ML20012A309

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Semiannual Radioactive Release Rept for Jul-Dec 1989. W/900228 Ltr
ML20012A309
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/31/1989
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003090216
Download: ML20012A309 (38)
v • d • e


Text

'

O *" NrC Duke 1%un Compaqr IIstit keer PO Box 3319s ' Yice President Charlotte, N C 2042 Nuclear Production (704)373-4531

' DUKE POWER E

February 28, 1990 U. S. Nuclear Regulatory Commission-ATTN: Document Control Desk Washington,'D.C. 20555 t

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414

' Semi-Annual Radioactive Release Report Gentlement Pursuant to Catawba Nuclear Station Technical Specification 6.9.1.7 please find enclosed the Catawba Semi-Annual Radiological Environmental Operating .I Report for the period from July 1989 to December 1989.

Attachment I contains information regarding radioactive effluent releases, <

-1989 fuel cycle calculations, 1989 meterological report, supplemental information, the solid radioactive vaste report, and an explanation of abnormal releases during the reporting period. Attachment II contains information regarding the inoperability of certain effluent nwnitors during the report period.

Please note that revision 4 to the Catawba Site Specific Process Control-

-program, and revision 4 to the Duke Power Process Control Program were made during the second half of 1989. Revision 25 to the Catawba Nuclear Station Offsite Dose Calculation Manual was also made during this time. These ,

revisions are being transmitted to the NRC per my February 28, 1990 letter j to the Document Control Desk.  !

JVery truly yours.

Hal . Tucker MHil-19 MHH-19/lcs Attachments 9003090216 891231 PDR R

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. a5ET TO NEW PACE AND PRESS RETURN CATANSA NUCLE *3 STATIDN f- W11 1  !

  • i ROIDACT!YE EFFLUENT RELEA5El j DATE 02126190 1

!. L!8UID ELEASES YEAR . 1989 UNIf5 IST DTR 2ND DTR 3RD OTR ATH DTR TDTAL '

1. GRD55 R40104CTIVIfT A. TDTAL RELEAR CURIE 5 1.61E-01 6 fM-02 4.81E 02 6.45E-02 3.4N-01 B. AVERAGE CONCENTRAf!DN KLEASED UC1/ML 6.72E-09 2 9K -09 1.55E-09 2.a4E-09 3.26E-09 i C. MAXIMun CDNCENTRAIIDN RELEASED UC11ML 3.85E-08 1.34E-08 1.67E-08 1.23E-08 3.85E-00
2. TRITi!UN A. TDTAL RELEASE CURIE 5 2.50E+02 5.40Ef01 5.94Ef 01 8.10E+01 4.45Ef02 B. AYERAGE CDNCENTRAf!DN RELEA5ED UCIIML 1.04E-05 2.32E-06 1.9M-06 3.07E-06 4.24E 06 c
3. 0155DLYE0 N0BLE CASE 5 A. TDTAL RELEASE CURIE 5 4.75E-02 9.03E-03 6.30E-03 2.59E-02 8.87E-02 B. AYERAGE CONCENTRAllDN RELEA$[D UC1/ML 1.9BE 09 3.83E-10 2.03E-10 9.79E-10 8.45E-10  :
4. CRD55 ALPHA ACT!Y!TT '

A. TOTAL RELEASE CURIE 5 0.00Ef00 0.00E+00 0.00E400 0.0K+00 0.00Ef00

8. AYERACE CONCENTRAT!DN RELEASED UCIIML 0.00E+00 0.00Ef00 0.0K+00 0.00E+00 0.00Lf00 )
5. YDLUME OF L18UID WA5fE TD DISCHARGE
  • CANAL LITER $ 5.91E+07 5.70Ef06 5.58E+07 1.79Ef06 1.22E+08
6. YDLUME OF DILUTIDN WATER LITER 5 2.40E+10 2.36E+10 3.10E+10 2.64E+10 1.0$E+11
7. RA0!DWUCL10E5 RELEASED CURIE 5 PE 7 0.00E+00 4.52E-06 2.19E 04 7.9M-05 3.02E-04 F-1B 6.76E-04 3.50E 05 4.75E-05 1.06[-03 1.82E-03 NA-24 B.46E-05 3.70E-05 0.00E+00 a .1M-05 1.6M-04 ,

CR-51 1.32E-02 3.3K-03 2.74E-04 2.46E-03 1.93E-02 Mh-54 3.78E-03 1.2BE-03 4.01E-04 1.77E-03 7.2M 03 FE-55 2.28E-02 1.51E-02 3.39E-02 3.50E-02 1.07E-01 FE 59 1.61E-03 7.27E-04 2.11E-05 2.14E-04 2.57E-03 CD-57 4.65E-05 1.64E-05 B.46E-06 1.1K-05 8.23E-05 CD 58 4.08E-02 2.40E-02 5.51E-03 4.5K-08 7.46E-02 CD-60 1.15E-02 3.6N-03 1.54E-03 6.47E-03 2.31E-02 ZN-65 5.38E-06 8.73E-06 0.0K+00 0.00E+00 1.41E 05 08-88 8.03E-06 1.52[-04 8.15E-06 3.43E-05 2.03E-04 50 59

  • 00Ef00 0.00E+00 0.0K+00 2.27E-05 2.27E-05 SR-91 0.00Ef00 3.93E-06 0.00E+00 4.37E 06 B.30E-06 5R 92 4.94E-06 3.7BE-05 7.97E-07 2.81E-06 A.6M 05 V-92 0.00E+00 1.37E-05 5.16E-06 0.00E+00 .1.89E-05 '

2R-95 8.69E-04 2.54E-04 6.94E-06 1.20E-04 1.25E-03 1R 97 0.00E+00 4.47E-05 2.66E-05 1,87E-05 9.01E-05 NB+95 1.47E-03 5.0$E-04 9.69E-05 2.01E-04 2.27E-03 NB 97 8.60E-05 2.69E-04 1.55E-05 3.37E-05 4.04E-04 MD-99 1.45E-06 0.00E400 0.00E+00 1.37E-05 1.52E-05 TC-99M 2.09E-05 6.50E 05 2.32E-04 1.54E-04 4.72E-04 RU-103 1.17E-04 0.00E400 0.00E+00 3.96E-06 1.21E-04 AG 110M 1.16E-05 7.69E-05 0.00E+00 0.00E+00 B.85E-05 1-131 7.01E-04 1.62E-04 2.6BE 04 2.2K-05 3.36E 03 1-132 7.07E-07 0.00Ef00 0.00E+00 .1.95E-06 2.66E-06 I-133 1.08E-04 1.14E-05 1.17E-04 7.10E-04 9.47E-04 1 135 1.71E-06 6.13E-07 8.66E-06 9.24E-05 1.03E-04 50-122 8.48E-05 6.30E-06 3.08E 05 0,0H-05 2.0M-04 5B-124 4.18E-03 2.02E-63 9.15E-05 5.28E-06 6.30E-03 '

58 125 2.04E-02 7.3E-03 1.26E-03 2.07E-03 3.10E-02

$N-113 1.26E-04 .1.5M 05 - 0.00E+00 3.36E 06 1,45E 04 C5-134 9.74E-04 3.04E 04 2.75E 04 B.17E-04 2.37E-03 C5-136 4.21E-06 7.40E-07 0.00E+00 3.98E-06 8.93E-06 C5-137 1.59E-03 5.66E-04 5.22E-04 1.5E-03 4.25E-03 C5-138 2.46E-02 4.83E-03 2.54E-03 2.49E-03 3.44E 02 BA-140 0.00E+00 0.00E400 0.0K+00 9.46E-05 9.46E-05 LA-140 1.6M-04 2.06E-04 6.69E-04 3.67E-04 1.41E-03 CE-143 0.00E+C0 0.00E+00 0.00Ef00 2.52E-06 2.5PE-06 W-187 1.06E-05 0.00Ef00 1.40E 06 1.70E-06 1.37E-05 B1-214 4.67E-05 1.02E-04 1.34E-05 1.10E-04 2.72E-04 PB 214 5.3BE-05 1.10E-04 1.35E-05 5.00E-05 2.29E-04 TL-208 0.00E+00 0.00E+00 0.0K+00 3.3K-05 3.30E-05 AC-228 1.63E-06 1.20E-06 1.16E-06 1.73E-06 5.72E-06 TH-22B 1.1N-02 2.97E-03 0.00E+00 1.66E-03 1.5BE-02 58-126 1.04E-06 3.58E-06 0.0K+00 0.00Ef00 4.62E-06 AR-41 2.02E-06 0.00E+00 0.00Ef00 0.00Ef00 2.02E-06 KR-85 1.14E-04 0.00E+00 1.97E-04 1.57E-04 4.68E-04 KR-87 0.00Ef00 0.0K+00 0.0K+00 1.19E-06 1.19E-06 KR-88 0.00Ef00 4.0K-06 0.00Ef00 0.00E+00 4.00E 06

'XE-153 4.34E-02 6.59E-03 4.55E-03 1.98E-02 7.44E 02 XE-133M 3.42E-04 1.93E 05 6.24E-06 1.60E-04 5.27E-04 XE-135 3.57E-03 2.42E-03 1.54E-03 5.7K-03 1.3M-02 XE-195M 0.00Ef00 0.00Ef00 2.44E-06 0.00E+00 2.44E-06

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CATASSA 49EET 1 LI4tAES MLEASE 981-365 89 C2/26/98 . ,

SKIM MAXIftSt S M -' 1.469-92 PREM CRITICAL AGE- ' TEEM CRITICAL PATISMY- SIM CS 60 67.93 % ~

SS 125 9.39 %

CS 137' 5.86 %

TM 2t8 9.66 %

DEDE MAXIft99 955E- 3.439-01 OREM CRITICAL AGE- CNILS . CRITICAL PATIsmY- FISet CS 134 21.75 %

CS 137 54.43 %

TN 228 20.58 %

i LIVER MAXIIGJM DSSE- . 3.789-61 IGIEM CRITICAL AGE- TEEM CRITICAL PATI 9mV- FIS80 CS 134 38.55 %

CS 137 52.37 %

T. BERY MAXIISM 955E- 2.675-91 fWlEM CRITICAL AGE- ASULT CRITICAL PATI 9t4Y- FISIE ,

M 3 6.52 %

CS 134 43.95 %

CS 137 46.52 %

TNYIIUID MAXIft98 DGSE- 4.419-02 IWtEM CRITICAL AGE- TEEM CRITICAL PAftetAY- FISM M 3 29.06 %

C6 66 18.86 %

I 131 41.36 %

KIODEY MAXDRst DOSE- 1.459-01 SWEEM CRITICAL AGE- TEEN CRITICAL PAfteenY- FISM N 3 8.87 %  !

CS 68 5.76 %

  • CS 134 32.14 %.

CS 137 46.90 %

i Lt989 MAXIftSt OGSE- 7.219-02 fWtEM CRITICAL AGE- TEEN CRITICAL PATIOt4Y- FISet '

N 3 17.78 %

C6 60 11.54 %

CS 134 24.83 %

CS 137 37.15 %

CI-LLI fthXDt90 DSSE- 4.040-01 SWEEM CRITICAL AGE- ABULT CRITICAL PAftetRY- FISet -

le 95 78.93 %

3 TM 228 14.00 %

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c gatagga NUcLtQ $1A110# i UNIT 1

-e *~ i R*2104CT!YE EFFLUENT RELEA$El I DATE ' 02I23/90- i

!!, Alb800E RELE45El YEAR : 1989  ;

UNIT 5 15T OTR 2ND BIR 3RD OTR ATH BTR TOTAL ,

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1. TDTAL NOBLE Gelti CUR!E5 7 26Ef01 1.10Ef02 6.6M+0! 6.57Ef01 3.1H+02 j
2. TOTAL HAL88 ENS- CURIE 5 2.79E-08 1.57E-04 1.92E-03 1.22E-03 3.58E-03 l.

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- 3.. 7014L PARf!CULATE

'GR055 8 ETA-GAMMA CURIE 5 1.05E 02 5.13E 03 2.3BE 03 )

1.60E 03 1.96E-02 '

4. 7DTAL TRIT!UM CURIEl 4.19Ef00 6.75E+00 4.84Ef00- 8.07E+00 2.38E+01
5. TOTAL PARf!tULATE  !

GRD55 ALPNA ACTIVITY CURIE 5 0.00E400 0.00E400 0.0K+00 0.00E+00 0.00Ef 00 i i 6. MAXIMUM N0BLE gal RELEASE DATE UCII!EC 1.60Ef03 1.60Et03 1.6K+03 ' 1.6K+03 8.00E+02 ,

7. RADIDNUCLIDEl RELEASED CURIEl 1

PARTICULATES l 1

F-18 1. 04E-02 5.0M 03 2.37E-03 1.60E 03 1.94E-02 NA-24 1.3M 08 0.00Ef00 0.00Et00 0.00Et00 1 33E-08 MN-54 0.00EtJ0 2.51E-06 0.00E+00 0.00Et00 2.51E-06 PN 56 1.30E 08 1.36E-08 0.0Kt00 0.0Kt00 2.67E-08 C0-57 7.73E-07 0.0Kf00 0.0Kf00 0.0Kf00 7.7K-07 CD-58 1.57E 05 3.71E-05 0.00Et00 0.00Ef00 5.29E-05 C0-60 2.80E-06 0.00Ef00 0.00E400 0.00E+00 2. 8K-04 ,

ZN-65 4.77E-10 0.0Kf00 0.00Et00 0.00E+00 4.77E-10 BR 82 1.30E-07 1.46E-08 t.10E-07 1.4K-07 3.VM-07 R8-88 6.69E 05 4.35E-05 4.06E-06 3.8M-06 1.18C-04 R8-89 2.67E-08 0.00Et00 0.00E400 0.00Ef00 2.67E-08 SR-90 0.0Kf00 0.0Kf00 1.27E-06 7.86E-07 2.06E-06 5R 92 6.08E 09 2.69E-08 0.00Ef00 0.00Ef00 3.30E-00 2R-97 7.37E 05 0.00Ef00 0.00E+00 0.00Et00 7.37E-05 TC 99M 2.83E 10 0.00Ef00 0.00E400 0.0K+00 2.8K-10 CD 115 6.80E-09 0.00E+00 0.00E+00 0.00Et00 6.8K 09 TE-131M 9.64E 10 0.00Et00 0.00Et00 0.00Ef00 9.64E 10 C5 134 3.51E-10 7.09E-09 1.22E-10 0.00E+00 7.56E-09 l C5-137 1.83E 06 0.00E+00 0.00E400 0.0Kf00 1.8K-06 C5-138 1.49E 06 5.18E-07 3.06E-09 7.15E-09 2.0M-06 8A-139 5.0$E-08 1.71E-08 0.00Ef00 0.00E+00 6.76E-08 CE-143 2.7K 06 0. OE+00 0.00Et00 0.00E+00 2.7K-06 58-126 4.20E-10 4.61E-10 0.00Ef00 0.00E400 8.81E-10 BR-80M 4.62E 07 1.24E 08 3.68E-07 3.13E-07 1.16E 06

. s HALDCEN5 1-131 1.29E-04 5.97E-05 2.73E-04 2.21E-04 6.83E-04 1-132 9.33E-07 2.32E 07 1.22E-04 1.46E 04 2.70E-04 1*i33 1.4BE-04 9.63E 05 9.44E-04 6.94E-04 1.88E-03 1 134 2.4M-07 6.00E-08 0.00Ef00 0.0Kf00 3.02E-07 I-135 1.6M-06 4.55E 07 5.78E-04 1.61E-04 7.41[-04 CASES AR 41 6.31E-01 9.79Et00 5.22Et00 2.67t+00 1. BK+01 KR-85 1.39E-01 2.201-01 6.15E-01 2.11E 01 1.19Ef00 KR 85M 1.13E-01 2.02E-01 2.06E-01 2,6M 01 7.83E-01 KR-87 2.23E-02 3.96E-02 3.53E-02 6.2BE-02 1.60E-01 KR-88 1.17E-01 2.1RE 01 2.16E-01 2.90E-01 8.34E-01 IE-131M 4.85E-01 3.69E-01 1.30E-01 2.76E-01 1.26E+00 XE-133 6.88Ef01 9.52Et01 5.52Et01 5.64E+01 2.76E+02 XE-133M 5.24E-01 7.66E-01 8.17E-01 7.88E-01 2.89Et00 XE-135 1.7BE+00 3.41Ef00 3.79E400 4.66E+00 1.36Ef01 XE-135M 4.18E-04 3.04E-05 2.21E-04 2.17E-02 2.24E-02 XE-138 0.00E+00 0.00E400 7.2M-06 5.76E-03 5.77E-03

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9tAMIttet WIOaft - TNVWWIS CRITICAL AGE - CIIILD CRITICAL PATISEY - VEGET 4 76.70%

9tMG9991 ERIGAf6 355E = 1.99E-91 9tILLINEM N' 3 67.90%

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CATMSA Latti 2 LIEUIS IELEASE 881-365 89 62/26/90- ... ;

' SKIM MAXIft99 955E- 1.469-92 IgtEM CRITICAL AGE- TEEN CRITICAL PATIONYC SNENIE CS 6e 67.03 %

SS 125 9.39 %

CS 137 5.86 %

TN 228 9.M %

SEBE MAXIft9f DEBE- 3.430-81 IWIEM- CRITICAL AGE- CHILS CRITICAL PATIstAY- FISM CS 334 . 21.75 %

CS 337 54.45 %

TM 228 29.54 %

5 LIVER MAXIftfl 955E- 3.789-91 ISEM CRITICAL AGE- TEEM CRITICAL PATIst4Y- FISM

. CS 134 38.55 %

CS 137 52.37 %

T. SERY MAXIft99 DEBE- 2.679-91 IWIEM CRITICAL AGE- ASULT CRITICAL PATIstAY- FISM i' N 3 6.52 %

CS 134 43.95 %

CS 137 46.52 %

j TMYllSID MAXIftSt DSSE- 4.419-02 fetEM CRITICAL AGE- TEEN CRITICAL PATIStAY- FISM M 3 29.M %

C6 60 16.% %

1 131 41.36 %

KIONEY fthXIft99 DEBE- 1.458-01 fetEM CRITICAL AGE- TEEN CRITICAL PATfet4Y- FISM M 3 8.87 %

, C5 60 5.76 %

CS 134 32.14 %

I CS 137 46.95 %

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LtStG MAXIftfl 8tBE- 7.219-02 fWlEM CRITICAL AGE- TEEN CRITICAL PAftetAY- FISM M 3 17.78 %

C5 60 11.54 %

l CS 134 24.83 %

CS 137 37.15 %

CI-LLI MAXIft99 OSSE- 4.049-01 PWlEM CRITICAL AGE- A8 ULT CRITICAL PATI 9tAY- FISII l 98 95 79.95 %

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  • RE!DACTIVE [FFLUENT RELEASE 5 DATE 02126190 1.-L10U10 RELEASES TEAR : 1999 UNIf5 151 OTR PN0 OTR 3RD STR 4TH DTR TOTA
1. CR055 RA010ACT10!TT A. TOTAL RELEelt CURIE 5 1.61E-01 6.tM42 4.01E42 6.4M42 3.4N-01 B. AYERAGE CONCENTRATION RELEASED UCllML 6.72E49 2.90E49 1.55E-09 f.44E-09 3. 3g-09 C. MAXIMUM CONCENTRAT10N RELEASED UC11ML 3.8M48 1.34E-08 1.67E4B 1.23E-00 3.tM-00
2. TRITT!UN A. TOTAL RELEASE CURIE 5 2.5KHf 5.4eE401 5.94EH1 8.10EH1 4.45EH2 B. AYERAGE CONCENTRATION RELEASED UCIIML 1.04E-05 2.3M46 1.9M46 3.07E46 4.24E-H
3. 01550LVED NOBLE CASES A. TOTAL RELEASE CURIE 5 4 7M42 9.0M43 6.3K43 2.59E-02 8.87E 02 B. AVERAGE CONCENTRA110N ELEASED UCllML 1.9K-09 3.8K 10 2.0M-10 9.79E-10 8.4M 10
4. GR055 ALPHA ACTIVlif A. )DTAL RELEASE CURIE 5 0.0MHO 0.00EH0 0.0MHO 0.00E+00 0.0MHO
8. AVERAGE CONCENTRAi!ON RELEASED UC!lML 0.00EHO 0.00EHO 0.00EMG 0.00EtH 0.0MHO
5. YDLUME OF'Litul0 WASTE TO 015 CHARGE CANAL LITERS 5.91EH7 5.70E606 5.58EH7 1.79EH4 1.tNHO
4. UDLUME OF O!LUT!DN WATER LITER $ t.40E+10 2.HE110 3.1K410 2.64E110 1.0M411
7. RADIONUCL!DE5 RELEASED CURIE 5 BE 7 0.0KH0 4 SIE46 2.19E44 7.9N45 3.0M44 F-18 6.76E44 3.50E45 4.75E45 1.NE-03 1.8tE43 NA44 B.46E-05 3.70E-05 0.00EH0 4.1N-M 1.6M44 CR41 1.3FE-02 3.38E43 2. 7 4E-04 2.4H-03 1.9M42 MN44 3.78E43 1.2BE-03 4.01E-04 1.77[ 4 3 7.ftt-03 FE45 2.29E-02 1.51E42 3.39E42 3.50E42 1.07E 01 FE49 1.61E-03 7.27E-04 2.11E-05 2.14E-04 f .57[ C047 4.6M-05 1.64E-05 B. 46E46 1.1K45 B.tM45 C048 4.00E-02 2.40E42 5.51E 03 4.3M48 7.4H-02 CD-60 1.15E-02 3.6PC-03 1.54E-03 6.47E-03 2.31E4r 2N-65 5.38E-06 8.73E46 0.00EH0 0.00EH6 1.41E-05 99-88 B.0M 06 1.5tE-04 B.15E46 3.4M-05 2.0K44 SR49 0.00EHO 0.0KH0 0.0KHO 2.tfE-05 2.27E45 50-91 0.00EH0 3.93E46 0.00EH0 4.37E 06 8.30E46 5R-92 4.94E46 3.7BE-05 7.97E47 2.01E46 4.6M45 Y 92 0.00EHO 1.37E45 5.16E46 0.00EH0 1.99E45 2R-95 8.69E44 2.54E 04 6.94E46 1.20E44 1.25E43 2R-97 0.00EH0 4.47E-05 2.66E45 1.87E45 9.01E-05 NF 95 1.47E-03 5,0$E44 9.69E*05 2.01E-04 2.27E 03 NS-97 B.60E45 E.69E-04 1.55E45 3.37E 05 4.04E 04 MD49 1.45E-06 0.00EHO 0.00EH0 1.37E45 1.5tE-05 TC-99M 2.09E-05 6.50E-05 2.3EE-C4 1.54E44 4.7M44 00-103 1.17E44 0.00EHO 0.0Kf 00 3.9R46 1.21E-04 AC 110M 1.16E45 7.69E-05 0.00EHC 0.00EH0 8.BSE-05 1 131 7.01E44 1.6tE-04 2.68E44 2.tM-03 3.HE-03 1 132 7.07E-07 0.00EH0 0.00EH0 1.9M-06 2.64E-H 1-133 1.06E44 1.14E-05 1.17E-04 7.10E-04 9.47E-04 1-135 1.71E46 6.1M 07 8.66E46 9 24E-05 1. 0M-04 50 122 B.40E-05 6.30E46 3.0K-05 8.0K45 2.0tE44 50-124 4.18E43 2. 0N-03 9.1M45 5.FIE46 6.30E-03 58 125 2.04E42 7.3M-03 1.26E43 2.07E43 3.1K42 5N-113 1.26E44 1.5M45 0.00EH6 3,3H-06 1.45E44 C5 134 9.74E-04 3.04E-04 2.75E-04 8.17E-04 2.37E-03 C5-136 4.21E46 7.40E-07 0.0KH6 3.99E46 8.93E46 Cl 137 1.59E-03 5.66E44 5.tPE44 1.5H43 4.tM 03 <

C5-130 2.46E42 4.8M-03 2.54E43 f.49E-05 3.44E42 BA-140 0.00EH0 0.00EH0 0.00EH6 9.4E-05 9.4K-05 LA-140 1.6K-04 2.06E-04 6.69E 04 3.67E44 1.41E43 CE-143 0.00EH0 0.00EHO 0.0KH4 2.5N-04 2.5tE46 W-187 1.06E-05 0.00EH0 1.40E46 1.70E-H 1.37E-05 81414 4.67E-05 1.02E-04 1.34E45 1.10E-04 2.7N-04 PI414 5.39E45 1.10E-04 1.3H-05 5.0M-05 2.29E44 TL400 0.0MHO 0.0KH0 0.00EH6 3.3K-05 3.30E45 AC428 1.63E46 1.20E-06 1.16E46 1.7K-H 5.7N44 TH420 1.1M42 f.97E-03 0.00EHO 1.NE-03 1.50E42 58 1N 1.04E46 3.5K46 0.00E600 0.00EH6 4.6M-06 AR-41 2.02E-06 0.0MHO 0.0MHO 0.00EH4 2.0K44 ER 85 1.14E-04 0.00EH0 1.97E44 1.57E44 4.68E-04 KR-If 0.00EH0 0.00EH0 0.00Et00 1.19E46 1.19E-06 ER 88 0.00EHO 4.0K46 0.00Ef00 0.0KH4 4.00E-H IE 133 4.34E 02 6.59E-03 4.5M-03 1.9K42 7.44E-02 XE-133M 3.4M-04 1.9M-05 6.24E46 1.6K-94 5.27E44 XE 135 3.57E-03 f.4K-03 1.54E 03 5.7M-03 1.3M42 XE-195M 0.00EHO 0.00EH0 2.44E46 0.00Et04 2.44E46

