste Filters and Filters Medias" OP/0/A/6250/16 " Operating Procedure for the Condensate Polishing Demineralized Backwash Tank Subsystem" 1

OP/0/B/6500/09 "Radwaste Chemistry Operating Procedure for the Control and Use of Vendor Procedures" OP/0/B/6500/13 " Operating Procedure for the Nuclear Solid Waste (WS) Disposal System" OP/0/B/6500/46 "Radwaste Operating Procedure for Solidification and Dewatering of Radioactive Waste" OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for Sampling the ECHT, ECBT, and RBT Using {

In-Line Samples" OP/0/B/6500/53 "Radwaste Chemistry operating Procedure for Dewatering Contaminated Secondary Resins" l

+

C-2 Rev. 3

SECT 10N 2.1.2

/ Drawing Index q Plant Interfaces: CN-1566-1.6 6

c-3 Rev. 3 ,

DUKE POWER COMPANY f

CATAWBA NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE The purpose of the Catawba Nuclear Station Precess Control Program is to insure all requirements of the DPC Corporate Process Control Program have been met for each container of solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. This PCP is applicable only to the solidification or dewatering of liquid or wet solid radioactive waste.

2.0 COMPOSITION 2.1 The Catawba Nuclear Station Process Control Program shall '

consist of:

2.1.1 The Duke Power Company Process Control Manual Introduction (Section I).

2.1.2 The Duke Power Company Corporate Process Control Program.

2.1.3 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program.

2.1.4 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and solidification and dewatering equipment.

2.1.5 Documentation of NRC approval of the initial Catawba Nuclear Station Process Control Program.

2.1.6 Documentation of System Radwaste Engineer, CNS Technical Services Superintendent and CNS Station Manager approval of all changes to the Corporate Process Control Program.

2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report, {

l L

i C-1 Rev. 3

40 l v

SECTION 2.1.1 Implementing Procedure CP/0/A/8700/03 " Chemistry Procedure for Sampling Local Secondary Sample Points" HP/0/B/1006/09 " Shipment of Radioactive Filters and Filter Media" '

HP/0/B/1006/10 " Shipment of Solidified Radwaste" HP/0/B/1006/12 " Shipment of Dewatered Resins" HP/0/B/1006/13 " Determination of the Waste Classification for Radioactive Waste Offered for Shallow Land Burial" HP/0/B/1006/15 " Handling and Packaging of Radwaste Filters and Filters Medias" OP/0/A/6250/16 " Operating Procedure for the Condensate Polishing Demineralized Backwash Tank Subsystem" OP/0/B/6500/09 "Radwaste Chemistry Operating Procedure for the Control and Use of Vendor Procedures" OP/0/B/6500/13 " Operating Procedure for the duclear Solid Waste (WS) Disposal System" OP/0/B/6500/46 "Radwaste Operating Procedure for Solidification and Dewatering ~of Radioactive Waste" OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for Sampling the ECHT, ECBT, and RBT Using In-Line Samples" OP/0/B/6500/53 "Radwaste Chemistry Operating Procedure for Dewatering Contaminated Secondary Resins" C-2 Rev. 3 i

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'J SECTION 2.1.2 t Drawing Index Plant Interfaces: CN-1566-1.6 i

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C-3 ROV- 3

t DUKE POWER COMPANY f

CATAWBA NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE The purpose of the Catawba Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate Process Control Program have been met for each container of solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. This PCP is applicable only to the solidification or dewatering of liquid or wet' solid radioactive waste.

2.0 COMPOSITION 2.1 The Catawba Nuclear Station Process Control Program shall consist of:

2.1.1 The Duke Power Company Process Control Manual Introduction (Section I).

2.1.2 The Duke Power Company Corporate Process Control Program.

2.1.3 A list of all station-specific procedures that implement the requirements of the Corporate. Process Control Program.

2.1.4 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and solidification and dewatering equipment.

2.1.5 Documentation of URC approval of the initial Catawba Nuclear Station Process Control Program.

2.1.6 Documentation oi System Radwaste Engineer, CNS Technical Services Superintendent and CNS Station Manager approval of all changes to the Corporate Process Control Program.

2.1.7 Documentation that all changes to the Corporate and/or i CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report. 1 C-1 Rev. 3

(e-- <

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SECTION 2.1.1

]

Implementing Procedure CP/0/A/8700/03 " Chemistry Procedure for Sampling Local Secondary Sample Points" HP/0/B/1006/09 " Shipment of Radioactive Filters and Filter Media" HP/0/B/1006/10 " Shipment of Solidified ' Radwaste" HP/0/B/1006/12 " Shipment of Dewatered Resins" HP/0/B/1006/13 " Determination of the Waste Classification- i for Radioactive Waste Offered for Shallow Land Burial" HP/0/B/1006/15 " Handling and Packaging of Radwaste Filters y and Filters Medias" '

OP/0/A/6250/16 " Operating Procedure for the Condensate .

f Polishing Demineralized Backwash Tank Subsystem" OP/0/B/6500/09 "Radwaste Chemistry Operating Procedure  ;

for the Control and Use of Vendor Procedures" OP/0/B/6500/13 " Operating Procedure for the Nuclear Solid I WF.ste (WS) Disposal System" OP/0/B/6500/46 "Radwaste Operating Procedure for Solidification' I and Dewatering of Radioactive Waste" i t

OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for Sampling the ECHT, ECBT, and RBT Using In-Line Samples"  !

OP/0/B/6500/53 "Radwaste Chemistry Operating Procedure for Dewatering Contaminated Secondary Resins" l

2 1

C-2 Rev. 3 L__------_------_------------------------------_- 3

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4 SECT 10ft 2.1.2 Drawing Index l

l Plant Interfaces: C!t-1SG6-1. 6 l

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l C-3 Rev. 3 k__ - _-__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ .