0CAN029406, ANO Units 1 & 2 Semiannual Radioactive Effluent Release Rept Jul-Dec 1993

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ANO Units 1 & 2 Semiannual Radioactive Effluent Release Rept Jul-Dec 1993
ML20067D585
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 12/31/1993
From: Mims D
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN029406, CAN29406, NUDOCS 9403080311
Download: ML20067D585 (40)
v • d • e


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February 28,1994 OCAN029406 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Units I and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Semiannual Radiological Efiluent Release Report for the Third and Fourth Quarters Of 1993 1'

Gentlemen:

l Arkansas Nuclear One, Units 1 and 2 (ANO-1 & 2) Technical Specifications 6.12.2.6 and )

6.9.3, respectively, require the submittal of a Semiannual Radioactive Efiluent Release Report.

The purpose of this letter is to complete this reporting requirement for the third and founh quarters of 1993 at ANO. This submittal also includes the additional information required by Technical Specifications 6.12.2.6 and 6.9.3 which is to be provided in the first report filed each year.

Should you have any questions regarding this submittal, please contact me.

Very truly yours, NL.a}/Y C. 'W/L Dwight C. Mims Director, Licensing DCM/jjd Attachment b O11.3 9403080311 931231

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' February 28,1994

. OCAN029406 Page 2 cc: Mr. Leonard 1 Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV -

611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. George Kalman -

NRR Project Manager Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Thomas W Alexion NRR Project Manager, Region IV/ANO-2 U. S; Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 P

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, OCAN029406 Page1 of38 ARKANSAS NUCLEAR ONE UNIT 1 AND UNIT 2 OPERATING LICENSE NO. DPR-51 AND NPF-6 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1,1993 TIIROUGII DECEMBER 31,1993

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, OCAN029406 i Page 2 of 38 1 1

TAllLE OF CONTENTS i

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1. Introduction
2. Regulatory Limits
3. Summary of Liquid Efiluent Data
4. Summary of Gaseous Efiluent Data  !

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5. Summary of Radiation Doses
6. Summary of Dose to Members of the Public )
7. IIistorical Efiluent Data
8. Solid Waste Summary

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9. Unplanned Releases
10. Radiation Instrumentation -j i 1. Changes to the Process Control Program
12. Changes to the Offsite Dose Calculation Manual j
13. LLD Levels
14. Radiological Environmental Monitoring Program A. Changes in Sample Locations it identification of New Sample Locations
15. Summary of th:liourly Meteorological Data  !
16. Description of Major Changes to Radioactive Waste Systems j l

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1. INTRODUCTION Arkansas Nuclear One is a two unit plant consisting of a B&W (Unit 1) and a CE (Unit 2) design. Both liquid and gaseous emuents are released in accordance with the Technical Specifications for each unit. This report is a summary of the emuent data in accordance with Unit 1 Technical Specification 6.12.2.6 and Unit Two Technical Specification 6.9.3. This report provides the following information:  :

A. Routine radioactive emuent release reports covering the operation of the units during the reporting period.

B. Description of unplanned releases to unrestricted areas.

C. Description of changes to Offsite Dose Calculation Manual (ODCM).

D. Description of changes to Process Control Program (PCP).

E. Summary of radiation doses due to radiological emuents during the previous calendar  !

year. This data is included in the first report of each year.

F. Radiation dose to members of the public due to their activities inside the site boundary. This data is included in the first report of each year. i G. Description oflicensee initiated major changes to the' radioactive waste systems during the previous calendar year. This data is included in the first report of each year, II. Items to be reported in the Semiannual Report per other miscellaneous Technical Specifications. ,

This report covers the period ofJuly 1,1993 through December 31,1993.

2. REGULATORY LIMITS Unit One and Unit Two Technical Specifications contain the limits to which Arkansas Nuclear One must adhere. Because of the "as low as reasonably achievable" (ALARA) philosophy at ANO, an attempt is made to reduce the amount of radiation released to the environment. The following are the limits required by the Technical Specifications.

A Gaseous Emuents

1. Dose rate due to radioactive materials released in gaseous emuent to unrestricted areas shall be limited to the following:

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

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. - OCAN029406 Page 4 of 38

a. Noble gases Less than or equal to 500 mrem / year to the total body Less than or equal to 3000 mrem / year to the skin
b. Iodine-131, tritium, and for all radionuclides in particulate form with halflives greater than 8 days Less than or equal to 1500 mrem /yr
2. Dose - Noble Gases Quarterly Less than or equel to 5 mrads gamma Less than or equal to 10 mrads beta t

Yearly Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta

3. Dose - Iodine-131, Tritium, and Radionuclides in Particulate Form Quarterly Less than or equal to 7.5 mrems to any organ Yearly Less than or equal to 15 mrems to any organ B. Liquid Emuents
1. Concentration ,

The concentration of radioactive material released to the discharge canal shall be limited to the concentration specified in 10CFR20,  :

Appendix B, Table II, Column 2 for radionuclides other than dissolved -

or entrained noble gases. For dissolved or entrained noble gases, the -i total concentration released shall be limited to 2E-4 microcuries/ml.  :

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. Page 5 of 38 2, Dose Quarterly '

Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ Yearly Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ

3.

SUMMARY

OF LIQUID EFFLUENT DATA 3 The following data is a summary of the number and times of releases for both Unit I and Unit-

2. These releases occurred between July 1,1993 and December 31,1993.

Unit 1 Unit 2 Number of releases: 197 37 Total time for all releases (minutes): 29269 12324 Maximum time for a release (minutes): 295 1847 1 Average time for a release (minutes): 147 333 Minimum time for a release (minutes): 12 144 As required by Regulatory Guide 1.21 Rev.1, a summary of data for liquid releases is to be provided in the Semiannual Report. One unplanned liquid release frora Unit 1 occurred  ;

during this period, as discussed in Section 9. The following five pages provide a summary of liquid efEuents for both Unit I and Unit 2:

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Attachment to

, OCAN029406 Page 6 of 38 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL LIQUID EFFLUENTS)

July 1993 through December 1993 Unit 1 Type of Efiluent Units Quarter 3 Quarter 4 Est. Tot Error %

A fission and Attivation Products

1. Total Release (Not Including l Tritium, Gases, Alpha) Curies 7.467E-1 6.444 E-1 0
2. Average Diluted Concentration During Period pCi/ml 2.965 E-8 3.757E-8
3. Percent of Applicable Limit  % 9.884E+0 1.252E+1 B. Trilitan!

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1. Total Release Curies 1.231 E+2 1.314E+2 0
2. Average Diluted Concentration ,

During Period pCi/ml 4.887E-6 7.662E-6 I

3. Percent of Applicable Limit  % 1.629E-1 2.554E-1 C. Dissolved and Entrained Gases
1. Total Release Curies 7.305E-1 4.977E-2 0
2. Average Diluted Concentration Ci/ml 2.901 E-8 2.902E-9
3. Percent of Applicable Limit  % 1.451E-2 1.45 I E-3 D. Gross Alpha Radioactivity I
1. Total Release Curies 3.477E-3 0.000E+0 0 FLWaste Vol Released (Pre-Dilution) Liters 8.316E+6 7.118E+ 6 0 F Volttmg p.[J1iluti.on Water Used Liters 8.745E+10 6.885E+10 0 l

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, OCAN029406  !

Page 7 of 38 UNIT 1 REPORT CATEGORY  : SEMIANNUAL LIQUID CONTINUOUS AND HATCil RELEASES -

TOTALS FOR EACII NUCLIDE RELEASED.

TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER # 3 AND QUARTER # 4 YEAR 1993 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 SR-92 CURIES 0.00E+ 00 0.00E+00 1.26E-05 0.00E400 M O-99 CURIES 0.00E+00 0.00E+00 2.48E-05 0.00E+00 KR-85M CURIES 0.00E+00 0.00E+00 2.52E-05 0.00E+ 00 RU-103 CURIES 0.00E+00 0.00E+00 - 1.66E-04 0.00E+00 SN-113 CURIES 0.00E+00 0.00E+00 4.55E-04 0.00E+00 +

SB-127 CURIES 0.00E+00 0.00E+00 9.88E-04 0.00E+00 -

XE-131M CURIES 0.00E+00 0.00E+00 1.01 E-03 0.00E+ 00 TE-132 CURIES 0.00E+00 0.00E+00 1.86E-03 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 3.46E-03 0.00E+ 00 G-ALPHA CURIES 0.00E+00 0.00E+00 3.48E-03 0.00E+00 S E-75 CURlES 0.00E+00 0.00E+00 4.09E-03 0.00E+00 '

MO-99 CURIES 0.00E+ 00 0.00E+00 4.12E-03 0.00E+00 Y-90' CURIES 0.00E+00 0.00E+00 3.81E-02 0.00E+00 NB-97 CURIES 0.00E400 .0.00E+00 3.84E-04 2.68E i OTHER CURIES O'.00E+00 0.00E+00 0.00E+00 2.94E-05 1-131 CURIES 0.00E+ 00 0.00E+00 1.14E-02 3.42E-05 1-133 CURIES 0.00E+00 0.00E+ 00 7.66E-04 3.55E-05 [

NA-24 CURIES 0.00E+00 0.00E+00 2.29E-05 4.79E-05 B A-140 CURIES 0.00E+00 0.00E+00 0.00E+00 1.39E-04 SR-89 CURIES 0.00E+00 0.00E+00 0.00E+00 2.10E-04 ,

FE-59 CURIES 0.00E+00 0.00E+00 1.96E-04 2.18E-04 XE-133M CURIES 0.00E+00 0.00E+00 9.73E-03 2.19E-04 XE-135M CURIES 0.00E+00 0.00E+00 0.00E+00 2.31E-04 AR-41 CURIES 0.00E+00 0.00E+00 1.03E-05 2.32E-04 I-132 CURIES 0.00E+00 0.00E+00 5.48E-03 2.67E-04 Y-91M CURIES 0.00E+00 0.00E+00 0.00E+00 3.85E-04 SB-126 CURIES 0.00E+ 00 0.00E+00 2.43E-03 4.48E-04 LA-140 CURIES 0.00E+00 0.00E+00 2.78E-04 5.92E-04.

SB-122 CURIES 0.00E+00 0.00E+00 7.41E-03 8.00E-04 XE-135 CURIES 0.00E+00 0.00E+00 ' 2.15E-03 8.62E-04 CO-57 CURIES 0.00E+00 0.00E+00 1.76E-03 8,73E-04 ZR-95 , CURIES 0.00E+00 0.00E+00 3.14E-03 1.15E-03 MN-54 CURIES 0.00E+00 0.00E+00 1.26E-03 1.44E-03 AG-110M CURIES 0.00E+00 0.00E+00 1.09E-02 1.68E-03 l

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

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, OCAN029406 Page 8 of 38 CONTINUOUS RE. LEASES BATCH RELEASES NUCLIDE UNIT - QUARTER 3

. QUARTER 4 QUARTER 3 QUARTER 4 ,

ND-95 CURIES 0.00E+ 00 0.00E+ 00 4.88E-03 2.41E-03 CS-134 CURIES 0.00E+00 0.00E+00 5.52E-03 3.10E-03 CO-60 CURIES 0.00E400 0.00E+00 2.01 E-02 7.37E-03 CS 137 CURIES 0.00E+00 0.00E+00 1.39E-02 1.05E-02 CR-51 CURIES 0.00E+00 0.00E+00 .l .76E-02 1.16E-02 FE-55 CURIES 0.00E+00 0.00E+00 ~ 6.57E-03 2.34E-02 SB-124 CURIES 0.00E+00 0.00E+00 2.73E-02 2.79E-02 XE-133 CURIES 0.00E+00 0.00E+00 7.18E-01 4.82E-02 SB-125 CURIES 0.00E+00 0.00E+00 1.59E-01 2.02E-01 CO-58 CURIES 0.00E+00 0.00E+00 3.93E-01 3.48E-01 1I-3 CURIES 0.00E+00 0.00E+00 1.23 E+02 1.31E+02 Total for CURIES 000E+00 0.00E+00 1.25E+02 .l.32E+02 Period i

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- - _ . . _ . - . - . - . . - - - ~ . . - . - . - - - - - - - - --- -

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, OCAN029406 '

Page 9 of 38 SEMIANNUAL SUMMATION FOR ALL RELEASES IlY QUARTER (ALL LIQUID EFFLUENTS)

July 1993 through December 1993 Unit 2 Type of Efiluent Units Quarter 3 Quader 4 Est. Tot Error %

A. Fission and Activation ProdtLqts

1. Total Release (Not Including Tritium, Gases, Alpha) Curies 9.632E-2 4.073E-2 0
2. Average Diluted Concentration Durmg Period pCi/ml 7.965E-9 7.03 IE-9
3. Percent of Applicable Limit  % 2.655E+0 2.344E+ 0 B, Tritium
1. Total Release Curies 2.047E+2 4.677E+1 0
2. Average Diluted Concentration During Period pCi/ml 1.694E-5 8.072E-6
3. Percent of Applicable Limit  % 5.647E-1 2.691E-1 C. Dissolved _and Entrained Gases
1. Total Release Curies 2.033E-1 3.526E-2 0
2. Average Diluted Concentration During Period pCi/ml 1.682E-8 6.086E-9
3. Percent of Applicable Limit  % 8.412E-3 3.043E-3 D. Gross Alpha Radioactivit.y i
1. Total Release Curies 2.475E-3 5.814E-4 0 E. Waste Vol Released (Pre-Dilution) Liters 4.899E+6 1.168E+6 0 F. Volume of Dilution Water Used Liters 8.745E+10 ' 6.885E+10 0

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. OCAN029406 Page 10 of 38 i

.I UNIT 2 l REPORT CATEGORY  : SEMIANNUAL LIQUID CONTINUOUS AND BATCll RELEASES

TOTALS FOR EACil NUCLIDE RELEASED.

TYPE OF ACTIVITY  : ALL RADIONUCLIDES REPORTING PERIOD  : QUARTER # 3 AND QUARTER t/ 4 YEAR 1993 l l

CONTINUOUS RELEASES BATCH RELEASES l NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 XE -135 CURIES 0.00E+00 0.00E+00 3.92E-05 0.00E+00 SN-113 CURIES 0.00E400 0.00E+00 5.28E-05 0.00E+00 l CO-57 CURJES 0.00E+00 0.00E+00 1.51 E-04 0.00E+00 j XE-133M CURIES 0.00E+00 0.00E+00 2.54 E-04 0.00E+00 '

NA-24 CURIES 0.00E+00 0.00E+00 2.96E-04 0.00E+00 SR-90 CURIES 0.00E+00 0.00E+00 3.65E-04 0.00E+00 CR-51 CURIES 0.00E+00 0.00E4 00 1.32E-03 0.00E+00 i KR-85 CURIES 0.00E+00 0.00E400 1.65 E-01 0.00E+00 1-132 CURIES 0.00E+ 00 0.00E+00 1.50E-03 2.42E-06 SB-127 CURIES 0.00E+00 0.00E+00 0.00E+00 2.47E-05 ZR-95 CURIES 0.00E+00 0.00E+00 4.30E-04 3.58E-05 MN-54 CURIES 0.00E+00 0.00E+00 9.26E-04 4.03E-05 NB-95 CURIES 0.00E+00 0.00E+00 9.99E-04 4.91E-05 AG-110M CURIES 0.00E+00 0.00E+00 2.72E-03 4.99E-05 S R-89 CURIES 0.00E+00 0.00E+00 6.92E-04 1.37E-04 TC-99M CURIES 0.00E+00 0.00E+00 1.02E-04 1.47E-04 W-187 CURIES 0.00E+00 0.00E+00 0.00E+00 1.71 E-04 MO-99 CURIES 0.00E400 0.00E+00 5.16E-05 1.84E-04 SB-124 CURIES 0.00E+00 0.00E+00 6.36E-04 2.56E-04 CO-60 CURIES 0.00E+00 0.00E+00 5.13 E-03 4.40E-04 CS-134 CURIES 0.00E+00 0.00E+00 7.97E-03 4.59E-04 G-ALPIIA CURIES 0.00E+00 0.00E+00 2.47E-03 5.81 E-04 l I-133 CURIES 0.00E+00 0.00E+00 1.19E-03 6.07E-04 i CS-137 CURIES 0.00E400 0.00E+00 1.57E-02 1.18E-03 FE-55 CURIES 0.00E+00 0.00E+00 4.60E-03 2.52E-03 I-131 CURIES 0.00E+ 00 0.00E+00 3.82E-03 4.06E-03 SB-125 CURIES 0.00E+00 0.00E+00 1.34E-02 8.83E-03 I CO-58 CURIES 0.00E+00 0.00E+00 3.42E-02 2.15E-02 l XE-133 CURIES 0.00E+00 0.00E+00 3.79E-02 3.53 E-02 11-2 CURIES 0.00E+00 0.00E+00 2.05 E+02 4.68E+01 Total for CURIES 0.00E+00 0.00E+00 2.05E+02 4.68E+01 Period 1

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4.

SUMMARY

OF GASEOUS EFFI,UENT DATA As required by Regulatory Guide 1.21 Rev.1, a summary of data for gaseous releases is provided in the Semiannual Report. This summary covers releases from July 1,1993, to December 31, 1993. The summary of gaseous effluents for both Unit I and Unit 2 is as follows:

Unit 1 Unil2 Number of releases. 66 73 Total time for all releases (minutes): 377297 443108 Maximum time for a release (minutes): 11832 10393 Average time for a release (minutes): 5716 6070 Minimum time for a release (minutes): 1 2 The Unit I gaseous releases consisted of:

7 emergency feedwater (EFW) pump releases - These releases were a result of surveillances to the steam driven EFW pump.

6 waste gas decay tank releases.

48 weekly vent releases.

2 unplanned releases.

I main steam dump release.

2 reactor building purges.

The Unit 2 gaseous releases consisted of:

13 cmergency feedwater (EFW) pump releases - These releases were a result of surveillances to the steam driven EFW pump.

59 weekly vent releases.

I steam release from steam generator blowdown through the flash tank.

The two unplanned releases are discussed in more detail in Section 9. Additional gaseous efiluent data is contained in the following summaries (4 pages):

1

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SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS)

July 1993 through December 1993 Unit 1 Type of Efiluent Units Quarter 3 Quarter 4 Est. Total Error %

A. Fission and Activation Products

1. Total Release Curies 1.735E+1 5.804E-1 0
2. Average Release Rate For Period pCi/Sec 2.182 E+0 7.302E-2
3. Percent of Applicable Limit  % 3.055E-2 1.022E-3 B. Radiciodines
1. Total Iodine-131 Curies 1.263E-6 1.166E-8 0 2 Average Release Rate For Period pCi/Sec 1.588E-7 1.467E 3. Percent of Applicable Limit  % 4.448E-7 4.106E-9 C. Particulates
1. Particulates(Half-Lives >8 Days) Curies 0.000E+0 5.764E-7 0
2. Average Release Rate For Period pCi/Sec 0.000E40 7.252E-8
3. Percent of Applicable Limit  % 0.000E+0 2.030E-7
4. Gross Alpha Radioactivity Curies 5.798E-7 1.182E-6 D. T1illum
1. Total Relee e Curies 6.767E-1 2.623E+0 0
2. Average Release Rate For Period pCi/Sec 8.514E-2 3.300E-1
3. Percent Of Applicable Limit  % 1.192E-4 4.620E-4

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. OCAN029406 Page 13 of 38 UNIT 1 REPORT CATEGORY  : SEMIANNUAL AIRHORNE GROUND LEVEL

CONTINUOUS AND BATCil RELEASES.
TOTALS FOR EACil NUCLIDE RELEASED.

TYPE OF ACTIVITY  : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD  : QUARTER # 3 AND QUARTER # 4 YEAR 1993 CONTINUOUS RELEASES BATCII RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 Fission Gases KR-85 CURIES 0.00E400 0.00E+ 00 0.0CE400 3.68E-04 XE-131M CURIES 0.00E+00 0.00E400 1.68E-03 5.39E-04 XE-135 CURIES 0.00E+00 0.00E+00 5.99E-02 7.27E-03 XE-133M CURIES 0.00E400 0.00E+00 1.49E+01 1.52E-02 I

XE-133 CURIES 0.00E4 00 0.00E400 2.36E+00 5.57E-01 l

Total for CURIES 0.00E+00 0.00E+00 1.73 E+01 5.80E-01 Period lodines 1-131 CURIES 0.00E4 00 0.00E+00 8.38E-06 0.00E+ 00 1-132 CURIES 0.00E4 00 0.00E+00 1.26E-06 1.17E-08 Total ihr CURIES 0.00E4 00 0.00E+ 00 9.65E-06 1.17E-08 Period Particulates l CO-58 l CURIES l 0.00E400 l0.00E400 l 0.00E400 l 2.55E-08 l Total for CURIES 0.00E+ 00 0.00E4 00 0.00E+ 00 2.55E-08 Period Other SR-89 CURIES 0.00E+ 00 0.00E+00 0.00E+00 5.51 E-07 G-ALr - CURIES 0.00E+00 0.00E+00 5.80E-07 1.18E-06 11-3 , CURIES 0.00E+00 0.00E+00 6.77E-01 2.62E+00 Total for CURIES 0.00E+00 0.00E+ 00 6.77E-01 2.62E+00 '

Period

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. OCA.N029406 Page 14 of 38 SEMIANNUAL SUMMATION FOR ALL RELEASES BY QUARTER (ALL AIRBORNE EFFLUENTS)

July 1993 through December 1993 Unit 2 Type of Efl!aent Units Quarter 3 Quarter 4 Est. Total Error %

ALEils.ip_n_a.nd Actlygtion Products

1. Total Release Curies 3.627E+1 0.000E+0 0 2 Average Release Rate For Period pCi/Sec 4.563E+0 0.000E40
3. Percent of Applicable Limit  % 6.388 E-2 0.000E4 0 IL Radigigjines
1. Total Iodine-131 Curies 0.000E40 0.000E+0 0
2. Average Release Rate For Period pCi/Sec 0.000E+0 0.000E+0

, 3. Percent of Applicable Limit  % 0.000E +0 0.000E+0 CmParticul.atc3

1. Particulates(llatf-Lives >8 Days) Curies 4.065E-6 1.946E-7 0
2. Average Release Rate For Period pCi/Sec 5.117E-7 2.448E-8
3. Percent of Applicable Limit  % 1.432E-6 6.855E-8
4. Gross Alpha Radioactivity Curies 0.000E40 2.809E-6 Illiitium
1. Total Release Curies 1.068E+0 1.951 E+0 0
2. Average Release Rate For Period pCi/Sec 1.343 E-1 2.455 E-1
3. Percent Of Applicable Limit  % 1.881 E-4 3.436E-4 E

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. OCAN029406 Page 15 of 38 UNIT 2 REPORT CNTEGORY  : SEMIANNUAL AIRilORNE GROUND LEVEL

CONTINUOUS AND HATCll RELEASES.
TOTALS FOR EACil NUCLIDE RELEASED

~ TYPE OF ACTIVITY  : FISSION GASES, IODINES, AND PARTICULATES REPORTING PERIOD  : QUARTER # 3 AND QUARTER # 4 YEAR 1993 CONTINUOUS RELEASES BATCII RELEASES NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 Fission Gases l XE-133 l CURIES l 0.00E400 l 0.00E+00 l 3.63E4 01 l 0.00E+00 l Total for CURIES 0.00E+ 00 0.00E4 00 3.63E4 01 0.00E+01 Period lodines 1-132 CURIES 0.00E+00 0.00E+00 0.00E400 1.21E-06 1-133 CURIES 0.00E400 0.00E+00 0.00E4 00 1.87E-06 Total for CURIES 0.00E+ 00 0.00E+ 00 0.00E+00 3.08E-06 Period Particulates CO-57 CURIES 0.00E+00 0.00E+00 4.54E-07 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 3.61 E-06 0.00E+00 Total for CURIES 0.00E+00 0.00E+00 4.0"i-06 0.00E400 Period Other S R-89 CURIES 0.00E+00 0.00E4 00 4.61E-09 1.95E-07 G ALPilA CURIES 0.00E+00 0.00E400 0.00E4 00 2.81E-06 11-3 CURIES 0.00E+00 0.00E+00 1.07E+00 195E400 Total for CURIES 0.00E+00 0.00E+00 1.07E+00 1.95E400 Period

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. OCAN029406 Page 16 of 38

[

S.

SUMMARY

OF RADIATION DOSES The following is a summary of the annual radiation doses due to radiological emuents during 1993 calculated in accordance with the Offsite Dose Calculation Manual.

UNIT 1

_ Liquid Radwaste Emuents (mrem.j Dose Limits: Total Body = 1.5/Qtr 3/Yr, Other Organs = 5/Qtr 10/Yr Qrgan Otr 1  % Otr 2  % Otr3  % Otr 4  % Year 3 TBody 0.0070 0.46 0.0097 0.65 0.0103 0.68 0.0120 0.80 0.0389 1.30 Bone 0.0086 0.17 0.0084 0.17 0.0084 0.17 0.0101 0.20 0.0355 0.35 Liver 0.0085 0.17 0.0135 0.27 0.0138 0.28 0.0163 0.33 0.0521 0.52 Thyroid 0.0008 0.02 0.0013 0.03 0.0084 0.10 0.0003 0.01 0.0074 0.07 Kidney 0.0029 0.06 0.0046 0.09 0.0048 0.10 0.0055 0.11 0.0178 0.18 Lung 0.0011 0.02 0.0017 0.03 0.0017 0.03 0.0021 0.04 0.0065 0.07 GI-LLI 0.0388 0.78 0.0202 0.40 0.0517 1.03 0.0448 0.90 0.1554 1.55 Gaseous Radwaste Emuents Iodine,11-3, and Particulate, and 11-3 (ITP) - Dose Limits (mrem) = 7.5/Qtr - 15/Yr 'I Q_rgan Otr 1 %_ ftr 2  % Otr 3  % Otr 4  % Year M TBody 0.0022 0.03 0.0020 0.03 0 0004 0.01 0.0016 0.02 0.0062 0.04 Bone 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0000 0.00 Liver 0.0022 0.03 0.0020 0.03 0.0004 0.01 0.0016 0.02 ~ 0.0062 0.04 Thyroid 0.0032 0.04 0.0021 0.03 0.0007 0.01 0.0016 0.02 0.0076 0.05 Kidney 0.0022 0.03 0.0020 0.03 0.0004 0.01 0.0016 0.02 0.0062 0.04 Lung 0.0022 0.03 0.0020 0.03 0.0004 0.01 0.0016 0.02 0.0062 0.04 i GI-LLI 0.0022 0.03 0.0020 0.03 0.0004 0.01 0.0016 0.02 0.0062 0.04 i Noble Gas Air Dose Limits (mrad) = Gamma 5/Qtr 10/Yr, Beta 10/Qtr 20/Yr Type._ Otr 1 -% Otr 2  % Otr 3  % Otr 4  % Year  %

Gamma 0.0000 0.00 0.0000 0.00 0.0005 0.01 0.0000 0.00 0.0005 0.00 Beta 0.0000 0.00 0.0000 0.00 0.0022 0.03 0.0001 0.00 0.0023 0.02

Attachment to-

, OCAN029406 Page 17 of 38 UNIT 2 Ilquidlad.gastrFJlluentsfmnem)

Dose Limits : Total Body = 1.5/Qtr 3/Yr, Other Organs =/Qtr 10/Yr  ;

Q1gan Strl

% Otr 2 M_ Otr 3  %- Str 4  % Year 3 TBody 0.0091 0.61 0.0417 2.78 00124 0.83 0.0014 0.10 0.0646 2.15 Bone 0.0071 0.14 0.0342 0.68 0112 0.22 0.0012 0.02 0.0537 0.54 Liver 0.0127 0.25 0.0575 1.1.5 0 0166 0.33 0.0019 0.04 0.0888. 0.89 Thyroid 0.0001 0.00 0,0010 0.02 0.0112 0.04 0.0028 0.06 0.0060 0.06 Kidney 0.0042 0.08 0.0205 0.41 0.0057 0.11 0.0007 0.01 0.0311 0.31 Lung 0.0014 0.03 0.0064 0.13 0.0021 0.04 0.0003 0.01 0.0101 0.10-GI-LLI 0.0056 0.11 0.0157 0.31 0.0103 0.21 0.0014 0.03 0.0330 0.33 >

Daseous Radwaste Efiluents Iodine,11-3, and Particulate - Dose Limits (mrem) = 7.5/Qtr 15/Yr Oruan RLr_!  % Otr L  %. Otr 3  % Rtt_4  % y_ cat $~

TBody 0,0017 0.02 0.0009 0.01 0.0007 0.01 0.0012 0.02 0.0045 0.03 Bone 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0000 0.00 0.0000 0.00 Liver 0.0017 0.02 0.0009 0.01 0.0007 0.01 0.0012 0.02 0.0045 0.03 Thyroid 0.0017 0.02 0.0010 0.01 0.0007 0.01 0.0012 0.02 0.0045 :0.03 Kidney 0.0017 0.02 0.0009 0.01 0.0007 0.01 0.0012 0.02 .0.0045 0.03 Lung 0.0017 0.02 0.0009 0.01 0.0007 0.01 0.0012 0.02 0.0045 0.03_ ~

GI-LLI 0.0017 0.02 0.0009 0.01 0.0007 0.01 0.0012 0.02 0.0045 0.03 l Noble Gas Air dose Limits (mrad) = Gamma 5/Qtr 10/Yr, Beta 10/Qtr 20/Yr  ;

Iyp.g_ _QLr._1.  % .Otr 2_  % Otr3  % Rtr 4  % Ygat 3 Gamma 0.0000 0.00 0.0001 0.00 0.0011 0.02 0.0000 0,00 0.0012 0.01-Beta 0.0000 0.00 0.0026 0.03 0.0034 0.05 0.0000 0.00 0.0060 0.04 l

. -- .-. -. ~

t Attachment to

. OCAN029406 Page 18 of 38

6. SUMM ARY OF DOSE TO MEMilERS OF Tile PUllLIC The following is a summary of the annual radiation dose to members of the public due to activities inside the site boundary.

UNIT I BONE LIVER TBODY THYROID KIDNEY GI-LLI LUNG SKIN Gaseous Emuent ITP 8.38E-6 2.73E-3 2.73E-3 3.31 E-3 2.73 E-3 2.73E-3 2.73E-3 Noble Gas 1.28E-4 6.12E-4 Liquid Emugnt Fish 3.55E-2 5.21E-2 3.89E-2 7.45 E-3 1.78E-2 6.51E-3 1.55E-1 Sediment 2.09E-3 2.45E-3 -l Unit 1 Total 3.55E-2 5.49E-2 4.17E-2 1.08E-2 2.05E-2 9.24E-3 1.58E-1 3.06E-3 UNIT 2 Gaseous Emuent ITP 2.49E-6 2.96E-3 1.96E-3 1.98E-3 1.96E-3 1.96E-3 1.96E-3 Noble Gas 3.18E-4 1.25E-3 Liquid i Emuent Fish 5.37E-2 8.88E-2 6.46E-2 6.01E-3 3.llE-2 1.01E-2 3.30E-2 Sediment 9.77E-4 1.14E-3 Unit 2 Total 5.37E-2 9.07E-2 6.69E-2 7.99E-3 3.31 E-2 1.21E-2 3.50E-2 2.39E-3 Site Total 8.92LI-2 1.46E-1 1.09E-1 1.87E-2 5.36E-2 2.13E-2 1.93E-1 5.45E-3 1

Limit (40CFR190) 25 25 25 75 25 25 25 25

% Limit 3.57E-1 5.82E-1 4.36E-1 2.49E-2 2.15E-1 8.53E-2 7.73E-1 2.18E-2 i l

1 1

Attachment to OCAN029406 i Page 19 of 38

7. IllSTORICAL EFFLUENT DATA The following graphs show the historical release data for both units on a yearly basis. These graphs compare data from 1988 through 1993.

Unit 1 Gaseous Effluents Maximum Critical Organ Dose 10 E -

~-'--

e i

$3 M.. .N. k

@ys/gl. );  :"sg o o, ., ,

1988 1989 1990 1991 1992 1993 Year Unit 1 Gaseous Effluents Fission and Activation Products 10000

,n ~ ~ ~ ~ ~i 1000 -

f"'

g ,.~....

,  :(ly,, 'I'i'; i: gjl { ~ O

.~ y.

e c'_ , "'i g'y,;, y ';.,,  ! .

3 . ;f  ! x c o yy., L;:

( --,

2 q g
l1 I' L

100 -

'l  ? Q L  ;  ; '{

h -

hl j f 'f g 3 L j  ;  :

$g ', .,

' , ~ ' ~ ~ "

I h~'

10

' ~ ~~ '

1988 1989 1990 1991 1992 1993 Year

Attachment to '  :

,. OCAN029406 -

Page 20 0f 38 Unit 1 Gaseous Effluents  ;

Tritium i 100

- -- /

W,#N'a

+sgg 10 - o  : --

i 1988 1989 1990 1991 1992 1993 Year Unit 1 Gaseous Effluents 1 Radiciodines  :

1.00e 002 1.000 003 r

1. De 0 r 1.00e-006

!. 1988 1989 1990 1991 1992 1993 Year

-- y & * -+ -eed+ r m.'1 =v-- 4 itw+em twa y 6-+r-- **g y

Attachment to OCAN029406 Page 21 of 38 Unit 1 Gaseous Effluents Particulates 1.00e 001 kV ,,

$1' '

1.000-002 -

W '-

gi'$:

b:h,Qf @ g!' @. '

1.000-003 LT6 2  % g$$ffF

.$ hkkhN i

$ , ,,:j k$IN$$'

pm,

/7 4 w b  ; E!!M iffh [ k Ib'b Yh

, $l[ih:

(Je,

'? e/js sl' 'b1 h i-$ k3. ' .

3w X

s

$ d,.

n,

% . i:

y

f;'[i

T g,jl 1.j  ; '4 - 2 p-1.000-005 -

h,"s. M?l 1 h,- :Jh[mp i # e' ,  :. $,,.

(,, wb n $l N;; up/ . g If 'j:

l'. J4%p f sv as,., $$,,&w, pg j,j W .) fj

/

. ym,

/,i  :

1.00e-006 h:kkh

' ^

Ih""N~$g$! Ihh'p$85! H

" ' ~ '

^, i Mb

~ ~ ~ ~ ~~

1988 1989 1990 1991 1992 1993 Year Unit 1 Gaseous Effluents Total Body Dose 1.00e + 000 1.00e-001 -

. j, lj'f;f$'M

, n. e Yi,,

V  !+ GS:

1.00e-002 -

f:  :

. ;;; I b$$@fi $, M)

EsF khh5 gjk)N f'j;p Nd i f (:

$$$ $DA gp 1 fh-? h

"~ " '

"~' ' ' ' ~ ~~

1.000-003 1988 1989 1990 1991 1992 1993 Year l

l l

Attachment to 0CAN029406 Page 22 of 38 Unit 1 Liquid Effluents Maximum Critical Organ Dose 1.00e+000 b,,?,+?,N',.

, ,, ,f i 1.00e-001 -

1.00e-002

' ' ' ' ~

1988 1989 1990 1991 1992 1993 Yoar Unit 1 Liquid Effluents Dissolved and Entrained Gases 100 ._ _ _ _ .

?'

, h,h,f, h,,'

O.1

~~

1988 1989 1990 1991 1992 1993 Year

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

Attachment to

- .- . OCAN029406 ,

- Page 23 of 38 Unit 1 Liquid Effluents Tritium 1000 1988 1989 1990 1991 1992 1993 Year Unit 1 Liquid Effluents Fission and Activation Products 100 I

10 -

o i$./gmm w$Y/h4 app ,a V6;htw%

fan -

' '~ ~

0.1 1988 1989 1990 1991 .1992 1993-Year 1

+*

_m + a.-a s s. . * - *, -*~r-- -+--?-r-- 't T7-'

Attachment to

. OCAN029406 i l

Page 24 of 38 Unit 1 Liquid Effluents  :

Total Body Dose 1

0 1 1988 1989 1990 1991 1992 1993 Year Unit 1 Liquid Effluents Total Volume Released 1e+008

$ sfjjhs#i .

. . .  ;)$Y}jf22

" ' ~ ' ^ ^ ' '

~~~~

1000000 1988 1989 1990 1991 1992 1993 Year

Attachment to OCAN029406 4

Page 25 of 38 Unit 2 Gaseous Effluents Maximum Critical Organ Dose 10 -

1 E '

tE 0.1 -

Y

$lllk9,,,NN,,i 0.001 ~ ~ - ~

-^

1988 1989 1990 1991 1992 1993 Year Unit 2 Gaseous Effluents Fission and Activation Products 10000 g %

1@0 -

M , f .

1

.$ . 1 L L  !! f j [ j j  ! j ( '!j -

.j 100 -

, ,j, . . ,

10

~

~ ~ - - - " ~--~ '- - - - - - ' ~ - ^ ~ - ~-

1988 1989 1990 1991 1992 1993 Year l

Attachment to OCAN029406  !

. Page 26 of 38 Unit 2 Gaseous Effluents Tritiurn 100

# E '1 3 10 ffy_',i[' fj

. _ , _ l 1

1988 1989 1990 1991 1992 1993 Year Unit 2 Gaseous Effluents Radiciodines 1.00e 002 1.00e-003 =  !

r ggg. ; -

-: L 1.00e 004 r  :

$ c  : .

3

^

i

] ;

1.00e 005 m

( ) [ #  :! i  !

s 4  :  :

.  : a L j i  ; l { i j (

1.00e 006 m

{ fj ,

)

['-  ; .

2 T'

.): ~

l 2

s'* 1 I 'l i l

' ' ' ~

1.00e-007 " ' " ' ' "

1988 1989 1990 1991 1992 1993 Year

Attachment to OCAN029406

  • Page 27 of 38 1

Unit 2 Gaseous Effluents  !

l Particulates 1.000-001 1.00e-002 7 1.00e-003 =

e

~

Ei 1.00e-004 r E' sjjfWng k I 2

w..,.,.,

1.00e-006

~

i

' ~ ~ ' ~ ' ' - -

~ ik~$$l

'~  ! ~ ~ ~ g~~ ~I ~ 1 $'$~$ '

' ~ ~

1992

~ ~ ~ ~ $

1993 1988 1989 1990 1991 Year Unit 2 Gaseous Effluents Total Body Dose 1.00e+000 1.00e-001 -

E 1 h -

a 1.000 002 -

1.00e-003

^ ' ' ' - - - ~ ^ ~ ~ ~ ~ ~ ~ '

1988 1989 1990 1991 1992 1993 Year

Attachment to OCAN029406 Page 28 of 38 Unit 2 Liquid Effluents Maximum Critical Organ Dose 1.00e+000

.I<:

7;.

^;

L j Rigd 1.00e-001  : j,, ,[p 1,00e-002

" ' ' ~ ~ ~

1988 1989 1990 1991 1992 1993 Year Unit 2 Liquid Effluents Dissolved and Entrained Gases 1000 _

f

. t a 10 m

~hkhkk)

o. ~ _ Ihhh 1988 1989 1990 1991 1992 1993 Year

Attachment to OCAN029406 Page 29 0f 38 Unit 2 Liquid Effluents Tritium 2000 1000 -

2 s I

,, '" ,, ll E
2
-,7 h  ; '! .
51. a  : 1 ,;  : .; s

-e U

O

' i?,Mf4

' e i

.' i  ?,

C . .

100 -

a > J

?

- 3  ?

[" .,  : .

,g L  ;  ; .; h^ i s i ; y p ./in  ; w  : L: i  ;:- m <  ;!

P' i b

i^ j l ,'

i 4  !

,o ts# L3 i: j Li 1j La j 1988 1989 1990 1991 1992 1993 Year Unit 2 Liquid Effluents  :

Fission and Activation Products 100 10 -

S .# mm

.. ' (,

0.1 /

1988 1989 1990 1991 1992 1993 Year

Attachment to -

OCAN029406 Page 30 of 38 d

Unit 2 Liquid Effluents Total Body Dose ,

1 0.01 1988 1989 1990 1991 1992 1993 ,

Year Unit 2 Liquid Effluents Total Volume Released 1o+008 E

{0 1e+007 - - - - -

1000000 1988 1989 1990 ,1991 1992 1993 ,

Year 4

i

Attachment to

' ' _, 0CAN029406 Page 31 of 38

8. SOLID WASTE

SUMMARY

j The following is a summary of the solid wastes shipped offsite, both annually and during the last six months of1993.

l IGGULATORY GUIDE 1.21 REPORT WASTE DISPOSAL ANNUAL

SUMMARY

REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1993 THROUGH DECEMBER 1993 A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 12-Month Est. Total

1. Type of Waste Unit - Period Error, %
a. Spent resins, filter sludges, m3 7.87E+00 evaporator bottoms, etc. Ci 1.94E+04 2.50E+00
b. Dry compressible waste, m3 7.07E+01 contaminated equip, etc. Ci 5.67E+00 2.09E+00  :
c. Irradiated components, control m3 0.00E+00 rods, etc. Ci 0.00E+00 0.00E+00
d. Other(describe) m3 0.00E+00 ,

Ci 0.00E+00 0.00E+00

2. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 8 Unshielded Van / Truck Oak Ridge, TN _

1 Cask Shipment (Type A) Barnwell, SC 1 Cask Shipment (Type B) Barnwell, SC B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A N/A N/A l

- x w-,

y ne- >--y -

JAttachment to  !

.- OCAN029406- -l Page 32 of 38 ,

REGULATORY GUIDE 1.21 REPORT WASTE DISPOSAL ANNUAL

SUMMARY

REPORT .

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY 1993 TIIROUGH DECEMBER 1993 A. Solid Waste Shipped Offsite For Burial or Disposal (Not irradiated fuel) 6-Month Est. Total

1. Type of Waste Unit Period Error, %
a. Spent resins, filter sludges, m3 3.75E+00 evaporator bottoms, etc. Ci 1.79E+02 - 2.06E+ 00
b. Dry compressible waste, m3 3.90E+01 contaminated equip, etc. Ci 3.89E+00 2.66E+00
c. Irradiated components, control m3 0.00E+00 rods, etc. Ci 0.00E+00 0.00E+00 ,
d. Other (describe) m3 0.00E+00 Ci 0.00E+00 0.00E+00
2. Estimate of major nuclide composition (by type of waste) ,
a. CS-137 23.0 % 4.06E+01 NI-63 15.9 % 2.81E+01 FE-55 15.3 % 2.71E+01 CS-134 15.0 % 2.65E+01  ;

SB-125 12.4 % 2.19E+01 ,

CO-58 8.3% 1.46E+01 l CO-60 4.6% 8.15E400 TE-125'.i 2.8% 4.90E+00 MN-54 2.3% 4.00E+00 i AG-110M 0.5% 8.41E -)

b. CS-137 87.0% - 3.39E+00 CS-134 4.7% 1.81E-01 NI-63 3.1% 1.21 E-01 FE-55 2.7% l .04E-01 CO-60 2.1% 8.30E-02 C-14 0.3% 1.21E-02

, TC-99 0.08 % 3.12E-03 I-129 0.06 % 2.34E-03 i

11-3 0.01% 3.89E-04 i l 1 i l- _ ._ _ i

_ _ _ . . _ _ . _ _ _ _ . ~ _ - . . - _ . _ . - _ . . ... _ . .. . . _ . -m.

Attachment to

. OCAN029406~

Page 33 of 38'

c. N/A
d. N/A
3. Solid Waste Disposition N_gluber of Shipments Mode of Trattsportation Destination 5 Unshielded Van / Truck Oak Ridge, TN 1 Cask Shipment (Type B) Barnwell, SC B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A N/A N/A t

to p - ,-> v 4 -+ r-e- -v--s, -

e, , - -

Attachment to-

  1. 4 . OCAN029406 Page 34 of 38
9. UNPLANNED RELEASES An unplanned release is defined as any release of radioactive material to the environment that does not meet the following criteria:

A. Sample analysis prior to release, and B. Release calculations performed prior to release.

During the third and fourth quarters of 1993, there were three unplanned releases (lGR93-0112, IGR93-0103 and ILR93-0257). The following is a summary of the unplanned releases:

1 GR93-0112 - T-18 A Release Release start time  : November 1,1993 at 0000 Release stop time  : November 2,1993 at 2021 Release volume 1.1537E3 cubic feet Release duration  : 2661 minutes Gamma Air Dose  : 8.50E-6 mrad - Percent of yearly limit < 0.01 Ileta Air Dose  : 2.46E-5 mrad - Percent of yearly limit < 0.01 ITP  : 7.14E-10 mrem - Percent of yearly limit < 0.01 A. . Description of occurrence On November 1,1993, gaseous waste decay tank (T18A) decreased in pressure from 56 psig to 3 psig in approximately 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> resulting in an unplanned release. It was assumed that the contents of this tank were consistent with the contents of the T18C ,

since both tanks were filled at approximately the same time from the same source.

T18C was later released with no problems.

B. Identify cause for exceeding limits.

No limits were exceeded due to this release.

C. Corrective actions taken to mitigate occurrence.

i No corrective actions were taken to mitigate the occurrence. The T18A outlet isolation valve  !

(GZ-13 A) leaked past the seat. l l

,,n- - r - e v- . , . - - .,

Attachment to

  • ^ .- OCAN029406 Page 35 of 38 1

D. Actions taken to prevent recurrence.

A job order was written to repair the valve and a subsequent successful leak test of T18A was conducted. Ilowever, an additional unplanned release occurred in January 1994 prior to the scheduled repair date for the valve. This subsequent unplanned ,