$[T TO NEW PAGE Am0 PREli RETURN CATAWBA NUCLE 3 STATION UNIT 2

.= . R'210 ACTIVE EFFLUENT RELEASEl DATE 02123190

11. AIRBORNE DELEA$El YEAR - 1989 UN!ft 1ST OTR 2ND ITR 3RD IIR 4TH GTR TOTAL
1. TOTAL NOBLE CASEl CURIES 7.26E+01 1.10E+02 6.62E+01 6 57E+01 3.1M+02
2. 101AL HALKEWS CURIEl 2.79E44 1.57E-04 1.92E-03 1.22E-03 3.5M-03
3. TOTAL PARTICULATE CR055 BETA-GA mA CURIEl 1.05E-02 5.1M-03 2.3M-03 1.60E-03 1.96E42
4. 101AL TRITIUM CURIE 5 4.19Ef00 6.75E400 4.84E+00 8.07E+00 2.38t+01
5. TOTAL PARt!CULATE CR0il ALPHA ACT!YIff CURIEl 0.00E+00 0.00E+00 0.00E+00 0.0M+00 0.00ft00
6. h4XIMUM NOBLE gal RELEASE RATE UC!!5EC 1.60F403 1.60Ef03 1.60Et03 1.60E+03 8.0M+02
7. RA010NUCL10E5 RELEA5ED CURIES Pati!CULATEl F 18 1.04E-02 5.0$E-03 2.37[-03 1.40E4B 1.94E42 NA-24 1.3M48 0.00Ef00 0.00E+00 0.00Ef 00 1.3M-08 M44 0 00E+00 2.51E-06 0.0M400 0.00E+00 2.51E-04 M46 1.30E48 1.36E-08 0.00E+00 0.00E+00 2.67E4B C047 7.73E47 0.0Mf00 0.00E+00 0.0Mf00 7.7M47 C0-58 1.57E-05 3.71E-05 0. 00E + 00 0.00E400 5.29E-05 CD 60 2.80E46 0.00E400 0.00E400 0.00E+00 2.80E46 IN-65 4.77E-10 0.0M+00 0.0M400 0.00E+00 4.77E 10 BR-82 1.30E47 1.46E-08 1.10E-07 1.40E47 3.9M-07 R9 88 6.69E 05 4 35E45 4.06E-06 3.8PE46 1.18E44 98-89 2.67[ 4 8 0.00E+00 0.00E+00 0.00E+00 2.67E48 5940 0.00E+00 0.00E+00 1.27E46 7.86E47 2.06E46 50 92 6. 08E49 2.49E 08 0.00!+00 0.00E+00 3.30E48 29 97 7.37E 05 0.00E400 0.00Ef00 0.0M400 7.37E-05 TC49M 2. 8M-10 0.00Ef00 0.00E+00 0.00E+00 2.BM 10 C0 115 6.00E49 0.00Ef00 0.00E400 0.00E+00 6.9M-09 TE 181M 9.64E 10 0.00E+00 0.00E+00 0.0M400 9.64E 10 C5-134 3.51E-10 7.09E 09 1.22E-10 0.00E+00 7.56E-09 C5 137 1.BSE-06 0.00E+00 0.00E+00 0.00E400 1.83E46 C5-138 1.49E46 5.1M-07 3.06E49 7.15E49 2.0M 06 BA-139 5.05E48 1.71E46 0 DM400 0.0M400 6.76E4B CE 143 2.70E-06 0.00Ef00 0.00E400 0.00E400 2.70E-06 5B 126 4.20E-10 4.61E-10 0.00Ef00 0.00E400 8.81E-10 BR-80M 4.62E47 1.24E48 3.68E-07 3.1M-07 1.16E46 HALOCEN5 1-131 1.29E44 5.97E45 2.73E44 2.21E 04 6.83E-04 1 132 9.33E-07 2.32E-07 1.22E44 146E44 2.7M-04 1-133 1.48E44 9.63E 05 9.44E-04 6.94[-04 1. BM-03 1-134 2.42E-07 6.0M48 0.00E+00 0.00E400 3.02E47 1 135 1.65E46 4.55E-07 5.78E 04 1.61E44 7.41E44 CASES AR 41 6.31E 01 9.79E400 5.2PE400 2.67E400 1.83E+01 KR-85 1.39E-01 2.2M-01 6.15E-01 2.11E-01 1.19E+00 KR-85M 1.13E 01 2.02E-01 2.06E-01 2.6M-01 7.BM-01 8R-87 2.23E42 3.96E-02 3.53E42 6.28E-02 1.60E-01 KR48 1.17E-01 2.12E-01 2.16E-01 2.90E-01 8.34E-01 XE-131M 4.85E-01 3.69E-01 1.30E-01 2.76E-01 1.26E+00 XE-133 6.88t+01 9.52E+01 5.5PE+01 5.64E+01 2.76E+02 XE-133M 5.24E41 7.66E-01 8.17E-01 7.88E-01 2.89Ef00 XE-135 1.78t+00 3.41Ef00 9.79E+00 4.66E+00 1.36E+01 XE-135M 4.18E44 3.04E-05 2.21E-04 2.17E-02 2.24E42 XE-138 0.00E400 0.0M+00 7.23E46 5.76E-03 5.77E-03

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!f SUPPLEMENTAL INFORMATION

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l:l"j . y. ' : .. EFFLUENT AW M57E 01500$E SUPPLEMENTE INFORMTION 1 . REPORT DATE: . 02/26190-J'; q ;-# ; ,-* -

PERITJ C0YERED: STCT DAY.s 001 STOP DAT e 365

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  • ~olcE At RESULATORT NOBLE CASE 5 -LIMITS-AIR DOSE , .- .

B. L10UID EFFLUENTS - 005E -

+

1. CALENDM OUARTER - CAMMA 005E = 5 MAD 1. CRESAR OUMTER - TOTAL BODY DOSE = 1.5 MREM - i

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2. C EENDAR SUARTER - SETA DOSE e 10 MRAD 2. CALENOM 00ARTER - ORCM 005E = $ MEM -

, 3. CALENDAR YEAR -

  • CMMA DOSE e 10 MAD ' 3. C RE W AR YEAR - TOTE BODY 00$E a - 3 MEM - ,

g' ' 4; CALE GAR YEAR - - BETA 00$E ...= to M40 4l C EE WAR YEAR - ORCM 005E = 10 MEM >

o CJ ~100!NE L- 131 Am 15, TRITIUM, PARTICULATE 5 U/T 1I2 ) 8 DAYS - ORCM 005E t c CALESM 00MTE3 e 7.5 MREN '

2.' CALENAR YEM .

  • 15 MREM-

'!!, MAXIMUM PERM 1551BLE CONCENTRATIONS A. CASE 005 EFFLUENTS - INFORMTION FOUNO IN OFFl!TE 005E CALCULAT10N MANUE O B. LIQUID EFFLUENTS - INFORMATION FOUNO IN 10CFR20, APPEWIX B TA8LE !!, COLUM 2

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!!!. AVERACE ENERGY - NOT APPLICABLE- -l t

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!NFORMTION FOUW IN OFF51TE 005E CALCULATION MMUAL r

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' V. SATCH RELEASES

A. LIEUID EFFLUENT -
1. 6.3Mt02 = TOTE NUMBER OF BATCH RELEASES l.
2. 5.90E+04 e TOTE TIMEIMIN.I FOR BATCH RELEASE 5. t

, 3.'2.60Ef04 e MAXIMUM TIMEIMIN.I FOR A SATCH RELEASE. ,

E 4. 9.4M+01 = MERAK TIMEIMIN.I FOR A BATCH RELEASE. .[4

5. 2.00ft00 m MINIMUM TIMEIMIN.I FOR A BATCH RELEASE.

<6. 2.5 Mf04 s AYERACE DILUTION UATER FLOU OURING RELE45EllCPMI. , ,

' B. CASEOUS EFFLUENT 1, 3.5Mf02 s. TOTE NUMBER OF BATCH RELEASES.

' 2. 8.55Et05 a TOTAL TIMEIMIN.I FOR BATCH RELEASES.

3, 1.95E+04

  • MAXIMUM TIMEIMIN.I FOR A BATCH RELEASE.

4J 2.42ft0S

  • AYERACE TIMEIMIN.) FOR A BATCH RELEASE.
5. 1.00Ef00
  • MINIMUM TIMEtMIN.I FOR A BATCH RELEASE. .

YI. ASNORMAL RELEASES l

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' li-NUMBER 0F RELEASES 2; TOTAL ACTIYITY RELEii@E0lE0illii'....N/.&_... .. j B.- CA$EOU5 -

1. NUMBER OF RELEASES 1.

2.lTOTALACT!Y!TTDELEiiE6IEURIlli'...h.3,;. b3.  !

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i SUPPLEMENTAL REPORT CATAWBA NUCLEAR STATION-Values represented by "O.00E+00" within the body of the; semi-annual and/or annual report are below the minimum detectable limits of.the Catawba counting systems. Typical MDA's for the Catawba. counting.. systems are listed'below:

AVERAGE

ISOTOPE ENERGY (Kev) MDA XE-133- 80 3.50E-08

, CE-144 133 3.00E-07 KR-88 196 3.60E-08 XE-135- 249 1.15E-08 KR-87 402 .3.15E-08 CS-137- 661L '

2.50E-08' L MO-99 778 1.45E .MN-54'. 834 2.65E-08

.ZN 1115' 6.85E-08

.CO-60-- 1332 2.95E-08 i-s

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-t The estimated percentage of error for both Liquid'and Gaseous effluent' release data'at Catawba Nuclear Station.has been determined to'be 123%. This number was derived by summing the .,

following individual estimates of errors:

-1) Flow rate determining devices = 1 5%

2) Counting. error = +15%'

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3) Sample preparation error = 1 3% ,

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SOLID WASTE REPORT 1:

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  • J-N SOLID RADIOACTIVE MRSTE' SHIPPED TO A DISPOBRL FACILITY REPORT" PERIOD 7-1-89 THROUGH 12-31-89' Types of Number of Number of. Waste Container Burial #

Waste Shipped- Shipments  : Containers. Class Type Vol. ft.3- Act. Ci'

1) Waste from Liquid Systems .

(A) Dewatered Secondary Resins 1 3 3A STC 622.2 -7.78E-4 l

1A HIC 205.8 3.97 (B)~Dewatered Primary Resins 1 'l 0 0 N/A N/A 0~ 0:

(C) Evaporator Concentrates

  1. 285.6 115.09 (D) Dewatered Mechanical Filters 6 6 IA,5B' HIC-0 0 N/A- N/A 0 0 (E) Dewatered Domineralizers (F) Solidified (Cement) Oils, O O N/A N/A 0- 0 --

Acids, Sludges

2) Dry Solid Waste 0 0 N/A N/A 0 .0 (A) Dry Active Waste (compacted)
  1. 137.5-(B) Dry Active Waste (non-compacted) 1 2 2A HIC 3.96 A. STC 811.40- 0.26-(C) Dry Active Waste (brokered) --- ---

0 0 N/A N/A 0 'O (D) Irradiated Components 9 11 2062.5 '123.28 denotes multiple waste stream container BIC - High Integrity container--

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STC - Strong Tight Container-b does not include brokered totals

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1 '4 2 SUISt&RY OF NARR RADIONUCLIDE CEEEPOSITI(M t

Type of Wastes- Radionuclide __% Abundance

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' 11. l Wastes frem liquid Systems

< -(A) Dewatered Secondary Resins Mn-54 3. 5 ~

Sb-122 1.0.

Cs-134 16.6 Cs-137 20.8-I-131 52.4. A

Xe-133 ~ 3.4; La-140 -1.0- i C-14' .1.1 '

(B) .Dewatered primary Resins 'Co-57 2.0-Co-58 38.3

, Co 10.9 Cs-134 6.3-l Cs-137 12.1. ,

Mn-54 7.4 Fe-55 14.4 p.