release, which had contents similar to IGR93-0112, will be discussed in the radiological efiluent release report covering operations during the first quarter of-1994. Since this subsequent release, T18A has been tagged-out and will not be q utilized until appropriate repairs have been made to valve GZ-13A. The cause of both releases is being addressed through the ANO corrective action program.

E. Sununary of consequences of occurrence. l

, l Although the release through T18A was unplanned, the contents of the tank were i released through the normal release pathway. Samples were obtained from the T18C waste tank and used for input for the unplanned release to calculate ofTsite doses. This data was determined to be representative of the T18A tank since both tanks were filled at approximately the same time from the same source ofinfluent. The weekly unit vent sample showed no increase in activity during this time period. The dose from this release is listed above and is low in comparison to the Technical Specification limit.

No abnormal consequences would be expected to occur due to this release. See data above for dose contribution from this release. ,

I IGR93-0103 - Release of Main Steam via Main Steam Safety Valvg Release start time  : October 28,1993 at 1836 Release stop time  : October 28,1993 at 1837 Release volume  : 7.5504E5 cubic feet Release duration ' I minute Gamma Air Dose  : 4.707E-10 mrad - Percent of yearly limit < 0.01 Beta Air Dose  : 6.031E-10 mrad - Percent of yearly limit < 0.01 ITP 1.061 E-07 mrem - Percent of yearly limit < 0.01 i

A. Description of occurrence :1 On October 18,1993,' the Unit 1 turbine was tripped manually. This resulted in the release of steam from the main steam system to the atmosphere via the main steam safety valves.  !

B. Identify cause for exceeding limits.

1 No limits were exceeded due to this release.

l

_. .- --,.--, a - ,., ~,. -. . - ..--:.---. A

. ' Attachment to

  • " . OCAN029406 Page 36 of 38  ;

l C. Corrective actions taken to mitigate occurrence.

No corrective actions were taken. The design of the Unit I tmbine system is to release secondary steam when the turbine trips.

D. Actions taken to prevent recurrence.

No actions were taken to prevent recurrence since the system is designed to function -

in this manner and the concentrations of radionuclides released were small.

E. Summary of consequences of occurrence. 1 i

The Unit I secondary system is designed to release steam to the atmosphere whenever l the turbine trips. However, due to a small primary to secondary leak (< 0.01 gpm),-

the contents of this release contained radioactivity. Sample results revealed that the steam contained H-3 and Xe-135 in levels above minimum detectable concentrations. ,

The dose due to this release is low in comparison to the yearly limits specified in the Unit 1 Technical Specifications. No abnormal consequences would be expected to I occur due to this release. See data above for dose contribution from this release.

i 1 LR93-0257 - Inadvertent Relgfise of T16B I Release start time  : October 16,1993 at 1800 Release stop time  : October 16,1993 at 1945 Release volume  : 605 gallons ,

Release duration 105 minutes I Total Body Dose  : 3.73E-6 mrem - Percent of yearly limit < 0.01 .

Critical Organ Dose 1.30E-4 mrem - Percent of yearly limit < 0.01 A. Description of occurrence On October 16,1993, treated waste monitor tank T16A was released to the discharge canal. ARer completing the release of T16A, a non-licensed operator noticed that the efTluent flow meter to flume was not reading zero. Investigation revealed that CZ-55B i (treated waste discharge to header from T16B transfer pump) was still open. 'CZ-55B ]

is the tank isolation valve for T16B. As a result of this valve being open, T16B was - -l also released to the flume. This resulted in an unplanned release. q q

B. Identify cause for exceeding limits.

No limits were exceeded due to this release.

l 1

l Attachment to

' ** . OCAN029406 Page 37 of 38 C. Corrective actions taken to mitigate occurrence. i 1

Upon discovery that CZ-55B was open, the operator isolated the valve to terminate the release.

D. Actions taken to prevent recurrence.

CZ-55B was checked prior to release of T16A and determined to be in the closed position. Subsequent investigation revealed that valve was not closed because more than the normally required force was necessary to secure the valve. Valve CZ-55B was repaired to correct the binding problems. Additionally, the damaged position indicator was repaired.

E. Summary of consequences of occurrence.

The Unit I treated waste monitor tanks are the normal release tanks for radioactive liquid efiluents. T16B was in the recirculation mode during the release. Samples obu.ined from T16B revealed that the contents of this tank. were consistent with previous tanks released from this pathway. Because the release pathway and activities were consistent with previous releases, no abnormal consequences would be expeued to occur due to this release. See data above for dose contribution from this release.

10. RADIATION INSTRUM ENTATION As required by Unit 1 and Unit 2 Technical Specifications, any radioactive efiluent instmmentation inoperable for more than 30 days shall be reported in the next Semiannual Radioactive Efiluent Release Report. During the third and fourth quarters of 1993, no instrumentation was inoperable longer than 30 days.

I 1. CIIANGES TO Tile PROCESS CONTROL PROGRAM As required by Unit I and Unit 2 Technical Specifications, a description of changes made to the Process Control Program (PCP) during the reporting period shall be included in the next Semiannual Radioactive EfIluent Release Report. During the third and fourth quarters of 1993, there were no changes to the PCP.

12. CIIANGES TO Tile OFFSITE DOSE CALCULATION MANUAL During the third and fourth quarters of 1993, no chany,es were made to the Offsite Dose Calculation Manual.

1 1

l l

l

~

Attachment to

% . OCAN029406 Page 38 of 38

13. LLD LEVELS In accordance with Unit I and Unit 2 Technical Specifications, lower limits of detection (LLDs) higher than required shall be documented in the Semiannual Radioactive Eniuent Release Report. During the report period, there were no LLDs higher than required.
14. RADIOLOGICAL ENVillONMENTAL MONITORING PROGRAM A. There were no environmental sample location changes during the reporting period.

B. During the reporting period, there were no sampling locations identified which would yield a calculated dose commitment greater than the values currently being calculated.

15. SUMM ARY OF llOURLY METEOROLOGICAL DATA in accordance with ANO-1 and 2 Technical Specification 6.12.2.6(e) and 6.9.3.4.1, respectively, in lieu ofincluding a summary of the meteorological data in this repod, the 1993 data is retained at ANO. This data is available for NRC review.

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16. DESCRIPTION OF MAJOR CIIANGES TO RADWASTE SYSTEMS During 1993, the liquid radwaste processing systems contract was awarded to a different vendor. The new system is identical to the previously used vendor system with the exception of some minor details such as tank size. This is not considered a major change and no revisions to the SARs were necessary. No major changes to the gaseous or . solid radwaste systems occurred during 1993.

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