. Hi-63 7.1 W ,

(C) Evaporator Concentrates- (none shipped this period)-

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'(D) Dewatered Mechanical Filters Mn 12.8 Co-58 13.1 '

Co-60 :29.3 Fe-55 39.2 Hi-63 4.3' '

(E)- Dewatered Demineralizers (none shipped this period)-

(F) -Solidified Acids, Oils, Sludges (none shipped this period).

o. .;

s 2. . Solid Dry Waste .

(A) Dry Active Waste (compacted) Cr-51 1.0

-( B) Dry Active Waste-(non-compacted) Mn-54 7.8 Co-58 7.6 Co-60 24.2 Fe-55 56.0 Ni-63 2.5

_(C) Dry Active Waste (brokered) Co-58 7.7 Co-60 27.3. i Mn-54 8.9- l

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Cr-51 1.1 Fe-55 51.7 Ni-63 2.3

.(D) oIrradiated Components (none shipped this period)

  • Average % abundance for all shipments

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EXPLANATION OF ABNORMAL RELEASES >

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1. Event' Description o

On November-9,'1989'during' maintenance activities on Waste Gas Catalytic Hydrogen Recombiner B, an inadvertent release of gas from the=

in-service process loop occurred.

Cause The release was a. result of maintenance activities on an inadequately isolated component.

. Corrective Action Chemistry will revise'their procedures to ensure that components in the Gaseous Waste System are adequately isolated during maintenance, and to provide notification to the Shift Manager (Health Physics and Control Room, Personnel are already required to be notified) in the event of an unusual event associated with the Gaseous Waste System. Operations and llcalth Physics will. establish an Operator Aid Computer alarm to' alert operators in the event of an upward trend on area radiation monitors associated with the'affected area.

Consequences Approximately'534.7 cubic feet.of radioactive gas containing approximately 18.9 curies of activity (expressed as Xe-133 equivalent) leaked into the Auxiliary Building.

11. Event Description During-the time period between December 3, 1989 and December 4, 1989, approximately 930 cubic feet of gas was lost from the Gaseous Waste System.

Cause This release was caused because valve IWG-64 was inappropriately identified as a reverse acting valve resulting in opening the valve when the required position was closed.

Corrective Actions The tags identifying Valve IW6-64 as a reverse acting valve was removed. The event was reviewed with station personnel to emphasize the need to document unusual operating conditions. procedures involving locked valves, and lessons learned. Other reverse acting valves will be reviewed to assure properly labeling. The appropriate procedure upgrades-will be made, along with communicating information to Chemistry Technicians to ensure against recurrence of this type of event.

Consequences The release of approximately 685.1 cubic feet of noble gases from the gaseous waste decay tank resulted in a radioactive release to the environment of 8.541 curies.

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,r ATTACHMENT II INOPERABILITY OF CERTAIN EFFLUENT MONITORS'

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l Equipment: 1 1 EMF 31,1 Unit 1 Turbine Building Sump Monitor  ;

l out of Service for more than 30 days:-

. August 14, 1989 to September 18, 1989 1

'WhyJinoperability was notLcorrected within'the time.

specified:  !

. .The-EMF was taken out of service due to exempt VN CE-2401  !

which was to replace / revise piping-from 1 EMF 31 WP sample lines.and tx) change carbon steel piping to stainless steel.

The.related W/R's were 12671NSM, 12655NSM and 12656NSM.  ?

Required samples were taken during this period of inoperability.

t Equipment: 1 EMF 35, Unit 1 Vent System, Particulate Sampler l 1

Out of Service for more than : 30 days:

. August 22, 1989 to September 29, 1989 Why inoperability was not corrected within the time specified:

The EMF was taken out of service awaiting completion of W/R 513370PS which was initiated to I/R paper not moving on i 1 EMF 35. Required samples were taken during this period of inoperability.

i i

Equipment: '1 EMF 34, Unit 1 Steam Generator Water Sample Monitor-out of Service for more than 30 days:

. July 1, 1989 to present Why inoperability was not corrected within the time  ;

specified:

The EMF was taken out of service due to sample flow problems related to design deficiencies. Required samples were taken during this period of inoperability.

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=I Equipment: 2 EMF 31, Unit 2 Turbine Building Sump Monitor out of Service for more than 30 days: c

. July 1, 1989 to August 4, 1989  ;

. August 8, 1989 to october 4, 1989  ;

Why inoperability was not-corrected within the time ,

specified:

  • The EMF was taken out of service due to exempt VN CE-2408 '

which is to replace / revise piping from.2 EMF 31 WP sample lines'and to change carbon steel piping to stainless steel.

It was also taken out of service due to NSM CN-20074 which ,

was-to provide yM flush water to 2 EMF 31'and add a check valve-in the Turbine Building sump sample pump discharge' -;

line. The related W/R's were 12686NSM and 12687NSM. .

Required samples were taken during this period of inoperability.

l Equipment: EMF 50, Waste Gas Holdup System, Noble Gas Activity Monitor L

Out of Service for more than 30 days:

L . July 12, 1989- to August- 15, 1989 l.

I Why inoperability was not corrected within the time

  • specified:

l The EMF was-taken out of service awaiting completion of W/R's 10569IAE, 10600IAE and 3752 SWR . EMF 50 was unable to obtain counts at' test point 2. Required samples were taken during this' period of_inoperability..

L L, ____________________________________________________________

i Equipment: 2 EMF 34, Unit 2 Steam Generator Water Sample Monitor l2 out of Service for more than 30 days:

. July 1, 1989 to present 1

Why inoperability was not corrected within the time specified:

The EMF was taken out of service due to sample flow

. problems related to design deficiencies. Required samples l were taken during this period of inoperability.

l l

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

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